ML18093A734

Monthly Operating Rept for Feb 1988

ML18093A734
Person / Time
Site:	Salem
Issue date:	02/29/1988
From:	Ronafalvy J, White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8803210452
Download: ML18093A734 (14)

Text

AVERAGE DAILY UNIT POWER LEVEL Completed by Pell White Month FEBRUARY 1988 Day Average Daily Power Level (MWe-NET) 1 0

2 0

3 0

4 0

5 0

6 0

7 0

8 0

9 0

10 0

11 0

12 0

13 0

14 0

15 0

16 0

P. 8.1-7 Rl

.. 88(>::.:::21 ()~*!22 :38(>22~? ------- '\\

PDR ADUCK 0~0<1<">?7~

R DCD Day 17 18 19 20 21 22 23 24 25 26 27 28 29 Docket No.

Unit Name Date Telephone Extension Average Daily (MWe-NET) 0 0

0 0

0 0

0 0

0 0

63 369 801 50- 27 2 Salem # 1 March 10, 1988 609-935-6000 4451 Power Level

e CPERATING DATA REPORT Completed by Pell White Operating Status Docket No.50-272

~,-----.---.~--=-~~-

Date:

March 10,1988 Telephone: 935-6000 Extension:

~4~4~5~1,..-~~,---~~,---

1.

Unit Name Salem No. 1 Notes

2.

Reporting Period February 1988

3.

Licensed Thermal Power (MWt) 3411

4.

Nameplate Rating (Gross MWe) 1170

5.

Design Electrical Rating (Net MWe) 1115

6.

Maximum Dependable Capacity(Gross MWe)ll49

7.

Maximum Dependable Capacity (Net MWe) 1106

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)

NA

~~~~~~~~~~~~

10. Reasons for Restrictions, if any N/A

,---__..;_~~~~~~~~,---~~~~~~~~~~

This Month Year to Date Cumulative

11. Hours in Reporting Period 696 1440 93529

12. No. of Hrs. Reactor was Critical 141. 2 141. 2 57836.3

13. Reactor Reserve Shutdown Hrs.

0 0

0

14. Hours Generator On-Line 63.7 63.7 55855.5

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 117089 117089 172386098

17. Gross Elec. Energy Generated (MWH) 32410 32410 57226900

18. Net Elec. Energy Generated (MWH) 16845 8187 54404396

19. Unit Service Factor 9.2 4.4 59.7

20. Unit Availability Factor 9.2 4.4 59.7

21. Unit Capacity Factor (using MDC Net) 2.2

0. 51 52.6

22. Unit Capacity Factor (using DER Net) 2.2 0.51 52.2 2 3. Unit Forced Outage Rate

21. 8

21. 8 24.2

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

N/A

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

N/A 8-1-7.R2

Completed by No.

Date 0001 1-8-88 0002 2-24-88 0003 2-26-88 0004 2-27-88 1

F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1988 Docket No.50-272 Uni:t Name Date Telephone Extension Salem No.l Pell White Method of Duration Shutting License Type Hours Reason Down Event 1

2 Reactor Report s

1131.5 B

9 s

54.5 B

9 F

12. 2 A

1 F

5. 6 A

1 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Exam F -Adm in i s t r a t iv e G-Operational Error-explain H-Other-explain System Component Code 4 Code 5 CA CRDRVE CA CRDRVE HA INSTRU HA INSTRU 3 Method 1-Manual 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther March 10,1988 609-935-6000 44 51 Cause and Corrective Action to Prevent Recurrence CONTROL ROD DRIVE MECHANISM LEAK CONTROL ROD MAGNETIC JACK DRIVE REPLACEMENT e

MAIN TURBINE EH CONTROL PROBLEM MAIN TURBINE EH CONTROL PROBLEM 4 Exhibit G Instructions for Prep a r a-t ion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit 1 Salem as Sou re e

WO NO 870127032 870226030 870716080 870807119 870905048 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1

13MS 10 D63 FAILURE DESCRIPTION:

VALVE LEAKS THRU PLEASE DISASSEMBLE AND INSPECT.

1 1DAE09 6 FAILURE DESCRIPTION:

lC DIESEL L.O. HEATER PIPING IS LEAKING AT PIPING ELBOW.

1 BA EVAPORATOR HEAD FAILURE DESCRIPTION:

BORIC ACID EVAPORATOR HEAD SHOWS SIGNS OF LEAKAGE.

REPLACE GASKETS.

1 12SW38 FAILURE DESCRIPTION:

RADIOGRAPHY REVEALED VALVE PARTIALLY OPEN, INSPECT FOR ABNORMAL CONDITIONS.

1 1MS92 4 FAILURE DESCRIPTION:

MS LEAK IN LINE UP STREAM OF 1MS924 UNDER INSULATION.

WO NO 870910051 870925103 871006112 871130127 871201497 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1

1SJ133 FAILURE DESCRIPTION:

REPLACE VALVE AS PER CDP # lSM-00391.

1 11GB91 7 FAILURE DESCRIPTION:

D3 LEAKS THRU.

REPLACE VALVE.

1 llMSlO FAILURE DESCRIPTION:

TROUBLESHOOT llMSlO CYCLING IN AUTO AND MANUAL.

1 13SJ313 FAILURE DESCRIPTION:

VALVE 13SJ113 LEAKS THROUGH, REWORK PER DISPOSITION FA-127.

1 12CS38 FAILURE DESCRIPTION:

12CS38, REPLACE BONNET GASKET AND 0-RINGS, MARK NO. M-61.

-I

WO NO 880104113 880106150 880115197 880127062 880129095 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1

1SJ151 FAILURE DESCRIPTION:

1SJ151 IS LEAKING PAST ITS SEATS.

REPLACE MARK NUMBER FA-27.

1 1PT544 FAILURE DESCRIPTION:

1PT544 #14 STEAM GENERATOR STEAM PRESSURE CHANNEL I CONSOLE FAILED LOW.

TROUBLESHOOT.

1 12 SGFP FAILURE DESCRIPTION:

TURNING GEAR WILL NOT STAY ENGAGED, INVESTIGATE AND REPAIR.

1 14 CFCU FAILURE DESCRIPTION:

14 CFCU SERVICE WATER FLOW HIGH, INVESTIGATE AND REPAIR.

1 1SJ13 FAILURE DESCRIPTION:

1SJ13 LEAKS BY ITS SEATS.

PERFORM VALVE DISK MODIFICATION AS PER MDCR-lSM-580.

WO NO 871203117 871219149 871223136 880103039 870104101 UNIT EQUIPMENT IDENTIFICATION 1

1 EXCESS LETDOWN HEAT EXCHANGER SALEM UNIT 1 FAILURE DESCRIPTION:

1 EXCESS LETDOWN HEAT EXCHANGER LEAKS AT HEAD AREA, REPAIR.

1 lA D/G FAILURE DESCRIPTION:

lA D/G ERRATIC INDICATIONS (SYNCHRO, SPEED, FREQ)

WERE OSCILLATING, TROUBLESHOOT.

1 SJ122 FAILURE DESCRIPTION:

1SJ122 IS LEAKING PAST ITS SEATS.

REPLACE MARK NUMBER FA-27.

1 1MSE4 FAILURE DESCRIPTION:

INVESTIGATE AND REPAIR INBOARD BEARING OIL LEAK.

1 1SJ22 7 FAILURE DESCRIPTION:

1SJ227 IS LEAKING PAST ITS SEATS.

REPLACE MARK NUMBER FA-27.

J

WO NO 880201190 880201204 880204039 880209139 880211120 880211122 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1

100 AIR LOCK FAILURE DESCRIPTION:

100 AIRK LOCK, REPAIR EXTERIOR CONTAINMENT DOOR EQUALIZING VALVE.

1 lRCEI SPARE CRDM FAILURE DESCRIPTION:

lRCEI SPARE CRDM NO. E-1, CANOPY REPAIR.

1 lC S.E.C.

FAILURE DESCRIPTON:

lC ?.E.C. RECEIVED AUTO TEST FAULT #18, TROUBLESHOOT.

1 1N31 FAILURE DESCRIPTION:

1N31 READING ERRATIC BOTH ON BEZEL AND INSTRUMENT RACK.

1 lA D/G DAY TANK FAILURE DESCRIPTON:

lA D/G DAY TANK SUPPORT NOT WELDED.

WELD 1

lB D/G DAY TANK FAILURE DESCRIPTION:

lB D/G DAY TANK SUPPORT NOT WELDED.

WELD

880211123 880215206 880215208 880215209 880215211 880225047 SALEM UNIT 1 1

lC D/G DAY TANK FAILURE DESCRIPTION:, lC D/G DAY TANK SUPPORT NOT WELDED.

WELD 1

11SJ14 3 FAILURE DESCRIPTION:

11SJ143 STUCK OPEN, X-RAY INTERNALS, MARK # FA-60 VALVE.

1 12SJ14 3 FAILURE DESCRIPTION:

12SJ143 STUCK OPEN, X-RAY INTERNALS, MARK # FA-60 VALVE.

1 13SJ143 FAILURE DESCRIPTION:

13SJ143 STUCK OPEN, X-RAY INTERNALS, MARK # FA-60 VALVE.

1 14SJ143 FAILURE DESCRIPTION:

14SJ143 STUCK OPEN, X-RAY INTERNALS, MARK # FA-60 VALVE.

1 1N35 FAILURE DESCRIPTION:

1N35 INTERMEDIATE RANGE CHANNEL SPIKING ABOVE P-6 SETPOINT.

TROUBLESHOOT.

J

MAJOR PLANT MODIFICATIONS REPORT MONTH FEBRUARY 1988

• OCR NO.

lEC-13 06 lEC-2016 lSC-0590 PRINCIPAL SYSTEM 4KV Relay Control Circuitry Service Water Intake Structure Fuel Unloading Station

• DCR - Design Change Request DOCKET NO.:

50-272 UNIT NAME:

Salem 1

~~~~~~~~~~-

DATE:

March 10,1988 COMPLETED BY: J. Ronafalvy TELEPHONE:

609/339-4455 SUBJECT This design change installed seismically qualified relays which operate in conjunction with the 28 VDC control circuitry for the vital 4KV

'infeed breakers.

These relays do not affect the operation of the breakers since their function is to eliminate constant alarm during blackout/undervoltage transfer testing.

This design change replaced the Service Water Intake Structure Sump Pumps with pumps which are made specifically for this application.

This design change constructed an oil retention system at the fuel unloading station to control oil spills.

MAJOR PLANT MODIFICATIONS REPORT MONTH FEBRUARY 1988 DOCKET NO.

50-272

--=,--,~~...,,......~~~~~~-

UN IT NAME:

Salem 1

• DCR lEC-1306 lEC-2016 lSC-0590

~~~~~,_-,,.....,,...,,...,,,~~~-

DATE:

March 10,1988 COMPLETED BY:

J. Ronafalvy TELEPHONE:

609/339-4455 SAFETY EVALUATION 10 CFR 50.59 This design change does not affect the operation of the breakers.

The purpose of the seismically qualified relays installed is to eliminate constant alarms during blackout/undervoltage transfer testing.

This modification does not alter any plant process or discharge and did not affect the existing plant impact.

No unreviewed safety or environmental questions are involved.

This design change replaced the SWIS sump pumps and pipe with new improved components.

This modification does not alter any plant process or discharge and did not affect the existing plant impact.

No unreviewed safety or environmental questions are involved.

This design change involved work on a non-safety related system in a non-vital area of the plant.

Proper cable separation was ensured.

This modification does not alter any plant process or discharge and did not affect the existing plant impact.

No unreviewed safety or environmental questions are involved.

DCR -

Design Change Request

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT NO. 1 FEBRUARY 1988 The Unit began the period shutdown with repairs rod drive mechanism (CRDM) columns in progress.

components on the Reactor Head were reassembled System (RCS) hydrostatic test was performed.

to the spare control The remaining and a Reactor Coolant The Unit entered Mode 2 on February 22, 1988, and commenced low power physics testing.

A reactor trip from 4% power occurred on February 24, 1988, due to technician error.

Subsequently, a cooldown to Mode 4 was performed to replace the mag jack assembly for the shutdown bank rod which had been indicating a low resistance to ground.

The coil was replaced and the Reactor reassembled.

The Unit was synchronized on February 27, 1988.

Reactor physics testing was completed at the 47% and 75% power levels.

The Unit finished the period, with power maintained at 80%, to evaluate a primary to secondary tube leak in No. 13 Steam Generator.

HEFUELING INFORMATION DOCKET NO.:

50-272 COMPLETED BY:

J. Ronafalvy UNIT NAME:

Salem 1 DATE:

March 10,1988 TELEPHONE:

609/935-6000 EXTENSION:

4497 Month FEBRUARY 1988

1.

Refueling information has changed from last month:

YES X

NO -----

2.

Scheduled date for next refueling:

April 15, 1989

3.

Scheduled date for restart following refueling: May 30, 1989

4.

A)

Will Technical Specification changes or other license amendments be required?

YES NO ---

NOT DETERMINED TO DATE X

B)

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

YES NO X

If no, when is it scheduled?

February 1989

5.

Scheduled date(s) for submitting proposed licensing action:

February if required

6.

Important licensing considerations associated with refueling:

7.

8.

9.

NONE Number of Fuel Assemblies:

A)

Inc ore B)

In Spent Fuel Storage Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

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

8-l-7.R4 19 3 464 11 70 1170 September 2001

e O~S~G Publi~ Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 Mar ch 11, 19 8 8 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of February 1988 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Sincerely yours,

~µQ.

J. M. Zupko, Jr.

General Manager -

Salem Operations RH:sl cc:

Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-1-7.R4 The Energy People 95-2189 (11M)12-84