ML18096A976

Monthly Operating Rept for August 1992 for Salem 1

ML18096A976
Person / Time
Site:	Salem
Issue date:	08/31/1992
From:	Fest J, Shedlock M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9209180356
Download: ML18096A976 (8)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station September 11, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 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 August 1992 are being sent to you.

RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information cc:

• Mr. Thomas T. Martin Regional.Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-l-7.R4

~~eo~ir~y People

.-----9209180356 920831 PDR ADOCK 05000272 R

PDR

~f,I 95-2189 (10M) 12-89

AVERAGE DAILY UNIT POWER LEVEL Docket No.:

50-272 Unit Name:

Salem #1 Date:

09/10/92 Completed by:

Mark Shedlock Telephone:

339-2122 Month August 1992 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 0

17 0

2 0

18 223 3

0 19 389 4

0 20 396 5

0 21 402 6

0 22 399 7

0 23 432 8

0 24 810 i

25 1027 I

9 0

10 0

26 1024 11 0

27 1095 12 0

28 1070 13 0

29 1065 14 0

30 1065 15 0

31 1046 16 46 P. 8.1-7 Rl

I I

OPERATING DATA REPORT Docket No:

50-272 Date:

09/10/92 Completed by:

Mark Shedlock Telephone:

339-2122 Operating status

1.

Un"it Name Salem No. 1 Notes

2.

Reporting Period August 1992

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) 1149

7.

Maximum Dependable Capacity (Net MWe) 1106

8.

If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA

9.

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

N/A

10. Reasons for Restrictions, if any ~~~~~~~N:..:..<-A=--~~~~~~~~~~~

11. Hours in Reporting Period

12. No. of Hrs. Rx. was Critical

13. Reactor Reserve Shutdown Hrs.

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Elec. Energy Generated (MWH)

18. Net Elec. Energy Gen. (MWH)

19. Unit Service Factor

20. Unit Availability Factor

21. Unit Capacity Factor (using MDC Net)

22. Unit Capacity Factor (using DER Net)

23. Unit Forced outage Rate This Month 744 496.5 0

346.3 0

882379.2 267080 238465 46.5 46.5 29.0 28.7 53.5 Year to Date 5855 2752.7 0

2464.0 0

8085499.2 2683320 2537599 42.1 42.1 39.2 38.9 35.0 Cumulative 133008 86353.0 0

83512.0 0

263582644.4 87487950 83314172 62.8 62.8 56.6 56.2 21.8

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

None

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

NA 8-1-7.R2

NO.

DATE 0017 08/01/92 0018 08/17/92 0019 08/17/92 0020 08/18/92 0021 08/19/92 0022 08/24/92 1

2 F:

Forced S:

Scheduled TYPE1 DURATION REASON2 (HOURS)

F 377.3 F

20.5 F

19.5 F

11.3 F

108.0 F

6.2 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refuel ing D-Requlatory Restriction B

B B

B B

B UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH AUGUST 1992 METHOD OF SHUTTING DOWN REACTOR 4

4 5

5 5

5 LICENSE EVENT REPORT #

3 Method:

1-Manual 2-Manual Scram SYSTzM CODE CH cc HB HB CH HB E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)

H-Other (Explain)

DOCKET NO.:

~5~0..,.-=27~2..,,..,.. __ _

UNIT NAME:

Salem #1 DATE:

09/10/92 COMPLETED BY:

Mark Shedlock TELEPHONE:

339-2122 COMPgNENT CAUSE AND CORRECTIVE ACTION CODE TO PREVENT RECURRENCE PIPEXX STEAM GEN. PIPING TURBIN UNIT PERFORMANCE TESTING INSTRU TURBINE CONTROL VALVES INSTRU TURBINE CONTROL VALVES INSTRU STEAM GEN. FEEDPUMP CONTROLS INSTRU TURBINE CONTROL VALVES 4

5 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161)

Exhibit 1 - Same Source

SAFETY RELATED MAINTENANCE MONTH: -

~UGUST 1992 DOCKET NO:

UNIT NAME:

50-272 SALEM 1 WO NO UNIT DATE:

COMPLETED BY:

TELEPHONE:

SEPTEMBER 10, 1992 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION 881028096 1

,J 910409164 1

910409189 1

911016165 1

920318208 1

920318213 1

920318228 1

920428066 1

920429165 1

920513123 1

920827093 1

VALVE 1S27C FAILURE DESCRIPTION:

PIPE SUPPORT STUDS MISSING -

REPLACE 12 REACTOR COOLANT PUMP FAILURE DESCRIPTION:

1. 3 SEAL LEAKING -

DISASSEMBLE AND INSPECT OR REPLACE 11 REACTOR COOLANT PUMP FAILURE DESCRIPTION:

1. 3 SEAL LEAKING -

DISASSEMBLE AND INSPECT OR REPLACE 13 REACTOR COOLANT PUMP FAILURE DESCRIPTION:

1. 3 SEAL LEAKING -

DISASSEMBLE AND INSPECT OR REPLACE 1 NIS CHANNEL B FAILURE DESCRIPTION:

LOOSE CONNECTORS -

INVESTIGATE 1 NIS CHANNEL C FAILURE DESCRIPTION:

LOOSE CONNECTORS -

INVESTIGATE 1 NIS CHANNEL D FAILURE DESCRIPTION:

LOOSE CONNECTORS -

INVESTIGATE 11 RHR PUMP FAILURE DESCRIPTION:

MECHANICAL SEAL LEAKING -

REPLACE VALVE 1SJ243 FAILURE DESCRIPTION:

VALVE STEM BROKEN -

REPLACE VALVE VALVE 12CS59 FAILURE DESCRIPTION:

VALVE LEAKS THROUGH -

REPLACE VALVE 12 STEAM GENERATOR FAILURE DESCRIPTION:

LEVEL FOUR READS LOW -

TROUBLESHOOT

l-OCFR50. 59 EVALUATIONS MONTH: -

~UGUST 1992 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-272 SALEM 1 SEPTEMBER 10, 1992 J. FEST (609)339-2904 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.

The Station Operations Review Committee has reviewed and concurs with these evaluations.

ITEM

SUMMARY

A.

Procedures and Revisions NC.NA-AP.ZZ-0004(Q)

B.

SAR Change Notice (SCN)

SCN# 92-050 "Station Operations Review Committee", Rev. 3 -

The purpose of this change is to incorporate the changes approved by the NRC in Tech Spec Amendment 52 (Hope Creek), 133 (Salem 1), and 112 (Salem 2).

Other changes have been made to simplify, clarify, and improve the flow of the process/procedure.

These changes are all in accordance with the revised Technical Specifications, therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 92-094)

"SORC Review of Procedures" - This change brings the FSAR into accordance with the Technical Specifications by removing from the FSAR the SORC review requirements for 2 categories of procedures for which SORC review is not required by the Technical Specifications.

The procedures involved are still required to receive a 10CFR50.59 applicability review.

In the event a 10CFR50.59 evaluation is required, the procedures would still require SORC review.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 92-092)

SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 1 AUGUST 1992 The Unit began the period shutdown.

On August 16, 1992, following completion of startup activities, the Unit was synchronized.

Following an eight hour soak, the Unit was removed from service to perform the main turbine overspeed test.

The Unit was again synchronized on August 17, 1992, and a power escalation commenced.

From August 18 -

23, 1992, power was held at 47% for reactor physics testing.

On August 25, 1992, at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />, power was increased to 100%.

With the exception of minor load reductions to correct problems with rod position indication, 14 steam Generator Feedwater Pump governor, and 11 Heater Drain Pump, the Unit continued to operate at full power throughout the remainder of the period.

REFUELING INFORMATION MONTH:

-_~UGUST 1992 MONTH AUGUST 1992 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

1.

Refueling information has changed from last month:

YES NO X

2.

Scheduled date for next refueling:

OCTOBER 2, 1993 50-272 SALEM 1 SEPTEMBER 10, 1992 J. FEST (609)339-2904

3.

Scheduled date for restart following refueling:

DECEMBER 13, 1993

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?:

5.

Scheduled date(s) for submitting proposed licensing action:

N/A

6.

Important licensing considerations associated with refueling:

7.

Number of Fuel Assemblies:

a.

Incore 193

b.

In Spent Fuel Storage 656

8.

Present licensed spent fuel storage capacity:

1170 Future spent fuel storage capacity:

1170

9.

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

September 2001 8-1-7.R4