ML18100A421
| ML18100A421 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/31/1993 |
| From: | Heller R, Shedlock M, Vondra C Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9306220173 | |
| Download: ML18100A421 (11) | |
Text
.PS~G
- Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 June 14, 1993 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 May 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
~:i?!-
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
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9306220f73 PDR ADOCK R
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- (!Pl I { I 95-2189 (10M) 12-89
~ERAGE DAILY UNIT POWER LE~
Docket No.:
50-311 Unit Name:
Salem #2 Date:
6/10/93 Completed by:
Mark Shedlock Telephone:
339-2122 Month May 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
P. 8.1-7 Rl
OPERATING DATA REPORT Docket No:
Date:
Completed by:
Mark Shedlock Telephone:
Operating Status
- 1.
Unit Name Salem No. 2 Notes
- 2.
Reporting Period May 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
- 9.
Power Level to Which Restricted, if any (Net MWe)
- 10. Reasons for Restrictions, if any
- 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 NA This Month Year to Date 744 3623 0
1716.71 0
0 0
1675.51 0
0 0
5590744.8 0
1913950
-11855 1818767 0
46.2 0
46.2 0
45.4 0
45.0 0
7.5 50-311 6/10/93 339-2122 since Last N/A Cumulative 101976 65482.31 0
63233.97 0
150686434.6 66621438 63404743 62 62 56.2 55.8 22.5
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
NA
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
Unknown.
8-l-7.R2
NO.
DATE 0014 03-17-93 1
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MAY 1993 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM TYPE 1 (HOURS)
REASON 2 REACTOR REPORT #
CODE4 s
1811.90 c
4 zz 2
Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain) 3 Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther DOCKET NO.
50-272 Salem #2 UNIT NAME DATE COMPLETED BY TELEPHONE 06/10/93
~
COMPONENT CODE 5 Mark Shedlock 339-21Z2 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE zzzzzzzz NUCLEAR NORMAL REFUELING 4
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161) 5 Exhibit 1 - Same Source
SAFETY RELATED MAINTEN.CE MONTH: -
MAY 1993 DOCKEAO:
UNIT NAME:
50-311 SALEM 2 WO NO UNIT 870403044 2
870808043 2
870923078 2
870923172 2
920625077 2
920807169 2
920915365 2
930318115 2
930505136 2
DATE:
COMPLETED BY:
TELEPHONE:
JUNE 10, 1993 R. HELLER (609)339-2212 EQUIPMENT IDENTIFICATION VALVE 22BR9 FAILURE DESCRIPTION:
VALVE LEAKING -
REPLACE DIAPHRAGM AND "0 11 RING VALVE 22SJ202 FAILURE DESCRIPTION:
VALVE HAS PACKING LEAK -
REPLACE WITH CHESTERTON PACKING PRESSURIZER LEVEL CHANNEL 1 FAILURE DESCRIPTION:
CHANNEL 1 INDICATING LOW -
TROUBLESHOOT CONTROL ROD 1D2 FAILURE DESCRIPTION:
ROD 1D2 INDICATION OUT OF CALIBRATION -
CALIBRATE VALVE 2SJ135 FAILURE DESCRIPTION:
2SJ135 LEAKS TROUGH -
OPEN AND INSPECT, REPAIR AS NECESSARY 22 CHARGING PUMP FAILURE DESCRIPTION:
GEAR BOX NOISE AND VIBRATION -
CHANGEOUT 22 AUXILIARY FEEDWATER PUMP FAILURE DESCRIPTION:
REPLACE ROTATING ELEMENT VALVE 21MS10 FAILURE DESCRIPTION:
21 S/G MAIN ATMOSPHERIC RELIEF -
NO OPEN INDICATION -
REPAIR VALVE 2CC117 FAILURE DESCRIPTION:
VALVE FAILED VOTES D/P TEST -
OPEN & INSPECT
SAFETY RELATED MAINTEN.CE MONTH: -
MAY 1993 e
DOCKET NO:
UNIT NAME:
50-311 SALEM 2 (cont'd)
WO NO UNIT 930505144 2
930505155 2
930506105 2
VALVE 2CC136 DATE:
COMPLETED BY:
TELEPHONE:
JUNE 10, 1993 R. HELLER (609)339-2212 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:
VALVE FAILED VOTES D/P TEST -
OPEN & INSPECT VALVE 2CC187 FAILURE DESCRIPTION:
OPEN, INSPECT & REPAIR AS NECESSARY 2A DIESEL GENERATOR FAILURE DESCRIPTION:
OUTLET EXPANSION.JOINT DAMAGED -
REPLACE
10CFR50.59 EVALUATIONS MONTH: -
MAY 1993 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 JUNE 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 2EE-0016 Pkg 1 2EC-3216 Pkg 1 11 21 Component Cooling Heat Exchanger Modifications" The purpose of this modification is to install a 2 11 drain valve, 21SW241 in the 20 11 service water supply line to 21 Component Cooling Heat Exchanger (CCHX).
This valve was to be installed by DCP 2SC-2018, but was not available in time to support implementation of this DCP.
A blind flange was installed in place of this valve by MCR 2sc-201a-011, with the valve to be installed at a later date.
This valve is a flanged (bolt on) installation, with no welding or system modification of any kind required.
Implementation of this DCP will occur during refueling outage Modes 5 or 6 with 21 CCHX out of service.
The service water header will be taken out of service and drained down to allow installation of this valve.
All applicable Technical Specification requirements will be complied with.
This minor configuration change has no effect on the function or reliability of the service water system.
Therefore, this DCP does not reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-041)
"E/C Fitting Replacement" Rev. 2 -
The purpose of this DCP is to replace various pipe segments due to normal wear, resulting in pipe wall approaching code minimum thickness values.
This DCP replaces existing carbon steel fittings with 2 1/4% Cr -
1%
Mo materials, and, in some cases, heavier wall material.
The design requirements of the replaced piping material are not changed and the replacement piping material meets or exceeds the design requirements of the original material specifications.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-042)
e 10CFR50.59 EVALUATIONS MONTH: -
MAY 1993 (cont'd)
ITEM 2EC-3148 Pkg 1 B.
Safety Evaluations NFS93-259 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-311 SALEM 2 JUNE 10, 1993 R. HELLER (609)339-2212 "Replace Containment Isolation Valves" - This DCP replaces pressure regulator 2NT31 with a higher range regulator, modify high pressure nitrogen containment isolation valve 2NT32 internals, and modify control air containment isolation valves 21CA330, 22CA330 and high pressure nitrogen containment isolation valves 2NT34 to accept soft seats. All changes are confined to component and do not affect component function. They also remove the external control pressure connection on the 2NT31 nitrogen pressure regulator. Valve 1NT901 will be deleted and valve 2NT54 will be replaced with a higher pressure class valve.
There is no change in the function of the valves and the Technical Specification requirements will still be met.
Therefore the proposal does not reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-046)
"Salem Unit 2 Cycle 8 Reload Safety Evaluation for Operation in all Modes and NRC Notification" -
The safety evaluation for operation of Salem Unit 2 Cycle 8 in all modes have been completed and supersede the previous Cycle 8 safety evaluations covering only Mode 6 and Modes 5 & 4, which were presented and approved by SORC on April 22, 1993 and April 29, 1993 respectively.
Issues previously identified regarding Auxiliary Feedwater flow rates and Main steam Safety Valve blowdown have been addressed and resolved.
The affects that these issues have upon safety analysis inputs were quantified and provided to Westinghouse for incorporation into Cycle 8 safety analyses.
The attached safety analyses demonstrate the acceptability of Salem Unit 2 Cycle 8 operation with the current AFW system configuration (up through Mode 2) and with modifications in the AFW and the MSSVs in all Modes.
The margin of safety as defined in the Technical Specification bases is not
10CFR50.59 EVALUATIONS.
MONTH: -
MAY 1993 (cont'd)
ITEM DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-311 SALEM 2 JUNE 10, 1993 R. HELLER (609)339-2212 reduced.
The Cycle 8 core design meets all applicable design criteria and ensures that all pertinent licensing basis acceptance criteria are met.
(SORC 93-042)
C.
Temporary Modifications TMOD # 93-030 TMOD # 93-052 "Temporary Modification for lSC-2297 11 This TMOD installs pressure switches and gages for Unit 2 circulating water pump control, screen wash pressure alarms and to monitor circulating water bearing lube and screen wash header pressure.
This TMOD will provided for continued operation of the Unit 2 circulating water pump permissive circuits and the screen wash pump low header pressure alarm circuits. It will also provide for continued monitoring of the circulating water bearing lube screen wash header pressures.
This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
This modification increases the margin of safety since the new equipment will maintain the system in the normal operating condition during the installation of lSC-2297.
(SORC 93-041)
"Temporary Circulating Water Bus Tie disconnect Switch" -
The purpose of this modification is to install a disconnect switch to provide electrical isolation of Unit 1 and Unit 2 circulating Water Switchgear.
This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
This modification only installs a temporary disconnect switch to provide electrical isolation required during the installation of DCP lSC-2297.
(SORC 93-041)
SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 2 MAY 1993 The Unit remained shutdown throughout the entire period for the Seventh Refueling outage.
RRFUELING INFORMATION DOCKET NO:
MONTH: -
~y 1993 UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
MONTH MAY 1993
- 1.
Refueling information has changed from last month:
YES X
NO ~~~~
- 2.
Scheduled date for next refueling:
MARCH 20, 1993 50-311 SALEM 2 JUNE 10, 1993 R. HELLER (609)339-2212
- 3.
Scheduled date for restart following refueling: (to be determined)
- 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 x
NO 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 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 l