ML18101B173

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

ML18101B173
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-96-0011, GMS-96-11, NUDOCS 9601190220
Download: ML18101B173 (7)

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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. 2 DOCKET NO: 50-311 GMS-96-0011 January 15, 1996 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating report for the month of December is being sent to you. RH: vis Enclosures C Mr. Thomas T. Martin General Manager -*Salem Operations Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 ------960119*5220

-951281 ----PDR ADOCK 05000311 R PDR The power is in your hands. 95-2168 REV. 6/94

DAILY UNIT POWER Docket No.: 50-311 Unit Name: Salem #2 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 e Docket No: Date: Completed by: Robert Phillips Telephone:

Operating Status 1. Unit Name Salem No. 2 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 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) 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 -3638 0 0 0 0 0 NA Year to Date 8760 2468.4 0 2261.6 0 6807220.8 2198890 2017510 25.8 25.8 20.8 20.6 65.4 50-311 01/10/96 339-2735 since Last N/A Cumulative 124633 78083.6 0 75229.5 0 187781005 78648898 74741054 60.4 60.4 54.2 53.8 24.6 24. Shutdowns scheduled over next 6 months (type, date and duration of each) We are presently in a scheduled refueling outage. 25. If shutdown at end of Report Period, Estimated Date of Startup: Under review. 8-1-7.R2 NO. DATE 3780 12/01/95 s 1 2 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH December, 1995 DURATION TYPE 1 (HOURS) REASON 2 744 c Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction METHOD OF SHUTTING DOWN REACTOR 4 E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain)

LICENSE EVENT SYSTEM REPORT # CODE 4 .. -------zz 3 Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE 5 DOCKET NO.: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-311 Salem #2 01-10-96 Robert Phillips 609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE zzzzz Refueling Outage 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -same Source -

10CFR50.59 EVALUATIONS MONTH: DECEMBER 1995 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50 ... 311 SALEM2 01/10/96 R.HELLER 609-339-5162 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) 2EE-0089, Pkg. 1 No. 26 Service Water Pump Replacement" Rev. 0 -This DCP will install a new pump in the No. 26 Service Water Pump position.

The existing pump was designed with encapsulation around the bowl assemblies and the replacement pump is. essentially the same but is designed without encapsulation.

This modification conforms with current ASME standards and meets the system operating requirements.

There is no reduction in the margin of safety as described in the basis for any Technical Specification. (SORC 95-073)

. ' REFUELING INFORMATION MONTH: DECEMBER 1995 MONTH: DECEMBER 1995 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-311 SALEM2 01/10/96 R. HELLER 609-339-5162

1. Refueling information has changed from last month: YES . X . NO .:....* _ _____,_ 2. Scheduled date for next refueling:

11/02/95 Scheduled date for restart following refueling:

09/30/96 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)

5. Scheduled date(s) for submitting proposed licensing action: . n/a 6. Important licensing considerations associated with refueling:

7. Number of Fuel Assemblies:

a. Incore b. In Spent Fuel Storage 8. Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

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

8-l-7.R4 0 749 1632 1632 March 2012

.. SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 2 DECEMBER 1995 SALEM UNIT NO. 2 The Unit 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:

• Appropriately address long standing equipment reliability and operability issues o 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