ML18096B340
| ML18096B340 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/28/1993 |
| From: | Fest J, Polizzi V, Shedlock M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9303170227 | |
| Download: ML18096B340 (14) | |
Text
PS~G*
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station March 12, 1993 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 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 Sincerely yours, rYo&oLJ--?
~eneral Manager -
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
/-- 9303i7022*t-93022a* ------ -\\
PDR ADOCK 05000311
~
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8-l-7.R2 AVERAGE DAILY UNIT POWER LEVEL Docket No.:
50-311 Unit Name:
Salem #2 Date:
3/10/93 Completed by:
Mark Shedlock Telephone:
339-2122 Month February 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET}
(MWe-NET}
1 0
17 1126 2
132 18 1126 3
561 19 1119 4
1065 20 1121 5
1104 21 1121 6
1129 22 1121 7
1122 23 1123 8
1122 24 1130 9
1123 25 1077 10 1131 26 1098 11 1106 27 1122 12 1131 28 1111 13 1131 29 14 1122 30 15 1132 31 16 1132 P. 8.1-7 Rl
. P> 8~1-7 Rl OPERATING DATA REPORT Docket No:
50-311 Date:
3/10/93 Completed by:
Mark Shedlock Telephone:
339-2122 Operating Status
- 1.
Unit Name Salem No. 2 Notes
- 2.
Reporting Period February 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
- 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)
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 672 672 0
642.63 0
2095737.6 715820 686409 95.6 95.6 92.4
- 91. 6 4.4 Year to Date Cumulative 1416 99769 1345.61 65111.21 0
0 1304.41 62862.87 0
0 4335669.6 149431359.4 1484910 66192398 1423774 63009750 92.1 63 92.1 63 90.9 57.1 90.2 56.6 7.9 22.6
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling outage scheduled to start 3-20-93 for approximately 74 da s.
- 25. If shutdown at end of Report Period, Estimated Date of startup:
NA
NO.
DATE 0009 01/28/93 F
0010 02/26/93 F
1 2
F:
Forced S:
Scheduled DURATION TYPE 1 (HOURS)
REASON2 111.58 10.92 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction A
B UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1993 METHOD OF SHUTTING DOWN REACTOR 2
5 LICENSE EVENT REPORT #
3 Method:
1-Manual 2-Manual Scram SYSTEM CODE4 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)
COMPONENT CODE5 DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE
-=-50=..,--=2"-7=-2 ~---~
Salem #2 03/10/93 Mark Shedlock -
339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE PUMP XX LOSS OF MAIN FEED PUMP PUMP XX STM UNITS THERMAL DISCHARGE LIMITS ENVIRON.
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 MAINTEN~E MONTH: -
F~BRUARY 1993 DOCKET.:
UNIT NAME:
50-311 SALEM 2 WO NO UNIT 921029184 1
921029185 1
930123047 1
930127059 1
930217149 1
DATE:
COMPLETED BY:
TELEPHONE:
MARCH 10, 1993 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION VALVE 2CV181 FAILURE DESCRIPTION:
SOLENOID VALVE AIR REGULATOR LEAKING -
REPAIR VALVE 2CV35 FAILURE DESCRIPTION:
SOLENOID VALVE AIR REGULATOR LEAKING -
REPAIR 21 COMPONENT COOLING HEAT EXCHANGER FAILURE DESCRIPTION:
21 CCHX FALSE INDICATION -
INVESTIGATE AND CORRECT RADIATION MONITORING FAILURE DESCRIPTION:
RMS ANNUNCIATOR TEST/LOCAL DOES NOT WORK -
INVESTIGATE VALVE 2SW307 FAILURE DESCRIPTION:
REPAIR LEAK IN UPSTREAM SPOOL
"10CFR50.59 EVALUATIONS.
MONTH: -
FEBRUARY 1993 DOCKET.O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 MARCH 10, 1993 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 2EC-3083 Pkg. 1 2EA-1026 Pkg. 1 "Phase II Chiller Condenser Service Water Pipe Replacement" - This DCP involves the replacement of 4 11 cement lined carbon steel service water piping with 6% molybdenum stainless steel.
This DCP is the second of two phases implemented for the 4 11 chiller condenser piping.
Phase I involved the replacement of all the 4 11 chiller condenser piping on elv. 100 1 in the mainsteam penetration area and chiller rooms.
This DCP is scheduled for implementation during the Salem Unit 2 7th Refueling Outage.
The scope of work entails the replacement of No. 21 & 22 4 11 chiller condenser s.w. headers from the 24 11 s.w.
nuclear headers located on el. 78' in the s.w. water valve rooms to a set of break flanges on el. 100 1 in the mainsteam penetration area.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-012)
"Unit #2 RCP Motor Bearing Temperature Alarm Setpoint Changes" -
Supplement No. 3 to the Safety Evaluation Report, NUREG-0517, approved lowering the RCP bearing temperature alarm to 175 F on Salem Unit
- 2.
In the presence of a loss of component cooling water flow alarm, the RCP motor bea~ing temperature alarm will signal the operator to immediately execute the pump trip procedure.
While reviewing station documents against NUREG-0517, System Engineering discovered drawings that were not in agreement with the NUREG; the drawings showed the RCP motor bearing temperature alarms as being 185 F instead of 175 F.
This change proposal will update drawings to agree with as-built conditions that are consistent with NUREG-0517.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-015)
- 1ocFR:50.59 EVALUATIONS.
MONTH: -
FEBRUARY 1993 DOCKET.O:
UNIT NAME:
50-311 SALEM 2 (cont'd)
ITEM 2SC-2163 Pkg. 1 2SC-2164 Pkg. 1 2EC-3205 Pkg. 1 DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
MARCH 10, 1993 J. FEST (609)339-2904 "Installation of Synchronizing Permissive Devices For No. 2 Unit Main Generator" - This change will provide a permissive to allow the operator to synchronize the Main Generator to the power grid.
The permissive will be enabled during a specific closing phase angle range, slip limit (F limit), and voltage range.
The permissive will be blocked when out of these specific ranges.
This change package will consist of (1) the modification of the Unit 2 Control Console to add a green light and keylock switch, (2) the modification to Relay rack 2R21 to add a syncrocloser check relay, test switch, and (3) the modifications to Relay Cabinets RC21-4 and RC23-4 to add two auxiliary relays each.
Four new cables will be required.
There is no reduction in the margin of safety as defined in the bases of the Technical Specifications.
(SORC 93-015)
"Installation of Synchronizing Permissive Devices for No. 2 Unit Emergency Diesel Generator -
2A" -
This change will provide a permissive to allow the operator to synchronize the Diesel Generator 2A with its associated vital bu,s.
The permissive will be enabled during a specific closing phase angle range, slip limit (F limit), and voltage range.
The permissive will be blocked when out of these specific range.
This change package will consist of the modification of the Design Generator Control Panel No. 2A to add a syncrocloser check relay, auxiliary relay, and green indicating light, remove the existing synch check relay and use the existing spare test switch in order to accomplish the above change.
The implementation of this design change will not reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-015)
"Modifications for Valve 2SJ135" -
The purpose of this change package is to replace the existing motor pinion gear, worm shaft gear and springpack in the motor operator for valve 2SJ135.
The valve is not specifically mentioned in the Technical
- 1ocFR50.59 EVALUATIONS e MONTH: -
FEBRUARY 1993 DOCKET.O:
UNIT NAME:
50-311 SALEM 2 (cont'd)
ITEM DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
MARCH 10, 1993 J. FEST (609)339-2904 Specifications.
The safety function to open has been previously assured by administratively controlling the valve in the locked open position in all modes of operation.
There is no reduction in the margin of safety as defined in the bases of the Technical Specifications.
(SORC 93-018) 2EC-3172 Pkgs. 1-3 "Diesel Generator Building Ventilation Upgrade" -
The purpose of this change is to entail modifications to the Unit 2 Diesel Generator Building Ventilation System, and consists of three (3) separately implementable packages.
Package No.
1 covers modifications to the No. 21 Diesel Generator Area ventilation, No. 21 Diesel Control Area ventilation, and the fuel oil storage area ventilation.
Package No. 2 covers modifications to the No. 22 Diesel Generator Area ventilation and the No. 22 Diesel Control Area ventilation.
Package No.
3 covers modifications to the No. 23 Diesel Generator Area ventilation and the No. 23 Diesel Control Area ventilation.
The operation of the Diesel Generator Area Ventilation system and the environmental space temperatures in the Diesel Generator Building are not addressed in the Technical Specifications.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-018)
B.
SAR Change Notice SAR CN # 92-58 "Moderate Energy Piping" -
DEF #DES-92-00590 identified that SGS-UFSAR Section 3.6.5.12.5 which applies only to Unit 2 indicates that the emergency diesel fuel oil transfer pump room contains no 'MEL (that is, moderate energy line) piping.
The section indicates that no modifications are required to provide protection for the effects of postulated moderate energy pipe failure.
SGS-UFSAR Section 3.1.3 identifies that the NRC required that a
1.0CFR50. 59 EVALUATIONS e MONTH: -
FEBRUARY 1993 DOCKET-:
UNIT NAME:
50-311 SALEM 2 (cont'd)
ITEM
- c.
Safety Evaluations DR SMD-93-018 DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
MARCH 10, 1993 J. FEST (609)339-2904 Moderate -
Energy Break Analysis (MEBA) be performed for Unit 2.
A MEBA inspection conducted in 1978 identified that there were no moderate energy lines in the area (that is, 21 fuel oil transfer pump room) and that no modifications were required in the area.
The text in SGS-UFSAR Section 3.6.5.12.5 with respect to the area is based on the inspection.
Section 4.9.1.B of DE-CB.DG-0024(Q), indicates that the maximum operating temperature of the transfer pump leg of the fuel oil system is ambient and that the maximum operating pressure is 74 psig.
Therefore, fuel oil piping associated with redundant 21 and 22 fuel oil transfer pumps is MEL piping.
It should be noted that a portion of SGS UFSAR Section 3.6.5.12.5 relating to the emergency diesel rooms fuel oil piping is identified as MEL piping.
Spray from fuel oil pipe cracks could affect fuel oil transfer pump motors.
However, 21 and 22 fuel oil transfer pumps are physically isolated from each other and local MEL failures in one room will not affect the redundant transfer pump room.
No modifications are required to provide protection for the effects of postulated a MEL pipe failure.
This proposal accordingly modifies SGS UFSAR Section 3.6.5.12.5 on the basis of the revised MEBA which is now identified as Design Calculation S-C-ZZ-SDC-1203.
This proposal only changes a document and does not involve work on the plant.
(SORC 93-012) 11 24 CFCU Performance Test Failure" -
The purpose of this Safety Evaluation is to justify the use of 24 Containment Fan Cooler Unit in its present operational condition (Q-rate = 65.1E6 vs. design =
81E6 Btu/hr at SW inlet temp of 90 degrees F.) with an additional operational restriction of 43 degrees F. imposed on the upper river water temp for continued fan cooler operation.
If river water temperature exceeds 43 degrees F, the CFCU will be declared inoperable and the Action Statement of Technical Specification 3.6.2.3 will be entered.
since the capability of 24 CFCU exceeds the design heat removal requirements while river water
- 1ocFR50. 59 EVALUATIONS e MONTH: -
FEBRUARY 1993 DOCKET.O:
UNIT NAME:
50-311 SALEM 2 DATE:
COMPLETED BY:
TELEPHONE:
(cont'd)
MARCH 10, 1993 J. FEST
{609)339-2904
~----------------------------------
ITEM DR SMD-93-021
SUMMARY
temperatures are less than 43 degrees F, the margin of safety as defined in the basis for the Technical Specification is not exceeded.
{SORC 93-017) 11 23 CFCU Performance Test Failure" -
The purpose of this Safety Evaluation is to justify the use of 23 Containment Fan Cooler Unit in its present operational condition {Q-rate = 70.1E6 vs. design=
81E6 Btu/hr at SW inlet temp of 90 degrees F.) with an additional operational restriction of 43 degrees F. imposed on the upper river water temp for continued fan cooler operation.
If river water temperature exceeds 43 degrees F, the CFCU will be declared inoperable and the Action Statement of Technical Specification 3.6.2.3 will be entered.
since the capability of 23 CFCU exceeds the design heat removal requirements while river water temperatures are less than 43 degrees F, the margin of safety as defined in the basis for the Technical Specification is not exceeded.
{SORC 93-018)
D.
Temporary Modifications T-Mod # 93-020 "Switchgear Penetration Area Ventilation" -
The proposed temporary modification enables replacement of the Salem Unit 2 Switchgear Penetration Area Ventilation System roll filters by modification DCP No. 2E0-2294 (see Attachment B).
The proposed temporary modification and DCP implementation will take place during Modes 5 and 6 and at night time (10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> out of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
This includes shutting down the switchgear penetration area supply and exhaust fans, adding temporary filters on the suction side of the supply fans.
In addition hourly area temperatures will be monitored during this temporary modification and as well as during implementation of DCP 2E0-2294.
This is to ensure area temperatures are maintained within the design limits as stated in the Modification Instructions.
The present operating procedure (II-16.3.2),
"Switchgear and Penetrations Areas Ventilation Operation", Section 2.2, states that the "Roll-0-Matic" filter selector switches must be in Auto position.
These selector switches will not be
iocFR50.59 EVALUATIONS MONTH: -
F~BRUARY 1993 (cont'd)
ITEM T-Mod # 93-021 DOCKET I:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-311 SALEM 2 MARCH 10, 1993 J. FEST (609)339-2904 in operation during this modification.
The temporary filters provided by this temp-mod provide equal filtration of the incoming air during the operation of this system (between shifts) when the system is put back into operation.
Therefore, it is concluded that the intent of this operating procedure is met.
The proposed temporary modification does not involve a change to the fire protection program or radioactive waste treatment systems.
The temporary filters do not perform any safety related function and do not affect any safety related system.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-018)
"Control Area Air-Conditioning System" -
The proposed temporary modification enables replacement of the Salem Unit 2 Control Area Air Conditioning (CACC) system roll filters by modification DCP No.
2E0-2292 (see Attachment B).
The proposed temporary modification and DCP work will take place during Modes 5 and 6 and at night time (10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> out of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
This includes shutting down the Unit 2 Emergency Air Conditioning System (EACS) to provide conditioned air to the Control Room Envelope (CRE)
- This temporary modification adds temporary filters on the suction side of the CAACS fans.
Subject roll filter assemblies (which include roll filters and bag filters) are located inside the CAACS filter enclosure.
In addition, hourly area temperatures will be monitored during this temporary modification as well as during the implementation of DCP 2E0-2292/
This is to insure that area temperatures are maintained within the design limits as stated in the Modification Instructions.
The present operating procedure (II-17.3.2), "Control Room Ventilation Operation", Section 2.4, states that the "Roll-0-Matic" filter selector switches must be in Auto position. It is also stated under "Precaution
" that "Do not operate the normal *supply fans without the prefilter (Roll-0-Matic) media installed".
In order to replace the roll filters and associated controls, these selector switches will not be operational during this modification.
The temporary filters provided by this temp-mod
'10CFR50. 59 EVALUATIONS.
MONTH: -
F~BRUARY 1993 DOCKET.O:
UNIT NAME:
50-311 SALEM 2 (cont'd)
ITEM J
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
MARCH 10, 1993 J. FEST (609)339-2904 provides equal (with respect to the existing roll filters) filtration of the incoming air during the operation of the CAAC system (when this system is put back into operation, between shifts) and therefore it is concluded that the intent of this operating procedure is met.
the proposed temporary modification does not involves a change to the fire protection program or radioactive waste treatment systems, not does it change any part of the CAACS and/or EACS.
The temporary filters do not perform any safety related function and do not affect any safety related system.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-018)
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 2 FEBRUARY 1993 SALEM UNIT NO. 2 The Unit began the period shutdown following a trip on January 28, 1993.
The Unit was returned to service on February 2, 1993 and achieved full power on February 4, 1993.
The Unit continued to operate at essentially full power throughout the remainder of the period.
- 'frEFT:JELING INFORMATION
- MONTH: -
FEBRUARY 1993 MONTH FEBRUARY 1993 DOCKET.O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES X
NO
- 2.
Scheduled date for next refueling:
MARCH 20, 1993 50-311 SALEM 2 MARCH 10, 1993 J. FEST (609)339-2904
- 3.
Scheduled date for restart following refueling:
JUNE 2. 1993
- 4.
a)
Will Technical Specification changes or other license amendments be required?:
YES NO x
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?: FEBRUARY 1993
- 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 464
- 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-l-7.R4