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

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 April 12, 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 February is being sent to you. RH:vls Enclosures C Mr. Thomas T. Martin Sincerely yours, C. Warren General Manager -Salem Operations Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 ... -c .. :;. I CJQ ).!10. -I.\.

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--9664190109 960331 . PDR ADOCK 05000311 R PDR The power is inyour hands. 95-2168 REV. 6/94

• OPERATING DATA REPORT 1./ Docket No: Date: Completed by: Robert Phillips Telephone:

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) 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) 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 NA This Month Year to Date 744 2184 0 0 0 0 0 0 0 0 0 0 0 0 -3074 -9209 0 0 0 0 0 0 0 0 100 100 50-311 04/10/96 339-2735 since Last NIA Cumulative 126817 78083.6 0 75229.5 0 187781005 78648898 74731845 59.3 59.3 53.3 52. 9/ 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

DAILY UNIT POWER Completed by: Robert Phillips Month March 1996 Day Average Daily Power Level (MWe-NET) 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 P. 8.1-7 Rl Day Docket No.: unit Name: Date: Telephone:

50-311 Salem #2 04/10/96 339-2735 Average Daily Power Level (MWe-NET) 17 0 18 0 19 0 20 0 21 0 22 0 23 0 24 0 25 0 26 0 27 0 28 0 29 0 30 0 31 0 NO. DATE 3859 03-01-96 F 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 744 F c Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refuel ing D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS 4 REPORT MONTH March 1996 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT # _ ..................

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 DATE COMPLETED BY TELEPHONE 50-311 Salem #2 04-10-96:

Robert Phillips' 609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE zzzz Refueling Schedule Exceeded 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161) 5 Exhibit 1 -Same Source *

• 10CFR50.59 EVALUATIONS MONTH: MARCH 1996 DOCKET NO: UNIT NAME: 50-311 SALEM2 04/10/96 DATE: COMPLETED BY: TELEPHONE:

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) 2EC-3287, Pkg. 1 2EC-3288, 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) "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 MONTH: MARCH 1996 DOCKET NO: UNIT NAME: 50-311 SALEM2 04/10/96 R.HELLER 609-339-5162 DATE: COMPLETED BY: TELEPHONE: (Cont'd) 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 MONTH: MARCH 1996 MONTH: MARCH 1996 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-311 SALEM2 04/10/96 R. HELLER 609-339-5162

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

Future spent fuel storage capacity:

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

8-1-7.R4 0 749 1632 1632 March 2012 SALEM GENERATING STATION MONTIIL Y 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