ML18106B101

Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr

ML18106B101
Person / Time
Site:	Salem
Issue date:	02/28/1999
From:	Garchow D, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N99-0114, LR-N99-114, NUDOCS 9903250367
Download: ML18106B101 (6)

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. e CPS~G Publi~ ~ervice ~lectric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit LR-N99-0114 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERA TING REPORT SALEM UNIT NO. 1 DOCKET NO. 50-272 Gentlemen:

In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical I

Specifications, the original Monthly Operating report for February 1999 is attached.

Sincerely, w

General Ma ager -

990:3250367 *99022a- *- - Salem Operations PDR ADOCK 05000272 R PDR

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C Mr. H.J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 The power is in your hands.

95-2168 REV. 6/94

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DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 3/15/99 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: February 1999 OPERATING DATA REPORT Design Electrical Rating (MWe-Net) 1115 Maximum Dependable Capacity (MWe-Net) 1106 Month Year-to-date Cumulative No. of hours reactor was critical 650 1394 105774 No. of hours generator was on line (service 650 1394 101782 hours)

Unit reserve shutdown hours 0 0 0 Net Electrical Energy (MWH) 697302 1517782 101654325 UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE F=FORCED (HOURS) (1) SHUTTING ACTION/COMMENT S=SCHEDULED DOWN THE REACTOR (2) 1 2/28/99 F 22 8 3 Turbine Trip: Lube Oil Incorrect valve manipulation (1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip/Scram C- Refueling 3 - Automatic Trip/Scram D - Regulatory Restriction 4 - Continuation E - Operator Training/License Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain)

H -Other Summary:

Salem Unit 1 began the month of February 1999, operating at full power. Full power operation continued until February 28, when power was reduced to 25% address a Reactor Coolant pump lubricating oil alarm. During the recovery from that power reduction, an incorrect manipulation of a valve in the Main Turbine Lubricating Oil

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 3715799 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782 system caused the Main Turbine to trip, resulting in an automatic reactor scram. The unit completed the month shut down.

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 3715799 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH: February 1999 The following items completed during February 1999 have been evaluated to determine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or

3. If the margin of safety as defined in the basis for any technical specification is reduced.

The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant; nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Design Changes - Summary of Safety Evaluations Minor Modification S97-112, Removal Of The Positioner From Valve 12SW92, 12 Auxiliary Building Chiller This modification removed the positioner from the 12SW92 valve, removing its flow modulating capability. This valve is not used for flow modulation and is either fully open or fully closed. Valve operation to either the fully open or fully closed position will be accomplished pneumatically via a solenoid valve. The

• modification was implemented to improve the reliability of the respective Auxiliary Building Chiller by reducing the number of parts susceptible to failure or calibration drift.

Review of this modification under 10CFR50.59 was required because removal of the 12SW92 positioner constituted a change to the facility as described in the Safety Analysis Report (SAR). The review determined that because the change did not alter the functionality of the 12SW92 valve, the change did not increase the probability or consequences of an accident previously evaluated in the SAR, did not increase the probability or consequences of a malfunction of equipment important to safety, and did not create the possibility of an accident or

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malfunction of a different type from any previously evaluated. Because the

. . change did not affect the existing analysis that forms the basis for the Technical Specifications, and will not violate Technical Specification and Updated Final Safety Analysis Report (UFSAR) requirements, the change will not reduce the margin of safety as defined in the basis for the Technical Specifications.

Temporary Modifications - Summary of Safety Evaluations There were no changes in this category implemented during February 1999.

Procedures - Summary of Safety Evaluations Procedure, SC.MD-CM.ZZ-0034(Q), DC Ground Fault Trouble Shooting Using AVO Battery Ground Fault Tracer This procedural change was made to permit the use of the AVO Battery Ground Fault Tracer to locate single polarity grounds on the ungrounded DC system.

The use of this equipment will facilitate location of grounds so that the grounds can be corrected and is an enhancement over the installed ground detection system. The installed ground detection system can identify the existence of a ground, the relative magnitude, and the polarity of the ground, but d.oes not identify the ground location. This change was evaluated as required by 10CFR50.59 because it represented a change to the facility as described in the SAR. Specifically, because the installed ground detection system must be removed from service to use the AVO system, and because the AVO system introduces a 25 hertz AC voltage to the faulted portion of the DC system.

This change did not increase the probability or the consequences of an accident previously evaluated in the SAR, did not increase the probability of occurrence or the consequences of a malfunction of equipment important to safety, and did not increase the possibility of an accident of a different type. Trouble shooting will only occur to one equipment train at a time, and the DC system will remain energized and available to perform its design function. Because the change did not affect the existing analysis that forms the basis for the Technical Specifications, and will not violate Technical Specification and Updated Final Safety Analysis Report (UFSAR) requirements, the change will not reduce the margin of safety as defined in the basis for the Technical Specifications.

UFSAR Change Notices - Summary of Safety Evaluations There were no changes in this category implemented during February 1999.

Deficiency Reports - Summary of Safety Evaluations There were no changes in this category implemented during February 1999.

Other - Summary of Safety Evaluations There were no changes in this category implemented during February 1999.