ML18106A915

Monthly Operating Rept for Sept 1998 for Salem,Unit 2.With 981012 Ltr

ML18106A915
Person / Time
Site:	Salem
Issue date:	09/30/1998
From:	Bakken A, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0479, LR-N98-479, NUDOCS 9810190245
Download: ML18106A915 (4)

Text

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Public Serv[ce Elect,ric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit OCT 12 1998 LR-N98-04 79 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERA TING 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 September 1998 is attached. I Sincerely,

~~

General Manager -

Salem Operations

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

,------9910190245-980930--* - - - - - - \ i

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• 1he power is in your hands.

95-2168 REV. 6/94

DOCKET NO.:

UNIT:

DATE:

50-311 Salem 2 10/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: September 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 720 5456 86662 No. of hours generator was on line (service 720 5343 83407 hours)

Unit reserve shutdown hours 0.0 0.0 0.0 Net Electrical Energy (MWH) 778218 5701426 82877011 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 operated at full power throughout the month of September 1998.

DOCKET NO.:

UNIT:

DATE:

50-311 Salem 2 10/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH: September 1998 The following items completed during September 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 There were no changes in this category implemented during September 1998.

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

Procedures - Summary of Safety Evaluations TSC.CH-AB.CN-1169 (Q), Steam Generator Carryover Testing This safety evaluation reviewed a procedure to be used for the conduct of steam generator carryover testing. This change was evaluated in accordance with 10CFR50.59 because the proposed testing methodology would use lithium hydroxide as the test medium vice sodium 24, and because installation of the test medium injection system required a change to the plant configuration as described in the SAR.

The proposed procedure did not involve an unreviewed safety question because the proposed test methodology and the proposed change to the plant configuration did not increase the probability of a steam generator tube rupture or introduce an accident or malfunction of a different type. In addition, because the test would not result in primary-to-secondary leakage, the margin of safety as defined in the Technical Specifications would not be reduced.

SC.MD-CM.ZZ-0024 (Q) - Revision 3, In-service Single Cell Battery Charging This safety evaluation reviewed Revision 3 to the procedure used during maintenance to connect a single cell battery charger to the station non-vital batteries. This evaluation determined that because the charger was to be used on non-vital batteries, failure of the charger would not increase the probability or consequences of an accident already analyzed; nor create an accident of a different type. Additionally, since the procedure involved non-vital equipment, the change would not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR or reduce the margin of safety as defined in the basis for any Technical Specifications.

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

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

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