ML19030A362

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

ML19030A362
Person / Time
Site:	Salem
Issue date:	04/06/1977
From:	Heller H Public Service Electric & Gas Co
To:	NRC/IE, Office of Nuclear Reactor Regulation
References
Download: ML19030A362 (4)

Text

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Public S_ervice Electric and Gas Company Salem Nuclear Generating Station P.O. Box #168 Hancocks Bridge, New 7J.ersek°EGDU\\TORY DOCKET' fllE COP{J Director Off ice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 MONTHLY OPERATING REPORT SALEM GENERATING STATION April In compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, the following Monthly Operating Reports for the month of March, 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 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 and Program Control US Nuclear Regulatory Commission Washington, D.C.

20555 (1 Copy)

(2 Copies)

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Pg. 1-4 8-1-7. Rl The Energy People H. J. Heller Manager -

Salem Generating Station I o ~ fJdd e; 7

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95-2189 (SM) 10-72

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• March, 1977 APPENDIX B AVERAGE DAILY UNIT POWER LEVEL OOCKET NO.

50-272 UNIT' Salem #1 DATE April 5, 1977 CQ.\\1PLETED BY J.M. Zupko, Jr.

TELEPHONE 609-365-7000 X507 UA..Y AVERAGE DAILY POWER LEVEL 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)*

0 0

0 0

0 0

0 0

21 315 474 537 570 824 821 103 (MWE-NET) 17 347 18 324 19 390 20 304 21 679 22 540 23 636 24 827 25 832 26 834 27 538 28 870 29 837 30 67 0

31

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~-1-7.Rf APPENDIX C t-*

OPERAUNG DATA P.EFO~

NO 50-272 tJNIT Salem #1 April 5, 1977 J.M. Zupko, Jr

• OPERATING ST.AlUS rm.EFfIDNE*609-365-7000 X507

l. REPORTING PERIOD:_M_.a...,.r_..c.-..h ___

GroSS HOURS IN REPORTING PERIOD: __

7_4...,.4~~----

'lb Be

2.

CURRENll.Y AtrrrlOIUZED FOWER LEVEL (MWt) :3338 MAX.DEPEND.CAPACITY(MWe-NET): Determined DFSIGN EL..-emICAL PJJING(MNe-Net): 1090

3.

PCWER LEVEL TO WHICli RESTRICTED (IF kW) i)Me-Net) : _

_.N_..o....,ne...._ ____ _

4.

REAS-ONS FOR RESI'RICTION (IF Rrl) :.

5. D1BER OF a:JURS REACTOR WAS CRITICAL * * *

• THIS ~"IH YR TO DATE

• 497.4 0.0 1524

6.

REACTOR RESERVE SHUIDJWN HOURS * -* * *.. *----

• 7.

HOURS GENERATOR ON LINE * * *

• S.

UNIT RESERVE SHCITIXJi'u'l' HCURS * * * * * * * *

9.

GROSS THERMAL FNERG'l GENERATED (}fi';H) * * *

• 470.3 0.0 1254.9 0.0 CtMJLATIVE 1825.6 0.0 1295.2 0.0 1904895

10.

GROSS ELECTRICAL ENERGY GENERATED (M!IH) * *

• 951900 311840 1856198 550960 554190 11'.

NET ELECTRICAL ENERGY GENERATED(.M~H). * *

• 300990 462490 490865

12.

REAC!OR SERVICE F.d!:.TOR * * * * * * * * *

• N/A N/A N/A

13.

REACTOR AVAII.ABILin" FACTOR

• N/A N/A N/A N/A N/A

14.

UNIT SERVICE F.A.CTOR * * * * *

• N/A lS.

UNIT AV.A.Ir;.BILITY FACTOR * * * * * * *

• N/A N/A N/A N/A N/A

16.

UNIT CJ\\F.d!:.ITY FACI'OR(Using MOC). * * * * * *---- ----

N/A

17.

UNIT CAPACIT'l FACTOR(Using Design MWe)

• N/A N/A N/A N/A N/A

18.

UNIT FORCED cur.~ RATE * * * * * * *,, * ----

N/A

19.

SHIJTIXJWNS SCllEDULED OVER NEcr 6 MJNIHS(TYPE,DA.i.""E,.AND DURATJ;ON OF EAGl):

9-12-77 Modification of IDw Pressure Turbine Blading, Eight Weeks.

ZO.

IF SHUT W'IN AT END OF ?.EPOR'.I' PERIOD, ESI'IMATEJ DATE OF SI'.~:

4-3-77 Zl.

UNITS -IN TES!" sr...mJS (PRIOR TO CCMERCI.~ OPERATION) :

FOP.ECA.ST INITIAL CRITIC.!.LITI 9-30-76 INITIAL ELECTRICITY ca.t.1ERCIAL OPERATION 11-01-76 12-20-76

-AC-IIEVED 12-11-76 12-25-76

APPENDIX D UNIT SHUTDOWNS.AND POWER REDUCTIONS DOCKET NO, 50-272

.l UNIT NAME Salem #1 r

DATE April 4, 1977

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I"-

COMPLETED BY J. M. Zupko, Jr.

TELEPHONE 609-365-7000 Ext. 507 REPORT MONTH MARCH, 19 7 7 METHOD OF TYPE OUTAGE SHUTTING DOWN F: FORCED DURATION TIIE REACTOR OR NO.

DATE S: SCHEDULED (HOURS)

REASON REDUCING POWER CORRECTIVE ACTIONS/COMMENTS 77-19 770224 s

202.1 B

3 Rod Drop Test 77-20 7.70 309 F

3.5 H

3 11 and 12 Stm.Gen.Feed Pump Trip.

77-21 '.770316 F

24.8 G

2 Inadvertant RCS Boration 77-22 770318 F

8.4 H

3 13 and 14 Reactor Coolant Pump Trip.

• 77-23 770321 F

0 D

4 Quadrant Power Tilt

• 77--24 770324 F

0 B

4 Condensate Pump Strainers

• 77-25 77.0329 s

0 B

4 50% Load Rejection Test 77-26 770331 F

34~9 A

3 13/14 Main Stm. Stop Valve Closure.

I P

SUMMARY

g.4-4 8.1-7.R 1

• Load Reduction.