Upload
others
View
1
Download
0
Embed Size (px)
Citation preview
*.
23]Oj OPERATING DATA REPORT
mc} DOCKET NO. 50-266>~c ui DATE July 7, 1983R8Fjp COMPLETED BY C. W. FAYOtntD(jgj TELEPHONE 414 277 2811cys4 OPERATING STATUS
@@O ........................
2 D' 1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1 . NOTES .
2. REPORTING PERIOD: JUNE 1983 . .
3. LICENSED THERMAL POWER (MUT): 1518. . .
4. NAMEPLATE RATING (GROSS MUE): 523.8 . .
5. DESIGN ELECTRICAL RATING (NET MUE): 497. . .
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 519. . .
7. MAXIMUM DEPENDABLE CAPACITY (FET MUE): 495. ........................
8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:NOT APPLICABLE
9. POWER LEVEL TO UHICH RESTRICTED, IF ANY (NET NUE): 390.010. REASONS FOR RESTRICTIONS, (IF Ant): Power level restricted because of self-imposed hot leg
limitation in an attempt to limit steam generator tube corrosion.THIS NONTH YR TO DATE CUNULATIVE
11. HOURS IN REPORTING PERIOD 720 4,343 110,87912. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 4,294.6 91,866.9
13. REACTOR RESERVE SHUIDOUN HOURS 0.0 1.4 625.414. HOURS GENERATOR ON LINE 720.0 4,287.9 89,396.215. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 793.516. GROSS THERMAL ENERGY GENERATED (MWH) 846,076 5,003,925 120,952,91417. GROSS ELECTRICAL ENERGY GENERATED (MWH) 282,740 1.669,870 40,545,66018. NET ELECTRICAL ENERGY GENERATED (MWH) 267,559 1,581,598 38,563,31619. UNIT SERVICE FACTOR 100.0 98,7 80.620. UNIT AVAILABILITY FACTOR 100.0 98.7 81.321. UNIT CAPACITY FACTOR (USING MDC NET) 75.1 73.6 71.222. UNT! CAPACITY FACTOR (USING DER NET) 74.8 73.3 70.023. UNIT FORCED OUTAGE RATE 0.0 0.1 2.724. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND LURATION OF EACH):
Twenty-six week refueling and steam generator replacing outage scheduled tocommence September 30, 1983. (f
Rh25. IF SHUTD0uN AT END OF REPORT PERIOD, ESildATED DATE OF STARTUP: NOT SHUTDOWNi
00 9)DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977 DD
s gs
DOCKET NO. 50-266
UNIT NAME Point Beach Unit 1
DATE July 7, 1983
COMPLETED BY C. W. Fay
TELEPIIONE 414/277-2811
AVERAGE DAILY UNIT POWER LEVEL
MONTil June, 1983
AVERAGE AVERAGE AVERAGEDAILY DAILY DAILY
POWER LEVEL POWER LEVEL POWER LEVELDAY MWe NET DAY MWe NET DAY MWe NET
1 372 11 371 21 371
2 372 12 372 22 371
3 372 13 373 23 372
4 372 14 372 24 372
5 373 15 373 25 372
6 357 16 372 26 3731
7 372 17 373 27 371
8 372 18 373 28 371
9 372 19 372 29 373
10 372 20 372 30 370
31 ---
AD-28A(1-77)
->cC
YNOwm*
m c:2w
HC
Cn N m. . . . g
OCn MOO3MQO
1CO- TypeC C,
w0Ca
Duration(Hours)
N
?977??yTy ReasonQ
O O > O m x 3 tn uncr t C. t O O o ic 0 C3O3Oc%HC3 Method Of ;3 =0 M H- M C C 3 H- " Shuttin9 M HM o D cJ HQnt 3 m 9
et H rt o H O 3 Down Reactor O~H U1 Orth 30 ~;3 inO O ct M O 3 0 3 e =x3M M 4 3 rt t* C0QQdN O w. 3 8"HMM CM O O O3 P m *;3 D ,O Z Ot*- M < H. O O H- t, s H t3 M Q 3 U1 MH T U3 = 2.-*M H-rt OO Cn
O 3M HM MQM C H- OC et >
0 U3 t?2 Ze et et - 2< q C-
O H- 0.J O c
X r* O X 3 3 5t H3 7 rt O OH O H t.
m o G toH- 3 H w ;$3 m 3 System e
4 m mO- -
Code w totn CX CO O3
Compongnt 3Code @w
enAwNH2I i | | O
rt OO > 3 3 3- Are C Q PJ O 4C3" rt 3 3 C. O U2OOCC" OM 9 CJ CJ T
WHH MN O- rt O3 8OO H Cn < Ca in 3 0x00 O t* M COC M 3O M t' ZOH Cn cJ rt O TM HM?J O3 M Zd 8 t!H- M MM OM 43Q OO ZCCZ~3 OO tu >>Z
C rt t:3 4 3 Ou A M H- K tu tu *
M<Cn t1 - Cn CJ tt t1 OO AODt* i
CO o* *OX Z 3 et H X 3 ^ H H 8C 3- C O H 0 3- O> N I < U NM H- *;3 O O 3 H- (3 O N ' # *O& m&Dm& &j f *O H- O US H H- q aW t OmW O g 9 mom%Q 3 M A # *H HO MO * * O
I MMC I * " OH Wmm * WCn - t* ct M3CJ C1 CJ O U3 f,9 |3 m rtO mon ~N3MC
H- rt i O gwM
NARRATIVE SUMMARY OF OPERATING EXPERIENCE
Docket No. 50-266Unit Name Point Beach Unit 1Date July 7, 1983Completed By C. W. FayPhone 414-277-2811
Unit 1 operated at approximately 371 MWe net throughout theperiod with no major load reductions. The primary-to-secondaryleakage remains stable at less than ten gallons per day.On June 18 the motor operator for redundant valve 1-826, whichcontrols flow from the boric acid storage tanks to the safetyinjection pump suction, was discovered with an open breaker. A
30-day Licensee Event Report will be filed to cover this event.On June 23 a Unit 1 pressure-operated relief valve lost indicationdue to a molded circuit breaker being open. Technical Specification15.3.5-5, Item 1, requires indication of this valve, there: Tore,a 30-day LER will be filed with the NRC.
.
e
. . . . . . . . :466752S 781
. .N EO V 4 1 601 90066871
. .S I 6694 84 63 88776,0,1 6,1 0, 6, 3,A T
. . E AL 54 2 209.R U 93 0 21 4.
5, 8, 9,E M. . V U
I C 4 8633 7. . G
1 71
. . , 9T 1
1 . .R1 O ,
8 . . P 2Y 2 E 3 2A . . R 6090 99750 8F 7 E 9 R
7 . . T T 33020503554 4 0 : 1 EA 4 0 9 5664 4 4 4 ) B.S. 23 A D H , M
8 3, 0, 9, 2, 2, 3,4 .4 L C 7 E
Jr . 1 . . O 4 2 1 7 90 A T
0 i C 4 E T 00 6 E Y PL E0,0,93 . . C
F U S- , N R0 7 . .I E Y 31 O J
L D5 Y E .S B N Ey B N .
4 O : T. l O )
O u D H . . 7 C I P AN J E P I T U D
T E . . H L A T
T E L G P 0000 000 0 0. R 9U 'E L E . . U P H
K E P T O A T 0 000C00000000J i |TC T M . S .R N 2 S T
O A O E H T O 7 D ED D C .T . T O M N F L
O N A O. N . 3 S C
E I , E R. . . . . . . . R : L H E I N
E ) B T T AB EA A L NM W C D I
. U MI D2 9 N L , E D
1 . T P E T ET 55S EP P A TI 9 M N A Y M SN . 4 E ( T I EU 7 : T T ( T U
9 ) I Y O ) S Q4 E : ( N N H S E E
8 U ) A W ) H RT
ME S L ) MHN ) ) T ,
A 83 : U G F : A H( W T T N D SL 1 2) S MN I ) C W M E E O O A
T P 55ES I Y I MD( N N M I
R 31 W OT T ,N T ( E R DO R8 MR EA DA I T D CR 6 E EP A 9 GN R E RS DAE D E P T
r CR ER T MD T AE E1 : : T ( ( 'C I U TEA X T LR L ) ) E YCET E H Y Y T I ( SO SANR GG E R U
A UNUW ( T T I R A H RREE N N N O CT N UN M I I C T , DW UEGN I I P LA J( GCCA SS O N ON E R SS R E AD H SNAA P EN I RW EHEYG OUUEE R C
C RS I PPA RO R OON GG T ( ( T VG A EOT AAC I ET DI N RY C A D F SN E W RACC HT PCT LW YEG A R RR O RI B OGR NECC A U OGNRRF OO D OT P( EEI LI I GEH NDREE0 T T EE D T
A T : LLL BHR N RSOT E N TY CCGL N CR NDLGA B B RAWT I UNLELT A A A U E AE I OA N CAAUC S T SERHEA AI F FT D FP OI N I I DD CI OE RRVOS CLFL UE T
O PRRT RN NCLT R OURT LI A I YYOH A DS EEA T EEOP P OEAEA RCEB T T C NU PHR CP P PLR EHSR VMT I CA I I D SE N AT : T EE ESAEO R EERR CRILCCE N WA EG ELDDE VF F RNEEET VI A A C SO O DT M N DT E GT E NO ESHLCRA P P R N N D ES AI EA M N N OLS I RGET EEEV A AOW T T
NT S L NU UA N N RO R LSA CCF O U RG RNFGM MH RO SET S SSE D H ON T O EEI I I C E S RBCRT SS TT T T T T b PI I PC M SX X W A U MAUI OOT I I I I I U ET NEI A EA A F OE O UEONRRENN N N N H F RA URLND NMI PR HNRHUGGN UUUUUS I
R AE . . . . . . . . . . . . . . . . . . . . . . . . . T
P 1 234 5678 90 1 2345678901 23 4 5 AO 1 1 1 1 1 1 1 1 1 1 22222 2 D
DOCKET NO. 50-301
UNIT NAME Point Beach Unit 2__
DATE July 7, 1983
COMPLETED BY L W. Fay
TELEPIIONE 41./277-2811
AVERAGE DAILY UNIT POWER LEVEL
MONTII June. 1983
AVERAGE AVERAGE AVERAGEDAILY DAILY DAILY
POWER LEVEL POWER LEVEL POWER LEVELDAY MWe NET DAY MWe NET DAY MWe NET
1 -2 11 -2 21 -2
2 -2 12 -2 22 -2
3 -2 13 -2 23 -2
4 -2 14 -2 24 -2
5 -2 15 -2 25 -2
6 -2 16 -2 26 -6
7 -2 17 -2 27 -7
8 -2 18 -2 28 -10
9 -2 19 -2 29 -8
10 -? 20 -2 30 -10
31 ---
AD-28A(1-77)
UNIT SilUTDOWNS AND POMER REDUCTIONS DOCKET NO. 50-301UNIT NAME Point Beach Unit 2
DATE July 7, 1(383REPORT MONTli June, 1983 COMPLETED BY C. W. Fay
TELEPilONE 414/277-2811
m4
d tu tD o 4
.S a "c 5t 8'e nn-Et u4 o o p rd Ot c Q) , ,
No. Date g gg ty jgg Licensee Event y g'g Cause and Corrective Actione :3 :n a) v .c Report No. u) Eu To Prevent Recurrence
O- (4 G) En C o'
:C 3 oO
. . -
1 830325 S 720 C 1 N/A ZZ 7,Z Z Z Z r Completing refueling and steamgenerator sleeving outage.
# 3F: Forced Reason: Method: Exhibit G-InstrucS: Scheduled A- Equipment Failure (explain) l- Manual tions for Prepar-
B- Maintenance or Test 2- Manual Scram ation of Data EntC- Refueling 3- Automatic Scram Sheets for LER FiD- Regulatory Restriction 4- Other (explain) (NUREG-0161)E- Operator Training & License Exam
#rF- Administrative Exhibit I- SameAD-28B G- Operational Error (explain) Source(01-78) 11- Other faxolain)
.
NARRATIVE SUMMARY OF OPERATING EXPERIENCE
Docket No. 50-301Unit Name Point Beach Unit 2Date July 7, 1983Completed By C. W. FayPhone 414-277-2811
Unit 2 was shut down during the entire report period as the14-week steam generator sleeving and refueling outage drew toa close. Outage-related maintenance included the replacenent ofprimary coolant sampling isolation valve 2-955 and the completionof the steam generator sleeving.
On June 15 at 2100 hours it was discovered during core reloadingthat fuel assembly J69 was leaning in the core at an approximateangle of 30 from vertical. Another fuel assembly was substitutedin the core in spite of the fact that there was no visual physicaldamage to J69.
The reloading of the core was completed on June 18 and the upperinternals were installed on June 19. On June 23 containmentisolation valve operability tests, safety injection signal actuationtests, auxiliary feedwater initiation test, and containment sprayactuation sequence tests were performed. On June 26 the fillingand venting of the reactor coolant system was completed and theprimary heatup commenced. On June 28 cold rod drop tests werecompleted along with the first cycle on steam generator creviceflushing.
On June 16 at 2345 hours during fuel motion the sample pump P707Afor radiation monitors 2RE-211 and 2RE-212, containment rad gasand air particulate monitors, was discovered out of service. OnJune 17 at 0130 hours a blown fuse was discovered in the powersupply to P707A. This fuse was replaced and the system was returnedto operation. The radiation monitoring system history file showsthat P707A probably tripped at 2018 hours on June 16. This eventis reportable in the format of a 14-day Licensee Event Report.
On June 21 safety injection pump 2P15A was being inspected for aseal problem and a broken shaft key was discovered. This issimilar to a failure in November 1981. Further investigation intothe cause of the pump failure mechanism is underway.
On June 27 during an attempt to equalize level in the safetyinjection accumulators the reactor coolant system was opened tothe accumulator piping. This caused a pressurization of thereactor coolant system which caused a pressurizer pressure-operatedrelief valve to open. This event is being evaluated for reportabilityto the NRC at this time.
.
/g C
Wisconsin Electnc eaara couraur231 W. MICHIGAN, P.O. BOX 2046. MilnAUKEE, WI 53201
July 11, 1983
Director of Regulator, perationsU. S. NUCLEAR REGULATORY COMMISSIONWashington, D. C. 20555
Gentlemen:
MONTHLY OPERATING REPORTSPOINT BEACH NUCLEAR PLANT
Attached are monthly operating reports for Units 1 and
2, Point Beach Nuclear Plant, for the calendar month of June
1983.
Very truly yours,
Y/-
6CG fVice President-Nuclear Power
C. W. Fay
Attachments
Copies to J. G. Keppler - NRC, Region IIINRC Resident InspectorC. F. Riederer - PSCW
+
1
1 \