ML17348B493

Monthly Operating Rept for Jul 1990 for Salem 2.W/900815 Ltr

ML17348B493
Person / Time
Site:	Salem
Issue date:	07/31/1990
From:	Miller L, Morroni M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9008210119
Download: ML17348B493 (22)

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ACCESSION .NBR 9008210119 DOC.DATE: 90/07/31 NOTARIZED: NO DOCKET g FACIL:50-311 Salem Nuclear Generating Station, Unit 2, Public Serv 0500031'1 AUTH. NAME AUTHOR AFFILIATION MORRONI, M. Public Service Electric & Gas Co. of New Jersey MILLER,L.K. Public Service Electric & Gas Co. of New Jersey RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

Monthly operating rept for Jul 1990 for Salem 2.W/900821 D

DISTRIBUTION CODE: IE24D TITLE: Monthly Operating Report (per Tech Specs)

COPIES RECEIVED- LTR r ENcL I SIZE: /0 NOTES:

RECIPIENT COPIES 'RECIPIENT COPIES A ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-2 LA 3 3 PD1~-2 PD 1 1 D 1 1 STONE,J'NTERNAL:

D AEOD/DOA AEOD/DS P/TPAB 1 1 IRM TECH ADV NRR/DJEQ EB10 1 1 NRR/DOEA/OEAB1 1 EG FILE RGN1 EXTERNAL .EG&G BRYCE g J H LPDR 1 1 NRC PDR NSIC 1 1 I

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D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE IVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR)NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON T NEED~

I TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19

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Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station August 15, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 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 July 1990 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Maj'or Plant Modifications Operating Summary Refueling Information Sincerely yours, L. K. Miller General Manager Sa'lem Operations RH:pc CC'r. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The Energy peop]e 9008210119 90 P~Q&P rv PDR ADOCK 05000311 eriC 95.2189(1iM) i2.a+

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem 2 Date 08-10-90 Completed by Art Orticelle Telephone 609-339-2122 Month JULY 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1'8 19 20 21 22 0, 23 24 '0 25 10 26 27 12 28 13 29 14 0 30 15 31 16 P. 8.1-7 Rl

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CORRECTED OPERATING DATA REPORT Docket No: 50-311 Date: 08-10-90 Completed by: Art Orticelle Telephone: 609-339-2122 0 eratin Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period JULY 1990

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 Report, Give Reason N/A 3 through 7) since Last

9. Power Level to Which Restricted, if any (Net NWej, ~N A

10. Reasons for Restrictions, if any ~N A This Month Year to Date Cumulative

11. Hours in Reporting Period 744 5087 77136

12. No. of Hrs. Reactor was Critical 21.9 2161.0 48166.9

13. Reactor Reserve Shutdown Hrs. 0 0

14. Hours Generator On-Line 2056.2 46601.5

15. Unit Reserve Shutdown Hours 0

16. Gross Thermal Energy Generated (MWH) 1797.6 6683479.2 95735218.6

17. Gross Elec. Energy Generated (MWH)

18. Net Elec. Energy Generated

19. Unit, Service Factor

20. Unit Availability Factor (MWH) -13760 0 2266270 2138224 40.

40.4 4'0.4 48313322 45938130 60.4

.21. Unit Capacity Factor (using MDC Net) 38 53.8

22. Unit Capacity Factor (using DER Net) 37.7 53.4

23. Unit Forced Outage Rate 10.0 25.4

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

None

25. If shutdown at end of Re ort Period Estimated Date of Startu 08 14 90 8-1-7.R2

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UNIT SHVIDM AND PNER RHXJCPIONS DOCKER NO.: 50-311 ~

REPORT MONIH JVLY 1990 DATE: 08-10-90.

CNPIZIKD K: Art Orticelle KIEPHNE: 339-2122 .

KNRSBF CAUSE AND (G81ZIXVE ACFION hQ. (EXJRS) KSE ~ m PREVENr MXXMuXCE 07/01/90 21-24 MS167 VALVES 1 2 3 4 5 F: Forced Reason: Method: Exhibit G - Instructions Exhibit 1 - Same S Scheduled A-Bp6poent Failure (Explain) 181anual for Preparation of Data Source B-Maintenance or Test 291anual Scram Entry Sheets for Licensee C-Refueling 3-Autcmatic Scram Event Report (IH0 File D-Regulatory Restriction 4-Continuation of (NUR~161)

M)perator Trains 6 License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-Other H-Other (Explain)

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SAFETY RELATED MAINTENANCE DOCKET NO: 50-311 MONTH'. JULY 1'990 UNIT NAME: SALEM 2 DATE: AUGUST 10, 1990 COMPLETED BY: M. MORRONX TELEPHONE: (609) 339-2068 WO NO UNIT EQUIPMENT IDENTIFICATION 880627079 2 2MISC-MECH-OUTER PENETRATION FAILURE DESCRIPTjON: GROUND WATER LEAK REPAIR 890724021 2 21WG032 FAILURE DESCRIPTION: REPLACE'IAPHRAGM 900501262. 2 SPOOL RD-2-SW-740 FAILURE DESCRIPTION: HOLE IN WELD REPAIR 900611130 2 22RCP SEAL OUT'EMP FAILURE DESCRIPTION: INDICATION READING LOW INVESTIGATE 900618122 2 TAC MOTOR AMPS INDICATION FAILURE DESCRIPTION: INDICATION FAILED HIGH INVESTIGATE 900722049 2 2A D/G SPEED CONTROL FAILURE DESCRIPTION: SPEED-LOAD CONTROL SLOW RESPONSE TROUBLESHOOT 900724121 2 21 SW PUMP FAILURE DESCRIPTION: PUMP WIIJL NOT RESTART TROUBL'ESHOOT AND REWORK

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MAJOR PLANT MODIFICATIONS DOCKET NO: 50-311 MONTH: JULY 1990 UNIT NAME: ,SALEM 2 DATE AUGUST 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068

• DCR PRINCIPAL SYSTEM DESCRIPTION 2EC-2122 Reactor Containment This design change provided for Fan Cooler Motors refurbishment of two 'Reactor Containment Fan Cooler Unit (RFCU) motors to improve their reliability.

2EC-2187 Chemical Volume This design change reduced the boron R Control System concentration in the Boron Injection Tank (BIT) from 21,000 ppm to less than 7,000 ppm. The recirculation lines between the BIT and the Boron Addition Tank (BAT) were cut and capped and the heat tracing was

.disconnected.

UHF Radio This design change increased the coverage of the UHF radio 2EC-2302'SM-0208 communication system by adding four antennas.

TAC Expansion This modification. installed a Tank permanent sightglass for the Turbine Auxiliaries Cooling Makeup and Expansion Tank.

DCR Design Change Request

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MAJOR PLANT MODIFICATIONS DOCKET NO: 50-311 MONTH: JULY 1990 UNIT NAME: SALEM 2 DATE: AUGUST 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068

• DCR SAFETY EVALUATION 10 CFR 50.59 2EC-2122 This design change provided for refurbishment of two RFCU motors to. improve their reliability. Certificate and qualification documentation, including workmanship qualification and seismic requalification to the original speci'fications and requirements, are provided by the vendor. There is no change to any plant process or discharge or to the environmental impact of .the plant. No unreviewed safety or environmental questions are involved.

2EC-2187 This design change reduced the boron concentration in the BIT from 21, 000 ppm to less than 7, 000 ppm. The recirculation lines between the BIT and the Boron Addition Tank (BAT) were cut and capped and the heat tracing was disconnected. These modifications eliminated the Technical Specifications associated with the BIT as well as the maintenance problems associated with high concentration boron. These modifications did not increase the probability of any accidents previously evaluated or introduce any new accidents. There is no change to any plant process or discharge or to the environmental impact of'he plant. No unreviewed safety or environmental questions are involved.

2EC-2302 This design change increased the coverage of the UHF radio communication system by adding four antennas. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety has not been increased. This modification has not created the possibility of an accident, or malfunction different than any evaluated in the FSAR. The margin of safety defined in the Technical Specifications and the FSAR has not been reduced. There is no change to any plant process or discharge or to the environmental impact of the plant.

No unreviewed safety or environmental questions are involved.

2SM-0208 This modification installed a permanent sightglass for the TAC Makeup and Expansion Tank. There is no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

• DCR Design Change Request

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MAJOR PLANT MODIFICATIONS DOCKET NO: '50-311 MONTH: JULY 1990 UNIT NAME: SALEM, 2 DATE: AUGUST 10, 1990 COMPLETED BY:, M. MORRONI TELEPHONE: (609) 339-2068 (cont'd)

• DCR SAFETY EVALUATION 10 CFR 50.59 2SM-0973 This design change raised the setpoint of the BIT pressure alarm from 2250 psig to 2610 psig to eliminate false alarms. The BIT high discharge pressure alarm provided the Control Room Operators a way of determining that there was a blocked flowpath during safety injection. The function of the hi'gh discharge pressure alarm has not been changed and the boric acid concentration in the BIT has been reduced to the point that boric acid solidification is no longer a concern. The new setpoint is still below the design pressure of the BIT and piping, including instrument inaccuracies. There is no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed'afety or environmental questions are involved.

• DCR Design Change Request

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 JULY 1990 SALEM UNIT NO. '2 The Unit entered the period shutdown, following a reactor trip on June 28, 1990 due to failure of the 2F 460V transformer. During the transient, two Main Steam Isolation Valves (MSIVs) failed to operate as expected. An investigation into the cause identified a weakness in the MSIV isolation logic. An evaluation, performed in support of a proposed d'esign change on the MSIVs indicated that ensured the valves would close during certain it could not be postulated main steam line pipe breaks. The Unit remained shutdown throughout the rest of the period while additional analyses and evaluations were performed.

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REFUELING INFORMATION DOCKET NO 50-311 MONTH: JULY 1990 UNIT NAME: SALEM 2 DATE: AUGUST 10, 1990 COMPLETED BY,: M. MORRONI TELEPHONE: (609) 339-2068 MONTH JULY 1990

1. Refueling information has changed from'last month:

YES X NO

2. .Scheduled date for next refueling: November 30 1991

3. Scheduled date for restart following refueling: ,Februar 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?: October 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 8-1-7.R4

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