ML18101A591

Monthly Operating Rept for Feb 1995 for Salem Unit 2.W/ 950315 Ltr

ML18101A591
Person / Time
Site:	Salem
Issue date:	02/28/1995
From:	Morroni M, Summers J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9503210060
Download: ML18101A591 (10)

Text

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. e OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit March 15, 1995 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 2 DOCKET NO: 50-311 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 February are being sent to you.

Sincerely yours, 1ftfu.__,

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 8-1-7.R4

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~ OPERATING DATA REPORT ~

Docket No: 50-311 Date: 03/10/95 Completed* by: Mike Morroni Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period February 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

11. Hours in Reporting Period 672 1416 117289

12. No. of Hrs. Rx. was Critical 266 266 75881. 2

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 89.2 89.2 73057.1

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 136886.4 13886.4 181110670.6 Gross Elec. Energy Generated (MWH) 30350 30350 76480358

18. Net Elec. Energy Gen. (MWH) 12090 - 5777 72717767

19. Unit Service Factor 13.3 6.3 62.3

20. Unit Availability Factor 13.3 6.3 62.3

21. Unit Capacity Factor (using MDC Net) 1. 6 0 56.1

22. Unit Capacity Factor (using DER Net) 1.6 0 55.6

23. Unit Forced Outage Rate 85.1 85.1 22.2

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

We are presently in a maintenance outage.

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

3 07 95.

8-1-7.R2

.ERAGE DAILY UNIT POWER LE. .

Docket No.: 50-311 Unit Name: Salem #2 Date: 03-10-95 Completed* by: Mike Morroni Telephone: 339-2122 Month February 1995 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 339 2 ,o 18 401 3 0 19 239 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 14 0 30 15 0 31 16 128 P. 8.1-7 Rl

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1995 DOCKET NO. 50-272 UNIT NAME Salem #2 DATE 3-10-95 COMPLETED BY Mike Morroni TELEPHONE 339-5142

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SHUTTING LICENSE

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TYPE 1 I'. (HOURS)*  !' REASON 2 REACTOR *REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE

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. 02/01/95. ,,.*, s.: _': 72 I

l*, c ', 4 ------------ RC FUELXXXXXX NORMAL REFUELING i  :

. 2346 02/03/95 I... F- 291.3. '. D 4 .. ...................... IA xxxxxxxxxx SSPS DESIGN INADEQUACY 2371 02/19/95 . . ,

F .. 236 A 1 ------------ CB PUMPXXXXXX 21 RCP SEAL 1-----------  :

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1 2 3 4 5 F: Forced ... :.*c 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-Refuel ing - .* ..' 3-Automatic Scram Event Report CLER) File

• ~* D-Requlatory Restriction ,,, 4-Continuation of CNUREG-0161)

E-Operato~:Training & License Examination Previous outage

-: **'-' F-Admini strative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

10CFRS0.59 EVALUATIONS DOCKET NO: 50-311 MONTH: FEBRUARY 1995 UNIT NAME: SALEM2 DATE: 03/10/95 COMPLETED 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.

1. Design Change Packages (DCP) 2EC-3323, Pkg. 1 "Revision of Rod Control System Auctioned Ave Lead/Lag Module and Filter Module Time Constants" Rev. 0 - The purpose of this DCP is to implement a recommendation from the primary vendor to PSE&G that the filter time constant (module 2TM-412P be revised to 10 seconds, the lead/lag time constant (module 2TM-412Q) be revised to 40/10. These changes are being made to eliminate false rod stepping. Operation of the plant with the revised rod control system compensation parameters does not adversely affect any physical parameters or conditions which are addressed in the Technical Specifications. The FSAR accident analysis remains bounding. Therefore, the margin of safety, as defined in the bases to the Technical Specifications is not reduced. (SORC 95-013) 2EC-3351, Pkgs.1&2 "SSPS Turbine Building Inputs" Rev. 0 - This modification reconfigures the SSPS input bay wiring such that the logic power supplies will not be affected by a postulated short to ground of the SSPS input wiring that interfaces with contacts in the turbine building. The new configuration moves the 120 V AC power feed for the SSPS logic power supplies upstream of existing 15 amp fuses such that fuses feed only the input relays through contacts located in the turbine building. The power supplies are individually fused.

The modification also replaces existing 15 amp fuses with 5 amp fuses to properly coordinate with the upstream breaker.

These modifications only correct a condition which was not previously thought to be credible, that is, a loss of the SSPS functionality due to a Design Basis Event. These modifications do not, in any way, alter

• 10CFRS0.59 EVALUATIONS DOCKET NO: 50-311 MONTH: FEBRUARY 1995 UNIT NAME: SALEM 2 DATE: 03/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 the function of SSPS. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 95-017) 2EE-0088, Pkg. 1 No. 22 Charging Safety Injection Pump Inboard Mechanical Seal Housing Replacement" Rev. 0 - This modification entails the replacement of a leaking inboard mechanical seal assembly and seal housing on No. 22 Charging Safety Injection (C/SI) pump. The seal housing of the new mechanical seal assembly, which is a later design, does not have the jacket water cooling connections or a design requirement for these cooling connections. As noted in Dresser Pacific (pump manufacturer) letter dated 8/24/84, the later design seal housings were revised to eliminate the cooling water jackets in 1976 and all pumps manufactured since have no seal housing water jackets. Nos. 11, 12 and 21 C/SI pumps have already been updated with new mechanical seals and housing and the component cooling connections have been cut back and capped. Unlike the other pumps, at this time, the proposed change to No. 22 C/SI pump will not change the outboard mechanical seal, which still has active connections for cooling the seal housing. The operability and reliability of the charging pump is not affected by the installation of a replacement seal assembly. The acceptance criteria for the design basis accidents continue to be met and the margin of safety as defined in the Technical Specifications is unchanged.

(SORC 95-025)

2. Temporary Modifications (T-Mods)95-020 "Blind Flange Installation at Relief Valves 21-23CN141/142 and 21 and 22BF82" Rev. 0 - The purpose ofthis T-Mod is to remove reliefvalves 21-23CN141/142 and 21 and 22BF82 and install blind flanges to restore the leak tight integrity of the condensate and feedwater systems

10CFRS0.59 EVALUATIONS DOCKET NO: 50-311 MONTH: FEBRUARY 1995 UNIT NAME: SALEM 2 DATE: 03/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 (Cont'd) respectively. The subject valves which are currently leaking through the valve seats, were installed to provide thermal relief protection for sections of piping/components in the condensate and feed water system, which if isolated during system heatup or power operations, could be ovepressurized. The subject relief valves were not designed/ installed to provide overall system overpressurization protection during normal system operations or transient conditions. The piping/components being temporarily modified are classified as non-safety related/non-seismic and perform no safety function.

Therefore, this modification will have no impact on any systems or equipment required for safe shutdown. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 95-020)93-140 "Salem Unit 2 Fuel Handling Crane Upgrade for Spent Fuel Pool Reracking - Revision to Ambient Temperature Requirement in Fuel Handling Building and Installation of Heater Plates on Top of Rack Handling Trolley" Rev. 1 -

To increase the spent fuel storage capacity of the Spent Fuel Pool (SFP), the existing nine Exxon racks will be removed and replaced with nine new Holtec racks. Due to the weight of the racks, the Fuel Handling Crane capacity needs to be increased from 5 tons to 20 tons. This T-Mod will install a new trolley and hoist for the removal and installation of racks. The existing trolley and hoist will be used for moving the spent fuel. The purpose of this revision is to add heater strips to the fracture critical members of the new trolley to maintain a temperature above 45°F when the ambient temperature falls below that level. This upgrading is in compliance with the provisions ofNUREG-0554, and in accordance with Appendix C to NUREG-0612. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 95-020)

• 10CFRS0.59 EVALUATIONS DOCKET NO: 50-311 MONTH: FEBRUARY 1995 UNIT NAME:* SALEM 2 DATE: 03/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162

3. Deficiency Reports (Use-As-Is) 950131128 "Justification For Allowing Uninsulated Portion of Pipe on 2PR3, 4 & 5 Inlet to Remain Uninsulated Until Next Outage" Rev. 0 - This proposal allows a small portion of the pressurizer safety relief valve (SRV) inlet piping to remain uninsulated until the next refueling outage. This proposal does not add, delete or modify any safety related equipment or components. The lack of insulation on a small portion of the SRV inlet piping does not compromise the safety related function of any safety related electrical equipment, the SRVs, or their associated piping. As such, this proposal does not impact any anticipated operational transients or design basis accidents previously evaluated in the UFSAR. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 95-016)

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REFUELING INFORMATION

• DOCKET NO:

• 50-311 MONTH: FEBRUARY 1995 UNIT NAME: SALEM2 DATE: 03/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH: FEBRUARY 1995

1. Refueling information has changed from last month: YES X'NO

2. Scheduled date for next refueling: April 6. 1996 Scheduled date for restart following refueling: June 5. 1996

3. 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? April 1996

5. Scheduled date(s) for submitting proposed licensing action: _ _ ____,.N~/~A=_ _ __

6. Important licensing considerations associated with refueling:

7. Number ofFuel Assemblies:

a. Incore 193

b. In Spent Fuel Storage 556

8. Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632

9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: March 2012 8-1-7.R4

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 FEBRUARY 1995 SALEM UNIT NO. 2 The Unit began the period shutdown as the refueling outage activities continued. The Unit entered Mode 2 (Startup) on February 10, 1995, and was synchronized to the grid on February 16, 1995. During the subsequent power escalation, problems developed with No. 21 Reactor Coolant Pump (RCP) seal leakoffflow and on February 19, 1995, the Unit was removed from service. The Unit remained shutdown throughout the rest of the period while the RCP seal replacement was in progress.

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