ML20235S522
| ML20235S522 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/02/1987 |
| From: | Alden W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC |
| Shared Package | |
| ML20235S267 | List: |
| References | |
| NUDOCS 8710090029 | |
| Download: ML20235S522 (5) | |
Text
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b yo NRC Monthly Operations Sumary Peach Bottom Atomic Power Station
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August, 1987 l^!
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UNIT-2 Lj.
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4 Unit 2 remained shutdown throughout the report period.
l' On' August'16, a half scram and Group'II:nnd III inboard isolations, f
1,nc3uding Shutdown Cooling System and Reactor Wate( Cleanup System isolations
" occurred as a result of a loss of offsite' power due to a trip of the startup fe'ed breaker caused by a tree contacting a high voltage line. 'M? of the isolations were reset within 15 minutes and all equipment respchided as expected.
On August 20, a' Group II and III inboard isolations occurred as a result of: maintenance workers operating a crane too close to the 220 kV supply
~line causing ah; electrical arc which tripped the startup feed bre der.
Essential systwas were restored to service as needed after the isolations.
Station electfical power via the #2 Startup feed was restored within five hours.
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On August 28, Shutdown Cooling isolated when Residual Heat' Ramoval (RHR)fuseswere'removedforamaintenancepermit. Shutdown Cooling was restored within eight minutes.
Unit 3-
,sa Unit 3 remained shutdown throughout the report period.
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OnAugust~16.ahoup!!outboardisolationoccurredasaresultofa lLg; loss of offsite power due>to the startup feed breaker trip caused by a tree r
Qj touching a high voltage line (previously discussed for' Unit 2) n 1
On August 20 a Group II outboard isolation occurred when the startup i
feed breaker tripped'due to a crane coming too close to the 220 kV supply line, causing an electrical arc (previously discussed for Unit 2).
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J 8710090029 071002 PDR ADOCK 00000277 i R
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i Docket No. 50-277
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Attachment to Monthly Operating I
Report for August, 1987 j
J UNIT 2 REFUEJ.ING INFORMATION 1.
-Name of facility:
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Peach Bottom Unit 2-2.
Scheduled date for next refueling shutdown:
I Reload 7 in progress 3.
' Scheduled date for restart following refueling:
Indeterminate due to Shutdown Order
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4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
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g Yes
- If answer is yes, what, in general, will these'be?
Technical Specifications to accommodate reload fuel. Modifications to reactor core operating limits.
5.
. Scheduled date(s) for submitting proposed licensing action and supporting information:
Reload 8 license amendment to be submitted January 1989.
6.
Igortant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviWed design or perfomance analysis methods, significant changes in fugl design, new operating procedures:
Noneexpecteb.
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The number of fuel assemblies (a) in the cc h and (b) in the spent fuel storage pool:
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(a) Core - 764 fuel Assemblies, Cord Offloaded During Outage (b) fuel Pool - 1462 Fuel Assemblit % 58 Fuel Rods l..
8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies.
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't' Docket No. 50-277 Attachment to Monthly Opertting
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Report for August, 1987 Page 2
-UNIT 2 REFUELING INFORMATION (Continued)
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The projected date of the last refueling that can be d 9.
of the new. fuel racks installation:
March,1998 (March 1995, with reserve full
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Docket No. 50-278 Attachment to Monthly Operating Report for August, 1987 UNIT 3 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 3 2.
Scheduled date for next refueling shutdown:
October,1987 (Major Pipe Replacement Outage) 3.
Scheduled date for restart following refueling:
July 9, 1988 1
4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes.
If answer is yes, what, in general, will these be?
l Technical Specifications to accommodate reload fuel. Modifications to reactor core operating limits.
S.
Scheduled date(s) for submitting proposed licensing action and supporting information:
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Reload 7 License Amendment to be submitted March 11, 1988 1
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Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
None expected.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a Core - 764 Fuel Assemblies (b Fuel Pool - 1496 Fuel Assemblies, 6 Fuel Rods
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Docket No. 50-278 Attachment to Monthly Operating Report for August, 1987 Page 2 UNIT 3 REFUELING INFORMATION (Continued) 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies. This modification began on February 20, 1987. The completion date for this modification has been rescheduled for February, 1989 to accommodate the Unit 3 pipe replacement outage.
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The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity, prior to the completion of the new fuel racks installation:
March, 1993 (reserve full core discharge following restart after 1987-88 pipe replacement and refueling)
- 10. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the relicensed capacity, subsequent to the
-completion of the new fuel racks installation:
March, 1999 (March, 1996, with reserve full core discharge) i
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