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Monthly Operating Rept for Sept 1997 for Salem,Unit 1. W/971015 Ltr
	ML18102B626
Person / Time
Site:	Salem
Issue date:	09/30/1997
From:	Bakken A, Knieriem R, Todd F; Public Service Enterprise Group
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LR-N970681, NUDOCS 9710210281
	Download: ML18102B626 (12)
	v • d • e

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. Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit OCT 15 1997 LR-N970681 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 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly I

operating report for September, 1997, is attached.

Sincerely yours,

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A. C. Bakken III General Manager -

Salem Operations RBK:tcp Enclosures c Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

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DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10/10/97 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 MONTHLY OPERATING

SUMMARY

MONTH SEPTEMBER 1997 The unit is in a refueling and a steam generator replacement outage and remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the unit will remain shutdown pending completion of the following actions:

Appropriately address long standing equipment reliability and operability issues.

After the work is completed, conduct a restart readiness review to determine for ourselves the ability of the unit to operate in a safe, event free manner.

After the restart review, meet with the NRC and communicate the results of that review.

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10/10/97 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 OPERATING DATA REPORT OPERATING STATUS 1 Reporting Period SEPTEMBER 1997 Hours in Report 720 Period 2 Currently Authorized Power Level (MWt) 3411 Max Dependable Capacity (MWe-Net) 1106 Design Electrical Rating (MWe-Net) 1115 3 Power level to which restricted (if any) (MWe Net) None 4 Reason For Restriction (if any)

This Month Yr To Cumulative Date 5 No. of hours reactor was critical 0.0 0.0 104380.5 6 Reactor reserve shutdown hours 0.0 0.0 0.0 7 Hours generator on line 0 0 100338.3 8 Unit reserve shutdown hours 0.0 0.0 0.0 9 Gross thermal energy generated (MWH) 0 0 31806229 10 Gross electrical energy generated (MWH) 0 0 105301000 11 Net electrical energy generated (MWH) -3779 -26247 100148489 12 Unit Service Factor 0. 0% 0.0% 51.9%

13 Unit Availability Factor 0. 0% 0.0% 51.9%

14 Unit Capacity Factor (MDC) O. 0 % 0.0% 46.8%

15 Unit Capacity Factor (DER) 0.0% 0.0% 46.4%

16 Unit Forced Outage Rate 100.0% 100.0% 38.1%

17 Shutdowns scheduled over next 6 months (type, date, duration) :

18 If shutdown at end of report period, estimated date of Startup: Under Review

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10/10/97 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS MONTH SEPTEMBER 1997 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F=FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S=SCHEDULED (HOURS) (1) POWER (2) ACTION/COMMENT 3859 970901 F 720.0 F, c 4 Steam Generator Replacement (1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip 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

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10/10/97 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 AVERAGE DAILY UNIT POWER LEVEL MONTH SEPTEMBER 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10/15/97 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION The following items completed during September 1997 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 lEA-1265, Pkg. 1, Feedwater Thermal Sleeve. This design change installs steam generator feedwater nozzle to piping transition pieces in the Salem Unit 1 replacement steam generators. The change resolves thermal fatigue concerns of steam generator feedwater inlet piping as reported by the NRC via I. E. Bulletin 79-13 and later by NRC Information Notice 93-20.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10/15/97 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEA-1259, Pkg. 1, Steam Generator J-Nozzle Replacement This design change replaced the original carbon steel feed ring J-nozzles in the replacement Westinghouse F Steam Generators that were installed in Salem Unit 1 with J-nozzles made from inconel. The original J-nozzles in service at a number of plants have experienced wall thinning by erosion and corrosion. The original equipment manufacturer has issued technical bulletins on this problem and recommended the replacement.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involv~ an Unreviewed Safety Question.

lEA-1248, Pkg. 1, Rebar Cut For Installation of Motion Restraint Structural arid Runway Beams. This design change is a modification to the Containment Building that was necessary during the Salem Unit 1 Steam Generator replacement. The modification addresses the cutting of rebar in the base mat and in the annular slab that was necessary to accommodate the installation of temporary motion and restraint structures and runaway beams used to facilitate rigging and handling of the steam generators.