ML20009C555
| ML20009C555 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/23/1981 |
| From: | Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20009C553 | List: |
| References | |
| 50-344-81-12, NUDOCS 8107210224 | |
| Download: ML20009C555 (2) | |
Text
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APPENDIX A NOTICE OF VIOLATION Portland General Electric Company Docket No. 50-344 121 S. W. Salmon Street Portland, Oregon 97204 As a result of the inspection conducted May 11-15, 1981, and in accordance with the Interim Enforcement Policy 45 FR 66754 (October 7, 1980), the following violations were identified:
A.
10 CFR 20.101(a) states tha+. no licensee shall possess, use, or transfer licensed material in such a manner as to cause any individual in a restricted area to receive in any period of one calendar quarter from radioactive material and other sources of radiation a total occupational dose in excess of 1.25 rems whole body exposure. The licensee may permit an individual in a restricted area to receive whole body exposures not exceeding 3 rems per calendar quarter provided the individual's accumulated occupational dose has first been determined and recorded on a Form NRC-4 (or an equivalent record) as authorized by 10 CFR 20.101(b).
Contrary to this requirement, an individual working in the restricted area was permitted to receive a whole body exposure of 2.07 rem during the first calendar quarter of 1981 without prior determination of the individual's accumulated occupational dose. The licensee identified this oversight, determined that the individual did not exceed the 5(N-18) criterion, and took effective corrective measures to minimize recurrence.
This is a Severity Level IV Violation (Supplement IV).
B.
Technical Specification 6.8, " Procedures" states in part that:
" Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recomended in Appendix "A" of Regulatory Guide 1.33, November, 1972...."
Regulatory Guide 1.33, November 3,1971, Appendix A, " Typical Procedures for Pressurized Water Reactors and Boiling Water Reactors" lists typical safety-related activities which should be covered by written procedures.
Paragraph G, " Procedures for Control of Radioactivity" to limit materials released to the environment and personnel exposure specifically mentions the Solid Waste System, including spent resin handling, baling machine operation, and drum handling and storage.
Section 6.8.2 states:
"Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PRB and approved by the General Manager prior to implementation and reviewed periodically as set forth in administrative procedures."
m G
Appendix A June 23, 1981 Contrary to this requirement, Procedures RP-107, " Radioactive Material Receipt and Shipment", Revision 7; TRP-003, " Radioactive Waste Druming",
Revision 0; TRP-006, " Dewatering Procedure for Resin Liners", Revision 0; and TRP-007, " Handling Procedure for CNSI Cask 6-80-2 Secondary Lid Removal and Replacement" Revision 0, involve limiting materials released to the environment and personnel exposure, have been implemented since April 1,1981 without review by the PRB and approval of the General Manager.
This is a Severity Level V Violation (Supplement V).
C.
10 CFR 20.203(f) " Caution signs, labels, signals and controls," states:
"Except as provided in subparagraph (3) of this paragraph, each container of licensed material shall bear a durable, clearly visible label identifying the radioactive contents."
Contrary to this requirement, on May 11, 1981 the inspector observed two unlibeled polyethylene bottles containing licensed material which produced radiation levels of 250 and 300 mr/hr at contact. The bottles were located on a storage shelf in the Primary Sample Room which was posted and controlled as a radiation / radioactive material area, however none of the exceptions provided in subparagraph (3) applied.
This is 9 Severity Level V Violation (Supplement IV).
Pursuant to the provisions of 10 CFR 2.201, Portland General Electric 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 to Items B and C of this Notice, including:
(1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further items of noncompliance; and (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 a ffirma tion.
Consideration may be given to extending your response time for good cause shown.
dated June 23, 19_81 b,
dd; G. P. Yu Radiation Specialist I
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