ML18095A642

Monthly Operating Rept for Nov 1990 for Salem 1.W/901214 Ltr

ML18095A642
Person / Time
Site:	Salem
Issue date:	11/30/1990
From:	Labruna S, Orticelle A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9012210138
Download: ML18095A642 (11)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department 1.....-;

.. *** December 14, 1990 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 1990 are being sent to you.

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, General Manager -

Salem Operations RH:pc 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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ADOCK 05000272 PDR 95-2168 (1 OOM) 12-84

.,ERAGE DAILY UNIT POWER L~L Docket No.: 50-272 Unit Name: Salem #1 Date: 12/10/90 Completed by: Art Orticelle Telephone: 339-2122 Month November 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1112 17 1095 2 1112 18 1087 3 1080 19 1106 4 1112 20 1116 5 1096 21 1061 6 1114 22 1109 7 1091 23 1102 8 1107 24 1086 9 1046 25 1095 10 505 26 1090 11 487 27 1112 12 493 28 1107 13 577 29 1107 14 592 30 1109 15 596 31 16 747 P. 8.1-7 Rl

OPERATING DATA REPORT e Docket No: 50-272 Date: 12/10/90 Completed by: Art Orticelle Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period November 1990

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 NA This Month Year to Date Cumulative

11. Hours in Reporting Period 720 8016 117649

12. No. of Hrs. Rx. was Critical 720 5310.9 76219.5

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 720 5127.8 73823.5

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2217345.6 16426324.8 231527250.8

17. Gross Elec. Energy Generated (MWH) 733970 5402240 76863600

18. Net Elec. Energy Gen. (MWH) 701944 5141397 73153107

19. Unit Service Factor 100 64.0 62.7

20. Unit Availability Factor 100 64.0 62.7

21. Unit Capacity Factor (using MDC Net) 88.1 58.0 56.2

22. Unit Capacity Factor (using DER Net) 87.4 57.5 55.8

23. Unit Forced Outage Rate 0 36.0 22.7

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

Refueling outage scheduled to start 2/9/91 and last 55 days.

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

NA 8-l-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH NOVEMBER 1990 DOCKET NO.: _5::.;0"---=2"-7=-2~--

UN IT NAME: _s~a:..:l:..;;e""'m'""'#,_.,1;.--

DATE: 12/10/90 COMPLETED BY: Art Orticelle TELEPHONE: 339-2122 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 1 2 NO. DATE TYPE (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 0089' 11/09/90 F 71.4 B 5 ------- CH PUMPXX #11 STEAM GEN. FEED PUMP 0090 11/12/90 F 48.9 B 5 ------- CH PUMP XX #11 STEAM GEN. FEED PUMP 0092 11/14/90 F 37.9 B 5 ------- CH INSTRU #11 STEAM GEN. FEED PUMP e

1 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-.Equipment Failure (explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Requlatory Restriction 4-Continuation of (NUREG-0161)

E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9"0ther H-Other (Explain)

SAFETY RELATED MAINTENANCE DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10,. 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 890412004 1 lA RX TRIP BRKR FAILURE DESCRIPTION: REPLACE UV TRIP DEVICE 900220102 1 11 CHILLER COND. PUMP FAILURE DESCRIPTION: BEARING HOUSING OIL LEAK - REPAIR 900322153 1 13 CHILLER COND. PUMP FAILURE DESCRIPTION: BEARING OIL LEAK - REPAIR 900919104 1 16SW25 FAILURE DESCRIPTION: VALVE STEM IS SEPARATED FROM THE DIAPHRAGM - REPAIR 901009117 1 12SW383 FAILURE DESCRIPTION: LEAKING SPOOL DOWNSTREAM -

REPLACE SPOOL 901119140 1 RMS 1R45A FAILURE DESCRIPTION: PLANT VENT SAMPLER FAILED -

TROUBLESHOOT AND REPAIR 901120089 1 1SW309 FAILURE DESCRIPTION: HOLE IN THE UPSTREAM FLANGE -

REPAIR

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (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 these evaluations and agrees with their conclusions that these items do not present Unreviewed Safety Questions (USQs).

ITEM

SUMMARY

A. Design Change Packages lEC-3039 Pkg. 2 "Steam Generator Flow Rate (Steam) Instrument Loop Enhancement" - The purpose of this design change is to modify the primary and secondary steam flow input signals to the Reactor Protection Cabinets. A total of eight channels will be affected by this change. A new summator will be added to the steam flow loops. The existing square root extractors will be eliminated from the Reactor Protection Cabinets to provide room for the summator cards. The existing multipliers will be rewired to provide a dual multiplier and square root extraction function. (SORC 90-153) lEC-3049 Pkg. 1 "1R13A and 1R13B Setpoint Basis" - The purpose of this design change is to provide the design basis for allowing the setpoints for the 1Rl3A and 1R13B monitors to be revised. These detectors had been replaced with a different model during the implementation of DCP 1EC-1794A. (SORC 90-153) lSC-2160 Pkg. 1 "C02 System Automation" - The purpose of this design change is to modify the manually actuated C02 Fire Suppression System to include automatic actuation circuitry. To accomplish this, new spot thermal detection will be added to the affected rooms. The new thermal type detectors will be utilized for automatic C02 system actuation. The existing ionization type detection zones will remain in place but will be rewired to provide an "early warning" signal only. (SORC 90-154)

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10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

lSC-2161 Pkg. 1 "C02 System Automation" - The purpose of this design change is to modify the manually actuated C02 Fire Suppression System to include automatic actuation circuitry. To accomplish this, new spot thermal detection will be added to the affected rooms. The new thermal type detectors will be utilized for automatic C02 system actuation. The existing ionization type detection zones will remain in place but will be rewired to provide an "early warning" signal only. (SORC 90-154) lSC-2154 Rev. 1 "Control Room Modifications" - The purpose of this design change package (DCP) is to perform modifications to the Salem Unit 1 Control Room Consoles and Recorder Panels to correct Human Engineering Deficiencies to comply with NUREG 0700 and the Salem Human Factors Guidelines.

This DCP is also to comply with the requirements of Specification S-C-VARX-MDS-0155 and licensing commitments for Salem Generating Station. (SORC 90-155) lEC-3056 Pkg. 1 "1R13 C, D & E" - The purpose of this design change package (DCP) is to establish and implement new setpoints for 1R13C, 1R13D & 1R13E Containment Fan Coil Unit effluent radiation monitors. (SORC 90-158)

B. Procedures and Revisions lIC-18.1.013 "Train A & B Reactor Trip Breaker Operability Test" Rev. 3 - The purpose of this revision is incorporate a change in the NRC reporting requirements from one (1) hour to thirty (30) days and provide a method of testing with a loss of the P-250 computer. (SORC 90-150)

NC.NA-AP.ZZ-0003(Q) "Document Control Program" Rev. 0 - This procedure describes the program for the control of Nuclear Department documents and the method of distribution and maintenance. (SORC 90-153)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

Sl.OP-PT.SW-OOll(Q) "11 CFCU Heat Transfer Performance Data Collection" Rev. 0 - The purpose of this procedure is to provide the instruction necessary to collect heat transfer data for the identified components. The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13. (SORC 90-158)

Sl.OP-PT.SW-0012(Q) "12 CFCU Heat Transfer Performance Data Collection" Rev. 0 - The purpose of this procedure is to provide the instruction necessary to collect heat transfer data for the identified components. The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13. (SORC 90-158)

Sl.OP-PT.SW-0013(Q) "13 CFCU Heat Transfer Performance Data Collection" Rev. 0 - The purpose of this procedure is to provide the instruction necessary to collect heat transfer data for the identified components. The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13. (SORC 90-158)

Sl.OP-PT.SW-0014(Q) "14 CFCU Heat Transfer Performance Data Collection" Rev. 0 - The purpose of this procedure is to provide the instruction necessary to collect heat transfer data for the identified components. The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13. (SORC 90-158)

Sl.OP-PT.SW-0015(Q) "15 CFCU Heat Transfer Performance Data Collection" Rev. 0 - The purpose of this procedure is to provide the instruction necessary to collect heat transfer data for the identified components. The data collected shall be used in a performance evaluation to meet the intent of NRC Generic Letter 89-13. (SORC 90-158)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

C. *Deficiency Reports (DRs)

SMD 90-301 This disposition addresses the repair of spool 1-SW-121 which is part of PSE&G Pipe Specification 1S27C which is Nuclear Class III, Seismic Class I and Safety Related.

Essentially, a window will be cut in the pipe and a replacement piece will be fabricated and welded in. Performance of this work requires a Code Job. All work shall be accomplished in accordance with the Nuclear Department Repair Program and the Welding and Brazing Manual.

(SORC 90-156)

D. Temporary Modifications (TMODS)

STD 90-121 This TMOD provides for the anchorage of the non-saf~ty related chemical addition tank support to prevent its' potential seismic interaction with safety related (i.e., component cooling piping and auxiliary feedwater) equipment. (SORC 90-154)

STD 90-120 The purpose of this temporary modification is to provide a means of chemical (hydrazine or ammonia) addition to the Unit 1 Auxiliary Feedwater System. (SORC 90-155)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 NOVEMBER 1990 SALEM UNIT NO. 1 The Unit began the period operating at 100% power. Power was reduced to 52% on 11/09/90 to repair No. 11 Steam Generator Feedwater Pump (SGFP) thrust bearing and various leaks in the feedwater heater drains. On 11/16/90, following completion of the repairs, the Unit was restored to full power and continued to operate at essentially full power throughout the remainder of the period.

REFUELING INFORMATION DOCKET NO: 50-272 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 MONTH NOVEMBER 1990

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: February 9, 1991

3. Scheduled date for restart following refueling: April 10, 1991

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?: January 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 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