ML18106A875

Monthly Operating Rept for Aug 1998 for Salem Generating Station,Unit 2.With 980915 Ltr

ML18106A875
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-N98-0436, LR-N98-436, NUDOCS 9809230024
Download: ML18106A875 (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

.SEP 15 1998 LR-N98-0436 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 August 1998 is attached.

Sincerely,

!Jj~f!eb 1l/c~r=kken Ill General Manager -

Salem Operations

/rbk Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 4 75 Allendale Road

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*------ ______ !5ing_~tP1ussia, PA 19046 9809230024 980831 PDR ADOCK 05000311 R PDR The power is in your hands. ,~ ... " ; . r,, 1_

95-2168 REV. 6/94

• v DOCKET NO.: 50-311 UNIT: Salem 2 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 545 4736 85942 No. of hours generator was on line (service 524 4623 82687 hours)

Unit reserve shutdown hours 0.0 0.0 0.0 Net Electrical Energy (MWH) 551651 4923208 82098793 UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CO,RRECTIVE F=FORCED (HOURS) (1) SHUTTING ACTION/COMMENT S=SCHEDULED DOWN THE REACTOR (2)

• 4 8/1/98 F 220 B 1 Pressurizer Safety Valve

- Replacement 8/10/98 (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 August 1998 shutdown to replace three pressurizer safety valves and to conduct various technical specification surveillances. This shutdown was completed on August 10. Salem Unit 2 returned to full power on August 11, and operated at full power for the remainder of the month.

• DOCKET NO.:

UNIT:

50-311 Salem 2 DATE: 915/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH: August 98 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 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-0189, Pkg. 1, Replacement Of Pressurizer Safety Valves 2PR3, 2PR4,

• I and 2PR5.

This modification replaced the existing seismic category I, safety-related Unit 2 Pressurizer Safety Valves (PSVs) 2PR3, 2PR4, and 2PR5 with new seismic category I safety-related valves meeting the requirements of ASME Section Ill, Class A, 1968 Edition through S68 Addendum. The replacement valves

• maintained the same internals and performance characteristics as the existing valves but differ with regard to the valve body and bolting arrangement. The installation of the new valves also incorporated new position indicators of a more reliable and modern design.

Review of this modification under 10CFR50.59 was required because the replacement of the PSVs constituted 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 the consequences of an accident previously evaluated in the SAR because the modification is bounded by existing accident evaluations. The review concluded that the change would not increase the

probability or the consequences of a malfunction of equipment important to safety and would not create the possibility of an accident or malfunction of a

~iffere!lt type from any previously evaluated in the SAR, because the change did not modify the operation or the design basis function of any safety equipment.

Because the change did not affect the existing analysis that forms the basis for "the Technical Specifications, and will not violateTechnical 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.

2EE-0327, Elimination Of Reactor Coolant System (RCS) Valve Stem Leakoff Lines This modification eliminated the valve stem leak-off lines from valves 2PS1, 3, 24, 25, 28, 29; and 2PR6, and 2PR7 in the Salem Unit 2 Coolant Pressurizing

• and Pressure Relief systems in order to reduce identified RCS leakage to the Pressurizer Relief Tank (PRT).

Review of this modification under 10CFR50.59 was required because the elimination of the RCS system valve stem leakoff lines constituted 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 or the malfunction of equipment important to safety previously

• evaluated in the SAR because the modification is bounded by existing accident evaluations. The review concluded that the modification would not create the possibility of an accident or malfunction of a different type from any previously*"

evaluated in the SAR, because the change did not adversely impact the function of the valves that were modified. The modification eliminated the routing of any

• potential valve packing leakage* to the PRT. 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

)here .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.