ML18102A468
| ML18102A468 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/30/1996 |
| From: | Garchow D, Heller R Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9610220303 | |
| Download: ML18102A468 (8) | |
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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 October 14, 1996 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 September is being sent to you.
RH:vls Enclosures C
Mr. H. J. Miller Sincerely yours,
~~how General Manager -
Salem Operations Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046 9610220303 960930 PDR ADOCK 05000272 R
PDR The power is in your hands.
95-2168 REV. 6/94
e OPERATING DATA REPORT e Docket No:
50-272 I
Date:
10/10/96 Completed by:
Robert Phillips Telephone:
339-2735 Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period September 1996
- 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:..i-:A=-~~~~~~~~~~~~~~~~~~~~~-
- 9.
Power Level to Which Restricted, if any (Net MWe)
N/A
- 10. Reasons for Restrictions, if any ~~~~~~~-N=-1-=A=---~~~~~~~~~~
- 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
- 24. Shutdowns scheduled over next 6 Refueling extension.
This Month 720 0
0 0
0 0
0
-2777 0
0 0
0 100 months (type, Year to Date 6575 0
0 0
0 0
0
-21438 0
0 0
0 100 Cumulative 168792 104380.5 0
100388.3 0
318062229 105301000 100183475 59.5 59.5 53.7 53.2 25.0 date and duration of each)
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
Under review.
8-1-7.R2
AVE~ DAILY UNIT POWER LEVEL
~
Docket No.:
50-272 Unit Name:
Salem #1 Date:
10/10/96 Completed by:
Robert Phillips Telephone:
339-2735 Month September 1996 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
NO.
DATE 4092 9/01/96 F
1 2
F:
Forced S:
Scheduled DURATION TYPE1 (HOURS)
REASON 2 720 F C Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction 4
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH September 1996 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT #
HJ 3
Method:
1-Manual 2-Manual Scram SYSTEM CODE4 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 CODE 5 DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 Salem #1 10/10/96" Robert,Phil Lips 609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 2422 Nuclear Steam Generator Svstems.
4 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 - Same Source
l_
'IOCFR50.59 EVALUATIONS MONTH: SEPTEMBER 1996 DOCKET NO:
UNIT NAME:
50-272 SALEM I CONTACT:
TELEPHONE:
R. HELLER 609-339-5162 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.
I. Design Change Packages (DCP) lEC-3360, Pkg. 1 "Control Room Modifications" Rev.0 - This DCP is for Control Room and Work Control Center layout changes to improve these areas in accordance with established Human Factors Guidelines as documented in NUREG-0700. This modification improved the Operator's Ready Room habitability by including it within the Control Room isolation boundary. The human factor improvements enhance operator performance, operator efficiency, and facilitate the command and control capabilities of the Nuclear Shift Supervisors and the Senior Nuclear Shift Supervisor. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 96-038)
- 2. UFSAR Change Notices (SCN)
SCN 96-057 "Service Water System Flow Rates and Heat Loads" - This SCN revises UFSAR Section 9.2.1, including Table 9.2-1, so that the UFSAR correctly reflects the Service Water System design flows and heat loads associated with the equipment and components required for various plant operating modes. The acceptance criteria for postulated design basis accidents affected by the system define the acceptable margin of safety.
This change does not affect the acceptance criteria or design limits of the operable loop of the system or any other system.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-119)
'10CFR50.59 EVALUATIONS MONTH: SEPTEMBER 1996 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 R.HELLER 609-339-5162
- 2. Procedures and Revisions SC.FP-TI.FP-0002(Q)
CONTACT:
TELEPHONE:
"Fire Protection Equipment I Systems Contingency Plans" Rev. 0 - This new procedure contains steps to install jumpers to disable trouble alarm signals that are generated by the design
- of the system. These trouble indications affect the ability of the fire protection alarm circuits to function properly and prevent testing of the fire protection equipment within the established time period. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 96-129)
REFUELING INFORMATION MONTH: SEPTEMBER 1996 MONTH : SEPTEMBER 1996 DOCKET NO:
UNIT NAME:
CONTACT:
TELEPHONE:
50-272 SALEM 1 R. HELLER 609-339-5162 Refueling information has changed from last month: YES _. _. NO. X Scheduled date for next refueling: (to be determined)
Scheduled date for restart following refueling: (to be determined)
- 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 of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
0 989 1632 1632 October 2008
~. '
r SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 1 SEPTEMBER 1996 SALEM UNIT NO. 1 The Unit is in a refueling and Steam Generator replacement outage and remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the Unit 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 the Unit to operate in a safe, event free manner After the restart review, meet with the NRC and communicate the results of that review