ML18096A836
| ML18096A836 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/30/1992 |
| From: | Fest J, Shedlock M, Vondra C Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9207200338 | |
| Download: ML18096A836 (16) | |
Text
'I e
PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station July 14, 1992 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 June 1992 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 cc:
Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures*
8-1-7.R4
__ Ihe_EIJ_e_r_qy _peqi:>le 9207200338 920630 PDR ADOCK 05000272 R
PDR 95-2189 (10M) 12-89
AVERAGE DAILY UNIT POWER LEVEL Docket No.:
50-272 Unit Name:
Salem #1 Date:
07/10/92 Completed by:
Mark Shedlock Telephone:
339-2122 Month June 1992 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 R1
OPERATING DATA REPORT Docket No:
50-272 Date:
07/10/92 Completed by:
Mark Shedlock Telephone:
339-2122 Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period June 1992
- 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 NA
- 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. 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
-3331 0
0 0
0 100 Year to Date 4367 2256.2 0
2117.8 0
7203120.0 2416240 2305872 48.5 48.5 47.7 47.4 8.1 Cumulative 131520 85856.4 0
83165.7 0
262700265.2*
87220870 83082445
. 63. 2 63.2 57.1 56.7 21.0
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
We are presently in a forced maintenance outage.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
July 28.1992 8-l-7.R2
NO.
DATE 0016 06/01/92 s
0017 06/29/92 F
1 2
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JUNE 1992 DURATION TYPE1 (HOURS)
REASON2 672.0 c
48.0 B
Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction METHOD OF SHUTTING DOWN REACTOR 4
4 E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
LICENSE EVENT SYSTEM REPORT #
CODE4 RC 3
CH Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE6 DOCKET NO.: -'5=0=--=2n'-=----
UNIT NAME:
Salem #1 DATE:
07/10/92 COMPLETED BY:
Mark Shedlock TELEPHONE:
339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE FUELXX NUCLEAR NORMAL REFUELING PIPEXX STEAM GEN. PIPING REPAIRS 4
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161) 5 Exhibit 1 - Same Source
SAFETY RELATED MAINTENANCE
. MONTH: -
JUNE 1992 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 WO NO UNIT 890429014 1
890429016 1
910320151 1
910718114 1
910724130 1
911118119 1
911226077 1
920123168 1
920201007 1
920218126 1
DATE:
COMPLETED BY:
TELEPHONE:
JULY 10, 1992 J. FEST (609)339.;...2904 EQUIPMENT IDENTIFICATION lB REACTOR TRIP BYPASS BREAKER FAILURE DESCRIPTION:
REPLACE THE UNDERVOLTAGE TRIP DEVICE lA REACTOR TRIP BYPASS BREAKER FAILURE DESCRIPTION:
REPLACE THE UNDERVOLTAGE TRIP DEVICE FLUX THIMBLES FAILURE DESCRIPTION:
REPLACE 6 UNIT 1 FLUX THIMBLES VALVE 11SW40 FAILURE DESCRIPTION:
VALVE HAS NO CLOSED INDICATION -
TROUBLESHOOT VALVE 16SW15 FAILURE DESCRIPTION:
VALVE IS LEAKING THOUGH, INSPECT AND REPAIR SOLENOID VALVE 1SV263 FAILURE DESCRIPTION:
VALVE 1SV263 HAS LEAKING TUBING -
REWORK VALVE 1SW175 FAILURE DESCRIPTION:
VALVE 1SW175 HAS NO CLOSED INDICATION -
INVESTIGATE SPOOL RD-1-SW-112 FAILURE DESCRIPTION:
SPOOL RD-1-SW-112 UT EXAMINATION UNSAT -
FABRICATE AND INSTALL REPLACEMENT SPOOL VALVE 1PR15 FAILURE DESCRIPTION:
1PR15 -
REPLACE DIAPHRAGM VALVE 1PR2 FAILURE DESCRIPTION:
1PR2/PZR PORV -
REPLACE COVER PLATE AND DIAPHRAGM
- e SAFETY RELATED MAINTENANCE MONTH: -
JUNE 1992 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 (cont'd)
WO NO UNIT 920405078 1
920415158 1
920420109 1
920421149 1
920424091 1
920504115 1
920511088 1
920511098 1
920511099 1
SPOOL 1-SW-P-1108 DATE:
COMPLETED BY:
TELEPHONE:
JULY 10, 1992 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:
SPOOL 1-SW-P-1108 HAS A THROUGH WALL LEAK -
REPAIR VALVE 1SS49 FAILURE DESCRIPTION:
VALVE 12249 FAILED LEAK RATE TEST
~ OPEN, INSPECT AND REPAIR CRDM CABLES FAILURE DESCRIPTION:
UNIT 1 CRDM CABLE PROBLEMS FOUND DURING REACTOR DISASSEMBLY -
REPAIR VALVE 1CV4 FAILURE DESCRIPTION:
VALVE 1CV4 FAILED LRT/STROKE -
TROUBLESHOOT 13 SWITCHGEAR RM SUPPLY FAN FAILURE DESCRIPTION:
13 SWITCHGEAR ROOM SUPPLY FAN STARTS -
WON'T STOP -
INVESTIGATE VALVE 11SW21 FAILURE DESCRIPTION:
VALVE 11SW21 HAS NO CLOSED INDICATION -
TROUBLESHOOT VALVE 1SJ68 FAILURE DESCRIPTION:
1SJ68 GREASE UNSAT -
REFURBISH OPERATOR VALVE 1SJ40 FAILURE DESCRIPTION:
11SJ40 GREASE UNSAT -
REFURBISH OPERATOR VALVE 11RH29 FAILURE DESCRIPTION:
11RH9 GREASE UNSAT -
REFURBISH OPERATOR
SAFETY RELATED MAINTENANCE MONTH: -
JUNE 1992 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 DATE:
COMPLETED BY:
(cont'd)
TELEPHONE:
JULY 10, 1992 J. FEST (609)339-2904
~-----------------------------~------------------------
WO NO UNIT 920522157 1
920525016 1
920530125 1
920607088 1
920610098
- 1 920611212 1
920613059 1
920615207 1
920617158 1
EQUIPMENT IDENTIFICATION 1 AUX ANNUNCIATOR FAILURE DESCRIPTION:
1 AUX ANNUNCIATOR DID NOT ALARM -
TROUBLESHOOT & REWORK lA REACTOR TRIP BREAKER FAILURE DESCRIPTION:
REPLACE THE UNDERVOLTAGE TRIP DEVICE lA D/G OUTPUT BREAKER FAILURE DESCRIPTION:
lA D/G OUTPUT BREAKER SPRINGS NOT CHARGING -
TROUBLESHOOT VALVE 1CV277 FAILURE DESCRIPTION:
1CV277 BLOWN DIAPHRAGM -
REPAIR 13 CHARGING PUMP FAILURE DESCRIPTION:
13 CHARGING SUCTION STABILIZER BLADDER LEAKS -
REPLACE VALVE 1CV41 FAILURE DESCRIPTION:
SIMULTANEOUS OPEN & CLOSED LIGHTS WITH VALVE IN CLOSED POSITION -
INVESTIGATE VALVE 1PR6 FAILURE DESCRIPTION:
INSPECT AND TROUBLESHOOT THE 1PR6 OPERATOR VALVE 1CC131 FAILURE DESCRIPTION:
VALVE 1CC131 HAS YOKE MOVEMENT -
REWORK AS REQUIRED VALVE 13SW72 FAILURE DESCRIPTION:
13SW72 JAMMED -
OPEN, INSPECT &
REPAIR
~----------------------------------------
SAFETY RELATED MAINTENANCE MONTH: -
JUNE 1992 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 (cont'd)
WO NO UNIT 920618108 1
920620085 1
920625090 1
920627058 1
920006026 1
DATE:
COMPLETED BY:
TELEPHONE:
JULY 10, 1992 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION VALVE 1SS64 FAILURE DESCRIPTION:
1SS64 HAS NO OPEN INDICATION -
INVESTIGATE & REPAIR VALVE 12CV104 FAILURE DESCRIPTION:
12CV104 WILL NOT OPEN -
INVESTIGATE 12 CHILLER COMPRESSOR FAILURE DESCRIPTION:
12 CHILLER COMPRESSOR WILL NOT START -
TROUBLESHOOT & REPAIR VALVE 1CC18 FAILURE DESCRIPTION:
VALVE 1CC18 FAILED STROKE TIME -
INVESTIGATE VALVE 1PR7 CABLES FAILURE DESCRIPTION:
REPLACE 1PR7 CONTROL AND POWER CABLES
10CFR50~59 EVALUATIONS
. MONTH: -
JUNE 1992 DOCKET NO:
.UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 JULY 10, 1992 J. FEST (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 and concurs with these evaluations.
ITEM
SUMMARY
A.
Design Change Packages (DCP)
DCP# lEC-3138 Pkg. 1 "Radwaste Panel Upgrade" - This DCP will provide for revitalization upgrades to Rad Waste Panel 104 and related equipment on elevations 84' and 64' of the Auxiliary Building.
The upgrades will consist of the following: a) replacement of the obsolete instrumentation, b) physical repair of Panel 104, c) provision of new labels to enhance operator interface with this panel, d) removal of unused components, including associated components external to the panel, e) upgrade of panel wire, cable restraints and labels, and f) functional verification of all panel instruments and components.
Replacement of certain components used to monitor the administratively controlled transfer and release of radiological liquids and gasses will not affect the limiting conditions or safety margins as described in the Technical Specifications.
(SORC 92-065)
DCP # lEA-1030 Pkg. 1 "Replacement of 1CC924 Mark #D-2 with Mark #D-65 11 The purpose of this design change is to revise the appropriate documentation to change valve 1CC94 from a mark no. D-2 to a mark no. D-65.
This is a Component Cooling drain valve located in the no. 12 cc Heat Exchanger Room, which had been replaced under WO 881010102.
The replacement of a non-nuclear valve with a nuclear class 3 valve ensures the integrity of the system.
Installing the valves properly with a Code Job Package and performing the NDE ensures the integrity of the pressure boundary.
This does not change the function of the system and does not impact the requirement of having two independent trains.
Therefore, this change will not reduce the margin of safety as defined in the basis for the Technical Specifications.
(SORC 92-067)
10CFR50~59 EVALUATIONS MONTH: -
JUNE 1992 (cont'd)
ITEM DCP# lEC-3155 Pkg. 1 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JULY 10, 1992 J. FEST (609)339-2904 "Circulating Water Screen Wash Strainer Breaker" -
The purpose of this change is to change the type and rating of the four circuit breakers that control the branch circuits used to feed No. 11, 12, 13, and 14 screen wash strainers.
These circuit breakers are located at the 6A20, 6A22, 6A9 and 6A10 positions in the No. 11 Circulating Water Intake 230V Control Center Sect, No. 1 (located in CWI Control House #1).
The change is to GE type TED 15 amp circuit breakers.
This DCP does not reduce the margin of safety as defined in the basis for any Technical Specification because the change in screen wash pump strainer circuit breakers will not affect any of the operating limits necessary to protect the fission barriers inherent in the plant's design.
(SORC 92-069)
B. Procedures and Revisions SC.SA-AP.ZZ-0012(Q)
"Technical Specification Surveillance Program Matrix" Rev. 16 - This proposal involves a revision to station Administrative Procedure, SC.SA-AP.ZZ-0012(Q), Technical Specification Surveillance Program.
The responsibility for performing Appendix "B" surveillance number 4.2.1 (Unit 1 & 2) has been changed from Licensing and Regulation to Chemistry/ Licensing and Regulation.. This revision to the procedure does not change any previously analyzed testing requirement nor does it change any testing method, therefore the proposal cannot reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-064)
TSl.OP-SO.AF-OOOl(Q) "Auxiliary Feedwater System Operation" -
The No.
13 Auxiliary.Feedwater Pump (AFWP) recirculation line was cut by mistake in order to allow the Maintenance Department to ~ebuild the 13 AFWP turbine.
This line is open ended back to the_ tank so there is no way to isolate the line to repair it by welding the pipe back together.
This temporary procedure will allow the Operations Department to drain the contents of the Unit 1 Auxiliary Feed Water Storage Tank by filling the steam generators using the motor driven AFWP.
The
10CFR50;59 EVALUATIONS
. MONTH: -
JUNE 1992 (cont'd)
DOCKET NO:
UNIT NAME:
DATE:*
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 JULY 10, 1992 J. FEST (609)339-2904 ITEM
SUMMARY
SCPl Rev. 3 SCP2 Rev. 3 pumps are required to be operable in Modes 1, 2 and 3, however, they are not required to be operable in Modes 4, 5 and 6.
The basis for these operability requirements is to be able to cool the plant down to less than 350°F from normal operating conditions even in the event of a loss of offsite power.
When the plant is in Modes 5 or 6, the Reactor Coolant System temperature is less than 350°F and is being cooled by the Residual Heat Removal (RHR) System, so the basis for the Auxiliary Feed Technical Specifications does not apply.
This temporary procedure does not reduce the margin of safety as defined in the basis of Technical Specification 3.7.1.2 because the plant can be maintained in a safe shutdown condition by the RHR system and auxiliary feed is not required.
(SORC 92-064)
"L.oss or Degradation of Physical Security System"
- This procedure has been revised to incorporate the changed reference to security contingency event reporting pursuant to revised NRC guidance.
The procedure also contains editorial changes which do not alter the procedure's intent or implementation.
There is no security related accident analysis in the SAR.
There is no connection.between this procedure and any plant system.
Therefore, there is no reduction to the margin of safety as defined in the basis for any Technical Specification. (SORC 92-067)
"Loss of Security Computer Power" -
This procedure has been revised to incorporate the changed reference to security contingency event reporting pursuant to revised NRC guidance and to include Operations under the responsibilities section (for restoration of power).
The procedure also contains editorial changes which do not alter the procedure's intent or implementation.
There is no security related accident analysis in the SAR.
There is no connection between this procedure and any plant system.
Therefore, there is no reduction to the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-067)
10CFR50~59 EVALUATIONS
. MONTH: -
JUNE 1992 (cont'd)
DOCKET NO:
UNIT NAME:*
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 JULY 10, 1992 J. FEST (609)339-2904 ITEM
SUMMARY
SCP5 Rev. 3 SCP6 Rev. 3 SCPlO Rev. 3 "Security Threat" -
The procedure has been revised to add extortion to the threat profile.
A sentence is added on security force job knowledge, self control, and professionalism, particularly under stress, as contributing to the perception and reality of a secure work place.
The systematic method of searching for destructive devices is changed to be compatible with current training methods.
The procedure also contains editorial changes which do not alter the procedure's intent or implementation.
There is no security related accident analysis in the SAR.
There is no connection between this procedure and any plant system.
Therefore, there is no reduction to the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-067)
"Discovery of Intruders or Attack" -
The procedure for initial rapid deployment and follow up actions in response to a confirmed intrusion has been revised.
The procedure also contains editorial changes which do not alter the procedure's intent or implementation.
There is no security related accident analysis in the SAR.
There is no connection between this procedure and any plant system.
Therefore, there is no reduction to the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-067).
"Discovery of Destructive Devices or Evidence of Malicious Acts" -
The revision changes assignments for making required nptif ications of the onset of the event, to reduce the burden on alarm station personnel during initial response.
New emphasis is added on searching for additional devices and malicious acts, regardless of what caused the event to be declared.
The procedure also contains editorial changes which do not alter the procedure's intent or implementation.
There is no security related accident analysis in the SAR.
There is no connection between this procedure and any plant system.
Therefore, there is no reduction to the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-067)
10C"FR50.59 EVALUATIONS MONTH: -
JUNE 1992 (cont'd)
DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 JULY 10, 1992 J. FEST (609)339-2904 ITEM
SUMMARY
SCP12 Rev. 3 "Security Alert" -
The procedure has been revised to expand the discussion of possible basis for declaring a Security Alert and to add direction concerning use of defensive positions.
The procedure also contains editorial changes which do not alter the procedure's intent or implementation.
There is no security related accident analysis in the SAR.
There is no connection between this procedure and any plant system.
Therefore, there is no reduction to the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-067)
C. Temporary Modifications TMR# 92-037 "Monitoring Temperatures at Different Locations Inside the Pressurizer Enclosure" -
~he pressurizer insulation was replaced with NUKON fiberglass type insulation, to reduce the temperature inside the pressurizer enclosure.
This temporary modification proposes to monitor the temperature inside the pressurizer enclosure.
The results will be used to evaluate the efficiency of the fiberglass insulation, determine the qualified life of cables inside the enclosure, and provide reliable means of evaluating heat stress conditions inside the pressurizer enclosure.
The temperature monitoring device does not perform any safety related function and does not affect any safety related system required for the safe shutdown of the Salem Unit.
There is no reduction to the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-065)
TMR# 92-039 Rev. 1 "Transfer Unit 2 BAST to Unit 1 BAST" -
The purpose of this temporary modification is to cross connect Unit 1 and Unit 2 Boric Acid storage Tanks (BAST) and be able to pump Unit 2 BAST to Unit 1 BAST to meet Tech Spec requirements on Unit 1.
The Technical Specifications dealing with required boration flowpath were reviewed.
The flowpath is from the Boric Acid Storage Tank (BAST) to the Boric Acid Transfer Pump (BATP) to the Reactor Coolant System (RCS), or Refueling Water Storage
10CFR50-.59 EVALUATIONS
' MONTH: -
JUNE 1992 (cont'd)
DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 JULY 10, 1992 J. FEST (609)339-2904
~---------------------------------------------------------------
ITEM
SUMMARY
Tank (RWST) to a Charging Pump to the RCS.
In Mode 5, only 1 flowpath is required.
Unit 1 and Unit 2 are both in Mode 5 and are using the flowpath from the RWST as the required flowpath.
The BAST and BATP are not required in Mode 5 if the RWST is lined up for injection.
This TMOD will not impair this flowpath from the RWST.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-068)
D. Deficiency Reports (DR) -
"Use-As-Is" DR SMD 92-643 "Repair of lPS-28 11 The purpose of this 'DR is.to evaluate taking a 15 mils skim cut on the stem of 1PS28, some indications still remain in back seat area.
Since the correct stem is not available to meet the outage schedule, this DR and safety evaluation accepts use-as-is disposition for 1 cycle.
It will be replaced with a new correct stem during lRll.
Use of P2R spray (1P53) or its isolation by 1PS28 is evaluated here.
This activity, by itself, does not introduce a failure mode of the stem or reduce the margin of safety since the stem is usually designed with a factor of safety greater than 2, the 20 mil diameter reduction is acceptable.
Additionally, the threaded section of the stem is minimum diameter reduced by depth of thread which is approximately 160 mils.
Therefore, a skim cut of 20 mils in the area of packing is acceptable with no reduction in margin of safety as provided by original component design.
(SORC 92-066)
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 JUNE 1992 The Unit was shutdown for the entire period for the 10th Refueling Outage.
REFUELING INFORMATION MONTH: -
JUNE 1992 MONTH JUNE 1992 e
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:
OCTOBER 2, 1993 50-272 SALEM 1 JULY 10, 1992 J. FEST (609)339-2904
- 3.
Scheduled date for restart following refueling:
DECEMBER 13. 1993
- 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 of Fuel Assemblies:
- a.
Incore 193
- b.
In Spent Fuel Storage 656
- 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-l-7.R4