ML20031F306
| ML20031F306 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/13/1981 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-44, REF-GTECI-EL, TASK-A-44, TASK-OR 749, NUDOCS 8110190514 | |
| Download: ML20031F306 (12) | |
Text
a TOLEDO h EDISON RO4AAo P. CnousE vce sw.oent Docket No.53-346 m-(41912b9-5221 License No. NPF-3 Serial No. 749 October 13, 1981 SD A-C Y q b
Mr. John F. Stolz, Chief 6 Ogy.
C Operating Reactors Branch No. 4 Og{ 1 M' c# ge Division of Licensing
'p U. S. Nuclear Regulatory Commission Washington, D.C.
20555
(,,
Dear Mr. Stolz:
Your July 9, 1981 (Log No. 754) letter requested information regarding Station Blackout, Unresolved Safety Issue A-44.
Toledo Edison's response to your request is enclosed as it relates to the Davis-Besse Nuclear Power Station Unit No. 1.
The July 9 request contained a questionnaire with four tables to be completed.
In response, Tables 1-3 are enclosed. Unfortunately, the time and manpower necessary to detail all equipment modifications for Table 4 completion is extensive and as a result is not provided.
However, all such modifications to the Emergency Diesel Generators'are reviewed and documented through the Facility Change Request System.
All are subject to a nuclear safety review in accordance with Part 50.59 of the Title 10 to the Code of Federal Regulation. This process gives Toledo Edison a high degree of confidence that any proposed change that might have negative nuclear safety impact on the diesel generator emergency power rystem has been screened and rejected.
Very truly yours,
.1 RPC:DAH: lab enclosures I
cc:
DB-1 NRC Resident Inspector
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THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652
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y ( .? age 5 of 11 - mt.E 2 Diesel Canarator Schsduled Downtime Racord Plant N:me Dav'ts-Besse Calendar Year 19JO Unic No. 1 l l Ilours of Downtime Razzon for Reactor shutdown Reactor not shutdows. Comments Downtime pu[ pur DGF UUf DGf DGF DGF DGF DG# DGf 4 Schsduled Maintenance i Preventive 6 45 34 19 Maintenance Corrective 34 40 0 0 l Maintenance Equipment 20 Modify EDG 81 idler gear bolt prior j Modification to failure i i l t; i 4 i } a i 1 1 l l l i i I ,i Time DG is unavalloble for emergency service l baccuse of required tacts 1
Page 6 of 11 - nuLE 2 Diesel Canarctor Schaduled Downtime Racord Plcnt N:me Davis-Besse j Calendar Year 192 Unit No. I 1 lburs of Downtime Rasson for Reactor shutdown Reactor not shutdown Co m nts Downtime put our DGr nur DUf DGF DGF DGF DG# DG# 1 2 1 2 I Scheduled Haintenance i Preventive 43 32 36 58 j Maintenance i Corrective 37 6 9 9 Maintenance 1 1 t I i i t 1 i I t I i i i 1 l 1 l 1 i Tine DC is unavalloble 2 for emergency service i b:cause of required tests i I
q t Page 7 of 11 Ecclosure 1 - l TABLE 2 Discal Canarator Schsduled Downtime Pecord Plant Name Davis-Besse Calendar Year 19_7,8 Unit No. 1 i. 4 !!ours of Downtime ? Raason for Reactor shutdown Reactor not shutdown ) Downtime ~ Commenta puy puy DGy puy puy DGF DGF DG# DG# DGF 1 2 1 2 s Sch:duled i Maintenance Preventive 26.5 70.5 51 11 Maintenance i Corrective 0 2 7 0 Maintenance 1 1 I i I t 4 l l 1 i l i i f i l Time DC is unovailable } for emergency service ] hsecuse of required tsses O
y Page 8 of 11 Encloante 1 - ,i m 2 Diesel Canarator Schadulsd Downtime Racord Plant Name Davis-Besse j Calendar Year 19 n Unit No. 1 4 i Hours of Downtime Raaron for Reactor shutdown Reactor not shutdown Comments Downtime ~DGf DGf ucy ugy puy puy DGF DGF DGF DGF 1 2 1 2 } Schsduled Haintenance Preventive 28 48 0 8.5 Maintenance i Corrective 32 20.5 2 0 Maintenance i I i i t i i i i i b l j Time DC is unovoilable i for emergency service } bsenuse of required tests e -M
Page 9 of 11 - Diecal Generator Schedisled Downtime Record Plant Name Davis-Besse unE2 Calendar Year 19 3 Unit No. 1 llours of Downtime Reason for Reactor shutdown Reactor not shutdows Comments Dountime pug vug' pug-uur uug DGU DG0 QW3 ~l DGG ^ Scheduled Haintenance Preoperational testing of EDG's 8/11/76 through 3/7/77 1 1 I 1 i 4 s i 4 S 1 l Time DG is unavailable i for emergency service { because of required tests t I e
Page 10 of 11 Enclosura 1 - TABLE 3 Disaal censratar Untchiduled Downt'ime Rscard Plant Name Davis-Besse Calendar Year 19_L6-80 Unit No. 1 LER Abstract N< Downtime llours Comments - It any of the reported failures would not have been a (Rafer to attel failure unde'r emergency conditions, please explain here. cd LER Abstract s) Total Trouble-l'a r t s. Del - Repair / Refer to attached LERs or the Ta11ures listed in Table 1. llours shooting tvery.etc teplace 1 Design deficiency in the SFAS sequencer could result in an undesired instantaneous loading of the EDC. 2 175 3 .13 Los,s of breaker position indication on C1 and the 4160 VAC Essential bus. This placed EDG l-1 inoperable. 4 EDG l-1 did not actually fail, it had a con'dit1.on which required 4 404 1 repair to prevent further damage. 5 No failure. Design deficiency. 6 Revision to abstract No. 1 i r i 7 No actual failure of DG l-1. Maintenance was investigating load swings on DG 1-1 and had mistakenly racked out the output breaker for DG l-2. For approximately 20 minutes, the station was in the action statement of T.S. 3.8.1.2 which requires one DG to be operable in Modes 5 or 6. 8 51 9 22 10 3 The DG room temperature rose to 110 F. The outside air damper would not open. DG l-2 would start and would have continued to function for an undetermined amount of time. o 1 =, h 9
.s Page 11 of 11 Enclosura 1 - TABLE 3 Discsl GInaratcr Unichidulad Downtimo Ricard Plant Name Davis-Besse Calendar Year 1976-80 Unit No. 1 LER Abstract Na Downtime llours Comments - It any of cl.a reported failures would not have been a (Rsfer to attet failure unde'r emergency conditions, please explain here. cd LER Abstract s) Total Trouble-Parts, Del - Repair / Refer to attached LERa or the failures listed in Table 1. Hours shooting Lvery.etc teplace 11 Failure to perform required surveillance testing during inoperability of EDG 1-1. EDG 1-2 was able to start and supply electrical power to the essential busses. 12 Procedure inadequacy to verify the time of acceleration to 900 RPM. Had emergency power been required, the diesels would have been able to start and supply electrical energy to the essential busses as verified by the monthly tests. 13 9.5 4 14 106.5 15 49.5 16 3.5 17 Failure to perform required surveillance testing during inoperability of EDG l-l. When EDG l-1 was declared inoperable, the required sur-I veillance was performed within one hour successfully. After the sur-18 66.5 veillance error was identified and the surveillance was performed, EDG l-2 performed satisfa'ctorily. 19 0 No failure. Design deficiency. No LER associated with this abstract. 20 0 No LER associated with this abstract. This failure was during preoperational testing.
- 21 14.5
- LER ABSTRACT NO. 21 is attached to Table 3.
This abstract was not enclosed with the LER documentation in your letter of July 9, 1981. 8 .}}