ML20039B696
| ML20039B696 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 11/30/1981 |
| From: | Brunner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20039B693 | List: |
| References | |
| 50-309-81-26, NUDOCS 8112230432 | |
| Download: ML20039B696 (2) | |
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4 APPENDIX A NOTICE OF VIOLATION Maine Yankee Atomic. Power Company Docket No. 50-309
' Maine Yankee Nuclear Power Station License No.-DPR-36 '-
As a~ result of the inspection conducted on October 6 - November 10;1981,.and in accordance with the' Interim Enforcement Policy, 45 FR 66754 (October 7, 1980),
the.following violations.were identified:
1.
10 CFR 50, Appendix B, Criterion III, Design Control, requires measures-to be established to assure that; the design basis for structures, components, and systems.are correctly translated into specifications, drawings, and instructions; and that these measures shall apply to design changes.
I' The Yankee Operational Quality ' Assurance Program (Y0 QAP-1A),Section III requires design control through.the implementation of correct translation of design bases into specifications, drawings and written; documents; and.
the subjection of design-changes to-these same design controls and approvals.
Quality Assurance Procedure 0-01-1,. Design Change Alteration, Revision 6, dated October 15, 1980, implements these design control measures and states, in part, "7.3.1... Insignificant changes shall be documented" and "7.3.2 Concurrence on proposed insignificant changes shall' be-obtained~..." and "7.4 The Plant Cognizant Engineer shall ensure that applicable design inputs are correctly translated into installation in-structions..."
- Contrary to. the above, as of October 23, 1981, the measures established to assure that design chang'es are controlled, did not ensure the correct trans-lation of a design document, Engineering Design' Change (EDCR) 80-37, into installation instructions, in that, during the June - July 1981 refueling
. outage:
a.
Piping was installed upstream of valve HSI-M-42 rather than upstream of valve HSI-M-40 as called for'in EDCR 80-37; and
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b.
The piping was installed by drilling the existing piping rather than by use of a standard piping tee as called for in'EDCR 80-37; and c.
No Insignificant Change or other design change app. royal had-i, been documented.
This is a Severity Level V Violation (Supplement I.E).
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Appendix A 2
2.
Technical Specification 4.2 requires weekly sampling of the reactor coolant for hydrogen.
Procedure 7.204.1 Primary System Sample Points, Revision 2 dated March 29, 1979, describes the method for sampling the volume control tank gas space to determine reactor coolant hydrogen concentration.
Technical Specification 5.8.1 states, in part,
" Written procedures shall be established, impicmented and maintained..."
Contrary to the above, on.0ctober 13, 1981 the weekly volume control tank gas sample was taken without returning the purged gas volume to the waste gas surge drum as called for by procedure 7.204.1.
This is a Severity Level V violation.
-(SupplementI.E)
Pursuant to the provisions of 10 CFR-2 331, Maine Yankee Atomic Power Company is hereby required to. submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including:
(1) the corrective steps which have been taken and the results achieved;.(2) corrective steps which will.be taken to avoid further violations;. (3) the 'date when full compliance will be achieved. Under the-authority of Section 182 of the Atomic Energy Act of 1954,:as amended, this response-shall be submitted-under oath or affinnation. Where good cause is shown, consideration"will be given to extending your response time.
The responses directed by this Notice are not subject to the clearance proce-dures of the Office of Management and Budget as required by the Paperwork Act of 1980, PL 96-511.
Originel Sicned Byi Dated Eldon J. Brunncr, Chief, Projects l
Branch #1, Division of Resident' and Project-Inspection
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