ML18095A691

Monthly Operating Rept for Dec 1990 for Salem Unit 1.W/ 910115 Ltr

ML18095A691
Person / Time
Site:	Salem
Issue date:	12/31/1990
From:	Labruna S, Orticelle A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9101220002
Download: ML18095A691 (10)

Text

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department January 15, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the originai copy of the monthly operating reports for the month of December 1990 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours, General Manager -

Salem Operations RH:pc cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 00n(lf\B r;,, 1rhe Ene*rgy 1 People ,--- ~?i(112:2oc102--9oi2.:3i ___ ------

PDR ADOCK 05000272 R PDR 95-2168 (1 QOM) 12-84

.,ERAGE DAILY UNIT POWER L.L Docket No.: 50-272 Unit Name: Salem #1 Date: 1/10/91 Completed by: Art Orticelle Telephone: 339-2122 Month December 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1070 17 1085 2 1099 18 1093 3 1092 19 1127 4 1106 20 1084 5 1091 21 1085 6 1093 22 1112 7 1093 23 1091 8 1027 24 1113 9 1113 25 1101 10 1093 26 1104 11 1111 27 1092 12 1095 28 1111 13 1098 29 1102 14 1107 30 1090 15 1094 31 1115 16 1096 P. 8.1-7 R1

• OPERATING DATA REPORT.

Docket No: 50-272 Date: 1/10/91 Completed by: Art Orticelle Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period December 1990

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) N/A

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

11. Hours in Reporting Period 744 8760 118393

12. No. of Hrs. Rx. was Critical 744 6054.9 76963.5

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 744 5871. 8 74567.5

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2535134.4 18961459.2 234062385.2

17. Gross Elec. Energy Generated (MWH) 849040 6251280 77712640

18. Net Elec. Energy Gen. (MWH) 815565 5956962 73968672

19. Unit Service Factor 100 67.0 63.0

20. Unit Availability Factor 100 67.0 63.0

21. Unit Capacity Factor (using MDC Net) 99.1 61.5 56.5

22. Unit Capacity Factor (using DER Net) 98.3 61. 0 56.0

23. Unit Forced Outage Rate 0 33.0 22.5

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

Refueling outage scheduled to start 2/9/91 and last 61 days.

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

NA 8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH DECEMBER 1990 DOCKET NO. : ~5~0"""*=27~2'"""""_ __

UNIT NAME: Salem #1 DATE: 1/10/91 COMPLETED BY: Art Orticelle TELEPHONE: 339-2122 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 2

NO. DATE TYPE 1 (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE

• 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)

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• SAFETY RELATED MAINTENANCE MONTH: - DECEMBER 1990

• DOCKET NO: 50-272 UNIT NAME: SALEM 1 DATE: JANUARY 10, 1991 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 880330096 1 SW PANEL 979-lC FAILURE DESCRIPTION: FUSE BLOCK BROKEN - REPLACE 900906100 1 VALVE 12SW158 FAILURE DESCRIPTION: RHR PUMP ROOM COOLER VALVE NOT MODULATING - TROUBLESHOOT AND REWORK 901031197 1 15 SERVICE WATER PUMP FAILURE DESCRIPTION: PUMP FAILED 4.0.5 SURVEILLANCE -

CHANGE OUT PUMP 901203069 1 1S27C PIPE SPOOL FAILURE DESCRIPTION: PIPE SPOOL HAS A THROUGH WALL LEAK - REPAIR 901206198 1 VALVE 11SW6 FAILURE DESCRIPTION: PIPE LEAKING UPSTREAM AND DOWNSTREAM OF VALVE - REPAIR 910718001 1 VALVE 14SW25 FAILURE DESCRIPTION: REPLACE DIAPHRAGM AND BONNET ASSEMBLY J

10CFR50.59 EVALUATIONS

• DOCKET NO: 50-272 MONTH: - DECEMBER 1990 UNIT NAME: SALEM 1 DATE: JANUARY 10, 1991 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 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 these evaluations and agrees with their conclusions that these items do not present Unreviewed Safety Questions (USQs).

ITEM

SUMMARY

A. Design Change Packages lEC-3058 Pkg 1 "Polar Crane Upgrade" - The purpose of this design change is to strengthen three trolley beam connections on the polar gantry cranes.

A325 high strength bolts will replace A307 bolts on the top flange plates and stiffeners will be welded to the bottom flanges. ( SORC 90-160) lEC-2272 Pkg 3 "Sequence of Events Computer" - The purpose of this DCP is to perform continuity and energized testing of cables, wiring, relays and switches for the Sequence of Events Computer installed by previous packages. The temporary systems testing being implemented by this DCP does not impact any surveillance or testing procedures described in the UFSAR. ( SORC 90-161)

B. Procedures and Revisions EOP-TRIP-1 The purpose of this revision is to address the information identified in Westinghouse Letter SECL 90-333, and address a concern identified in NRC Generic Letter 88-04. The procedural change to EOP-TRIP-1 will allow the closure of one RHR discharge cross connect valve (RH19) to eliminate the influence of one RHR discharge path to dead head the opposite pump, if both pumps are on recirculation. Although this scenario is not currently the case at Salem, the procedure revision is being prepared as a contingency remedy. (SORC 90-160)

• 10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: - DECEMBER 1990 UNIT NAME: SALEM 1 DATE: JANUARY 10, 1991 COMPLETED BY: F. THOMSON TELEPHONE: {609)339-2904 (Cont'd)

ITEM

SUMMARY

Sl.RE-ST.ZZ-0002(Q) "Shutdown Margin Calculation" Rev. 0 - The purpose of this revision is to convert the Reactor Engineering Manual Procedures to the AP numbering system, and revise the procedures to add in the worth from a stuck rod. Other changes include revising the procedures such that initial xenon reactivity is that reactivity relating to the reference critical conditions and not the shutdown conditions. The change ensures that the reactivity balance is calculated correctly and consistently. (SORC 90-160)

C. Temporary Modifications (TMODS)

STD 90-124 The purpose of this modification is to provide temporary power to the 11 & 12 MAC panels during installation of DCP lSC-2161 Pkg. 4. The DCP changes the input and output power cables to the UPS. during installation of the cables the UPS will be completely deenergized, therefore the 11

& 12 MAC panels require temporary power. The appropriate DCP installation instructions were extracted from the DCP and placed into this TMOD as per the directions of the GMSO. This approach will make the operating shift totally cognizant of plant conditions during the DCP implementation. {SORC 90-159)

STD 90-135 The purpose of this modification is to install a Leak Repair enclosure on a line break upstream of Valve 12BS900, and inject the enclosure with I Leak Repair compound to stop the leakage. The I line cannot be isolated at power and a permanent I repair will be made during the next outage of I sufficient duration. (SORC 90-163) I I

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10CFR50.59 EVALUATIONS

• DOCKET NO: 50-272 MONTH: - DECEMBER 1990 UNIT NAME: SALEM 1 DATE: JANUARY 10, 1991 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

E. Safety Evaluations (S/E}

I.D. #: 901123135-1 This evaluation analyzes the removal of a portion of the service water supply piping to 14 and 15 Containment Fan Coil Units (CFCUs) and replacing it with a patch. The 16" service water supply line to the 14 and 15 CFCUs has a thru wall failure. The line will be repaired by removing a patch around the leak and replacing that portion of pipe with new pipe. The original pipe is made of ASTM A106 16" x 1/2" tar lined pipe. The patch is made of A106 16" x 1/2" non-lined pipe. In lieu of lining, the pipe in the area of the patch will be UT examined on a regular basis to determine if there is any reduction in wall thickness.

(SORC 90-159)

S-C-F300-MSE-0706-3 The purpose of this Safety Evaluation is to allow the packing of the Unit 1 & 2 BF19 valves to be adjusted while the valves are in service, without the need for full closure testing. This evaluation concludes the BF19 valve packing can be adjusted while the valves are in service with a partial stroke of the valves demonstrating that the performance is unaffected and there is no impact to the safety of the plant. ( SORC 90-160)

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• SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 DECEMBER 1990 SALEM UNIT NO. 1 The Unit began the period operating at full power and continued to operate .at essentially full power throughout the remainder of the reporting period.

REFUELING INFORMATION

• DOCKET NO: 50-272 MONTH: - DECEMBER 1990 UNIT NAME: SALEM 1 DATE: JANUARY 10, 1991 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 MONTH DECEMBER 1990

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: February 9, 1991

3. Scheduled date for restart following refueling: April 10, 1991

4. 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?: January 1991

5. Scheduled date(s) for submitting proposed licensing action:

N/A

6. Important licensing considerations associated with refueling:

7. Number of Fuel Assemblies:

a. Incore 193

b. In Spent Fuel Storage 588

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170

9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2001 8-l-7.R4