ML20234E807

Corrected Notice of Violation from Insp on 861215-19. Violation Noted:Qualification Documentation for Limitorque Motorized Valve Actuators Did Not Establish Similarity Between Installed Actuator & Actuator Tested

ML20234E807
Person / Time
Site:	Diablo Canyon
Issue date:	12/21/1987
From:	Pate R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML16341E485	List: ML20234E807
References
50-275-86-33, 50-323-86-31, NUDOCS 8801110180
Download: ML20234E807 (2)

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$PENDIX A NOTlf3FVIOLATION 4

Pacific Gas and Electric Company Docket Nos. 50-275 and 50-323 Diablo Canyon Nuclear Power Plant 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 violations were identified:

1. Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and sections 2.2 and 5(1) of NUREG 0588, Category-II, PG&E did not establish complete functional performance requirements for safety-related Conax RTDs in that

'the required accuracy for the RTDs was specified in the file as "11.75"F," but there were no criteria or standard values established with which to evaluate the data against this specification. Examination of the raw data showed that several of the samples during the design basis event simulation deviated from the others by more than 1.75'F.

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

2. Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and section 5(1) of NUREG 0588, Category II, the qualification documentation for Limitorque motorized valve actuators.(ID No. 8703) did not establish similarity between the installed actuator and that tested in that, unlike that tested, there was no gear case grease relief on the installed actuator.

The files contained no analyses to demonstrate that grease reliefs were not required for the DCPP applications.

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

3. Contrary to paragraph (1) of 10 CFR 50.49, PG&E had not upgraded'to 10 CFR 50.49 requirements the level of qualification of their Scotch 33+/Scotchco putty cable splice insulation system used on qualified equipment purchased after the effective data of 10 CFR 50.49 (February 22, 1983) and the file contained no sound reasons to the ,

contrary.

This is a Severity Level V 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 this Notice. This reply should be clearly marked as a l " 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 8801110100 871231 1 PDR ADOCK 05000275 l

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taken to avoid further violations, and (4) the date when the full compliance will be achieved. If an adequate reply is not received within the time specified ,

3 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. ,

FOR THE NUCLEAR REGULATORY COMMISSION obert J. Pate, Chief Reactor Safety Branch Dated at Walnut Creek, California thisQ}"dayof07ZaOb(1987 *

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