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 Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9605210322
Download: ML18101B369 (9)

Text

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e 0 PS~G Public Service Electric and Gas Company P.O, Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit May 15, 1996 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 1 DOCKET NO: 50-272 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.

Sincerely yours, J.Lll.1f:-fo da~LC. Warr:n General Manager -

Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046

-----ci6o52io322-9oo43o _______ --- --~----114 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 Reason.~~~~N:..s...:.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

12. Hours in Reporting Period 719 2903 165120

12. No. of Hrs. Rx. was Critical 0 0 104380.5

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator on-Line 0 0 100388.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 318062229.2

17. Gross Elec. Energy Generated (MWH) 0 0 105301000

18. Net Elec. Energy Gen. (MWH) -1889 -8733 100196180

19. Unit Service Factor 0 0 60.8

20. Unit Availability Factor 0 0 60.8

21. Unit Capacity Factor (using MDC Net) 0 0 54.9

22. Unit Capacity Factor (using DER Net) 0 0 54.4

23. Unit Forced Outage Rate 0 0 22.9

24. Shutdowns scheduled over next 6 months (type, date and 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.

8-1-7.R2

.. AVERA~ 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

UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH April 1996

• DOCKET NO. 50-272 UNIT NAME Salem #1 DATE 05/10/96 COMPLETED BY Robert Phil lips TELEPHONE 609-339-2735 METHOD OF SHUTTING LICENSE DURATION DOYN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 2

NO. DATE TYPE' (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 3824 04-01-96 s 719 c 4 ---------- zz zzzz Schedule Extension of Refueling 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-Refueling 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: 50-272 MONTH: APRIL 1996 UNIT NAME: SALEM I DATE: 05/10/96 C01\.1PLETED 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.

I. Design Change Packages (DCP)

IEC-3540, Pkg. I "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) .

IEC-3540, Pkg. 2 "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 DOCKET NO: 50-272 MONTH: APRIL 1996 UNIT NAl\ffi: SALEM 1 DATE: 05/10/96 CO:MPLETED BY: R.HELLER TELEPHONE: 609-339-5162 (Cont'd)

2. UFSAR SCN 96-36 "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 Spe~ification 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)

3. Procedures and Revisions S-C.RE-FR.ZZ-0003 "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)

4. Evaluations ES-4.004 Rev. 2 "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 DOCKET NO: 50-272 MONTH:APRIL1996 UNIT NAME: SALEM 1 DATE: 05/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 ES-3.002 Rev. 1 "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 DOCKET NO: 50-272 MONTH: ~RIL 1996 UNIT NAME: SALEM 1 DATE: 05/10/96 COMPLETED BY: RHELLER TELEPHONE: 609-339-5162 MONTH : APRIL 1996 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 0

b. In Spent Fuel Storage 993 Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632 Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2008 8-1-7.R4

• r" SALEM GENERATING STATION MONTfilY 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