ML18100A876

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Monthly Operating Rept for Jan 1994 for Salem Unit 2.W/ 940214 Ltr
ML18100A876
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/31/1994
From: HAGAN J J, HELLER R, MORRONI M
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9402180106
Download: ML18100A876 (12)
v • d • e


Text

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

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 February 14, 1994 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 January 1994 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 Safety Valve Actuations Operating summary Refueling Information Sincerely yours, ger -ions cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The

_______ . _____________

_ . 9402180106 940131 --'-** \ PDR ADOCK 05000311 R PDR 95-2189 (10M) 12-89 AVERAGE DAILY UNIT

,. Docket No.: 50-311 Unit Name: Salem #2 Date: 02-10-94 Completed by: Mike Morroni Telephone:

339-2122 Month January 1994 Day Average Daily Power Level Day Average Daily Power Level* (MWe-NET) (MWe-NET) 1 0 17 1122 2 0 18 1143 3 0 19 1116 4 0 20 1119 5 274 21 1079 6 439 22 1089 7 470 23 1118 8 762 24 1091 9 1047 25 1109 10 958 26 1075 11 1157 27 1092 12 1157 28 1146 13 1157 29 720 14 1111 30 493 15 1107 31 462 16 1134 P. 8.1-7 Rl OPERATING DATA REPae Docket No: Date: Completed by: Mike Morroni Telephone:

Operating Status 1. Unit Name Salem No. 2 Notes 2. Reporting Period January 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) Report, Give Reason NA 9. Power Level to Which Restricted, if any (Net MWe) 10. Reasons for Restrictiqns, 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 744 667.03 0 647.27 0 1917542.4 646120 614862 86.9 86.9 74.7 77.9 13 Year to Date 744 667.03 0 647.27 0 1917542.4 646120 614862 86.9 86.9 74.7 77.9 13 50-311 02/10/94 339-2122 since Last N/A Cumulative 107857 69946.59 0 67536.79 0 164380481.8 71192638 67742139 62.6 62.6 56.8 59.2 22.6 24. Shutdowns scheduled over next 6 months (type, date and duration of each) NONE 25. If shutdown at end of Report Period, Estimated Date of Startup: NA 8-1-7.R2 NO. DATE 0053 01/01/94 0001 01/06/94 0003 01/10/94 0005 01/29/94 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 F 48.73 A F 23.80 A F 5.00 B F 58.00 A Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS REPORT 'MONTH JANUARY 1994 METHOD OF SHUTTING DOWN REACTOR 1 5 5 5 LICENSE EVENT REPORT # ------------

3 Method: 1-Manual 2-Manual Scram SYSTEM CODE 4 EE CH HF CH 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)

DOCKET NO.:

______ _ UNIT NAME: Salem #2" -DATE: 02-08-94 COMPLETED BY: Mike Morroni TELEPHONE:

339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION CODE 5 TO PREVENT RECURRENCE GENERA OTHER AC INSTRUMENT POWER PROBLEMS PIPEXX S/G FEEDWATER NOZZLES HTECXH CONDENSER TUBE WATER BOX CLEANING PUMPXX FEEDWATER PUMP 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -Same Source * ----------------

SAFETY,RELATED MAIN.ANCE

  • -JANUARY 1994 DOC.T NO: UNIT NAME: 50-311 SALEM 2 WO NO UNIT DATE: COMPLETED BY: TELEPHONE:

FEBRUARY 10, 1994 R. HELLER (609)339-5162 EQUIPMENT IDENTIFICATION 931227094 931227112 931229093 931231113 940108086 940115066 2 2 2 2 2 PRESSURIZER LEVEL INDICATION FAILURE DESCRIPTION:

CHANNEL 2 IS READING 4% HIGHER THAN CHANNELS 1 AND 3 -INVESTIGATE AND REPAIR 22 AUXILIARY BUILDING EXHAUST FAN MOTOR FAILURE DESCRIPTION:

EXHAUST FAN MOTOR NOISY -REPLACE BEARINGS PRESSURIZER LEVEL INDICATION FAILURE DESCRIPTION:

CHANNEL 1 IS READING 4% LOWER THAN CHANNEL 2. CHANNEL 2 HAS CHECKED SAT -INVESTIGATE CHANNEL 1 FOR DEVIATION.

22 STEAM GENERATOR LEVEL INDICATION FAILURE DESCRIPTION:

LEVEL INDICATION AT THE HOT SHUTDOWN PANEL >2% DEVIATION FROM CONTROL ROOM INDICATION

-REPAIR POWER RANGE CHANNEL III FLUX RECORDER FAILURE DESCRIPTION:

FLUX RECORDER READS LOW -INVESTIGATE 2 REFUELING WATER STORAGE TANK FAILURE DESCRIPTION:

RWST LEVEL READING IS LOW, -INVESTIGATE

-10CFR50.59 EVALUATIONS

  • -JANUARY 1994 DoclT NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-311 SALEM 2 FEBRUARY 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

A. Design Change Packages 2EC-3215 Pkg 1 2EC-3179 Pkg 2 "Replace Garret/SCI Emergency Lighting Inverters" -This project replaces the three Garret/SCI Emergency Lighting Inverters with higher rated and more efficient Cyberex Inverters.

This DCP downgrades the Emergency Lighting Inverters from safety related to non-safety related. The new inverters are qualified as Seismic II/I. System safety is not degraded since the emergency lighting system is a non-safety related system and the new inverters are provided with Class lE breakers or breaker-fuse combination for their AC and DC inputs, which together with the Class lE breakers in the AC and DC supply switchgear provide double isolation between the lE system and the non-lE system. The Technical Specifications do not specifically address the Emergency Lighting System. This modification does not affect the Unit 2 Technical Specifications.

Therefore, this modification does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-004) "Salem Fire Damper Upgrade" -The design scope for this package includes the replacement, relocation and/or modification of existing fire dampers of Unit 2's Auxiliary Building Ventilation (ABV) Containment Purge System. The function, basic configuration and operation of the system will not be altered and the codes, standards, qualification and design criteria of the original system will apply. Fire dampers 2ABF-016 and 2ABF-024 will be modified in place in accordance with the results of the manufacturer's (PREFCO) fire test report recommendations to obtain a 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> fire rating. The existing fire protective coating will not be necessary, and later replaced to facilitate damper modification.

Fire dampers 2ABF-222 and 2ABF-228 will be replaced with new Ruskin 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> rated fire damper and moved into

-10CFR50.59 EVALUATIONS

  • -JANUARY 1994 (cont'd) ITEM DoclT No: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-311 SALEM 2 FEBRUARY 10, 1994 R. HELLER (609)339-5162 the fire barrier, eliminating the need for existing fire protective coatings.

The margin of safety is not reduced because we are merely enhancing the Fire Protection System to meet the criteria of 10CFR50, Appendix "R". These modifications will not reduce the margin of safety for the Auxiliary Building Ventilation System or the Fire Protection System. (SORC 94-008) B. Temporary Modifications T-Mod 93-063 T-Mod 93-128 "Emergency Lighting Inverters Bypass" -This T-Mod installs three (3) temporary cables to provide power supplies to Emergency Lighting Distribution panels 2ELD-A, 2ELD-B and 2ELC during their respective inverter replacement in plant mode 5 and 6 or defueled.

These temporary cables will be removed after the new inverters installation.

The temporary cables are fed from the original alternate AC power source for each inverter.

This power source is the Vital 230 VAC bus which is backed up by the emergency Diesel Generator.

Preparing the cables in place (without termination) may be done before the refueling outage. The temporary feeder meets the proper design criteria.

In addition, the temporary modification will only be in place during Modes 5 and 6 or defueled.

Therefore, the proposal does not create the possibility of an accident of a different type than any previously evaluated in the SAR. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-004) "Emergency Lighting Panels Temporary Supply" -T-Mod 93-128 provides temporary power supplies to Emergency Lighting panels 2ELD-A, 2ELD-B and 2ELC from their respective Solatron transformers, when the existing emergency lighting inverters are being replaced during lRll outage. The Solatron transformers are supplied from 230 VAC Vital buses 2A and 2B. When 230 VAC Vital bus 2A is deenergized for maintenance during the outage, Emergency Lighting Panel 2ELD-A will lose its power supply. This T-Mod will provide an alternate temporary power 10CFR50.59 EVALUATI.

MarTH: ._ JANUARY 1994 (cont'd) ITEM ooclT No: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

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

T-Mod 93-129 T-Mod 94-007 supply to Emergency Lighting Panel 2ELD-A from Lighting Panel A22A. The 60 A breaker installed in position 16 of panel A22A by T-Mod 93-129 will be reused. The existing temporary feeder for Emergency Lighting Panel 2ELD-A installed under T-Mod 93-063 will be reused. The T-Mod will be installed just before 230 VAC Vital bus 2A is deenergized and will be removed when the bus is reenergized.

The temporary feeders meet the proper design criteria.

There is no reduction in the margin of safety as uef ined in the basis for any Technical Specification. (SORC 94-004) "Emergency Lighting Panels Temporary Supply" -T-Mod 93-129 provides temporary power supplies to Emergency Lighting panels 2ELD-A, 2ELD-B and 2ELC from their respective Solatron transformers, when the existing emergency lighting inverters are being replaced during 2R08 outage. The Solatron transformers are supplied from 230 VAC Vital buses 2A and 2B. When 230 VAC. Vital bus 2B is deenergized for maintenance during the outage, Emergency Lighting Panel 2ELD-B and 2ELC will lose their power supplies.

This T-Mod will provide two alternate temporary power supplies to Emergency Lighting Panel 2ELD-B and 2ELC from Normal Lighting Panel A22A. The 60 Amp breaker and the 50 Amp breaker will be installed in position 16 and 19 respectively in panel A22A and will be used to supply alternate temporary power to Emergency Lighting Panels 2ELD-B and 2ELC respectively.

The T-Mod will be installed just before 230 VAC Vital bus 2B is deenergized and will be removed when the bus is reenergized.

The temporary feeders meet the proper design criteria.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-004) "Installation of Temporary Space Heaters" -This T-Mod will provide additional necessary heating to the Unit 2 Auxiliary Feedwater Storage Tank and Refueling Water Storage Tank level instrumentation lines to prevent these instrument and sample lines 10CFR50.59 EVALUATI.

  • -JANUARY 1994 (cont'd) ITEM DoclT No: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-311 SALEM 2 FEBRUARY 10, 1994 R. HELLER (609)339-5162 from freezing.

The T-Mod will install a temporary enclosure heated by space heaters. The temporary enclosure will be constructed of scaffold material enclosed by Herculite.

The existing heat trace system is not adequate for the present cold spell at Salem Station. This T-Mod will be monitored hourly by Maintenance when the temporary heaters are in service, and removed when weather conditions permit. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-007)

CHALLENGES TO PORVs OR SAFETY VALVES Salem Unit 2 In accordance with the requirements of Salem Generating Station Unit 2 Technical Specifications Section 6.9.1.6, the following recent challenges to PORVs or Safety Valves are being reported:

  • 12/28/93 On 12/28/93, at 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />, Reactor Coolant System (RCS) #22 Accumulator outlet valve 22SJ54 unexpectedly opened and injected an estimated volume of 1735 to 2640 gallons (2200 ppm boric acid) into the RCS. The resultant RCS pressure transient actuated Pressurizer Overpressure Protection System (POPS) Channel I, causing Pressurizer Relief Valve 2PR1 to open. Highest indicated RCS pressure was approximately 372 psig. RCS pressure decreased to approximately 280 psig prior to being recovered by the Pressurizer heaters. This event occurred when test switch TS-603 was operated, per procedure S2.0P-ST.SSP-0010(Q), "Solid State Protection System (SSPS) Train B Slave Relays Testing. Plant equipment responded properly to this event and TS-603 was reset to allow reclosure of 2SJ54. The root cause of this event is Defective Procedure, per NUREG 1022. The procedure did not indicate that operation of the TS-603 would result in opening of 22SJ54. Details of this event are contained in Licensee Event Report 311/93-014-00.

SALEM UNIT NO. 2

  • SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 2 JANUARY 1994 The Unit began the period with heatup in progress, power was held at 480MWE waiting for 22 Steam Generator Feedwater Pump (SGFP) to be returned to service. The SGFP was returned to service on January 7, 1994, and the Unit achieved 97% power on January 8, 1994. Power was reduced to 85% on January 9, 1994, due to circulating water problems.

The Unit was returned to 100% power on January 10, 1994, and continued to operate at essentially full power until January 30, 1994, when load was reduced to 50% to implement a temporary modification to both SGFP governors.

The Unit continued to operate at 50% power throughout the remainder of the period.

  • *
  • REFUELING INFORMATION DoclT NO:

JANUARY 1994 UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

MONTH JANUARY 1994 1. Refueling information has changed from last month: YES NO 50-311 SALEM 2 FEBRUARY 10, 1994 R. HELLER (609)339-5162

2. Scheduled date for next refueling:

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

YES NO X 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

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