ML20237K418

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Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-424/87-11 & 50-425/87-07.Violation a Withdrawn Due to Violation Covering Same Issue as Deviation in .Severity Level Stands
ML20237K418
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/18/1987
From: Reyes L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: James O'Reilly
GEORGIA POWER CO.
References
NUDOCS 8708270172
Download: ML20237K418 (4)


See also: IR 05000424/1987011

Text

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AU G 1 8 190I

Georgia Power Company

L#fTN: Mr. James P. O'Reilly

Senior Vice President

Nuclear Operations

P. O. Box 4545

Atlanta, GA 30302

Gentlemen:

SUBJECT:

DOCKET NOS. 50-424/87-11 AND 50-425/87-07

Thank you for your response of March 31, 1987, to our Notice of Violation

issued on March 3,1987, concerning licensed activities conducted at your

Vogtle facility.

We have evaluated

your response to Violation B and found

that it meets the requirements of 10 CFR 2.201.

We will examine the

implementation of your actions to correct Violation B during future inspections.

After careful consideration of the basis for your denial of Violation A, we

have concluded that the violation is the same issua as the deviation discussed

in your March 31, 1987 letter, and is, therefore, withdrawn and our records will

be so amended.

Based on the conversation between Mr. Charles Hayes of your staff and

Mr. W. P. Kleinsorge of this office on July 15, 1987, it is our understanding

that you will provide a supplemental response for the devittion discussed in

our letter, dated August 29,1986 (50-424/86-59 and 50-424/86-26) to this

office.

After careful consideration of the basis for your request that the Severity

Level for Violation B should be reduced to Severity Level V, we have concluded,

for the reasons presented in the enclosure to this letter that the Severity

Level stands.

The response directed by this letter is not subject to the clearance procedure

of the Office of Management and Budget issued under the Paperwork Reduction

Act, PL 96-511.

We appreciate your cooperation in this matter.

Sincerely,

Original Signed by

Luis A. Reyes

Luis A. Reyes, Director

Division of Reactor Projects

Enclosure:

(See page 2)

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Enclosure:

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Staff Assessment of Licensee Response

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d E. Conway, Senior Vice President &

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Project Director

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L4r Whitney, General Manager Project

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W D. Rice, Vice President, Project

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'R' H. Pinson, Vice President, Project

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LG(W. - Hayes, Vogtle Quality

Jssurance Manager

vG'. B. Bockhold, General Manager,

fuclear Operations

. Gucwa, Manager, Nuclear Safety

and Licensing

T A. Bailey, Project Licensing

I .Mjnager

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W. Churchill . Esq. , Shaw.

Pittman, Potts and Trowbridge

E E Joiner, Troutman, Sanders,

Lockerman and Ashmore

[d-G.Ledbetter, Commissioner,

DJpartment of Human Resources

LC'.H. Badger,OfficeofPlanning

and Budget

'V Kirkland, III, Counsel,

Office of the Consumer's Utility

ouncil

. Feig, Georgians Against

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LJi. B. Margulies, Esq., Chairman,

Atomic Safety and Licensing Board

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. 0. H. Paris, Administrative Judge

Atomic Safety and Licensing Board

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VA. Linenberger, Jr., Administrative Judge

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ENCt.050RE

STAFF ASSESSMENT OF LICENSEE RESPONSE

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Restatement of Violation B (50-424/87-11-02 and 50-424/87-07-02)

10 CFR 50.55(e)(3) requires the holder of a construction permit to submit

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a written report on a reportable deficiency within thirty (30) days.

The

report shall include a description of the deficiency, an analysis of the

safety implications and the corrective action taken, and sufficient

information to permit analysis and evaluation of the deficiency and of

the corrective action.

Contrary to the above, the licensee did not submit a report with

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sufficient information to permit analysis and evaluation of the corrective

actions in that the licensee was unable to identify the 120 deficient

heating ventilating and air conditioning duct supports reported in

Construction Deficiency Report (CDR) No. 82-32 of September 30, 1982.

Summary of Licensee's Response

After careful review of the severity categories prescribed in Supplement

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II to 10 CFR 2, Appendix C, and evaluation of the event cited in

the violation, GPC has concluded that a more appropriate severity

classification is Severity Level V - violations that have minor safety

or environmental significance.

Since GPC's corrective actions relative

to CDR 82-32 were determined to be adequate by the NRC, the violation

identifies a document retrievability discrepancy that has minor safety

significance; therefore, the Severity Level should be reduced to Severity

Level V.

NRC Evaluation

The violation was a failure to provide an adequate report of significant

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construction deficiency which is contrary to 10 CFR 50(e)(3) which was

exacerbated by a document retrievability discrepancy.

NRC Conclusion

Violation B was appro,priately categorized as a Severity Level IV.

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