ML19030A353
| ML19030A353 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/10/1977 |
| From: | Public Service Electric & Gas Co |
| To: | NRC/IE, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19030A353 (5) | |
Text
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Public Service Electric and Gas Company Salem Nuclear Generating Station P.O. Box #168 Hancocks Bridge, New Jersey 08038 Director Off ice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 August lO,
\\,
MONTHLY OPERATING REPORT
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SALEM GENERl>~TING STATION In compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, the following Monthly Operating Reports for the month of July 1977 are being sent to you.
(Original plus 10 copies)
Appendix B -
Average Daily Unit Power Level Appendix C -
op*erating Data Report Appendix D -
Unit Shutdowns and Power Reductions Additional copies of the Monthly Operating Reports are being sent to:
- 1.
Mr. James P. O'Reilly Director of US NRC Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, PA 19406
- 2.
Director, Office of Management Information and Program Control US Nuclear Regulatory Commission Washington, D.C.
20555 (1 COPY)
(2 COPIES)
Manager -
Salem Generating Station Enc.
Pg. 1-4 8-1-7. Rl The Energy People 95-2189 (5M) 10-72
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APPENDIX B e
AVERAGE DAILY UNIT POWER LEVEL MONTH JULY 1977 DAY AVERAGE DAILY POWER LEVEL 1
2 3
4 5
6 7
8 9
10 11
- 12
. 13 14 15 16 Pg. 2-4 8.1-7.Rl (MWe-NET) 1048 1058 1076 1052 581 261 677 299 0
0 Q
0 461 822 1070 1037 DOCKET NO.
50-272 UNIT,
SALEM # 1 DATE Augast 8, 1977 COMPLETED BY J. M. Zupko, J:i::.
TELEPHONE 309-365-7000 X50 7 DAY AVERAGE DAILY POWER LEVEL (MWE-:NET) 17 897 18 338 19 1030 20 858 21 982 22 545 23 501 24 511 25
. 426
-26 578 27 661 28 544 29 769 30 364 31 762
- 1.
APPF.NDIX C OPER.i\\UNG DATA mo19.
- OOCKET NO. ____
5_0_-_21_2 ____ _
UNIT Salem #1 DA'IE 8/9/77 CCMPLETED BY J.M. Zupko, Jr.
OPERATING S'l'AnIS TELEPHONE *309-365-7000 X507
- 1.
REPORTING PERIOD: July 19 7 7 GROSS HOURS IN REPORTING PERIOD: __ 7_4_4 __ __..._
- 2.
CURREN!!.Y AUl'HORIZED POWER LEVEL (MWt)3338 *MAX.DEPEND.CAPACITf(MWe-NET): lo 9o DFSIGN ELECTRICAL RATING(MNe-Net): 1090
- 3.
PCWER. LEVEL TO WHICi RESTRICTED (IF ANf) (MW'e-Net) :._N_o_n_e _____ _
- 4.
REASONS FOR RESTRICTION (IF.ANY) :.
'lmS MJN'lH YR TO DATE ctMJLATIVE S.
Nm4BER OP BllRS REACTOR WAS CRITICAL * * *
- 604.5
- 6.
REACTOR RF.SERVE SHTII'OOWN HOURS * * * * * *
- 0
- 0 583.3
- 1.
HOURS GENERATOR ON LINE * * *.......
o.o 3,761 4,062.6 o.o o.o.
3,371.9 o.o 3' 412. 2.
o.o
- 8.
UNIT RESERVE SHtl'I'OOWN HOURS * * * *.... ---- ---- ------
- 9.
GROSS mERMAL ENERGY GENERATED(}m). * *.1, 5 31, 6 7 3 7,162,860 7,211,557
- 10.
GROSS ELECTRICAL ENERG'l GENERATED (MWH) * *
- 4 8 9, 3 3 0 2,282,940 2,286,170
\\ 11.
NET ELECl'RICAL ENERGY' GENERATED(M1'1H) **** 459,115 I 12.
REA~ SERVICE FACTOR * * * * * * * * *
- 81
- 3 l l 2,093,598 2,093,598 81.8 81.8 I j l
I
- 13.
REACTOR AVAILABILIT! FACTOR * * * * * * *.* __ 0_1_._3_ _ __
0_1_. 0_ _ ___
0_1_..... 0_
- 14.
- UNIT SERVICE FACI'OR * * * * *...
lS.
UNIT AVAILABILITY FACTOR * ****
- 16.
UNIT CAPACITY FACI'OR(Using MDC). *
- * *
- __ 7_8_._4_
78.4 56.6 79.1 79.1 79.1 79.1 57.2
, 17. tlN1T
- OOACm FACTOR(Using Design MNe) * *
- __ 5_6_._6_ _ __
5_7.;... 2_ _ ___
s_1_._2_
- 18.
UNIT FORCED our.AGE RATE * * * * * * * * *
- 2 2
- 7 22.l 22.1
- 19.
SHU"TOO'NNS SOiEDULED OVER Nm 6 MJNI'HS (TYPE,DATE,AND DURATJ;ON OF EA.01) : 9-17-7 7 Modif +/-cation of Low Pressure Turbine ZO.
IF SHUT :OOWN AT END OF REFORI' PERIOD, ESTIMATED DATE OF sr.~:
N/A Zl.
UNITS IN TEST STATUS (PRIOR TO ca.MERCIAL OPERATION) :
FO~CASr
. *.ACHIEVED INITIAL CRITICALIT!
9..-3 O,... 7 6 12-11-7 6 Pg.,:3-4 8-1-7.Rl~
INITIAL ELEC!RICITf CCMt!ERCIAL OPERATION 11..-01-76 12-25-76 12-20-76 6-30-77
NO.
77',70 77-71 77-72 77-75 77-76 77-77 77-78 77..-81 77-82 l
SUMMARY
Pg.4-4 I
8.1-7.R 1 APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH July 1977 METHOD OF TYPE OUTAGE SHUTTING DOWN F: FORCED DURATION TIIB REACTOR OR DATE S: SCHEDULED (HOURS)
REASON REDUCING POWER 7-23-77 F
0.0 H
4 7-24-77 F
o.o H
4 7-25-77 F
1.9 A
1 7-25-77 F
o.o H
4 7-28-77 F
o.o H
4 7-28-77 F
0.0 H
4 7-29~77 F
0.0 H
4 7-30-77 s
11.1 B
3 7-31-77 F
0.0 H
4
- LOAD REDUCTION.
DOCKET NO.
50-272 UNIT NAME SJ\\.LE:M NO. l DATE 8/9/77 COMPLETED BY J. M. Zupko, Jr.
TELEPHONE 609-365-7000 X507 CORRECTIVE ACTIONS/COMMENTS Clean #13 Condensate Pump Strainers Cleari #12 Feed Pump Strainers Partial Loss of Vacuum -
12 Vacuum Pump Seals Clean #13 Condensate Strainer3 Clean S.G.Feedwater Pump Strainers C*lean #12 Condensate Pump Strainers Clean #11 Condensate Pump Strainers Elect.Trip Test from 100%
Clean Condensate Pump Straine rs
APPENDIX D DOCKET NO.
5a-272 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME SALEM NO. 1 DATE 8/9/77 COMPLETED BY J. M. Zupko, Jr.
TELEPHONE 6a9-365-7aaa x5a 7 REPORT MONI'H Jl.llY 1977 METHOD OF TYPE OUTAGE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR NO.
DATE S: SCHEDULED (HOURS)
REASON REDUCING POWER CORRECTIVE ACTJONS/CO:MMENI'S 77-47 7-4-7 F
a.a H
4 lean Condensate ~Pump Straine s 77-49 7-5-7 F
13.7 A
1 enerator Voltag~ Regulator ailure,...4 KV under: voltage tr' p 77-5a 7-6-7 F
a.a H
4 lean #12 Condensate Pump strainers 77-51 7-6-7 F
a.a H
4 lean S.G.Feed Pump Strainers 77-52 7-6-7 F
6.9 A
3 2 S~G.Low Level Trip-12 S.G.Feed Pump Control 77-53 7-7-7 F
a.a H
4 lean Condensate Pump Straine s 77-54 7-8-7 F
112.6 D
2 xcessive R.C.S.Leakage -
Valve 1 CV-75 77-59 7-17-7 F
a.a H
4 lean Condensers 77-6a 7-17-7 s
14.5 B
3 lectrical trip test from laa%
77-65 7-2a-7 F
a.a D
4 Insufficient Bit Tank Boron Concentration 77-68 7-22-7 F
a.a H
4 lean 12 S.G.Feed Pump Strain rs 77-69 7-23-7 F
a.a H
4 lean 13 Condensate Pump Strainer P 4
SUMMARY
- g. -4 8.1-7.R 1
- LOAD REDUCTION.