ML19319B908
| ML19319B908 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/15/1975 |
| From: | Hunnicutt D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19319B907 | List: |
| References | |
| NUDOCS 8001290645 | |
| Download: ML19319B908 (2) | |
Text
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NUCLEAR REGULATORY COMMIS0!ON
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I 799 ROO'.,EVCLT HO/5.0 C
9 CLCN ELLYN ILLINots 60137 A
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.December 15, 197 h 9
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.S.1.Ild_a Knr1 V. Seyfrit, Chief, Reactor Technical Assistance Branch Oftice of Inspection and Enforcement, Headquarters PHfSICAL SEPARATION OF PROTECTIVE AND CONTROL FUNCTION OUTPUT WIRING WITilIN REACTOR PROTECTION AND SAFEGUARD SYSTEM CABINETS Attention has been recently focused upon viring problems at the Davis-Besso Nuclear Power Station, Unit 1, concerning the separation of protective and control function output circuitry within the Reactor Protective System (RPS) and Safety Features Actuation System (SFAS) cabinets.
The Davis-Besse Unit 1 RPS equipment was manufactured by the Babcock and Wilcox (B&W) Company, Bailey Meter Division, and the SFAS by the Consolidated Controls Corporation.
Through discussion with Bailey Meter Division and Consolidated Controls Corporation representatives and physical verification by 1E:III inspectors, it has been concluded O
that no actual design effort was made by either company to provide g
(Q internal separation between protective and control function outputs.
The licensee had no evidence to show that an analysis had been performed to justify the " intermingling" of protective and control function wiring. This same situation is also believed to exist at the Oconee and Midland plants and, possibly, at all other facilities that have B&W NSSS.
The wiring of these RPS and SFAS cabinets appears to be in conflict with IEEE-279, 1971. Section 4.7.2.
Because of the possible generic nature of this probi.sm and extensive effort and time required to rewire the cabinets, this apparent noncompliance is being forwarded to you for resolution.
Resolution of the following is specifically requested:
1.
Is this an acceptable design for this vintage of plant? If not, what analyses or other justifiestion should be required to establish acceptance at the Davis-Besse Unit 1 planc?
2.
If this design does not meet requirements, what corrective action l
1s required?
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Karl V. Seyfrit 2-December 15, 1975 i
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Mr. A. J. Szukiewicz, NRR-TR (cicetrical) is also familiar with the l
j witing concerns at Davis-Besse, Unit 1.
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Sh: auld you have any questions concernitig this matter, please contact 1
Mr D. U. Ilayes or Mr. F. J. Jablonski.
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b (k 4m W D. M. Ilunnicutt, Chief Reactor Construction and i
Engineering Support Branch l
cc:
H. D. Thornburg, IE: LIQ
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G. W. Roy, IE: LIQ J. G. Keppler 4
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