ML20153D423

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Notice of Violation from Insp in Jan 1986
ML20153D423
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 02/18/1986
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20153D417 List:
References
50-313-86-02, 50-313-86-2, 50-368-86-02, 50-368-86-2, NUDOCS 8602240144
Download: ML20153D423 (2)


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t APPENDIX A ,

NOTICE OF VIOLATION .

Arkansas Power & Light Company Dockets: 50-313/86-02 50-368/85,02 Arkansas Nuclear One, Units 1 &.2 Licenses: DPR NPF-6 1

During an NRC inspection conducted during the period January 1-31, 1986, violations of the NRC requirements were identified. The violations- involved . .

failure to follow a quality control procedure in seismic support inspection 'and failure to perform pump testing per ASME Section XI as required by Technical Specifications. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the violations are listed below: ,

A ~. Criterion V of Appendix B to 10 CFR Part 50 requires, in part, that

-activities affecting quality shall be accomplished in accordance with docu-mented procedures. This requirement is a part of the licensee's approved quality assurance program.

Licensee Field-Inspection Procedure G-6, " Inspection, Examination and Test Control, Arkansas ,GSA 11306," Revision 2 of January 23, 1981, paragraph 3.6, required, in part, that the quality control inspection verify-that'the dimensions and geneial workmanship on pipe supports were as specified in the governing specifications and drawings.

Contrary. to the above, the licensee failed to identify dimensional ,

deficiencies and unsatisfactory workmanship on the emergency feedwater sys-tem seismic pipe support 3EFW-116-H20 during the post-installation quality control inspection as documented in licensee Quality Control: Inspection

. Record 72930-84 approved 3-27-85.

This is a Severity Level IV violation (Supplement I.D) (313/8602-01).

B. Technical Specification 4.0.5 requires that the emergency feedwater pumps (2P7A and 2P7B). undergo inservice testing in accordance with Section XI of the ASME Boiler and Pressure Vessel Code,1974 ' Edition. Licensee Plant Analysis Procedure 1022.07, "ASME Code Section XI Inservice Testing Program Unit 2," Revision 1, dated January 17, 1986, indicates in Attachmentti that inservice testing is accomplished for 2P7A and 2P7B using licensee proce--

dure 2106.06, " Emergency Feedwater System Operations," Revision'15 of December 12, 1985, Supplements I and II. Article IWP-3000 of Section XI of the code requires that reference values Lfor. differential pressure (dP) and flow (Q) be defined and that they be used to establish acceptance criteria in the form of ranges of these parameters.

Contrary to the above, licensee procedure 2106.06 does not define appropriate reference values for dP and Q and provide the specified acceptance criteria.

This is a Severity Level V violation (Supplement I.E) (368/8602-01).

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. Pursuant the provisions of 10 CFR.2.201,' Arkansas Power & Light. Company'is 3 l .hereby required to. submit-to this Office within 30 days of the date of the. ,~.

letter. transmitting this Notice, a written statement or explanation in reply, >

including for each violation: (1) the reason for thesviolation if admitted,

, ' (2) the corrective steps which have been taken' and-the results achieved, (3)-the c corrective steps'which will be taken to avoid further violations, and (4)-the s, date when full . compliance will: be' achieved., Where good cause is: shown,_

l consideration will be given to extending the-response . time. >

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L Dated at Arlington, Texas, ~1986. "

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