ML20010A270
| ML20010A270 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 04/24/1981 |
| From: | Conway W VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20010A267 | List: |
| References | |
| FVY-81-72, IAL-81-17, NUDOCS 8108110258 | |
| Download: ML20010A270 (4) | |
Text
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VERMONT Y AN KEE NUCLEAR POWER CORPORATION SEVENTY SEVEN GROVE STREET FVY 81-72 RUTLAND, VERMONT 05701 2.C.2.1 REPLY 70; ENGINEERING OFFICE 1671 WORCESTER ROAD FRAMINGH AM, M ASSACH USETTS 017o1 TELEPHONE 817 872-8100 April 24, 1981 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Attentic*:
Mr. Boyce H. Grier, Director
References:
(a) License No. DPR-28 (Docket No. 50-271)
(b)
Immedin e Action Letter 81-17, dated April 1, 1981
Dear Sir:
Subject:
Response to Immediate Action Letter 81-17 In response to the above referenced letter, Vermont Yankee has completed a review and evaluation of the application of the plant's-quality assurance program (10 CFR 50, Appendix B) as applied to the packaging and delivery of radioactive material to a carrier for transport. The results of our evaluation are provided below.
I.
Organization Responsibilities and organizational relationships are es-tablished in YOQAP-1-A,Section I, for personnel involved with activities requiring QA. Further controls are pro-vided in the existing plant radwaste packaging procedure.
II.
Quality Assurance Program The responsibility for training of personnei lies with the appropriate plant department. OQA reviews vendor QA programs to assure satisfaction of applicable vendor re-quirements of Appendix B.
Packaging of radioactive ma-terials has been identified as an item requiring Quality Assurance via revisions of YOQAP-1-A,'as such, the Quality Assurance implemanting procedures are automati-cally invoked for the procurement ami use of casks and liners.
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VERMONT YANKEE NUCLEAR POWER CORPORATION United States Nuclear Regulatory Commission April 24, 1981 Page 2 III.
Design Control The existing plant procuremenP. procedures provide the necessary controls.
IV.
Procurement Document Control The existing plant procurement procedures provide the necessary controls.
V.
Instructions, Procedures and Drawings The plant radwaste packaging procedure has been revised to include the controls necessary to ensure that activi-ties affecting quality are satisfactorily accomplished.
VI.
Document Control Plant and 0QAD procedures are controlled in accordance with specified administrative procedurts; the existing document control procedures provide the necessary controls.
VII.
Control of Purchased Material, Equipment, and Fervicas The plant radwaste packaging procedure has been revised to incorporate detailed receipt inspection criteria for the casks. The existing plant receipt inspection proce-dures provide the necessary controls for the liners.
VIII.
Identification and Control of Material, Parts and Components The plant radraste packaging procedure has been revised to verify the canufacture's identification number of the cask. The existing plant receipt inspection procedures l
provide the necessary controls for the liners.
IX.
Control of Special Processes The existing plant procurement procedures provide the i
necessary controls.
X.
Inspection The plant radwaste packaging procedure has been revised to include inspection, verification, and documentation measures adequate to determine conformance to procedure requirements.
~
. VERMONT YANKEE NUCLEAR POWER CORPORATION j
United States Nuclear Regulatory Commission April 24, 1981 Page 3 Periodic inspections of plant activities will be conducted by 0QAD to verify compliance with plant procedures, speci-fically:
1.
Receipt of MPR stipulated documentation.
2.
Plant. submittal of its name/ license #, vendor name/
license # and package ID# to the NRC prior to ini-tial use of the package.
3.
Plant compliance with the applicable terms of the package license.
4.
Package is loaded and closed in accordance with plant procedure.
The frequency of the above inspections will be increased and the scope of these inspections will be expanded.
XI.
Test Control The existing plant procurement procedures provide the necessary controls.
XII.
Control of Measuring and Test Equipment The existing plant calibration and test procedures pro-vide the necessary controls.
XIII.
Handling, Storage, and Shipping The existing plant radwaste packaging and storage proce-dures provide the necessary controls.
XIV.
Inspection, Test, and Operating Status The existing plant radwaste packaging procedure incorpor-ates tracking the status of the cask. The existing plant procedure for identification and control of materials pro-vides the necessary controls for the liners.
XV.
Nonconforming, Materials, Parts, or Components The plant radwaste packaging procedure has been revised to provide a categorizatica of cask-related discrepancies.
Major discrepancies will be documented and corrected in accordance with the existing plant nonconformance proce-dure.
VERMONT YANKEE NUCLEAR POWER CORPORATION United States Nuclear Regulatory Commission April 24, 1981 Page 4 The existing plant receipt inspection and nonconformance procedures provide the necessary controls for the liners.
XVI.
Corrective Action The plant radwaste packaging procedure has been revised as described under Section XV.
Minor disccepancies of the cask will be documented and corrected in accordance with the existing plant maintenance request procedures.
XVII.
Quality Assurance Records The existing record retention procedures provide the necessary controls. OQAD retains records associated with OQA inspections and audits.
XVIII.
Audits The scope of the annual Health Physics audit, which is performed as part of the In-House-Audit Program, will be expanded to provide a more detailed evaluation of the activities partaining to the packaging and delivery of radioactive material to a carrier for transport in ac-cordance with the requirements of 10 CFR 71.51.
We trust this information is satisfactory; however, should you desire additional information, please contact us.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION W.
William F. Conway Vice President and Manager of Operations DAR/jh
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