ML18100A759

Monthly Operating Rept for Nov 1993 for Salem Unit 1.W/ 931210 Ltr

ML18100A759
Person / Time
Site:	Salem
Issue date:	11/30/1993
From:	Heller R, Shedlock M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9312200005
Download: ML18100A759 (13)

Text

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station December 10, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 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 November 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

~erely yours,  ?

~~~

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 T_h~ l::n?rg~J>eQple __________ _

9312200005 931130 \ ' 95-2189 (10M) 12-89 PDR ADOCK 05000272 i '

R PDR L*

~ERAGE DAILY UNIT POWER LE~

Docket No.: 50-272 Unit Name: Salem #1 Date: 12/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Month November 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 16 0 P. 8.1-7 R1

e OPERATING DATA REPORT e Docket No: 50-272 Date: 12/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period November 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) N/A

10. Reasons for Restrictions, if any --~~~~~~N==O=N=E=--~~~~~~~~~~-

This Month Year to Date Cumulative

12. Hours in Reporting Period 720 8016 143953

12. No. of Hrs. Rx. was Critical 0 5949.99 95131.97

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 0 5747.43 91887.84

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 18573705.6 290772314

17. Gross Elec. Energy Generated (MWH) 0 6162980 96535970

18. Net Elec. Energy Gen. (MWH) -1053 5869548 91941207

19. Unit Service Factor 0 71.7 63.8

20. Unit Availability Factor 0 71.7 63.8

21. Unit Capacity Factor (using MDC Net) 0 66.2 57.7

22. Unit Capacity Factor (using DER Net) 0 65.7 57.3

23. Unit Forced Outage Rate 0 12.6 21

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

The Unit is presently in a refueling outage scheduled to last 72 da s.

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

December 16 1993.

8-1-7.R2

UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH NOVEMBER 1993 DOCKET NO. :-'5:..:0._..,--=2"'-72::..,,,~-

UNIT NAME: Salem #1 DATE: 12/10/93 COMPLETED BY: Mark Shedlock TELEPHONE: 339-2122 METHOD OF SHUTTING LICENSE DURATION DOYN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 134 10-02-93 s 1440.88 c 1 --------- RC FUELXX NUCLEAR NORMAL REFUELING 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-Refuel ing 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)

"SAFETY RELATED MAINTEN,CE 1

DOCKE. .O: 50-272 MONTH: - NOVEMBER 1993 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 WO NO UNIT EQUIPMENT IDENTIFICATION 920524002 1 12 SERVICE WATER PUMP FAILURE DESCRIPTION: PULL AND REPLACE WITH SPARE REBUILT PUMP 920909153 1 VALVE 11RH8 FAILURE DESCRIPTION: BONNET LEAK - REPLACE BONNET GASKET 920921177 1 VALVE 12CS36 FAILURE DESCRIPTION: BONNET LEAKS - OPEN, INSPECT &

REPAIR 921030169 1 RADIATION MONITOR 1R18 FAILURE DESCRIPTION: 1R18 READS HIGH - REPLACE 921117162 1 VALVE 11MS44 FAILURE DESCRIPTION: LEAK AT DRAIN FLANGE - REPLACE GASKET 921125078 1 VALVE 11SW36 FAILURE DESCRIPTION: 11SW36 CHECK VALVE INSTALLED IN VERTICAL POSITION - CORRECT 921208154 1 1A DIESEL GENERATOR FAILURE DESCRIPTION: lA DIESEL GENERATOR - SLOW ENGINE RESPONSE - TROUBLESHOOT 930708104 1 VALVE 11SJ134 FAILURE DESCRIPTION: OPEN, INSPECT & REPAIR AS REQUIRED 931013155 1 11 AUXILIARY BUILDING SUPPLY FAN FAILURE DESCRIPTION: REPLACE SUPPLY FAN BREAKER WITH A SPARE

- SAFETY RELATED MAINTEr9CE DOCKE.O: 50-272

'MONTH: - NOVEMBER 1993 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)

WO NO UNIT EQUIPMENT IDENTIFICATION 931111135 1 VALVE 1SJ53 FAILURE DESCRIPTION: CONTROL ROOM HAS NO INDICATION FOR 1SJ53 - INVESTIGATE 931113057 1 12 FUEL HANDLING BUILDING EXHAUST FAN FAILURE DESCRIPTION: FAN BREAKER TRIPPED AND FLAMES SHOT FROM MOTOR - REPLACE MOTOR 931114062 1 NUCLEAR INSTRUMENT N31 FAILURE DESCRIPTION: N31 IS CONTINUOUSLY SPIKING - ALL WELDING IN THE AUX. BUILDING AND THE CONTAINMENT WERE STOPPED BUT THIS DID NOT STOP THE SPIKING -

INVESTIGATE 931127101 1 lC 460VAC CONTROL POWER BREAKER FAILURE DESCRIPTION: CONTROL POWER BREAKER/BOLTS LOOSE

- TIGHTEN 931130142 1 VALVE lPRl FAILURE DESCRIPTION: lPRl STROKED CLOSE AND FAILED TO REOPEN - INVESTIGATE AND REPAIR AS REQUIRED

- 10C~R50.59 EVALUATIONStt DOCKE.O: 50-272

'MONTH: - NOVEMBER 1993 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (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

A. Design Change Packages (DCPs) lEC-3297 Pkg 1 "Stabilize and then Plug S/G 13 Tube R14C39" - The purpose of this design change is to install a stabilizer in the hot leg side of Steam Generator (S/G) 13 Tube R14C39 (and plug both ends of the tube). The stabilizer installation will be done in accordance with the new appendix VI to Westinghouse Procedure MRS.2.3.2PSEG-13 which will be incorporated into the Salem ISI Procedure VSC.SS-IS.RCE-0036(Q). Stabilization will preclude the possibility of the tube becoming severed and interacting with an adjacent active tube, which could result in a primary to secondary leakage event. The stabilizer is sized such that the difference between the diameter of the stabilizer and the inside diameter of the tube is less than the distance between adjacent tubes.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. The pressure boundary integrity and function of the steam generator are not adversely altered. Steam generator tube plugging up to a level consistent with the current analyzed level (10%) will not affect current LOCA analyses. (SORC 93-098) lEC-3296 Pg 1 "Turbine Bypass Sparger Repair and Improvement" -

The purpose of this design change is to repair damaged turbine bypass spargers by replacing damaged baffle plates and adding a sparger pipe cap. Piping external to the condenser will be modified by the addition of a sediment leg to the existing drain connection upstream of the turbine dump valves prior to entering the steam trap assembly piping. The Technical Specifications do not reference the turbine bypass system. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 93-099)

10CFR50.59 EVALUATIONS~ DOCKE.O: 50-272

'MONTH: - NOVEMBER 1993 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)

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ITEM

SUMMARY

lEA-1050 Pkg 1 "Addition of Sample Lines to DM Plant P&ID" - This DCP covers a Workbook No. 5 to document an as-built condition on P&ID No. 205213 (UFSAR Figure No. 9.2-11) involving a total of seventeen (17) existing sample lines from various points in the Makeup Demineralization System to the existing Sample Sink on Elevation 100 1 in the Unit No. 1 Turbine Building. Several previously unnumbered sample line isolation valves were found during the walkdowns and are also being added to the P&ID.

MMIS and TRIS data sheets have been prepared for these valves. P&ID No. 205223 (Building and Equipment Drains - conventional) will also be revised to provide a better representation of the drain from the Sample Sink to the No. 15 Sump. No physical work or process changes are involved.

This is an as-built change only and will close out DEF DES-91-00470. This DCP does not impact* either the Fire Protection Program or the Radioactive Waste Treatment Systems. The Demineralized Water Makeup system is non-safety related. No physical changes are being made to the system. The changes to the P&ID do not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-100) lEC-3245 Pkg 1 "Replace Garret/SCI Emergency Lighting Inverters" Rev. 1 - This project replaces the three Garret/SCI Emergency Lighting Inverters with higher rated and more efficient Cyberex Inverters. Existing Garret/SCI Emergency Lighting Inverters are experiencing end of life and age related fatigue failure. These inverters are also experiencing overloading conditions. The inverters efficiencies are very low. Replacement parts are expensive and difficult to obtain. The Technical Specifications do not specifically discuss the emergency lighting system. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 93-100) lEC-3243 Pkg 1 "SGFP/Condensate Pump/Feedwater Heaters: System Design Press Modifications" Rev. 2 - This DCP will provide a high pressure trip setpoint for the

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lOCF'.R.50. 5*9 EVALUATIONS- DOCKE~O: 50-272

• MONTH: - NOVEMBER 1993 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)

ITEM

SUMMARY

11 and 12 SGFP turbines at 1620 psig. Two new transmitters will be installed on the discharge piping of each f eedwater pump and by modifying the existing trip circuitry, the feed pump will trip (2/2 logic) on a high feed pump discharge pressure. The system pressure will be monitored by the P-250 computer. High & Low alarm limits will be installed to notify the operator when conditions have approached a pump trip pressure or a transmitter failure, respectively. Setpoint corrections of 5000 gpm and 5500 gpm will be made to the 11, 12 and 13 condensate pump recircu-lation flow control loops to ensure a maximum sus-tained pressure of approximately 625 psig during a cold startup. during installation of cable thru penetration seals in the east wall of the Auxiliary Building, flood protection will be compromised. During this installation, Operations can contact the National Weather Service of Wilmington Airport in Delaware via telephone, as necessary, to obtain information on meteorological conditions which may cause flooding. At that time, work will be stopped and a temporary barrier installed. Therefore, this proposal does not reduce the margin of safety as defined in the basis for any Technical Specification.

( SORC 93-103)

B. Procedures and Revisions NC.NA-AP.ZZ-0052(Q) "Water Chemistry Control Program" Rev. 1 - This is a full revision to the procedure. Changes are identified with revision bars. The following changes have been made: 1.) Statements have been added to Attach. 3 which permit judgement on reducing station power and temperature based on the specific corrosion concern and the most rapid means to effect cleanup; 2.) Statement recommends confirmatory sampling/analysis prior to reporting exceeding of an Action Level (step 5.4.2) and increased chemistry sampling and analysis

10CFR5 0. 5'9 EVALUATION- DOCKE.O: 50-272

" MONTH: - NOVEMBER 1993 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)

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ITEM

SUMMARY

frequency for short term trending during transients (step 5.6.1); 3.) Attach 3, PWR Secondary Chemistry Corrective Actions: The Action Level 2 power reduction time requirement has been increased from 4 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after initiation of Action Level 2. This is !AW Revision 3 of the PWR Secondary Water Chemistry Guidelines, and 4.) Other minor editorial changes. Vendor and industry primary and secondary *chemistry guidelines protect the RCS components and steam generators by assuring good water chemistry. This change does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-098)

c. Safety Evaluations (S/E)

NFS93-630 "Salem Unit 1 Cycle 12 Core Loading Pattern and Safety Evaluation for Refueling and Operation in Modes 5 - 1 11 - During the Salem Unit 1 Cycle 11/12 refueling, 63 fuel assemblies will be replaced with 2 once burned Region 10, 2 twice burned Region 10 fuel assemblies, 7 twice burned Region 9 fuel assemblies, 32 fresh Region 14A fuel assemblies, and 20 fresh Region 14B fuel assemblies. Fuel assembly K24 has been reconstituted with a stainless steel filler rod in pin location K-10. Fuel assembly K41R has also been reconstituted with one stainless steel filler rod in location N-16. Furthermore, fuel assembly K41R has been recaged with a VANTAGE 5H (V5H) skeleton. In addition to the reconstituted assemblies, the Cycle 12 loading pattern also contains 768 Zircaloy-4 rodlets arranged in clusters. These Zircaloy damper rodlets are inserted in burnt V5H assemblies located adjacent to the baffle in order to reduce the possibility of flow induced vibration causing fuel rod fretting. Cycle 12 also includes the use of assembly K28 which requires special handling due to a folded vane segment in one of its grids.

Also new for Salem Unit 1 cycle 12 is a revised

"'

10CFR50.59 EVALUATIONS- DOCKE. .O: 50-272

~MONTH: - NOVEMBER 1993 UNIT NAME: SALEM 1 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)

ITEM

SUMMARY

V5H assembly grid axial orientation on feed fuel (Region 14). For Region 14 V5H assemblies, alternate grids are rotated 90 degrees clockwise in order to minimize the susceptibility of flow induced fuel assembly vibration. There is no physical change to the grids or their axial positions. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. The cycle 12 reload core design meets all applicable design criteria and ensures that all pertinent licensing basis criteria are met. It has been determined that-the Salem Unit 1 V5H reload design and safety analysis limits remain applicable, and that these limits are supported by the applicable Salem Unit 1 Technical Specifications for Cycle 12. (SORC 93-100)

D. SAR Change SCN 93-53 "SAR Change Notice" - The proposed change associated with this Safety Evaluation involves an update to the Salem UFSAR section 7.5.3.2, Regulatory Guide 1.97 Compliance Levels, to revise the following statement: "Regulatory Guide 1.97 variables will be displayed on the Safety Parameter Display System (SPDS)" to read as follows: "Most of the Regulatory Guide 1.97 variables are displayed on the Safety Parameter Display system (SPDS)". There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-103)

SCN 93-55 "SAR Change Notice" - The proposed change associated with this Safety Evaluation involves an update to the Salem UFSAR, Table 7.2-2 to correct the function description of the permissive P-7 from "Blocks Reactor Trip on Pressurizer High Pressure" to "Blocks Reactor trip on Pressurizer High Level". There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-103)

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 NOVEMBER 1993 SALEM UNIT NO. 1 The Unit remained shutdown throughout the entire period for the eleventh refueling outage.

• REiuELING* INFORMATION

~MONTH: - NOVEMBER 1993 e DOCKE.O:

UNIT NAME:

50-272 SALEM 1 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 MONTH NOVEMBER 1993

1. Refueling information has changed from last month:

YES X NO -~~-

2. Scheduled date for next refueling: OCTOBER 2, 1993

3. Scheduled date for restart following refueling: DECEMBER 16, 1993

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

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

YES X 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 732

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: September 2001 8-1-7.R4