ML20211Q769
| ML20211Q769 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 02/24/1987 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20211Q741 | List: |
| References | |
| 50-313-87-01, 50-313-87-1, 50-368-87-01, 50-368-87-1, NUDOCS 8703030179 | |
| Download: ML20211Q769 (2) | |
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APPENDIX A NOTICE OF VIOLATION Arkansas Power & Light Company Dockets:
50-313/87-01 Arkansas Nuclear One 50-368/87-01 Licenses: DPR-51 NPF-6 During an NRC inspection conducted on January 19-23, 1987, three violations of NRC requirements were identified. The violations involved:
(1) failure to meet personnel qualifications, (2) failure to perform laboratory analyses, and (3) failure to report effluent doses.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2,
-Appendix C (1986), the violations are listed below:
A.
Failure to Meet Health Physics Personnel Qualifications Technical Specification 6.3.1 for Units 1 and 2 states, in part, "Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions...." Qualifications are further defined in health physics administrative procedure, 1612.013,
" Contract HP Technician Selection," which requires that senior health l
physics technicians have a minimum of 2 years (4000 hours0.0463 days <br />1.111 hours <br />0.00661 weeks <br />0.00152 months <br /> in a minimum of 80 weeks) of radiological protection experience in commercial nuclear power stations or their equivalent.
Contrary to the above, the NRC inspector determined on January 23, 1987, i
that a contract junior health physics technician was promoted to a senior health physics technician position prior to acquiring the minimum of 4000 hours0.0463 days <br />1.111 hours <br />0.00661 weeks <br />0.00152 months <br /> of radiological protection experience.
This is a Severity Level IV violation. (Supplement IV)(313/8701-01; 368/8701-01)
B.
Failure to Perform Laboratory Analyses Technical Specification 4.29.2.1B for Unit 1 states, in part, "The dose rate in unrestricted areas,... shall be determined in accordance with the Offsite Dose Calculation Manual... by using the sampling and analyses program specified in Table 4.29-3."
Technical Specification 3/4.11.2.1.2 for Unit 2 states, in part, "The dose rate
... shall be determined... in accordance with the Offsite Dose Calculation Manual by obtaining representative samples and performing l
analyses in accordance with the sampling and analysis program specified in l
Table 4.11-2."
The respective Technical Specification Tables 4.29-3 and l
4.11-2 require a monthly gross alpha analysis of unit vent air particulate samples.
=
l 0703030179 070224 PDH ADOCK 0500 13 G
. Contrary to the above, the NRC inspector determined on January 22, 1987, that the licensee had been performing quarterly gross alpha analyses on unit vent air particulate samples during the period January 1,1985, through December 31, 1986.
This is a Severity Level V violation.
(Supplement IV)(313/8701-02; 368/8701-02)
C.
Failure to Report Radwaste Effluent Radiation Doses Technical Specifications 6.12.2.6(e)(2) and (3) for Unit 1 and Technical Specifications 6.9.3.4(2) and (3) for Unit 2 states, "The first report filed each year shall contain:..
- 2. A summary of radiation doses due to radiological effluents during the previous calendar year calculated in accordance with the methodology specified in the Offsite Dose Calculation Manual.
- 3. The radiation dose to members of the public due to their activities inside the site boundary. This calculated dose shall include only those dose contributions directly attributed to operation of the unit and shall be compared to the limits specified in 40 CFR 190."
Contrary to the above, the NRC inspector determined on January 21, 1987, i
that the licensee had not included in the first semiannual effluent release report filed in 1986, a summary of radiation doses due to radiological effluents released to the environment during the previous calendar year (1985) nor did the report contain the radiation dose to members of the public due to their activities inside the site boundary.
This is a Severity Level V violation.
(Supplement IV)(313/8701-03; 368/8701-03)
Pursuant to the provisions of 10 CFR 2.201, Arkansas Power & Light Company is hereby required to submit to this office within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including for each violation:
(1) the reason for the violation if admitted, (2) the corrective steps which have been taken and the results achieved, (3) the corrective steps which will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.
Dated at Arlington, Texas this 24th day of February 1987 l
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