ML18100A605
| 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) | |
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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.
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 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
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95-2189 (10M) 12-89
~ERAGE DAILY UNIT POWER L~L 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: 50-272 Date: 09/10/93 Completed by: Mark Shedlock Telephone: 339-2122 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) since Last Report, Give Reason NA 2
- 9. Power Level to Which Restricted, if any (Net MWe) N/A
- 10. Reasons for Restrictions, if any NA This Month Year to Date cumulative
- 12. Hours in Reporting Period 744 5831 141768
- 12. No. of Hrs. Rx. was Critical 744 5205.32 94387.3
- 13. Reactor Reserve Shutdown Hrs. 0 0 0
- 14. Hours Generator On-Line 744 5003.31 91143.72
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 2506725.6 16060850.4 288259458.8
- 17. Gross Elec. Energy Generated (MWH) 815430 5333250 95706240
- 18. Net Elec. Energy Gen. (MWH) 780935 5078693 91150352
- 19. Unit Service Factor 100 85.8 64.3
- 20. Unit Availability Factor 100 85.8 64.3
- 21. Unit Capacity Factor (using MDC Net) 94.9 78.8 58.1
- 22. Unit Capacity Factor (using DER Net) 94.1 78.l 57.7
- 23. Unit Forced Outage Rate 0 14.2 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
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH AUGUST 1993 DOCKET NO.: -'s"-'o".,--=27'-'2'""="_ __
l UNIT NAME: Salem #2 DATE: 09/10/93 COMPLETED BY: Mark Shedlock '.
NONE TELEPHONE: 339-2122 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE
-e 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 (NUREG-0161)
E-Operator Training & License Examination Previous outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)
SAFETY RELATED MAINTEN,CE DOCKETtlto: 50-272 MONTH: - AUGUST 1993 UNIT NAME: SALEM 1 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 WO NO UNIT EQUIPMENT IDENTIFICATION 930720123 1 FUEL HANDLING BLDG EXHAUST FAN FAILURE DESCRIPTION: REPLACE SHEAVE AND BELTS ON EXHAUST FAN 930811067 1 BREAKER 1CX1AX7X FAILURE DESCRIPTION: SPRING CHARGING MOTOR BURNED OUT
- REPLACE 930821097 1 lC 125V BATTERY FAILURE DESCRIPTION: BATTERY CELL 47 LOW ICV - REWORK
1--.
10CFR50.59 EVALUATIONS e DOCKET~O: 50-272 MONTH: - AUGUST 1993 UNIT NAME: SALEM 1 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (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 "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) lSC-2269 Pkg 7 "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 modifi-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
10CFR50.59 EVALUATIONS e DOCKEAO: 50-272 MONTH: - AUGUST 1993 UNIT NAME: SALEM 1 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)
ITEM
SUMMARY
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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) lEC-3251 Pkg 1 "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)
NC.NA-AP.ZZ-0008(Q) "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
10CFR50.59 EVALUATIONS e DOCKEAO: 50-272 MONTH: - AUGUST 1993 UNIT NAME: SALEM 1 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)
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ITEM
SUMMARY
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) lEE-0028 Pkg 1 "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) lEC-3285 Pkg 1 "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 DOCKET NO:
UNIT NAME:
DATE:
50-272 SALEM 1 SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)
ITEM
SUMMARY
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) lEC-3184 Pkg 1 "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) lEC-3208 Pkg 1 "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
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10CFK50.59 EVALUATIONS e e DOCKET NO: 50-272
'MONTH: - AUGUST 19 9 3 UNIT NAME: SALEM 1 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)
ITEM
SUMMARY
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)
B. Safety Evaluations S-C-DG-ESE-0820 "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 EVALUATIONS~
MONTH: - AUGUST 1993 DOCKE,NO:
UNIT NAME:
50-272 SALEM 1 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)
ITEM
SUMMARY
w.o. 930807094 "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)
- c. Temporary Modifications TMOD # 93-082 "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
10CFR50.S9 EVALUATIONS e e DOCKET NO: 50-272 MONTH: - AUGUST 1993 UNIT NAME: SALEM 1 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)
ITEM
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)
TMOD # 93-066 "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)
TMOD # 93-077 "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)
TMOD # 93-90 "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
10CFR50.59 EVALUATIONS e e DOCKET NO: 50-272
'MONTH: - AUGUST 1993 UNIT NAME: SALEM 1 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212
.(cont'd)
ITEM
SUMMARY
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 GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 1 AUGUST 1993 SALEM UNIT NO. 1 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.
REFUELING INFORMATION e e DOCKET NO: 50-272
.MONTH: - AUGUST 1993 UNIT NAME: SALEM 1 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 MONTH AUGUST 1993
- 1. Refueling information has changed from last month:
YES X NO ~~~-
- 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 ~=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 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