ML18101A341

Monthly Operating Rept for Oct 1994 for Salem Generating Station Unit 2.W/941114 Ltr

ML18101A341
Person / Time
Site:	Salem
Issue date:	10/31/1994
From:	Hagan J, Morroni M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9411230308
Download: ML18101A341 (10)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station November 14, 1994 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 2 DOCKETN0.: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 October 1994 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours, ager-Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue

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AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-311 Unit Name: Salem #2 Date: 11-10-94 Completed by: Mike Morroni Telephone: 339-5142 Month October 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 164 17 0 2 420 18 0 3 990 19 0 4 968 20 0 5 1035 21 0 6 1033 22 0 7 1037 23 0 8 1050 24 0 9 1021 25 0 10 1056 26 0 11 1040 27 0 12 1037 28 0 13 606 29 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 Rl

.. OPERATING DATA REPORT ~

Docket No: 50-311 Date: 11/10/94 Completed by: Mike Morroni Telephone: 339-5142 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period October 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 None.

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 745 7296 114409

12. No. of Hrs. Rx. was Critical 310.7 6335.7 75615.2

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 303.6 6078.4 72967.9

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) *941985.6 18510844.8 180973784.2 Gross Elec. Energy Generated (MWH) 288670 5903490 76450008

18. Net Elec. Energy Gen. (MWH) 271853 5606784 72734061

19. Unit Service Factor 40.8 83.3 63.8

20. Unit Availability Factor 40.8 83.3 63.8

21. Unit Capacity Factor (using MDC Net) 33.0 69.5 57.5

22. Unit Capacity Factor (using DER Net) 32.7 68.9 57.0

23. Unit Forced outage Rate 2.1* 10.1 21.8

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

We are presently in a maintenance and refueling outage scheduled to last 77 days.

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

December 29 1994.

• Monthly number has been adjusted to reflect a revision of Augusts monthly number and an adjustment due to feed flow nozzle inaccuracies.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH OCTOBER 1994 DOCKET NO. 50-311 ~*

UNIT NAME Salem*#2 DATE 11-10-94 COMPLETED BY M;ke Morron; TELEPHONE: -'3=3...,9_.-5._.1-..4.._2_ __

METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # COOE 4 COOE 5 TO PREVENT RECURRENCE 1785 10/01/94 F 6.6 G 4 ---------- CD zzzzzzzzzz INADVERTANT VALVE CLOSURE 1788 10/01/94 F 23.3 A 5 ---------- CH INSTRU STEAM GEN. FEED PUMP CONTROLS 1861 10/04/94 F .8 A 5 ---------* HC PUMPXX # 24 VACUUM PUMP 1862 10/04/94 F 7.6 A 5 ----------- CH VAL VEX # 23 CN27 VALVE 1881 10/13/94 s 434.8 c 1 ----------- RC FUELXX NORMAL REFUELING 1 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-Equ;pment Fa;lure (expla;n) 1-Manual for Preparation of Data Source B-Ma;ntenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refuel;ng 3-Automatic Scram Event Report CLER) File D-Requlatory Restr;ct;on 4-Continuation of (NUREG-0161)

E-Operator Tra;n;ng & L;cense Exam;nation Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

, 10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: OCTOBER 1994 UNIT NAME: SALEM2 DATE: 11/10/94 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 1

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.

1. Design Change Packages (DCP) 2EE-0053, Pkgs 1-4 Service Water System Check Valve Replacements - The proposed modification entails the replacement of check valves 21SW53, 22SW77, 21SW51, 2lSW79, 22SW5, 22SW51, 22SW79, 24SW5, 22SW53 and 22SW77. The existing check valves are carbon steel rubber lined Mission Duo Check Valves, which have a history of erosion/

corrosion problems due to the rubber lining becoming separated from the valve body, allowing the valve to leak by. The replacement valves are C&S Valve Co. Dual Plate, hard seat, 6% Molybdenum stainless steel valves which have excellent corrosion/erosion resistance. In addition, the valve closure spring configuration has been redesigned to alleviate valve plate chattering due to turbulence. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-077) 2EE-0060, Pkg. 1 Feedwater System, Section 1 Boundary Change - Change the Section I Code boundary of the feedwater system from the BF3 Valves to the BF19 valves. This will bring the boundary in line with Section 1, Figure PG-58.3.1 "Code Jurisdictional limits for Piping Drum type Boilers", and the PSE&G commitment to the State ofNew Jersey. This change affects the non-safety related portion of the Feedwater System. It changes the boundary of the Section 1, boiler external pipe jurisdiction. It makes no other changes. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-077

IOCFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: OCTOBER 1994 UNIT NAME: SALEM 2 DATE: 11/10/94 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 2EC-3319, Pkg. 1 Feedwater Flow Nozzle Replacement - The scope of this DCP is for the replacement of the existing feed water flow metering nozzles to improve accuracies of flow measurement and control. The new installation will utilize flanges to provide for convenient access to flow nozzles for periodic inspections. In addition, new Chordal Type Leading Edge Ultrasonic Meters will be installed upstream of the replaced flow meters to provide divers flow measurement for information purposes. There is a reactor trip system signal associated with Steam/feedwater flow Mismatch and Low Steam Generator Water Level. The feedwater flow control circuitry associated with the replacement of the flow metering nozzles is not affected by the nozzle replacement. The reactor trip setpoints were not altered by this change. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-078) 2EC-3269, Pkg. 1 Auxiliary Building Ventilation System Enhancements - Rev.

1 - This DCP provides design enhancements which will increase ABV system performance and reliability and reduce auxiliary building pressure problems. The enhancements simplify the way the system operates, which will facilitate balancing and also reduce maintenance requirements. This revision to the package incorporates pressure instrumentation and partial balancing. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-080) 2EC-3228, Pkg. 2 Waste Gas Analyzer Panel Replacement - This package installs one new gas analyzer panel, 110-2, on elevation 122' of the Unit 2 Auxiliary Building. The panel consists of two (2) hydrogen analyzers, one (1) recorder, sample selection sequencing logic, alarm unit, flow instrumentation,

... ' 10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: OCTOBER 1994 UNIT NAME: SALEM 2 DATE: 11/10/94 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 sample pumps, tubing and valving. One set of 02 and H 2 analyzers in the panel will continuously monitor the in-service waste gas decay tank (WGDT). The second set of analyzers will normally monitor the cover gasses in sequential manner. Under administrative control, the sequential monitoring is also capable of including the in-service WGDT for both Units and the tank cover gasses from Unit 1. The proposed change does not reduce the margin of safety as defined as defined in the basis of the Technical Specifications. The proposed changes will not increase the risk of explosivity and do not have effect on monitoring of gaseous efiluents. Since no system having a safety function i_s affected by the modification, the margin of safety is not reduced. (SORC 94-080) 2EE-0065, Pkg. 1 22SJ145 Replacement - Valve 22SJ145 will be replaced with an equivalent valve. there is no anticipated impact from this change. The valve serves as a test connection for the Safety Injection hot leg to the RCS and is adjacent to valve 22SJ40, which is the containment isolation boundary valve. The margin of safety of the service water system is defined, in part, by the requirements set forth by ASME I design code. The design requirements for the proposed modification have been satisfied. The function of the 22SJ145 globe valve/safety injection system has not changed. The margin of safety as defined by Technical Specifications is therefore, unaffected.* (SORC 94-081) 2EE-0063, Pkg. 1 No. 26 Service Water Pump Discharge Check Valve 26SW2 Replacement - The proposed modification entails the replacement of No. 26 Service Water Pump discharge check valve 26SW2. The existing check valve is a C&S

• Valve Co. Dual Plate, soft seat, aluminum bronze valve, which had a history of erosion problems due to the soft seat becoming separated from the valve body and allowing the valve to leak by. The replacement valve is C&S Valve Co.

... ...11., y 10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: OCTOBER 1994 UNIT NAME: SALEM 2 DATE: 11/10/94 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 (Cont'd)

Dual Plate, hard seat, 6% Molybdenum Stainless Steel valve, which has excellent erosion/corrosion characteristics.

The seat material for the new valve is the same as the valve body and should exhibit the same excellent erosion/

corrosion characteristics. The replacement valve is dimensionally the same, no modifications to the piping system are required. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-080)

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 OCTOBER 1994 SALEM UNIT NO. 2 The Unit began the period ma power escalat10n fotiowing a manual trip on September 29, 1994. On October 4, 1994, power was briefly reduced to 87% due to problems with #24 Vacuum Pump. The Unit was returned to 100% power, and continued to operate at full power until October 13, 1994, when a 5% per hour power reduction was commenced to take the Unit off line for the 2R8 refueling outage. The Unit remained shutdown throughout the rest of the period while outage activities continued.

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REFUELING INFORMATION DOCKET NO: 50-311 MONTH: OCTOBER 1994 UNIT NAME: SALEM2 DATE: 11/10/94 CO:MJ>LETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH: OCTOBER 1994

1. Refueling information ha~ changed from last month: YES____A_NO _ _

2. Scheduled date for next refueling: October 14. 1994

3. Scheduled date for restart following refueling: December 29. 1994

4. a. Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO DATE __A_

b. Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO ____A_

Ifno, when is it scheduled? November

5. Scheduled date(s) for submitting proposed licensing action: ---~N/A._ _ __

6. Important licensing considerations associated with refueling:

7. Number ofFuel Assemblies:

a. Incore 0

b. In Spent Fuel Storage 749

8. Present licensed spent fuel storage capacity: _1170_ _

Future spent fuel storage capacity: 1170

9. Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: March 2003 8-1-7.R4