ML17348B493

Monthly Operating Rept for Jul 1990 for Salem 2

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)

Text

ACCELERATED DIST BUTION DEMONSTIMTION SYSTEM t

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REGULATORY.INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION.NBR 9008210119 DOC.DATE: 90/07/31 NOTARIZED:

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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 DISTRIBUTION CODE:

IE24D COPIES RECEIVED-TITLE: Monthly Operating Report (per Tech NOTES:

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RECIPIENT ID CODE/NAME PD1-2 LA STONE,J'NTERNAL:

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NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE IVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR)NAMEFROM 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 P~Q&P rv PDR ADOCK 05000311 9008210119 90 The Energy peop]e R

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AVERAGE DAILY UNIT POWER LEVEL Month JULY 1990 Docket No.

Unit Name Date Completed by Telephone 50-311 Salem 2

08-10-90 Art Orticelle 609-339-2122 Day Average Daily Power Level (MWe-NET)

Day Average Daily Power Level (MWe-NET) 1'8 19 20 21 22 0,

23 24

'0 25 10 26 27 12 13 14 15 0

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CORRECTED OPERATING DATA REPORT Completed by:

Art Orticelle 0 eratin Status Docket No:

Date:

Telephone:

50-311 08-10-90 609-339-2122 Notes 1.

Unit Name Salem No.

2 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 3 through

7) since Last

Report, Give Reason N/A 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 12.

No. of Hrs. Reactor 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 Generated (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 744 21.9 0

1797.6 0

-13760 5087 2161.0 0

2056.2 77136 48166.9 0

46601.5 6683479.2 95735218.6 38 53.8 37.7 10.0 53.4 25.4 2266270 48313322 2138224 45938130 40.4'0.4 40.4 60.4 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 REPORT MONIH JVLY 1990 DOCKER NO.:

50-311

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DATE:

08-10-90.

CNPIZIKD K: Art Orticelle KIEPHNE:

339-2122 hQ.

07/01/90 (EXJRS)

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CAUSE AND (G81ZIXVE ACFION m PREVENr MXXMuXCE 21-24 MS167 VALVES 1

F:

Forced S

Scheduled 2

Reason:

A-Bp6poent Failure (Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction M)perator Trains 6 License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain) 3 Method:

181anual 291anual Scram 3-Autcmatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-Other 4

5 Exhibit G - Instructions Exhibit 1 - Same for Preparation of Data Source Entry Sheets for Licensee Event Report (IH0 File (NUR~161)

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SAFETY RELATED MAINTENANCE MONTH'.

JULY 1'990 DOCKET NO:

50-311 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 MONTH:

JULY 1990 DOCKET NO:

UNIT NAME:

DATE COMPLETED BY:

TELEPHONE:

50-311

,SALEM 2 AUGUST 10, 1990 M.

MORRONI (609) 339-2068

• DCR PRINCIPAL SYSTEM DESCRIPTION 2EC-2122 2EC-2187 2EC-2302'SM-0208 Reactor Containment Fan Cooler Motors Chemical Volume R Control System UHF Radio TAC Expansion Tank This design change provided for refurbishment of two 'Reactor Containment Fan Cooler Unit (RFCU) motors to improve their reliability.

This design change reduced the boron 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.

This design change increased the coverage of the UHF radio communication system by adding four antennas.

This modification. installed a

permanent sightglass for the Turbine Auxiliaries Cooling Makeup and Expansion Tank.

DCR Design Change Request

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MAJOR PLANT MODIFICATIONS MONTH: JULY 1990 DOCKET NO:

50-311 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 MONTH: JULY 1990 (cont'd)

DOCKET NO:

'50-311 UNIT NAME:

SALEM, 2 DATE:

AUGUST 10, 1990 COMPLETED BY:,

M.

MORRONI TELEPHONE:

(609) 339-2068

• 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 it could not be ensured the valves would close during certain 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 MONTH: JULY 1990 DOCKET NO UNIT NAME:

DATE:

COMPLETED BY,:

TELEPHONE:

50-311 SALEM 2 AUGUST 10, 1990 M.

MORRONI (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 b.

In Spent Fuel Storage 8.

Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

9.

Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

193 316 1170 1170 March 2003 8-1-7.R4

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