ML18096A784

Monthly Operating Rept for May 1992 for Salem,Unit 2.W/ 920612 Ltr

ML18096A784
Person / Time
Site:	Salem
Issue date:	05/31/1992
From:	Shedlock M, Vondra C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9206230113
Download: ML18096A784 (9)

Text

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station June 12, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 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 May 1992 are being sent to you. RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information lida General Manager -Salem Operations cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The Energy

__ _ --*9*206-2:30113 920531 PDR ADOCK 05000311 R

• PDR ' 1'\ (, '(*' h J t ., * ' ; ,., \.)\,.)'..IV 95-2189 (10M) 12-89

.. .ERAGE DAILY UNIT POWER Docket No.: Unit Name: Date: Completed by: Mark Shedlock Telephone:

Month May 1992 50-311 Salem #2 06/10/92 339-2122 Day Average Daily Power Level (MWe-NET)

Day Average Daily Power Level (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 158 5 0 21 749 6 0 22 531 7 0 23 958 8 34 24 1027 9 32 25 936 10 159 26 1082 11 361 27 1074 12 389 28 488 13 380 29 826 14 0 30 1090 15 0 31 4'87 16 0 P. 8.1-7 Rl 1--1 Completed by: Operating Status

• OPERATING DATA REPORT Mark Shedlock

• Docket No: Date: Telephone:

1. Unit Name Salem No. 2 Notes 2. Reporting Period May 1992 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 50-311 06/10/92 339-2122 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give

9. Power Level to Which Restricted, if any (Net MWe) N/A 10 .. Reasons for Restrictions, if any

11. 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 This Month 744 583.45 0 392.22 0 949466.4 276030 248632 52.7 52.7 30.2 30.0 0 Year to Date Cumulative 3647 93216 731.94 59348.07 0 0 392.22 57290.97 0 0 970305.6 130172122.1 276030 60003078 221685 57089970 10.8 61.4 10.8 61.4 5.5 55.4 5.5 54.9 15.5 23.3 24. Shutdowns scheduled over next 6 months (type, date and duration of each) NA 25. If shutdown at end of Report Period, Estimated Date of Startup: NA 8-1-7.R2 NO. DATE 0001 01/04/92 0002 05/08/92 0003 05/14/92 0004 05/09/92 1 . F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MAY 1992 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM TYPE 1 (HOURS) REASON 2 s 3026.23 s 10.77 s 15.67 s 130.07 2 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction c c c c E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain)

REACTOR 4 4 4 4 3 REPORT # -.. --.... .............

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Method: 1-Manual 2-Manual Scram COOE 4 RC RC RC RC 3-Automatic Scram 4-Continuation of Previous outage 5-Load Reduction 9-0ther DOCKET NO.: 50-311 UNIT NAME:

DATE: 06/10/92 *-, COMPLETED BY: .Hark Shedlock i TELEPHONE:

339-2122 ', COMPONENT CAUSE AND CORRECTIVE ACTION COOE 5 TO PREVENT RECURRENCE FUELXX NUCLEAR NORMAL REFUELING FUEL XX NUCLEAR NORMAL REFUELING FUEL XX NUCLEAR NORMAL FUELXX NUCLEAR NORMAL 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161)

REFUELING REFUELING 5 Exhibit 1 -Same Source ._

• SAFETY RELATED MAINTENANCE MONTH: MAY 1992 DOCKET NO: UNIT NAME: 50-311 SALEM 2 .WO NO UNIT 891109085 2 920428130 2 920514207 2 920515135 2 DATE: COMPLETED BY: TELEPHONE:

JUNE 10, 1992 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION VALVE 2NT34 FAILURE DESCRIPTION:

VALVE 2NT34 HAS A BODY TO BONNET LEAK -REPLACE GASKET #21 AUXILIARY FEEDWATER PUMP FAILURE DESCRIPTION:

INVESTIGATE THE OPERATION OF 21 AFWP DISCHARGE PRESSURE CONTROLS VALVE 23BF40 FAILURE DESCRIPTION:

OPEN AND INSPECT VALVE -REPAIR AS DIRECTED FEEDWATER CONTROLS VALVES 21-24 BF19 & 40 FAILURE DESCRIPTION:

INSPECT THE LINKAGES OF VALVE 21-24 BF19 & 40. REPAIR OR ADJUST AS NECESSARY

. 10CFR50.59 EVALUATIONS MONTH: MAY 1992 *

• DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-311 SALEM 2 JUNE 10, 1992 J. FEST (609)339-2904 The fallowing i terns were e.valuated 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.

ITEM

SUMMARY

A. Design Change Packages (DCP) DCP# 2EC-3056 Pkg. 1 B. Safety Evaluations S/E WO 920417117

c. Temporary Modifications TMR# SMD 92-035 "Control Room Modifications" -This DCP was issued to implement the corrective actions required to resolve fourteen of the Human Engineering Discrepancies (HED) identified in the Salem Unit 2 Control Room. The HEDs were generated during the Detailed Control Room Design Review conducted in accordance with NRC NUREG-0700 requirements.

A review of the Technical Specifications did not 'identify any setpoint, operational limit or design limit which is impacted by these modifications.

There is no reduction to the margin of safety as defined in the basis for any Technical Specifications. (SORC 92-063) "Breaching a Penetration Seal" -Activities associated with the work order involve breaching a penetration seal (Penetration N-25511-020) in a Unit 2 Auxiliary Building barrier for the purpose of routing a temporary commodity (that is, a welding lead), removing the temporary commodity, and restoring the penetration seal to its design basis configuration.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 92-061) "Installation and Use of a Skid Mounted Fire Pump" -This proposed modification involves the temporary installation and use of a skid mounted pump and diesel motor driver to exist as a secondary backup fire water system while both Salem Fire Water Pumps undergo maintenance repairs. Because this temporary pump serves only as a secondary backup to the Hope Creek 10CFR50.59 EVALUATIONS MONTH: -MAY 1992 (cont'd) ITEM *

• DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE: .

SUMMARY

50-311 SALEM 2 JUNE 10, 1992 J. FEST (609)339-2904 Fire Water system, which is considered the primary backup, the proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 92-063)

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• SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 2 MAY 1992 SALEM UNIT NO. 2 The Unit began the period shutdown for repairs to a main feed regulating valve. On May 10, 1992, the Unit was returned to service, following completion of repairs and turbine overspeed testing. During the subsequent power escalation, power was held at 47% for nuclear instrumentation calibrations.

On May 14, 1992, at 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, the Unit was taken off line due to steam generator chemistry conditions.

The steam generator cleanup was completed and power was increased to 20% in preparation for placing the Unit in service. Later, the same day, at 1757 hours0.0203 days <br />0.488 hours <br />0.00291 weeks <br />6.685385e-4 months <br />, a reactor trip occurred due to a low low level in #23 steam generator.

The Unit was synchronized on May 20, 1992, and a power escalation commenced.

On May 22, 1992, power was reduced from 88% to 50% to blowdown #22 steam generator feedpump suction strainer and adjust the pump governor controls.

The Unit achieved 100% power on May 23, 1992, and, with the exception of a minor load reduction to repair a gland leak on #22 heater drain pump, continued to operate at full power until May 27, 1992. On May 27, 1992, the Unit experienced a low suction pressure trip of #22 steam generator feedwater pump, and power was reduced to 53% for single feedwater pump operation.

Power was increased to 100% on May 29, 1992, but was reduced to 47% on May 30, 1992, in order to change oil in the steam generator feedwater pump oil reservoirs and to repair #21 condensate pump mechanical seal. The Unit continued to operate at 47% power throughout the remainder of the period.

REFUELING INFORMATION MONTH: -MAY __ 1992 MONTH MAY 1992 *

• DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

L Refueling information has changed from last month: YES NO

2. -scheduled date for next refueling:

MARCH 27, 1993 50-311 SALEM 2 JUNE 10, 1992 J. FEST (609)339-2904

3. Scheduled date for restart following refueling:

MAY 21, 1993 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?:

FEBRUARY 1993 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 408 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:

March 2003 8-1-7.R4