ML18101A777

Monthly Operating Rept for May 1995 for Salem Unit 1.W/ 950614 Ltr

ML18101A777
Person / Time
Site:	Salem
Issue date:	05/31/1995
From:	Phillips R, Summers J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9506200068
Download: ML18101A777 (10)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit June 14, 1995 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTfilY 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 reports for the month of May are being sent to you.

~John C. Summers General Manager -

Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 8-l-7.R4 9506200068 950531 PDR ADDCK 05000272 R PDR The power is in your hands.

95-2168 RE . 6/94

.VERAGE DAILY UNIT POWER L~L Docket No.: 50-272 Unit Name: Salem #1 Date: 06/10/95 Completed by: Robert Phillips Telephone: 339-2735 Month MAY 1995 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1048 17 0 2 1046 18 0 3 1045 19 0 4 1074 20. 0 5 528 21 0 6 445 22 0 7 505 23 0 8 404 24 0 9 472 25 0 10 453 26 0 11 463 27 0 12 470 28 0 13 468 29 0 14 526 30 0 15 620 31 0 16 914 P. 8.1-7 Rl L

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OPERATING DATA REPORT Docket No: 50-272 Date: 06/10/95 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period May 1995

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

12. Hours in Reporting Period 744 3623 157080

12. No. of Hrs. Rx. was Critical 387.3 2660.9 104380.45

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 386.03 2632.09 100388.27

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 829060.8 5781911. 6 315833814.4

17. Gross Elec. Energy Generated (MWH) 267840 2689850 105301000

18. Net Elec~ Energy Gen. (MWH) 247176 2554430 100236594

19. Unit Service Factor 51. 9 72.6 63.9

20. Unit Availability Factor 51. 9 72.6 63.9

21. Unit Capacity Factor (using MDC Net) 30.0 63.7 57.7

22. Unit Capacity Factor (using DER Net) 29.8 63.2 57.2

23. Unit Forced Outage Rate 48.l 27.4 21. 5

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

A 60 day refueling outage scheduled to start 9-9-95.

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

Start up is presently scheduled for July 5, 1995.

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UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MAY 1995 DOCKET NO.: 50-272 UN IT NAME: _sa~l..._e~m~#.._1~--:

DATE: -'6=--....:.1-=-0-_,9""'5-~

COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 2577 5-4-95 F 132.9 A 5 .. __ ................ CH PUMP XX NUCLEAR STEAM GENERATOR FEEDPUMP 2614 5-15-95 F 19.9 A 5 ...................... SH CKTBRK SWITCHGEAR ROOM* VENTILATION

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2616 5-16-95 F 4.6 A 4 SH CKTBRK SWITCHGEAR ROOM VENTILATION 2671 5-17-95 . F 357.97 D 1 ----------- SH CKTBRK TECH. SPEC. 3.0.3 1 2 3 4 5 F: F.orced 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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IOCFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: MAY I995 UNIT NAME: SALEM I DATE: 06/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5I62 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations IOCFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations.

I. Design Change Packages (DCP)

IEC-3387, Pkgs I- 3 "EDG IA, B & C Air Receiver Low Pressure Alarms" Rev. 0 -

The purpose ofthis design change is to install two pressure switches each, along with all associated tubing, valves, and wiring for the starting air receivers for Diesel Generators IA, IB & IC. These pressure switches are to provide new low pressure alarms for each of the starting air receivers. These will provide early warning to the operating personnel so that they can take adequate action to mitigate starting air receiver degraded conditions and maintain the receiver pressure adequate for three diesel starts. The Diesel Air Start System and its components, including instruments, are not the subject of any technical specifications or technical specification basis.

There is no reduction in the margin of safety as defined in the basis for any technical specification. (SORC 95-042)

IEC-3252, Pkg. 1 "Reracking of Spent Fuel Pool for Increased Storage Capacity" Rev. 3 - This DCP removes nine existing Exxon racks and replaces them with nine maximum density Holtec racks. This revision to the DCP is being made to: I) delete references to the Offset Tool; 2) clarify the rack handling procedure, and 3) address minor errors observed during Part A closure. This revision involves neither the addition, deletion or modification of any equipment designed to monitor or control plant systems or components. There is no reduction in the margin of safety as defined in the basis for any technical specification. (SORC 95-053)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: MAY 1995 UNIT NAME: SALEM 1 DATE: 06/i0/95 C01\.1PLETED BY: R. HELLER TELEPHONE: 609-339-5162 (Cont'd)

2. Temporary Modifications (T-Mod)95-035 "Temporary Blank for 1VHE838" Rev. 1 - 1VHE57, 12 Switchgear Ventilation Supply Fan and Motor are to be removed for maintenance. To support this activity, the filter plenum, 1VHE838 must be isolated. There is no isolation point on the upstream side of the fan. There is only one on the downstream side. Therefore, the upstream side is to be blanked off The temporary blank is to be constructed from safety related steel, with a thickness equivalent to or greater than that required of the plenum. The blank will take the place of the current nozzle, there is no loading on the existing nozzle area; immediately downstream is a rubber expansion joint.

Therefore, no seismic loading contribution exists. The .

modification involves neither the addition, deletion or modification of any equipment designed to monitor or control plant systems or components. There is no reduction in the margin of safety as defined in the basis for any technical specification. (SORC 95-051)95-036 "Temporary Blank for 1VHE838" Rev. 1 - 1VHE58, 13 Switchgear Ventilation Supply Fan and Motor are to be removed for maintenance to replace a bad motor. To support this activity, the filter plenum, 1VHE838 must be isolated.

There is no isolation point on the upstream side of the fan.

There is only one on the downstream side. Therefore, the upstream side is to be blanked off The temporary blank is to be constructed from safety related steel, with a thickness equivalent to or greater than that required of the plenum. The blank will take the place of the current nozzle, there is no loading on the existing nozzle area; immediately downstream is a rubber expansion joint.

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10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: MAY 1995 UNIT NAME: SALEM I DATE: 06/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 Therefore, no seismic loading contribution exists. The modification involves neither the addition, deletion nor modification of any equipment designed to monitor or control plant systems or components. There is no reduction in the margin of safety as defined in the basis for any technical specification. (SORC 95-051)

3. Safety Ev~luations (S/E)

WO 950513085 "Freeze Seal of 13 Charging Pump Relief Valve Tailpipe" Rev.

0 - The purpose of this proposal is to install a freeze seal on the downstream piping of the Reciprocating Charging Pump discharge relief valve ICVl41. The freeze seal is needed to allow .the replacement of the relief valve. The freeze seal will prevent fluid from leaking out of the Volume Control Tank (VCT) while the valve is being replaced. In addition, the freeze seal will block any fluid should relief valves ICVl24 and I CV253 lift or leak by their seats. However, their relief path will not be affected by the freeze seal. The Chemical and Volume Control System (CVCS) will continue to be operated in accordance with normal operating procedures. At no time during the maintenance evolution, will the requirement that at least one boration injection flow path be available be challenged: The flow path from either Boric Acid Tank or Refueling Water Storage Tank to the Reactor Coolant System (RCS) will not be affected by the proposed activities. The margin of safety as defined in the bases for the technical specifications will not be reduced. (SORC 95-052)

• r 10CFR50.59 EVALUATIONS DOCKET NO: 50-272 110NTH:~Y1995 UNIT NAME: SALEM 1 I DATE: 06/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 (Cont'd)

4. Deficiency Reports (DR) Us~-As-Is DRDSI.8-0010/ "DR 950501234 "V5H Fuel Grid Mxing Vanes" Rev. 0 - This safety evaluation is being written to provide a use-as-is disposition to DR 950501234 which documents the non-conforming condition which presently exists in the V5H fuel loaded at Salem Units 1and2. During the manufacturing of the 17 x 17 fuel assembly grid straps, the mid-grid mixing vanes were under bent. Westinghouse has since determined that the mean production vane angle for the as loaded Salem VHS fuel assemblies could be as much as 2.2° less than the mean angle in place during design basis DNB testing. Since the vanes are under bent, there is no risk of mechanical contact with a fuel rod. Westinghouse has concluded that the under bent vanes do not adversely affect the mechanical or structural integrity of the fuel assemblies. Westinghouse has determined that a conservative evaluation of the under bent mixing vanes results in a 1.9% DNBR penalty. Since sufficient DNBR margin still exists, no safety limits have been violated and the conclusions of the UFSAR Chapter 15 accident analyses remain valid. The change in vane grid angle does not result in changing any fuel related limits or design failure points. Although generic DNBR margin is affected by this change, the limits as defined by any technical specification basis are not affected. Hence the margin of safety is preserved. (SORC 95-042)

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REFUELING INFORMATION DOCKET NO: 50-272 MONTH: MAY 1995 UNIT NAME: SALEM 1

• DATE: 06/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH : MAY 1995 Refueling information has changed from last month: YES~NO X Scheduled date for next refueling: September 9. 1995 Scheduled date for restart following refueling: November 7. 1995-

a. Will Technical Specification changes or other license amendments be required?

YES X NO~

NOT DETERMINED TO DATE

b. Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X Ifno, when is it scheduled? September 1995 Scheduled date(s) for submitting proposed licensing action: NIA Important licensing considerations associated with refueling:

Number of Fuel Assemblies:

a. Incore 193

b. In Spent Fuel Storage 732 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-l-7.R4

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• SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 MAY 1995 SALEM UNIT NO. 1 The Unit began the period operating at 94% power and continued at that level until 5/4, when load was reduced to 50% to support replacement of both Steam Generator Feedwater Pump (SGFP) governors. A power increase was initiated on 5/14, following completion of SGFP

. post maintenance testing. On 5/15, the power increase was stopped at 60% due to concerns over operability of equipment serviced by #12 & 13 switchgear supply fans. The #13 fan motor had failed on 5/14, and #12 had been out of service due to a failed motor bearing. The appropriate justification for continued operation with only one fan could not be obtained and a conservative decision was made to shutdown. The Unit was removed from service on 5/17, and remained shutdown throughout the rest of the period.