ML19322B822

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Ack Receipt of Util Informing NRC of Steps Taken to Correct Violations Noted in IE Insp Repts 50-269/77-09, 50-270/77-09 & 50-287/77-09.Requests Addl Response Re Instruments Used to Test safety-related Sys
ML19322B822
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 08/16/1977
From: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Thies A
DUKE POWER CO.
Shared Package
ML19322B820 List:
References
NUDOCS 7912050803
Download: ML19322B822 (2)


See also: IR 05000269/1977009

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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230 PEACHTREE STREET. N.W. SulTE 1217

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ATLANTA, GEORGI A 30303

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AUG j g 1977

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In Reply Refer To:

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50-269/77-9

50-270/77-9

50-287/77-9

Duke Power Company

Attu:

Mr. A. C. Thies

Senior Vice President for

Production and Transmission

P. O. Box 2178

422 South Church Street

Charlotte, North Carolina 28242

Gentlemen:

This is in response to your letter of August 4,1977, which responded to

the Notice of Violation sent to you with our letter of July 13, 1977.

Item A of your response states that fire protection equipment is not

considered safety-related and that an item of noncompliance did not

exist. Criterion 3 of Appendix A to 10 CFR 50 requires that fire

detection and fighting systems be provided to minimize the adverse

effects of fire on structures, systems and components important to

safety. This criterion and the introduction to Appendix A establishes

that fire protection systems are safety-related.

Failure to maintain

the installed fire detection system in the reactor building could have

an adverse effect on the safety of the plant and is considered to be

noncompliance. Notwithstanding, corrective actions stated in your

response to Item A are considered adequate.

No further response in

regard to this item is requested.

With regard to Item B of your response, instruments of the type identi-

fied in the Notice of Violation used to verify the operability and

functional acceptability of safety-related systems as required by

facility Technical Specifications clearly places such instruments in the

category covered by Criterion XII of Appendix B to 10 CFR 50 and

Section 17.2.12 of the Duke Power Company Quality Assurance Program

Topical Report. Accordingly, with respect to Item B, please submit an

additional written response to this office, within ten (10) days of your

receipt of this letter, which provides the information required by

Section 2.201(a) of 10 CFR 2.

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AUG 1t;1977

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Duke Power Company

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Your response should also address your administrative system for identi-

fying safety-related structures, systems and components and your planned

corrective action.

Should you have any questions concerning this letter, we would be happy

to meet with you and discuss the matter further.

Very truly yours,

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es P. O'Reilly

D ector

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cc:

W. O. Parker, Jr.

Vice President Steam Produ

Duke Power Company

P. O. Box 2178

422 South Church Street

Charlotte, North Carolina 28242

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