ML20215F673
| ML20215F673 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/17/1986 |
| From: | Brownlee V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20215F655 | List: |
| References | |
| 50-413-86-45, 50-414-86-48, NUDOCS 8612240022 | |
| Download: ML20215F673 (2) | |
Text
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t ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-413, 414 Catawaba License Nos. NPF-35, 52 9
During the Nuclear Regulatory Commission (NRC) inspection conducted on October 27-31, 1986, violations of NRC requirements were identified.
The violations involved technical specification surveillance inadequacies.
In accordance with the " General Statement of Policy and Procedure for NRC Enforce-ment Actions," 10 CFR Part 2, Appendix C (1986), the violations are listed below:
A.
Technical Specification 4.7.4.a requires that, at least two Nuclear Service Water loops shall be demonstrated operable at least once per 31 days by verifying that each valve (manual, power operated, or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position is in its correct position.
Contrary to the above, at least two nuclear service water loops were not demonstrated operable by verifying that each valve is on its correct position in that manual valves IRN-C21, -C22,1RN-21, -22, -23 and -25, which are in the seal water supply lines to the Nuclear Service Water pumps were not included in the monthly valve verification surveillance check lists.
This was identified by the inspector on October 30, 1986.
This violation is applicable to Units 1 and 2.
This is a Severity Level V violation (Supplement I).
B.
10 CFR 50 Appendix B, Criterion XII and the accepted Quality Assurance Program (Duke 1-A, Amendment 9) collectively require that measures be l
established to assure that instruments used in activities affecting quality are properly controlled and calibrated.
The licensee is committed to Regulatory Guide 1.33, Quality Assurance Program Requirements (0perations),
t which endorses ANSI N18.7-1976, Quality Assurance for the Operational Phase of Nuclear Power Plants.
Section 5.2.16 of this standard requires that instruments used for measurements shall be calibrated and maintained at specified intervals or prior to use.
Contrary to the above, these requirements were not being met in that a noncalibrated magnehelic (aP Detector) was used during the performance of Technical Specification surveillance 4.9.4.2.D.1 on August 28, 1986.
This surveillance demonstrates the operability of the reactor building containment purge system.
This violation is applicable to Unit 1 only.
This is a Severity Level V violation (Supplement I).
8612240022 861217 PDR ADOCK 05000413 G
Duke Power Company 2
Docket Nos. 50-413, 414 Catawaba License Nos. NPF-35, 52 Pursuant to the provisions of 10 CFR 2.201, Duke Power 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) 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.
o FOR THE NUCLEAR REGULATORY COMMISSION I
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gil L. Brownlee, Chief Reacto}r Projects Branch 3 f
Division of Reactor Projects Dated at Atlanta, Georgia this 17 day of December 1986 r
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