ML18106A874

Monthly Operating Rept for Aug 1998 for Salem Unit 1.With 980915 Ltr

ML18106A874
Person / Time
Site:	Salem
Issue date:	08/31/1998
From:	Bakken A, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0435, LR-N98-435, NUDOCS 9809220331
Download: ML18106A874 (6)

Text

--._*.-0 PS~G e Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit SEP 15 1998 LR-N98-0435 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.

I Specifications, the original Monthly Operating report for August 1998 is attached. I !

General Manager -

Salem Operations

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Enclosures **- *,,

C Mr. H.J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

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9809220331 980831 --~--~:

PDR ADOCK 05000272 R PDR The power is in your hands.

95-2168 REV. 6/94

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 9/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: August 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 3511 107892 No. of hours generator was on line (service 744 3270 103659 hours)

Unit reserve shutdown hours 0 0 0 Net Electrical Energy (MWH) 784329 3322849 103459392 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 August 1998, operating at full power. Full power operation continued until August 2, when power was reduced to 80% to address a high temperature condition in a Main Power Transformer. The unit returned to full power

• DOCKET NO.:

UN IT:

50-272 Salem 1 DATE: 9715798 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782 later that day. Full power operation continued until August 5, when power was reduced to 64% following the trip of the 12 Steam Generator Feed Pump. Salem Unit 1 returned to full power on August 7, and operated at full power for the remainder of the month.

I I

I

• DOCKET NO.:

UNIT:

50-272 Salem 1 DATE: 9715798 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH: August 1998 The following items completed during August 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

~ured.

• 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 1EC-3306, Pkg. 2, Reactor Protection System (RPS) Signal Low-Low Tavg Nomenclature Change This design change was.implemented to clarify conflicting documentation regarding the RPS LOW Tavg function versus the LOW-LOW Tavg function.

The modification implemented changes to drawings, procedures, and control room bezels to clearly differentiate between the LOW-LOW Tavg function and the LOW Tavg function. The resulting clarifications in functional descriptions will eliminate potential confusion during plant operation.

Review of this modification under 10CFRS0.59 was required because the nomenclature change constituted a change to the facility as described in the Safety Analysis Report (SAR). Because this modification is limited to the clarification of the two RPS functions, and does not affect the function, operation, and setpoint for either function, the review determined that the modification will not increase the probability or consequences of an accident or malfunction of equipment important to safety previously analyzed. Because the change does not add additional equipment or alter the function or operation of the RPS system, the review concluded that the change will not increase the probability of a new accident or a malfunction of equipment important to safety not previously

_j

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

1EE-0189, Pkg. 1, Permanent Installation Of Fuel Elevator Reconstitution Basket This modification provided a permanent replacement of the new fuel elevator carriage with a specially designed reconstitution basket. The reconstitution basket is designed to handle new fuel and support fuel repair activities. The use of the reconstitution basket will prevent interference of the basket with fuel repair tooling.

Review of this modification under 10CFR50.59 was required because the replacement of the reconstitution basket constitutes a change to the facility as described in the Safety Analysis Report (SAR). This review determined that the change did not increase the probability or consequences of an accident previously evaluated in the SAR because the modification is bounded by the existing accident evaluation for a fuel handling accident. The review determined that because the change did not adversely impact the functions of any safety-related systems and components, the change would not increase the probability or consequences of a malfunction of equipment important to safety or create the

. possibility of an accident or malfunction of a different type from any previously evaluated in the SAR. 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.

Minor Modification 597-111, Removal Of The Positioner From Valve 11 SW92, 11 Auxiliary Building Chiller This modification removed the positioner from the 11 SW92 valve, removing the flow modulating capability of valve. This valve is not used for flow modulation and is either fully open or fully shut. 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 the removal of the 11 SW92 positioner constitutes a change to the facility as .

described in the Safety Analysis Report (SAR). This review determined that

because the change does not alter the functionality of the 11 SW92 valve, the change will not increase the probability or consequences of an accident p*reviously evaluated in the SAR, increase the probability or consequences of a malfunction of equipment important to safety, or create the possibility of an accident or 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 August 1998.

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

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

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

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