ML18095A885
| ML18095A885 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1991 |
| From: | Orticelle A, Thomson F Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9104220275 | |
| Download: ML18095A885 (9) | |
Text
CPS~G*
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station April 15, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 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 March 1991 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
~y~
General 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 1:>11 (>4*22(>275 c, :I cr::**-=* 1 PDR ADOCK 6~656272 R
PDR 95-2189 (10M) 12-89
Month MARCH 1991 Day Average Daily (MWe-NET) 1 0
2 0
3 0
4 0
5 0
6 0
7 0
8 0
9 0
10 0
11 0
12 0
13 0
14 0
15 0
16 0
P. 8.1-7 Rl
~ERAGE DAILY UNIT POWER LE~
Power Level Docket No.
Unit Name Date Completed by Telephone 50-272 Salem #1 04-10-91 Art Orticelle 609-339-2122 Day Average Daily Power Level (MWe-NET) 17 0
18 0
19 0
20 0
21 0
22 0
23 0
24 0
25 0
26 0
27 0
28 0
29 0
30 0
31 0
e OPERATING DATA REPORT e Completed by:
Art Orticelle Operating Status Docket No:
Date:
Telephone:
50-272 04-10-91 609-339-2122
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period MARCH 1991
- 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~A=--~~~~~~~~~~~~~~~~~~~~~~~-
- 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. Reactor 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 Generated (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 744 0
0 0
0 0
0 (2377) 0 0
0 0
0 Year to Date 2160 950.2 0
949.5 0
3183019.2 1058820 1011088 44.0 44.0 42.3 42.0 0
Cumulative 120553 77913.7 0
75517.0 0
237245404.4 78771460 74979760 62.6 62.6 56.2 55.8 22.3
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
N/A
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
4/20/91 8-1-7.R2
UNIT SHUI'OOWN AND rowER REDUCTIONS OOCKEI' NO. : 50-272 REEDRI' IDNTII MARCH 1991 MEl'HOD OF SHUTI'ING DURATION OOWN NO.
DATE TYPE 1 (HOURS)
REASON z REACTOR 0010 02-09-91 s
1210.5 c
4 1
2 F: Forced Reason:
S: Scheduled A-Fquiµrent Failure (Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Qperator Training & License Examination F-Admi.nistrative G-Operational Error (Explain)
H--Other (Explain)
LICENSE EVENT SYSTEM REEDRI' #
ffiDE 4
'Cl 3
Method:
1-Manual 2-Manual Scram 3-Autanatic Scram 4-COntinuation of Previous outage 5-1.oad Reduction 9--0ther UNIT NAME:
Salem #1 DATE: 03-10-91 CDIPl.EI'ED BY: Art Orticelle TELEPHONE: 339-2122
<mroNENT CAUSE AND a>RRECTIVE ACTION a>DE 5
'IO PREVENT RECURRENCE
'l2Zl NUCIBAR NORMAL REruELING 4
5 Exhibit G *-- Instructions Exhibit 1 - Same for Preparation of Data Source Entry Sheets for Licensee Event Report (LER) File (NURID-0161)
SAFETY RELATED MAINTENANCE MONTH: -
MARCH 1991 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 WO NO UNIT DATE:
COMPLETED BY:
TELEPHONE:
APRIL 10, 1991 F. THOMSON (609)339-2904 EQUIPMENT IDENTIFICATION
~-----~--
901003066 1
901125007 1
901125008 1
901281891 1
910301223 1
910305162 1
910318141 1
910327104 1
12 SERVICE WATER PUMP FAILURE DESCRIPTION:
BEARING LUBE VALVE 12SW8 STUCK CLOSED -
REPLACE SW EXPANSION JOINTS FAILURE DESCRIPTION:
REPLACE SW EXPANSION JOINT FC-1-42 SW EXPANSION JOINTS FAILURE DESCRIPTION:
REPLACE SW EXPANSION JOINT FC-3-41 11 COMPONENT COOLING HEAT EXCHANGER FAILURE DESCRIPTION:
llCCHX STUDS AND NUTS DEFECTIVE -
REPLACE lB DIESEL FAILURE DESCRIPTION:
VARIOUS SMALL OIL AND JACKET WATER LEAKS -
REPAIR PENETRATION SEAL FAILURE DESCRIPTION:
PENETRATION SEAL FOR NUCLEAR INSTRUMENT CONDUIT D IN CHILLER ROOM DAMAGED -
REPAIR 11 STEAM GENERATOR FAILURE DESCRIPTION:
AUX. FEED INLET VALVE -
BROKEN AIR LINE -
REPAIR 1N31 NUCLEAR INSTRUMENTATION FAILURE DESCRIPTION:
1N31 SOURCE RANGE CHANNEL INDICATION ERRATIC -
TROUBLESHOOT
10CFR50.59 EVALUATIONS MONTH: -
MARCH 1991 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 APRIL 10, 1991 F. THOMSON (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 these evaluations and agrees with their conclusions that these items do not present Unreviewed Safety Questions (USQs).
ITEM A.
Design Change Packages 1PD-0143A Pkg. 11 lSC-2154 Pkg. 1 lEC-3083 Pkgs. 1 & 2
SUMMARY
"Main Steam Sample Line Process Connections" -
This DCP completes the installation of four (4)
Main Steam Sample lines to the Secondary Chemistry Laboratory.
This is accomplished by making the final tubing connection to the four (4) R46 Main Steam Radiation Monitor sample lines.
There will be no negative impact from the changes.
(SORC 91-019)
"Human Factors Control Room Enhancements" -
The purpose of this revision (Rev. 2) to the DCP is to update the associated Safety Evaluation for clarification.
Changes to pages 9 and 10 of the evaluation add several indicators and correct typographical errors.
Changes were made to page 11 of the evaluation to address human factors concerns regarding Dixon flow transmitters.
Changes to pages 12 and 16 were made to incorporate the technical standards.
There are no changes to the original conclusions in the safety evaluation.
(SORC 91-022)
"Chiller Condenser Service Water Isolation Valves" -
The purpose of these modifications is to install isolation valves in the service water supply and return piping for the chiller condensers near the tie-ins to the nuclear headers for Nos. 11 and 12.
This change will allow the chiller condenser piping to be isolated during nonoutages in order to allow for NDE work without having to isolate the nuclear headers.
Installation of these valves will provide redundancy with two sets of isolation valves in the flowpath.
(SORC 91-023)
J
- 10CFR50.59 EVALUATIONS MONTH: -
MARCH 1991 (Cont'd)
ITEM B.
Safety Evaluations (S/E)
DCP lEC-3057 Pkg. 2 NFU 91-145 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 APRIL 10, 1991 F. THOMSON (609)339-2904 The purpose of the revision to this Safety Evaluation (S/E) is to remove the specification of the size of the orifice.
The current plans call for increasing the size of the orifice to one slightly larger than the size specified in the S/E.
The increased size, however, is still well within the bounds of the existing analysis.
The increased orifice size represents a further fine tuning intended to optimize valve performance.
The actual orifice size is a design detail which is not appropriate for inclusion in a S/E.
(SORC 91-021)
"Salem Unit 1 Cycle 10 Redesign Loading Pattern a~d Mode 6 Safety Evaluation" -
During the Salem Unit 1 Cycle 9/10 refueling, 48 fresh Region 12 4-. 0 w/o assemblies containing 64 Integral Fuel Burnable Absorber (IFBA) pins will be inserted into the core.
During the refueling operations, four previously burned fuel assemblies scheduled to be used in the original Cycle 10 loading pattern were discovered to be damaged.
The scope of this evaluation is limited to Mode 6 for the redesign of the core.
A full evaluation covering all Modes will be provided prior to leaving Mode 6.
(SORC 91-023)
C.
Temporary Modifications (TMODs)
TMR 91-029 The purpose of this TMOD is to provide temporary power to No. 12 Fuel Handling Building (FHB)
Exhaust Fan, No. 1 Battery Room Exhaust Fan, No.
1 Radiation Monitor Containment Sample Pump and the Service Water Lighting Transformer during the "B" Bus outage.
The function and capability of the UFSAR described equipment will not be altered.
Electrical separation is adequate for Modes 5 & 6 due to their being no common failure mode introduced between channels "A" & "C" by the installation of the temporary jumpers.
(SORC 91-025)
)
n
- SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 MARCH 1991 SALEM UNIT NO. 1
-The Unit began the period shutdown for the 9th Refueling Outage.
Major outage activities included:
11 & 12 Charging Pump Full Flow Tes~s RCS Fill and Vent Containment Type "A" Leak Rate Testing Core Reload and Reactor Head Stud Tensioning Safety Injection Full Flow Testing ECCS Full Flow Testing Stearn Generator Eddy Current Testing Main Stearn Isolation Valve Overhaul
,.4 I
< t 61.
REFUELING INFORMATION MONTH: -
MARCH 1991 MONTH MARCH 1991 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES X
NO
- 2.
Scheduled date for next refueling:
APRIL 18, 1992 50-272 SALEM 1 APRIL 10, 1991 F. THOMSON (609)339-2904
- 3.
Scheduled date for restart following refueling:
JUNE 12, 1992
- 4.
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?:
- 5.
S~heduled 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 588
- 8.
Present licensed spent fuel storage capacity:
1170 Future spent fuel storage capacity:
1170
- 9.
Date of last refueling that can be discharged to ~he spent fuel pool assuming the present licensed capacity:
September 2001 8-1-7.R4