ML18116A073
| ML18116A073 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/30/1990 |
| From: | Verrelli D NRC Office of Inspection & Enforcement (IE Region II) |
| To: | |
| Shared Package | |
| ML18009A747 | List: |
| References | |
| 50-400-90-21, NUDOCS 9012170036 | |
| Download: ML18116A073 (4) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Carolina Power and Light Company Shearon Harris Unit 1
Docket No. 50-400 License No. NPF-63 During an NRC inspection conducted on October 20 -
November 16,
- 1990, violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1990), the violations are listed below:
A.
Technical Specification 6.8.1.a requires that written procedures be established and implemented covering procedures outlined in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Regulatory Guide 1.33, Appendix A, paragraph 10, requires that written procedures be provided for radiochemical analysis.
Radiochemistry Procedure RCP-660, Sample Preparation for Determination of Radioactivity, steps 10.3. 1.2.2 and 10.3. 1. 1.3, specify that nitric acid be added to the'sample prior to the analysis for radioactivity.
Contrary to the
- above, on October 24 and October 26,
- 1990, procedure RCP-660 was not properly implemented in that nitric acid was not added to an "A" steam generator sample and a reactor coolant system
- sample, respectively, prior to radioactivity analysis.
This is a Severity Level IV violation (Supplement I).
B.
10 CFR 50.59(b)(1) requires, in'art, that the licensee shall maintain records of changes in the facility from that described in the safety analysis report and that these records must include a written safety evaluation which provides the bases for the determination that the change does not involve an unreviewed safety question.
The Final Safety Analysis Report (FSAR) table
- 11. 1.7-1 list's the design concentrations of specific activity for various nuclides in the spent fuel pools.
Section
- 11. 1.1 of the FSAR further states that these maximum activities have been used in the design basis for shielding and facilities design and for calculating the consequences of postulated accidents.
Contrary to the above, a sample taken on October 12,
- 1990, found that the specific activities of manganese and cobalt in the spent fuel pools exceeded the design concentrations listed in the FSAR by as much as 5000 times and the licensee failed to provide a written safety evaluation for an unreviewed safety question determination.
This is a Severity Level, IV violation (Supplement I).
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Carolina Power and Light Company 2
Docket No. 50-400 Shearon Harris Unit 1
License No.
NPF-63 C.
10 CFR 50.74 requires, in part, that the licensee notify the NRC in writing within 30 days of the termination of any licensed senior operator.
Contrary to the above, the NRC was 'not notified of the termination of a licensed senior operator, Docket No. 20019, which occurred on September 8,
1989.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light Company is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission, ATTN:
Document Control
- Desk, Washington, D.C.
20555, with a copy to the Regional Administrator, Region II, and if applicable, a copy to the NRC Resident Inspector, within 30 days of the date of the letter transmitting this Notice of Violation.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results
- achieved, (3) the corrective steps that will be taken to avoid further viola-
- tions, and (4) the date when full compliance will be achieved.
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.
Where good cause is
- shown, consideration will be given to extending the response time.
FOR THE NUCLEAR REGULATORY COMMISSION
-A D
id M. Vgrelli, Chief Reactor Projects Branch 1
Division of Reactor Projects Dated at Atlanta, Georgia this $0+ day of November 1990