ML18106A653

Monthly Operating Rept for May 1998 for Salem Unit 2. W/980615 Ltr

ML18106A653
Person / Time
Site:	Salem
Issue date:	05/31/1998
From:	Bakken A, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0293, LR-N98-293, NUDOCS 9806170110
Download: ML18106A653 (5)

Text

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• Public.Service,Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUN 121998 LR-N98-0293 June 15, 1998 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 May 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 9ao6170-110 * *990531 - - *

~DR ADOCK 05000311 PDR The power rs myour nanus.

95-2166 REV. 6/94

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• DOCKET NO.:

UNIT:

DATE:

50-311 Salem 2 6/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: May 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 2890 84097 No. of hours generator was on line (service 744 2800 80863 hours)

Unit reserve shutdown hours 0.0 0.0 0.0 Net Electrical Energy (MWH) 812068 2986728 80162313 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 2 began the month of May operating at full power. Full power operation continued until May 23, when load was reduced to 80% to investigate an increase in the Reactor Coolant system leakage rate. The unit returned to full power on the following day and operated at full power for the remainder of the month.

• DOCKET NO.:

UNIT:

50-311 Salem 2 DATE: 6/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH: May 1998 The following items completed during MAY 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-3570, Pkg. 1, Nitrogen Purge/Blanket Of The Auxiliary Feedwater Storage Tank This modification provided a nitrogen purge/blanket system for the Salem 2 Auxiliary Feedwater Storage Tank in order to control the dissolved oxygen concentration in the feed water.

This design change does not negatively impact any accident response nor does it 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.

2EC-3590, Pkg. 9, No. 22 Service Water, Installation Of A Redundant Check Valve This modification installed a redundant check valve in the No. 22 Service Water Nuclear Header Containment Fan Coil Unit 16" supply piping. The redundant check valve will prevent drainage of the supply piping to the No. 23, No. 24, and

• No. 25 Containment Fan Coil Units in the event of a failure of the existing check valve.

This design change does not negatively impact any accident response nor does it 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 May 1998 Procedures - Summary of Safety Evaluations There were no changes in this category implemented during May 1998.

UFSAR Change Notices - Summary of Safety Evaluations UFSAR Change Notice S98-017, Accumulator Sample Line Purging This revision reflects changes to the procedure for purging of the Reactor Coolant system accumulator sample lines to a different location than currently described in the UFSAR. This proposed change will allow accumulator purges to other plant systems, such as the liquid waste system.

This change does not negatively impact any accident response nor does it 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.

UFSAR Change Notice S98-013, Nuclear Business Unit Organization Change - Succession Of Authority This change revises the succession of authority and responsibility for Salem to reflect an Operations led organization.

This change does not negatively impact any accident response nor does it 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.

Deficiency Reports - Summary of Safety Evaluations Salem Unit 2 Steam Generator Tube Support Plate Indications This safety evaluation considers indications of degradation in three of four Salem Unit 2 Steam Generator tube support plates that were identified during testing performed in response to Generic Letter 97-06. The indications are likely the

• result of manufacturing irregularities and do not affect the reactor coolant pressure boundary.

This design change does not negatively impact any accident response nor does it 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.

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