ML18102A928

Monthly Operating Rept for Feb 1997 for Salem,Unit 1. W/970311 Ltr

ML18102A928
Person / Time
Site:	Salem
Issue date:	02/28/1997
From:	CONICELLA N, GARCHOW D F, PHILLIPS R, TISDALL D Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703240182
Download: ML18102A928 (8)

Text

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 1 DOCKET NO: 50-272 March 11, 1997 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly operating report for the month of February is being sent to you. VS:pc Enclosures

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,! /.., L V '--C Mr. H.J. Miller Regional Administrator USNRC, Regionl 4 7 5 Allendale Road King of Prussia, PA 19046 ---9703240182 970228 PDR ADOCK 05000272 R PDR The pOtVer is in }Dllf hands. (jjy;ms, David F.

General Manager -Salem Operations

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• 95-2168 REV. 6/94 e e , 10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: FEBRUARY 1997 NAME: UNITl CONTACT: N. CONICELLA TELEPHONE:

609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.

The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE (No 50.59 S/E) lEA-1134 Pkg. 1, Rev. 0 on addition of Station Air Valves 1SA549 and 1SA550 in Auxiliary Building and Valves 1 SA541 through 1 SA548 50.59 S/E S97-026, lEA-1126, Pkg. 1, Rev. 0 As-Built SGFP Suction Strainer Cleanout Valves, 11CN926 & 12CN926 50.59 S/E S97-032, lEC-3486 Pkg. 2, Rev. 1 OCFR50 Appendix R alternate Shutdown Methodology

-Installation of Transfer Switches 50.59 S/E S97-043, lEC-3495, Rev. 2 on Steam Trap Replacement Project This modification provides as-built documentation for the non-safety related portion of the station air in the auxiliary building, turbine building and in the clean facilities building.

SORC: 97-022 This DCP provides as-built documentation for valves 11 CN926 and 12CN926. The valves provide for controlled manual blowdown of strainers at the suction of both Unit 1 SGFP's. SORC: 97-021 This modification addresses concerns regarding the Alternate Shutdown Methodology at Salem in the event of a Control Room evacuation due to fire in the Control Room, Relay Room, or ceiling area of the 460/230 Volt Switchgear Room, which calls for the use of electrical wiring modifications and jumpers. SORC: 97-019 In order to enhance system performance and eliminate high maintenance components, twenty seven steam traps (1MSE21through1MSE35 and 1MSE38 through 1MSE49) and associated bypass orifices (where presently installed), bypass valve(s), drain valves and isolation valves will be removed (except four isolation valves required by procedure for Steam Generator Tube Rupture) and are being replaced.

SORC: 97-025

. ' e e , lOCFRS0.59 EVALUATIONS DOCKET NO: 50-272 MONTH: FEBRUARY 1997 NAME: UNITl CONTACT: N. CONICELLA TELEPHONE:

609-339-2124 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.

The Station Operations Review Committee has reviewed and concurs with these evaluations DESIGN CHANGE PACKAGE 50.59 SIB S97-049, lEC-3620, Pkg. 1, Rev. 0 on Letdown Isolation Valve Bypass Key switch 50.59 SIB S97-058, lEC-3648, SSPS Phase A and containment Ventilation Isolation Modification PROCEDURE 50.59 SIB S97-023, SU.CC-0003(Q), Rev. O "Component Cooling Pump Performance with 11CC16 & 12CC 16 Throttled" SAFETY EVALUATION This proposal will revise Section 5.6.4 and Figure 7.2-5 of the UFSAR to describe the new bypass circuitry of the low pressurizer level isolation signal so that operator control of the letdown isolation valves is possible during steam generator tube rupture conditions.

SORC: 97-025 This modification adds relays and additional Main Control Room pushbuttons to both Train A and Train B to allow manual initiation of Containment Ventilation Isolation separately from Phase A Containment Isolation.

SORC: 97-028 This procedure describes an "experimental" test which will demonstrate if the CC system is capable of reaching pump run-out flow and also whether the CC pump and motor are capable of surviving at maximum pump flow. SORC: 97-017 50.59 SIB S96-047, S.C.ZZ-ESE-This safety evaluation addresses separation of the free air cables installed in 0841 Rev. 1 Separation distance the Salem Relay Rooms. of cables in free air installed in SORC: 96-099 Salem U/1 and U/2 relay rooms 1*

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OPERATING DATA REPORT Docket No: 50-272 Date: 03/10/97 Completed by: Robert Phillips Telephone:

339-2735 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period February 1997 3. Licensed Thermal Power (MWt) 3411 4. Nameplate Rating (Gross MWe) 1170 5. Design Electrical Rating (Net MWe) 1115 6. Maximum Dependable Capacity(Gross MWe) 1149 7. Maximum Dependable Capacity (Net MWe) 1106 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA 9. Power Level to Which Restricted, if any (Net MWe) N/A 10. Reasons for Restrictions, if any

11. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) 17. Gross Elec. Energy Generated (MWH) 18. Net Elec. Energy Gen. (MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate This Month 672 0 0 0 0 0 0 -2446 0 0 0 0 100 Year to Date 1416 0 0 0 0 0 0 -5470 0 0 0 0 100 Cumulative 172417 104380.5 0 100388.3 0 318062229 105301000 100169266 58.2 58.2 52.5 52.1 27.0 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Steam Generator replacement.

25. If shutdown at end of Report Period, Estimated Date of startup: Under review. 8-1-7.R2

DAILY UNIT POWER LEVEL tt Docket No.: 50-272 Unit Name: Salem #1 Date: 03/10/97 Completed by: Robert Phillips Telephone:

339-2735 Month February 1997 Day Average Daily Power Level (MWe-NET)

Day Average Daily Power Level (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 14 0 30 15 0 31 16 0 P. 8.1-7 Rl NO. DATE 4092 2-1-97 1 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 F 744 F.C UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH February 1996 METHOD OF SHUTTING LICENSE DOWN EVENT REACTOR REPORT # SYSTEM CODE 4 4 -----------

2422 2 3 Reason A-Equipnent Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction E-Operator Training & License Examination F-Adninistrative G-Operational Error (Explain)

H-Other (Explain)

Method: 1-Manual 2-Manual Scram 3*Automatic Scram 4-Continuation of Previous Outage S*Load Reduction 9*0ther 4 DOCKET NO.: _,s,,.,o..,.-3:.1...,1:.,,....---s*

• -* UNIT NAME: _s,..a .... l""em"-""#""'l

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__ COMPLETED BY: Robert.Phillips TELEPHONE:

609-339-2735 COMPONENT CAUSE AND CORRECTIVE ACTION CODE 6 TO PREVENT RECURRENCE Steam Generator Replacement Exhibit G

• Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG*0161) 5 Exhibit 1

• Same Source _J Refueling Information Month: February, 1997 Month: February, 1997

• Docket No. 50-272 Unit Name: Salem 1. Contact: D.Tisdall Telephone:

609-339-1538

1. Refueling information has changed from last month: Yes: No: X 2. Scheduled date for next refueling:

To Be Determined Scheduled date for restart following refueling:

To Be Determined

3. a. Will Technical Specification changes or other license amendments be required?

Yes: No: Not Determined to Date: X b. Has the reload fuel design been reviewed by the Station Operating Review committee?

Yes: No: X If no, when is it scheduled?

To be Determined

4. Scheduled date (s) for submitting proposed licensing action: N/A 5. Important licensing considerations associated with refueling:

6. Number of Fuel Assemblies:

a. lncore: 0 b. In Spent Fuel Storage: 953 7. Present Licensed spent fuel storage capacity:

1632 Future spent fuel storage capacity:

1632 8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

April 2012 I I I _ _J SALEM UNIT 1 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 1 FEBRUARY 1997 The unit is in a refueling and 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 nit to operate in a safe, event free manner.

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