Text

Monthly Operating Rept for Nov 1990 for Salem 1
	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)
	v • d • e

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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.

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, General Manager -

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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90:1.2:2101:3::: 901130 1

2J PDR ADOCK 05000272 R

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:

Date:

Completed by:

Art Orticelle Telephone:

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)

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 This Month 720 720 0

720 0

2217345.6 733970 701944 100 100 88.1 87.4 0

NA Year to Date 8016 5310.9 0

5127.8 0

16426324.8 5402240 5141397 64.0 64.0 58.0 57.5 36.0 50-272 12/10/90 339-2122 since Last N/A Cumulative 117649 76219.5 0

73823.5 0

231527250.8 76863600 73153107 62.7 62.7 56.2 55.8 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

NO.

DATE 0089' 11/09/90 0090 11/12/90 0092 11/14/90 1

2 F:

Forced S:

Scheduled DURATION TYPE 1 (HOURS)

REASON 2 F

71.4 F

48.9 F

37.9 Reason A-.Equipment Failure (explain)

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

B B

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH NOVEMBER 1990 METHOD OF SHUTTING DOWN REACTOR 5

5 5

3 LICENSE EVENT REPORT #

Method:

1-Manual 2-Manual Scram SYSTEM CODE4 CH CH CH 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) 4 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 COMPONENT CAUSE AND CORRECTIVE ACTION CODE5 TO PREVENT RECURRENCE PUMPXX

11 STEAM GEN.

PUMP XX

11 STEAM GEN.

INSTRU

11 STEAM GEN.

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

SAFETY RELATED MAINTENANCE MONTH: -

NOVEMBER 1990 DOCKET NO:

UNIT NAME:

50-272 SALEM 1 WO NO UNIT 890412004 1

900220102 1

900322153 1

900919104 1

901009117 1

901119140 1

901120089 1

DATE:

COMPLETED BY:

TELEPHONE:

DECEMBER 10,. 1990 F. THOMSON (609)339-2904 EQUIPMENT IDENTIFICATION lA RX TRIP BRKR FAILURE DESCRIPTION:

REPLACE UV TRIP DEVICE 11 CHILLER COND. PUMP FAILURE DESCRIPTION:

BEARING HOUSING OIL LEAK -

REPAIR 13 CHILLER COND. PUMP FAILURE DESCRIPTION:

BEARING OIL LEAK -

REPAIR 16SW25 FAILURE DESCRIPTION:

VALVE STEM IS SEPARATED FROM THE DIAPHRAGM -

REPAIR 12SW383 FAILURE DESCRIPTION:

LEAKING SPOOL DOWNSTREAM -

REPLACE SPOOL RMS 1R45A FAILURE DESCRIPTION:

PLANT VENT SAMPLER FAILED -

TROUBLESHOOT AND REPAIR 1SW309 FAILURE DESCRIPTION:

HOLE IN THE UPSTREAM FLANGE -

REPAIR

10CFR50.59 EVALUATIONS MONTH: -

NOVEMBER 1990 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-272 SALEM 1 DECEMBER 10, 1990 F. THOMSON (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 A.

Design Change Packages lEC-3039 Pkg. 2 lEC-3049 Pkg. 1 lSC-2160 Pkg. 1

SUMMARY

"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)

"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)

"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)

*~-----------------1 10CFR50.59 EVALUATIONS MONTH: -

NOVEMBER 1990 (Cont'd)

ITEM lSC-2161 Pkg. 1 lSC-2154 Rev. 1 lEC-3056 Pkg. 1 B.

Procedures and Revisions lIC-18.1.013 NC.NA-AP.ZZ-0003(Q)

DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-272 SALEM 1 DECEMBER 10, 1990 F. THOMSON (609)339-2904 "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)

"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)

"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)

"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)

"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 MONTH: -

NOVEMBER 1990 (Cont'd)

ITEM Sl.OP-PT.SW-OOll(Q)

Sl.OP-PT.SW-0012(Q)

Sl.OP-PT.SW-0013(Q)

Sl.OP-PT.SW-0014(Q)

Sl.OP-PT.SW-0015(Q)

DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-272 SALEM 1 DECEMBER 10, 1990 F. THOMSON (609)339-2904 "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.