ML18096A140

Monthly Operating Rept for June 1991 for Salem Unit 2.W/

ML18096A140
Person / Time
Site:	Salem
Issue date:	06/30/1991
From:	Fest J, Shedlock M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9107190114
Download: ML18096A140 (8)

Text

0 Public Service Electric and Gas Company P.O. Box 236 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. 2 July 15, 1991 0 DOCKET NO. 50-311 0

0 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 June 1991 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 Sincerely yours, rJ/&P4~

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General Manager -

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Salem Operations cc:

Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4

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9107190114 910636.

PDR ADOCK 05000311 R

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'/1 95-2189 ( 1 OM) 12-89

AV~E DAILY UNIT POWER LEVE~

I Docket No.:

50-311 Unit Name:

Salem #2 Date:

7/10/91 Completed by:

Mark Shedlock Telephone:

339-2122 Month June 1991 Day Average Daily Power Level Day Average Daily Power Level

{MWe-NET)

{MWe-NET) 1 1112 17 969 2

1097 18 964 3

1010 19 984 4

1083 20 968 5

1080 21 973 6

1080 22 1039 7

1094 23 1097 8

1066 24 1063 9

1073 25 1073 10 1053 26 1069 11 1075 27 1069 12 1058 28 1089 13 1039 29 1058 14 885 30 1067 15 971 31 16 981 P. 8.1-7 Rl

~PERATING DATA REPORT Docket No:

50-311 Date:

7/10/91 Completed by:

Mark Shedlock Telephone:

339-2122 Operating Status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period June 1991

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 720 720 0

720 0

2410972.8 792681 760747 100 100 95.5 94.8 0

Year to Date Cumulative 4343 85152 4103.6 55459.8 0

0 4079.3 53789.3 0

0 13667834.4 119661303.4 4555524 56287451 4367604 53575415 93.9 63.2 93.9 63.2 90.9 56.9 90.2 56.4 0

22.9

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

Refueling outage scheduled to start 1-4-92 and last 75 days.

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

NA 8-l-7.R2

NO.

DATE 0044 6/12/91 1

2 F:

Forced S:

Scheduled DURATION TYPE 1 (HOURS)

REASON2 F

9.0 Reason A-Equipment Failure (explain)

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

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JUNE 1991 METHOD OF SHUTTING DOWN REACTOR 5

3 LICENSE EVENT REPORT #

Method:

1-Manual 2-Manual Scram SYSTEM CODE4 HH E-Operator Training & License Examination F-Aaninistrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)

H-Other (Explain)

COMPONENT CODE6 DOCKET NO.:

50-311 UNIT NAME:

Salem #2 DATE:

7/10/91 COMPLETED BY:

Mark Shedlock TELEPHONE:

339-2122

• CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE PUMPXX

1. 21 HEATER DRAIN PUMP 4

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 - Same Source

SAFETY RELATED MAINTENANCE MONTH: -

JUNE 1991 DOCKET NO:

UNIT NAME:

50-311 SALEM 2 WO NO UNIT 900905106 2

910507086 2

910522107 2

910614062 2

DATE:

COMPLETED BY:

TELEPHONE:

JULY 10, 1991 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION VALVE 22AF22 FAILURE DESCRIPTION:

VALVE 22AF22 HAS BODY TO BONNET LEAK -

REPLACE VALVE 22 COMPONENT COOLING HEAT EXCHANGER FAILURE DESCRIPTION:

HEAT EXCHANGER FLOW CONTROL CAUSING HEADER PRESSURE SWINGS -

TROUBLESHOOT CONTAINMENT IODINE RADIATION MONITOR 2R12B FAILURE DESCRIPTION:

CONTAINMENT IODINE RADIATION MONITOR 2R12B FAILED -

INVESTIGATE 25 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION:

25 CONTAINMENT FAN COIL UNIT FLOW INDICATION FAILED -

TROUBLESHOOT

10CFR50.59 EVALUATIONS MONTH: -

JUNE 1991

• DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-'-311 SALEM 2 JULY 10, 1991 J. FEST (609)339-2904

--1 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 these evaluations and agrees with their conclusions that these items do not present Unreviewed Safety Questions (USQs).

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ITEM

SUMMARY

A.

Temporary Modification Requests (TMRs)

TMR # 91-031 "BIT Tank Relief Valve 2SJ10" - This modification is to mechanically gag the Boron Injection Tank (BIT) relief valve, 2SJ10.

The modification is needed because 2SJ10 currently leaks by, contributing to Reactor Coolant System (RCS) leakage originating from the CVCS discharge flow path.

The relief valve function is no longer required since the BIT has been removed.

A special test was performed to provide pump discharge pressure data for the design input section of the analysis.

Use of the special test to provide data was actually more conservative than using the existing pump curve data.

In accordance with the Code requirements, the system pressures will not and cannot reach the system design value.

(SORC 91-035)

SALEM UNIT NO. 2 SALEM GENERATING* STATION MONTHLY OPERATING

SUMMARY

UNIT 2 JUNE 1991 The Unit began the period operating at full power and continued operating at essentially full power until June 12, 1991, when load was reduced to 80% to remove 21 Heater Drain Pump from service for leak repairs and as precautionary measure against the solar magnetic disturbances.

Power was returned to 94% (limited by the Heater Drain Pump being out of service) following channel functional tests and continued at that power until June 22, 1991, when the Unit was returned to 100% power.

The Unit continued to operate at full power throughout the remainder of the period.

REFUELING INFORMATION MONTH: -

JUNE 1991 MONTH JUNE 1991 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

1.

Refueling information has changed from last month:

YES NO

~----=-X~~

50-311 SALEM 2 JULY 10, 1991 J. FEST (609)339-2904

2.

Scheduled date for next refueling:

JANUARY 4, 1992

3.

Scheduled date for restart following refueling:

MARCH 15, 1992

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?:

December 1991

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 316

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:

March 2003 8-l-7.R4