ML18101A893

Monthly Operating Rept for Jul 1995 for Salem Unit 2.W/ 950814 Ltr

ML18101A893
Person / Time
Site:	Salem
Issue date:	07/31/1995
From:	Phillips R, Warren C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9508180005
Download: ML18101A893 (7)

Text

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• Public S(:lrvice 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 August 14, 1995 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of July are being sent to you. RH:vls Enclosures C Mr. Thomas T. Martin Sincerely

yours, General Manager -Salem Operations Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 8-1-7.R4 The power is in your hands. 9508180005 950731 PDR ADOCK 05000311 R PDR ' I

DAILY UNIT POWER Docket No.: 50-311 Unit Name: Salem #2 Date: 08-10-95 Completed' by: Robert Phillips Telephone:

339-2735 Month July 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 L Unit Name Salem No. 2 Notes 2 0 Reporting Period July 1995 3 0 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 N A 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. N,et 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 NA This Month Year to Date 744 5087 0 2468.4 0 0 0 2261.6 0 0 0 6807220.8 0 2198890 -12775 2041100 0 44.5 0 44.5 0 36.3 0 36.0 100 47.0 50-311 08/10/95 339-2735 since Last N/A Cumulative 120960 78083.6 0 75229.5 0 187781005 78648898 74764644 62.2 62.2 55.9 55.4 22.9 24. Shutdowns scheduled over next 6 months (type, date and duration of each) To be determined.

25. If shutdown at end of Report Period, Estimated Date of Startup: To be determined.

8-1-7.R2 NO. DATE 2692 7-1-95 F 1 2 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1995 DURATION TYPE 1 (HOURS) REASON 2 744 A Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refuel ing 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 -----------

SH 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 . 8-10-95 Robert Ph fl lips 609-339-2735 . CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE CKTBRK BREAKER FAILURE 1-9 500KV 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -Same Source *

• 10CFRSQ:59 EVALUATIONS M'ONTH: JULY 1995 DOCKET NO: UNIT NAME: 50-311 SALEM2 08/10/95 R.HELLER 609-3 3 9-5162 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) The reporting ofDCP related 10CFR50.59 evaluations is being modified to address these items only after they have been implemented and turned over to Operations.

For the next several months, during this transition phase, we anticipate few new DCPs to report. 2. Temporary Modifications (T-Mod)95-048 "Installation of Blind Flange on Downstream Side of Process Stream of Spent Fuel Pit Heat Exchanger" Rev. 0 -This T-Mod is for installation of blind flange on downstream side of process stream of spent fuel pit heat exchanger to allow isolation of No. 2 spent fuel pit heat exchangers to allow maintenance to be performed.

The downstream piping does not have a means of isolation when the cross-tie is in operation.

1SFE12 and 2SFE12 (No. 1 and 2 spent fuel pit heat exchangers) will be isolated by installation of the blind flange on the downstream piping and by closing upstream isolation valves. The required minimum depth of water above the top of the irradiated fuel assemblies (23 ft) will be maintained during implementation or use of the T-Mod. The location of anti-siphon holes on the return piping will limit the loss of pool water inventory by gravity for any gross failures.

Similarly, the basis for the fuel handling area ventilation system or margins of safety will not be altered by the isolation of the Unit 2 SFP heat exchanger.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-077)

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* REFUELING INFORMATION JULY 1995 MONTH: JULY 1995

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

50-311 SALEM2 08/10/95 R.HELLER 609-3 3 9-5162 1. Refueling information has changed from last month:

NO 2. Scheduled date for next refueling: (to be determined)

Scheduled date for restart following refueling:

2nd quarter 1996 3. a. Will Technical Specification changes or other license amendments be required?

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: ____

___ _ 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:

8-1-7.R4 _193 __ 556 1632 1632 March 2012

• SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 2 JULY 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

• 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