ML18101A385

Monthly Operating Rept for Nov 1994 for Salem Generating Station Unit 1.W/941213 Ltr

ML18101A385
Person / Time
Site:	Salem
Issue date:	11/30/1994
From:	Hagan J, Morroni M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9412190093
Download: ML18101A385 (13)

Text

e PS~G Publi,c; Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit December 13, 1994 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 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 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, ger-Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 8-1-7.R4 The P9-wffis_in_vour_h~mds

9412190093 941130

PDR ADOCK 05000272 95-2168 REV. 6/ 4

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.ERAGE DAILY UNIT POWER LE~

Docket No.: 50-272

' .. Unit Name: Salem #1 Date: 12/10/94 Completed by: Mike Morroni Telephone: 339-5142 Month November 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1088 17 1108 2 1123 18 867 3 1100 19 1005 4 1078 20 1113 5 1033 21 1113 6 1102 22 1099 7 1100 23 1105 8 1111 . 24 1106 9 1128 25 1107 10 1094 26 1108 11 1113 27 1102 12 1102 28 810 13 1132 29 233 14 1099 30 348 15 1087 31 -----

16 1029 P. 8.1-7 Rl

OPERATING DATA REPORT Docket No: 50-272 Date: 12/10/94 Completed by: Mike Morroni Telephone: 339-5142 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period November 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 N A.

9. Power Level to Which Restricted, if any (Net MWe) N/A

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

12. Hours in Reporting Period 720 8016 152713

12. No. of Hrs. Rx. was Critical 720 5843.6 100975.6

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 720 5124.3 97012.2

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2296142.4 16921828.8 307694142.8

17. Gross Elec. Energy Generated (MWH) 769720 5277830 101813800

18. Net Elec. Energy Gen. (MWH) 737771 4980197 96917750

19. Unit Service Factor 100 63.9 63.5

20. Unit Availability Factor 100 63.9 63.5

21. Unit Capacity Factor (using MDC Net) 92.6 56.2 57.4

22. Unit Capacity Factor (using DER Net) 91.9 55.7 56.9

23. Unit Forced Outage Rate 0 28.6 21.4

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

Refueling outage scheduled to start 4-8-95 and last 60 days.

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

N A.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH NOVEMBER 1994 DOCKET NO. :-'5,.,0::_-.::.272=----

UNIT NAME: Salem #1 DATE: 12-10-94 COMPLETED BY: Mike Morroni TELEPHONE: 339.-5142 METHOD OF SHUTTING LICENSE '

DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACllf)N NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 1958 11-16-94 F 4.7 A 5 HF FILTER cw. INTAKE TRASH RAKE JAMMED 1972 11-19-94 F 4.9 A* 5 --------- EA RELAYX FAULTY CONTROL RELAYS 1984 11-28-94 F 46.8 B 5 --------- EA RELAYX ACTUATION OF DIFF. PROTECTION RELAY FOR

1. 2 S.P.T.

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 (LER) 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)

• Most probable cause was faulty control relays actuated causing 4 T60 disconnect to open on# 4 Station Pwr. Trans ** relays have been replaced.

10CFRS-0.59

'. . EVALUATIONS DOCKET NO: 50-272

• MONTH: NOVEMBER 1994 UNIT NAME: SALEM 1 DATE: 12/10/94 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.

1. Design Change Packages (DCP) lEA-1063, Pkg. 1 Added l" Drain Valves and Component I.D. Numbers to Required Documentation - This DCP adds l" drain valves and component I.D. Numbers to P&ID 205249 (Sht 3),

piping arrangement drawing 212823 and MMIS database.

These valves were installed on fire pump (350 gallon) day tanks 1DFE21and1DFE23, located in the fire pump house at Salem Generating Station, but were never addressed appropriately on P&ID's or MMIS. This DCP is for documentation update and does not modify any system or process. The Fire Pump Room Fuel Oil System is not addressed in the Technical Specifications. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-083) lEA-1073, Pkg. 1 Document Update on Salem Biocide Monitoring Building -

All pertinent documentation will be revised to show that the Biocide Monitoring Building is no longer operable and has been converted over to a Service Water Fab Shop. All drawings will be revised to reflect an as-built condition.

Salem FSAR Fig. 1.2-1 (General Site Plan) will be revised to show a Service Water Fab Shop in place of the Biocide Monitoring Building. This DCP is for documentation update and does not modify any system or process. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-083) lEC-3324, Pkg. 1 RG 1.97 Isolator Replacement and Separate Class IE from Non-Class IE Loads - This DCP will install new signal isolation devices in class IE instrument loops within instrument racks which contain various monitoring and

10CFRS0.59 EVALUATIONS DOCKET NO: 50-272

. MONTH: NOVEMBER 1994 UNIT NAME: SALEM 1 DATE: 12/10/94 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5I62 protection channels. Installation of these components will provide electrical isolation for Reg. Guide I.97 instrument loops, ensuring that faults within non-class IE portions of these loops will not propagate to the Class IE portion, damaging the functions provided by the affected instrument.

This DCP will make no changes to the functional, operational or design requirements of any of the affected instrument loops, including instrument ranges, setpoints and protection channel response times. The margin of safety as defined in the bases of the Technical Specifications will not be reduced. (SORC 94-083)

IEC-3324, Pkg. 3 Separate class IE from Non-Class IE Loads - This modification separates Class IE loads from Non-Class IE loads in various process and computer interface racks by internal wiring modifications and the use of spare breakers in the I I 5 VAC Vital Instrument Busses. This modification does not involve any margin of safety as described in the basis section of the Technical Specifications. The margin of safety as defined in the bases of the Technical Specifications will not be reduced. (SORC 94-083)

IEC-3206, Pkg. 2 Digital Feedwater/Reg. Guide I.97 Isolators - This DCP will install new signal isolation devices in Class IE instrument loops within instrument racks which contain various monitoring and protection channels. Installation of these components will provide electrical isolation for Reg.

Guide I. 97 instrument loops, ensuring that faults within non-class IE portions of these loops will not propagate to the Class IE portion. There is no reduction in the margin of safety as defined in the basis of any Technical Specification.

(SORC 94-083)

IEC-3340, Pkg. I Waste Gas Setpoint Modification - The purpose of this DCP is to implement the necessary setpoint and piping changes to enable the Waste Gas Comnpressors to operate

10CFRS0.59 EVALUATIONS DOCKET NO: 50-272

. MONTH: NOVEMBER 1994 UNIT NAME: SALEM 1 DATE: 12/10/94 COMPLETED BY: R.HELLER TELEPHONE: 609-3 39-5162 (Cont'd) in the continuous/automatic mode, as cited in the SAR. All plant modifications for this DCP are confined to the recalibration of selected Waste Gas intrumentation and rerouting of existing compressor recirculation piping. The affected components remain in the same location and do not change in regard to their function in the loops. There is no reduction in the margin of safety as defined in the basis of any Technical Specification. (SORC 94-083) lEC-3345, Pkg. 2 Steam Generator Narrow Range Low and Low Low Level Setpoint Change - Steam Generator Narrow Range Low and Low Low Level Setpoint Change -The purpose of this DCP is to change the SG NR Level Low Setpoints from 25% to 10% and the corresponding allowable values from 24% to 9%. In addition, this DCP also changes the SN NR Level Low-Low setpoints from 16% to 9% and the corresponding allowable values from 14.8% to 8%. The proposed setpoint and allowable values continue to ensure that the assumptions in the safety analyses remain valid, with appropriate consideration of protection system channel uncertainties. Therefore, there is no reduction in the margin of safety as defined in the bases for the Technical Specifications. (SORC 94-085) lEC-3337, Pkg. 1 Switchgear & Penetration Area Ventilation System Upgrade

- This project provides design enhancements which will improve switchgear and penetration area ventilation (SP AV) system performance, reliability, and reduce area pressure problems. The Technical Specifications do not address the SPAV system. There is no reduction in the margin of safety as defined in the bases for the Technical Specifications. (SORC 94-085) lEC-3289, Pkg. 1 Cable Protection - Safety Related - This DCP provides improved cable protection of the subject circuits without limiting the load capability and also improves the protection

10CFR50.59 EVALUATIONS DOCKET NO: 50-272

..MONTH: NOVEMBER 1994 UNIT NAME: SALEM 1 DATE: 12/10/94 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 and operability of the equipment. This DCP will also remove the jumpers from the overload heater circuits that are presently in place for safety-related MOVs. This modification is in compliance with Reg. Guide 1.106, Thermal Overload Protection for Electric Motors on Motor Operated Valves. Calculation ES-18.006, Selection of Thermal Overload Heater Elements, Unit 1 & 2, Safety Related MOVs, documents the sizing of the overloads to comply with the requirements of Reg. Guide 1.106. There is no reduction in the margin of safety as defined in the bases for the Technical Specifications. (SORC 94-088) lEC-3321, Pkg. 1 Diesel Generator Combustion Air Modification - This design change modifies the combustion air intake and exhaust subsystem of the emergency diesel generator system "DG and consists of the following scope items: 1.)

Installation of a protective tornado barrier for each of the three combustion air intakes; 2.) Replacement of the combustion air exhaust piping from the exhaust silencer to the auxiliary bldg. roof, and 3.) Installation/ modification of the subsystem's piping supports such that the subsystem meets seismic class I. The work performed during Modes 5

&6 will only proceed on one DG at a time, such that no less than two separate and independent DGs will be operable at any given time. Surveillance requirement 4. 8 .1. 2 will be performed to ensure operability of the DGs. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-090) lEC-3338, Pkg. 1 Rod Control Timing Change - This modification is to make a rod control timing change. The change is incorporated by changing the orientation or existing diodes on existing slave cycle decoder circuits cards located in the logic cabinet.

The decoder cards have been manufactured to accommodate the timing changes of this DCP. Testing of the slave cycler outputs will be performed at the Training

10CFRS0.59 EVALUATIONS DOCKET NO: 50-272

. MONTH: NOVEMBER 1994 UNIT NAME: SALEM 1 DATE: 12/10/94 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 Center first, then repeated in the plant. The DCP will schedule these two surveillance's of a refueling cycle frequency. The proposed timing changes do not affect the margin of safety as defined in the basis for any Technical Specification. A generic safety evaluation has been performed by WOG which concluded that all safety limits continue to be met. In fact, the timing change in combination with the Rod Control surveillance tests increase the reliability of the Rod Control System.

(SORC 94-090) lEE-0066, Pkg. 1 Circulating Water Traveling Screen 1 lA, 1 lB, 12A, 12B, lEE-0067, Pkg. 1 13A, 13B Modifications - These modifications will replace lEE-0068, Pkg. 1 the existing fish baskets in the circulating water traveling lEE-0069, Pkg. 1 screens with redesigned baskets to provide greater fish lEE-0070, Pkg. 1 survivability. Two additional spray nozzles will be added to lEE-0071, Pkg. 1 the main debris spray header to provide better spray coverage to the traveling water screen and improve debris removal. Two spray nozzles will be added to the source pipe of the two inside fish spray headers to provide better spray coverage and improve fish handling. A shield will be provided over the top of the existing fish spray nozzles to prevent grass and other debris from lodging on the spray nozzles and blocking the flow. The Circulating Water System is non-safety related and is not required to support the safe shutdown of the reactor plant or maintain it in a safe condition after shutdown. The function and operation of the equipment and system remains the same. Therefore, there is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 94-092)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272

, "MONTH: NOVEMBER 1994 UNIT NAME: SALEM 1 DATE: 12/10/94 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 (Cont'd)

2. Temporary Modifications (T-Mods)

T-Mod 93-109 Fuel Handling Crane Ambient Temperature Requirement -

This T-Mod is to upgrade the hoisting capacity of the Fuel Handling Crane from 5 Tons to 20 Tons. The safety evaluation which accompanied the LCR for the Spent fuel Pool rerack stated that to assure absence of brittle fracture tendency of the crane material, ambient temperature in the fuel pool area will be kept above 70°F during the rack lift operation. Because this requirement cannot be met, it was necessary to justify operation of the Fuel Handling Crane at a lower temperature. The new Rack Handling Trolley has plate sizes greater than 1/2", therefore it is subject to the requirements of NUREG-0554, Paragraph 2.4. UT examination of these plates shows there are no flaws.

According to Figure 1 of ASTM E208, ifthere are no flaws in the material, fracture initiation will not start if the service temperature is kept at or above the Nil Ductility Temperature (NDT) of the material. ASME Table NC-231 l(a)-1 shows that the NDT of ASTM A36 material is

+40°F. To assure absence of brittle fracture tendency of the material of the temporary trolley, minimum ambient temperature will be kept at or above +45°F. Also, the maximum stresses that the crane will experience are less than 20% of the brittle fracture stress of 36,000 psi. There is no reduction in the margin of safety as defined in the bases for the Technical Specifications. (SORC 94-086)

_J

IOCFRS0.59 EVALUATIONS DOCKET NO: 50-272

. MONTH: NOVEMBER 1994 UNIT NAME: SALEM 1 DATE: 12/10/94 C01\1PLETED BY: R.HELLER TELEPHONE: 609-339-5162

3. Safety Evaluations S-C-ZZ-ESE-0841 Safety Evaluation for Separation Distance of Cables in Free Air Installed in Salem Unit 1 and Unit 2 Relay Rooms (El.

100) - This evaluation will be used to create SAR Change Notice 94-40 which will revise UFSAR section 8.1.4.2.4, "Separation in Plant" and will provide additional flexibility to the allowable separation distance between cables in redundant channels, including associated circuit cables, which are installed in free air of the Salem Units 1 and 2 relay rooms (El. 100). There is no existing Technical Specification that is associated with Salem's Appendix R Alternate Shutdown Methodology. Therefore, the proposed text change in the UFSAR does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-083)

4. Procedures NC.NA-AP.ZZ-0065(Q) Nuclear Department Resource Allocation Program - Rev. 2

- This revision deletes this procedure and creates a new Nuclear Business Procedure ND.OA-BP.ZZ-0005(Z) to cover this information. The operational Quality Assurance Program does not apply to this procedure. although this procedure is briefly described in the UFSAR (Section 13 .5.1 (Hope Creek), Plant Procedures, and Section 13.5.1.1 (Salem), Nuclear Administrative Procedures), it performs no function relative to the safe operation of either Hope Creek or Salem Stations. Therefore, deleting this procedure will have no affect on the safe operation of either Hope creek or Salem Stations. UFSAR Change Requests for Hope creek and Salem UFSARs are being prepared to remove the description ofthis procedure from the UFSAR.

There is no reduction in the margin of safety as defined in the bases for the Technical Specifications. (SORC 94-087)

REFUELING INFORMATION DOCKET NO: 50-272

- MONTH: NOVEMBER 1994 UNIT NAME: SALEM 1 DATE: 12/10/94 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH: NOVEMBER 1994

1. Refueling information has changed from last month: YES _ _NO _X_

2. Scheduled date for next refueling: April 8. 1995

3. Scheduled date for restart following refueling: June 6. 1995

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 ____A_

If no, when is it scheduled? March 1995

5. Scheduled date(s) for submitting proposed licensing action: ---~NIA~---

6. Important licensing considerations associated with refueling:

7. Number ofFuel Assemblies:

a. Incore _193 _ _

b. In Spent Fuel Storage 732

8. Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: _1632_ _

9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2008 8-1-7.R4

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 NOVEMBER 1994 SALEM UNIT NO. 1 The Unit began the period operating at 100% power and continued to operate at essentially full power until 11/16/94, when power was briefly reduced to 80% to free up the trash rake which had become jammed. The Unit was restored to full power later, the same day, and continued to operate at full power until 11/19/94, when load was reduced due to the loss of#4 and #14 station power transformers. The Unit was restored to full power on 11/19/94 and continued to operate at essentially full power until 11/28/94, when load was reduced to 30% due to loss of#2 station power transformer. The transformer was returned to service and a power escalation commenced on 11/30/94. The Unit ended the period with a power escalation in progress.