ML18102B627

Monthly Operating Rept for Sept 1997 for Salem,Unit 2. W/971015 Ltr

ML18102B627
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-N970682, NUDOCS 9710220117
Download: ML18102B627 (9)

Text

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ublic S~rvice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit OCT 15 1997 LR-N970682 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 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly operating report for September, 1997, is attached.

I Sincerely yours, 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 9710220117 970930 PDR ADOCK 05000311 R PDR

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.us12A8 The power is in your hands.

95-2168 REV. 6/94

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 10/10/97 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 MONTHLY OPERATING

SUMMARY

MONTH SEPTEMBER 1997

• Salem 2 began the month at 17% power in power ascension from outage.

• Salem 2 performed various tests on the digital feedwater system including feed pump trips and associated Rx power runbacks.

• Ended the month at 45% power due to condenser tube leaks.

DOCKET NO.: 50-311 UNIT: Salem 2 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 720 1003 78366.6 6 Reactor reserve shutdown hours 0.0 0.0 0.0 7 Hours generator on line 720 765 75274.5 8 Unit reserve shutdown hours 0.0 0.0 0.0 9 Gross thermal energy generated (MWH) 1612546.8 1612546. 189393551.

10 Gross electrical energy generated (MWH) 488781.0 497011.0 79145609.0 11 Net electrical energy generated (MWH) 458483 367157 75069791 12 Unit Service Factor 10 0. 0% 11.7% 49.9%

13 Unit Availability Factor 100.0% 11.7% 49.9%

14 Unit Capacity Factor (MDC) 57.6% 5.1% 44.7%

15 Unit Capacity Factor (DER) 57.1% 5.0% 44.3%

16 Unit Forced Outage Rate 0.0% 88.3% 33.9%

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

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

DOCKET NO.: 50-311 UNIT: Salem 2 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 ACTION/COMMENT (2)

(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.: 50-311 UNIT: Salem 2 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) 1 170 17 582 2 331 18 790 3 334 19 946 4 39.6 20 987 5 402 21 923 6 419 22 1,036 7 421 23 1,120 8 424 24 1,132 9 437 25 1,132 10 451 26 1,101 11 422 27 927 12 465 28 1,110 13 448 29 1,098 14 477 30 828 15 563 31 N/A 16 532

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 10/15/97 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH SEPTEMBER 1997 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 lEC-3651, Pkg. 1, Modification to Station Air Compressor Controls. This design change improves compressor controls to eliminate cycling of the compressor and reduces air leakage by the addition of an orifice and flow transmitter to the 3rct stage compressor discharge piping and the addition of automatic drain valves to the inter and after cooler drain tanks.

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,

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 10/15/97 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 this design change does not involve an Unreviewed Safety Question.

2EE-0248, Pkg. 1#22 Charging Pump Outboard Mechanical Seal Housing Replacement. This design change replaces the existing water-cooled outboard mechanical seal housing for

1. 22 Charging Safety Injection pump with an air-cooled housing that does not require external cooling connections.

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 involve an Unreviewed Safety Question.

Temporary Modifications Summary of Safety Evaluations There were no changes in this category implemented during September, 1997.

Procedures Summary of Safety Evaluations Procedure NC.NA-AP.ZZ-0002(Q)/Revision 2, Nuclear Business Unit Organization This change shifts responsibilites within the Salem Operations Department, revises the Salem Operations Organization succession of authority and changes titles in both the Hope Creek and Salem Oeprations Departments.

This procedure revision does not negatively impact any accident response. This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.

Therefore, this procedure revision does not involve an Unreviewed Safety Question.

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 10/15/97 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 UFSAR Change Notices Summary of Safety Evaluations UFSAR Change Notice 96-13, Post Accident Sampling System (PASS)

This change reconciles the UFSAR with the current configuration of the PASS to reflect that the containment air sample lines do not require heat tracing to prevent iodine plateout and that he PASS sampling lines and components meet or exceed the quality group and seismic classification requirements that are consistent with NRC guidance on PASS.

This UFSAR 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 involve an Unreviewed Safety Question.

UFSAR Change Notice 97-117, Nuclear Operations Department Organization Change This change shifts responsibilities for the Nuclear Security and the Loss Prevention Organizations within the Nuclear Operations Department. The change shifts the reporting relationship for these organizations from the General Manager - Nuclear Maintenance to the General Manager - Hope Creek Operations for the Loss Prevention Organization; and the General Manager - Salem Operations for the Nuclear Security Organization.

This UFSAR 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 involve an Unreviewed Safety Question.

.I DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 10/15/97 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Deficiency Reports Surrunary of Safety Evaluations There were no changes in this category implemented during September, 1997.

Other Summary of Safety Evaluation There were no changes in this category implemented during September, 1997.