ML18101B187
| ML18101B187 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/30/1995 |
| From: | Heller R, Phillips R, Warren C Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9601230158 | |
| Download: ML18101B187 (9) | |
Text
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.PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 1 DOCKET NO: 50-272 December 14, 1995 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of:the monthly operating report for the month of November is being sent to you.
1 RH:vls Enclosures C
Mr. Thomas T. Martin fgely~
C.~
General Manager -
Salem Operations Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 8-l-7.R4 23004-1 9601230158 951230 PDR ADOCK 05000272 R
PDR The power is in your hands.
95*2168 REV. 6/94
AVERA~DAILY UNIT POWER LEVEL
-~
Docket No.:
50-272 Unit Name:
Salem #1 Date:
12/10/95 Completed by:
Robert Phillips Telephone:
339-2735 Month November 1995 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
OPERATING DATA REPORT.,.
Docket No:
Date:
Completed by:
Robert Phillips Telephone:
Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period November 1995
- 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
- 12. 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 720 0
0 0
0 0
0
-2002 0
0 0
0 0
NA Year to Date 8016 2660.9 0
2632.1 0
8010326.4 2689850 2525388 32.8 32.8 28.5 28.3 56.3 50-272 12/10/95 339-2735 since Last N/A Cumulative 161473 104380.5 0
100388.3 0
318062229.2 105301000 100207552 62.2 62.2 56.1 55.7 22.9
- 24. Shutdowns scheduled.over next 6 months (type, date and duration of each)
We are presently in a scheduled refueling outage.
- 25. If shutdown at end of Report Period, Estimated Date of startup:
Under review.
8-l-7.R2
NO.
DATE 3642 11-1-95 1
F:
Forced S:
Scheduled DURATION TYPE 1 (HOURS)
REASON 2 UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH November 1995 METHOD OF SHUTTING LICENSE DOWN EVENT SYSTEM REACTOR REPORT #
CODE4 s
720 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 COMPONENT CODE 5 DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 Salem #1 12/10/95 Robert Phillips 609-339-2735.
CAUSE AND CORRECTIVE ACTION TO PREVENT* RECURRENCE zzzzzz Refueling Outage 4
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161) 5 Exhibit 1 - Same Source
10CFR50.59 EVALUATIONS MONTH: NOVEMBER 1995 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 12/10/95 DATE:
COMPLETED BY:
TELEPHONE:
R. HELLER 609-339-5162 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)
The reporting ofDCP related IOCFR50.59 evaluations is being modified to address these items only after they have been implemented and turned over to Operations. For the next several months, during this transition phase, we anticipate few new DCPs to report.
- 2. Procedures SGS/HCGS Security Plan "Salem - Hope Creek Security Plan" Rev. 5 - The following changes are being made by this revision: Plan Section:
Paragraph 1.1, pages 1-3 Management organization and title changes, reflecting the re-organization of the PSE&G Nuclear Business Unit. Plan Section: Paragraph 2.2, page 7 Change specifies that station personnel such as Emergency Duty Officer and Senior Nuclear Shift Supervisors, who have security responsibilities under the Security Contingency Plan receive training appropriate to their duties through participation in Security drills and Emergency Preparedness drills and exercises having Security involvement. Plan Section: Chapter 9, page 33 Deletes the requirement to post primary reactor containments during outages and major maintenance in accordance with the Final Rule change to IOCFR73.55(d)(8),
published in the Federal Register, Volume 60, No. 173, dated 9/5/95. These changes involve no plant equipment and do not reduce the security effectiveness of the Security Plan. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-129)
NC.NA-AP.ZZ-0024(Q)
"Radiation Protection Program" Rev. 5 - This is a major revision of the procedure which consolidates the following procedures into one procedure: 1) NC.NA-AP.ZZ-0007(Q)
Rev. 2 - ALARA Program; 2) NC.NA-AP.ZZ-0024(Q) Rev. 4
10CFR50.59 EVALUATIONS MONTH: NOVEMBER 1995 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 12/10/95 R.HELLER 609-339-5162 (Cont'd)
DATE:
COMPLETED BY:
TELEPHONE:
- Radiation Protection Program, and 3) NC.NA-AP.ZZ-0029(Q) Rev. 2 - Radioactive Material Control Program. This revision implements a commitment in letter NLR N94202 to the NRC, Reply to Notice of Violation, Inspection Report 50-354/94-20, Section F. Re-examination of Root Cause Investigation, Corrective Action 1, "The existing requirements contained in upper tier radiation protection related administrative procedures will be consolidated into one procedure, and the remaining procedure will be strengthened with additional guidance (on removal and release of contaminated equipment from the RCA)." These changes do not relate to design criteria, specifications, operation of the fuel cladding, RCS boundary, or containment, and do not address any margin of safety as described in Section B3/4.0. Therefore, the proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 95-135)
TMOD95-061 "Temporary Isolation of Fuel Handling Building Exhaust Fan (1VHE21) - No. 12 Fuel Handling Building Exhaust Fan" Rev.
0 - This TMOD will install blanks near the inlet and discharge of the 12 FHB exhaust fan. These blanks will allow for the partial operation of the system during removal of the 12 FHB exhaust fan for corrective maintenance. The blanks will be removed following completion of the corrective maintenance on 12 FHB. Installation of these blanks allows the remaining portion of the FHB ventilation system to provide the temperature and humidity control for the FHB and the routing of exhaust effiuents for various interfacing systems (Waste Gas, Containment Pressure Relief, etc.) through the systems HEP A and charcoal filters in the event of high radiation. These blanks will ensure the system effiuents will be vented to the outside and not inadvertently discharged to the 100' elevation of the Auxiliary Building. The FHB can still be maintained under a negative pressure with one FHB exhaust fan isolated. Technical Specification Section 3/4.9. q requires that whenever
10CFR50.59 EVALUATIONS MONTH: NOVEMBER 1995 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 12/10/95 TMOD95-042 DATE:
COMPLETED BY:
TELEPHONE:
R. HELLER 609-339-5162 irradiated fuel is in the storage pool, the fuel handling area ventilation system shall be operable. The basis of this is to ensure that all of the radiological material released during a fuel handling accident will be filtered through the HEP A and charcoal adsorber prior to release. In the event that the ventilation system is not operable all operations involving movement of fuel within the storage pool or crane operation with loads over the pool shall be suspended until the ventilation is restored. There is no reduction in the margin of safety as defined in the basis for any Technical Specifications. All effluent from the FHB will continue to be filtered through the filter trains via the 1 lFH exhaust fan and associated flow path.
(SORC 95-132)
"Heater Drains Iron Sampling Modification" Rev. 0 - The TMOD being installed off the 13HD91 root valve is to sample heater drains for iron particle entrainment. It will consist of a second isolation valve, pressure reducing valve, heat exchanger, and sampling device. The effects from this TMOD on the Heater Drain, Fresh Water, Chemical Waste or Building Drain System will be minimal. This modification is in accordance with PSE&G pipe specs and will meet the pressure and temperature limitations of the system. A second isolation valve will be installed to improve modification isolation. There is no reduction in the margin of safety as defined in the basis for any Technical Specifications. (SORC 95-138)
REFUELING INFORMATION MONTH: NOVEMBER 1995 MONTH : NOVEMBER 1995 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 12/10/95 R. HELLER 609-339-5162 Refueling information has changed from last month: YES ~* -~* NO.
X Scheduled date for next refueling: 09/10/95 Scheduled date for restart following refueling: 2nd quarter 1996
- 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? (to be determined)
Scheduled date(s) for submitting proposed licensing action:.
n/a Important licensing considerations associated with refueling:
Number of Fuel Assemblies:
- a. Incore
- b. In Spent Fuel Storage Present licensed spent fuel storage capacity:
Future spent fuel storage capacity:
Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
8-1-7.R4 0
1005 1632 1632 September 2008
~
C'..,,
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 1 NOVEMBER 1995 SALEM UNIT NO. 1 The Unit is in a refueling outage and remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, both Units will remain shutdown pending completion of the following actions:
Appropriately address long standing equipment reliability and operability issues After the work is completed, conduct a restart readiness review to determine for ourselves the ability of each Unit to operate in a safe, event free manner o
After the restart review, meet with the NRC and communicate the results of that review