ML18096A721

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Monthly Operating Rept for Apr 1992 for Salem Generating Station Unit 1.W/920514 Ltr
ML18096A721
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/30/1992
From: Fest J, Shedlock M, Vondra C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9205210244
Download: ML18096A721 (17)
v • d • e


Text

-*

  • ops~G Put:>lic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station May 14, 1992 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 April 1992 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 Si~~

neral~er 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

..-Ihe_Enerav_f>_film Ie 9205210244 920430 -

c&ZJ/-',, ,

kDR ADOCK 05000272 PDR 95-2189 (10M) 12-89

AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-272 Unit Name: Salem #1 Date: 05/10/92 Completed by: Mark Shedlock Telephone: 339-2122 Month April 1992 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1120 17 0 2 1118 18 0 3 1001 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 Rl

  • OPERATING DATA REPORT Docket No: 50-272 Date: 05/10/92 Completed by: Mark Shedlock Telephone: 339-2122 O:geratinq Status
1. Unit Name Salem No. 1 Notes
2. Reporting Period A:gril 1992
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. . . . A~~~~~~~~~~~~

This Month Year to Date Cumulative

11. Hours in Reporting Period 719 2903 130056
12. No. of Hrs. Rx. was Critical 72.15 2256.15 85856.43
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 71. 67 2117.77 83165.71
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 238874.4 7203120.0 262700265.2
17. Gross Elec. Energy Generated (MWH) 80970 2416240 87220870
18. Net Elec. Energy Gen. (MWH) 73313 2311885 83088458
19. Unit Service Factor 10 73.0 63.9
20. Unit Availability Factor 10 73.0 63.9
21. Unit Capacity Factor (using MDC Net) 9.2 72.0 57.8
22. Unit Capacity Factor (using DER Net) 9.1 71.4 57.3
23. Unit Forced Outage Rate 0 6.1 21. 0
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

NA

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

JUNE 15 1992 8-l-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH APRIL 1992 DOCKET NO.: -'5=0'--=27...,,2,___ __

UNIT NAME: Salem #1 DATE: 05/10/92 COMPLETED BY: Mark Shedlock TELEPHONE: 339-2122 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION*

2 NO. DATE TYPE 1 (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 0016 04/03/92 s 647.33 c 1 ------------ RC FUELXX NUCLEAR NORMAL REFUEL! NG 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 CNUREG-0161)

E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

MONTH: - APRIL 1992 SAFETY RELATED MAINTENANCE DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 910417046 1 VALVE 1SJ233 FAILURE DESCRIPTION: HANDWHEEL IS MISSING - REPLACE 910730112 1 1C DIESEL GENERATOR FAILURE DESCRIPTION: REFURBISH GENERATOR SLIP RINGS 911018107 1 1C DIESEL GENERATOR FAILURE DESCRIPTION: RECEIVER DRAIN VALVE LEAKS BY -

REPAIR 920128129 1 1R46 RADIATION MONITORS FAILURE DESCRIPTION: WRONG TYPE DETECTORS INSTALLED -

REPLACE 920317155 1 1R11A RADIATION MONITOR FAILURE DESCRIPTION: MOVEMENT OF CABLE CAUSED ISOLATION - INVESTIGATE & CORRECT 920330156 1 1R46C RADIATION MONITOR FAILURE DESCRIPTION: MONITOR ALARMS LOW - INVESTIGATE 920330298 1 11 COMPONENT COOLING PUMP FAILURE DESCRIPTION: 11 COMPONENT COOLING PUMP DISCHARGE PRESSURE IS HIGH -

INVESTIGATE 920331127 1 11 RHR PUMP FAILURE DESCRIPTION: 11 RHR PUMP COMPONENT COOLING FLOW ALARM - INVESTIGATE 920416087 1 lC DIESEL GENERATOR FAILURE DESCRIPTION: INLET HEAD SERVICE WATER LEAK -

REPAIR 970225001 1 lC DIESEL GENERATOR FAILURE DESCRIPTION: REPLACE TURBO BOOST INLET SOLENOID VALVE

10CFR50.59 EVALUATIONS MONTH: - APRIL 1992

  • DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 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 (DCP)

DCP# lSC-2256 Pkg. 1 "Interim Operability for Intake Bay No. l" Rev. 1

- The purpose of this change is to replace the existing Salem Unit 1, Intake Bay l, Service Water piping and fittings associated with the strainer backwash lines, the bay overpressurization line (including reroute), the 20-inch strainer discharge flanged elbows and the screenwash/SW Pump Motor Cooler and bearing lube lines with 6%

molybdenum stainless steel. The temporary conditions associated with the installation of this modification do not impact the ability of the Service Water system to perform its intended safety functions. If a postulated flooding event were to occur, the appropriate Technical Specification Action Statement will be entered until the event is mitigated. The permanent configuration installed by this DCP does not affect the emergency operation of the Service Water system. The system will function in the same manner as it did prior to this modification since this is a material upgrade and the configuration changes are minor. The proposed modifications do not reduce the margin of safety as defined in the basis for any Technical Specifications. ( SORC 92-043)

DCP# lEC-3144 Pkg. 1 "Containment Pressure High-High Setpoint Reduction" - The purpose of this change is to establish the new Allowable Value and Setpoint for Containment High-High (High2) Pressure based on Safety Analysis Value of 17 PSIG. This will result in a change to the Technical Specification Allowable Value from 24.0 PSIG to 16.0 PSIG and therefore a new Trip Setpoint from 23.5 PSIG to 15.0 PSIG based on the setpoint calculation.

Westinghouse, in conjunction with the Nuclear Fuels Group, has concluded in Westinghouse Safety Evaluation SECL-92-049, that

10CFR50.59 EVALUATIONS MONTH: - APRIL 1992

  • DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

adequate margin exists between the new analytical limit of 17 psig and the associated safety limit of 47 psig. This modification will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 92-046)

DCP# lEC-3131 Pkg. 1 "Generator Hydrogen Gas Dryer Replacement" - The purpose of this change is to replace existing hydrogen dryer 1HYE2,3 in Turbine Generator Area (TGA) Unit 1 (EL. 120' near Col. Line H-3) with Pneumatic Products Corp. (OOC) Hydrogen Gas Dryer Model 1/2" carbon steel supply and return hydrog-en line with 1" stainless steel lines to accommodate increased hydrogen dryer flow. Since this DCP only involves replacing the existing hydrogen gas dryer with a new dryer of a similar type, and replacing the existing hydrogen lines using the same routing as the original lines, it is concluded that no additional analyses beyond that already in the UFSAR is required. Furthermore, this DCP does not involve a change in the quantity of hydrogen on site or in its method of storage.

The operation of the hydrogen system, and or the hydrogen dryer is not addressed in the Technical Specifications. The margin of safety as defined in the Technical Specifications is not reduced.

(SORC 92-046)

DCP# lEC-3111 Pkg. 1 "Replacement of Electronics Processing Signals from the Radiation Detectors of 2 Radiation Monitors" Rev. 1 - In revision 1 of this package, the relays that provide the downscale signal to an ESF actuation will have the jumpers removed. All downscale signals such as low flow, pump out, paper tear, delta flow, and checksource fail will be an alarm/annunciation to the Control Room only. All upscale readings and loss of power will both signal an ESF actuation and alarm/annunciate to the Control Room. This change will only pertain to the 1R41A,B and C channels. This modification is being implemented to reduce the number of spurious ESF actuations generated by the existing radiation monitoring equipment. There is no reduction in the margin of safety, as defined in the Technical Specifications since the monitors

10CFR50.59 EVALUATIONS MONTH: - APRIL 1992

  • DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

perform no function required to mitigate radiation exposures at the site boundary, resulting from accidents described in the UFSAR Sections 15.3 and 15.4. (SORC 92-046)

DCP# lSC-2269 Pkg. 5 "Salem Electrical Distribution System Upgrade" -

The intent of this change package is to install prefabricated bus sections on the east and west sides of the 500KV bus structure and to install prefabricated bus and switches on the east and west sides of the 13KV ring bus. This change does not reduce the margin of safety as defined in the basis for any Technical Specification. The new 13KV disconnect switches installed between the 500/13KV transformers and the.13KV North Ring Bus are only required to operate to isolate the transformer after the transformer has been taken out of service. These switches are not required to open in any other condition and will not impact any other equipment. The remaining 13KV disconnect switches and the 500KV circuit switchers are not required to operate and will remain locked open. Therefore, this change does not reduce the margin of safety as defined in the bases for any Technical Specification.

(SORC 92-049)

DCP# lEC-3162 Pkg. 1 "Installation of Turbine Auto Stop Oil System Filters" - This modification involves the installation of a parallel set of 6 micron filters on the supply side of the Autostop Oil System in response to the Salem Unit 2 turbine/generator failure of November 9, 1991. The addition of the filters is intended to prevent the clogging of the supply orifice by foreign particles. This modification will also add an input to the Control Room annunciator to alarm on high filter differential pressure. It also changes the operating procedures to require checking the differential pressure prior to performance of the periodic tests, require shift logging of the differential pressure reading, and changeout of the filters on high differential pressure. No change is made to the design or function of the turbine trip system. Although valves included with this modification for the valving in and out

10CFR50.59 EVALUATIONS MONTH: - APRIL 1992 DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

of service of the filter assemblies create a new possibility for the turbine trip, administrative controls, Control Room alarm, gages and procedures are put in place to ensure that the probability of this type of failure has not been increased. No safety related functions or system are impacted.

(SORC 92-051)

DCP# lEC-3166 Pkg. 1 "Turbine Generator Betterment - Misc. Turbine Control Systems" - The purpose of this chang-e is to add/change the following: 1) Add a 110%

overspeed trip signal to the regular turbine trip circuit with interlocks from the Main Generator Breakers; 2) Modify the shape of the turbine overspeed trip test lever, and 3) Interlock the operation of the main steam stop valves bypass valves with the governor valves. This modification does not reduce the margin of safety as defined in the Technical Specifications. This modification only adds an additional means of tripping the turbine on an overspeed condition and has no effect on the existing OPC or mechanical over speed trip. ( SORC 92-054)

DCP# lSC-2049 Pkg. 1 "Seismic Gap Seals Obstruction Removal" - The purpose of this change is to relocate or modify obstructions identified during preliminary walkdowns for installation of Seismic Gap Seals.

The bases for all Technical Specifications were reviewed to determine that no margins of safety as defined are therein reduced as a result of removing seal material from the affected penetration, drilling a hole through the wall, or installing seal material in the penetrations.

(SORC 92-054)

10CFR50.59 EVALUATIONS MONTH: - APRIL 1992

  • DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

B. Procedures and Revisions (Proc)

NC.NC-AP.ZZ-0013(Q) "Control of Temporary Modifications" Rev. 1 - The purpose of this revision is to enhance the overall process for identifying, preparing, reviewing, approving, installing and removing temporary modifications. This revision also provides additional clarification for processing previously undocumented modifications. This revision to the procedure does not involve any portion of the Technical Specifications, therefore, the proposal cannot reduce the margin of safety as defined in the basis for any Technical Specification.

(SORC 92-039)

Security Plan "Artificial Island Security Plan" Rev. 2 The purpose of this procedure is to revise the plan primarily to incorporate regulatory changes required by 10CFR73.56, which imposes uniform nuclear plant access authorization programs.

Other changes of significance include: 1) revised perimeter intrusion detection zones and increased testing frequency, a result of implementation of commitments in response to concerns raised bi the NRC Regulatory Effectiveness Review (TAC No.

72711) conducted 4/10-14/89;2) definition of temporarily designated licensee vehicles (TDLV).

The Security Plan changes are designed to contribute to the overall program objective of preventing intentional acts such as attacks or attempts to sabotage the plant. The changes contribute to reducing the probability of an intentional act of sabotage by increasing overall personnel trustworthiness and security system reliability. There is no reference in the Technical Specifications to the procedure subject. Therefore, the margin of safety as defined in the Technical Specifications is not reduced. ( SORC 92-043)

SP-9 "SP 9 - Control of Packages and Material" Rev. 4 -

The purpose of this procedure revision incorporates provisions for screening material at the Centralized Warehouse, adds examples of Category III material (exempted from search requirements), and specifies materials prohibited

10CFR50.59 EVALUATIONS MONTH: - APRIL 1992

  • DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

from being introduced to primary containment, and contains editorial changes which do not alter the procedure's intent of implementation. The procedure is designed to prevent intentional acts such as attacks or attempts to sabotage the plant, or restore security systems that are necessary toward that purpose. The procedure changes are intended to decrease the probability of success of an act of sabotage arising from the surreptitious introduction of firearms, explosives, incendiary devices, etc. There is no reference in the Technical Specifications to the procedure subject. Therefore, the margin of safety as defined in the Technical Specifications is not reduced. (SORC 92-043)

VSI.RE-FR.ZZ-0004(Q) "Westinghouse Refueling Procedure" - The purpose of this Westinghouse Refueling Procedure is to guide the Salem Unit 1 Tenth Refueling Operations. This procedure provides instructions for fuel movement operations and for unlatching (and latching) driveshafts from (to) control rods. Fuel movement operations include: fuel handling equipment checkout and operation, refueling equipment checkout and operation, full core unload, insert changeouts, core reload, and core mapping system setup and operation. The proposed refueling procedure will not reduce the margin of safety as defined in the basis for any Technical Specifications since no TS Limiting Conditions for Operation will be violated. The Charging system and boron tnjection f lowpaths will be maintained in accordance with TS 3.1.2.

Furthermore, all refueling operations will be conducted within the limits of TS 3.9. Therefore, the margin of safety is not reduced by this procedure. ( SORC 92-043)

Application Procedure "CeramAlloy Cladding" - It is assumed that the tubesheet of SGS Unit 1 pump room coolers (11 total) are suffering from crevice corrosion at the tube/tubesheet interface similar to SGS Unit 2 pump room coolers. This will be confirmed by inspection during the SGS Unit 1 tenth refueling outage. The room coolers for both SGS Units 1 and 2 were purchased of the same materials under one

10CFR50.59 EVALUATIONS MONTH: - APRIL 1992

  • DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

purchase order (P.O.# 892514) and were subjected to the same environment and/or service water chemistry. Unit 1 and Unit 2 cooling coils were installed in May, 1984 (DCR 2EC-0506),

respectively. The tubesheet is fabricated from Type 316L stainless steel plate, 1.4 inches thick. Tubes are AL-6X (UNS NO 8366) stainless steel. To stop further crevice attack and enhance the tube/tubesheet interface leak tightness the tubesheet will be cladded/coated with a polymer (CeramAlloy Nuclear Grade). The application of CeramAlloy cladding on the pump room cooler tubesheet will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the SAR. The possibility of the cladding/coating to peel off from the substrate is very unlikely. The tests, (Push-Out, Bend, Adhesion and Disbandment) performed on the coating assure the reliability and effectiveness of the coating. (SORC 92-045)

VSC.SS-IS-RCE-0036(Q) "The purpose of this procedure is to revise VSC.SS-IS-RCE-0036(Q), Mechanical Plugging of Steam Generator Tubes for Salem Nuclear Power Plant. This is a limited revision to the procedure. Appendix V has been added to incorporate the increased steam generator tube plugging limit based on safety evaluation S-C-RC-MSE-0807. The evaluation for the increased plugging limit has taken into account the applicable Technical Specifications and has bounded the conditions under which the specifications permit plant operation. This safety evaluation has concluded that the results as presented in the FSAR remain bounding. As such, the margin of safety as defined in the bases to the Technical Specifications, and protected by the safety analyses, will not be reduced.

(SORC 92-046)

TSC.OP-SH.CH-OOOl(Q) "Chilled Water Cross Tie Connection - Unit 1 RlO Outage" - The purpose of this procedure is to address allowing chilled water system operation in the cross-tied configuration with three chillers operating of Salem Unit Two and none operating on Salem Unit One. Although Operating Procedure

1 10CFR50.59 EVALUATIONS MONTH: - APRIL 1992

  • DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 I

I I

I I

I I

I COMPLETED BY: J. FEST I I

TELEPHONE: (609)339-2904 I (Cont'd) I I

ITEM

SUMMARY

V-9.3.l already allows the Ul and U2 chilled water systems to be cross-tied in this configuration, review of the design calculation and subsequent Safety Evaluation (S-C M915-MDC-053 and S-1-M915-MSE-243, respectively), which the procedure was based on, has raised further questions on this operating mode. A new design calculation using data collected in the Configuration Baseline Documentation Program has been developed (no. S-C-CAV-MDC-0984 Rev. 1), and will be used as a basis to allow this mode of operation. The margin of safety as defined in the Technical Specification bases is unaffected.

Sufficient cooling is still available to ensure Control Room air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and habitability.

(SORC 92-046)

OP-II-12.3.3A "Containment Purge to the Plant Vent" Rev.2 - This revision permits a Containment Purge to be performed with only 2 Auxiliary Building Ventilation (ABV) Exhaust Fans in operation, instead of the 3 that had formerly been required, while still maintaining a negative pressure in the Aux. Bldg. This evolution will only be performed when the Unit is in Mode 7 (the Undefined Mode, with all fuel in the Spent Fuel Pool), to provide fresh air and cooling for personnel working in Containment. While Tech Specs do not preclude Containment Purging with only 2 ABV Exhaust Fans in operation, FSAR Section 9.4.4.2.2 states that 3 ABV Exhaust Fans provide the dual capability of purging the Containment and exhausting the Aux.

Bldg. Consequently, Question 2.a (Does the proposal change the facility as described in the SAR?) of the 50.59 review was answered "Yes", and the remainder of the 50.59 review completed to demonstrate that no Unreviewed Safety Question exists. ( SORC 92-050)

NC.NA-AP.ZZ-0002(Q) "Nuclear Department Organization" Rev. 0 - The delegation of authority is provided within this procedure to ensure that the functions and responsibilities of a position will be maintained. This is an administrative procedure

1 10CFR50.59 EVALUATIONS MONTH: - APRIL 1992 DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 I

I I

COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

that is limited to defining roles and responsibilities pertaining to organizational functions, and as such, does not change any safety limit, safety system setting, limiting condition for operation, or design feature as described in the Technical Specifications. (SORC 92-054)

NC.NA-AP.ZZ-0055(Q) "Outage Management Program" Rev. 1 - The purpose of this procedure is to make the necessary changes in the wording, responsibilities, and add/change specific guidance. The revision to the procedure enhances the administrative control of outage management. The implementation of this procedure, in conjunction with other Nuclear Department Procedures, provides controls to ensure that outage activities are performed safely and in compliance with licensing requirements and suggested industry guidelines for outage management. {SORC 92-054)

C. Temporary Modifications TMR# 92-005 "Supply of Temporary Power to the #12 Fuel Handling Building Exhaust Fan" - These electrical modifications are required to supply Temporary Power to the Exhaust Fan, No. 1 Battery Room Exhaust Fans, and No. 1 Radiation Monitor Containment Sample Pump. 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, meets all electrical separation requirements for modes 5 or 6 operation, and has been Seismically evaluated to insure 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 TMOD package. (SORC 92-044)

10CFR50.59 EVALUATIONS MONTH: - APRIL 1992 DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (Cont'd)

ITEM

SUMMARY

TMR# 92-002 "Supply of Temporary Power to Turbine Area Welding and Stress Relieving, Met Tower, Turbine Building Elevator, Service Building Elevator, Cafeteria Power Panels, TRIS Computer A/C, and Service Building HVAC Fan During the 11 SPT Outage" - The sizes of the temporary jumpers are IAW the National Electrical Code; Table 310-16, based on the expected load requirements. The overcurrent protection selected for the jumpers will prevent overload should the actual load exceed the expected load. System voltage degradation and electrical system overload concerns have been addressed per the requirements to monitor and/or shed load. ( SORC 92-052)

TMR# 92-003 "Installation of Temporary Electrical Jumpers" -

The purpose of this T-MOD is to install temporary 460V and 230V electrical jumpers between No.

1F-460V Bus & No. 1H-460V bus, and between No.

1F-230V Bus & No. 1H-230V Bus. The Electrical Modifications are required to supply temporary power to Heating Boiler 460V & 230V Control Centers, Turbine Area Welding Outlets, Turbine Crane, & Administrative Building Cafeteria Ventilation 230V C.C, during SPT # 12 Outage. The sizes of the Temporary Jumpers are IAW the National Electrical Code, Table 310-16, based on the expected load requirements. The Overcurrent Protection selected for the temporary jumpers will prevent overload, should the actual load exceed the expected load. The temporary jumper cables used are our standard 90 degree C, low voltage type cables which can be used in wet or dry conditions and have been qualified for class lE use. Systems voltage degradation and Electrical System overload concerns have been addressed per the requirements to monitor and/or shed loads as described in this TMOD package. (SORC 92-054)

" .

  • SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 APRIL 1992 SALEM UNIT NO. 1 The Unit began the period operating at full power, and continued to operate at full power until April 3, 1992, when it was removed from service for the 10th Refueling Outage.

. - ~

REFUELING INFORMATION MONTH: - APRIL 1992 DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 MAY 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 MONTH APRIL 1992

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next refueling: APRIL 4, 1992
3. Scheduled date for restart following refueling: JUNE 16, 1992
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 x 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 0
b. In Spent Fuel Storage 849
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

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