ML18153C086
| ML18153C086 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/23/1990 |
| From: | Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18152A420 | List: |
| References | |
| 50-280-89-32, 50-281-89-32, NUDOCS 9001310096 | |
| Download: ML18153C086 (2) | |
Text
ENCLOSURE.1 NOTICE OF VIOLATION Virginia Electric and Power Company Surry Nuclear Plant Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37 During the Nuclear Regulatory Commission (NRC) inspection conducted on October 16-20, 1989 and October 30 - November 3, 1989, a violation of NRC requirements was identified.
Ir;* accordance with the "General Statement of Policy and Procedure for NRC Enforcemen~ Actions~** 10 CFR Part 2, Appendix C (1989), the violtion is listed below:
10 CFR 50.59(a)(l) sta.tes that th~ holder of a license authorizing operation of a production of util izc.1tion faci 1 ity may make changes in the facility as described in the Safety Analysis Report, without prior Commission approval unless the proposed change involv~s a change in the Technical Specifications incorporated in the license or.an unreviewed safety question.
Section 9,.13~4 of the Surry Updated Final Safety Analysis Report (UFSAR),
Design Evaluation, states that the ventilation systems in areas of po ten ti al contamination pro vi de contamination control by ensurfog that air is not recirculated, that 10 or more air changes per hour are supplied, and that air is supplied to the least likely areas to be contaminated for circulation to and exhaust from locations subject to the greatest contamination potential.
Section 11.3.3.3 of the UFSAR, Ventilation Vent Particulate and gas Mani tor-s, states that a multi-probe i sokineti c sampler is provided to obtain a representative sample in the 80 inch diameter duct.
10 CFR 20.201(b) requires that each licensee make or cause to be made such surveys as may be necessary to comply with the regulations in 10 CFR 20 and surveys are reaso*nable under the circumstances to ev~luate the extent of -radiation hazards that may be present.
Technical Specification 4.9.E requires that the dose rate due to Iodine-131, Tritium, and all radionuclides in particulate form with half life greater than eight days in gaseous effluents shall be determined to be within the limits of Technical Specification 3.11.6.1 (Offsite Dose Limitations) in accordance with the Offsite Dose Calculation Manual by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.9.2.
This tc1t,le specifies authorized gaseous effluent re1ease types and sample frequency.
Virginia Electric and Power Company Surry Nuclear Plant 2
Docket Nos. 50-280, 50-281 License Nos. DPR-32,_DPR-37 Contrary to the above, the licensee's evaluation of the modification to the ventilation system did not adequately address the resulting effects on the system air flow in that the resulting modifications did not ensure that air was supplied to the least likely areas to be contaminated for circulation to and exhaust from locations subject to the greatest contamination potential as stated in Section 9.13.4 of the Updated Final Safety Analysis Report (UFSAR).
Additional radiation monitors were added to the Ventilation-vent No. 2 sampling system without an adequate safety evaluation in that the effect of the additional flows required for these monitors were not properly evaluated for its effect on sample representativeness.
Flows of air from degraded and leaking ventilation systems to the environment potentially containing radioactive materials were not sampled to determine compliance with 10 CFR 20 and, Section 3.11.B.1, 3.11.B.2 and 3.11.B.3 of the Technical Specifications (TSs).
Samples of effluent from Ventilation vent No. 2 were not in accordance with Section 4.9.E of the TSs which require representative samples to be obtained from gaseous effluents.
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, Surry, 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:
(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 good cause 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 -0r why such other action as may be proper should not be taken.
Dated atfAtlanta, Georgia thi s,23~~ay of January 1990 FOR THE NUCLEAR REGULATORY COMMISSION A./~'.-*>'...
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.tJ. Philip Stohr, Director Division of Radiation Safety and Safeguards