ML18101B174

Monthly Operating Rept for Dec 1995 for Salem Generating Station Unit 1.W/960115 Ltr

ML18101B174
Person / Time
Site:	Salem
Issue date:	12/31/1995
From:	Heller R, Phillips R, Warren C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GMS-96-0010, GMS-96-10, NUDOCS 9601190269
Download: ML18101B174 (8)

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• 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 GMS-96-0010 January 15, 1996 In compliance with Section 6.9.1.6J Reporting Requirements for the Salem Technical Specifications, the original copy of 1 the monthly operating report for the month of December is being sent to you. RH:vls Enclosures C Mr. Thomas T. Martin General Manager -Salem Operations Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 9601

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PDR ADOCK 05000272 R PDR 190C43 The power is in your hands. 95-2168 REV. 6/94 o T AVERA. DAILY UNIT POWER LEVEL

• Docket No.: 50-272 Unit Name: Salem #1 Date: 01/10/96 Completed by: Robert Phillips Telephone:

339-2735 Month December 1995 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 P. 8.1-7 Rl

• OPERATING DATA REPORT

• Docket No: Date: Completed by: Robert Phillips Telephone:

Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period December 1995 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) Report, Give Reason NA 9. Power Level to Which Restricted, if any (Net MWe) 10. Reasons for Restrictions, if any 12. 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 744 . 0 0 0 0 0 0 -2639 0 0 0 0 0 NA Year to Date 8760. 2660.9 0 2632.1 0 8010326.4 2689850 2522749 30.0 30.0 26.0 25.8 56.3 50-272 01/l0/96 339-2735 since Last N/A Cumulative 162217 104380.5 0 100388.3 0 318062229.2 105301000 100204913 61.8 6L8 55.8 55.4 22.9 24. Shutdowns scheduled over next 6 months (type, date and duration of each) We are presently in a scheduled extension of refueling outage. 25. If shutdown at end of Report Period, Estimated Date of startup: Under review. 8-l-7.R2 NO. DATE 3642 12-1-95 s 3824 12-14-95 s 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 312 c 432 c Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction 4 4 UNIT SHUTDOWN AND POWER .REDUCTIONS REPORT MONTH December 1995 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT # ---------zz ---------zz 3 Method: 1-Manual 2-Manual Scram SYSTEM CODE 4 E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)

H-Other (Explain)

COMPONENT CODE 5 DOCKET NO. :

__ _ UNIT NAME: Salem #1 DATE: 01/10/96 COMPLETED BY: Robert Phillips TELEPHONE:

609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE zzzzzz Refueling Outage zzzzzz Scheduled extension to refueling outage 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File 5 Exhibit 1 -Same Source . . ' (NUREG-0161)

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• 10CFR50.59 EVALUATIONS MONTH: DECEMBER 1995 DOCKET NO: UNIT NAME: 50-272 SALEM 1 01/10/96 R.HELLER 609-339-5162 DATE:

• COMPLETED BY: TELEPHONE:

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.

1. Design Change Packages (DCP) lEC-3322, Pkg. 4 lEC-3323, Pkg .. 2 "Service Water Pipe Replacement

-Auxiliary Building Nuclear Header i2" Rev. 0 -This package replaces portions of the supply and return piping for 12A and 12B Component Cooling Exchanger (CCHX) from the 12 Service Water (SW) header. It replaces carbon steel cement or coal tar epoxy lined pipe (spec. 27C) with 6% molybdemiin austenitic stainless steel pipe (spec. 27F) and maintains the current pipe routing. This package replaces portions of the SW supply and return headers for 12A and 12B CCHX in the Auxiliary building at floor elevation 84'-0." There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95.-108) "Service Water Large Bore Pipe-Replacement" Rev. 2 -This modification upgrades the material for Service Water (SW) system piping. Due to corrective maintenance activities on valve 13 SW20 and the current system outage schedule constraint, it is necessary to establish an interim system configuration and boundaries without 13 SW20 to facilitate the restoration of the No. 12 SW Header. The system will be restored to original flow configuration by re-installing the refurbished 13 SW20 valve and the associated p.iping spools during a later header 12 outage with completion of SW DCP, lEC-3323, Pkg. 3, Rev. 1. The interim configuration, by replacing the turbine crosstie isolation valve with a blind flange, maintains the design basis and safety related function of the system. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-146)

• 10CFR50.59 EVALUATIONS MONTH: DECEMBER 1995 DOCKET NO: UNIT NAME: 50-272 SALEM 1 01/10/96 (Cont'd) 4. Safety Evaluation (S/E) W/O 940524110 DATE: COMPLETED BY: TELEPHONE:

R. HELLER 609-339-5162 "Freeze Seal of the Spray Additive Tank (SAT) Sample Line to Valve 1CS30" -The proposal is to install a temporary freeze seal on the 3/4", stainless steel, Spray Additive Tank (SAT) local sample line, upstream of the sample isolation valve, 1CS30. The installation of a freeze seal will allow approximately 4000 gallons of30% wt. Sodium Hydroxide (NaOH) solution to remain in the SAT (1CSE5) while maintenance of the sample line isolation valve is performed.

The only components affected are part of the Containment Spray System. As the Containment Spray System is not required to be operable in Modes 5, 6 or defueled, and this proposal will only be used during these modes, the margin of safety as defined in the bases of the Technical Specifications will not be compromised. (SORC 95-152)

• REFUELING INFORMATION MONTH: DECEMBER 1995 MONTH : DECEMBER 1995

• DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 01/10/96 R.HELLER 609-339-5162 Refueling information has changed from last month: YES . X . NO ..._. Scheduled date for next refueling:

09/10/95 Scheduled date for restart following refueling:

06/30/96 a. Will Technical Specification changes or other license amendments be required?

YES.

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 ) Scheduled date(s) for submitting proposed licensing action: . n/a Important licensing considerations associated with refueling:

Number of Fuel Assemblies: .a. Incore b. In Spent Fuel Storage Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

8-l-7.R4 0 1005 1632 1632 September 2008

• SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 1 DECEMBER 1995 SALEMUNITNO.

1 The Unit is in a refueling outage and remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, both Units will remain shutdown pending completion of the following actions: e 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 each Unit to operate in a safe, event free manner

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