ML20138J800

Monthly Operating Rept for Nov 1985

ML20138J800
Person / Time
Site:	Salem
Issue date:	11/30/1985
From:	White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8512180048
Download: ML20138J800 (10)

Text

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l AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-272 Unit Name Salem # 1 Date December 10,1985 Completed by Pell White Telephone 609-935-6000 Exte nsion 4455 Month-November 1985 Day Average Daily Power Level

. Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1-1089-17 1078 2

1089 18 1091 3

-1089 19 1084 4

1085 20 1063 5

1065 21 1094 6

1099 ___

22 1082 7

1089 23 1090 8

1096 24 1082 9

1078 25 1086 10 1087 26 1067 11-1081 27 1099 12 1088 28 1084 13 1070 29 1100 14 1078 30 1074 15 1070-31 16 1092 P. 8.1-7 R1 pg=TenST*4" R

T.E1Y

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OPERATING DATA REPORT Docket No.50-272 Date December 10, 1985 Telephone 935-6000 Completed by Pell White Extension 4455 Operating Status 1.

. Unit Name Salem No. 1 Notes 2.

Reporting Period November 1985 3.

Licensed Thermal Power (MWt) 3338 4.-

Nameplate Rating (Gross MWe) 1170 5.

Design Electrical Rating (Net MWe)

T6F6 6.

Mcximum Dependable Capacity (Gross MWe)1124 7.

Maximum Dependable Capacity (Net MWe) 1079 8.

If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A 9.

Power Level to Which Restricted, if any (Net MWe)

N/A

10. Reasons for Restrictions, if any N/A This Month Year to Date-Cumulative

11. Hours in Reporting Period 720 8016 73825

12. No. of Hrs. Reactor was Critical 720 7617.9 43441.4

13. Reactor Reserve Shutdown Hrs.

0 0

3088.4

14. Hours Generator On-Line 720 7602.2 41760.8

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2407063 25247970 128015967

17. Gross Elec. Energy Generated (bnRI) 811850 8551970 42468020

18. Net Elec. Energy Generatdd (MWH) 780456 8211595 40309577 L

19. Unit Service Factor 100 94.8 56.6

20. Unit Availability Factor 100 94.8 56.6

21. Unit Capacity Factor (using MDC Net) 100.5 94.9 50.6

22. Unit Capacity Factor (using DER Net) 99.4 94.0 50.1

23. Unit Forced Outage Rate.

0.0 0.6

-29.0

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refue'.ng,-March 22, 1986, approximately 60 days

25. If shutdown at end of Report' Period, Estimated Date of Startup:.

N/A

(

26.LUnits in Test Status (Prior to Commercial Operatiori :

Fordcast Acf..leved Initial Criticality '

9/30/76

~I2311/76 Initial Electricity 11/1/76 12/25/76 Commercial-Operation 12/20/76 6/30/77 8-1-7.R2 Page of.

m.

UNIT SHUTDOWN. AND POWF.R REDUCTIONS Dockat No.50-272 REPORT-MONTH Nm*wmber 1985 Unit Name Selm,t No.1 Date December 10,1985 l

-Completed by Pell White' Telephone 609-935-6000 Extension 4455 Method of Duration Shutting License Cause and Corrective No.

Date Type Hours Reason Down Event System Component action to 1

2 Rea cto r Report Code 4 Code 5-Prevent Recurrence There were no ' Outages for the month of November resulting in a load reduction of greater than 20%.

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2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S:. Scheduled B-Maintenance or Test 2-Manual - Scr am.

for Prepara-Source C-Refueling 3-Automatic Scram tion of Data D-Regulatory' Restriction 4-Continuation of Entry Sheets-

.E-Operator Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-Other

'(LER) File H-Other-explain (NUREG 0161) 4 i

T T

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1 MAJOR PLANT MODIFICATIONS DOCKET NO. :

50-272 REPORT MONTH November 1985 UNIT NAME:

Salem 1 DATE:

December 10, 1985 COMPLETED BY:

J.

Ronatalvy TELEPHONE:

609/339-4455

• DC R N O.

PRINCIPLE SYSTEM SUBJECT 1EC-1241 Service Water Provide electric space heating in El.-78' Penetration Area, Service Water Valve Rooms to prevent freezing of header overpressure.

1EC-2112 Spent Fuel Storage Provide vent holes in swollen Racks-Fuel Handling spent fuel storage cells.

System.

I 4

Design Change Request i

I 1

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.. - - ~.. _.,

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-272 REPORT MONTH NOVEMBER 1985 UNIT NAME:

Salem 1 DATE:

December 10, 1985 COMPLETED BY:

J.

Ronafalvy TELEPHONE:

609/339-4455

• DC R NO.

SAFETY EVALUATION 10 CFR 50.59 lEC-1241 The supports to be installed are seismically qualified.

The work does not effect the safe shutdown of the reactor I

and it does not change any plant process or discharge.

No unreviewed safety or environmental questions are involved.

lEC-2112 The fuel cell inner shroud deformation is due to the build-up of off gases in the Boral poison plates.

When water is present in the annulus between the shrouds, there will be corrosion of the aluminum with hydrogen gas as a by-product.

With a buildup of pressure due to the hydrogen gas, the inner shroud will bulge and reduce the inside area of the storage cell.

The possibility of deterioration of the boral in the spent fuel racks due to the water pressure was examined and evaluated in NUREG-0517 Supp. #4.

The evaluation states "This small amount of deterioration would have no effect on neutron shielding, alternation of properties or critically safety.

The hydrogen produced by the corrosion of the aluminum will be released by venting to minimize bulging."

Venting by piercing a hole at the top of the cell will relieve the L

pressure and may allow the inner shroud to return to some position closer to the original. The tools are designed to vent cells with or without a fuel assembly.

If a fuel assembly is located in the cell, the venting process will cause no damage to the fuel assembly.

The hydrogen, produced by the corrosion of aluminum, is radiologically stable since tritium production in stagnated water is extremely low (not detectable).

I

• DCR - Design Change Request i

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l PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8511210610 SMD 1

BORIC ACID TRANSFER PMP FAILURE DESCRIPTION:

THE PUMP IS LEAKING BORATED WATER THRU SEAL.

THIS IS CAUSING A LARGE BORIC ACID BUILDUP AND IS INTERFERING WITH DORIC HEAT TRACE MONITORING.

CORRECTIVE ACTION:

REBUILT PMP & REPLACED SEAL 8511160116 SMD 1

1. 12 BAT PUMP FAILURE DESCRIPTION:

DORIC PT 128 INDICATES 12 BAT PUMP ENCLOSURE 142 DEGREES, TECH SPEC IS 145 DEG. PLEASE VERIFY OPERABILITY OF HEAT TRACE AND ADEQUATE INSULATION.

CORRECTIVE ACTION:

WENT TO #12 BAT AND FOUND PROBE NOT IN PROPER PLACE.

RESET PROBE AND REINSULATED AROUND PUMP.

TEMP ON DORIC CAME UP TO 148 DECREES F.

8511080481 SIC 1

PRT TEMP. INDICATION FAILURE DESCRIPTION:

P.R.T. TEMPERATURE INDICATION ON CONTROL BOARD IS IS FAILED HIGH.

COMPUTER INDICATES TEMP. AT 86 DEG.

PLEASE REPAIR.

CORRECTIVE ACTION:

CHECKED CALIBRATION OF INDICATOR FOUND OUT OF SPEC.

ADJUSTED TO SPEC.

8511070371 SMD 1

PRT RUPTURE DISK FAILURE DESCRIPTION:

NORTH RUPTURE DISK (FIRST ONE AS,ONE COMES UP THE LADDER) IS LEAKING ALL AROUND THE UPPER FLANGE.

CORRECTIVE ACTION:

TIGHTENED UP ON FLANGE STOPPED LEAK.

SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8511020161 SMD 1

NO 14 SERVICE WATER PUMP FAILURE DESCRIPTION:

WHEN PUMP WAS STARTED THE AMP. PEGGED AND THE PUMP IMMEDIATELY TRIPPED, A LARGE FLASH OF LIGHT WAS SEEN BY THE OPERATOR IN THE-BAY AT THE TIME.

THE "N" PHASE 51 RELAY FLAG IS UP AT THE BREAKER.

l l

CORRECTIVE ACTION:

REINSULATED MOTOR LEAD WHICH WAS ~ GROUNDED IN PACKING HEAD ADDED EXTRA RUBBER INSULATION IN PACKING HEAD l

COVER.

l 8510260036 SIC 1

SEAL TANK FAILURE DESCRIPTION:

CANNOT CONTROL THE MOISTURE SEPERATOR LEVEL.

CORRECTIVE ACTION:

FOUND llWG13 STEM STOP NUT SECURING THE VALVE IN THE l

OPEN POSITION.

ADJUSTED STEP NUT TO ALLOW THE VALVE TO CLOSE.

RAN COMPPESSOR LEVEL OPENING l

AND CLOSING TO MAINTAIN LEVEL.

l l

8510260303 SIC 1

LEVEL INDICATION FAILURE DESCRIPTION:

THE LEVEL GAUGE FOR THE CONCENTRATES HOLDING TANK IS BROKEN AND IS INDICATING 30% WITH.THE TANK DRAINED.

j CORRECTIVE ACTION:

BLEWDOWN BUBBLER AND RETURNED TO SERVICE: LEVEL IS NOW INDICATING 0%.

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 NOVEMBER 1985 SALEM NO. 1 The Unit operated at full power for the entire period.

REFUELING INFORMATION DOCKET NO. :

50-272 COMPLETED BY:

J.

Ronafalvy UNIT NAME:

Salem 1 DATE:

December 10, 1985 TELEPHONE:

609/935-6000 EXTENSION:

4455 Month November 1985 1.

Refueling. information has changed from last month:

YES NO X

2.

Scheduled date for next refueling:

March 22, 1986 3.

Scheduled date for restart following refueling:

May 20, 1986 4.

A)

Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO DATE B)

Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES ___

NO X

If no, when is it scheduled?

February 1986 5.

Scheduled date(s) for submitting proposed licensing action:

February 1986 if required 6.

Important licensing considerations associated with refueling:

NONE 7.

Number of Fuel Assemblies:

A)

Incore 193

.B)

In Spent Fuel Storage 296 8.

Present licensed spent fuel storage capacity:

1170 Future spent' fuel storage capacity:

1170 9.

Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:

September 2001 8-1-7.R4

"O PSEG Public Service E!ectric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station December 10, 1985 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission

-Washington, DC 20555

Dear-Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of November 1985 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, ph-J. M.

Zupko, Jr.

General Manager - Salem Operations JR:kcb cc:

Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director,- Office of Management

-Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosures 8-1-7.R4 76 AY The Energy People 2

9s e a uti m o d, i

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