ML18101B369

Monthly Operating Rept for Apr 1996 for Salem Unit 1.W/ 960515 Ltr

ML18101B369
Person / Time
Site:	Salem
Issue date:	04/30/1996
From:	HELLER R, PHILLIPS R, WARREN C C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9605210322
Download: ML18101B369 (9)

Text

'* 0 e 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. 1 DOCKET NO: 50-272 May 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 April is being sent to you. RH:vls Enclosures C Mr. Thomas T. Martin Sincerely yours, J.Lll.1f:-fo Warr:n General Manager -Salem Operations Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046 :-----ci6o52io322-9oo43o

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3 ' PDR ADOCK 05000272 1 ' R PDR

• The power is in your hands. 95-2168 REV. 6/94 e OPERATING DATA REPORT e Docket No: 50-272 Date: 05/10/96 Completed by: Robert Phillips Telephone:

339-2735 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period April 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

9. Power Level to Which Restricted, if any (Net MWe) N/A 10. Reasons for Restrictions, if any 12. 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 24. Shutdowns scheduled over next 6 This Month 719 0 0 0 0 0 0 -1889 0 0 0 0 0 months (type, NA Year to Date Cumulative 2903 0 0 0 0 0 0 -8733 0 0 0 0 0 date and 165120 104380.5 0 100388.3 0 318062229.2 105301000 100196180 60.8 60.8 54.9 54.4 22.9 duration of each) The Unit remained in a scheduled extension of a refueling outage. 25. If shutdown at end of Report Period, Estimated Date of Startup: To be determined.

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DAILY UNIT POWER LEVEL Docket No.: 50-272 Unit Name: Salem #1 Date: 05/10/96 Completed by: Robert Phillips Telephone:

339-2735 Month April 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 16 0 P. 8.1-7 Rl NO. DATE 3824 04-01-96 s 1 2 F: Forced S: Scheduled DURATION TYPE' (HOURS) REASON 2 719 c Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction 4 UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH April 1996

• METHOD OF SHUTTING DOYN 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 50-272 Salem #1 05/10/96 Robert Phil lips 609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE zzzz Schedule Extension of Refueling 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: APRIL 1996 DOCKET NO: UNIT NAME: 50-272 SALEM I 05/10/96 DATE: C01\.1PLETED 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.

I. Design Change Packages (DCP) IEC-3540, Pkg. I IEC-3540, Pkg. 2 "ISJI & ISJ2 SI RWST to Charging Pump Stop Valves Disc Weep Holes" Rev. 0 -This DCP drills weep holes in the valve discs (Pump side) of the Safety Injection RWST to Charging Pump Stop Valves ISJI and ISJ2. This modification provides , an internal relief path to preclude potential pressure locking due to a pressure buildup in the valves' bonnet cavities and in the space between the valve discs. This is consistent with preventive methods promulgated in NUREG-1275, Vol. 9. This modification does not reduce the safety margin of the Safety Injection System and enhances-the reliability of the system by providing an internal relief path for any fluid trapped in the valve bonnets, thus ensuring valve operability. (SORC 96-013) . "Safety Injection Pump Cross Over Motor Operated Valves (I ISJI 13 And 12SJI 13) Disc Weep Holes" Rev. 0 -This DCP drills weep holes in the valve discs (1ISJI14 valve side) of the Safety Injection Pump Cross Over Motor Operated Valves I ISJI 13 and 12SJI 13. This modification provides an internal relief path to preclude potential pressure locking due to a pressure buildup in the valves' bonnet cavities and in the spaces between the valve discs. This is consistent with preventive methods promulgated in NUREG-1275, Vol. 9. This modification does not reduce the safety margin of the Safety Injection System and enhances the reliability of the system by providing an internal relief path for any fluid trapped in the valve bonnets, thus ensuring valve operability. (SORC 96-019) 10CFR50.59 EVALUATIONS MONTH: APRIL 1996 DOCKET NO: UNIT NAl\ffi: 50-272 SALEM 1 05/10/96 R.HELLER 609-339-5162 DATE: CO:MPLETED BY: TELEPHONE: (Cont'd) 2. UFSAR SCN 96-36 3. Procedures and Revisions S-C.RE-FR.ZZ-0003

4. Evaluations ES-4.004 Rev. 2 "Chemistry Organization Flow Chart" -This revision describes the Chemistry Department organization and organization duties different than the UFSAR. The proposed procedure change does not conflict with any Technical requirement, nor does the procedure change reduce the margin of safety required by Technical Specifications because specific programs and policies are still required by UFSAR Section 12.3.5, Procedures. (SORC 96-046) "New Fuel Transfer and Shipment" Rev. 0 -The purpose of this procedure it to provide the steps necessary to load unirradiated fuel assemblies into a shipping container(s) and transfer the shipping container(s) either off-site or between units. The transfer of new fuel between units does not affect the bases for any of these Technical Specifications and therefore, does not reduce the margin of safety. (SORC 96-050) "125V Battery And Battery Charger Sizing Calculation" -This is a revision to calculation ES-4.004(Q)

Revision 2, which is the basis of the 125V DC battery load. This revision sizes the battery, battery charger and determines the Battery Voltage Profiles and supersedes and incorporates ES-45.002(Q) for Station blackout event (SBO). The load profiles provide the basis of the Technical Specification Surveillance (4.8.2.3.2) for the 18 month battery service test. The 125V DC battery load profile is shown in table 8.3.6 of the Salem UFSAR. The revision to this calculation proposes no changes to the structures systems or components.

This calculation revision is more precise and conservative and does not reduce the margin of safety as defined in the Technical Specifications. (SORC 96-053)

. . 10CFR50.59 EVALUATIONS MONTH:APRIL1996 DOCKET NO: UNIT NAME: 50-272 SALEM 1 05/10/96 ES-3.002 Rev. 1 DATE: COMPLETED BY: TELEPHONE:

R. HELLER 609-339-5162 "28V DC Battery And Battery Charger Sizing Calculation" -This is a revision to calculation ES-3.002(Q)

Revision 1, which is the basis of the 28V DC battery load profiles.

This revision sizes the battery, battery charger and determines the Battery Voltage Profiles and supersedes and incorporates ES-45.00l(Q) for Station blackout event (SBO). The load profiles provide the basis of the Technical Specification Surveillance (4.8.2.5.2) for the 18 month battery service test. The 28V DC battery load profile is shown in table 8.3-5 of the Salem UFSAR. The revision to this calculation proposes no changes to the structures systems or components.

This calculation revision is more precise and conservative and does not reduce the margin of safety as defined in the Technical Specifications. (SORC 96-053)

-' . REFUELING INFORMATION MONTH:

1996 MONTH : APRIL 1996 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 05/10/96 RHELLER 609-339-5162 Refueling information has changed from last month: YES _ X _ NO ..__. _ ____,_ Scheduled date for next refueling: (to be determined)

Scheduled date for restart following refueling: (to be determined)

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

Number of Fuel Assemblies:

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

Future spent fuel storage capacity:

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

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• SALEM GENERATING STATION MONTfil Y OPERATING

SUMMARY

-UNIT 1 APRIL 1996 SALEMUNITNO.

1 The Unit is in a refueling outage and remained shutdown for the entire period. Evaluation and assessment of the Steam Generator tube indications continues.

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 review