ML19345E721
| ML19345E721 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/30/1980 |
| From: | Randazza J Maine Yankee |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19345E720 | List: |
| References | |
| WMY-80-168, NUDOCS 8102050717 | |
| Download: ML19345E721 (2) | |
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CQ) W'9 (207) 623-3521 mas *O December 30, 1980 UMY 80-168 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention:
Mr. Boyce H. Grier, Director
References:
(a)
License No. DPR-36 (Docket No. 50-309)
(b)
USNRC Letter to MYAPC dated December 8,
- 1980, Inspection 50-309/80-16
Subject:
Response to IE Inspection 50.~S3/80-16
Dear Sir:
In reply to Reference (b), the following information is hereby submitted.
ITEM OF NONCOMPLIANCE A.
10 CFR 50, Appendix B, Criterion V, states in part, " Activities affecting quality shall be prescribed by documented...
procedures aad shal.1 be accomplished in accordance with these... procedures".
The facility Operational Quality Assurance Program states in part, " Compliance with require-l ments of the Program - based on the criteria of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, and ANSI N18.7 - 1976 - shall be the responsibility of all personnel...".
ANSI N18.7 - 1976 states in part, "5.22.
Procedure Adhercnce.
Procedures shall be followed...".
Procedure 9.1.15, " Shipment of Radioactive Material",
requires in part that, "7.3.2 Quality Control personnel will verify that the handling equipment used to load radio-actice material has been inspected, checked, and is designed to handle the intended load weight".
Contrary to the above, during an inspection of the loading process for radioactive waste shipment 10-80-069A on October 6, 1980 the inspector observed that the cask lid and full liner were lifted without the above' required verification.
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MAINE YANKEE ATOMIC POWER CCMPANY 2
United States Nuclear Regulatory Cojmission December 29, 1980 Attention:
Mr. Boyce H. Grier, Director
RESPONSE
Maine Yankee Quality Control personnel have verified that the handling equipment used to lift the cask lid and full liner for radioactive waste shipment 10-80-069A was inspected and checked and was designed to handle this load.
Procedure 9.1.15
" Shipment of Radioactive Material" will be modified to include a hold point for accomplishment of this verification by Quality Control personnel.
Personnel involved with the shipment of radioactive waste have been briefed to stress this requirement.
We trust this information is satisfactory.
Should you have _.y further questions, please feel free to contact us.
Very truly yours, MAINE YANKEE ATOMIC POWER' COMPANY MN f
"f J. B.
Randazza Vice President, Operations
.