Text

Monthly Operating Rept for Oct 1997 for Salem,Unit 2.W/ 971117 Ltr
	ML18102B681
Person / Time
Site:	Salem
Issue date:	10/31/1997
From:	Bakken A, Knieriem R, Todd F; Public Service Enterprise Group
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LR-N970753, NUDOCS 9711250127
	Download: ML18102B681 (10)
	v • d • e

.. e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit NOV 171997 LR-N970753 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 October, 1997, is attached. Included with this report is a table containing revised Net Electrical Energy Generated data. This table corrects 1997 data that was provided in previous reports.

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

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The power is in your hands.

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SALEM GENERATING STATION DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 11/15/ 97 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 MONTHLY OPERATING

SUMMARY

- UNIT 2 OCTOBER 1997 Salem Unit 2 began the month of October operating at full power. On October 2, at 0713, the unit was manually tripped following the loss of both operating Steam Generator Feed Pumps. The cause of the loss of feedwater was isolated to the failure of a temporary data acquisition device connected to monitor feedwater control system performance. This event was reported in Licensee Event Report 311/97-014-00 on 10/31/97.

Unit 2 returned to service on October 6, and remained in service for the remainder of the month.

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 11/06/97 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 OPERATING DATA REPORT OPERATING STATUS 1 Reporting Period OCTOBER 1997 Hours in Report 745 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 Mdnth Yr To Cumulative Date 5 No. of hours reactor was critical 656 1659 79743 6 Reactor reserve shutdown hours 0.0 0.0 0.0 7 Hours generator on line 641 1405 76635 8 Unit reserve shutdown hours 0.0 0.0 0.0 9 Gross thermal energy generated (MWH) 1853218 3465765 191246770 10 Gross electrical energy generated (MWH) 599322 1096333 79744931 11 Net electrical energy generated (MWH) 567312 934469 75637103 12 Unit Service Factor 86.0% 19.3% 48.7%

13 Unit Availability Factor 86.0% 19.3% 48.7%

14 Unit Capacity Factor (MDC) 68.9% 11.6% 43.5%

15 Unit Capacity Factor (DER) 68.3% 11.5% 43.1%

16 Unit Forced Outage Rate 14.0% 80.7% 33.8%

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: 11/06/97 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS MONTH OCTOBER 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) 3408 10/2 F 104.2 A - 2 Manual trip

- Feed following the 10/6 Pump loss of both Trip feed pumps.

Loss of feed caused by failed temporary data acquisition device. LER 311/97-014-00, 10/31/97 (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: 11/06/97 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 AVERAGE DAILY UNIT POWER LEVEL MONTH OCTOBER 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 688 17 1083 2 294 18 1088 3 0 19 1092 4 0 20 1094 5 0 21 1101 6 10 22 1101 7 212 23 1101 8 319 24 1101 9 325 25 1102 10 317 26 1103 11 305 27 1094 12 599 28 1101 13 1027 29 1103 14 1071 30 1104 15 1079 31 1103 16 1087

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 11/06/97 COMPLETED BY: F. Todd TELEPHONE: ( 609) 339-1316 OPERATING DATA REPORT Revised Net Electrical Energy Generated Listed below are the monthly, year-to-date and cumulative figures for the 1997 Net Electrical Energy Generated:

MONTH YEAR-TO-DATE CUMULATIVE January -6303 -6303 74696331 February -9429 -15732 74686902 March -7465 -23197 74679437 April -7074 -30271 74672363 May -7624 -37895 74664739 June -13045 -50940 74651694 July -22587 -73527 74629107 August -17799 -91326 74611308 September 458483 367157 75069791

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 11/15/97 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH OCTOBER 1997 The following items completed during October 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 2EC-3178, Pkg. 1, Analog Feedwater Control System Replacement This modification replaced the existing analog f eedwater control system with an Advanced Digital Feedwater Control System (ADFCS) . The ADFCS was installed to provide operators with a more reliable design that will reduce the number of plant trips due to f eedwater control system malfunctions.