ML18100A605

Monthly Operating Rept for Aug 1993 for Salem Generating Station Unit 1.W/930913 Ltr

ML18100A605
Person / Time
Site:	Salem
Issue date:	08/31/1993
From:	Heller R, Shedlock M, Vondra C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9309150400
Download: ML18100A605 (15)

Text

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station September 13, 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 August 1993 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 Operating Summary Refueling Information Salem Operations 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

---\!l 0 0 9 R . . PDR \)' ' 95-2189 (10M) 12-89

DAILY UNIT POWER Docket No.: 50-272 Unit Name: Salem #1 Date: 9/10/93 Completed by: Mark Shedlock Telephone:

339-2122 Month August 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1036 17 1054 2 1067 18 973 3 1082 19 739 4 1064 20 1038 5 1010 21 1038 6 1051 22 1084 7 1109 23 1069 8 1095 24 976 9 1091 25 1086 10 1065 26 1065 11 1090 27 1052 12 1059 28 1055 13 1086 29 1064 14 1099 30 1065 15 1074 31 1071 16 1030 P. 8.1-7 Rl

'/ OPERATING DATA REPORT Docket No: Date: Completed by: Mark Shedlock Telephone:

Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period August 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 2 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 NA This Month Year to Date 744 5831 744 5205.32 0 0 744 5003.31 0 0 2506725.6 16060850.4 815430 5333250 780935 5078693 100 85.8 100 85.8 94.9 78.8 94.1 78.l 0 14.2 50-272 09/10/93 339-2122 since Last N/A cumulative 141768 94387.3 0 91143.72 0 288259458.8 95706240 91150352 64.3 64.3 58.1 57.7 21.1 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Refueling, 10-02-93 approximately 72 days. 25. If shutdown at end of Report Period, Estimated Date of Startup: NA 8-l-7.R2 NO. DATE 1 2 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH AUGUST 1993 DURATION TYPE 1 (HOURS) REASON 2 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refuel ing D-Requlatory Restriction METHOD OF SHUTTING DOWN REACTOR E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain)

NONE 3 LICENSE EVENT SYSTEM REPORT # CODE 4 Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous outage 5-Load Reduction 9-0ther 4 DOCKET NO.: -'s"-'o".,--=27'-'2'""=" __ _ UNIT NAME: Salem #2 DATE: 09/10/93 COMPLETED BY: Mark Shedlock '. TELEPHONE:

339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION CODE 5 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161)

TO PREVENT RECURRENCE 5 Exhibit 1 -Same Source -e l SAFETY RELATED MAINTEN,CE MONTH: -AUGUST 1993 DOCKETtlto:

UNIT NAME: 50-272 SALEM 1 WO NO UNIT 930720123 1 930811067 1 930821097 1 DATE: COMPLETED BY: TELEPHONE:

SEPTEMBER 10, 1993 R. HELLER (609)339-2212 EQUIPMENT IDENTIFICATION FUEL HANDLING BLDG EXHAUST FAN FAILURE DESCRIPTION:

REPLACE SHEAVE AND BELTS ON EXHAUST FAN BREAKER 1CX1AX7X FAILURE DESCRIPTION:

SPRING CHARGING MOTOR BURNED OUT -REPLACE lC 125V BATTERY FAILURE DESCRIPTION:

BATTERY CELL 47 LOW ICV -REWORK 1--. . . e 10CFR50.59 EVALUATIONS MONTH: -AUGUST 1993 UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 SEPTEMBER 10, 1993 R. HELLER (609)339-2212 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) lEA-1038 Pkg 1 lSC-2269 Pkg 7 "Removal of Freshwater Pretreatment System" -This DCP documents the removal from service of the Fresh Water Pretreatment System. The DCP will provide for the revision and update of the associated drawings as listed on the Document Change Cover sheet. This system which consisted of clarifiers, gravity filters, pumps, chemical feeds, and associated controls was intended to serve as a "kidney" to remove very low level particulate and colloidal matter from well water before it was supplied to the Makeup Demineralizer system. The system proved to be very labor intensive to operate, produced higher volumes of waste than originally anticipated, and offered only marginal improvement in water quality. With the availability of better quality raw water from new wells, the Fresh Water Pretreatment System was no longer needed. The system was demolished and the building converted by station Maintenance some years ago to a 4KV Breaker Test Facility.

The Technical Specifications and Environmental Technical Specifications were reviewed.

Neither addresses Fresh Water, Fresh Water Pretreatment, Potable Water or Demineralized Water Makeup. There is no reduction in the margin of safety as defined in the SAR. (SORC 93-073) "Connection of Offsite Power Sources" -This package will provide the final connections between the two (2) new offsite power sources between the offsite transmission network and the Salem Unit #2 class lE distribution system (Vital buses 2A, 2B, & 2C) and Unit #2 new cw switchgear.

All cations required to make the system operable, not covered under other packages 1, 2, 3, 5, 6, a, 10, 12, 13 & 14 will be done under this package. This change will increase voltage recovery on vital and

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

50-272 SALEM 1 SEPTEMBER 10, 1993 R. HELLER (609)339-2212

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ITEM

SUMMARY

lEC-3251 Pkg 1 NC.NA-AP.ZZ-0008(Q) group buses during bus transfer, provide load growth capacity, improve voltages in the plant, provide margin for short circuit capability and improve plant reliability.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-075) "Restoration of Upfront Chlorination" -The upfront chlorination system is presently configured to permit the upfront chlorination valves (SW32s) to remain in the open position during strainer backwash, thus allowing chlorinated water to be discharged into the river, which was viewed as an "Unpermitted Discharge".

This resulted in the upfront chlorination system being taken out of service. This design change will restore the upfront chlorination system to a configuration that will prevent chlorinated water from being discharged into the river during strainer backwash.

This modification does not affect the function of the Service Water System, only the upfront chlorination system which is not addressed in the Technical Specifications.

Therefore, this modification does not reduce the margin of safety as defined in the Technical Specifications. (SORC 93-075) "Control of Design & Configuration Change, Tests and Experiments" -This proposal involves the following changes: 1.) Formally recognize the Temporary Workbook 6, Engineering Change Authorization, as the permanent Workbook 6 in section 4.1.2 and 5.5.4 of the text and Attachments 2, 4A, 4B and 11; 2.) Relocate the Workbook 6 selection criteria from the Temporary Workbook 6 to Attachment 3C, a new NAP-8 attachment; 3.) Limit SORC review of Workbook 6 Configuration Change Packages to only those requiring Safety Evaluations (10CFR50.59 applicable), per Attachment 4A, SORC Review Determination Logic Chart; 4.) Modify the definition of Change Document (CD) to address its --------

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

50-272 SALEM 1 SEPTEMBER 10, 1993 R. HELLER (609)339-2212 ITEM

SUMMARY

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lEE-0028 Pkg 1 lEC-3285 Pkg 1 special use in Workbook 6 as the only type of interim document revision.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-075) "Chemical Feed/Steam Quality Pipe Removal" -This design change entails the removal of three (3) chemical injection feed lines on the condensate system, one (1) chemistry sample line on the feedwater system and two (2) steam quality sample lines on the main steam system at the following locations:

lBFlO (1" Chemistry sample isolation valve); 11CF19 (i" Chemical feed isolation valve); 12CF19 (1 11 Chemical feed isolation valve); 13CF19 (1" Chemical feed isolation valve); 11MS122 (1 11 steam quality sample line); 12MS122 (1" Steam quality sample line). Chemical injection/steam quality sample lines similar to the subject lines have a history of failure (Reference PSE&G Research and Testing Laboratory Report No. 74151) which could affect the operations/function of equipment and components downstream of these connections.

Recently, failure of 2BF10 sample line on the Salem Unit 2 resulted in the loss of feedwater isolation on the 24BF19 valve during a plant trip due to the sample pipe lodging in the valve seat area. The subject lines have been identified by the Salem Chemistry and Technical Departments as not functional and not required.

The proposed modification does not change or effect the secondary chemistry program as presently implemented.

There is no reduction in the margin of safety as defined in the basis for the Technical Specifications. (SORC 93-076) "SW Auto-start Setpoint" -The purpose of this design change is to reconstitute design basis for low SW Header Press Alarm and auto start setpoints, recalibrate instrumentation to reflect new setpoint and recalibrate SW Header Pretransmitter and local gauge to reflect new scaling valves. The reason for this change is

.* -*

• 10CFR50. 5*9 EVALUATIONS

'MONTH: -AUGUST 1993 (cont'd) ITEM lEC-3184 Pkg 1 lEC-3208 Pkg 1 -DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 SEPTEMBER 10, 1993 R. HELLER (609)339-2212 discrepancies in several documents and settings for the auto/start setpoints.

Service Water System setpoints and operating pressure band are not specifically listed in basis Section 2.0 or in the RPS or ESFAS section 3/4/3/1 and 3/4.3.2, therefore they do not have an analytical limit. The function of the setpoints is equipment protection while maintaining minimum flow. Calculations S-C-M600-MCD-1289 and S-C-SWOOl-01 demonstrated that the setpoints adequately perform their function.

There is no reduction in the margin of safety as defined in the basis of any Technical Specification. (SORC 93-076) "SBO Emergency Air Compressor" -A system designed to function as a backup to the Emergency Control Air Compressor during Station Blackout is to be installed.

This system consists of a diesel engine-driven air compressor and auxiliary equipment.

To meet the Control Air quality requirements, an air cooled aftercooler equipped with an air monitor driven fan, purification, filter and a heatless dryer will be included.

The air compressor will be permanently connected to the Control Air header. The system is designed to be self-contained, battery started, and would require manual action locally for starting following an SBO. No remote/automatic start and control capabilities from the control rooms are provided for this compressed air system. The proposed modification is being implemented in response to commitment to the NRC per NLR-N92031.

As this modification does not alter the operation of the existing system and introduces no new station operational scenarios or requirements, it is concluded that the proposed modification does not impact the Technical Specifications and does not reduce the margin of safety as defined in the Technical Specification bases. (SORC 93-076) "Salem Fire Damper Upgrade" -The design scope for this package includes the replacement of two fire dampers and an existing fire door/damper in the h .. e 10CFK50.59 EVALUATIONS

'MONTH: -AUGUST 19 9 3 (cont'd) ITEM B. Safety Evaluations S-C-DG-ESE-0820 e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 SEPTEMBER 10, 1993 R. HELLER (609)339-2212 Battery Room Exhaust System, a subsystem of the Control Area Ventilation (CAV) 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. This modification is intended to meet PSE&G's commitment to the NRC and comply with the requirements of 10CFR50, Appendix R. The basis for the Technical Specifications does not address the fire protection features or the Battery Room Exhaust System. Since replaced fire dampers and louvre associated with the system perform no safety related functions and are equivalent to or better than existing components, these modifications do not affect the system. Therefore, there is no reduction in the margin of safety as defined in the basis for the Technical Specifications. (SORC 93-081) "Diesel Generator Load Calculation Updates" -This change updates the documents impacted by the revised Salem Diesel Generator Load Calculation (ES-9.002) and confirms the adequacy of each of the Diesel Generators (D/G's). The documents impacted are the D/G CBD (DE-CBD.DG-0024(Q))

and the SAR section 8.3.1.5.1 and tables 8.3-2 and 8.3-3. This revision of calculation ES-9.002(Q) incorporates 11 DCPs that all have minor impact to the D/G loading. The D/G's ability to respond to the largest load (Service Water Pump, 1030 HP) being applied has been verified to be acceptable by special test during the Unit 1 10th refueling outage. Similarity between the Unit 1 and Unit 2 D/Gs is taken credit for to establish the capability of the Unit 2 D/Gs. This evaluation supports the conclusion that the D/Gs are capable of accepting the auto-connected loads and therefore does not reduce the margin of safety as defined in the basis of the Technical Specifications. (SORC 93-073) 10CFR50.S9 MONTH: -AUGUST 1993 (cont'd) DOCKE,NO:

UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 SEPTEMBER 10, 1993 R. HELLER (609)339-2212

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ITEM

SUMMARY

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w.o. 930807094

c. Temporary Modifications TMOD # 93-082 "Repair of Spool 1-SW-118 11 -Activities associated with the repair of spool l-SW-118 involve breaching a penetration seal (Penetration S-15511-012) in a Unit 1 Auxiliary Building barrier for the purpose of routing temporary commodities (that is, welding leads), installing a temporary penetration*

seal (that is, PSBP No. 309896) in the penetration, securing a watertight door (lDOOR-AUXCll-l)in an open position for the purpose of routing temporary commodities, breaching the temporary seal for the purpose of removing the temporary commodities, restoring the penetration seal to its design basis configuration and securing the watertight door in a closed position.

The breaching of the penetration seal impairs a fire protection feature and shall be performed in accordance with NC.NA-AP.ZZ-0025(Q) for planned impairments.

Activities pertaining to the penetration seal and the watertight door do not affect parameters such as, DNBR, fuel temperature, fuel enthalpy, clad strain, clad temperature, clad oxidation or containment pressure.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-074) "Installation of Threaded Cap in Place of 1 11 Valve 11ST60" -This safety evaluation is to document the installation of a threaded cap in place of 1 11 valve 11ST60, Service Water Vent Valve located on 11 TAC* Heat Exchanger.

The cap was installed immediately after 11ST60 had blown off the heat exchanger, in the turbine building.

The valve is part of PSE&G pipe specification S27D, classified non-nuclear, non-safety related seismic class III. Work Order #930803162 was written to remove the cap and have valve 11ST60 (Mark #R-5) reinstalled in its proper place at a later date. Only the Service Water Nuclear Headers are addressed by the Technical Specifications.

The change has no effect, either directly or

.* e 10CFR50.S9 EVALUATIONS MONTH: -AUGUST 1993 (cont'd) e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 SEPTEMBER 10, 1993 R. HELLER (609)339-2212

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ITEM TMOD # 93-066 TMOD # 93-077 TMOD # 93-90

SUMMARY

indirectly on the nuclear header. Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-073) "Control Air lA Header Jumper Installation Mechanical Penetration Area" -This T-Mod will be worked in conjunction with DCP lEC-3150.

lEC-3150 adds break flanges at 2 sections of pipe as follows: 1.) each side of the 11CA330 containment Isolation valve; 2.) a branch section of the lA .Header up-stream of the 11CA330 between manual valves 11CA424 and 11CA415. These lines pass through the stairway in the mechanical penetration area in Unit 1. The break flanges essentially make the two sections of the lA Header, including the 11CA330 valve, removable spools. 11CA330 is an automatic containment isolation valve. This temporary modification will be removed prior to returning to Mode 4. This proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-075) "Temporary Movement of Blowdown Analyzer Drains Receiver" -This temporary modification will remove from service the drain receiver 1BDE008 and relocate it south of the design location in the mechanical penetration area on elevation 78 1-0 11* The source of influent to the drain receiver its from the generator blowdown sample panel. The existing pipe class is 1S59E which is non nuclear, seismic class III, non safety related. This proposal does not reduce the margin of safety as defined in the basis for any Technical Specification.

There are no technical specifications applicable to the 1GBE008 Drain Receiver Tank or its function. (SORC 93-075) "Installation of a Temporary Battery Cell" -This TMOD will install a temporary C&D type LCR-33 Parallel Battery Cell on the floor next to lC-125 VDC Battery Rack; use jumper cables to connect it

, . e 10CFR50.59 EVALUATIONS

'MONTH: -AUGUST 1993 .(cont'd)

ITEM e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 SEPTEMBER 10, 1993 R. HELLER (609)339-2212 across Battery Cell# 47, and then electrically disconnect Battery Cell # 47 to allow lC-125 VDC to remain operable.

The parallel battery cell will be adequately supported to withstand a seismic event. This TMOD installs a parallel battery cell that: 1.) is equivalent to the existing lC-125 VDC battery design; 2.) is adequately supported to withstand a seismic event; 3.) will still maintain the lC Vital Bus loads for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of operation after a loss of AC power requirements; 4.) fails the same as any of the existing battery cells mounted in the battery rack to cause the loss of the lC-125 voe Battery. Therefore, this TMOD does not reduce the margin of safety as defined in the bases of the Technical Specifications. (SORC 93-078)

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

SUMMARY

-UNIT 1 AUGUST 1993 The Unit began the period operating at full power, and continued to operate at full power until August 19, 1993, when load was reduced for maintenance on 13A and 13B circulators.

The Unit was returned to full power on August 20, 1993. on August 24, 1993, a power reduction was initiated to comply with technical specification limitations due to a failed cell in the lC 125V battery bank. A discretionary enforcement was received from the NRC and the Unit was returned to full power later, the same day. The Unit continued to operate at full power throughout the remainder of the period.

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

1. Refueling information has changed from last month: YES X NO 50-272 SALEM 1 SEPTEMBER 10, 1993 R. HELLER (609)339-2212

2. Scheduled date for next refueling:

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

DECEMBER 13, 1993 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?:

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 680 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