Proposed tech specs for increase in max fuel enrichment ... · The initial enrichment is 4.5 weight percent U-235 or less; or b. The initial enrichment is from 4.5 up to a maximum

ATTACHMENTB

MARKED-UPTECHNICALSPECIFICATIONS

Remove Pa e Insert Pa e

XII

XVII

3/4 9-173/4 9-1 83/4 9-19

B 3/4 9-35-55-6

XII

XVII

3/4 9-173/4 9-1 83/4 9-193/4 9-203/4 9-213/4 9-22B 3/4 9-3

5-55-6

9502iOOZb3 95020bPDR ADCICK 05000275P PDR

INOEX

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIRENENTS

SECTION PAGE

3 4.9 REFUELING OPERATIONS

3/4.9.1 BORON CONCENTRATION.....................................

3/4.9.2 INSTRNENTATIONe~ ~ e ~ ~ ~ o ~ o ~ os ~ ~ ~ o o ~ os ~ os sos e o ~ ~ ~ ~ e e e ~ ~ e e ~

3/4.9.3 DECAY TIMEoo

3/4.9.4 CONTAINNENT PENETRATIONS................................3/4.9.5 COWNICATIONS......

3/4.9e6 NNIPULATOR CRANE.ssoooooooooosoooooooooooosoo ~ oo ~ oososo

3/4.9.7 CRANE TRAVEL —FUEL HANDLING BUILDING...................3/4.9.8 RESIDUAL HEAT REHOVAL AND COOUNf CIRCUITION

igh Mater Level........................................H

ow Mater Level.........................................L

3/4 9-1

3/4 9-2

3/4 9-3

3/4 9-4

3/4 9-5

3/4 EHR

3/4 9-7

3/4 9-8

3/4 ~3/4.9.9 CONTAINNENT VENTILATION ISOLATION SYSTEM................ 3/4 9-10

3/4.9.10 RATER LEVEL —REACTOR VESSE

uel ASsemblieseeoe ~ ~ ooooooooooooeoeoo ~ oooooooooeoooooooF

Atrol Rods e e o e e o o e o o o e o o o o e o o e e o e o o e s e e o e e e e o o e o o e o e e eCo

3/4.9.11 MATER LEVEL —SPENT FUEL POOL...........................

3/4 9-11

3/4 9-11a

3/4 9-12

3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM............... 3/4 9-13

3Fl&VAE 8.5'-1 VNiYS t AP ~ ~re~ PLIee PENIAL.

/ - F AS BSL DRAG~ZPJS~WT h

3 4.10 SPECIAL TEST EXCEPTIONS

o e e e epee

4 5-2 +9-I6

3/4 10 1 HUTDOMN MARGINsooooooooooooooooooeoooooo ~ oooooooeooosooS 3/4 10-1

3/4.10 2 GROUP HEIGHT, INSERTION AND POMER DISTRIBUTION LIMITS . 3/4 10-2

3/4.10.3

/4.10.4

HYSICS TESTS o o o o o o o o o o s o o o o o o o o o s o o o o o o o o o s o s o s e o o o o o o sP

POSITION INDICATION SYSTEM —SHUTDOMN...................

3/4 10-3

3/4 10"4

DIABLO CANYON —UNITS 1 5 2TSIN.4A

No .A 0, 9

J

7

I ~

4

e

.g '4, - ~/

't s

~ =>

p S0

P

P I P P

Insert APage xii

Spent Fuel Pool Region 2....................... ............3/4 9-17

FIGURE 3.9-2 MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP AS

A FUNCTION OF INITIAL ENRICHMENT AND PELLET

DIAMETER TO PERMIT STORAGE IN REGION 2..........3/4 9-18

Spent Fuel 'Pool Boron'Concentration............ ............'3/4 9-19

Spent Fuel Pool Region 1....................................3/4 9-20

FIGURE 3.9-3 MINIMUM RE(UIRED ASSEMBLY DISCHARGE BURNUP AS

A FUNCTION OF INITIAL ENRICHMENT (NO IFBA) TO

PERMIT STORAGE IN REGION 1............ 3/4 9-22

P 141

IJ

INDEX

BASES

SECTION

3 4.9 REFUELIHG OPERATIONS

PAGE

3/4.9.1

3/4.9.2

3/4.9.3

3/4.9.4

3/4.9e5

3/4.9o6

BORON CONCENTRATION.........~........................... B 3/4 9-1

INSTRUMENTATION.... .................................... B 3/4 9-1

ECAY TIMEo ~ ~ o ~ oooo ~ o ~ oo ~ ~ oooo ~ ~ o ~ ~ oo ~ ~ ooo ~ ooooo ~ ~ ~ o ~ eelD B 3/4 9-1

CONTAINMENT PENETRATIOHS................................ B 3/4 9-1

COWUHICATIONS.......-....----.....-..................-. B 3/4 9-1

MNIPULATOR CRANE....................................... B 3/4 9-1

3/4.9.7 CRNE TRAVEL —FUEL HNDLIHG BUILDING..... .. . ....... B 3/4 9-2

3/4.9.8

3/4.9.9

RESIDUAL HEAT REMOVAL AND CtmLANT CIRCULATION........... B 3/4 9-2

CONTAIHMENT VENTILATIOH ISOLATION SYSTEM....... ~ ~ ~ B 3/4 9-2

3/4.9.10 and 3/4.9.11 MATER LEVEL —REACTOR VESSEL and SPENT FUELLo ~ ~ e ~ eoe ~ eooooo ~ eeeoeeeoeee ~ eeeeee ~ oeeoeeeeoeoeeeee ~POO B 3/4 9-2

3/4.9.12 FUEL HNDLING BUILDING VENTILATIONSYSTEM............... B 3/4 9-3

9.13 SPE I PI V NToe ooooooooo oooooo e

3f4. PE'EL ASSEMel g SToRA&E'....4.1 SPECIAL TEST EXCEPTION

B 3/y 9-3

3/4.10.1

3/4.10.2

3/4.10.3

3/4.10.4

HUTDOWN MARGINo o o o o o o o o ~ o o o o o o e o ~ ~ o ~ ~ ~ o o ~ o o ~ ~ o o o o o o o o ~ ~S

GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTIONLIMITSoo o o e o o o ~ o ~ o o e o o ~ ~ ~ ~ o ~ o o ~ o o ~ ~ e ~ e o o o o ~ o ~ e ~ o e e ~ o o ~ o ~

HYSICS TESTSo ~ o ~ ~ ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ oo ~ ~ o ~ ~P

B 3/4 10-1

B 3/4 10-1

B 3/4 10-1

POSITION INDICATION SYSTEM —SHUTDOWN................... B 3/4 10-2

DIABLO CNYON —UNITS 1 5 2TSIN.4A

xv) 1

~ ~

d

l

~ s ~ ~ ~ ~ i > a e ~ ~ ~ 4 ~ k'CA ~ ~ "~ ~ 4 " ' ~ '..i p» v s, "4 ~ ~ >

4

REFUELING OPERATIONS

3 4-9-14 SPENT FUEL ASSBSLY STORAGE

Semor VE;~ 000~ eecioe Z.

LIMITING COHDITI FOR OPERA IOH

pa. f lc + d's m ~wW~y

3.9.14.1 The combination of initial enrichment and ative burnup orspent fuel assemblies stored in Region 2 shall be within the acceptable areaof Figure 3.9-2.

APPLICABILITY: Mhenever fuel assemblies are in the s nt fuelfo'(lo wigp.

ACTION:

ao

b.

Nth the requirements of the abov specification not satisfied,suspend all Novement of fuel ass lies and crane operations (withloads in the fuel storage area) move the non-complying fuelassemblies to R ion 1 Until the requirements of the abovespeci ica ion are satisfied, boron concentration of the spent fuelpool shall be verified to be greater than or equal to 2000 ppm atleast once per 8 hours.

The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.

SURVEILLANCE RE UIREMEHTS

4.9.14.1 The cumulative burnup of each spent fuel assembly stored in Region 2shall be determined by analysis of its burnup history, prior to storage inRegion 2. A complete record of analysis shall be maintained for the timeperiod that the spent fuel assemb y remains in Region 2 of the spent fuelpool.

(DIABLO CANYON —UNITS 1 5 2 3/4 9-17 n os. and

ay 3 , 1986

g~r

Ilk '

I

E

\ r

*

'.)V t '

X .000Cl

26.0003

0

20.000

15,000

C

t0,000

te I I~

5.000

2.S 8.0 $-5 4.0 4.5

inttlal E ment, Wt% U-255

FIGURE 3.9-2MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP

AS A FUNCTION OF INITIALENRICHMENT TO PERMIT ~Q P8<<~STORAGE IN REGION 2 p(gms'l 6R.

DIABLO CANYON — UNITS 1 5 2 3/4 9-18 nt s. andM 30 986

C

~ ~',II ~ -..g ~

~ ~ ~ ~

I ~

~ ' ~ ~'

I ~

4V

rp~ '


SPENT FUEL

5pg~g F.</GAL. I OoL go~cd coNC. ~~7 /8~0&LIHITING CONDITION FOR OPERATION

3.9.14.2 The boron concentration of the spent fuel pool shall be greater thanor equal to 2000 ppm.

APPLICABILITY: Whenever fuel assemblies are in the spent fuel pool.

ACTION:

ao Mith the requirements of the above specification not satisfied,imediately suspend al1 movement of fuel assemblies in the spentfuel pool and initiate corrective actions to restore the boronconcentration.

b. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.

SURVEILLANCE RE UIREHENTS

4.9.14.2 The boron concentration of the spent fuel pool shall be determinedby chemical anaTysis at least once per 31 days.

DIABLO CANYON — UNITS 1 5 2TS39.4A

3/4 9-19 n t N . 8 day, 6

r .~

Jl,b

,4 ~A

P,

) l'

i14

E

'V 'V

("


Insert CPage 3/4 9-20

SPENT FUEL ASSEMBLY STORAGE

SPENT FUEL POOL REGION 1

LIMITING CONDITION FOR OPERATION

3.9. 14.3 The following conditions shall be met for storage of fuelassemblies in Region 1 of the spent fuel pool:

a. The initial enrichment is 4.5 weight percent U-235 or less; or

b. The initial enrichment is from 4.5 up to a maximum of 5.0weight percent U-235, and any of the following conditions aremet:

1) The combination of initial enrichment and cumulativeburnup of the assemblies is within the acceptable area ofFigure 3.9-3; or

2) The assemblies initially contained a minimum of a nominal36 mg/in. per assembly of the isotope B-10 integrated inthe fuel rods; or

3) The assemblies are put in a checkerboard pattern with anyof the following:a) water cells, orb) assemblies that initially contained a minimum of a

nominal 72 mg/in. per assembly of the isotope 8-10integrated in the fuel rods, or

c) partially irradiated fuel of at least 8000 MWD/MTU

cumulative burnup; or

4) The assemblies are put into a pattern with alternate rowsof fuel assemblies and water cells.

APPLICABILITY: Whenever fuel assemblies are in Region 1 of the spentfuel pool.

DIABLO CANYON — UNITS 1 AND 2 3/4 9-20

Insert C (Continueci)Page 3/4 9-21


LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

a ~ With the requirements of the above specification not satisfied,suspend all movement of fuel assemblies and crane operations(with loads in the fuel storage area) except to perform thefollowing: move the non-complying fuel assemblies into a

pattern that complies with requirements of the abovespecification. Until the requirements of the abovespecification are satisfied, boron concentration of the spentfuel pool shall be verified to be greater than or equal to 2000

ppm at least once per 8 hours.


SURVEILLANCE RE(UIRENENTS

4.9. 14.3 The cumulative burnup of each fuel assembly stored in Region 1

shall be determined by analysis of its burnup history, prior to storage inRegion 1. A complete record of initial enrichment, initial integral boroncontent, and the cumulative burnup analysis shall be maintained for thetime period that the fuel assembly remains in Region 1 of the spent fuelpool.


Insert C (Continued)Page 3/4 9-22

4000

(i

3000

I-

z 2000CL'

Acceptable

Unacceptable

1000

4.6 4.7 4.8 4.9INITIALENRICHMENT, WTs U-235

FIGURE 3.9-3MINIMUMREQUIRED ASSEMBLYDISCHARGE BURNUP

AS A FUNCTION OF INITIALENRICHMENT (NO IFBA) TO PERMITSTORAGE IN REGION 1


II


BASES

3 4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM

The OPERABILITY of this system ensures that the containment ventilationpenetrations will be automatically isolated upon detection of high radiation levelswithin the containment. The OPERABILITY of this system is required to restrict therelease of radioactive material from the containment atmosphere to the environment.

3 4.9.10 and 3 4.9.11 MATER LEVEL —REACTOR VESSEL gild SPENT FUEL POOL

The restrictions on minimun water level ensure that sufficient water depth isavailable to remove 9% of the assumed 1(C iodine gap activii>- released from therupture of an irradiated fuel assembly. The miniaanu water depth is consistent withthe assumptions of the safety analysis.

The miniaam water level for movement of fuel assemblies (23 feet above thevessel flange) assures that sufficient water depth is maintained above fuel elementsbeing moved to or from the vessel. Mith the upper internals in place, fuelassemblies and control rods cannot be removed from the vessel. Operations involvingthe unlatching of control rods with the vessel upper internals in place may proceedwith less than 23 feet of water above the vessel flange provided that 23 feet ofwater (12 feet above the flange) is maintained above all irradiated fuel assemblieswithin the reactor vessel.

3 4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM

The limitations on the Fuel Handling Building Ventilation System ensure thatall radioactive material released from an irradiated fuel assembly will be filteredthrough the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.The OPERABILITY of this system and the resulting iodine removal capacity areconsistent with the assumptions of the safety analyses. Transfer of systemoperation into the iodine removal mode (exhaust through HEPA filters and charcoaladsorbers) is initiated automatically by either the new fuel storage or spent fuelpool area radiation monitors required by Specification 3.3.3. Followinginstallation of the Fue'i: Handling Building Ventilation exhaust radiation monitors,the automatic function oF.'.the fuel storage area monitors will be removed. Transferof system operation into the iodine removal mode will be by either of the two FuelHandling Building Ventilation exhaust radiation monitors required by Specification3.3.3. ANSI N510-1980 will be used as a procedural guide for surveillance testing.

3 4.9.13 SPENT FUEL SHIPPING CASK MOVEMENT

The restriction on spent fuel shipping cask movement ensures that no fuelassemblies will be ruptured in the event of a spent fuel shipping cask accident.The dose consequences of this accident are within the dose guideline values of10 CFR Part 100.

3 4.9.14 SPENT FUEL ASSEMBLY STORAGE

The restrictions acfuel poolnot be greater than 0.9

maximum enrichme

lMSER~ p

on t fue assemblie in the spentc ensure that keff will

The spent fuel storage as been designed and analyzed forweight percent U-235.

g.Q

DIABLO CANYON —UNITS 1 5 2 B 3/4 9-3 ND N . 70 D 6A 20 992

p )Q p,,W g P

Insert DPage B 3/4 9-3

under normal conditions, as discussed in TS 5.6.1.a. The requirement for 2000ppm boron concentration ensures that k-eff will not be greater than 0.95 underaccident conditions.

~"

r,>

J

DESIGN FEATURES

DESIGN PRESSURE AND TEMPERATURE

5.2.2 Containment is designed and shall be maintained for a maxiaam internalpressure of 47 psig and a temperature of 271 F, coincident with a Double DesignEarthquake.

5.3 REACTOR CORE

FUEL ASSEMBLIES

5.3.1 T core all contai 3 fuel ass ies with eac fuel assembly ormallyconta ng 264 uel rods c d with Zircal -4 except th limited subs tion offue rods b ilier rods onsisting of rcaloy& or ainless steel r by vacanciesm be ma if justif by a cycle- cific reload alysis. Ea fuel rod shal

ave a ominal acti fuel length 144 inches. e initial co loading shal avea m mum enric t of 3.15 wei t percent U- . Reload f shall be si ar inp ica'l desig the initia core loading d shall have saxiaaau enri nt of.5 weight ent U-235.

I

CONTROL ROD ASSEMBLIES

5 .3.2 The reactor core shall contain 53 full length and no part length control rodassemblies. The full length control rod assemblies shall contain a nominal 142inches of absorber raateria1. The nusinal values of absorber saterial shall be 85silver, 15% indium, and 5X cadmium. All control rods shall be clad with stainlesssteel tubing.

5.4 REACTOR COOLANT SYSTEM


5.4.1 The Reactor Coolant System is designed and shall be aaintained:

a0

b.

Ci

VOLUME

In accordance with the Code requirements specified in Section 5.2 of theFSAR, with allowance for normal degradation pursuant to the applicableSurveil1 ance Requirements,

For a pressure of 2485 psig, and

For a temperature of 650 F, except for the pressurizer which is680 F.

5.4.2 The total water and steam volume of the Reactor Coolant System is 12,811 +100 cubic feet at a nominal Tavq of 576 F for Unit I and 12,903 + 100 cubic feet ata nominal Tavg of 577 F for Unit 2.

DIABLO CANYON — UNITS I 5 2 5-5ne 8 19

o 13 11

Insert EPage 5-5

5.3. 1 The reactor shall contain 193 fuel assemblies. Each assembly shallconsist of a matrix of Zircaloy-4 or ZIRLO clad fuel rods with an initialcomposition of natural or slightly enriched uranium dioxide as fuelmaterial. Limited substitutions of zirconium alloy or stainless steelfiller rods for fuel rods, in accordance with NRC-approved applications offuel rod configurations, may be used. Fuel assemblies shall be limited tothose fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analysis to comply withall fuel safety design bases. A limited number of lead test assembliesthat have not completed representative testing may be placed in non-limiting core locations.

'7

DESIGN FEATURES

5.5 HETEOROLOGICAL TOWER LOCATION

5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE

CRITICALITY

5.6.1@1 The spent fuel storage racks are designed and shall be eaintainedwith:

a. A keff equivalent to less than or equal to 0.95 when flooded with~h borated 'water, which includes a conservative allowance for

uncertainties as described in Section 9.1 of the FSAR.

b. A nominal 10.93 inch center to-center distance between fuelassemblies placed in the storage racks.

5.6. Th ff r new el fo he fir core ading ored y in ts t fu stor e rack shall t exc 0.90 w n fl ed wi unbor edater

DRAINAGE

5.6.2 The spent fuel storage pool is designed and shall be maintained toprevent inadvertent draining of the pool below elevation 133.

CAPACITY

5.6.3 The spent fuel storage pool is designed and shall be maintained with astorage capacity limited to no more than 1324 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIHIT

5.7.1 The components identified in Table 5.7-1 are designed and shall bemaintained within the cyclic or transient limits of Table 5.7-1.

INSERT F

DIABLO CANYON — UNITS I 5 2 Ame nt os. &30 986

't

1

Ri

'l' 1

Insert FPage 5-6

c. Fuel assemblies having a maximum U-235 enrichment of 5.0 weightpercent.

ATTACHMENTC

PROPOSED TECHNICALSPECIFICATION PAGES

INDEX

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS

SECTION PAGE


3/4.9.1

3/4.9.2

3/4.9.3

3/4.9.4

3/4.9.5

3/4.9.6

3/4.9.7

3/4.9.8

BORON CONCENTRATION.....................................

INSTRUMENTATION.........................................

ECAY TIME~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~D

3/4 9-1

3/4 9-2

3/4 9-3

COMMUNICATIONS..........................................

MANIPULATOR CRANE.......................................CRANE TRAVEL — FUEL HANDLING BUILDING...................

RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION

3/4 9-5

3/4 9-6

3/4 9-7

CONTAINMENT PENETRATIONS................................ 3/4 9-4

H igh Water Level........................................ow Water Level.........................................L

3/4 9-8

3/4 9-9

3/4.9.9

3/4.9.10

CONTAINMENT VENTILATION ISOLATION SYSTEM................ 3/4 9-10

WATER LEVEL — REACTOR VESSEL

Fuel Assemulles.........................................ontrol Rods............................................C

3/4 9-11

3/4 9-11a

3/4.9.11

3/4.9.12

3/4.9.13

FIGURE 3.9-1

WATER LEVEL — SPENT FUEL POOL........................... 3/4 9-12

FUEL HANDLING BUILDING VENTILATION SYSTEM............... 3/4 9-13

SPENT FUEL SKIPPING CASK MOVEMENT....................... 3/4 9-15

UNITS 1 AND 2 SPENT FUEL POOL LAYOUT............... 3/4 9-16

DIABLO CANYON — UNITS 1 & 2TSIN.4A

xi'mendment Nos. and

INDEX

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENT

SECTION

3 4.9 REFUELING OPERATIONS continued

3/4.9.14 SPENT FUEL ASSEMBLY STORAGE

Spent Fuel Pool Region 2................................

~Pa e

3/4 9-17

FIGURE 3.9-2

FIGURE 3.9-3

MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP ASA FUNCTION OF INITIAL ENRICHMENT AND PELLETDIAMETER TO PERMIT STORAGE IN REGION 2.............

Spent Fuel Pool Boron Concentration.....................Spent Fuel Pool Region 1................................

MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP ASA FUNCTION OF INITIAL ENRICHMENT AND PELLETDIAMETER TO PERMIT STORAGE IN REGION 1.............

3/4 9-18

3/4 9-19

3/4 9-20

3/4 9-22


3/4.10.1 SHUTDOWN MARGIN............................... -."... 3/4 10-1

3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS... 3/4 10-2

3/4.10.3 PHYSICS TESTS' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 10-3

3/4.10.4 POSITION INDICATION SYSTEM — SHUTDOWN................... 3/4 10-4

3 4.11 RADIOACTIVE EFFLUENTS

3/4.11.1

3/4.11.2

LIQUID EFFLUENTS

Liquid Holdup Tanks.....................................GASEOUS EFFLUENTS

Explosive Gas Mixture...................................as Storage Tanks.......................................6

3/4 11-1

3/4 11-2

3/4 11-3

DIABLO CANYON — UNITS 1 & 2TSIN.4A

Amendment Nos. and

INDEX

BASES

SECTION


PAGE

3/4.9.1

3/4.9.2

3/4.9.3

3/4.9.4

3/4.9.5

3/4.9.6

BORON CONCENTRATION..................................... B 3/4 9-1

INSTRUMENTATION......................................... B 3/4 9-1

E CAY T IME~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~D 8 3/4 9-1

CONTAINMENT PENETRATIONS................................ B 3/4 9-1

COMMUNICATIONS.......................................... B 3/4 9-1

MANIPULATOR CRANE....................................... B 3/4 9-1

3/4.9.7 CRANE TRAVEL — FUEL HANDLING BUILDING................... B 3/4 9-2

3/4.9.8

3/4.9.9

RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION........... B 3/4 9-2

CONTAINMENT VENTILATION ISOLATION SYSTEM................ B 3/4 9-2

3/4.9.10 and 3/4.9.11 WATER LEVEL — REACTOR VESSEL and SPENT FUEL00L ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~P 8 3/4 9-2

3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM............... B 3/4 9-3

3/4.9.13 SPENT FUEL SHIPPING CASK MOVEMENT....................... B 3/4 9-3

3/4.9.14 SPENT FUEL ASSEMBLY STORAGE............................. B 3/4 9-3


3/4.10.1

3/4.10.2

3/4.10.3

3/4.10.4

GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTIONL IMITS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~

PHYSICS TESTS.......................................... 1

B 3/4 10-1

B 3/4 10-1

POSITION INDICATION SYSTEM — SHUTDOWN................... B 3/4 10-2

SHUTDOWN MARGIN......................................... B 3/4 10-1

DIABLO CANYON — UNITS 1 L 2TSIN.4A

xv'l 1 Amendment Nos. and





3.9.14.1 The combination of initial enrichment, pellet diameter, andcumulative burnup for spent fuel assemblies stored in Region 2 shall be withinthe acceptable area of Figure 3.9-2.


ACTION:

a ~

b.

With the requirements of the above specification not satisfied,suspend all movement of fuel assemblies and crane operations (withloads in the fuel storage area) except to perform the following:move the non-complying fuel assemblies to Region 1 in accordancewith TS 3.9.14.3. Until the requirements of the abovespecification are satisfied, boron concentration of the spent fuelpool shall be verified to be greater than or equal to 2000 ppm atleast once per 8 hours.


SURVEILLANCE RE UIREMENTS

4.9.14.1 The cumulative burnup of each spent fuel assembly stored in Region 2shall be determined by analysis of its burnup history, prior to storage inRegion 2. A complete record of initial enrichment, fuel pellet diameter, andthe cumulative burnup analysis shall be maintained for the time period thatthe spent fuel assembly remains in Region 2 of the spent fuel pool.


3/4 9-17 Amendment Nos. and

~ ~ ~ [I I <two ' ~

~ ~

~ ~ ~ ~

I ~

~ '~ ~ '

~$

~ f I I

I I~ I

~ ~ ~

~ ~

~ I I



SPENT FUEL POOL BORON CONCENTRATION


- 3.9.14.2 The boron concentration of the spent fuel pool shall be greater thanor equal to 2000 ppm.


ACTION:

With the requirements of the above specification not satisfied,immediately suspend all movement of fuel assemblies in the spentfuel pool and initiate corrective actions to restore the boronconcentration.



4.9.14.2 The boron concentration of the spent fuel pool shall be determinedby chemical analysis at least once per 31 days.







3.9.14.2 The following conditions shall be met for storage of fuel assembliesin Region 1 of the spent fuel pool:

'a ~

b.

The initial enrichment is 4.5 weight percent U-235 or less; or

The initial enrichment is from 4.5 up to a maximum of 5.0 weightpercent U-235, and any of the following conditions are met:

1) The combination of initial enrichment and cumulative burnupof the assemblies is within the acceptable area of Figure3.9-3; or

2) The assemblies initially contained a minimum of a nominal 36mg/in. per assembly of the isotope B-10 integrated in thefuel rods; or

3) The assemblies are put in a checkerboard pattern with any ofthe following:a) water cells, orb) assemblies that initially contained a minimum of a

nominal 72 mg/in. per assembly of the isotope B-10integrated in the fuel rods, or

c) partially irradiated fuel of at least 8000 MWD/MTUcumulative burnup; or

4) The assemblies are put into a pattern with alternate rows offuel assemblies and water cells.

APPLICABILITY: Whenever fuel assemblies are in Region 1 of the spent fuelpool.

DIABLO CANYON — UNITS 1 & 2TS39.4A


0


LIMITING CONDITION FOR OPERATION Continued

ACTION

a ~

b.

With the requirements of the above specification notsatisfied, suspend all movement of fuel assemblies and craneoperations (with loads in the fuel storage area) except toperform the following: move the non-complying fuelassemblies into a pattern that complies with requirements ofthe above specification. Until the requirements of theabove specification are satisfied, boron concentration ofthe spent fuel pool shall be verified to be greater than orequal to 2000 ppm at least once per 8 hours.



4.9.14.3 The cumulative burnup of each fuel assembly stored in Region 1 shallbe determined by analysis of its burnup history, prior to storage in Region 1.A complete record of initial enrichment, initial integral boron content, andthe cumulative burnup analysis shall be maintained for the time period thatthe fuel assembly remains in Region 1 of the spent fuel pool.



~ ~ ~ ~

II~

- ~ s

II~

~ ~

I'

I II ' ~ ~ ~

~ g $~ ~

~ i


BASES

3 4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM

The OPERABILITY of this system ensures that the containment ventilationpenetrations will be automatically isolated upon detection of high radiation levelswithin the containment. The OPERABILITY of this system is required to restrict therelease of radioactive material from the containment atmosphere to the environment.

3 4.9.10 and 3 4.9.11 WATER LEVEL — REACTOR VESSEL and SPENT FUEL POOL

The restrictions on minimum water level ensure that sufficient water depth isavailable to remove 99% of the assumed 10K iodine gap activity released from therupture of an irradiated fuel assembly. The minimum water depth is consistent withthe assumptions of the safety analysis.

The minimum water level for movement of fuel assemblies (23 feet above thevessel flange) assures that sufficient water depth is maintained above fuel elementsbeing moved to or from the vessel. With the upper internals in place, fuelassemblies and control rods cannot be removed from the vessel. Operations involvingthe unlatching of control rods with the vessel upper internals in place may proceedwith less than 23 feet of water above the vessel flange provided that 23 feet ofwater (12 feet above the flange) is maintained above all irradiated fuel assemblieswithin the reactor vessel.

3 4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM

The limitations on the Fuel Handling Building Ventilation System ensure thatall radioactive material released from an irradiated fuel assembly will be filteredthrough the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.The OPERABILITY of this system and the resulting iodine removal capacity areconsistent with the assumptions of the safety analyses. Transfer of systemoperation into the iodine removal mode (exhaust through HEPA filters and charcoaladsorbers) is initiated automatically by either the new fuel storage or spent fuelpool area radiation monitors required by Specification 3.3.3. Followinginstallation of the Fuel Handling Building Ventilation exhaust radiation monitors,the automatic function of the fuel storage area monitors will be removed. Transferof system operation into the iodine removal mode will be by either of the two FuelHandling Building Ventilation exhaust radiation monitors required by Specification3.3.3. ANSI N510-1980 will be used as a procedural guide for surveillance testing.

3 4.9.13 SPENT FUEL SHIPPING CASK MOVEMENT

The restriction on spent fuel shipping cask movement ensures that no fuelassemblies will be ruptured in the event of a spent fuel shipping cask accident.The dose consequences of this accident are within the dose guideline values of10 CFR Part 100.


The restrictions placed on spent fuel assemblies stored in the spent fuel poolensure that k-eff will not be greater than 0.95 under normal conditions, asdiscussed in TS 5.6.1.a. The requirement for 2000 ppm boron concentration ensuresthat k-eff will not be greater than 0.95 under accident conditions. The spent fuelstorage has been designed and analyzed for a maximum enrichment of 5.0 weightpercent U-235.

DIABLO CANYON - UNITS 1 5 2TSB39.4A

B 3/4 9-3 Amendment Nos. and

8DESIGN FEATURES


5.2.2 Containment is designed and shall be maintained for a maximum internalpressure of 47 psig and a temperature of 271'F, coincident with a Double DesignEarthquake.

5.3 REACTOR CORE

FUEL ASSEMBLIES

5.3.1 The reactor shall contain 193 fuel assemblies. Each assembly shall consistof a matrix of Zircaloy-4 or ZIRLO clad fuel rods with an initial composition ofnatural or slightly enriched uranium dioxide as fuel material. Limitedsubstitutions of zirconium alloy or stainless steel filler rods for fuel rods, inaccordance with NRC-approved applications of fuel rod configurations, may be used.Fuel assemblies shall be limited to those fuel designs that have been analyzed withapplicable NRC staff-approved codes and methods, and shown by tests or analysis tocomply with all fuel safety design bases. A limited number of lead test assembliesthat have not completed representative testing may be placed in non-limiting corelocations.

CONTROL ROD ASSEMBLIES

5.3.2 The reactor core shall contain 53 full length and no part length control rodassemblies. The full length control rod assemblies shall contain a nominal 142inches of absorber material. The nominal values of absorber material shall be 80%silver, 15/. indium, and 5Ã cadmium. All control rods shall be clad with stainlesssteel tubing.

5.4 REACTOR COOLANT SYSTEM


5.4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.2 of theFSAR, with allowance for normal degradation pursuant to the applicableSurveillance Requirements,

b. For a pressure of 2485 psig, and

c. — For a temperature of 650 F, except for the pressurizer which is680'F.

VOLUME

5.4.2 The total water and steam volume of the Reactor Coolant System is 12,811 +100 cubic feet at a nominal Tavq of 576'F for Unit 1 and 12,903 + 100 cubic feet ata nominal Tavg of 577'F for Unit 2.


5-5 Amendment Nos. and

DESIGN FEATURES

!

5.5 METEOROLOGICAL TONER LOCATION

5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE

CRITICALITY

5.6.1 The spent fuel storage racks are designed and shall be maintained with:

a ~

b.

c ~

DRAINAGE

A keff equivalent to less than or equal to 0.95 when flooded withunborated water, which includes a conservative allowance foruncertainties as described in Section 9.1 of the FSAR.

A nominal 10.93 inch center-to-center distance between fuelassemblies placed in the storage racks.

Fuel assemblies having a maximum U-235 enrichment of 5.0 weightpercent.

5.6.2 The spent fuel storage pool is designed and shall be maintained toprevent inadvertent draining of the pool below elevation 133.

CAPACITY

5.6.3 The spent fuel storage pool is designed and shall be maintained with astorage capacity limited to no more than 1324 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT

5.7.1 The components identified in Table 5.7-1 are designed and shall bemaintained within the cyclic or transient limits of Table 5.7-1.


5-6 Amendment Nos. and

A%IACHMENTD

CRITICALITYSAFETY EVALUATIONOFTHE DIABLOCANYON NEW FUEL VAULT

WITH FUEL OF 5% ENRICHMENT

Documents

Proposed tech specs for increase in max fuel enrichment ... · The initial enrichment is 4.5 weight percent U-235 or less; or b. The initial enrichment is from 4.5 up to a maximum