ML18096A351
| ML18096A351 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/31/1991 |
| From: | Fest J, Shedlock M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9111220195 | |
| Download: ML18096A351 (14) | |
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.*OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station November 14, 1991 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 October 1991 are being sent to you.
RH:pc cc:
Mr. Thomas T. Martin Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information s~ilf Salem Operations Regional Region I Administrator USNRC 631 Park Avenue King of Prussia, PA Enclosures 8-l-7.R4 19046
- r.G i 'f 95-2189 (10M)/ t_~9
.ERAGE DAILY UNIT POWER L~
Completed by:
Mark Shedlock Month October 1991 Day Average Daily Power Level (MWe-NET) 1 1058 2
1092 3
1069 4
1082 5
1063 6
1079 7
1082 8
1064 9
1083 10 1075 11 1087 12 1058 13 1099 14 874 15 1085 16 1078 P. 8.1-7 Rl Day Docket No.:
50-311 Unit Name:
Salem #2 Date:
11/10/91 Telephone:
339-2122 Average Daily Power Level (MWe-NET) 17 1084 18 781 19 0
20 25 21 534 22 1086 23 1049 24 1075 25 1071 26 1091 27 1077 28 1073 29 990 30 1086 31 1110
e OPERATING DATA REPORT
- Docket No:
50-311 Date:
11/10/91 Completed by:
Mark Shedlock Telephone:
339-2122 Operating Status
- 1.
Unit Name Salem No. 2 Notes
- 2.
Reporting Period October 1991
- 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.~~~N~A-=-~~~~~~~~~~~~~~~~~~~~~~~
- 9.
Power Level to Which Restricted, if any (Net MWe)
N/A
- 10. Reasons for Restrictions, if any ~~~~N"-+-=A=-~~~~~~~~~~~~~~
- 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)
- 17. Gross Elec. Energy Generated (MWH)
- 18. Net Elec. Energy Gen. (MWH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (using MDC Net)
- 22. Unit Capacity Factor (using DER Net)
- 23. Unit Forced Outage Rate This Month 745 745 0
698.1 0
2318373.6 756950 724109 93.7 93.7 87.9 87.2 6.3 Year to Date Cumulative 7296 88105 7056.6 58412.8 0
0 6985.4 56695.4 0
0 23428358.4 129421827.4 7767241 59499168 7447518 56655329 95.7 64.3 95.7 64.3 92.3 58.1 91.5 57.7
.7 22.1
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling outage scheduled to start 1-4-92 and last 75 days.
- 25. If shutdown at end of Report Period, Estimated Date of startup:
NA 8-1-7.R2
NO.
0072 0076 0077 1
DATE 10/14/91 10/18/91 10/28/91 2
F:
Forced S:
Scheduled DURATION TYPE1 (HOURS)
REASON2 F
14.2 A
F 46.9 A
F 7.6 H
Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH OCTOBER 1991 METHOD OF SHUTTING DOWN REACTOR 5
1 5
3 LICENSE EVENT REPORT #
Method:
1-Manual 2-Manual Scram SYSTEM CODE4 CH HH EB 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)
COMPONENT CODE5 DOCKET NO.:
~5~0_-~31~1 ___ _
UNIT NAME:
Salem #2 DATE:
11/10/91 COMPLETED BY:
Mark Shedlock*
TELEPHONE:
339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE INSTRU
- 21 S.G. FEED PUMP CONTROLS HTEXCH STEAM GEN. CHEMISTRY TRAN SF SOLAR MAGNETIC DISTURBANCES 4
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 - same Source
'SAFETY RELATED MAINTENANCE MONTH: -
OCTOBER 1991 DOCKET NO:
50-311 UNIT NAME:
SALEM 2 WO NO UNIT 900614136 2
910523152 2
910622073 2
910716156 2
910905133 2
910918167 2
910919122 2
910928099 2
911010116 2
DATE:
COMPLETED BY:
TELEPHONE:
NOVEMBER 10, 1991 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION 2N31 FAILURE DESCRIPTION:
2N31 FAULTY -
TROUBLESHOOT 21 CHILL WATER PUMP FAILURE DESCRIPTION:
21 CHILL WATER PUMP MECHANICAL SEAL LEAKING -
TROUBLESHOOT 22 CHILLER CONDENSER PUMP FAILURE DESCRIPTION:
22 CHILLER CONDENSER PUMP OIL LEAK -
REPAIR VALVE 24SW24 FAILURE DESCRIPTION:
24SW24 DIAPHRAGM LEAKING -
REPLACE DIAPHRAGM VALVE 21SW47 FAILURE DESCRIPTION:
VALVE 21SW47 FAILED X-RAY -
REPLACE SERVICE WATER PIPING FAILURE DESCRIPTION:
THROUGH WALL LEAK IN THE SW PIPING TO 21 CHARGING PUMP -
REPAIR SERVICE WATER PIPING FAILURE DESCRIPTION:
2S27C CHILLER CONDENSER SW SUPPLY AND RETURN PIPING PIN HOLE LEAKS REPLACE 25 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION:
25 CFCU FLOW IS LOW IN HIGH SPEED INVESTIGATE RMS MONITOR 2R12B FAILURE DESCRIPTION:
2R12B CONTAINMENT IODINE RADIATION MONITOR FAILED -
INVESTIGATE
~---------------
SAFE~1 RELATED MAINTENANCE
- MONTH: - *OCTOBER 1991 DOCKET NO:
50-311 UNIT NAME:
SALEM 2
{cont'd)
Wb NO UNIT 911011149 2
911021162 2
911022165 2
911024148 2
DATE; NOVEMBER 10,.1991 COMPLETED BY:
J. FEST.
TELEPHONE:
( 609) 339-2904 EQUIPMENT IDENTIFICATION CHARCOAL FILTER 2VHE304 FAILURE DESCRIPTION:
2VHE304 CHARCOAL FILTER WAS DELUGED -
REPLACE CONTAINMENT NOBLE GAS RADIATION MONITOR FAILURE DESCRIPTION:
2R12A NOBLE GAS RADIATION MONITOR ERRATIC -
INVESTIGATE RMS MONITOR 2R45 FAILURE DESCRIPTION:
2R45 CONTROL TERMINAL/NO RESPONSE INVESTIGATE SW SPOOL RD-2-SW-444 FAILURE DESCRIPTION:
SPOOL RD-2-SW-444 LEAKING -
REPAIR
10CFR50.59 EVALUATIONS MONTH: -*OCTOBER 1991 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 NOVEMBER 10, 1991 J. FEST (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 # 2SC-2166 PKG. 1 DCP # 2EC-3043 PKG. 1 "Service Water Pipe Replacement SWIS Bay # 2"
- This DCP involves changing out various sections of the existing Service Water (SW) piping and valves in the Salem Unit 2 Service Water Intake Structure, Bay No. 2, during a refueling outage.
The existing SW piping is primarily cement lined carbon steel with small sections of low alloy stainless steel and aluminum bronze.
This piping which is Nuclear Class 3, Seismic Class l, and Pipe Class 27C is being upgraded with 6% molybdenum stainless steel.
The new piping is also Nuclear Class 3, Seismic Class l, however, the new Pipe Class is 27F.
The safety related portions of this new piping is designed to ANSI B31.1 1967 and fabricated, erected and inspected per ANSI B31.7 1969.
It should be noted that these are the original construction codes as permitted under ASME SECTION XI -
RULES FOR PLANT REPLACEMENT.
The temporary conditions associated with the installation of this modification do not impact the ability of the SW system to perform its intended safety functions.
The permanent configuration does not affect the emergency operation of the SW system.
The SW system will function in the same manner as it did prior to these modifications, since this is a material upgrade and the configuration changes are minor.
The proposed modification does not reduce the margin of safety as defined in the basis for the Technical Specifications.
(SORC 91-101)
"Penetration Area 6% Moly Pipe Replacement" -
This DCP involves the replacement of 10" cement lined carbon steel Service Water (SW) pipe with 6% molybdenum stainless steel on elevation 78' in the mechanical piping penetration area.
iocFk50.59 EVALUATIONS
~ONTH: -*OCTOBER 1991 (Cont'd)
ITEM DCP # 2EC-3045 PKG. 1 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-311 SALEM 2 NOVEMBER 10, 1991 J. FEST (609)339-2904 The scope of work for this DCP entails the replacement of 10 containment fan coil unit SW supply and return lines from the first set of break flanges outside No. 21 and 23 SW valve rooms through the containment penetrations to the first set of break flanges inside containment.
There are a number of major configuration changes which have been incorporated into the new piping and hanger design package which will significantly reduce the material and installation costs while enhancing the system reliability, maintainability and operability.
The proposed modification will not increase the probability of an accident previously evaluated in the SAR.
The proposed modification fully meets the design, material and construction requirements applicable to the modified system.
The new piping material and its installation is designed to be equivalent or better than the pipe it replaces and will result in a significant reliability improvement.
( SORC 91-101)
"Service Water Pipe Replacements -
21-25 CFCUs"
- This DCP involves the replacement of the 10" cement lined carbon steel SW supply and return piping for fan coil units 21,22,23,24 & 25, below elevation 102, down to the break flanges at the penetrations inside containment, including all associated vents.
The purpose of this replacement is to significantly increase system reliability and service life.
Routing of the new piping is expected to be identical to the existing routing.
The configuration was not changed, therefore, the system will function identically to that currently installed.
Therefore, there is no increase in the probability of an accident previously evaluated in the SAR.
The proposed change also does not create the potential for an accident not previously evaluated.
There is no increase in the consequences of an accident previously evaluated in the SAR.
(SORC 91-101)
10CFR50.59 EVALUATIONS MONTH: -*OCTOBER 1991 (Cont'd)
ITEM
SUMMARY
DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 NOVEMBER 10, 1991 J. FEST (609)339-2904 DCP # 2EC-3040 Pkgs 1-2 "Boric Acid Transfer Pumps" -
These modifications propose to install a larger diameter shaft in the Boric Acid Transfer (BAT) pump.
A new frame adapter, frame foot, power end, stuffing box, and mechanical seal will be used to accommodate the new shaft.
The new stuffing box is designed with a tapered bore allowing increased circulation in the seal cavity which provides improved seal cooling.
Being that all hydraulic characteristics, manual and automatic controls, and pump to pipe connections will remain unchanged and overall pump integrity is improved with the new shaft, there are no unreviewed safety concerns pertaining to the completed pump upgrade.
(SORC 91-103)
DCP # 2EC-3073 Pkg. 2 "MSIV Internal Modifications" -
This change package consists of four different topics: 1)
Increase the diameter of the bore hole in the equalizing orifice within the steam cylinder piston from 1/16"(1.6mm) to.441"; 2) Modify structural platforms in the vicinity of the MSIVs to enable ease of removal required during MSIV maintenance; 3) Modify the pipe.whip restraints on the vent line off 23MS167 to enable ease of removal required during MSIV maintenance, and 4) Provide documentation to allow the use of three different OEM supplied materials for the MSIV discs.
The proposed changes do not create the possibility of an accident of a different type than any previously evaluated in the SAR.
The modifications will not require change to any previously analyzed accidents which credit steam line isolation capability and will not impose new transients on the facility.
The originally intended function of the pressure equalization orifice will be retained and as such the possibility of a different type of accident is not created.
The change in material of the MSIV discs will not alter the performance of the MSIV and will therefore not create the possibility of an accident of a different type other than previously evaluated in the SAR.
(SORC 91-106)
10CFRS0.59 EVALUATIONS MONTH: -*OCTOBER 1991 (Cont'd)
ITEM DCP # 2EC-3073 Pkg. 3 DCP # 2EC-3056 Pkg. 1 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-311 SALEM 2 NOVEMBER 10, 1991 J. FEST (609)339-2904 "MSIV Vent Valve Actuator Replacement" - This modification proposes to replace existing Fischer Type 657, Size 50 air actuators on MSIV vent valves (MS169 & MS171) with Fischer type 657, Size 60 actuators to improve seat leak tightness.
Since the new actuators are designed and operated in the same manner as the existing actuators, the consequences of a malfunction will not be any greater than those for the existing actuators.
The method and modes of operation for the vent valves and MSIVs will not be changed as a result of making these modifications.
Therefore, the possibility of an accident of a different type than any previously evaluated is not created.
(SORC 91-106)
"Phase III Annunciator Modifications" -
The purpose of this modification is to implement the corrective actions required to resolve 14 of the Human Engineering Discrepancies (HED) identified in the Salem Unit 2 Control Room.
The HEDs were generated during the Detailed Control Room Design Review (DCRDR) conducted in accordance with NRC NUREG-0700 requirements.
This modification is a replacement and an upgrade of the existing overhead annunciator system.
This modification does not affect any existing safety related system and has no effect on Class lE circuits.
There is no change to system performance, instrument setpoints, or any other operating parameter.
The modification enhances notification to the operator of abnormal conditions.
The modification does not increase the radiological consequences of any of the accidents evaluated in the SAR because the change does not: 1) prevent or degrade actions assumed in the SAR accident analysis; 2) alter any assumptions previously made in evaluating the radiological consequences of an accident described in the SAR, or 3) affect a fission product barrier.
( SORC 91-110)
10CFRS0.59 EVALUATIONS MONTH: -.OCTOBER 1991 (Cont'd)
Safety Evaluations WO 911023150 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-311 SALEM 2 NOVEMBER 10, 1991 J. FEST (609)339-2904 "Ammonia & Hydrazine Injection" -
The purpose of this design change is to provide a permanent addition path for injection of ammonia and hydrazine into the Condensate Polishing discharge line.
The existing ammonia path, which runs from valve 2CF103 to a common injection line for the two chemicals, (upstream of 2CF87) will be modified to connect to valve 2CN129.
The tie in to the common injection path will be capped.
This change will remove and supersede temporary modification STD 89-072.
The additional chemical injection path will enhance the ability of the Chemistry Department to maintain proper chemistry control while the Condensa~e Polishing system is in service, thereby improving the reliability and integrity of the Feed & Condensate system chemistry.
There is no change to the function of any system and the change is to a non-safety related system.
Therefore, there is no possibility of an accident or malfunction of a different type than that evaluated in the SAR being created.
(SORC 91-110)
"PSWR S-1587" -
This 10CFR50.59 Review and Safety Evaluation is issued to permit the breaching of a penetration seal in the barrier located between the Mechanical Penetration at the 100' elevation and the 100' elevation North-South Aisle of SGS Unit No. 2.
In order to breach this penetration, it is necessary to breach a contiguous zone barrier for a short period of time.
The time period will be governed by the time required to complete the work activity and may range, for example, from four to seven days in length.
If a postulated HELB were to occur during the time period the environmental effects on equipment in the Auxiliary Building at 100' elevation would not be significant due to many mitigating effects.
10CFRS0.59 EVALUATIONS MON~H: -*OCTOBER 1991 (Cont'd)
ITEM C.
Temporary Modifications TMR # 91-088 TMR # 91-089 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-311 SALEM 2 NOVEMBER 10, 1991 J. FEST (609)339-2904 Because of these mitigating effects, it is judged that a significant increase in temperature will not occur in the Auxiliary Building.
Therefore, operability of any 1E equipment in this area would not be affected by this postulated HELB.
(SORC 91-108)
"Temporary Power For No. 21 Station Power TransformerOutage (SPT)" -
"Temporary Power For No. 22 Station Power Transformer Outage (SPT)" -
The purpose of these modifications is to install temporary 460V and 230v electrical jumpers to supply power to necessary loads during 21 & 22 SPT outages.
The only accident having relevance to these TMRs is "Loss of Offsite Power to the Station Auxiliaries". A somewhat related event, Loss of Offsite Power as seen by the Vital Busses", occurred at the Salem plant during August 1986, due in part to unanalyzed increased electrical system loading.
These TMRs will not increase existing electrical system loading above already analyzed levels.
Therefore, the probability of causing a "Loss of Offsite Power as seen by the Vital Busses" event will not increase as a result of installing these TMRs.
The Reactor Coolant Pump (RCP) flow was not lost during the* above described "Loss of Offsite Power as seen by the Vital Busses" event.
If for some reason, this event could/did cause a loss of RCP flow, the existing "Loss of Offsite Power to the Station Auxiliaries" accident analysis demonstrates the reactor core to remain adequately cooled without RCP motors.
(SORC 91-108)
SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 2 OCTOBER 1991 The Unit began the period operating at full power and continued operating at full power until October 14, 1991, when power was reduced to 70% to investigate an instrumentation problem on 21 Steam Generator Feedwater Pump (SGFP).
The SGFP was returned to service and the Unit was restored to 100% power later the same day.
The Unit continued to operate at full power until October 18, 1991, when a shutdown was commenced to remove chlorides from a steam generator.
The Unit was restored to full power on October 21, and, with the exception of *a minor load reduction on October 28, 1991, due to a Solar Magnetic Disturbance, continued to operate at full power throughout the remainder of the period.
REFUELING INFORMATION MONTH:
!...... OCTOBER 1991 DOCKET NO:
50-311 UNIT NAME:
SALEM 2 DATE:
COMPLETED BY:
TELEPHONE:
NOVEMBER 10, 1991 J. FEST (609)339-2904 MONTH OCTOBER 1991
- 1.
Refueling information has changed from last month:
YES X
NO
- 2.
Scheduled date for next refueling:
- JANUARY 4, 1992
- 3.
Scheduled date for restart following refueling:
- MARCH 21, 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?:
December 1991
- 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 356
- 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
- - Refueling outage dates may be revised due to turbine generator failure.