ML18101A893

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Monthly Operating Rept for Jul 1995 for Salem Unit 2.W/ 950814 Ltr
ML18101A893
Person / Time
Site: Salem PSEG icon.png
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)
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  • Public S(:lrvice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit August 14, 1995 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 2 DOCKET NO: 50-311 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.

Sincerely yours, 4.,:!Pr~n-General Manager -

Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin 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 ' I PDR ADOCK 05000311 R PDR

A~GE DAILY UNIT POWER LEV~

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:

50-311 08/10/95 Completed' by: Robert Phillips Telephone: 339-2735 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) since Last Report, Give Reason N A
9. Power Level to Which Restricted, if any (Net MWe) N/A
10. Reasons for Restrictions, if any NA This Month Year to Date Cumulative
11. Hours in Reporting Period 744 5087 120960
12. No. of Hrs. Rx. was Critical 0 2468.4 78083.6
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 2261.6 75229.5
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 6807220.8 187781005 Gross Elec. Energy Generated (MWH) 0 2198890 78648898
18. N,et Elec. Energy Gen. (MWH) -12775 2041100 74764644
19. Unit Service Factor 0 44.5 62.2
20. Unit Availability Factor 0 44.5 62.2
21. Unit Capacity Factor (using MDC Net) 0 36.3 55.9
22. Unit Capacity Factor (using DER Net) 0 36.0 55.4
23. Unit Forced Outage Rate 100 47.0 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

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1995 DOCKET NO. 50-311 UNIT NAME Salem #2 DATE . 8-10-95 COMPLETED BY Robert Ph fl lips TELEPHONE 609-339-2735 METHOD OF SHUTTING LICENSE .

DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 2

NO. DATE TYPE 1 (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 2692 7-1-95 F 744 A 4 ----------- SH CKTBRK BREAKER FAILURE 1-9 500KV 1 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-Equipment Failure (explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refuel ing 3-Automatic Scram Event Report CLER) File D-Requlatory Restriction 4-Continuation of (NUREG-0161)

E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

10CFRSQ:59 EVALUATIONS

  • DOCKET NO:
  • 50-311 M'ONTH: JULY 1995 UNIT NAME: SALEM2 DATE: 08/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-3 3 9-5162 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)

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)

REFUELING INFORMATION

  • DOCKET NO:
  • 50-311 MbNTH~ JULY 1995 UNIT NAME: SALEM2 DATE: 08/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-3 3 9-5162 MONTH: JULY 1995
1. Refueling information has changed from last month: YES~X 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?

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 _193 _ _
b. In Spent Fuel Storage 556
8. Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632
9. Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: March 2012 8-1-7.R4

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
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