ML18096B043

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Monthly Operating Rept for Sept 1992 for Salem Unit 2.W/ 921013 Ltr
ML18096B043
Person / Time
Site: Salem PSEG icon.png
Issue date: 09/30/1992
From: Fest J, Shedlock M, Vondra C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9210190188
Download: ML18096B043 (9)
v • d • e


Text

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  • Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station October 13, 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 September 1992 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 PORV or Safety Valve Challenges Refueling Information Since elY. yours, RH:pc

Z#r:!--

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

_T_he Energy People

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  • OPERATING DATA REPORT.

Docket No: 50-311 Date: 10/10/92 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 2 Notes
2. Reporting Period September *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
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 ~~~~N~A"'-~~~~~~~~~~~~~~

This Month Year to Date Cumulative

11. Hours in Reporting Period 720 6575 96144
12. No. of Hrs. Rx. was critical 640.8 2940.5 61556.6
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator on-Line 627.3 2511.8 59410.6
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 2032075.2 7789552.8 137901274.6
17. Gross Elec. Energy Generated (MWH) 674930 2535970 62263018
18. Net Elec. Energy Gen. (MWH) 643931 .2370243 59238528
19. Unit Service Factor 87.1 38.2 61.8
20. Unit Availability Factor 87.. 1 38.2 61.8
21. Unit Capacity Factor (using MDC Net) 80.9 32.6 55.7
22. Unit capacity Factor (using DER Net) 80.2 32.3 55.3
23. Unit Forced outage Rate 12.9 26.0 23.4
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling outage scheduled to start 03/27/93 and last 55 days.

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

NA 8-1-7.R2

. ' ttvERAGE DAILY UNIT POWER L:9L Docket No.: 50-311 Unit Name: Salem #2 Date: 10/10/92 Completed by: Mark Shedlock Telephone: 339-2122 Month September 1992 Day Average Daily .Power Level Day Average Daily Power Level*

(MWe-NET) (MWe-NET) 1 1107 17 1099 2 1075 18 1103 3 413 19 1114 4 0 20 1113 5 0 21 1106 6 0 22 1090 7 359 23 1098 8 1086 24 1098 9 1073 25 1113 10 1088 26 340 11 1097 27 1065 12 1107 28 1028 13 1100 29 1002 14 1084 30 1072 15 858 31 16 1051 P. 8.1-7 Rl

UNIT SHUTDOIJN AND POIJER REDUCTIONS REPORT MONTH SEPTEMBER 1992 DOCKET NO.: ~5~0~*~31""'1_ __

UNIT NAME: Salem #2 DATE: 10/10/92 COMPLETED BY: Mark Shedlock TELEPHONE: 339-2122 METHOD OF -

SHUTTING LICENSE DURATION DOIJN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # COOE 4 COOE 5 TO PREVENT RECURRENCE 0022 09/03/92 F 92.7 A 3 ------ IA CKTBRK REACTOR TRIP BREAKER TRIP 0021 09/15/92 F 15.3 A 5 I

HJ VAL VEX REHEAT STOP VALVE 0023 09126/92 F 16.2 I

A 5 ------ HF MOTORX CIRCULATING WATER PUMPS 0024 09/26/92 F 3.2 B 5 ------ RB zzzzzz REACTOR PERFORMANCE DATA 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

&-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refuel ing 3-Automatic Scram Event Report (LER) File D-Requlatory Restriction 4-Continuation of (NUREG-0161)

E-Operator Training & License Examination Previous Outage F-Aaninistrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain>

MONTH: *

  • .SAFETY RELATED MAINTENANCE SEPTEMBER 1992
  • DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

50-311 SALEM 2 OCTOBER 10, 1992 J. FEST TELEPHONE: (609)339-2904 WO No* .UNIT EQUIPMENT IDENTIFICATION 920811102 2 VALVE 26SW25 FAILURE DESCRIPTION: VALVE NOT FULLY CLOSING, INSPECT

& REPAIR 920916077 2 2C DIESEL GENERATOR FAILURE DESCRIPTION: CLEAN OR REPLACE THE STARTER 920921116 2 PZR LEVEL FAILURE DESCRIPTION: PZR LEVEL CHANNEL II 3% DIFFERENT FROM CHANNELS I AND III -

INVESTIGATE

~----------------

  • EVALUATIONS MONTH: - SEPTEMBER 1992 *
  • DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

50-311 SALEM 2 OCTOBER 10, 1992 J. FEST 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 and concurs with these evaluations.

ITEM

SUMMARY

(None for the period.)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 SEPTEMBER 1992 SALEM UNIT NO. 2 The Unit began the period operating at full power. On September 3, 1992, a Reactor Scram occurred due to the "A" Reactor Trip Breaker opening without a demand signal~ An Unusual Event (UE) was declared following the trip due to steam generator safety valves lifting and not reseating as expected. The UE was terminated following closure of the safety valves. The Unit was restored to full power on September 7, 1992, and continued to operate at full power until September 15, 1992, when power was reduced to 40% to repair 11 22w 11 reheat stop valve. The repairs were completed and the Unit was restored to full power later, the same day. The Unit continued to operate at full power until September 26, 1992, when power was reduced to 28% due to tripping of the circulators which are powered from the Hope Creek Switchyard. The Unit was returned to full power on September 27, 1992, and continued to operate at essentially full power throughout the remainder of the period.

CijALLENGES TO PORVs OR SAFETY VALVES

  • 09/03/92 - On September 3, 1992, at 0938 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.56909e-4 months <br />, following a trip of Salem Unit 2, Main steam Safety Valves 21MS15 and 22MS15 lifted. The highest observed steam Generator pressures were 1020 psig on 21 and 22 steam Generator (S/G) loops, while 1035 psig was observed on 23 S/G. This pressure was higher than the others due to the 23MS10 being tagged for maintenance. An Unusual Event (UE) was declared at 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br /> due to 21 and 22MS15s lifting and failing to reseat at a pressure (980 psig) below the safety valve setpoint. A cooldown was started at about 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br /> to reseat the safety valves. 22MS15 briefly reseated from 1018 to 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br /> with 22 S/G pressure at 990 psig. 21MS15 reseated at 1029 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.915345e-4 months <br /> with Tave.at 547°F and 21 S/G pressure at 980 psig. 22MS15 reseated fully at 1041 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.961005e-4 months <br /> with Tave at 540°F and S/G pressure at 930 psig. A slow heatup was commenced at 1118 hours0.0129 days <br />0.311 hours <br />0.00185 weeks <br />4.25399e-4 months <br /> to verify proper reseating of the safety valves. The heatup was terminated at 1235 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.699175e-4 months <br /> due to leakage observed from the safety valves at 544.6°F on RCS Tave and at 986 and 970 psig pressures in 21 and 22 S/Gs respectively. Three safety valve lift setpoints (21-23MS15) have been determined to have lifted within the 3% tolerance band of the rated lift setpoint.

Adjustments were made to all three valves to restore them to the 1% acceptance criterion.

, ,.REFUELIMG "INFORMATION MONTH:,- SEPTEMBER 1992 DOCKET NO:

UNIT NAME:

DATE:

50-311 SALEM 2 OCTOBER 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 MONTH SEPTEMBER 1992

1. Refueling information has changed from last month:

YES NO ---=X_ _

2. Scheduled date for next refueling: MARCH 27, 1993
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
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