ML18101A183

Monthly Operating Rept for Jul 1994 for Salem Generating Station Unit 2.W/940812 Ltr

ML18101A183
Person / Time
Site:	Salem
Issue date:	07/31/1994
From:	HAGAN J J, MORRONI M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9408190224
Download: ML18101A183 (7)

Text

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New 08038 Salem Generating Station August 12, 1994 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 1994 are being sent to you. RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours, cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-l-7.R4 Th53 l::nerny People 9408190224 940731 PDR ADOCK 05000311 R PDR 95-2189 (10M) 1 -89

DAILY UNIT POWER Completed by: Mike Morroni Month July 1994 Day Average Daily Power Level (MWe-NET) 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 315 13 899 14 999 15 1067 16 1037 P. 8.1-7 Rl Day Docket No.: 50-311 Unit Name: Salem #2 Date: 08-10-94 Telephone:

339-2122 Average Daily Power Level (MWe-NET) 17 1011 18 1027 19 1033 20 1019 21 1032 22 1027 23 1024 24 1021 25 1015 26 1015 27 1035 28 1042 29 1033 30 1049 31 1042

• OPERATING DATA REPORT

• Docket No: 50-311 Date: 08/10/94 Completed by: Mike Morroni Telephone:

339-2122 Operating Status 1. Unit Name Salem No. 2 Notes 2. Reporting Period July 1994 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

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 This Month 744 525.08 0 477.77 0 1582257.6 495560 466128 64.2 64.2 56.6 56.2 35.8 Year to Date Cumulative 5087 112200 4723.76 74003.32 0 0 4517.07 71406.59 0 0 13596047.7 176058987.1 4332880 74879398 4116463 71243740 88.8 63.6 88.8 63.6 73.2 57.4 72.6 56.9 9.4 21.9 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Refueling outage scheduled to start October 15, 1994 and last 60 da s. 25. If shutdown at end of Report Period, Estimated Date of Startup: NA 8-l-7.R2 NO. DATE 1288 07-01-94 1 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1994 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM TYPE 1 (HOURS) REASON 2 REACTOR REPORT # COOE 4 F 266.23 A 3 ----------

CH 2 3 Reason A-Equipment Failure (explain)

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

H-Other (Explain)

Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther DOCKET NO. 50-272

• Salem #2 08-10-94.

UNIT NAME DATE COMPLETED BY TELEPHONE:

Mike Morroni__, 339-2122 . COMPONENT CAUSE AND CORRECTIVE ACTION COOE 5 TO PREVENT RECURRENCE PUMPXX OTHER FEEDWATER PUMP PROBLEMS 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -Same Source *

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10CFR50.59 EVALUATIONS MONTH: JULY 1994 . '

• DOCKET I UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-311 SALEM 2 AUGUST 10, 1994 R. HELLER (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.

ITEM

SUMMARY

NONE FOR THE PERIOD J SALEM UNIT NO. 2 *

• SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 2 JULY 1994 The Unit began the period shutdown as investigations into the June 29, 1994 reactor trip continued.

On July 3, 1994, the Unit was cooled down to Mode 5, "Cold Shutdown," due a flange leak on 22 Reactor Coolant Pump. The repairs were completed and startup activities commenced.

on July 13, 1994, during the power escalation, power was briefly held at 90% for resolution of a heater drain pump control valve problem. Power was increased to 100% on July 14, 1994, and the Unit continued to operate at essentially full power throughout the remainder of the period.

' REFUELING INFORMATION MONTH': _,. JULY 1994 ,. J w ' '"' MONTH JULY 1994

• DOCKET I UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

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

2. Scheduled date for next refueling:

OCTOBER 15, 1994 50-311 SALEM 2 AUGUST 10, 1994 R. HELLER (609)339-5162

3. Scheduled date for restart following refueling:

DECEMBER 13, 1994 4. a) Will Technical Specification changes or other license amendments be required?:

YES NO NOT DETERMINED TO DATE b) Has the reload fuel design been reviewed by the Station Operating Review Committee?:

YES NO If no, when is it scheduled?:

OCTOBER 94 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 492 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