ML18102B681

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)

Text

L .. e 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. RBK:tcp Enclosures C Mr. H. J. Miller Sincerely yours, A. C. Bakken III General Manager -Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 9711250127 971031 PDR ADOCK 05000311 R PDR The power is in your hands. ,-, ,.; "::: 'l *j ,,,, ... I llllll lllll lllll llllll llll llllll Ill llll ' * & & 4 0 8 E

• 95-2168 REV. 6/94

... SALEM GENERATING STATION DOCKET NO.: 50-311 MONTHLY OPERATING

SUMMARY

-UNIT 2 OCTOBER 1997 UNIT: Salem 2 DATE: 11/15/ 97 COMPLETED BY: R. Knieriem TELEPHONE:

(609) 339-1782 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 Period 2 Currently Authorized Power Level (MWt) Max Dependable Capacity (MWe-Net)

Design Electrical Rating (MWe-Net) 3 Power level to which restricted (if any) (MWe Net) 4 Reason For Restriction (if any) This Mdnth Yr To Date 5 No. of hours reactor was critical 6 Reactor reserve shutdown hours 7 Hours generator on line 8 Unit reserve shutdown hours 9 Gross thermal energy generated (MWH) 10 Gross electrical energy generated (MWH) 11 Net electrical energy generated (MWH) 656 0.0 641 0.0 1853218 599322 567312 1659 0.0 1405 0.0 3465765 1096333 934469 12 Unit Service Factor 86.0% 19.3% 13 Unit Availability Factor 86.0% 19.3% 14 Unit Capacity Factor (MDC) 68.9% 11.6% 15 Unit Capacity Factor (DER) 68.3% 11.5% 16 Unit Forced Outage Rate 14.0% 80.7% 17 Shutdowns scheduled over next 6 months (type, date, duration)

18 If shutdown at end of report period, estimated date of Startup: 745 3411 1106 1115 None Cumulative 79743 0.0 76635 0.0 191246770 79744931 75637103 48.7% 48.7% 43.5% 43.1% 33.8%

DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:

OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS 50-311 Salem 2 11/06/97 F. Todd (609) 339-1316 MONTH OCTOBER 1997 TYPE F=FORCED DURATION NO. DATE S=SCHEDULED (HOURS) 3408 10/2 F 104.2 -10/6 (1) Reason A -Equipment Failure (Explain) B -Maintenance or Test C -Refueling D -Regulatory Restriction REASON ( 1) A -Feed Pump Trip E -Operator Training/License Examination F -Administrative G -Operational Error (Explain) H -Other METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING CORRECTIVE POWER ACTION/COMMENT (2) 2 Manual trip following the loss of both feed pumps. Loss of feed caused by failed temporary data acquisition device. LER 311/97-014-00, 10/31/97 (2) Method 1 -Manual 2 -Manual Trip 3 -Automatic Trip/Scram 4 -Continuation 5 -Other (Explain)

DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:

50-311 Salem 2 11/06/97 F. Todd (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.: UNIT: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH OCTOBER 1997 50-311 Salem 2 11/15/97 R. B. Knieriem (609) 339-1782 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.

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.

2EC-3336, Pkg. 1, Feed Pump Recirculation System Upgrade This design change modified the feed pump recirculation piping and enhanced feed pump recirculation control. This was done to minimize erosion in feed pump recirculation piping and valves; and to reduce feedwater system startup flow transients.

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.

2EC-3353, Pkg. 1, Replacement of Low Pressure Turbine Rotors With A Fully Integral Design This design change involved the replacement of the existing Low Pressure Turbine rotors with new Mono-block Design rotors. 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.

2EC-3449, 1, Steam Generator Tube leak Detection Main Steam Line N Monitors This design change installed N 16 radiation monitors that will provide operations personnel with enhanced ability to identify and respond to a Steam Generator tube leak. 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.

2EC-3554, Pkg. 1, Heater Drain Pump Start and Heater Drain < Valve Open Interlock Modification This design change modified the controls for the Bleed Steam Heater Drain pump discharge valve to prevent the Feedwater Heater and Moisture Separator Reheater Drain Tanks from draining down too rapidly during Bleed Steam Heater Drain pump startup. 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.

2EC-3264, Pkg. 1, Steam Generator Level Sensing Line Modification This design change modified the Steam Generator narrow and wide range instrumentation sensing lines to ensure that allowable stress limits are not exceeded.

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 October, 1997. Procedures Summary of Safety Evaluations EPlan 11, Rev. 8 & EPIP 902, Rev. 17. This procedure change alters the backup method of performing protected area accountability.

The change will allow badged personnel to take their accountability card home with their site security badge. 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.

SC.MD-EU.DG-003(Q), Rev 1, Astro-Med Recorder/Equipment Setup For Emergency Diesel Generator Related Surveillance Testing. This procedure change provides test equipment and test equipment setup that will allow an Emergency Diesel Generator (EDG) train to remain operable during its monthly Technical Specification Surveillance Test. 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.

' .. UFSAR Change Notices Summary of Safety Evaluations UFSAR Change Notice 97-08, Main Steam Flow Transmitter Time Response.

This Change Notice changes the UFSAR description of the steam flow transmitters to reflect a modification performed on the steam flow transmitters to provide variable dampening.

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.

Deficiency Reports Summary of Safety Evaluations Other There were no changes in this category implemented during October, 1997. Summary of Safety Evaluation Safety Evaluation S97-254, Revised Technical Specification Bases 3/4.1.3, Movable Control Assemblies This Technical Specification Bases change involves a change to the bases section to allow use of the plant computer as a rod position indicator.

The current bases section describes rod position indication but is not specific as to what indicators satisfactorily meet Technical Specification Requirements.

The plant computer receives the same input from the Analog Rod Position Indication system as does the Control Console indicators and provides resolution equivalent to or better than the Control Console indicators.

This Technical Specification Bases change does not negatively impact any accident response.

It does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this Technical Specification Bases change does not involve an Unreviewed Safety Question.