ML18102A259

Monthly Operating Rept for June 1996 for Salem Generating Station Unit 1.W/960715 Ltr

ML18102A259
Person / Time
Site:	Salem
Issue date:	06/30/1996
From:	Garchow D, Heller R, Phillips R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9607230182
Download: ML18102A259 (8)

Text

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 July 15, 1996 In compliance with Section 6.9 . .J.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating report for the month of June is being sent to you. RH:vls Enclosures C Mr. Thomas T. Martin Sincerely yours, David F. Garchow General Manager -Salem Operations Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046 ------------------------\ 9607230182 960630 PDR ADOCK 05000272 R PDR The power is in your hands. 95-2168 REV. 6/94 AVE, DAILY UNIT POWER LEVEL e Docket No. : 50-272 Unit Name: Salem #1 Date: 07/10/96 Completed by: Robert Phillips Telephone:

339-2735 Month June 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 I L L OPERATING DATA REPORT Docket No: 50-272 Date: 07/10/96 Completed by: Robert Phillips Telephone:

339-2735 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period June 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 A 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 Forced outage. This Month 720 0 0 0 0 0 0 -2430 0 0 0 0 100 months (type, NA Year to Date Cumulative 4367 166584 0 104380.5 0 0 0 100388.3 0 0 0 318062229.2 0 105301000

-13621 10191292 0 60.3 0 60.3 0 54.4 0 53.9 100 23.8 date and duration of each) 25. If shutdown at end of Report Period, Estimated Date of Startup: To be determined.

8-l-7.R2 NO. DATE 4092 06-01-96 F 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 720 F c Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction 4 UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH June 1996 METHOD OF SHUTTING Dmm REACTOR LICENSE EVENT REPORT # ----------

HJ 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 07/10/96 Robert Phillips 609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 2422 Nuclear Steam Generator Systems. 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -Same Source

• 10CFR50.59 EVALUATIONS MONTH: JUNE 1996 DOCKET NO: UNIT NAME: 50-272 SALEM 1 CONTACT: 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) lEC-3476, Pkg. 1 "Annular Steel Framing Modifications" Rev. 0 -This change modifies annular steel columns in ten (10) locations by bracing the columns to the crane wall. The surface mounted channels were modified by the addition of drilled in concrete anchors, to reduce their span length. The implementation of this change ensures that the annular steel columns and surface mounted channel member stresses remain within their design allowables, as specified in the design criteria.

There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 95-156) 2. Temporary Modifications (TMOD)96-019 "Temporary Chilled Water for the CAAC Air Conditioning Units" Rev. 0 -DCP lEC-3505, Pkg. 7 provides design enhancements which will improve the Chilled Water system performance, and reliability.

During the implementation of this DCP the Unit 1 Chilled Water system will be shutdown.

This TMOD enables the Control Room, Unit 1 Electrical Equipment Room, Unit I Data Logging Room and Unit I Relay Room environments to remain within their design temperature limits during the DCP implementation phase. The Chilled Water system has no Technical Specification requirements.

There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-081)

• 10CFR50.59 EVALUATIONS N.IONTH:JUNE1996 DOCKET NO: UNIT NAN.IE: 50-272 SALEN.I I 3. Evaluations S-C-SW-N.ISE-085 9 S-C-FHB-MDC-1616 CONTACT: TELEPHONE:

R. HELLER 609-339-5162 "Service Water and Component Cooling EOP Alignment Issues" (Westinghouse SECL-96-043)

-This evaluation modifies the emergency operating procedures (EOP's), along with some non EOP procedures, to support resolution of Service Water (SW) and Component Cooling (CC) EOP alignment issues. The procedure changes to resolve SW & CC alignment concerns during an accident will ensure the SW and CC system flows and temperatures are within their design limits, along with ensuring sufficient flow to components cooled by SW and CC. This ensures the safety parameters of the interfacing system will not be adversely impacted and will also remain within their design limits. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 96-074) "Fuel Handling Accident Analysis Radiological Evaluation" Rev. 0 -This evaluation reconciles differences between calculation S-C-FHV-MDC-1616, the Licensing Report submitted in License Change Request 93-02 (Fuel Handling Accident Reanalysis Following Spent Fuel Pool High Density Rack N.lodification), and the NRC's evaluation in the Safety Evaluation Report (SER) for Amendments 151 and 131. Calculation S-C-FHV-MDC-1616 remains well within the Guidelines of NUREG-0800, and the calculation results essentially equal the NRC staff analysis of 13. 2 rem at the exclusion area boundary.

There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC L__ -* REFUELING INFORMATION MONTH: JUNE 1996 MONTH : JUNE 1996 DOCKET NO: UNIT NAME: CONTACT: TELEPHONE:

50-272 SALEM 1 R.HELLER 609-339-5162 Refueling information has changed from last month: YES _. _. NO . X . 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.

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:

0 989 1632 1632 September 2008

' -. . , .. SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT I JUNE 1996 SALEMUNITNO.

I The Unit is in a refueling and Steam Generator replacement outage and 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 review