ML18153B601
| ML18153B601 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/27/1989 |
| From: | Dan Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18152A294 | List: |
| References | |
| 50-280-88-49, NUDOCS 8902070020 | |
| Download: ML18153B601 (2) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Virginia Electric and Power Company Surry Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37 During -the Nuclear Regulatory Commission (NRC) inspectfon conducted on December 12-16, 1988, *violations of NRC requirements were identified.
In a*ccordance with the "General Statement of Policy.and Procedure for NRC Enforcement Actions, 11 10 CFR Part 2, Appendix C (1988), the. violations are listed below:
A.
Technical Specification 6.4.D requires that radiation control procedures be followed.
Health Physics Procedure HP-5.4.50, "Temporary Shielding" dated April 28, 1988, contains guidance on shielding and provides, in attachments to the procedure, forms to be utilized to give detailed instructions on shielding placement and attachment.
A copy of Attachment 3 of Health Physics Procedure HP-5.4.50, contained in Temporary Shie*lding Request 88-55 and completed specifically for shielding the reactor cavity drain line on the
-27 foot elevation of the Unit 1 containment, requires in step 3 that temporary shielding shall be attached with ties, stainless steel, wire or red tape.
Step 3 also states that if tape is used, it will not be placed directly on the pipe.
Contrary to the above, on December 14, 1988, temporary shielding placed at various locations on the reactor cavity drain line located on the -27 foot eleva~ion in Unit 1 containment was not fastened with ties, wire or tape.
Also, on December 15, 1988, the temporary shielding had been secured in plac~ with tape, but the tape was placed.directly on the pipe.
This is a Severity Level IV violation (Supplement IV).
B.
10 CFR 20.20l(b) requires each licensee to make or cause to be made such surveys as (1) may be necessary for the licensee to comply with the regulations in this part and (2) are reasonable under the circumstances to evaluate the extent of radiation hazards that* may be present.
10 CFR 2Q.201(a) defines a 11 survey 11 as an evaluation of the radiation hazards incident to the production, use, release, disposal or presence of radioactive materials or other sources of radiation under a specific set of conditions.
10 CFR 20.202 requires each licensee to* supply appropriate personnel monitoring equipment to specific individuals and requires the use of such equipment.
Virginia Electric and Power Company Surry 2
Docket Nos. 50-280, 50-281 Licens~ Nos. DPR~32, DPR-37 Technical Specification 6.4.D requires that radiation control procedures be fo 11 owed.
Health Physics Procedure HP-3.1.3, ~'Personnel Dosimetry-: Dosimetry Issue and Dose Determination, 11 dated July 27, 1988, requires in step 4.7.3.2 that the licensee evaluate the need for extremity badges when_ the expected exposure to the hands and forearms or feet and ankles is equal to or greater than one rem per hour and the extremity to whole body dose (12 inches from the contact dose rate) ratio i~ 5:1 or greater.
Contrary to the above,.the licensee failed to _evaluate adequately the extent of the radiation hazards present in that, on December 14, 1988, personnel performing decontamination operations in the Unit 1 reactor*
cavity g_enerated decontamination rags with radi atfon level readings up to 8 rem per hour while reviews of survey data and the reactor cavity
- conditions priof to initiating the job did not cause plant personnel to anticipate such problems and those assigned to the job were not cognizant of the problem as it developed.
The inadequate evaluation also resulted in the licensee's failure to comply with radiation control procedures in that personnel performing decontamination operations in the Unit 1 reactor cavity were not issued*extremity dosimetry.
This.is a Severity Level IV violation (Supplement IV).
Pursuant to the provisions of 10 CFR 2.201, Virginia Electric and Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC
- 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include [for each violation]: (1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where goodcause is shown, consideration will be given to extending _*the response time.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified~ suspended, or revoked or why such other action as may be proper should not be taken.
Dated at Atlanta, Georgia this '277'-<iay _ of !Ji, I\\,,..1v11989 FOR THE NUCLEAR REGULATORY COMMISSION Douglas M. Collins, Acting Director Division of Radiation Safety and Safeguards