ML20106D192
| ML20106D192 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/05/1984 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20106D174 | List: |
| References | |
| 1-469, NUDOCS 8410250034 | |
| Download: ML20106D192 (2) | |
Text
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Docket No. 50-346 rotsoo License No. NPF-3 Serial No. 1-469 NN" naw-
"' 8' 3" "2 October 5, 1984 Mr. C. E. Norelius, Director Division of Reactor Projects United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Norelius:
Toledo Edison acknowledges receipt of your Septerber 11, 1984 letter (Log No. 1-1031), and anclosures, Appendix A, Notice of Violation, and Inspection Report No. 50-346/C4-18 (DRP).
Following an examination of the items of concern, Toledo Edison herein offers information regarding these items:
1.
Violation:
10 CFR 50 Appendix B, Criterion III, states in part:
" Measures shall be established to assure that applic-able regulatory requirements and the design basis, as defined in 10 CFR 50.2 and as specified in the license applice. tion, for those structures, systems and compon-ents to which this appendix applies are correctly trans-lated into specifications, drawings, procedures, and instructions...
Design changes, including field changes, shall be subject to design control measures commensurate with those applied to the original d;g_
sign..."
Contrary to the above, the design basis power supply for reactor coolant system high point vent valve RC 4608A was not correctly translated into the drawings and instructions included in Facility Change Request (FCR)80-120 for supplying power to valve RC 4608A.
The design basis power supply for RC 4608A was Class IE power. The drawings and instructions included in FCR 80-120 erroneously required RC 4608A to receive non-Class 1E power.
This is a Severity Level IV violation (Supplement I).
8410250034 841016 PDR ADOCK 05000346 O
PDR THE TOLEDO EDISON COMPANY EOISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652 h)
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O S -- DocketcNd[50-346
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- License'No. NPF-3
' Serial No.Ll-469
' October =5 1984.
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Page 2
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1 Response: (1),
Corrective action taken and results achieved..
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A review'of,the appropriate drawings was conducted to
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confirm that a wiring problem existed.. The Station
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Technical-Section was notified by-Surveillance Report 84-30 to. determine reportability.
Drawing Change Notices were issued by Bechtel and a supplement to the Facility Change Request (FCR)80-120 was initiated to provide ~an essential source of DC power to_SV_4608A.,
Bechtel has reviewed the power supplies to the other three solenoid valves installed under FCR 80-120 as well as power supplies to all Class 1E relay cabinets.
No discrepancies were' discovered.
-(2) Corrective action'to be taken to avoid further noncompli-ance.
Based on Bechtel'a' review, the' design error was an isolated case and-there was no breakdown in their design verification procedures.
_ Additionally, to-ensure that. future modifications are reviewed for proper power supplies, the Loss.of Instrument Power (LIP) review sheet has been revised to show a separate check-off block for a review to verify safety-related components have an essential source'of power. Procedure-NFEP-020, Design Work Packages, was revised to require'the incorporation of
- the revised LIP into future applicable work packages.
'(3) Date'when full compliance will be achieved.
' Full compliance will' be' achieved upon implementation of the supplement to FCR 80-120, which will occur by
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the end of the 1984 refueling outage.
' Very truly yours, f fk==^
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RPC TPB:SGWinif
-'cci> DB-1 NRC Resident Inspector
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