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

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. 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 Sincerely yours, (U/J-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 Energy People ,-930819c1202-

-930731 ------n

_ ADOCK 05000311 _ -!' Q 0 5 PDR I 95-2189 (10M) 12-89

DAILY UNIT POWER 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: Date: Completed by: Mark Shedlock Telephone:

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) Report, Give Reason NA 9. Power Level to Which Restricted, if any (Net MWe) 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) 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 NA This Month Year to Date 744 5087 744 2513.11 0 0 691. 60 2367.11 0 0 2121232.8 7720483.2 681990 2595940 649079 2445836 93 46.5 93 46.5 78.9 43.5 78.2 43.1 .1 21.7 50-311 8/10/93 339-2122 < since Last NIA cumulative 103440 66278.71 0 63925.57 0 152816173 67303428 64031812, 61. 8 61.8 56.0 55.5 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 NO. DATE. 0022 6-11-93 0023 7-6-93 0024 7-6-93 0025 7-8-93 0027 7-10-93 0028 7-11-93 0030 7-14-93 0031 7-28-93 1 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 F 520.38 A F 8.0 B F 38.12 B F 29.02 B F 32.80 B F .83 B F 29.27 B F 29.77 B 2 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction

_ UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1993 METHOD OF SHUTTING DOWN REACTOR 4 5 4 5 4 4 5 5 LICENSE EVENT REPORT # ---------IB ---------CB ---------CB ---------CH ---------CH ---------CH ---------HF ---------HF 3 Method: 1-Manual 2-Manual Scram SYSTEM CODE 4 E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)

H-Other (Explain)

COMPONENT CODE 5 CONRAD INSTRU INSTRU xxxxxx xxxxxx xxxxxx PUMPXX PUMPXX 4 DOCKET NO. UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 Salem #2 Mark Shedlock" 339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE NUCLEAR CONTROL ROD INSTRUMENTATION NUC. PRESSURIZER LEVEL INST. & CONTROLS NUC. PRESSURIZER LEVEL INST. & CONTROLS NUCLEAR OTHER CORE/FUEL PROBLEMS CHEM. NUCLEAR OTHER CORE/FUEL PROBLEMS CHEM. FEEDWATER CHEMISTRY CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS 5 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File Exhibit 1 -Same Source (NUREG-0161)

SAFETY RELATED MAINTEN.E MONTH: -JULY 1993 DOCKETttO:

UNIT NAME: 50-311 SALEM 2 WO NO UNIT 930112090 2 930121207 2 930428098 2 930604156 2 931009018 2 DATE: COMPLETED BY: TELEPHONE:

AUGUST 10, 1993 R. HELLER (609)339-2212 EQUIPMENT IDENTIFICATION GRAB SAMPLE PALLET GSP-1 FAILURE DESCRIPTION:

GRAB SAMPLE PALLET VALVES LEAK BY -REPAIR FIRE DAMPER 2CVF603 FAILURE DESCRIPTION:

OPEN AND REPAIR DAMPER 2CVF603 VALVE 2SJ70 FAILURE DESCRIPTION:

2SJ70 FAILED SURVEILLANCE

-PERFORM RADIOGRAPHY OVERHEAD ANNUNCIATOR FAILURE DESCRIPTION:

OHA ROD INSERTION LIMIT DID NOT REFLASH FOR STARTUP -INVESTIGATE "B" REACTOR TRIP BREAKER FAILURE DESCRIPTION:

REPLACE UNDERVOLTAGE TRIP DEVICE 10CFR50.59 MONTH: -JULY 1993 DOCKETttO:

UNIT NAMB: DATE: COMPLETED BY: TELEPHONE:

50-311 SALEM 2 AUGUST 10, 1993 R. HELLER (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 UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 2 JULY 1993 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 49 MONTH: -JULY 1993 MONTH JULY 1993 DOCKET,O:

UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

1. Refueling information has changed from last month: YES NO 50-311 SALEM 2 AUGUST 10, 1993 R. HELLER (609)339-2212

2. Scheduled date for next 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 __ 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