ML18106B026

Monthly Operating Rept for Dec 1998 for Salem Unit 1.With 990115 Ltr

ML18106B026
Person / Time
Site:	Salem
Issue date:	12/31/1998
From:	Bakken A, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N99-0007, LR-N99-7, NUDOCS 9901250177
Download: ML18106B026 (5)

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' . e OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit LR-N99-0007 JAN 15 1999 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 1 DOCKET NO. 50-272 Gentlemen:

In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating report for December 1998 is attached. I Sincerely, A. C. Bakken Ill General Manager -

Salem Operations

/rbk Enclosures C Mr. H.J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 9901250177 981231 PDR ADOCK 05000272 R PDR The power is in your hands.

95-2168 REV. 6/94

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 1/15/99 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: December 1998 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 744 6440 110821 No. of hours generator was on line {service 744 6199 106588 hours}

Unit reserve shutdown hours 0 0 0 Net Electrical Energy {MWH} 819582 6475620 106612163 UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE F=FORCED (HOURS) (1) SHUTTING ACTION/COMMENT S=SCHEDULED DOWN THE REACTOR (2)

(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 December 1998, operating at full power. Full power operation continued until December 26, 1998 when power was reduced to 90% to perform turbine control valve testing. Full power operation was restored that day and continued for the remainder of the month.

1-1 DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 1715799 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH: December 1998 The following items completed during December 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 Design Change Package 1EC-3724, Package 1, Demineralizer Alley/Waste Evaporator Room Fire Detection Upgrade This design change package installed five additional ionization chamber smoke detectors, cable, and conduit in the Salem Unit 1 Waste Evaporator Room and Demineralizer Alley area. Review of this modification under 10CFR50.59 was required because the modification constituted a change to the facility as described in the Safety Analysis Report (SAR), specifically the Salem Fire Protection Program.

This modification added additional fire detection capability for the Salem Unit 1 Waste Evaporator Room and Demineralizer Alley area. The detectors were installed per the manufacturer and National Fire Protection Association requirements and mounted to meet seismic II/I requirements. As such, the change did not increase the probability or the consequences of an accident previously evaluated in the SAR. The change did not increase the probability of occurrence or the consequences of a malfunction of equipment importance to safety because no changes were made to any system or component required to

. safely operate or to shut down the reactor. The change did not increase the possibility of a different type from any previously evaluated in th~ SAR because no new failure modes were created by the change. Finally, this modification did not involve any changes to Technical Specifications and therefore did not affect the margin of safety, as defined in the Technical Specification Bases. Based upon the above, this modification does not involve an Unreviewed Safety Question.

Temporary Modifications - Summary of Safety Evaluations Temporary Modification 98-0009, Auxiliary Feed Storage Tank (AFST)

Hydrazine Removal Skid Temporary Modifications This temporary modification provided connections to the AFST to permit the use of a temporary recirculating demineralizer loop to remove hydrazine from the feed water. Review of this modification under 10CFRS0.59 was required because the modification constituted a change to the facility as described in the SAR.

This temporary modification did not affect any existing design basis inputs or safety analysis assumptions, and did not involve a test or procedure not described in the SAR. Neither normal operation, abnormal operation, or failure of the temporary modification can result in a loss of level in the AFST that lowers the level of the water stored to less than the Technical Specification required minimum volume of 200,000 gallons. The AFST and the Auxiliary Feedwater system continue to function as before to mitigate Design Basis Accidents and to perform shutdown and cooldown of the reactor plant. The dose consequences of previously analyzed Design Basis Accidents are not increased by the installation of this temporary modification. Based upon the above, this temporary modification does not involve an Unreviewed Safety Question.

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

• UFSAR Change Notices - Summary of Safety Evaluations UFSAR Change Notice SCN 98-039, Salem Spent Fuel Cooling System

• This UFSAR Change Notice documents the seismic upgrade of the Spent Fuel Pool Cooling system. This upgrade, along with other system attributes and administrative controls, together would preclude bulk pool temperatures from exceeding 180°F, making Spent Fuel Pool boiling a non-credible event.

. The original Salem spent fuel pool licensing basis did not preclude pool boiling.

Following identification of several technical and practical concerns associated with pool boiling, it was decided to seismically upgrade the system and render boiling a non-credible event. This evaluation summarizes upgrade activities and justification for rendering boiling non-credible. The upgrade does not constitute an Unreviewed Safety Question because plant design remains within current licensing basis parameters (i.e. maximum pool temperature of 149°F under normal conditions and 180°F under emergency conditions) and no technical specification changes are required.

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

Other - Summary of Safety Evaluations There were no changes in this category implemented during December 1998.