ML18106A715

Monthly Operating Rept for June 1998 for Salem,Unit 2. W/980715 Ltr

ML18106A715
Person / Time
Site:	Salem
Issue date:	06/30/1998
From:	Bakken A, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0334, LR-N98-334, NUDOCS 9807210201
Download: ML18106A715 (4)

Text

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• Public Sr;irvice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit LR-N98-0334 July 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 t9r the Salem Technical I

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

Sincerely, dal~

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

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• 1he power 1s in your hands.

95-2168 REV. 6/94

DOCKET NO.:

UNIT:

DATE:

50-311 Salem 2 7/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: June 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 3610 84817 No. of hours generator was on line (service 720 3520 81583 hours)

Unit reserve shutdown hours 0.0 0.0 0.0 Net Electrical Energy (MWH) 764665 3751393 80926978 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 June operating at full power. Full power operation continued until June 7, when load was reduced to 25% to replace an oil level switch on the 23 Reactor Coolant pump. The unit returned to full power on June 9, and continued full power operation until June 26, when power was reduced to 95% following a Moisture Separator Reheater isolation. The unit returned to full power on June 28, and operated at full power for the remainder of the month.

DOCKET NO.:

UNIT:

DATE:

50-311 Salem 2 7/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH: June 1998 The following items completed during June 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 Minor Modification S98-010, Unit 2 Auxiliary Feedwater Storage Tank (AFST) Nitrogen Blanket Vent Orifice This modification provided a vent orifice in the vent of the Salem 2 AFST to allow for the purging of air and to allow a constant flow of nitrogen 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.

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

Procedures - Summary of Safety Evaluations Salem Emergency Plan, Section 15, Revision 5 This change revised Section 15 of the Emergency Plan to clarify how the PSE&G Nuclear Business Unit will conduct accountability drills and defines "limited" accountability.

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.

UFSAR Change Notices - Summary of Safety Evaluations Salem UFSAR Change Notice S98-020, Section 13.5, Administrative Procedures This UFSAR Change Notice modified section 13.5 of the Salem UFSAR to make it consistent with the Hope Creek UFSAR with regard to the administrative.

procedure sections and descriptions.

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.

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

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