ML18101A393
| ML18101A393 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/30/1994 |
| From: | Hagan J, Heller R, Morroni M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9412200092 | |
| Download: ML18101A393 (9) | |
Text
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e PS~G Pu~lic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit December 13, 1994 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 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 November 1994 are being sent to you.
RH:vls Enclosures C
Mr. Thomas T. Martin Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions 10CFR50.59 Evaluations Operating Summary Refueling Information J. J. Hag General Manager -
Salem Operations Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 8-1-7.R4 9412200092 941130
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PDR ADOCK 05000311
~R PDR The power is in your hands.
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95-2168 REV. 6/9
AVERAGE DAILY UNIT POWER LEVEL Docket No.:
50-311 Unit Name:
Salem #2 Date:
12-10-94 Completed by:
Mike Morroni Telephone:
339-5142 Month November 1994 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 16 0
P. 8.1-7 Rl J
OPERATING DATA REPORT ~
Docket No:
Date:
Completed by:
Mike 1Morroni Telephone:
Operating Status
- 1.
Unit Name Salem No. 2 Notes
- 2.
Reporting Period November 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)
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 N/A This Month Year to Date
. 720 8016 0
6335.7 0
0 0
6078.4 0
0 0
18510844.8 0
5903490
-1699 5605085 0
75.8 0
75.8 0
63.2 0
62.7 0
10.1 50-311 12/10/94 339-5142 since Last N/A Cumulative 115129 75615.2 0
72967.9 0
180973784.3 76450008 72732362 63.4 63.4 57.1 56.7 21.8
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
We are presently in a maintenance and refueling outage.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
December 25 1994.
I
- Monthly number has been adjusted to reflect a revision of Augusts monthly number and an adjustment due to feed flow nozzle inaccuracies.
8-l-7.R2
NO.
DATE 1881 11-01-94 s
1 2
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH NOVEMBER 1994 DURATION TYPE1 (HOURS)
- REASON2 720 c
Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction METHOD OF SHUTTING DOWN REACTOR 4
E-Operator Training & License Examination F-Acininistrative G-Operational Error (Explain)
H-Other (Explain)
LICENSE EVENT SYSTEM REPORT #
CODE4 RC 3
- Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE5 DOCKET NO.
50-272 UNIT NAME Salem #2 DATE 12-10-94 COMPLETED BY Mike Morroni TELEPHONE: -'3=3=9.....;-5... 1...
4.,..2 __ _
CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE FUELXXX NORMAL REFUELING 4
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 - Same Source
IOCFR50.59 EVALUATIONS
. MONTH: NOVEMBER 1994 DOCKET NO:
UNIT NAME:
50-311 SALEM2 12/10/94 R.HELLER 609-339-5162 DATE:
COMPLETED BY:
TELEPHONE:
The following items were evaluated in accordance with the provisions of the Code of Federal Regulations IOCFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations.
- 1. Design Change Packages (DCP) 2EC-3327, Pkg. 1 2EC-3229, Pkg. 1 2EC-3215, Pkg. 1 NO. 21, 22, 23 and 24 Reactor Coolant Pump Thermal Barrier Pressure Tap Modification/CV251 and 252 Valve Elimination - The purpose of this DCP is to eliminate the leakage potential at each of the flange connections by deleting each of the high and low pressure tap root valves and associated flanges by cutting off the respective mating flanges on the pipe taps connected to the RCPs and welding pipe caps on the pipe ends. The modification represents only a minor configuration change to enhance the long term reliability of the subject pipe connections. There is no effect on the margin of safety as defined in the basis for any Technical Specification. (SORC 94-083)
Small Bore Piping Replacement - The purpose of this DCP is the replacement of safety related and non-safety related small bore piping (2 inch and smaller) for portions of various plant systems. In addition, a small quantity of non-safety related, 3" large bore piping is also slated for replacement. In general, the existing piping is schedule 40, A-106 carbon steel, which is being replaced with schedule 80, A-335, P22 chrome-moly. In certain areas, alternate piping materials such as 316 stainless steel will be installed for severe erosion/corrosion conditions. No details for either the small bore piping or the 3 inch feedwater heater piping are addressed in the Technical Specifications. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-083)
Replace Garret/SCI Emergency Lighting Inverters - Rev. 2
- This modification will upgrade the emergency lighting
10CFR50.59 EVALUATIONS
. MONTH: NOVEMBER 1994 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 12/10/94 R. HELLER 609-3 3 9-5162 system for Salem Generating Station Unit 2. This revision is being made to the 10CFR50.59 evaluation to update Table 8.3.6 in the SAR. This revision to the DCP is for a document change and does not alter any plant component or process. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 94-084) 2EC-3306, Pkg. 2 Steam Generator Narrow Range Low and Low Low Level
- Setpoint Change - The purpose of this DCP is to change the SG NR Level Low Setpoints from 25% to 10% and the corresponding allowable values from 24% to 9%. In addition, this DCP also changes the SN NR Level Low-Low
- setpoints from 16% to 9% and the corresponding allowable values from 14.8% to 8%. The proposed setpoint and allowable values continue to ensure that the assumptions in the safety analyses remain valid, with appropriate consideration of protection system channel uncertainties.
Therefore, there is no reduction in the margin of safety as defined in the bases for the Technical Specifications.
(SORC 94-085) 2EA-1044, Pkg. 1 Update Configuration Documents for As-Built Valve 2WG189 - This As-built DCP updates affected documentation to reflect the installation of a drain valve on the No. 2 Waste Gas (WG) compressor suction header (2" -
2WG1000). This 3/4"drain valve, currently tagged as 2WG104 and Mark No. M-181, provides low point drainage capability on the compressors' common header.
This valve is physically located immediately downstream of check valve 2WG6 on El. 64' of the Unit 2 Aux. Bldg. The as-built condition of the valve does not increase the risk of developing explosive mixture in the Waste Gas system, nor does it affect the monitoring of gaseous effluents. No system or equipment serving a safety function is affected by
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10CFR50.59 EVALUATIONS
. MONTH: NOVEMBER 1994 DOCKET NO:
UNIT NAME:
50-311 SALEM 2 12/10/94 DATE:
COMPLETED BY:
TELEPHONE:
R. HELLER 609-339-5162 this as-built condition. Therefore, the margin of safety as defined in the bases of the Technical Specifications, is not reduced. (SORC 94-090)
- 2.
Safety Evaluations (S/E)
DS2.8-0002 PR 941129111 NFS94-624 Safety Evaluation for Salem Unit 2 Cycle 9 Refueling and Operation in Mode 6 - This safety evaluation is for the reload and operation of Salem Unit 2 Cycle 9 in Mode 6. Operation of the Salem Unit 2 Cycle 9 reload core design for refueling and Mode 6 operation has been analyzed in accordance with approved Westinghouse reload methodology which takes into consideration the normal operating conditions as allowed in the Technical Specifications. Within the assumptions used in the safety evaluation and following established core loading guidelines, there is no reduction in the margin of safety as defined in the bases of the Technical Specifications. The Cycle 9 reload does not cause any of the existing acceptance limits to be exceeded. (SORC 94-088)
Re-energize SPT #2 and #4 With Only Backup Differential Relay Protection - The purpose of this evaluation is.to assess energizing #2 and #4 Station Power Transformers (SPTs) with only one set of Transformer Differential Relay Protection (backup) in service while the other set of Transformer Differential Relay Protection (primary) is being taken out of service for monitoring purposes. This approach does not affect the operability requirements of Technical Specifications 3/4.8 and 3/4.9, nor does it violate any Technical Specification requirements. By taking this approach, the reliability of #2 and #4 SPTs will be maintained while troubleshooting of the primary differential relay protection is completed. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-091)
REFUELING INFORMATION
. MONTH: NOVEMBER 1994 MONTH: NOVEMBER 1994 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1. Refueling information has changed from last month: YES X
- 2. Scheduled date for next refueling: October 14. 1994 NO
- 3. Scheduled date for restart following refueling: December 29. 1994 50-311 SALEM2 12/10/94 R.HELLER 609-339-5162
- 4. a. Will Technical Specification changes or other license amendments be required?
YES __x_ NO __
NOT DETERMINED TO DATE --
- b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES__A_NO If no, when is it scheduled?
- 5. Scheduled date(s) for submitting proposed licensing action: ---~NIA~--
- 6. Important licensing considerations associated with refueling:
- 7. Number of Fuel Assemblies:
- a. Incore
- b. In Spent Fuel Storage
- 8. Present licensed spent fuel storage capacity:
Future spent fuel storage capacity:
- 9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
8-l-7.R4 0
749 1632 1632 March 2012
- .1
.e SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 2 NOVEMBER 1994 SALEM UNIT NO. 2 The Unit remained shutdown throughout the entire period as the 2R8 Refueling Outage activities continued.
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