ML18100A549

Monthly Operating Rept for Jul 1993 for Salem,Unit 2.W/ 930813 Ltr

ML18100A549
Person / Time
Site:	Salem
Issue date:	07/31/1993
From:	Heller R, Shedlock M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9308190202
Download: ML18100A549 (8)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station August 13, 1993 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 July 1993 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, (U/J-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

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~ERAGE DAILY UNIT POWER L~

Docket No.: 50-311 Unit Name: Salem #2 Date: 8/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Month July 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 1069 2 0 18 1108 3 175 19 1042 4 380 20 1117 5 395 21 1074 6 431 22 1057 7 510 23 1072 8 661 24 1118 9 864 25 1112 10 997 26 1097 11 1040 27 1093 12 1069 28 1088 13 1091 29 1090 14 1051 30 1084 15 1027 31 1097 16 1114 P. 8.1-7 Rl

OPERATING DATA REPORT e Docket No: 50-311 Date: 8/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Operating status

1. Unit Name Salem No. 2 Notes

2. Reporting Period July 1993 <

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) NIA

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

11. Hours in Reporting Period 744 5087 103440

12. No. of Hrs. Rx. was Critical 744 2513.11 66278.71

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 691. 60 2367.11 63925.57

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2121232.8 7720483.2 152816173 Gross Elec. Energy Generated (MWH) 681990 2595940 67303428

18. Net Elec. Energy Gen. (MWH) 649079 2445836 64031812,

19. Unit Service Factor 93 46.5 61. 8

20. Unit Availability Factor 93 46.5 61.8

21. Unit Capacity Factor (using MDC Net) 78.9 43.5 56.0

22. Unit Capacity Factor (using DER Net) 78.2 43.1 55.5

23. Unit Forced Outage Rate .1 21.7 22.8

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-l-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1993 DOCKET NO. 50-272 UNIT NAME Salem #2 DATE 08/10/~3 COMPLETED BY Mark Shedlock" TELEPHONE 339-2122 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 5 TO PREVENT RECURRENCE 0022 6-11-93 F 520.38 A 4 --------- IB CONRAD NUCLEAR CONTROL ROD INSTRUMENTATION 0023 7-6-93 F 8.0 B 5 --------- CB INSTRU NUC. PRESSURIZER LEVEL INST. &CONTROLS 0024 7-6-93 F 38.12 B 4 --------- CB INSTRU NUC. PRESSURIZER LEVEL INST. &CONTROLS 0025 7-8-93 F 29.02 B 5 --------- CH xxxxxx NUCLEAR OTHER CORE/FUEL PROBLEMS CHEM.

0027 7-10-93 F 32.80 B 4 --------- CH xxxxxx NUCLEAR OTHER CORE/FUEL PROBLEMS CHEM.

0028 7-11-93 F .83 B 4 --------- CH xxxxxx FEEDWATER CHEMISTRY 0030 7-14-93 F 29.27 B 5 --------- HF PUMPXX CIRCULATING WATER PUMPS 0031 7-28-93 F 29.77 B 5 --------- HF PUMPXX CIRCULATING WATER PUMPS 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 (NUREG-0161)

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

~ MONTH:

SAFETY RELATED MAINTEN.E

- JULY 1993 DOCKETttO:

UNIT NAME:

50-311 SALEM 2 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 WO NO UNIT EQUIPMENT IDENTIFICATION 930112090 2 GRAB SAMPLE PALLET GSP-1 FAILURE DESCRIPTION: GRAB SAMPLE PALLET VALVES LEAK BY

- REPAIR 930121207 2 FIRE DAMPER 2CVF603 FAILURE DESCRIPTION: OPEN AND REPAIR DAMPER 2CVF603 930428098 2 VALVE 2SJ70 FAILURE DESCRIPTION: 2SJ70 FAILED SURVEILLANCE -

PERFORM RADIOGRAPHY 930604156 2 OVERHEAD ANNUNCIATOR FAILURE DESCRIPTION: OHA ROD INSERTION LIMIT DID NOT REFLASH FOR STARTUP - INVESTIGATE 931009018 2 "B" REACTOR TRIP BREAKER FAILURE DESCRIPTION: REPLACE UNDERVOLTAGE TRIP DEVICE

10CFR50.59 EVALUATIONS~

MONTH: - JULY 1993 DOCKETttO:

UNIT NAMB:

50-311 SALEM 2 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 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

A. Design Change Packages 2SC-2292 Pkg 1 "Replacement of Condenser Coatings" - This Design Change Package (DCP) includes the following Unit 2 modifications: a) provide new coatings for the six inlet and six outlet waterboxes, associated tubesheets and other internal components for the main steam condenser. The waterboxes will be coated with a thin film (30-35 mils) multilayer coating; the tubesheets will receive a thick film. (200 + 40 mils) coating; b) replace 6" waterbox drain valves 21CW31, 21CW131, 22CW31, 22CW131, 23CW31 and 23CW131 with fully lined plug valves, and c) relocate valves 21CW31 and 22CW31 for better access. These modifications will: a) provide erosion/corrosion protection in the inlet and outlet condenser waterbox interior and exterior surfaces as well as the tubesheets; b) ensure better reliability from debris accumulation due to infrequent use, and c) provide improved accessibility. The Salem Technical Specifications do not address the main condensers.

Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-060)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 JULY 1993 SALEM UNIT NO. 2 The unit started the period with the reactor critical and physics testing in progress. The unit was synchronized to the grid on July 3, 1993, ending the refueling outage. During the subsequent power ascension, power was briefly held to allow replacement of 22 Steam Generator Feedwater Pump (SGFP) governor. The unit achieved 100%

power on July 10, 1993, following completion of maintenance. With the exception of minor load reductions to address: secondary chemistry problems; SGFP suction pressure oscillations; Tave spikes and feedwater heater suction pressure swings, the unit continued to operate at full power throughout the remainder of the period.

• • REFbELING INFORMATION MONTH: - JULY 1993 49 DOCKET,O:

UNIT NAME:

50-311 SALEM 2 DATE: AUGUST 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 MONTH JULY 1993

1. Refueling information has changed from last month:

YES NO -~X-~

2. Scheduled date for next refue~ing: SEPTEMBER 24, 1994

3. Scheduled date for restart following refueling: NOVEMBER 22, 1994

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?:

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 464

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-l-7.R4