ML20214C123
| ML20214C123 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/07/1986 |
| From: | Heward R GENERAL PUBLIC UTILITIES CORP. |
| To: | Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8611200692 | |
| Download: ML20214C123 (2) | |
Text
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GPU Nuclear Corporation
- Nuclear
- = = = 388 Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
November 7, 1986 Mr. Harry B. Kister, Chief Projects Branch No.1 U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Kister:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Inspection Report 86-21 The attachment to this letter provides GPU Nuclear's response to the identified violation in Appendix A of your letter dated October 9,1986.
If further information is required, please contact Mr. Michael Heller, OC Licensing Engineer at (609)971-4680.
Very truly yours, V
R. W. Heward, J r.
Vice President and Director Radiological & Environmental Co'ntrols RWH/MH/ dam:0254A Attachment cc:
Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Jack N. Donohew, Jr.
U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue, Phillips Bldg.
Bethesda, MD 20014 Mail Stop No. 314 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 8611200692 861107 PDR ADOCK 05000219 G
PDR GPU Nuclear Corporatton is a subsidiary of the General Public Utilities Corporation
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o.'4 ATTACHMENT I Violation:
10 CFR 20.201 requires, in part, that each licensee make or cause to be made such surveys as may be necessary to comply with the regulations and reasonable under the circumstances to evaluate the extent of radiation hazards that may be present. A survey is defined, in part, in 10 CFR 20.201 as an evaluation of the radiation hazards incident to the presence of radioactive materials or other sources of radiation under a specific set of conditions. When appropriate, such evaluation includes a physical survey of the location of materials and equipment, and measurements of levels of radiation or concentrations of radioactive material present.
Contrary to the above, during the period June 28 - July 2,1986, necessary and reasonable surveys were not made during control rod drive removal work sufficient to ensure compliance with 10 CFR20.101. The surveys made during the period failed to identify changes in the uniformity of radiation exposure of individuals standing on the floor under the reactor vessel and the subsequent need to reposition dosimetry and/or place multiple dosimetry badges on personnel in that area. As a result, the maximum whole body exposure received by these individuals standing on the floor underneath the reactor vessel was underestimated by a factor of two.
Response
GPUN concurs with the violation, l.
The corrective steps which have been taken and the results achieved:
(1) Radiological Controls technicians (RCT) were briefed on the importance of detailed surveys and the influence of radiation levels on dosimetry placement. All Radiological Engineers and Group Rad Con Supervisors (GRCS) reviewed the critiques.
(2) A copy of the critique and corrective actions was placed in the ALARA review file for incorporation into instructions for future control rod drive exchanges.
(3) A review of all active Radiation Work Permits and ALARA reviews was conducted and appropriate revisions were made to address lack of specificity in dosimetry placement.
2.
Corrective steps that will be taken to avoid further violations:
This event and the "D" recirc pump seal replacement incident also mentioned in Inspection Report 86-21 will be incorporated into GRCS and RCT cyclic training.
3.
Date when full compliance will be achieved:
Full compliance was achieved on July 3,1986.
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