ML18106A611

Monthly Operating Rept for Apr 1998 for Salem Unit 2. W/980515 Ltr

ML18106A611
Person / Time
Site:	Salem
Issue date:	04/30/1998
From:	Bakken A, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0244, LR-N98-244, NUDOCS 9805260042
Download: ML18106A611 (5)

Text

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OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit LR-N98-0244 May 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 I

Specifications, the original Monthly Operating report for April 1998 is attached.

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 9805260042 980430 PDR ADOCK 05000311 R PDR The power is in your hands. : , ') r* .~-, r'. 0

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95-2168 REV. 6/94

DOCKET NO.:

UNIT:

DATE:

50-311 Salem 2 5/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: April 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 719 2146 83353 No. of hours generator was on line (service 649 2056 80119 hours)

Unit reserve shutdown hours 0.0 0.0 0.0 Net Electrical Energy (MWH) 693436 2174660 79350245 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 April operating at full power. On April 8, the Unit 2 generator was removed from service and reactor power was reduced to 10% to address biological fouling of the Service Water system. The unit returned to service at 1606 on April 11, and proceeded to full power. Full power operation continued through the end of the month.

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 5/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH: April 1998 The following items completed during APRIL 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-3303, Pkg. 1, Circulating Water Bearing Lubrication/Screen Wash Setpoint And System Changes This modification implemented changes to the Circulating Water system to improve system reliability and performance. The changes included recalibration of system pressures and flows, changes to the Lubrication pump and Screen Wash pump controls, replacement of the Lubrication Water and Screen Wash strainer pressure gauges, and replacement of control valves with manual valves to simplify system operation.

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.

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2EC-3590, Pkg. 14, Protection For Service Water Accumulator Tanks And Associated Equipment This modification installed a gated security barrier in the area of the Service Water Accumulator vessel enclosure and a tornado missile barrier on the roof of the Auxiliary Building. The barrier was installed to provide protection for the vessels and their associated equipment.

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-3630, Pkg. 1, Auxiliary Building Chiller Compressor, Freon Discharge Pressure Controller Modification This modification replaced the existing Auxiliary Building Chiller Compressor, Freon Discharge Pressure Controllers with a proportional plus integral plus derivative (PIO) type controller to improve the response of the chiller Service Water control valves.

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 Temporary Modification 98-02, Blind Flange For The Discharge Pipe From Relief Valve 2CV141.

This modification installed a blind flange on the discharge line of relief valve 2CV141 to provide isolation of the downstream piping during maintenance.

This temporary modification 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 temporary modification does not involve an Unreviewed Safety Question.

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

UFSAR Change Notices - Summary of Safety Evaluations There were no changes in this category implemented during April 1998.

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Deficiency Reports - Summary of Safety Evaluations

. There were no changes in this category implemented during April 1998.

Other - Summary of Safety Evaluations Salem Work Order 00980416312, Freeze Seal For Discharge Pipe From Relief Valve 2CV141 This work order installed a freeze seal on the discharge line of relief valve 2CV141 to provide isolation of the downstream piping during maintenance.

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 change does not involve an Unreviewed Safety Question.

Change To Salem Unit 2 Technical Specification Bases 3/4.9.1, Refueling Operations, Boron Concentration This change to the Bases for Technical Specification 3/4.9.1 provided clarification of the Technical Specification requirements for sampling of the Salem Unit 2 Refueling Canal.

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 change does not involve an Unreviewed Safety Question.

Change To Salem Unit 2 Technical Specification Bases 2.2.1, Safety Limits And Limiting Safety System Settings This change to Technical Specification Bases 2.2.1 revised the description of Negative Flux Rate Trip (NFRT) to make the Bases consistent with the Salem Updated Final Safety Analysis Report. This change was required because of the implementation of an updated Westinghouse rod drop methodology in which the NFRT is no longer credited with protecting against minimum Departure From Nucleate Boiling Ratio (DNBR) concerns.

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 change does not involve an Unreviewed Safety Question.