TECHNICAL SPECIFICATION PAGES - UNIT 1 - ie . --p--, u 4. e'...j1 ENCLOSURE 3. BRUNSWICK STEAM ELECTRIC PLANT,- UNITS 1 AND 2 f NRC DOCKETS 50-325 4.50-324 i OPERATING LICENSES DPR-71.4.DPR-62

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ENCLOSURE 3.

BRUNSWICK STEAM ELECTRIC PLANT,- UNITS 1 AND 2 f'

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NRC DOCKETS 50-325 4.50-324 i

OPERATING LICENSES DPR-71.4.DPR-62 -|REQUEST FOR LICENSE AMENDNENT- . j

ROD SEQUENCE CONTROL' SYSTEM

TECHNICAL SPECIFICATION PAGES - UNIT 1 - i

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INDEX.

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LIMITING CONDITIONS FOR OPERATION AND SURVE!LLANCE REQUIREMENTS

SECTION PACE

3 / 4 . 0 A P P L I C A B I L I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 0 - 1

3/4.1 REACTIVITY CONTROL SYSTEM,S

3/4.1.1 SHUTDOWN MARCIN............................................ 3/4 1-13/4.1.2 REACTIVITY AN0MALIES....................................... 3/4 1-23/4.1.3 CONTROL RODS

Control Rod Operability.................................... 3/4 1-3

Cont rol Rod Maximum Sc ram Insert ion Time s. . . . . . . . . . . . . . . . . . 3 /4 1-$

Control Rod Average Scram Insertion Times.................. 3/4 1-6Four Cont rol Rod Croup Scram Insert ion Times. . . . . . . . . . . . . . 3/4 1-7Control Rod Scram Accumulators............................. 3/4 1-8Cont rol Rod Dr i ve Cou pl i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 /4 1-9

Control Rod Position Indication............................ 3/4 1-11Control Rod Drive Housing Support.......................... 3/4 1-13 |

3/4.1.4 CONTROL ROD PROGRAM CONTROLS| Rod Worth Minimiter........................................ 3/4 1-14

":d 5:g: :: ": :::1 Sy::: ..... ......................... 2f' l-!!

Rod Block Monitor.......................................... 3/4 1-17

3/4.1.5 STANDBY LIQUID CONTROL SYSTEM.............................. 3/4 1-18

3/4.2 POWER DIS 1RIBUTION LIMITS

3/4.2.1 AVERACE PLANAR LINEAR HEAT CENERATION RATE. . . . . . . . . . . . . . . . . 3/4 2-1

3/4.2.2 APRM SETP0!NTS............................................. 3/4 2-23/4.2.3 MI NI MUM CRI TICAL POWER RATI0. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 /4 2- 3

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BRUNSWICK - UNIT 1 IV Amendment No. 131

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INDEX'

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

SECTION PACE

3/4.9 REFUELINC OPERATIONS (Continued)

3/4.9.3 CONTROL RCJ POSIT!0N.................................. 3/4 9-5

3/4.9.4 DECAY TIME............................................ 3/4 9-6,

3/4.9.$ COMMUNICATIONS........................................ 3/4 9-7

3/4.9.6 CRANE AND HOIST OPERABILITY........................... 3/4 9-8

3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE P00L.................. 3/4 9-9

3/4.9.8 WATER LEVEL-REACTOR VESSEL............................ 3/4 9-10

3/4.9.9 WATER LEVEL-SPENT FUEL STORACE P00L................... 3/4 9-11

3/4.9.10 CONTROL ROD REMOVAL

Single Control Rod Removal............................ 3/4 9-12Multiple Control Rod Removal.......................... 3/4 9-14

3/4.10 SPECIAL TEST EXCEPTIONS

3/4.10.1 PkIMARY CONTAINMENT INTECRITY......................... 3/4 10-1

gg,,ETbT3 /4.10. 2 :;C ;; ;; E ^ L ..;C E CC N T :L '"| ^ T L . .v . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-23/4.10.3 SHUTDOWN KARCIN DEMONSTRATIONS........................ 3/4 10-33/4.10.4 R EC I R CU LAT I ON L00 P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-43/4.10.5 PLANT SERVICE WATER................................... 3/4 10-5

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BRUNSWICK - UNIT 1 IX Amendment No. 133

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REACTIVITY COWrROL SYFTEMS I. .

LIMITING CONDITION FOR OPERATION (Continued)'

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ACf!ON: (Continued).

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2. Lf the inoperable control rod (s) is inserted |;

a) Within one hour disarm the associated directional control valves !either: ,'1) Electrically, or

2) Hydraulically by closing the drive water and exhaust water *,

isolation valves.

b) Otherwise, be in at least HOT SHUTDOWN within the next 12 hours.

c. With more than 8 control rods inoperable, be in at least HUT SKUTDOWNwithin 12 hours.

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3RVEILLANCE REQUIREMENTS

4.1. 3.1.1 The scran discharge volume drain and vent valves shall bedemonstrated OPERABLE at least once per 31 days byt*

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n. Verifying each valve to be open.

b. Cycling each valve at least one complete cycle of full travel.

4.1. 3.1. 2 All withdrawn control rods not required to have their directionalcontrol valves disarmed electrically or hydraulically shall be demonstrated

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OPERABLE by moving each control rod at least one notcht

a. At least once per 7 days when above the preset power level of the RWMnf ?_fCE, and

b. At least once per 24 hours when above the preset power level of theRWM ann and any control rod is ismovable as a result ofexcessive friction or mechanical interference.

4.1.3.1 3 All withdrawn control rods shall be determined OPERABLE bydemonstrating the scram discharge volume drain and vent valves OPERABLE, whenthe reactor protection system logic is tested per Specification 4.3.1.2, by

*ver1fying that the drain and vent valves:

a. Close within 30 seconde af ter receipt of a signal for control rods toscram, and*

b. Open when the scraa signal is reset or the scran discharge volumetrip is bypassed.

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*These ialves may be closed intermittently for testing under administrativecontrol.

iBRUNSWICK - UNIT 1 3/41-4 g

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RMU986-990er-9P999.. ,l _ . 2 7 . . . _ _ .-l . ! !

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REACTIVITY CONTROL SYSTEMS

CONTROL ROD MAXIMUM SCRAM INSERTION TIMES

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LIMITING CONDITION FOR OPERATION

3.1.1.2 The maximum scram insertion time of each control rod from the fullywithdrawn position to notch position 6, based on de-energization of the scrampilot valve solenoids as time zero, shall not exceed 7.0 seconds.

_APPLICARILITY: CONDITIONS I and 2.

ACTION:

With the maximum scram insertion time of one or more control rods exceeding7.0 seconds, operation may continue snel the provisions of Specification 3.0.4are not applicable provided thatt

a. The control rod with the slow insertion time is declared inoperable,

b. The requirements of Specification 31.31 are satisfied, and

A7 X.d The Surveillance Requirements of Specification 4.1.3 2.c are

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performed at least once per 92 days when operation is continued with

three or more control rods with slow scras insertion times:

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours.

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SURVEILLANCE REOUIREMENTS

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4.1.1 2 The maximum scram insertion time of the control rode shall bedemonstrated through measurements

; a. For all control rods prior to THERMAL POWER exceeding 40% of RATED '

l THERMAL POWER following CORE ALTEkATIONS or af ter a reactor shutdownthat is greeter than 120 days,

b. For specifically affected individual control rods followingmaintenance on or undification to the control rod or rod drive systeswhich could affect the scram insertion time of those specific controlrods, and

c. For 10% of the control rods, on a rotating basis, et least once per120 days of operation.

C

Q I F \4(tggy g;g ggy wcn:. usvet or RvtM,C.

M D% dWMD OF- M gACMCM %. l.4.1.d hJP.C 4%

M M M \ Gr %. ARb,

BRUNSWICK - UNIT 1 3/4 1-$

Antes.et Mowwm-eemr-erees,';ir :: 7.:... .A.43

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TOUR CONTROL ROD GROUP SCRAM INSERTION TIMES


3.1.3.4 The average scram insertion time, from the fully withdrawn position,for the three fastest control rods in each group of four control rods arrangedin a two-by-two array. based on deenergitation of the scram pilot valvesolenoids as time zero, shall not exceed any of the following:

Position Inserted From Average Scram inser- <Fully Withdrawn tion Time (Se cond s)

I46 0.33 )

36 1.12 k26 1.93

6 3.58

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2. }

ACTION:

With the average scram insertion times of control rods exceeding the abovelimits, operation may continue and the provisions of Specification 3.0.4 arenot applicable provided:

The control rods with the slower than average scram insertion timesa.are declared inoperable,

b. The requirements of Specification 3.1.3.1 are satisfied, andM

/. 4 The Surveillance Requirements of Specification 4.1.3.2.c areperformed at least once per 92 days when operation is continued with

| three or more control rods with slow scram insertion times.


SURVEILLANCE REQUIREMENTS-

4.1.3.4 All control rods shall be demonstrated OPERABLE by. scram time testingfrom the fully withdrawn position as required by Surveillance Requirement

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BRUNSWICK - UNIT 1 3/4 1 7 Amendment No. 56I

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*CONTROL ROD SCRAM ACCUMULATORS

LIMITINC CONDITION FOR OPERATION

3.1.3.5 All control rod scram accumulators shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*. %

ACTION!

a. In OPERATIONAL CONDITION 1 or 2 with one control rod scram baccumulator inoperable, the provisions of Specification 3.0.4 are notapplicable and operation may continue, provided that within 8 hourst

1. The inoperable accumulator is restored to OPERABLE status, or

2. The control rod associated with the inoperable accumulator isdeclared inoperable, and the requirements of Specificatiun3.1.3.1 are satisfied.


b. In OPERATIONAL CONDITION 5* with a withdrawn control rod scram iaccumulator inoperable, fully insert the affected control rod andelectrically disarm the directional control valves within one hour.The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS

4.1.3.5 The control rod scram accumulators shall be determined OPERABLEt

a. At least once per 7 days by verifying that the pressure and leakdetectors are not in the alarmed condition, and

b. At least once per 18 months by performance of at<

1. CHANNEL FUNCTIONAL TEST of the leak detectors, and

2. CHANNEL CALIBRATION of the pressure detectors.

. *At least the accumulator associated with each withdrawn control rod. Notl applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.|

b. AMby iE WlMf4 Y MD5F 'Pesl/stit led O@ MW 4 y 'g W ogg SE%T5 OF 9 0 C t F i c A r t o u ~5 l. A.\.dME AA $ 0 AT\ WlD . I

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BRUNSWICK - UNIT 1 3/4 1-8 Amendment No. 130

REACTIVITY CONTROL SYSTEMS* *

. CONTROL ROD DRIVE COUPLING,

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LIMITING CONDITION POR OPERATION

3 1 3.6 All control rods shall be coupled to their drive mechanisms. i

APPLICARILITY: CONDITIONS 1, 2, and $*.

ACTION:

a. In CONDITION 1 or 2 vith one control rod not coupled to itsassociated drive mechanism, the provisions of Specification 3.0.4 arenot applicable and operation may continue provided;

RW N4

1. Within the preset power level of the 4999,#tte control rod isdeclared inoperable and fully inserted until recoupling can he ,

attempted with THERMAL POWER above the preset power level of theasest hwh ed. % reIair mee .+ Sta.iSc.h 3.l.4J.d.< s. s.Ari s Gi e ik.

2. Above the preset power level of the ese , t / control rod drive t

is inserted to accomplish recoupling. If recoup 11ng is notaccomplished on the first attempt, declare the control rodinoperable, fully insert the control rod, and electricallydisarm the directional control valves.

3. The requirements of Specification 3 1.3.1 are satisfied.!

b. In CONDITION 5*, with a withdrawn control rod not coupled to its

! associated drive mechanism, insert the control rod to accomplishrecoupling. The provisions of Specification 3.0.3 are notapplicable. ,

SURVEILLANCE REOUIREMENTS

4.1.3.6 The coupling integrity of a control rod shall be demonstrated bywithdrawing the control rod to the fully withdrawn position and verifying thatthe rod does not go to the overtravel position;

a. Prior to reactor criticality af ter completing CORE ALTERATIONS thatcould have af f ected the control rod drive coupling integrity,

1*

| *At least each withdrawn control rod. Not applicable to control rods removed|

per Specification 3.9 10.1 or 3 9 10.2.

BRUNSWICK - UNIT 1 3/4 1-9 /Amendese*T- No- 1

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' CONTROL ROD POSITION INDICATION',

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3.1.1.7 All control rod reed switch position indicators shall be OPERARLF..,

APPLICABILITY: CONDITIONS 1, 2, and $*. ,

ACTION:

In CONDITION 1 or 23 gga.

[CWith one or more contro rod reed switch position indicatorsinoperable. : - ,. .%.," Full-in" or " Full-out" indication, the

provisions of Specification 3 0.4 are not applicable and -

operation may continue, provided that within one hour:

(, /) The position of the control rod is determined by analternate method, or

1./) The control rod is moved to a position with an OPERABLEreed switch position indicator, or ,

_3 , /) The control rod with the inoperable reed switch position

indicator is declared inoperable and the requirements off

Specification 313.1 are satisfied:

Otherwise, be in at least HOT SHUTDOWN within 12 hours..-

With one or more control rod reed switch " Full-in" and/oI. -out" position indicators inoperable, the control

rod may passed in the Rod Sequence ol Systes, theprovisions o p cification 3.0.4 ar applicable andoperation may co(ntIn provide

, a) The actual contro od po i n is known,I b) The af fectep trol rod is move he correct position

in the r sequence, and

c) ch bypassed control rod is separated in all directfros any other bypassed control rod by at least two contcells.

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b. In CONDITION 5* with a withdrawn control rod reed switch positionindicator inoperable, fully insert the withdrawn control rod. Theprovisions of Specification 3 0 3 are not applicable.

*At least each withdrawn control rod. Not applicable to control rods removed

b.

per Specification 3.9 10.1 or 3.9 10 2.

BRUNSWICK - UNIT 1 3/4 1-11

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KEACTIVITY CONTROL SYSTEMS :.

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4.1.3.7 i The control rod reed switch position indicators shall be determinedOPERABLE by verifying

a. At least once per 24 hours, that the position of the control rod laindicated, '

Ib. That the indicated control rod position changes during the movementof the control rod when performing Surveillance Requirement ,

4.1.3.1.2, and

c. That the control rod reed switch position indicator corresponds tothe control rod position indicated by the " full-out" reed switches

3

when performing Surveillance Requirement 4.1.3.6.b. '

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\4.1. . When the RSCS is required to be OPERABLE, the post f aa :d ~~

bypassing of c rods with inoperable " Full i " u l-out" reed switch..

position indication sha u _-'Wsecond licensed operator or otherqualified me e technical a

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BRUNSWICK - UNIT 1 3/4 1-12 Amendment No. 76 ,

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.R'EACTIVITY CONTROL SYSTEMS

3/4.1.4 CONTROL ROD PROGRAM CONTROLS -

ROD WORTH MINIMIZER


3.1.4.1 The Rod Worth Minimizer (RWM) shall be OPERABLE when THERMAL POWER is

1esa thanp\o,of RATED THERMAL POWER.loAPPLICABILITY: OPERATIONAL CONDITIONS 1 and 2*. |

ACTION:)

With the WM ino rable, t e provisi ns of Sp ificatio 3.0.4 a not*k applic le, op ation ma continue nd conte rod mo ment is ermittg( Q ,1\ prov ed tha a second icensed o erator o other qu ified . mber of he

te nical s aff is pr ent at t reactor ontrol nsole a verifi sb mplianc with the prescribed ontrol r d patter |


4.1.4.1.1 The RWM shall be demonstrated OPERABLE in OPERATIONAL CONDITION 2, Iprior to withdrawal of control rods for the purpose of making the reactorcritical and in OPERATIONAL CONDITION 1 when the RWM is initiated during |control rod insertion when reducing THERMAL POWER byl

a. Verifying proper annunciation of the selection error of at least oneout-of-sequence control rod, and

b. Ver.ifying the rod block function of the RWM by n.oving an out-of-m.luence control rod.

4.1.4.1.2 The RWM shall be demonstrated OPERABLE by verifying the control rodBanked Position Withdrawal Sequence input to the RWM computer is correct |following any loading of the sequence program into the computer.

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* Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is |permitted for the purpose of determining the OPERABILITY of the RWM prior towithdrsaal of control rods for the purpose of bringing the reactor tocriticality.


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ATTACHMDG 1.

(3.1.4.1 ACTION)

With the RWM inoperable after the first 12 control rods have lr a.

been fully withdrawn on a startup, operation may continue || provided that control rod movement and compliance with theprescribed BPWS control rod pattern are verified by a secondlicensed operator or qualified member of the plant technical

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staff. cA _b. With th'a RWM inoperable before the irst 12 control rods arewithdrawn on a startup, one startup per . ear aay be performedprovided that control rod movement and compliance with theprescribed BPWS control rod pattern are verified by a secondlicensed operator or qualified member of the plant technicalstaff,

c. With RWM inoperable on a shutdown, shutdown may continueprovided that control rod movement and compliance with. theprescribed BPWS control rod pattern are verified by a second' licensed operator or qualified member of the plant technicalstaff.

d. With RWM operable but 1:1dividual control rod (s) declaredinoperable, operation and control rod movement below the presetpower level of the RWM may continue provided:

1. No more than three (3) control rods are declaredinoperable in any one BPWS group, and,

2. The inoperable control rod (s) is bypassed on the RWM andcontrol rod movement of the bypassed rod (s) is verified by asecond licensed operator or qualified member of the planttechnical staff.

e. With RWM inoperable, the provisions of Specification 3.0.4 arenot applicable.

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REACTIVITY CONTROL SYSTEMS.

R,0D SEQUENCE CONTROL SYSTEM

LIMITING CONDITION FOR OPERATION DA\b

1.4.2 The Rod Sequence Control System (RSCS) shall be OPERABLE when THEPt .R is less than 20% of RATED THERMAL POWER.

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APPL ABILITY: CONDITIONS 1* and 2* #.

ACTION:

a. W the RSCS inoperable:

1. ntrol rod withdrawal for reactor startup shal not begin.

2. If ntrol rod withdrawal has started and T POWER is lessthan 0% of RATED THERMAL POWER, control r movement shall notbe pe tted, except by scram, until the sequence controlsystem returned to OPERABLE status.

3. With THE POWER being reduced by c trol rod insertion, donot continu ontrol rod insertion ept by a scram.(

b. With erroneous contr rod position i t to the RSCS, the sequencerestraints may be bypa d for corr ion of the erroneous '

information and reiniti ation the RSCS provided that a secondItcensed operator or othet ual ed member of the technical staff ispresent at the reactor cont onsole and verifies compliance withthe prescribed control rod p en.

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*See Sp al Test Exception 3.10.2.

#En - into CONDITION 2 and withdrawal of selected control rods is raittedf the purpose of determining the OPERABILITY of the RSCS prior to hdrawal..

control rods for the purpose of bringing the reactor to criticalit,

BRUNSWICK - UNIT 1 3/4 1-15 gigy Q ,ECu. arr.w.w.aar .

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YkNb |SlfRVEll.I.ANCE RE01f f REMENTS1

j4. e RSCS shall be demonstrated OPERABLE by attempting to se -

move an ou uence control rod in each of the other groups:

a. In CONDITION 2 p o control rod withdrawal for areactor startu

b. as the RSCS is automatically in during control rodnsertion when reducing THERMAL POWER.

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1 _Am Mo.BRUNSWICK - UNIT 1 3/4 1-16 lu.n rr.u Itun. drs.65,

w-- sud 'Tnru . a-.u - 53

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SPECIAL TEST EXCEPTIONS

3/4 10.2 ROD SEOUENCE CONTROL SYSTEM*

/',

LIMITING CONDITION FOR OPERATION (MLL '

nd B3g by the Rod Sequence Control System per Specification 3.1. ay beended by means of the individual rod position bypass switeor thefo ing tests, provided that at least the requirements o cifications3.1. . nd 3.1.4.1 are satisfied

a. Sh margin demonstrations, Spe tion 4 1 1,

b. Control r ran time and4.1 3.2.a. iction measurements, Specification

c. Start-up Testi og. ith THERMAL POWER < 20% of RATED 'INERMALw

POWER.~

4APPLICABILI OND1TIONS I and 2.

ACTION *

the requirements of the above specification notOPERAB12 per Specification 3.1.4.2. satisfied, verif y that'

[SURVEILLANCE REOUIREMENTS L4N

_

f .10.2 When the sequence constraints of control rod groups A12' A34' Iare bypassed, verify

the RWM is OPERABLE per Specification kee,1,a.

b. That move -

the control rofs.Je6in 0% ROD DENSITY to the RSCSopreset power le -

'or limited to the single notch mode,

c. Conf his spec h dures by a secondneed operator or other qualified me % hp3 chnical staff.-

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(.BRUNSWICK - UNIT 1 3/4 10-2

Amme M.~ . . s.s s

";f= ;J Th a. _ _ ..f. 53.-.

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REACTIVITY CONTROL SYSTEM.

BASES

CONTROL RODS (Continued)

on a scram than has been analyzed even though control rods with inop9 tableaccumulators may still be inserted with normal drive water pressure.Operability of the accumulator ensures that there is a means available toinsert the control rods even under the most unfavorable depressuritation ofthe reactors.

Control rod coupling integrity is required to ensure compliance with theanalysis of the rod drop accident in the FSAR. The overtravel positionfeature provides the only positive means of determining that a rod is properlycoupled and, therefore, this check must be performed prior to achievingcriticality after reach refueling. The subsequent check is performed as abackup to the initial demonstration.

!

In order to ensure that the control rod patterns can be followed and,therefore, that other parameters are within their limits, the control rodposition indication system must be OPERABLE.

The control rod housing support restricts the outward movement of acontrol rod to less than 3 inches in the event of a housing failure. The

,

amount of rod reactivity which could be added by this small amount of rodwithdrawal is less than a normal withdrawal increment and will not contributeto any damage to the primary coolant system. The support is not required whenthere is no pressure to act as a driving force to raoidly eject a drivehousing.

The required surveillance intervals are adequate to determine that therods are OPERABLE and not so frequent as to cause excessive wear on the systemcomponents.

3/4.1.4 CONTROL ROD PROCRAM CONTROLS

ControA rod withdrawal and insertion sequences are established to assurethat the maximum in sequence individual control rod or control rod segmentswhich gre withdrawn at any time during the fuel cycle could not be worthenough to result in a peak fuel enthalpy greater than 280 cal /gm in the eventof a control rod drop accident. The specified sequences are characterized byhomogeneous, scattered patterns of control rod withdrawal. When THERMAL POWERisgreaterthanorequaltoi[DEofRATEDTHERMALPOWER,thereisnopossiblej

rod worth which, if dropped at the design rate of the velocit -limi ray. couldresult in a peak enthalpy o i 280 cal /gm. Thus, requiring th RWM to i

be OPERABLE when THERMAL POWER is less than h of RATED THERMAU rVWLKprovides adequate control. h%

Use of the Banked Position Withdrawal Sequence (BPWS) ensures that in theevent of a control rod drop accident the peak fuel enthalpy will not begreater than 280 cal /gm (Reference 4).

BRUNSWICK - UNIT 1 B 3/4 1-3 Amendment No. 127.

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dt4SE@T ht W A C- N M d T 1p

RkACTIVITY CONTROL SYSTEM,

| BASES

CONTROL ROD PROCRAM CONTROLS (Continued)

he RSCS and RWM provid automatic upervision o assure t t

ou of-sequence rods will ot be withd awn or ins ted.

The analysis of the rod drop accident is presented in Section 15.4.6 ofthe Updated FSAR and the techniques of the analysis are presented in a topicalreport (Reference 1) and two supplements (References 2 and 3).

,

The RBH is designed to automatically prevent fuel damage in the event oferroneous rod withdrawal from locations of high power density during highpower operation. Two channels are provided. Tripping one of the channelswill block erroneous rod withdrawal soon enough to prevent fuel damage. This-

,

' system backs up the written sequence used by the operator for withdrawal of| control rods.

3/4.1.5 STANDBY LIQUID CONTROL SYSTEM,

1,

| The standby liquid control system provides a backup capability for| maintaining the reactor suberitical in the event that insufficient rods are

| inserted in the core when a scram is called for. The volume and weight' percent of poison material in solution is based on being able to bring the

reactor to the suberitical condition as the plant cools to ambientcondition. The temperature requirement is necessary to keep the sodiumpentaborate in solution. Checking the volume and temperature once each 24hours assures that the solution is available for use.

With redundant pumps and a highly reliable control rod scram system,operation of the reactor is permitted to continue for short periods of timewith the system inoperable or for longer periods of time with one of theredundant components inoperable.

Surveillance requirements are established on a frequency that assures ahigh reliability of the system. Once the solution is established, boronconcentration will not vary unless more boron or water is added, thus a checkon the' temperature and volume once each 24 hours assures that the solution isavailable for use.

.

1. C. J. Paone, R. C. Stirn, and J. A. Woodley, " Rod Drop Accident Analysisfor Large BWRs, "C. E. Topical Report NEDO-10527, March 1972.

2. C. J. Paone, R. C. Stirn, and R. M. Yound, Supplement 1 to NESO-10527,July 1972.

3. J. A. Haum, C. J. Paone, and R. C. Stirn, addendum 2, " Exposed Cores",supplement 2 to NEDO-10527, January 1973.

4. NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel,"Revision 6, Amendment 12.

$ tW.DE-2Voll-9- "6W UecSNC- M **d Y '" '" "

* '

BRUN C UN 1 /4 -4 Amendment No. 127

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t!.

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.

ATTACHMENT 2- |~

?

(3/4.1.4' BASES) |

.

- The RWM as a backup! to:procedurali control provides an automatic control rod -! pattern- monitoring- function to' ensure adherence to the BPWS control movement .!E sequences from 100% control rod density to 10% RATED THERMAL POWER and, thus,- ;

1eliminates the postulated . control rod drop accident , fromiresulting in a peak. fuel enthalpy greater' than 280 cal /gm .(Reference 5).~. . |,

The' requirement that: RWM be operable for the' withdrawal of-the first .12 -control 1 rods on a start'up is-.to; ensure that the' RWM' system maintainsia high:degree of availability,

s

Deviation from the BPWS control rod. pattern may be allowed 'for the performanceof ~ Shutdown- Martin Demonstration tests.' ,

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1. .

.1/4.10 SPECIAL TEST EXCEPTIONS.(, I

.

BAS F.S

i

3/4.10.1 PRIMARY CONTAINMENT INTECRITY

! The requirements for PRIMARY CONTAIN4ENT INTEGRITY is removed during theperiod when open vessel tests are being performed during low power PHYSICSTESTS. *

ii

/' x

3/4.10.2 ROD SEOUENCE CONTROL SYSTEM EUt;( Q

to perform the tests required in the Technical S ecif '

tis necessar the sequence restr movement. Theadditional surveillance ure that the specifications on heatr,enerstion own marg te not exceeded during the

n these tests are being performed.

3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS

Performance of shutdown margin demonstrations with the vessel head removedrequires additional restrictions in order to ensure that criticality does not

These additional restrictions are specified in this LCO.occur.

[ 3/4.10.4 RECIRCULATION LOOPS,

This special test exception permits reactor- criticality under no flowconditions and is required to perform certain start-up and PHYSICS TESTS whileat low WERMAL POWER levels.

3/4.10.5 PLAfff SERVICE WATER| .

l

This Special Test Exception permits securing the Service Water Systemconventional header when the nuclear header is out of service and is requiredto permit flange installation in service water system header cross-connectpiping.

'

gBRUNSWICK - UNIT 1 B 3/4 10-1 MhM QS ,

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~:cENCLOSURE $.::,

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. BRUNSWICK STEAM ELECTRIC PLANT, UNITS l'AND 2 7f'

-

NRC DOCKETS 50-325 & 50-324-. !- OPER ATING - LICENSES DPR-71 - & . DPR-62 |f

7 REQUEST:FOR LICENSE AMENDMENT 3-|JROD SEQUENCE CONTR0!! SYSTEM. i

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-rITECHNICAL SPECIFICATION PAGES - UNIT 21 ;j

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VNDEX.

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

SECTION PACE

3/4.0 APPLICABILITY.............................................. 3/4 0-13/4.1 REACTIVITY CONTROL SYSTEMS

3/4.1.1 SHUTDOWN MARCIN.......................................... 3/4 1-13/4.1.2 REACTIVITY AN0KALIES..................................... 3/4 1-23/4.1.3 CONTROL RODS

Control Rod Operability.................................. 3/4 1-3Control Rod Maximum Scram Insertion Times................ 3/4 1-5Control Rod Average Scram Insertion Times................ 3/4 1-6Four Cont rol Rod Group Scram Insertion Times. . . . . . . . . . . . . 3/4 1-7Control Rod Scram Accumulators........................... 3/4 1-8Control Rod Drive Coupling............................... 3/4 1-9Control Rod Position Indication.......................... 3/4 1-11Control Rod Drive Housing Support........................ 3/4 1-13

3/4.1.4 CONTROL ROD PROGRAM CONTROLS

Rod Worth Minimizer...................................... 3/4 1-140 ;J C ; ; _ ; ;; ; C ;; ; . ; '. 0 . : ;; . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1 1;3

Rod Block Monitor........................................ 3/4 1-173/4.1.5 STANDBY LIQUID CONTROL SYSTEM............................ 3/4 1-183/4.2 POWER DISTRIBUTION LIMITS

3/4.2.1 AVERACE PLANAR LINEAR HEAT CENERATION RATE............... 3/4 2-1

( 3/4.2.2 MINIMUM CRITICAL POWER RATIO............................. 3/4 2-2

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168BRUNSWICK - UNIT 2 IV Amendment No.

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INDEX.

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS- .

SECTION PACE

3/4.9 REFUELINC OPERATIONS (Continued)

3/4.9.3 CONTROL ROD P0SITION.................................. 3/4 9-5

3/4.9.4 DECAY TIME............................................ 3/4 9-6

3/4.9.5 COMMUNICATIONS........................................ 3/4 9-7.

3/4.9.6 CRANE AND HOIST OPERABILITY........................... 3/4 9-8

3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE POOL.................. 3/4 9-9

3/4.9.8 WATER LEVEL-REACTOR VESSEL............................ 3/4 9-10

3/4.9.9 WATER LEVEL-SPENT FUEL STORACE POOL................... 3/4 9-11-

3/4.9.10 CONTROL ROD REMOVAL

Single control Rod Removal............................ 3/4 9-12Multiple Control Rod Remova1.......................... 3/4 9-14

3/4.10 SPECIAL TEST EXCEPTIONS

3/4.10.1 PRIMARY CONTAINMENT INTECRITY......................... 3/4 10-1d /4.10.2 $0 OEQUENCE-00NTRob-eVeHMn. . . . . . . . . . . . . . . . . . . . . . . . .3/4 10-2

TA 3/4.10.3 SHUTDOWN MARCIN DEMONSTRATIONS........................ 3/4 10-33/4.10.4 RECIRCULATION L00PS................................... 3/4 10-43/4.10.5 PLANT SERVICE WATER................................... 3/4 10-5

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BRUNSWICK - UNIT 2 IX Amendment No. 163

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REACTIVITY CONTROL SYSTEMS I

LIMITING CONDITION FOR OPERATION (Continued).

|. . . . - -

ACTION: (Continued) |j

2. Lf the inoperable control rod (s) is inserted:

a) Within one hour disara the associated directional control valves jeither i

|1) Electrically, or |

2) Hydraulically by closing the drive water and exhaust waterisolation valves.

b) Otherwise, be in at least HOT SHUTDOWN within the next 12 hours,

c. With more than 8 control rods inoperable, be in at least HOT SHUTDOWNwithin 12 hours.

SURVEILLANCE REQUIREMENTS.

4.1.3.1.1 The scran discharge volume drain and vent valves shall bedemonstrated OPERABLE at least once per 31 days bys*

a. Verifying each valve to be open.

b. Cycling each valve at least one complete cycle of full travel.

4.1.3.1.2 All withdrawn control rods not required to have their directionalj control valves disarmed electrically or hydraulically shall be demonstrated'' OPERABLE by moving each control rod at least one notch:

j a. At least once per 7 days when above the preset power level of the RWMm , and

b. At least once per 24 hours when above the preset power level of theRWH aaN and any control rod is immovable as a result' of

excessive friction or mechanical interference.

4.1.3.1.3 All withdrawn control rods shall be determined OPERABLE bydemonstrating the scran discharge volume drain and vent valves OPERABLE, whenthe reactor protection system logic is tested per Specification 4.3.1.2, byverifying that the drain and vent valves:

'a. Close within 30 seconds af ter receipt of a signal for control rods toscras, and

b. Open when the scraa signal is reset or the scran discharge volumetrip is bypassed.

*These valvec may be closed intermittently for testing under administrativecontrol.

BRUNSWICK - UNIT 2 3/41-4 Ambed No.-L';l;;;J T..m . . ...J. 'S .

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AEACTIVITY CONTROL SYSTEMS

'CONTROL ROD MAXIMUM SCRAM INSERTION TIMES


3.1.3.2 The maximum scram insertion time'of each control rod from the fullywithdrawn position to notch position 6, based on de-energitation of the scrampilot valve solenoids as time zero, shall not exceed 7.0 seconds.

J

]( ,

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

|ACTION: I

With the maximum scram insertion time of one or more control rods exceeding7.0 seconds, operation may continue and the provisions of Specification 3.0.4are not applicable provided thatt

The control rod with the slow insertion time is declared inoperable,a.

b. The requirements of Specification 3.1.3.1 are satisfied, and

k.bTheSurveillanceRequirementsofSpecification.4.1.3.2. careperformed at least once per 92 days when operation is continued withthree or more control rods with slow scram insertion timest

kOtherwise, be in at least HOT SHUTDOWN within the next 12 hours.

Is


4.1.3.2 The maximum scram insertion time of the control rods shall beq['demonstrated through measurement

For all control rods prior to THERMAL POWER exceeding 40% of RATEDa.THERMAL POWER following CORE ALTERATIONS or after a reactor shutdownthat is greater than 120 days,

b. For specifically affected individual control rods followingmaintenance on or modification to the control rod or rod drive systemwhich could affect the scram insertion time of those specific' controlrods, and

c. For 10% of the control rods, on a rotating basis, at least once per120 days of operation.

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. REACTIVITY CONTROL SYSTEMS.

FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES.


3.1.3.4 The average scram insertion time, from the fully withdrawn position,for the three fastest control rods in each group of four control rods arrangedin a two-by-two array, based on deenergitation of the scram pilot valvesolenoids as time zero, shall not exceed any of the following:

Position Inserted From Average Scram Inser-Fully Withdrawn tion Time (Second s )

46 0.33 (36 1.1226 1.93 g

6 -3.58 /

APPLICABILITY: OPERATIONAL CONDITIONS I and 2.

ACTION:

With the average scram insertion times of control rods exceeding the abovelimits, operation may continue and the provisions of Specification 3.0.4 arenot applicable provided:

\ The control rods with the slower than average scram insertion timesa.

are declared inoperable,

b. The requirements of Specification 3.1.3.1 are satisfied, andL The Surveillance Requirements of Specification 4.1.3.2.c are

performed at least once per 92 days when operation is continued withthree or more control rods with slow scram insertion times.



4.1.3.4 All control rods shall be demonstrated OPERABLE by scram time testingfrom the fully withdrawn position as required by Surveillance Raquirement d'4.1.3.2.

,

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) REACTIVITY CONTROL SYSTEMS

CONTROL ROD SCRAM ACCUMULATORS


3.1.3.$ All control rod scram accumulators shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*.

ACTION:.

a. In OPERATIONAL CONDITION 1 or 2 with one control rod scramaccumulator inoperable, the provisions of Specification 3.0.4 are notapplicable and operation may continue, provided that within 8 hours:

1. The inoperable accumulator is restored to OPERABLE status, or

2. The control rod associated with the inoperable accumulator isdeclared inoperable, and the requirements of Specification3.1.3.1 are satisfied.m

-

-


b. In OPERATIONAL CONDITION $* with a withdrawn control rod scram'

accumulator inoperable, fully insert the affected control rod andelectrically disarm the directional control valves within one hour.The provisions of Specification 3.0.3 are not applicable.


4.1.3.5 The control rod scram accumulators shall be determinei OPERABLE:

a. At least once per 7 days by verifying that the pressure and leakdetectors are not in the alarmed condition, and

b. At least once per 18 months by performance of<t

)<[1. CHANNEL FUNCTIONAL TEST of the leak detectors, and

2. CHANNEL CALIBRATION of the pressure detectors.

*At least the accumulator associated with each withdrawn control rod. Notapplicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

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* CONTROL 900 DRIVE COUPLING.


3.1.3.6 All control rode shall be coupled to their drive mechanisme.

APPLICABILITY: CONDITIONS 1, 2, and 5*.

ACTION:

a. In CONDITION 1 or 2 with one control rod not coupled to itsassociated drive mechanies, the provisions of Specification 3.0.4 i

are not applicable and operation may continue provided:$WM

1. Within the preset power level of the 400lP.jthe control rod isdeclared inoperable and fully inserted until recoupling can beattempted with THERMAL POWER above the reset power level ofthe =R$0er RWM %d. %e feyvire mset of QecificAdien3.l.Y.I.d mec. s.4 s 4 ed . we

2. Above the preset power level of the he control rod drive.

is inserted to accomplish recoupling. Ir recoupling to notaccomplished on the first attempt, declare the control rodinoperable, fully insert the control rod, and electricallydisarm the directional control valves.

3. The requirements of Specification 3 1 3.1 are satisfied.

b. In CONDITION 5*, with a withdrawn control rod not coupled to itsassociated drive mechanism, insert the control rod to accomplishrecoupling. The provisions of Specification 3.0.3 are notapplicable.

SURVEILLANCE REQUIREDGtifr$

Mn y .;b .

4.1.3. ~

integrity of a control rod shall be demonstrated bywithde eisatp1 rod to the fully withdrawn position and verifying thatthe r M 'to the overtravel position

-4 Q 's.

. .

*At least each withdrawn control rod. Not applicable to control rode removedper Specification 3 9 10 1 or 3.9.10.2.

BRUNSWICK - UNIT 2 3/4 1-9 4,y fg,g gg,

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REACTIVITY CONTROL SYSTEMS,

CONTROL ROD POSITION INDICATION :*

. +

b LIMITING CONDITION FOR OPERATION t

i

3.1.3.7 All control rod reed switch position indicators shall be OPERABLE.

APPLICABILITY: CONDITIONS 1, 2, and $*..

ACTION: ,

a. In CONDITION 1 or 2 A# gMC.L.VD Wa

/ C. With one or more kontrol rod reed switch position indicatorsinoperable, M 4 for " Full-in" or " Full-out" indication, theprovisions of Specification 3 0.4 are not applicable andoperation may continue, provided that within one hour

[./) The position of the control rod is determined by an.alternate method, or

'l, . )) The control rod is moved to a position with an OPERABLEreed switch position indicator, or

). g) The control rod with the inoperable reed switch positionindicator is declared inoperable and the requirements ofSpecification 3.1.3.1 are satisfied; .

A(, Otherwise, be in at least HOT SHUTDOWN within 12 hours.

2. With one or more control rod reed switch " Full-in" and/or" Full-out" position indicators inoperable, the affected controlrod may be bypassed in ' the Rod Sequence Control System, theprovisions of Specificat'.on 3.0.4 are not applicable, andoperation may continue, provided:

.

a) The actual control rod position is known,

b) The affected control rod is moved to the correct positionin the proper sequence, and

'

c) Each bypassed control rod is separated in all directionsfrom any other bypassed control rod by at least twocontrol cells.

*At least each withdrawn control rod. Not applicable to control rods removedper Specification 3.9.10.1 or 3.9.10.2.

['h_ BRUNSWICK - UNIT 2 3/4 1-11

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REACTIVITY CONTROL SYSTEMS,

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.

LIMITING ';WDITION FOR OPERATION (Continued)

b. In CONDITION 5* with a withdrawn control rod reed switch positionindicator inoperable, fully insert the withdrawn control rod. Theprovisions of Specification 3.0.3 are not applicable.

,


4.1.3.7f E The control rod reed switch position indicators shall be determinedOPERABLE by verifyings

a. At least once per 24 hours, that the position of the control rod is '

indicated,

1'

b. That the indicated control rod position changes during the movementof the control rod when performing Surveillance Requirement )

"'

4.1.3.1.2, and 5 g

c. That the control rod reed swith position indicator corresponds to theecntrol rod position indicated by the " Full-out" reed switches when

,

I performing Surveillance Requirement 4.1.3.6.b.

\4.1.3. 2 When the R CS is required t be OPERABLE, the positio andbypas ing of control rods with inoper le " Full-in" r " Full-ou " reed swice

. posi ion indication shall be verifie by a secord 1 censed ope ator or othequ ified member o the technical s ff.

L _s

.

a

*At least each withdrawn control rod. Not applicable to control rods removedper Specification 3.9.10.1 or 3.9.10.2.


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liEACTIVITY CONTROL SYSTEMS

3/4 1.4 CONTROL ROD PROCRAM CONTROLS

ROD WORTH MINIMIZER,


3.1.4.1 The Rod Worth Minimizer (RWM) shall be OPERABLE when THERMAL POWER isless than RATED THERMAL POWER.

APPLICABILITY OPERATIONAL CONDITIONS 1 and 2*. |

ACTION:

I With t RWM in etable, e provis ns of Sp ification 3 4 are n@M appli able, op ration ma continue and cont ol rod move ni is per itted|

gg pro ded that a second icensed c.erator or other quali ied membe of thet nical s ff is pr ent at t reactor ontrol con le and-v tftes )

,

g j

1 mpliance ith the rescribed ontrol r d pattern. J'


4.1.4.1.1 The AWM shall be demonstrated OPERABLE in OPERATIONAL CONDITION 2, |prior to withdrawal of control rods for the purpose of making the reactor s

critical and in OPERATIONAL CONDITION 1 when the RWM is initiated during jcontrol rod insertion when reducing THERMAL POWER byt

a. Verifying proper annunciation of the selection error of at least oneout-of-sequence control rod, and

b. Verifying the rod block function of the RWM by moving an out-of-sequence control rod.

4.1.4.1.2 The RWM shall be demonstrated OPERABLE by verifying the control rod iBanked Position Withdrawal Sequence input to the RWM computer is correct

|following any loading of the sequence program into the computer..

..

.

* Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is|permitted for the purpose of determining the OPERABILITY of the RWM prior to

withdrawal of control rods for the purpose of bringing the reactor tocriticality.


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ATTACHMENT 1*-

(3.1.4.1 ACTION)

With the RWM inoperable after the first 12 control rods havea.been fully _ withdrawn on_a startup, operation may continueprovided that control rod movement and compliance with theprescribed BPWS control rod pattern are verified by a secondlicensed operator or qualified member of the plant technicalstaff. Q _. gb. With th'a RWM inoperable before the irst 12 control-rods arewithdrawn on a startup, one startup per ear may be performedprovided that control rod movement and compliance- with theprescribed BPWS control rod pattern are verified by a secondlicensed operator or qualified member of the plant technicalstaff,

c. With RWM inoperable on a shutdown,- shutdown may continueprovided that control rod movement and compliance with theprescribed BPWS control rod pattern are verified by a secondlicensed operator or qualified member of the plant- technicalstaff.

d. With RWM operable but individual control rod (s) declaredinoperable, operation and control rod movement below the presetpower level of the RWM may continue provided:

1. No more than three (3) control rods are declaredinoperable in any one BPWS group, and,

2. The inoperable control rod (s). is bypassed on the RWM andcontrol rod acvement of the bypassed rod (s) is verified by asecond licensed operator or qualified member of the planttechnical staff.

e. With RWM inoperable, the provisions of Specification 3.0.4 arenot applicable.

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REACTIVITY 00RTROL SYSTEh3 |

'

ROD SEOUENCE CONTROL SYSTEM*,

'

t

LIMITING CONDITION FOR OPERATION h \ 4L

t.4.2 The Rod Sequence Control System (RSCS) shall be OPERABLE when THERMP .R is less than 20% of RATED THERMAL POWER.

APPLI ILITY: CONDITIONS 1* and 2* f.

, ACTION:

a. With e RSCS inoperable

1. Cont rod withdrawal for reactor at up shall not begin.

2. If control withdrawal has sta and THERMAL POWER is lessthan 20% of D THERMAL POWE ontrol rod movement shall notbe permitted, e t by sera ntil the rod sequence control

system is returned OPE status.

3. With THERMAL POWER be educed by control rod insertion, do-not continue contro' d rtion except by a scram.

b. With erroneous contr rod position put to the RSCS, the sequencerestraints may be assed for correc n of the erroneous'

( information and nitialization of the CS provided that a second-licensed oper or other qualified membe f the technical staff'

is present he reactor control console a erifies compifance

with the scribed control rod pattern.

.

*See Spec Test Exception 3 10.2.

nto CONDITION 2 and withdrawal of selected centrol rods is pe teed#Entpurpose of determining the OPERABILITY of the RSCS prior to wit Iggawal

,

fo'

control rods for the purpose of bringing the reactor to criticality.

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BRUNSWICK - UNIT 2 3/4 1-15

l RETYPED TECH. SPECS.|I Updated Thru. Amend. 78|

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'4., ,


SURVEILLANCE REOUIREMENTS DED -

,

4.1. RSCS shall be demonstrated OPERABLE by attempting to select and.

move an out- ence control rod in each of the other three .

a. In CONDITION 2 the et ntrol rod withdrawal for a '-reactor start-up, and-

b. As soon SCS is automatically in ring control rod

on when reducing THERMAL POWER.

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BRUNSWICK - UNIT 2 3/4 1-16 M%M.

M o^. 78

oo .

SPECI AL TEST EXCEPTIONS

, .3/4.10.2 ROD SEOUENCE CONTROL SYSTEM

'

LIMITING CONDITION FOR OPERATION W B'b

-- ._- - A'

f 10.2 The sequence constraints imposed on control rod groups Ag 4, n12a by the Rod Sequence Control System per Specification 3. may be..

susp d by means of the individual rod position bypass sw es for the

| follow ents, provided that at least the requirements pecifications3.1.3.1 an .l.4.1 are satisfied

a. Shutd in demonstrations, Sp cation 4.1.1,

y*and/ riction measurements, specificatiob. Control rod sei 4.1.3.2.a. and

Vc. Start-up Testin gram, with' L POWER < 20% of RATED THE

POWER.,

APPLICABILITY: ITIONS 1 and 2.

, ACTION: '-

,

i W the requirements of the above specification not satisfied, verifyL e _ RSCS is OPERABLE per Specification 3 1 4 9.

[% M c$SURVEILLANCE REOUIREMENTS

(enq es= N ele c - --_,--

(. 2 When the sequence constraints of control rod groups A12, A , or

--._ _- - __ . _.. ._. . _-

B - a,ssed, verify:,34

.

.,,0PERABLE per Specifica g$. 4.1,a. That the *

~ #gb. That movement of the N.t from 5fA ROD DENSITT to the RSCS

C ipreset power level i , or limited to the single notch mode ,and

/,.

e'/c. Confo with this specification and proced cond*,

''ed operator or other qualified member of the techn staff.| s

k-

2

, --

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'' e,

BRUNSVICK - UNIT 2 3/4 10-2 gg g g g

Kr.urED TECH hL'rl_ ..J lu u . .-.O 78

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,4

REACTIVITY CONTROL SYSTEM'

llBASES

CONTROL RODS (Continued)

( on a scram than has been analyzed even though control rods with inoperableaccumulators may still be inserted with normal drive water pressure.'

Operability of the accumulator ensures that there is a means available toinsert the control rods even under the most unf avorable depressurization ofthe reactors.

Control rod coupling integrity is required to ensure compliance withthe analysis of the rod drop accident in the FSAR. The overtravel positionfeature provides the only positive means of determining that a rod is properlycoupled and therefore this check must be performed prior to achievingcriticality after each refueling. The subsequent check is performed as abackup to the initial demonstration.

| In order to ensure that the control rod patterns can be followed andi therefore that other parameters are within their limits, the control rod

j position indication system must be OPERABLE.

The control rod housing support restricts the outward movement of acontrol rod to less than 3 inches in the event of a housing failure. Theamount of rod reactivity which could be added by this small amount of rodwithdrawal is less than a normal withdrawal increment and will not contributeto any damage to the primary coolant system. The support is not required whenthere is no pressure to act as a driving force to rapidly eject a drivehousing.

The required surveillance intervals are adequate to determine thatthe rods are OPERABLE and not so frequent as to cause excessive wear on the|

I system components.

3/4.1.4 CONTROL ROD PROGRAM CONTROLS

Control rod withdrawal and insertion sequences are established toassure,that the maximum in sequence individual control rod or control rodsegments which are withdrawn at any time during the fuel cycle could not beworth enough to result in a peak fuel enthalpy greater than 280 cal /gm in the,

event of,a control rod drop accident. The specified sequences arecharacterized by homogeneous, scattered patterns of control rod withdrawal.

| When THERMAL POWER is greater than or equal to 4 of RATED THERMAL POWER,'

there is no possible rod worth which, if dropp d at the design rate of thevelocity limit d result in a peak enth py of 280 cal /gm. Thus,requiring th. C "" RWM to be OPERABLE wh THERNAL POWER is less than %of RATED THERMAL POWER provides adequate con rol.

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BRL% MK - UNIT 2 B 3/4 1-3 Amendment No. 157

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REACTIVITY CONTROL SYSTEM

BASES

CONTROL ROD PROGRAM CONTROLS (Continued)

Use of the Banked Position Withdrawal Sequence (BPWS) ensures that in theevent of a control rod drop accident, the peak fuel enthalpy will not begreater than 280 cal /gm (Reference 4).

(seg/ence rodt will not/ be withdheRSCS/ndRWMp[videauttic superv/sion to sure tha out-of })

wn or inserted. yThe analysis of the rod drop accident is presented in Section 15.4.6 of

the FSAR, Updated and the techniques of the analysis are presented in atopical report (Reference 1) and two supplements (References 2 and 3).

| The RBH is designed to automatically prevent fuel damage in the event oferroneous rod withdrawal from locations of high power denstty during highpower operation. The RBM is only required to be operable when the limitingcondition described in Specification 3.1.4.3 exists. Two channels areprovided. Tripping one of the channels will block erroneous rod withdrawatsoon enough to prevent fuel damage. This system backs up the written sequenceused by the operator for withdrawal of control rods. Further discussion ofthe RSH system is provided in Reference 5.

3/4.1.5 STANDBY LIQUID CONTROL SYSTEM

The standby liquid control system provides a backup capability formaintaining the reactor subcritical in the event that insufficient rods areinserted in the core when a scram is called for. The volume and weightpercent of poison material in solution is based on being able to bring thereactor to the suberitical condition as the plant cools to ambient

. condition. The temperature requirement is necessary to keep the sodium| pentaborate in solution. Checking the volume and temperature once each 24| hours assures that the solution is available for use.

With redundant pumps and a highly reliable control rod scram system,operation of the reactor is permitted to continue for short periods of timewith the system inoperable or for longer periods of ti e with one of the

,

! redundant components inoperable.

1. C. J. Paone, R. C. Stirn, and J. A. Woodley, " Rod Drop Accident Analysis.

for Large BWRs " C. E. Topical Report NEDO-10527, March 1972.1

i 2. C. J. Paone, R. C. Stirn, and R. H. Yound, Supplement 1 to NEDO-10527,July 1972.

3. J. A. Haum, C. J. Paone, and R. C. Stirn, addendum 2 " Exposed Cores"supplement 2 to NEDO-10527, January 1973.

I 4. NEDE-24011-P-A, "Ceneral Electric Standard Application for Reactor Fuel,"Revision 6, Amendment 12.

5. NEDC-31654P, " Maximum Extended Operating Domain Analysis for BrunswickSteam Electric Plant," February 1989.

b . N E1DE -M oI l- f'- A "Gc.gc \ Mt.cAvi( .54AN Y "j

Ste.L b Nd RcVis{on } bMW O'

BRUNSWICK - UNIT 2 B 3/4 1-4 Amendment No. 168

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ATTACHMENT 2- -

3: (3/4.1.4, B ASES)

The RWM as-a backup to procedural control provides an.automatio control' rod -pattern' monitoring function to ensure ' adherence to the BPWS control movementsequences from 100% control rod. density- to 10% ? RATED.. THERMAL. POWER and, thus, =.oliminates .t he postulated control rod drop aooident from resulting in :a peak:fuel. enthalpy greater -than 280 cal /gm (Reference. 5).

,. . =. .

Tho requirement.that RWM betoperableifor;the withdrawal'ofitheffirst112; . ,

control rods on' a startup . is to' erisure that the. RWH. system maintains ;a high1-degree of' availability.

' Deviation from the BPWS control rod- pattern' may be allowed for the performance;of Shutdown Martin Demonstration tests. ,,

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3/4.10 SPECIAL TEST EXCEPTIONS I

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(' *.* \"BASES 1

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3/4.10.1 PRIMARY CONTAINMENT INTEGRITY

The requirement for PRIMARY CONTAINMENT INTEGRITY is removed during the j

period when open vessel tests are being performed during low power PHYSICS 1

TESTS.

3/4.10.2' ROD SEQUENCE CONTROL SYSTEM ggher to perform the tests required in the Techni 1 cations,

it is nece bypass the sequence restrain ol rod movement.The additional ou e re u e that the specifications onheat generatio rgin requirements are not exceeded duringt n these tests are be .

3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS

Performance of shutdown margin demonstrations with the vessel headremoved requires additional restrictions in order to ensure that criticalitydoes not occur. These additional restrictions are specified in this LCO.

( 3/4.10.4 RECIRCULATION IDOPS

This special test exception permits reactor criticality under no flowconditions and is required to perform certain start-up and PHYSICS TESTS while'at low THERMAL POWER . levels.

3/4.10.5 PLANT SERVICE WATER

This Special Test Exception permits securing the Service Water Systemconvencional header when the nuclear header is out of service and is required

I to permit flange installation in service water system header cross-connect| piping.

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BRUNSWICK - UNIT 2 B 3/4 10-1 AggqTnarrirr u A r.un. sr r.us .

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Documents

TECHNICAL SPECIFICATION PAGES - UNIT 1 - ie . --p--, u 4. e'...j1 ENCLOSURE 3. BRUNSWICK STEAM ELECTRIC PLANT,- UNITS 1 AND 2 f NRC DOCKETS 50-325 4.50-324 i OPERATING LICENSES DPR-71.4.DPR-62