ML18095A809
| ML18095A809 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/28/1991 |
| From: | Orticelle A, Thomson F Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9103250385 | |
| Download: ML18095A809 (13) | |
Text
.. 'C PS~G
- Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station March 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 February 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 Sincerely yours, 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 95-2189 (10M) 12-89
(.
OPERATING DATA REPORT Docket No:
50-272 Date:
3/10/91 Completed by:
Art Orticelle Telephone:
339-2122 Operating status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period February 1991
- 3.
Licensed Thermal Power (MWt) 3411
- 4.
Nameplate Rating (Gross MWe) 1170
- 5.
Design Electrical Rating (Net MWe)
~
- 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)
- 10. Reasons for Restrictions, if any ~~~~~~~N"'"'"""'A""-~~~~~~~~~~--
- 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)
- 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 672 206.2 0
205.5 0
644136 211110 198355 30.6 30.6 26.7 26.5 0
Year to Date 1416 950.2 0
949.5 0
3183019.2 1058820 1013465 67.1 67.1 64.7 64.2 0
Cumulative 119809 77913.7 0
77517 0
237245404.4 78771460 74982137 64.7 64.7 56.6 56.1 21.8
- 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:
04/10/91 8-1-7.R2
Completed by:
Art Month February Day Average Daily
{MWe-NET) 1 1107 2
1107 3
1110 4
1038 5
1081 6
1107 7
991
(
8 824 9
39 10 0
11 0
12 0
13 0
14 0
15 0
16 0
(
P. 8.1-7 Rl
.ERAGE DAILY UNIT POWER LE..
Orticelle 1991 Power Level Docket No.:
50-272 Unit Name:
Salem #1 Date:
3/10/91 Telephone:
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 30 31
NO.
DATE 0009 02/06/91 0010 02/09/91 1
F:
Forced S:
Scheduled DURATION TYPE 1 (HOURS)
REASON 2 s
24.5 s
466.5 2
Reason A-Equipment Failure (explain)
B-Maintenance or Test C*Refueling D*Requlatory Restriction c
c UNIT SHUTDO\\JN AND PO; EDUCTIONS REPORT MONTH FE;....,ARY 1991 METHOD OF SHUTTING DO\\IN REACTOR 5
1 LICENSE EVENT REPORT #
3 Method:
1-Manual 2-Manual Scram SYSTEM COOE4 RC zz E*Operator Training & License Examination F-Aaninistrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther
- G-Operational Error (Explain)
H*Other (Explain) 4 DOCKET NO.:
~~ d11 UN IT NAME: _S __ a...,l-em~#""1:----
DATE:
3/10/91 COMPLETED BY:
Art Orticelle TELEPHONE:
339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION COOE6 TO PREVENT RECURRENCE zzzzzz Core Coastdown Nuclear zzzzzz Nuclear Normal RefuelinQ Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161)
I 5
Exhibit
- Same Source
SAFETY RELATED MAINTENANCE MONTH: -
FEBRUARY 1991 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 WO NO UNIT 900321142 1
901210195 1
901211087 1
910214092 1
891006135 1
DATE:
COMPLETED BY:
TELEPHONE:
MARCH 10, 1991 F. THOMSON (609)339-2904 EQUIPMENT IDENTIFICATION 13 SERVICE WATER PUMP FAILURE DESCRIPTION:
PUMP FAILED SURVEILLANCE -
PULL AND INSTALL SPARE PUMP DETECTOR 1N31 FAILURE DESCRIPTION:
REPLACE NUCLEAR INSTRUMENTATION SOURCE RANGE CABLES DETECTOR 1N35 FAILURE DESCRIPTION:
REPLACE NUCLEAR INSTRUMENTATION INTERMEDIATE RANGE CABLES POLAR CRANE FAILURE DESCRIPTION:
TROUBLESHOOT MAIN.HOIST TROLLEY AND REWORK 2P-22SWH-42 FAILURE DESCRIPTION:
SPRING CAN HANGER BROKEN -
REPLACE
10CFR50.59 EVALUATIONS MONTH: -
FEBRUARY 1991 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 MARCH 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 lEC-3057 Pkg 2 lEC-3057 Pkg 3 lEC-3055 Pkg 1
SUMMARY
"MSIV Minor Internal Modifications" -
The purpose of this design change is to improve condensate removal from steam driven fast actuators for Unit 1 MSIVs (MS167 valves) by: a) increasing the through hole diameter at the bottom of condensate tube; b) increasing the diameter of the pressure equalization orifice.
These modifications are similar to those performed at D.C. Cook generating Station.
There will be no negative impact from the changes.
(SORC 91-011)
"MS169/MS171 Air Actuator Replacement" -
This DCP involves increasing the size of the air diaphragm actuators for Salem Unit 1 MSIV vent valves (MS169 & MS171 valves).
This DCP covers removal of existing actuators, installation of new actuators on the vent valves, and documentation of all changes.
The larger vent valve actuators will increase the valve seating force, thereby reducing seat leakage, which in turn will help ensure that the MSIVs will meet their Technical Specification fast closure time requirements.
(SORC 91-011)
"NIS Console Rear Panel Door Extension" -
This DCP adds a new door to the rear access panel of the Nuclear Instrumentation System (NIS) console to provide additional depth for enclosing cables which presently protrude beyond the existing panel envelope.
The purpose of this modification is to avoid potentially adverse interaction between the normally open doors and the protruding cables.
Installation.
of the new rear door extends the cabinet envelope and reduces the potential for an inadvertent reactor trip due to the sensitivity of the NIS equipment.
(SORC 91-015)
10CFR50.59 EVALUATIONS MONTH: -
FEBRUARY 1991 (Cont'd}
ITEM lSC-2269 Pkg 8 B.
Procedures and Revisions Sl.OP-PM.CC-OOll(Q}
Sl.OP-PM.CC-0012(Q}
VSl.RE-FR.ZZ-OOOl(Q}
OP-V-1.3.2 OP-V-1.3.3 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 MARCH 10, 1991 F. THOMSON (609)339-2904 "Electrical Distribution System Upgrade" -
Two new 13KV/4.16KV transformers have been set on new transformer pads located near the southwest corner of the switchyard.
Both transformers will be oil filled, grounded and tested prior to energization.
The transformers will not be energized in this pa6kage.
This package is part of the Salem Electrical Distribution system upgrade project which will enhance the 500KV switchyard by improving voltage recovery on the vital busses; increasing load growth capacity on the group buses; providing the capacity to serve the existing and new 13KV switchgear.
(SORC 91-015}
"Component Cooling Heat Exchanger High Flow Flush" - These are new procedures which were developed to meet the intent of NRC Guideline 89-13.
These procedures provide the instruction necessary to collect pressure drop data across the service Water side of the Component Cooling Heat Exchangers so that the relationship between flow and pressure drop can be trended.
(SORC 91-011}
"Westinghouse Refueling Procedure FP-PSE-R9" -
This procedure details refueling equipment checkouts, full core unload/reload, control rod drive shaft latching/unlatching, insert charigeouts and core mapping.
The procedure includes QA hold points in accordance with the QA program requirements.
(SORC 91-012}
"Service Water System -
11 Nuclear Header Outage" Rev. 1 "Service Water System -
12 Nuclear Header Outage" Rev. 1 -
These revisions to the procedures incorporate various steps and cautions that exist in the Loss of RHR and RCS Draindown procedures to enable the plant to respond to the Loss of RHR in a more efficient manner.
In addition, a new Checkoff Sheet and Table for the review of Service Water Header jobs during Single Service Water Header Operation were also added to the procedures.
(SORC 91-14}
10CFR50.59 EVALUATIONS MONTH: -
FEBRUARY 1991 (Cont'd)
ITEM OPS. PROC. II-1.3.6 Sl.SS-IS.ZZ-1
- c.
Safety Evaluations (S/E)
NFU 102 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 MARCH 10, 1991 F. THOMSON (609)339-2904 "Draining the Reactor Coolant System" Unit 1, Rev. 11" -
This revision to the procedure revised the time delay from shutdown to reduced inventory operation with various size hot leg openings and with or without cold leg side openings and operable Steam Generators.
These changes are being incorporated to implement the Salem-specific Engineering Standard Analysis (PSE 90-557).
Other, minor improvements have also been made to the procedure.
(SORC 91-014)
"Leak Rate Testing" LR 1 - This Limited Revision (LR) will give instructions to I&C personnel to be able to jumper out the LO PZR LVL/CHARGING Pp RUNNING/2CV2 & 2CV277 open permissive on CV-3 &
- 5.
This will allow these valves to be controlled from the Control Room.
Requirements to C&T close lCV-2 & lCV-277 have also been added.
The CV-4 jumper has already been added to the procedure under an ACN.
These jumpers are required to allow draining for leak rate testing.
Nitrogen will be used to clear the path and thereby reduce oscillations in metering.
(SORC 91-017)
."Salem Unit 1 Cycle 10 Reload Safety Evaluation and NRC Notification" - This S/E presents an evaluation for Salem Unit 1, Cycle 10, which demonstrates that the conditions described in Section 1.3 for the core reload will not adversely affect the safety of the plant.
This evaluation was accomplished utilizing the methodology described in WCAP-9273-NP-A, "Westinghouse Reload Safety Evaluation Methodology".
The evaluation takes a number 6f factors into accounti including: operations with the Boron Injection Tank removed; up to 10%
Steam Generator tube plugging, and operation with and without thimble plugs.
(SORC 91-018)
10CFR50.59 EVALUATIONS MONTH: -
FEBRUARY 1991 (Cont'd)
ITEM SAR Change # 91-03 SAR Change # 91-04 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 MARCH 10, 1991 F. THOMSON (609)339-2904 "Refueling Procedure - Units 1&2" - This SAR change will change Section 9.1.4.1.3 (Refueling Procedure) to reflect the way refuelings are performed.
The change will delete Step 16 in the preparation section and Step 7 in the reactor reassembly section, which deals with raising and lowering the Reactor Head with the cavity flooded.
This change will also delete steps 16 & 20 in the reassembly section which deal with hydrostatic test and preoperational testing.
The sequence of the steps have been changed to reflect the order in which the operations are performed.
(SORC 91-012)
"Tables 8.3-2 and 8.3-3" - Replacement of No. 12 Service Water Pump became necessary when the existing unit failed to meet the pressure/flow acceptance criteria of its routine in service inspection procedure (SP(0)4.0.5-P-SW).
It was determined by initial review of the manufacturer's supplied data, that there was a potential for its replacement pump to deliver more mechanical horsepower than the unit being replaced, thus drawing more electrical power, and calling to question the associated Diesel Generator loading, as documented in the FSAR.
Additionally required to be documented, are the necessary design analyses for the acceptability of all electrical distribution components associated with this component change out.
Considerations addressed included motor impact, cable impact, and diesel loading impact.
(SORC 91-010)
10CFR50.59 EVALUATIONS MONTH: -
FEBRUARY 1991 (Cont'd)
ITEM
SUMMARY
DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 MARCH 10, 1991 F. THOMSON (609)339-2904 D.
Temporary Modifications (TMODs)
TMR 91-001 TMR 91-002 TMR 91-003 Electrical modifications are required to supply temporary power to the Turbine Area Weld Stress Relieving, MET Tower, Turbine Building, Service Building, Cafeteria Power Panels, TRIS Computer A/C, and Service Building HVAC Fan during No. 11 Station Power Transformer outage.
Load monitoring and load shedding have been included in the package to prevent electrical system problems.
The breaker positions will be controlled administratively in accordance with the package instructions. Periodic load monitoring will be used to ensure there is no overloading of a bus.
(SORC 91-010)
Electrical modifications are required to supply temporary power to the Heating Boiler 460/230V Control Center, Turbine Crane, Turbine Area Welding Outlets, and Administration Building plus Cafeteria Ventilation 230V Control Center during No. 12 Station Power.Transformer outage.
Load monitoring and load shedding have been included in the package to prevent electrical system problems.
The breaker positions will be controlled administratively in accordance with the package instructions. Periodic load monitoring will be used to ensure there is no overloading of a bus.
(SORC 91-010)
Electrical modifications are required to supply
-temporary power to No. 11 Fuel Handling Building Exhaust Fan, lRPA Status Panel, and Radiation Monitor R41A,B,C Pump during the "A" Bus outage.
The jumpers for the Fuel Handling Building exhaust fans will be installed in conduit for seismic concerns.
In all cases, electrical separation criteria will be met.
The jumpers which will not be in conduit have all been reviewed by the PAG Group and are found to be acceptable.
The same overcurrent breaker protection will be maintained and load monitoring will be performed to ensure the capacity of the battery charger is not overloaded.
(SORC 91-010)
10CFR50.59 EVALUATIONS MONTH: -
FEBRUARY 1991 (Cont'd)
ITEM TMR 91-004 TMR 91-009 TMR 91-016 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 MARCH 10, 1991 F. THOMSON (609)339-2904 Electrical modifications are required to supply temporary power to No. 12 Fuel Handling Building Exhaust Fan, No. 1 Battery Room Exhaust Fan, No.
1 Radiation Monitoring Containment Sample Pump, and Service Water Lighting during the "B" Bus outage.
The jumpers for the Fuel Handling Building exhaust fans will be installed in conduit for seismic concerns.
In all cases, electrical separation criteria will be met.
The jumpers which will not be in conduit have all been reviewed by the PAG Group and are found to be a6ceptable.
The same overcurrent breaker protection will be maintained and load monitoring will be performed to ensure the capacity of the battery charger is not overloaded.
(SORC 91-010)
The purpose of this modification is to allow refueling test cables to be run through a modified electrical penetration during Modes 5 &
6, and during Mode 6 while fuel movement is in progress.
This modification meets the modified containment integrity requirements in the Technical Specifications.
Prior to Mode 4 the penetration will be restored and tested.
(SORC 91-011)
The purpose of this modification is to provide a temporary pump to be used when draining 11 & 12 Service Water Headers during the refueling outage while the applicable header is tagged out of service for* maintenance.
An air operated diaphragm pump will be located in the yard area and a suction line will be lowered through a manhole in to the Service Water Valve Room on the 78' elevation in the Unit 1 Auxiliary Building.
The suction hose will be connected to drain valve 1SW693 via a hose connection.
(SORC 91-013)
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 FEBRUARY 1991 The Unit began the period operating at full power and continued to operate at essentially full power until February 9, 1991, when the Unit was taken off line for the 9th Refueling Outage.
Major outage activities included:
Removal of the Reactor Head and Upper Internals Core unload Extensive Reactor Coolant Pump and motor inspections Diesel Generator overhauls Service Water piping replacement Main Turbine/Generator inspections.
Steam Generator U-Bend heat treatment and plug removal
~
v REFUELING INFORMATION MONTH: -
FEBRUARY 1991 MONTH FEBRUARY 1991 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES X
NO 50-272 SALEM 1 MARCH 10; 1991 F. THOMSON (609)339-2904
- 2.
Scheduled date for next refueling:
February 9, 1991
- 3.
Scheduled date for restart following refueling:
April 10, 1991
- 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 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 6f Fuel Assemblies:
- a.
Incore 0
- b.
In Spent Fuel Storage 781
- 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:
September 2001 8-1-7.R4