ML19030A366

Submit Monthly Operating Report for the Month of January 1977 for Salem No. 1

ML19030A366
Person / Time
Site:	Salem
Issue date:	02/07/1977
From:	Heller H Public Service Electric & Gas Co
To:	NRC/IE, Office of Nuclear Reactor Regulation
References
Download: ML19030A366 (4)

Text

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v' Reguratory Public Service Electric and Gas Company Salem Nuclear Generating Station P.O. Box #168 Hancocks Bridge, New Jersey 08038 February Director Off ice of Inspection and En -

U.S. Nuclear Regulatory Washington, D.C. 20555 MONTHLY OPERATING REPORT SALEM GENERATING STATION In compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, the following Monthly Operating Reports for the month of January 1977 are being sent to you.

(original plus 10 copies)

Appendix B - Average Daily Unit Power Level Appendix C - Operating 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 (1 Copy)

Director of US NRC Off ice of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, PA 19406

2. Director, Office of Management Information (2 Copies) and Program Control US Nuclear Regulatory Commission Washington, D.C. 20555 I /

~:PJtL H. J. Heller Manager - Salem Generating Station Enc.

Pg. 1-4 8-1-7. Rl The Energy People 95-2189 (SM) 10-72

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-272 UNIT' Salem No.l DATE 2-7-77 COMPLETED BY J.M. ZUPKO JR.

TELEPHONE 609-365-7000 EXT. 507 MONTH January DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) (MWE-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 61 5 0 21 111 6 0 22 23 7 0 23 0 8 38 24 24 9 17 25 173 10 0 26 226 11 0 27 229 12 0 28 147 13 0 29 119 14 0 30 238 15 0 31 220 16 ' 0 Pg. 2-4 8.1-7.RL.

APPF.NDIX C

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.....:i. . . .

OPERA'UNG DAT.A REroirr e OOCKET NJ. 50-272 UNIT Salem No. 1 DATE 2-7-77 CCMPLEIED BY J.M. Zupko Jr.

OPERATING S""...ATUS TELEPHONE* 609-365-7000 Ext.507

l. REPORI'ING PEUOD: January 1976 GROSS HOURS IN RE.PORTING PERIOD:

744 To Be

2. CURRml'I.Y AUIHORIZED FOWER LEVEL (Ml'lt): 3398 MAX.DEPEND.CAPACITY(}Me-NET) :netennined EIGN ELECTRICAL RATING(MWe-Net): 1 og-0--

3. POWER LEVEL TO WHICli RESTRICTED (lF ANY) (}Me-Net) :__N_o_n_e_ _ _ __

4. RF.ASONS FOR P.ESTRICI'ION (IF .ANY) : .

nn:s MJNIH YR TO DATE CUMULATIVE

s. NWBER OF muRS REACTOR WAS CRITICAL

• 481 ..5 481.5 783.1

6. REACTOR RESERVE SHU'I'tOltm HOURS * * * * ... 0.0 0.0 o~o

• 7. HOURS GENERATOR ON LINE * * * * .. * * *

• 256.1 256.1 296.4 UNIT RESERVE SHin'OOWN HOURS * * . . *

• 0.0 0.0 0.0 s.

9. GROSS 'raEmifAL ENERGY GENERATED (MM{) * * *

• 246014 246014 294711

10. GROSS ELECl'RICAL ENERG'f GENERATED~ * *. . 53,290 53,290 56,520

11. NET ELECTRICAL ENERGY GENERATED (Ml'IH) *

• 28 2 375 28,375 28,375

12. BEACl'OR SERVICE FACTOR * * * * * * * * *

• N/A N/A N/A I 13. REACICR AVAILABILITY FACTOR * ... . .* N/A N/A N/A

14. UNIT SERVICE F..4.CTOR * * * * * . . *

• N/A N/A N/A lS. UNIT AVAILABILIT'f FACTOR

• I *** . ** . N/A N/A . N/A

16. UNIT CAPACITY FACI'OR(tJsing MDC). * . . . *

• N/A N/A N/A

17. UNIT CAPN:.rrf FACTOR(tJsing Design MNe) * . . ~L.8. NLA. NIA

18. UNIT FORCED cur.AGE RATE * * * * * * *

• i

• N/A N/A N/A

19. SEUiro.ms SCllEDULED OVER Nm 6 M'JNm.S (T'1PE ,DATE ,AND DURATJ;ON OF EArn) : 4-2-77 Modification of Low Pressure Turbine Blading, Eight Weeks.

ZO.

21.

IF SHU'T OOWN AT END OF ?.EPORI' PERIOD, ESTIMATEJ DATE OF 5r.i\RTUP:

UNITS IN TEST STATIJS(PR.!OR TO CCMwiERCIAL OPERATION): FORECAST

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AC-IIEVED INITIAL CRI'!'ICALIT! 9-30-76 12-11-76 INITIAL EI...EC!RIClTY 11 76 12-25-76 Pg, .3-4 12-20-76 CCM-1ERCI..lJ.. OPERATION 8-1.-7 ~ Rl

APPENDIX D DOCKET NO, 50-272 UNIT SIBJTDOWNS AND POWER REDUCTIONS UNIT NAME Salem No. 1 "* ..

1 l

DATE 2-7-77 COMPLETED BY J.M. Zupko Jr.

TELEPHONE 609-365-7000 Ext. 507 REPORT MONTH January 1977 METHOD OF TYPE SIIDTTING DOWN F: FORCED DURATION TI-IE REACTOR OR NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER CORRECTIVE ACTIONS/COMMENTS 76-4 770101 F 15.1 A 3 12 Stm. Gen. Feedwater Regulating Valve 77-1 770102 F 13.0 H 3 11, 12 Stm. Gen. Feed Pump Trip 77-2 770102 s 16.0 B 3 Test Procedure-Loss of Offsite Pwr 77-3 770103 s 112.0 B 3 Test Procedure-Steam Dump Control 77-4 770108 F 12.2 H 3 11 Stm. Gen. Feed Pump Trip 77-5 770109 F 17.6 B 1 Turbine Intercept Valve Leak 77-6 770110 F 29.5 H 3 12 Stm. Gen. Feed Pwnp Trip 77-7 770111 F 203.7 B 3 11, 12 Stm. Gen. Feed Pump Trip 77-8 770122 F 56.7 H 3 12 Stm. Gen. Feed PLTinp Trip 77-9 770125 F 2.8 H 3 Loss of Generator Excitation~

77-10 770128 F 3.1 H 3 12 Stm. Gen. Flow Calibration -

Procedural Error.

77-11 770128 F 3.2 H 3 Frozen Impulse Pressure Feeler

.Line - Turbine Trip.

77-12 770129 F 3.0 H 3 11, 12 Stm. Gen.Feed PLTinp Trip

SUMMARY

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