ML16341E726

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Notice of Violation from Insp on 861215-19.Violation Noted: Qualification Documentation for Resistance Temp Devices Did Not Demonstrate Qualification for post-LOCA Submerge Conditions
ML16341E726
Person / Time
Site: Diablo Canyon  
Issue date: 07/12/1988
From: Pate R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML16341E725 List:
References
50-275-86-33-01, 50-275-86-33-1, 50-323-86-31, NUDOCS 8807210168
Download: ML16341E726 (4)


Text

APPENDIX A NOTICE OF VIOLATION Pacific Gas and Electric Company Diablo Canyon Nuclear Power Plant Docket Nos.

50-275 and 50-323 License Nos.

DPR-80 and DPR-82 As a result of the inspection conducted on December 15-19,

1986, and in accordance with NRC Enforcement Policy, 10 CFR Part 2, Appendix C, the following violation was identified:

Paragraph (f) of 10 CFR 50.49 requires qualification of each item of electric equipment important to safety.

Paragraph (k) of 10 CFR 50.49 provides that equipment that the commission has previously required to be qualified to NUREG-0588, "Interim Staff Position on Environmental gualification of Safety-Related Electrical Equipment" need not be requalified.

The licensee agreed during the licensing process to meet category I for certain equipment including the equipment in question.

Paragraph 2.2(5) of NUREG-0588, Category I, requires qualification by test where equipment could be submerged and test and analysis to demonstrate adequacy of watertight enclosures.

6 Paragraph 2.4 of NUREG-0588, Category I, allows qualification by analysis supported by partial test data on critical components of the equipment.

Paragraph 5(l) of NUREG-0588, Category I, requires auditable documentation in which the Eg basis is fully explained and data is pertinent to the application.

Contrary to the above, the qualification documentation for Minco RTDs did not, at the time of the inspection, demonstrate qualification for the post"LOCA submergence conditions to which they could be subjected in that documentation of submergence type testing for the equipment was not included in the Eg file nor was there adequate partial type test data and analysis.

This is a Severity Level IV violation (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, Pacific Gas and Electric Company is hereby required to submit a written statement or explanation to the U.

S.

Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region V, and a copy to the NRC Resident Inspector, Mr.

P.

P. Narbut, within 30 days of the date of the letter transmitted with this Notice.

This reply should be clearly marked as a

"Reply to a Notice of Violation" and should include for each violation:

(1) the reason for the violation if admitted, (2) the corrective steps that have been taken and the results

achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.

If an adequate reply is not received within'he time speci, fied in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other actions as may be proper should not be taken.

Consideration may be given to extending the response time for good cause shown.

88072i0i68 8807i2 PDR ADOCK 05000275 G!

PDC

FOR THE NUCLEAR REGULATORY COMMISSION Dated.at Wa1 nut Cree Jc Ca 1 iforni a this I & day of l

1988 Robert J.

Pa e

Chief Reactor Safety Branch