ML18096A392

Monthly Operating Rept for Nov 1991 for Salem Unit 1.W/

ML18096A392
Person / Time
Site:	Salem
Issue date:	11/30/1991
From:	Fest J, Polizzi V, Shedlock M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9112200231
Download: ML18096A392 (9)

Text

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CPS~G*

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station December 13, 1991 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 November 1991 are being sent to you.

RH:pc cc:

Mr. Thomas T. Martin 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, v(;Jt?o-LJ~

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G.fhe~al Manager -

Salem Operations Regional Region I 631 Park King of Administrator USNRC Enclosures Avenue Prussia, PA 8-1-7.R4 2_0 Q.£~fl

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95-2189 (10M) 12-89

AVERAGE DAILY UNIT POWER LEVEL Completed by:

Mark Shedlock Month November 1991 Day Average Daily Power Level (MWe-NET) 1 1114 2

1116 3

1115 4

1105 5

1117 6

1111 7

1082 8

1082 9

1075 10 1118 11 1128 12 1110 13 1112 14 1089 15 512 16 203 P. 8.1-7 Rl Day Docket No.:

50-272 Unit Name:

Salem #1 Date:

12/10/91 Telephone:

339-2122 Average Daily Power Level (MWe-NET) 17 391 18 1097 19 1097 20 1119 21 1121 22 1121 23 1119 24 1114 25 1124 26 1120 27 1120 28 1086 29 1081 30 1108 31

OPERATING DATA REPORT Docket No:

Date:

Completed by:

Mark Shedlock Telephone:

Operating Status

1.

Unit Name Salem No. 1 Notes

2.

Reporting Period November 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)

Report, Give Reason NA

9.

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

10. Reasons for Restrictions, if any

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 NA This Month Year to Date 720 8016 720 5892.8 0

0 720 5736.4 0

0 2306186.4 18918100.8 775870 6276020 744178 5989130 100

71. 6 100

71. 6 93.5 67.6 92.7 67.0 0

4.7 50-272 12/10/91 339-2122 since Last N/A cumulative 126409 82856.3 0

80303.9 0

252980486.0 83988660 79957802 63.5 63.5 57.2 56.7

21. 5

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

Refueling Outage scheduled to start 4-4-92 and last 67 days.

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

NA 8-1-7.R2

NO.

DATE 0075 11/08/91 0067 11/15/91 0064 11/15/91 0065 11/15/91 1

F:

Forced S: Scheduled DURATION TYPE 1 (HOURS)

REASON 2 F

10.1 F

.7 F

48.2 F

3.9 2

Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction H

A A

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

5 5

5 3

LICENSE EVENT REPORT #

Method:

1-Manual 2-Manual Scram SYSTEM CODE4 EB IB IB WA 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)

COMPONENT CODE 5 TRAN SF INSTRU INSTRU DOCKET NO.: _.5._,0'--=27'-':2,..,...._ __ _

UNIT NAME:

Salem #1 DATE:

12/10/91 COMPLETED BY:

Mark ~hedlock TELEPHONE:

339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE SOLAR MAGNETIC DISTURBANCES 1B SAFEGUARDS EQUIPMENT CAB.

1B SAFEGUARDS EQUIPMENT CAB.

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PIPEXX SERVICE WATER PIPE LEAK 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: -

NOVEMBER 1991 DOCKET NO:

50-272 UNIT NAME:

SALEM 1 WO NO UNIT 910107094 1

910725101 1

910903133 1

911002162 1

911031093 1

911111141 1

911115161 1

911115168 1

911117125 1

91112219 1

911127069 1

VALVE 11SW15 DATE:

DECEMBER 10, 1991 COMPLETED BY:

J. FEST TELEPHONE:

(609)339-2904 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:

11SW15 LEAKS THROUGH -INVESTIGATE 12 BORIC ACID PUMP FAILURE DESCRIPTION:

12 BAT PUMP MECHANICAL SEAL LEAKING -

REPAIR VALVE 12SW380 FAILURE DESCRIPTION:

12SW380 -

LEAK IN PIPE DOWNSTREAM OF VALVE -

REPAIR FIRE DAMPER 1ABF13 FAILURE DESCRIPTION:

FIRE WRAP SEPARATED -

REWORK RCS SAMPLE VALVE 1SS104 FAILURE DESCRIPTION:

VALVE 1SS104 NOT MAKING OPEN LIMIT -

INVESTIGATE VALVE 12SW25 FAILURE DESCRIPTION:

12SW25 -

UPSTREAM PIPING/ELBOW LEAKS -

REPLACE VALVE 12SW8 FAILURE DESCRIPTION:

12SW8 -

LEAK IN PIPE UPSTREAM OF VALVE -

REPLACE VALVE 12SW6 FAILURE DESCRIPTION:

12SW6 -

LEAK IN PIPE UPSTREAM OF VALVE -

REPLACE VALVE 12SW8 FAILURE DESCRIPTION:

12SW8 WILL NOT OPEN -

INVESTIGATE VALVE 1FP284 FAILURE DESCRIPTION:

1FP284 INOPERABLE -

REPAIR 12 SAFETY INJECTION PUMP FAILURE DESCRIPTION:

21 SI PUMP TRIPPED -

INVESTIGATE

10CFR50.59 EVALUATIONS MONTH: -*NOVEMBER 1991 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-272 SALEM 1 DECEMBER 10, 1991 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 (Proc)

NC.NA-AP.ZZ-0055(Q)

SC.SA-AP.ZZ-0012(Q)

II-3.3.6 Rev. 12 "Outage Management Program" -

Rev. 0 of this procedure is to provide guidelines for forced and scheduled outage activities.

This procedure also provides guidelines for developing and reviewing outage goals and for reviewing the outage process via post-outage critiques.

The implementation of this procedure in conjunction with other Nuclear Department Administrative Procedures provides the necessary controls to ensure that outage activities are performed safely and in compliance with licensing requirements and suggested industry guidelines for outage management.

(SORC 91-111)

"Technical Specification Surveillance Program" -

This limited revision to Attachments 1& 2 of the procedure is being made to identify the Nuclear Licensing & Regulation will monitor the posting of "procedures and related materials" as identified in Amendment 129/108 (Appendix "B" Section 4.2.1 -

Monitoring of Endangered Turtles and Fish) to the Unit 1 and 2 Technical Specifications.

The new surveillance task was generated to ensure compliance with Environmental Technical Specification requirements.

These requirements are designed to enhance the probability of success of efforts to preserve various forms of endangered marine life.

These efforts are completely independent of and have no impact on plant operation.

(SORC 91-114}

"Boron Concentration Control" - This revision allows the Demineralized Water Transfer System to be used as a source of water for boron concentration control.

The current procedure allows only the use of the Primary Water Storage Tank water to perform this evolution.

10CFR50.59 EVALUATIONS MONTH:

~ NOVEMBER 1991 (Cont'd)

ITEM C. SAR Changes SAR Change 91-48 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-272 SALEM 1 DECEMBER 10, 1991 J. FEST (609)339-2904 Since this change does not decrease the quality of water entering the RCS or alter or impact the operation of any safety related equipment, the change will not increase the possibility of an accident of a different type than any previously evaluated in the SAR.

Also, this change will not increase the probability of occurrence or the consequences of any accidents previously evaluated in the SAR.

( SORC 91-119)

"Section 5.5.1.3.4, Bearing Integrity~ Page

5. 5-6" -

Section 5. 5. 1. 3. 4, page 5. 5-6 of the Salem Updated Final Safety Analysis Report (UFSAR) requires shutting down a Reactor Coolant Pump (RCP) when a low oil level alarm in the lube oil reservoirs alarm in the Control Room.

Since the alarm alone is not indicative of a degraded pump, current operating procedures require monitoring the RCP motor bearing temperatures and motor vibrations in conjunction with the high/low lube oil alarm.

This represents true indication of a degraded pump motor.

If RCP temperatures or motor vibrations are less than predetermined safe levels, the RCP motor bearing temperatures, motor winding temperatures, and both RCP shaft and flange vibrations are monitored every hour while the oil level alarm exists.

An investigation is made as to the cause of the alarm when a containment entry can be made.

If the alarm is accompanied by either higher: 1) motor bearing high temperature, or 2) motor flange vibration, or 3) shaft vibration, or 4) rapid increase in vibration or temperature, then corrective action is taken to trip the associated pump in accordance with operating procedures.

These predetermined limits are conservatively bound in that they are lower than the Westinghouse trip setpoints.

(SORC 91-119)

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SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 1 NOVEMBER 1991 The Unit began the period operating at full power and continued to operate at full power until November 8, 1991, when load was reduced to 78% due to a Solar Magnetic Disturbance.

The Unit was restored to 100% power on November 9, 1991, and continued to operate at essentially full power until November 15, 1991, when load was reduced due to a failure of the "B" Safeguards Equipment Cabinet (SEC).

The SEC chassis was replaced and the Unit returned to 100% power on November 18, 1991.

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

µ R~FUELING INFORMATION MONTH: -

NOVEMBER 1991 MONTH NOVEMBER 1991 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:

APRIL 4, 1992 50-272 SALEM 1 DECEMBER 10, 1991 J. FEST (609)339-2904

3.

Scheduled date for restart following refueling:

JUNE 9, 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?:

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 588

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