ML20211A490

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Notice of Violation from Insp on 861226-870125
ML20211A490
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 02/06/1987
From: Reyes L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20211A432 List:
References
50-413-86-51, 50-414-86-54, NUDOCS 8702190178
Download: ML20211A490 (2)


Text

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e ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-413 and 50-414 Catawba 1 and 2 License Nos. NPF-35 and NPF-52 During the Nuclear Regulatory Commission (NRC) inspection conducted on December 26, 1986 - January 25, 1987,. violations of NRC requirements were identified.

The violations involved: 1. Failure to follow procedures and technical specification surveillance requirements and failure to comply with a technical specification limiting condition for operations.

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.

Technical Specification 6.8.1 requires that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A to Regulatory Guide 1.33, Revision 2.

Licensee procedure Station Directiva 3.0.3, Rev. 8 requires appropriate personnel to assign the responsible group for releasing a system to be worked on.

Technical Specification 4.11.2.1.1 requires dose rates to be determined for gaseous effluent releases.

Contrary to the above, a procedure was not followed in that work on the Gaseous Waste System was assigned to be released by the Operations group; instead of the responsible group which was Radweste Chemistry. This failure to follow procedures caused the inadvertent gas release of January 5,1987.

Also, the dose rate was not determined prior to this release on January 5, 1987.

This is a Severity Level IV Violation (Supplement I).

B.

Technical Specification 6.8.1 requires that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A to Regulatory Guide 1.33, Revision 2. Licensee Operations Procedure OP/1/B/6100/10X requires operator actions upon receiving the alarm for the Auxiliary Building Ventilation High Radiation Monitor, EMF-41.

Contrary to the above, on January 5,1987, operators did not take actions after receiving the EMF-41 alarm and failed to follow the procedure.

This is a Severity Level IV Violation (Supplement I).

8702190170 E70206 PDR ADOCK 05000413 G

PDR

Duke Power Company 2

Docket Nos. 50-413 and 50-414 Catawba 1 and 2 License Nos. NPF-35 and NPF-52 C.

Technical Specification 3.3.2 requires the licensee to have Engineered Safety Features Actuation System instrumentation channels operable as shown in Table 3.3-3.

The table identifies the Containment Pressure - High and Containment Pressure - High-High actuation instrumentation as a requirement for Operational Modes 1, 2 and 3.

Three total channels of Containment Pressure - High are a required condition of operability and the action statement requires the licensee to place an inoperable channel in the tripped condition within one hour.

Four total channels of Containment Pressure - High-High are a required condition of operability and the action statement requires an inoperable channel to be placed in the bypassed condition.

Contrary to the above, from November 19, 1986 to December 6, 1986, while the unit was in Operational Modes 1 and 2 and one channel of containment pressure inoperable due to its transmitter being isolated, the licensee did not place the inoperable Containment Pressure - High channel in the tripped condition and the inoperable Containment Pressure - High-High channel in the bypassed condition.

This is a Severity Level IV Violation applicable to Unit 1 only.

(Supple-menti).

Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit to this Office within thirty (30) days of the date of the letter transmitting this Notice a written statement or explanation in reply including :

(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 viola-tions, and (5) the date'when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed by Luis A. Reyes Luis A. Reyes, Acting Director Division of Reactor Projects Dated at Atlanta, Georgia this 6th day of Feb. 1987

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