ML18101B325

Monthly Operating Rept for March 1996 for Sgs Unit 2.W/ 960412 Ltr

ML18101B325
Person / Time
Site:	Salem
Issue date:	03/31/1996
From:	Heller R, Phillips R, Warren C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9604190109
Download: ML18101B325 (9)

Text

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit April 12, 1996 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 report for the month of February is being sent to you.

Sincerely yours,

~~r C. Warren 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

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PDR ADOCK 05000311 R PDR The power is inyour hands.

95-2168 REV. 6/94

• OPERATING DATA REPORT 1./

Docket No:

Date:

50-311 04/10/96 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period March 1996

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) NIA

10. Reasons for Restrictions, if any NA This Month Year to Date Cumulative

11. Hours in Reporting Period 744 2184 126817

12. No. of Hrs. Rx. was Critical 0 0 78083.6

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 0 0 75229.5

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 187781005

17. Gross Elec. Energy Generated (MWH) 0 0 78648898

18. Net Elec. Energy Gen. (MWH) -3074 -9209 74731845

19. Unit Service Factor 0 0 59.3

20. Unit Availability Factor 0 0 59.3

21. Unit Capacity Factor (using MDC Net) 0 0 53.3

22. Unit Capacity Factor (using DER Net) 0 0 52. 9/

23. Unit Forced Outage Rate 100 100 26.1

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

We are presently forced beyond the scheduled refueling outage.

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

Under review.

8-1-7.R2

~RAGE DAILY UNIT POWER LE~

Docket No.: 50-311 unit Name: Salem #2 Date: 04/10/96 Completed by: Robert Phillips Telephone: 339-2735 Month March 1996 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

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH March 1996 DOCKET NO. 50-311 UNIT NAME Salem #2 DATE 04-10-96:

COMPLETED BY Robert Phillips' TELEPHONE 609-339-2735 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 3859 03-01-96 F 744 F c 4 _.................. zz zzzz Refueling Schedule Exceeded 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 CNUREG-0161)

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

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: MARCH 1996 UNIT NAME: SALEM2 DATE: 04/10/96 COMPLETED BY: R. HELLER TELEPHONE: 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) 2EC-3287, Pkg. 1 "Service Water Large Bore Pipe Replacement" Rev. 0 -

This DCP was initiated to replace piping in the #21 Service Water Header. It involves replacement of carbon steel cement or coal tar epoxy lined pipe with 6% molybdenum austenitic stainless steel pipe. It is intended to maintain the current pipe routing. This replacement involves portions of the service water supply and return headers in the Auxiliary Building at floor elevation 78' -0". These modifications upgrade the pipe material from cement or epoxy lined carbon steel to 6% molybdenum austenitic stainless steel.

The new material provides superior corrosion resistance relative to the existing material. The piping material, fabrication, installation and configuration has been designed to meet or exceed the original design basis. Therefore, these modifications do not reduce the margin of safety as defined in the bases for any Technical Specification. (SORC 96-001) 2EC-3288, Pkg. 1 "Service Water Large Bore Pipe Replacement" Rev. 0 -

This Design Change Package was initiated to replace service water piping in Unit 2 Intake Bay #2. It involves replacement of carbon steel cement or coal tar epoxy lined pipe with 6% molybdenum austenitic stainless steel pipe. It involves maintaining the current pipe routing. This replacement changes out portions of the service water supply header in the Service Water Intake Structure Bay #2 and a portion of the discharge piping from service water pump No. 22. The new material provides superior

10CFR50.59 EVALUATIONS

• DOCKET NO: 50-311 MONTH: MARCH 1996 UNIT NAME: SALEM2 DATE: 04/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 (Cont'd) ll:::::i:::::lt:1::]:1Wi~:::]:::::::::::::1:1i:::::::::::::::::i:))l]l::::1:::::1:1:::::t=]:t:l]::1::_]=]=:,::,,,::.:]:::::::=:~-1=1::::::]:::::::::::::::=:::::::::i::::::::::::]:::::::::::::::=:]:::::::t]::::::::::::]:::11 will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 96-036)

2. Temporary Modifications (TMOD)96-011 "Temporary Ventilation In Support OfCAACS Cooling Coil Replacement" - This Temporary Modification (TMOD) package provides an alternate source of ventilation to the Unit 2 control equipment room (CER), data logging room, and relay room areas which are normally supplied from the Control Area Air Conditioning System (CAACS). In order to support maintenance activities for replacing the cooling CAACS coils, the Unit 2 CAACS will be out of service, and therefore will be unavailable to provide ventilation to the areas listed above. PSE&G calculation S-2-CAV-MDC-1573 indicates the TMOD will maintain acceptable temperatures in the affected areas. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-039)

REFUELING INFORMATION

• \*

DOCKET NO: 50-311 MONTH: MARCH 1996 UNIT NAME: SALEM2 DATE: 04/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH: MARCH 1996

1. Refueling information has changed from last month: YES . X . NO "'"--"_ __,_

2. Scheduled date for next refueling: 11102/95 Scheduled date for restart following refueling: 08/31/96

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 ofFuel Assemblies:

a. Incore 0

b. In Spent Fuel Storage 749

8. Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632

9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: March 2012 8-1-7.R4

SALEM GENERATING STATION MONTIILY OPERATING

SUMMARY

- UNIT 2 MARCH 1996 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, 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 each Unit to operate in a safe, event free manner

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