ML18100A712

Monthly Operating Rept for Oct 1993 for Salem Unit 1.W/ 931115 Ltr

ML18100A712
Person / Time
Site:	Salem
Issue date:	10/31/1993
From:	Heller R, Shedlock M, Vondra C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9311190292
Download: ML18100A712 (18)

Text

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station November 15, 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 October 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 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 ____ __The Energy People R PDR . Sincerely yours, General Manager -Salem Operations

{;Jf ?" ' l 1 95-2189 (10M) 12-89 9311190292 PDR ADOCK 05000272 i

.* RAGE DAILY UNIT POWER LE-Docket No.: 50-272 Unit Name: Salem #1 Date: 11/10/93 Completed by: Mark Shedlock Telephone:

339-2122 Month October 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 634 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 0 16 0 P. 8.1-7 R1 OPERATING DATA REPORT Docket No: Date: Completed by: Mark Shedlock Telephone:

Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period October 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) Report, Give Reason NA 9. Power Level to Which Restricted, if any (Net MWe) 10. Reasons for Restrictions, if any 12. 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) 17. 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 745 24.67 0 24.12 0 51549.6 16190 11035 3.2 3.2 1. 3 1.3 0 NONE Year to Date 7296 5949.99 0 5747.43 0 18573705.6 6162980 5870601 78.8 78.8 72.8 72.2 12.6 50-272 11/10/93 339-2122 since Last NIA Cumulative 143233 95131.97 0 91887.84 0 290772314 96535970 91942260 64.2 64.2 58 57.6 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 12 1993. 8-1-7.R2 NO. DATE 127 10-01-93 128 10-01-93 129 10-01-93 130 10-01-93 134 10-02-93 1 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH OCTOBER 1993 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 s 3.98 c 5 ------------

RC s 4.00 c 5 ------------

RC s 6.00 c 5 ------------

RC s 2.00 c 5 ------------

RC s 720.88 c 1 ------------

RC 2 3 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction E-Operator Training & License Examination F-Administrative 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 COMPONENT CODE 5 FUELXX FUEL XX FUELXX FUELXX FUELXX 4 DOCKET NO.

UN IT NAME: Salem #1 DATE: 11/10/93 COMPLETED BY: Mark Shedlock TELEPHONE:

339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE CORE COASTDOWN NUCLEAR CORE COASTDOWN NUCLEAR CORE COASTDOWN NUCLEAR CORE COASTDOWN NUCLEAR NUCLEAR NORMAL REFUELING 5 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File Exhibit 1 -Same Source (NUREG-0161)

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SAFETY RELATED MONTH: -OCTOBER 1993 DOCKE.O: UNIT NAME: 50-272 SALEM 1 WO NO UNIT 920512152 1 920707096 1 920805151 1 921207096 1 930107097 1 930920180 1 931004075 1 931010097 1 931015240 1 VALVE 11CC19 DATE: COMPLETED BY: TELEPHONE:

NOVEMBER 10, 1993 R. HELLER (609)339-5162 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:

11CC19 LEAKS THROUGH -OPEN & INSPECT lB DIESEL GENERATOR FAILURE DESCRIPTION:

lB DIESEL GENERATOR LOW OUTPUT SIGNAL -TROUBLESHOOT

& REWORK ORIFICE R0-47 FAILURE DESCRIPTION:

FLANGE LEAKS -REPLACE GASKETS lC DIESEL GENERATOR FAILURE DESCRIPTION:

lC DIESEL GENERATOR SLOW ENGINE RESPONSE -TROUBLESHOOT

& REWORK lC DIESEL GENERATOR FAILURE DESCRIPTION:

lC DIESEL GENERATOR TROUBLE ALARM/NO GROUP ALARM -INVESTIGATE 11 CONTROL AREA SUPPLY FAN FAILURE DESCRIPTION:

11 CONTROL AREA SUPPLY FAN FEED CABLE HOT -INVESTIGATE VALVE 1ABV20 FAILURE DESCRIPTION:

1ABV20 WILL NOT REPOSITION

-TROUBLESHOOT VALVE 13CV252 FAILURE DESCRIPTION:

FLANGE UPSTREAM OF VALVE WAS FOUND LEAKING -REPLACE GASKET lC DIESEL GENERATOR FAILURE DESCRIPTION:

lC DIESEL GENERATOR BREAKER TRIPPING -INVESTIGATE SAFETY RELATED MAINTEN,CE MONTH: -OCTOBER 1993 (cont'd) WO NO UNIT 931030085 1 VALVE 11SW122 DOCKE.O: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 NOVEMBER 10, 1993 R. HELLER (609)339-5162 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:

11SW122 OPERATES OPPOSITE ITS AIR SIGNAL -INVESTIGATE e 10eFR50.59 EVALUATIONS MONTH: -OCTOBER 1993 UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 NOVEMBER 10, 1993 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 (DCPs) lSC-2267 Pkg 3 lEC-3281 Pkg 1&2 "Safeguards Equipment Controller

-ATI Restoration" -This DCP will install new EPROMs in the ATis of the three SECs and spare chassis. It will activate the ATis for the first time. Output alarm relays will be installed in existing XK-90 and XK-91 sockets. Wires will be terminated, as required to allow annunciation at the Aux and Overhead Annunciator System. The ATI provides a self checking function of the SEC. No actuation of plant equipment is initiated by the ATI. Therefore, channel trip accuracy and channel response times are not affected.

No channel indication is affected by the ATI restoration.

Therefore, the restoration of the ATI does not decrease the channel indicated accuracy beyond an acceptance limit. No plant parameters are affected by the ATI restoration.

This modification does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-089) "1SJ12 & 1SJ13 Motor and Motor Gear Set Change" -This change replaces the existing motor, motor overload heater and the motor gear set in the motor operators for valves 1SJ12 & 1SJ13. Under assumed worst case conditions, sufficient margin may not be available to open or close the 1SJ12 & 1SJ13 without exceeding the valve/actuator thrust ratings. This DCP will change from a 15 Ft-lb, 3400 rpm Porter-Peerless to a 15 Ft-lb, 3400 Reliance motor for configuration control. Additionally, the motor overload heaters have been resized to facilitate valve performance and the overall gear ratio has been changed from 69.56:1 to 78.81:1 to optimize valve torque and thrust operational range and reduce the effects of inertial trust. The modifications do not reduce e 10CFR50.59 EVALUATIONS MONTH: -OCTOBER 1993 (cont'd) ITEM lEC-3254 Pkg 1 lEC-3294 Pkg. 1 UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 NOVEMBER 10, 1993 R. HELLER (609)339-5162 the margin* of safety as defined in the basis for any Technical Specification.

The valve maximum allowable stroke time, though slower than existing actual valve stroke time, remains within the ten (10) second IST limit. (SORC 93-089) "Boric Acid Concentration Reduction Modifications" Rev. 1 -This DCP will perform modifications in support of licensing changes being made to the Boric Acid System. These licensing changes are being supported by submittals and recommendations from ABB-CE concerning a reduction of the boric acid concentration in the Boric Acid Tanks (BATs) from 12% to approximately 3.75%. This DCP will provide changes to instruments and components of the Boric Acid System that will incorporate the reduction of concentration of boric acid into the system design basis. Salem Station will be changing the concentration of borated water in the Boric Acid Tanks (BATs) from the present 12% concentration to approximately 3.75%. Analysis for this change has been performed by ABB-CE to support the Licensing Change Request (LCR) for this reduction.

This DCP provides changes to instrumentation and components which support the ABB-CE design analysis.

The implementation of this design change package will not reduce the margin of safety as defined in the basis for any Technical specification.

Licensing Change Request 93-17 has made this determination.

Disconnection of the heat trace and reduction of the boric acid solution concentration in the BAT will not reduce the flow paths and borated water sources required by the Technical Specifications.

The ability to keep the boric acid in solution and deliver the required quantity of borated water remains the same. (SORC 93-090) "No. 11 CCHX Manway Installation" -This DCP entails the installation of an eighteen inch diameter manway and davit on the turnaround side (front) closure head for No. 11 CCHX. In addition, the entire head (wetted side only) will be reclad with 3/8 11 thick 90-10 copper nickel e 10CFR50.59 EVALUATIONS MONTH: -OCTOBER 1993 (cont'd) ITEM 1EC-3287 Pkg 1 UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 NOVEMBER 10, 1993 R. HELLER (609)339-5162 liner. The new manway is similar to the manway installed on the existing service water inlet/outlet (rear) closure head of No. 11 CCHX, which is used for cleaning the service water inlet side tubes and tubesheet.

The new manway will not be hydrostatically tested by the fabricator.

It will be hydrotested in place after being reinstalled on No. 11 CCHX. The proposed modification does not reduce the margin of safety as defined in the basis for any Technical Specification.

The design requirements for the proposed modification have been satisfied.

The function of No. 11 CCHX has not changed. In addition, the proposed modification is being performed during No. 11 SW header maintenance outage as allowed by Technical Specification 3.9.8.2 provided the requirements of the subject Technical Specification are satisfied.

The margin of safety is, therefore, unaffected. (SORC 93-095) "Ammonia/Hydrazine Removal at Salem NRW" -This design change package will provide the Salem Non-Radioactive Liquid Waste Disposal System (NRLWDS,)

the capability to continuously monitor for hydrazine, a non-permitted parameter in its discharge, and distribute a calculated amount of sodium hypochlorite into the NRLWDS Equalization Basin. Other features of this design allow the operators to transfer sodium hypochlorite directly to the NRLWDS Equalization Basin for emergency breakpoint chlorination practices and transfer from storage tank to storage tank for maintenance purposes.

The Technical Specifications do not discuss the NRLWDS. The Sodium Hypochlorite Storage Tanks are not discussed in the Technical Specifications.

No hazardous conditions will result from the implementation of the modifications.

Therefore, the proposed modifications will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-096)

. e 10CFR50.59 EVALUATIONS " MONTH: -OCTOBER 1993 (cont'd) ITEM DOCKE.O: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 NOVEMBER 10, 1993 R. HELLER (609)339-5162 B. Procedures and Revisions TS1.0P-SO.WG-0006(R)

NC.NA-AP.ZZ-0007(Q)

Sl.OP-SO.SF-0002(Q) "Modified Containment Purge to the Plant Vent" -The purpose of this procedure is to provide an alternate method of purging Unit 1 Containment when less than the full compliment of Auxiliary Building supply and exhaust fans area available and a normal Containment Purge is not possible.

This procedure is written to support: 1.) vital bus outages; 2.) ABV fans unavailable, and: 3.) DCP lEC-3208, package 1, fire dampers. The Auxiliary Building Ventilation System and the Containment Purge equipment will continue to perform their intended design function.

The flow rates will be reduced, but all plant effluent will continue to be filtered.

Although total flow rates will be reduced, the effectiveness of the filtration remains unchanged.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-089) "ALARA Program" -In addition to general editorial revisions, the procedure was revised to include the following:

1.) Requires that change packages that include activities in a Radiologically Controlled Area undergo review by the cognizant station ALARA group, regardless of the package's sponsoring organization; 2.) Assigns ALARA responsibilities for all station department managers, and 3.) Deletes attachments for all station ALARA implementing procedures.

This procedure is administrative in nature and has no affect on safety margins. (SORC 93-090) "Spent Fuel Cooling System Operation" Rev. 5 -This limited revision to the procedure:

1.) Changed all references of "pool" to "pit" to match the P&IDs; 2.) Deleted precaution, "Do not cross connect systems after recent spent fuel additions.";

3.) Changes maximum spent fuel temperature during cross connect operations from 11 120°F 11 to 11 150°F 11* Consolidated the spent

. e 10CFR50.59 EVALUATIONS MONTH: -OCTOBER 1993 (cont'd) DOCKE.O: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 NOVEMBER 10, 1993 *R. HELLER (609)339-5162

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ITEM

SUMMARY

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VSC.MD-PM.SW-0009(Q) fuel pit demineralizer maximum temperature "130°F 11 with this step; 4.) Changed "System Engineering" to "Reactor Engineering";

5.) Added a step to ensure that the demineralizer is not purifying the RWST; 6.) Directs Rx Eng. to supply SFP H/U rate estimation; 7.) Deleted System Engineering notification of pending cross connect; 8.) Added a step to ensure the FHB ventilation system is in service, and 9.) Revised the caution preceding step 5.7.lE to reflect the changes at step 3.9. Deleted "Do not cross connect systems after recent spent fuel additions." Moved the statement that normal/emergency cooling must be restored at 120°F from CAUTION, to step 5.7.lM. Changed 11 120°F 11 to 11 150°F 11* This revision does not reduce the margin of safety as defined in the basis for any Technical Specification.

According to the NRC Safety Evaluation Report relating to the modification of the spent fuel storage pool Section 5.3.2, 11 *** even if there were a temporary higher evaporation rate from the spent fuel pool, the resulting increase in tritium and iodine released from the station would be small compared to the amount normally released from the station without these modifications, as was previously evaluated in the FES. In addition, the station radiological effluent Tech. Specs, which will not be affected by this action, will limit total releases of gaseous activity including those from spent fuel. If levels of airborne radioiodine become too high, the air over the spent fuel pool can be routed through charcoal filters for the removal of radioiodine before release to the environment." (SORC 93-092) "Specification/Procedures For In-Situ Application of Palmer International's Tubesheet Cladding System" Rev. O -This is a new vendor procedure that provides instructions for the CeramAlloy Cladding System to be applied to the CFCU main cooling coils/tubesheets and motor coils/tubesheets in accordance with vendor instructions.

This application has been evaluated in accordance with Engineering Evaluation

. e 1oeFR50.59 EVALUATIONS r MONTH: -OCTOBER 19 9 3 (cont'd) ITEM MRS-2.4.2-GEN 38 DOCKE .. O: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 NOVEMBER 10, 1993 R. HELLER (609)339-5162 S-C-CBV-MEE-0829-1, Cladding/Coating Containment Fan Coil Units With a Polymer (CeramAlloy Nuclear Grade) Salem Generating Station, Units 1 and 2. This application serves to inhibit further crevice corrosion attack and extend the existing coil/ tubesheet service life of the containment fan coil units. The proposal does not reduce the margin of safety as defined in the basis for any Technical Specification.

During normal plant operations, at least three of the five fan coil units are required with four units in operation when necessary.

The standby unit will take over for the malfunctioning

/inoperable unit. During accident conditions, three (3) options are available for mitigation. (SORC 93-092) "Shot Peening of the Steam Generator Hot Leg Side Tubes" Rev. 5 -Shot peening of the hot leg side stream generator tubes is being proposed at the Salem Units during lRll and 2R8. The shot peening will be performed under Westinghouse field procedure MRS-2.4.2-GEN 38 Rev. 5. The intent of the shot peening process is to increase the margin of resistance in the areas of the tubes within the tubesheet and transition region that are susceptible to primary water stress corrosion cracking (PWSCC). The shot peening operation includes the shot peening of each tube through the tubesheet area, the transition area, and an increment of the unexpanded tube above the top of the tubesheet.

The margin of safety can be increased for tubes which are not degraded.

Corrosion testing has shown the shot peening process will significantly retard the development of PWSCC at the tube expansion transition.

The evaluation shows that all applicable acceptance criteria will continue to be met. There are no adversely impacted Technical Specifications, and the safety margins are not reduced. Thus the margin of safety as defined in the basis for the Technical Specifications will not be changed. (SORC 93-093)

-10CFR50.59 EVALUATIONS MONTH: -OCTOBER 1993 (cont'd) ITEM DOCKE.O: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 NOVEMBER 10, 1993 R. HELLER (609)339-5162

c. Temporary Modifications TMOD 93-114 TMOD 93-102 "Provide Temporary Diesel Generator Power to Facilitate Unit 1 No. 11 Screenwash Pump as an Emergency Standby Spare Screenwash Pump During 1Rll 11 -The purpose of this TMOD is to provide temporary diesel generator power to facilitate Unit 1 No. 11 Screenwash Pump as an emergency standby spare screenwash pump during lRll. By TMOD 93-105, one end of two temporary cables, (1) 3/C-2/0 AWG and (1) 3-1/C #12 AWG will be connected to the 480 VAC No. 11 Screewash Pump motor terminals and 230 VAC supply terminals to the related strainer motor control panel (947-lA) respectively.

By this TMOD, the other ends of the two cables will be connected to the 480 VAC and 230 VAC power supply fed from the diesel generator.

The Unit 1 screenwash components will then be available to supplement Unit 2 demand. This modification.does not reduce the margin of safety as defined in the basis for any Technical Specification.

This modification increases Circulating Water System reliability and availability during lRll. (SORC 93-088) "lB Bus outage" -The electrical modifications are required to supply temporary power to the #12 Fuel Handling Building Exhaust Fan. The temporary jumper cables specified are used in the same application and environment as the normal power supply cables. The temporary jumper cables are of the same size, type, temperature rating, voltage rating and meet the same qualification requirements as the normal power supply cables. The overcurrent protection provided to the temporary jumper and normal power supply cables is not altered by this TMOD package. The temporary jumper cable installation precludes physical damage and has been seismically evaluated to ensure the temporary cables will remain in place during a seismic event. System voltage degradation and electrical system overload concerns have been addressed per the requirements to monitor and/or shed loads as described in this e 10CFR50.59 EVALUATIONS MONTH: -OCTOBER 1993 (cont'd) ITEM TMOD 93-092 TMOD 93-092 UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 NOVEMBER 10, 1993 R. HELLER (609)339-5162 TMOD package. The Temporary Jumpers are limited in use to Modes 5, 6 or Mode undefined.

All temporary jumpers must be removed and equipment must be returned to normal configuration before entering Mode 4. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-089) "Emergency Lighting Panels Temporary Power Supply" -The installation of DCP lEC-3245 during Unit 1 outage 1R11 replaces existing Emergency Lighting Inverters with new 7.5KVA Cyberex inverters.

T-Mod 93-062 provides temporary power supplies from existing Solatron transformers to Emergency Lighting panels lELD-A, lELD-B, and lELC. This T-Mod provides temporary power from lighting panel A12A to Emergency Lighting panel lELD-A while 230VAC Vital bus "lA" which supplies power to the Solatron transformer is deenergized.

The Emergency Lighting Panel feeder will be returned to the Vital bus "lA" Solatron transformer which is its normal alternate source of power as soon as 230VAC Vital Bus "lA" is reenergized.

Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-090) "Emergency Lighting Panels Temporary Power Supply" -The installation of DCP lEC-3245 during Unit 1 outage 1R11 replaces existing Emergency Lighting Inverters with new 7.5KVA Cyberex inverters.

T-Mod 93-062 provides temporary power supplies from existing Solatron transformers to Emergency Lighting panels lELD-A, lELD-B, and 1ELC. This T-Mod provides temporary power from lighting panel A12A to Emergency Lighting panel lELD-B and lELC while 230VAC Vital Bus "1B" which supplies power to the Solatron transformers is deenergized.

The Emergency Lighting Panel feeders will be returned to the Vital bus "lB" Solatron transformers which are their normal alternate source of power as soon as 230VAC Vital Bus "1B" is reenergized.

e 1oeFR50.59 EVALUATIONS MONTH: -OCTOBER 1993 (cont'd) ITEM TMOD 9.3-122 TMOD 93-101 TMOD 93-103 DOCKE,NO:

UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 NOVEMBER 10, 1993 R. HELLER (609)339-5162 Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-090) "Provide Temporary Power to 230V Bus "lH" During # 11 Station Power Transformer Outage" Rev. 1 -The purpose of this modification is to install temporary electrical jumpers between 230V Bus "lF" Breaker 1F4Y & 230V Bus "lH" Breaker 1H6Y to provide temporary power to 230V Bus "lH" loads. The electrical modifications are necessary to provide temporary power to 230V Bus "lH" to feed miscellaneous loads during the #11 Station Power Transformer (SPT) outage. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-094) "Provide Temporary Power to #11 Fuel Handling Building Exhaust Fan" -The purpose of this modification is to install temporary electrical jumpers to provide temporary power to #11 Fuel Handling Building Exhaust Fan. The temporary jumpers are limited in use to Modes 5, 6 or Mode undefined.

All temporary jumpers must be removed and equipment must be returned to normal configuration before entering Mode 4. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-096) "Provide temporary Power to 230V Bus "lF" During #12 Station Power Transformer outage" -The purpose of this modification is to install temporary electrical jumpers between 230V Bus "lH" Breaker 1H6Y & 230V Bus "lF" Breaker 1F4Y to provide temporary power to 230V Bus 11 1F" loads. The electrical modifications are required to provide temporary power to"lF" 230V Group Bus, during the #12 Station Power Transformer (SPT) outage. All the temporary jumpers are for convenience items and are 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 93-096) e 10CFR50.59 EVALUATIONS MONTH: -OCTOBER 1993 (cont'd) ITEM D. SAR Change SCN 92-01 UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 NOVEMBER 10, 1993 R. HELLER (609)339-5162 "UFSAR Changes" -This change will remove the manufacturer and model numbers for the major waste gas system equipment from section 11.3 of the UFSAR. There is no physical or operational change, it is purely administrative.

Neither the Technical Specifications in Section 3/4.11, Radioactive Effluents, nor their basis, Section 2.0, are changed as there is no physical or operational changes. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-090)

.* SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 1 OCTOBER 1993 The Unit began the period operating at full power. The Unit was removed from service at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on October 2, 1993 to commence the scheduled eleventh refueling outage. The refueling outage continued throughout the remainder of the period.

. e ,. REFUELING INFORMATION MONTH: -OCTOBER 1993 MONTH OCTOBER 1993 -DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

1. Refueling information has changed from last month: YES X NO 50-272 SALEM 1 NOVEMBER 10, 1993 R. HELLER {609)339-5162

2. Scheduled date for next refueling:

OCTOBER 2. 1993 3. Scheduled date for restart following refueling:

DECEMBER 12, 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 NO x If no, when is it scheduled?:

NOVEMBER 93 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 b. In Spent Fuel Storage 925 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