ML18100A944
| ML18100A944 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/28/1994 |
| From: | HAGAN J J, MORRONI M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9403180075 | |
| Download: ML18100A944 (14) | |
Text
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station March 14, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 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 February 1994 are being sent to you. RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance lOCFRS0.59 Evaluations Safety Valve Actuations Operating Summary Refueling Information Sincerely yours, 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 9403180075
.940228 PDR ADDCK 050003i1 R PDR*
' <JP+/ I 95-2189 (10M) 12-89
DAILY UNIT POWER Docket No.: Unit Name: Date: Completed-by:
Mike Morroni Telephone:
Month February 1994 50-311 Salem #2 03-10-94 339-2122 Day Average Daily Power Level (MWe-NET)
Day Average Daily Power Level (MWe-NET) 1 487 17 1079 2 668 18 1076 3 1065 19 1084 4 0 20 938 5 0 21 486 6 42 22 1016 7 847 23 1048 8 1084 24 1096 9 1137 25 740 10 1136 26 905 11 1031 27 1086 12 1110 28 980 13 1103 29 14 1074 30 15 1074 31 16 1039 P. 8.1-7 Rl OPERATING DATA REPORT Docket No: 50-311 Date: 03/10/94 Completed by: Mike Morroni Telephone:
339-2122 Operating Status 1. Unit Name Salem No. 2 Notes 2. Reporting Period February:
1994 3. Licensed Thermal Power (MWt) 3411 4. Nameplate Rating (Gross MWe) 1170 5. Design Electrical Rating (Net MWe) 1115 6. Maximum Dependable Capacity(Gross MWe) 1149 7. Maximum Dependable Capacity (Net MWe) 1106 8. If Changes Occur in Capacity Ratings (items 3 through 7) *since Last Report, Give Reason NA 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
- 11. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) Gross Elec. Energy Generated (MWH) 18. Net Elec. Energy Gen. (MWH) .19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate 672 672 0 607.98 0 1848480 614560 585216 90.5 90.5 78.7 78.l 9.5 1416 108529 1339.03 70618.59 0 0 1255.25 68144.77 0 0 166228961.
8 1260680 71807198 1200078 68327355 88.6 62.8 88.6 62.8 76.6 56.9 76.0 56.5 11.4 22.5 24. Shutdowns scheduled over next 6 months (type, date and duration of each) NONE 25. If shutdown at end of Report Period, Estimated Date of startup: NA 8-1-7.R2 _ j NO. DATE 0005 01/29/94 0006 02/04/94 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 F 86.00 F 64.02 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction B A UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1994 METHOD OF SHUTTING DOWN REACTOR 3 LICENSE EVENT REPORT # -----------
3 Method: 1-Manual 2-Manual Scram SYSTEM CODE 4 CH HF E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
H-Other (Explain) 4 DOCKET NO.: 50-272 r UNIT NAME: Salem #2 DATE: 03-10-94 COMPLETED BY: Mike Morroni. TELEPHONE:
339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION CODE 5 TO PREVENT RECURRENCE PUMPXX FEEDWATER PUMP PUMPXX CIRCULATING WATER PUMPS Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -Same .. Source e SAFETX RELATED MAINTENANCE DOCKET I: 50-311 SALEM 2 MONTH: -FEBRUARY 1994 UNIT NAME: WO NO UNIT 931009019 2 931013157 2 931104069 2 940126194 2 DATE: COMPLETED BY: TELEPHONE:
MARCH 10, 1994 R. HELLER (609)339-5162 EQUIPMENT IDENTIFICATION "B" REACTOR TRIP BREAKER FAILURE DESCRIPTION:
REPLACE UNDERVOLTAGE TRIP DEVICE 21 AUXILIARY BUILDING SUPPLY FAN FAILURE DESCRIPTION:
REPLACE BREAKER NUCLEAR INSTRUMENTS FAILURE DESCRIPTION:
2N44B POWER RANGE DRAWER DEFECTIVE TESTS POTS -REWORK SERVICE WATER SPOOL 25SW25 FAILURE DESCRIPTION:
SPOOL MISSING BOLTING -REPLACE BOLTING --------------------------------------------------------------------------
940203062 2 RADIATION MONITOR 2R45 FAILURE DESCRIPTION:
2R45 CONTROL TERMINAL FAILED TO .PRINT -INVESTIGATE 10CFR50.59 EVALUATIONS MONTH:. -FEBRUARY 19 9 4 -DOCKET.: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
50-311 SALEM 2 MARCH 10, 1994 R. HELLER {609)339-5162
The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
The Station Operations Review Committee has reviewed and concl:lrs with these evaluations.
ITEM
SUMMARY
A. Design Change Packages 2EX-2136 Pkg 1 2EE-0019 Pkg 1 "Feedwater Flow Verification and Moisture Carry Over Test" -The purpose of this DCP is to install equipment to inject and monitor the transport of a tracer (lithium hydroxide) through each individual Unit 2 feedwater leg, steam generator, steam generator blowdown line and mainstream line. A datalogger will be temporarily connected into the P-250 to gather associated parameter values required to perform the flow calculations through the feedwater nozzles. All safety limits continued to be met. Also, plant protection systems or alarms are not impacted.
Containment isolation or radiological releases as evaluated in the SAR are not affected.
Integrity of RCS or feedwater/main steam systems are not impacted.
No equipment malfunctions are anticipated.
Plant leakage limits or its consequences are not impacted.
As such, there is no reduction in the margin of safety as described in the basis of the Technical Specifications. (SORC 94-010) "Installation of a Flowmeter for No. 23 Charging Pump Seal Water Tank Overflow Line" -This design change will install a turbine flowmeter and digital flow totalizer on the No. 23 charging pump packing seal tank over flow line (3/4"-WL1125).
Presently No. 23 charging pump packing seal leakage from the seal water tank is classified as unidentified leakage. The flowmeter to be installed in the seal tank over flow lines will be used to measure this leakage, therefore, pump seal leakage will be considered as identified leakage. This modification does not affect the function of the No. 23 charging pump system, only the seal tank system which is not addressed in the Technical Specifications.
Therefore, this modification does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-011) 10CFR5.0.59 EVALUATIONS MONTH: -FEBRUARY 1994 (cont'd) ITEM 2EC-3240 Pkg 1 2EC-3179 Pkg 1 2EC-3179 Pkg 6 e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
SUMMARY
50-311 SALEM 2 MARCH 10, 1994 R. HELLER {609)339-5162 "Installation of Secondary Chemistry Lab Readouts in the Control Room" -The purpose of this change is to monitor and alarm plant chemistry information in the Control Room from the existing Secondary Chemistry Lab, an RS422 data link will be installed between the Chemistry Department's Data Management System (DMS) computer {VAX 4000/300) and two (2) Speedomax 25000 Series recorders installed in the 2RP5 panel located in the Control Room. {This data link cable was partially installed from the VAX 4000/300 computer and left coiled in the Aux. Building hallway by DCP lEC-3274.)
The two recorders, associated alarms, cable and conduit installed by this DCP are non-safety related. The recorders will be mounted and qualified seismic category II/I in panel 2RP5, which is a seismically qualified class lE structure.
The parameters monitored by the software are neither safety related nor required for safe shutdown.
They are monitored as a means to prevent conditions which may result in premature system degradation.
The data for these parameters , .provided to the control room via the software, is also displayed locally at the subject analyzers.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-014) "Salem Fire Damper Upgrade" -The design scope for this package includes the replacement, relocation, and/or modification of existing fire dampers to the Unit 2's Auxiliary Building Ventilation (ABV) 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. The margin of safety is not reduced because we are enhancing the Fire Protection system to meet the criteria of 10CFR50 Appendix R. {SORC 94-016) "Salem Fire Damper Upgrade" -The design scope for this package includes the replacement, relocation and/or modification of existing fire dampers to the Unit 2 1 s Switchgear and Penetration Area Ventilation
{SPAV) System. The function, basic configuration 10CFR50.59 EVALUATIONS MONTH: -FEBRUARY 1994 (cont'd) e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
50-311 SALEM 2 MARCH 10, 1994 R. HELLER (609)339-5162
ITEM
SUMMARY
2EC-3187 Pkg 1 2EC-3186 Pkg 1 and operation of the system will not be altered and the codes, standards, qualification and design criteria of the original system will apply. The basis for the Technical Specifications does not address the fire protection features or the SPAV system. The replaced or modified dampers with the SPAV System perform no safety related functions.
The margin of is not reduced. (SORC 94-016} "SW Supply To Station Air Compressors" -The carbon steel cement lined service water piping (SPS-27D}
will be replaced with austenitic stainless steel 25% chromium-6%
molybdenum (SPS-27H}.
The change will take place in the Salem Unit 1 and 2 Turbine Building between 102 1-0 11 and 88 1-0 11* This package replaces the 6 inch service water cross-tie pipe between unit one and unit two which feeds the station air compressors in the Unit 1 turbine building.
The pipe between 2ST21 and 1ST21 will be replaced including 2ST21. The 1ST21 will remain in place as a tagged boundary.
The supply pipe will be replaced down to the discharge side of the domestic water backflow preventer.
The service water discharge from the compressor over to the unit 2 circulating water tie-in will be replaced beyond the crosstie isolation valve 1ST13. The Technical Specifications have no applicability to service water in the Turbine Building.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-016} "Downstream Service Water Piping To STOOl Valve" -The carbon steel cement lined service water piping (SPS-27D}
will be replaced with austenitic stainless steel 25% chromium-6%
molybdenum (SPS-27H} . The change will take place in the Salem Unit 2 Turbine Building elevation 88 1-0 11* The scope of the piping changeout consists of the eight, ten, twelve and fourteen inch pipe downstream of the 2ST26 and 2ST901 valves. The new piping will be the same as the existing configuration.
This modification will be installed during the Unit 2 8th refueling outage
EVALUATIONS MONTH: -FEBRUARY 1994 (cont'd) ITEM 2EC-3188 Pkg 1 2EC-3189 Pkg 2 e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
SUMMARY
50-311 SALEM 2 MARCH 10, 1994 R. HELLER (609)339-5162 as part of the Salem service water project system upgrade. The Technical Specifications have no applicability to service water in the Turbine Building.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-016) "SW From TAC HXs Piping Replacement" -The purpose of this change is to replace the carbon steel lined service water piping {SPS-27D) from the outlets of the Salem Unit 2 Turbine Auxiliary Cooling Heat Exchangers up to their associated outlet isolation valves with 6% molybdenum stainless steel {SPS-27H).
The modification is confined between elevations 100 1-0 11 and 88'-0" in the Salem Unit 2 Turbine Building.
The existing piping that is to be replaced is flanged at both ends to allow for disassembly and maintenance of the heat exchangers and associated outlet isolation valves. The new piping will be installed with flanged connections at both ends to allow for the same maintenance disassembly convenience.
The Technical Specification bases section was reviewed and 3/4.7.4 for Service Water Systems {SWS) was the only bases found to be related to the proposed modification.
- However, no specific margin of safety is defined there. The Salem Unit 2 Turbine Building Service Water System has no safety related functions.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
{SORC 94-018) "Permanent Backup Power -Salem 2 11 -The purpose of this change is to modify wire GE SB-1 selector switches into the control circuits for 11 & 12 Fuel Handling Exhaust Fans and No. 2 Battery Room Exhaust Fan. During 2R07 outage, Operations could support the functional testing of above 460 VAC and 230 VAC Systems. As a result, GE SB-1 selector switches could not be wired into the control circuits of these systems. This work {i.e., wiring of GE SB-1 selector switches and functional testing of 460 VAC and 230 VAC System) is removed out of DCP 10CFR50.59 EVALUATIONS MONTH: -FEBRUARY 1994 (cont'd) ITEM e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
SUMMARY
50-311 SALEM 2 MARCH 10, 1994 R. HELLER \:} (609)339-5162 2EC-3225 Pkg 1 2EC-3189 PKG #1. This package is generated to identify this remaining work. The modification will not involve any loads that may affect the reactor criticality or reactor coolant boron concentration.
Tying group busses 2F&2H with permanent connections with tie breakers at each end will increase operation flexibility.
The loads can be powered without individual alternate power sources. Therefore, this proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-018) "Boric Acid Concentration Reduction Modification" -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 This DCP will provide changed to instruments and components of the Boric Acid System that will incorporate the reduction of concentration of boric acid into the system design basis. Due to the reduction in Boric Acid concentration from 12% to approximately 3.75%, operational changes in the Boric Acid System are being made. Changing system parameters which will affect boric acid instrumentation include: (a) fluid density, (b) fluid operating temperature, (c) flow rate, (d) VCT pressure and (e) tank operating levels. Instrumentation associated with the boric acid system which is affected by this DCP will be replaced and/or recalibrated to compensate for the above parameter changes. Where necessary, new calculations have been performed to support any required changes. The implementation of this DCP will not reduce the margin of safety as defined in the basis of any Technical Specification.
Disconnection of the heat trace and reduction of the boric acid solution concentration in the BAT will not reduce the f lowpaths and borated water sources required by Technical specification.
The ability to keep the boric acid in solution and deliver the required quantity of borated water remains the same. (SORC 94-018) 10CFR50.59 EVALUATIONS MONTH: -FEBRUARY 1994 (cont'd) e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
50-311 SALEM 2 MARCH 10, 1994 R. HELLER (609)339-5162 ITEM 2EC-3191 Pkg 1 2EC-3129 Pkg 1
SUMMARY
"AFW Flow Reduction
-AFll and AF21 Modifications" -It is proposed to reduce the maximum auxiliary feedwater (AFW) flow rates, under certain plant conditions, delivered by the turbine-driven and motor-driven AFW pumps by modifying flow control valves 21 through 24AF11, and 21 through 24AF21. The proposed design change consists of replacing the existing valve trim with a reduced capacity trim (anti-cavitation design). Additionally, it is proposed to restore the handwheel locks, and stem and handwheel travel scales on AFll valves to their original configuration.
That is, the locks and travel scales installed during 2R7 will be replaced with the original valve vendor parts to keep the design identical among all AFlls and AF21s with respect to the handwheel locks (latches) and stem and handwheel travel scales. since the existing AFll and AF21 valves are oversized, installation of reduced capacity trim will assure the minimum flow delivery capability of the system under design basis conditions.
The flow rates to the steam generators will be maintained above the minimum required flow rates stated in the bases section. The acceptance criteria of the licensing basis accidents and transients will continue to be satisfied and the existing margins of safety will not be affected.
The excess safety margin will be increased for those design basis accidents which assume the maximum flow rates. The proposed modifications will not reduce the margin of safety as defined in the basis of the Technical Specifications. (SORC 94-018) "Service Water Piping Replacement" -:-This DCP will replace the carbon steel lined service water piping (SPS-27D) will be replaced with austenitic stainless steel steel 25% chromium-6%molybdenum (SPS-27H).
The change will take place in the Salem Unit 2 Turbine Building and confined to elevation 120 1-0 11* The proposed modifications will not reduce the margin of safety as defined in the basis of the Technical Specifications. (SORC 94-018) 10CFR50.59 EVALUATIONS MONTH: -FEBRUARY 1994 (cont'd) ITEM 2EC-3173 Pkg 1 e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
SUMMARY
50-311 SALEM 2 MARCH 10, 1994 R. HELLER {609)339-5162 "Replacement CS6 Valves" -DCP 2EC-3173 removes existing temporary spool pieces and installs new valves 21CS6 and 22CS6. Fabricate new "make-up" spool pieces to close gap between existing piping flanges and shorter standard length valves. The substitution of the spools with suitable valves does not reduce the margin of safety as defined in the basis of the Technical Specifications.
{SORC 94-018) B. Technical Specification Interpretations
{TSI) T/S #3.7.4 "Operable Service Water Loop" -The purpose of this package is to support revision of the Salem Operations Technical Specification Interpretation for an Operable Service Water Loop( {T/S Interpretation 3.7.4 for Salem Unit 2. The primary objectives of the revision are to update the interpretation(s) to more clearly address the requirements for Service Water Loop operability and to correct an inconsistency which currently exists between the interpretation for Salem Unit 2 when compared to that of Unit 1. The proposed revision is more complete in that prior versions of this interpretation have tended to focus on the acceptable combinations of pumps and power buses. The major changes to the revision are conservative enhancements that include specific identification of the acceptable combinations of pumps, valves, and piping which are required to provide operable Service Water loop(s). An additional change was made to remove a statement in regard to Technical Specification 3.0.5. The intent of this change is to eliminate confusion by permitting Technical Specification 3.0.5 to be the governing requirement.
This TSI provides guidance consistent with the basis of the Technical Specifications.
It does not alter the parameters of plant design or operation.
This revision does not reduce the margin of safety as defined in the basis for any Technical Specification.
{SORC.94-014)
SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
-UNIT 2 FEBRUARY 1994 The Unit began the period in a power escalation.
On February 3, 1994, the reactor achieved 100% power. On February 4, 1994, the Unit was taken off line due to grass and ice buildup on the circulating water intake screens. The Unit was resynchronized at 17:24 on February 6, 1994 and achieved 100% power at 22:27 on February 7, 1994. The Unit continued to operate at essentially full power until February 20, 1994, when load was reduced to replace filters on both steam generator feedwater pumps. Power was then increased to 100% on February 23, 1994. on February 25, 1994, power was reduced due to heavy grass conditions at the circulating water inlet area and problems with the travelling screen wash pumps. The repairs were completed and the reactor was returned to full power on February 26, 1994. With the exception of a load reduction to clean circulator waterboxes and screens, the Unit continued to operate at essentially full power throughout the remainder of the period.
REFUELING INFORMATION MONTH: -FEBRUARY 1994 MONTH FEBRUARY 1994 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
- 1. Refueling information has changed from last month: YES NO 50-311 SALEM 2 MARCH 10, 1994 R. HELLER (609)339-5162
- 2. Scheduled date for next refueling:
SEPTEMBER 24, 1994 3. Scheduled date for restart following refueling:
NOVEMBER 22, 1994 4. a) Will Technical Specification changes or other license amendments be required?:
YES NO NOT DETERMINED TO DATE X b) Has the reload fuel design been reviewed by the Station Operating Review Committee?:
YES NO If no, when is it scheduled?:
OCTOBER 94 5. Scheduled date(s) for submitting proposed licensing action: N/A 6. Important licensing considerations associated with refueling:
- 7. Number of Fuel Assemblies:
- a. Incore 193 b. In Spent Fuel Storage 492 8. Present licensed spent fuel storage capacity:
1170 Future spent fuel storage capacity:
1170 9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
March 2003 8-1-7.R4