ML18106A459

Monthly Operating Rept for Mar 1998 for Salem Unit 2. W/980415 Ltr

ML18106A459
Person / Time
Site:	Salem
Issue date:	03/31/1998
From:	Bakken A, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0193, LR-N98-193, NUDOCS 9804210275
Download: ML18106A459 (6)

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~ Publi.,:;_Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit April 15, 1998 LR-N98-0193 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 2 DOCKET NO. 50-311 Gentlemen:

In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating report for March, 1998, is attached.

I Sincerely, A. C. Bakken Ill General Manager -

Salem Operations RBK/rbk Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of

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Prussia, PA 19046 9804210275 980331 PDR ADOCK 05000311 R PDR The power is in your hands.

95-2168 REV. 6/94

DOCKET NO.: 50-311 UNIT: Salem 2 DA TE: 4/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: March 1998 OPERATING DATA REPORT Design Electrical Rating (MWe-Net) 1115 Maximum Dependable Capacity (MWe-Net) 1106 Month Year-to-date No. of hours reactor was critical 418 1427 No. of hours generator was on line (service 398 1406 hours0.0163 days <br />0.391 hours <br />0.00232 weeks <br />5.34983e-4 months <br />)

Unit reserve shutdown hours 0.0 0.0 0.0 Net Electrical Energy (MWH) 403024 1481224 78656809 UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE F=FORCED (HOURS) (1) SHUTTING ACTION/COMMENT S=SCHEDULED DOWN THE REACTOR (2) 3 3/1/98 F 346 A 4 Service Water System

- Biofouling 3/15/98 (1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual 8 - 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 2 began the month of March shutdown. The unit was shutdown on February 11, 1998, to address the failure of the 2A Emergency Diesel Generator (EOG) turbocharger. This shutdown was reported in Licensee Event Report 311198-005-00. The 2A EOG was returned to service on February 23, but Unit 2 remained shutdown until March 15, to address Pressurizer Safety valve and Power Operated Relief valve leakage; and biofouling of the Ser\tice Water system. Following its return to service, Unit 2 operated at full power until March 24, when an electrical fault on a

controls transformer caused a plant runback to 60% power. Unit 2 returned to full po~er on the following day and operated at full power for the remainder of the month.

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DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 4/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH March 1998 The following items completed during MARCH 1998 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 2EC-3298, Pkg. 1, Switchgear And Penetration Area Ventilation (SPAV)

System Upgrade. This design incorporated enhancements to the SPAV system by modifying system components (fans, dampers, and instrumentation),

modifying the system temperature control scheme, and by testing and balancing the system.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

Minor Modification, S97-147, Steam Line Radiation Monitors. This modification deleted a steam trap and rerouted the drain from the Steam Line Radiation monitors to the 22 Condenser via an existing connection in the Unit 2 Main Steam system.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

Temporary Modifications Summary of Safety Evaluations There were no changes in this category implemented during March, 1998.

Procedures Summary of Safety Evaluations There were no changes in this category implemented during March, 1998.

UFSAR Change Notices Summary of Safety Evaluations UFSAR Change Notice 98-011, Control Room Ventilation (CRV) -

Radiologically Contaminated Air Intrusion. This UFSAR Change Notice documented a change to the UFSAR description of CRV system operation for the Control Room Emergency Air Conditioning system (CREACS) in the single filtration train alignment, without pre-selecting an outside air intake.

This evaluation does not negatively impact any accident response. This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this procedure revision does not involve an Unreviewed Safety Question.

Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during March, 1998.

Other Summary of Safety Evaluations Safety Evaluation S97-026, Offsite Dose Calculation Manual, Revision 11.

Revision 11 to the Offsite Dose Calculation Manual (ODCM) corrected Safety Factor values used to calculate radioactive effluent waste release rates and radioactive liquid waste radiation monitor setpoints.

This evaluation does not negatively impact any accident response. This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this procedure revision does not involve an Unreviewed Safety Question.

Safety Evaluation S97-027, Steam Generator Tube Sentinel Plugs Incorrectly Repaired. This Safety Evaluation evaluated the operation of Salem Unit 2 with two Steam Generator tubes that were incorrectly repaired. This repair compromised the ability of sentinel plugs installed in those tubes to provide tube leak detection capability.

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This evaluation does not negatively impact any accident response. This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this procedure revision does not involve an Unreviewed Safety Question.