ML20199C757

Notice of Violation from Insp on 860407-11 & 21-25

ML20199C757
Person / Time
Site:	Fermi
Issue date:	06/13/1986
From:	Paperiello C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20199C748	List: IR 05000341/1986011 ML20199C745 ML20199C757
References
50-341-86-11, NUDOCS 8606180241
Download: ML20199C757 (2)

Text

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i NOTICE OF VIOLATION i l

Detroit Edison Company Docket No. 50-341 Enrico Fermi Nuclesr Power Plant, Unit 2 As a result of the inspection conducted on April 7-11 and 21-25, 1986, and in )

accordance with the " General Policy and Procedures for NRC Enforcement Actions," l 10 CFR Part 2, Appendix C (1985), the following violations were identified:

1. Technical Specification Limiting Condition for Operation 3.4.2.2 requires the low-low set function for safety relief valves F013A and F013G to be operable in Operational Conditions 1, 2 and 3. Technical Specification Section 4.4.2.2 requires performance of a channel functional test at least once every 31 days and a channel calibration test at least once every 18 months on the low-low set function pressure actuation instrumentation for safety relief valves F013A and F013G. Technical Specification Section 4.0.4 states, " Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the surveillance requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified".

Contrary to the above, channel functional tests were not performed during the 31 days prior to achieving criticality (Operational Condition 2) on June 21, 1985, and two of four calibrations were not performed on June 27 and 29, 1985, as required. Failure to perform the functional tests and calibration resulted in the low-low set function pressure actuation instrumentation for safety relief valve F013G being inoperable from June 21 to July 3,1985, with the plant in Operational Conditions 2 and 3.

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

l

2. Technical Specification Limiting Condition for Operation 3.4.3.1.b requires the primary containment sump flow monitoring system to be operable in Operational Conditions 1, 2 and 3. Technical Specification Surveillance Requirement 4.4.3.1.b requires performance of a channel functional test at least once per 31 days and a channel calibration test i at least once per 18 months on the primary containment sump ficw and drywell floor drain sump level monitoring systems. Technical Specification Section 4.0.4. states, " Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified."

Contrary to the above, on September 13, 1985, and four occasions prior to that date, the unit entered into Operational Conditions 2 and 3 without the following:

8606100241 860613 PDR APOCK 05000341 0 PDR

Notice of Violation 2

a. Performance within the previous 31 days of channel functional tests for the drywell equipment drain sump pump-run-time system, the equipment drain sump pump-run-time system, the drywell floor sump level, and the drywell equipment drain sump level.

b. Performance within the previous 18 months of channel calibration tests for the drywell equipment drain sump pump-run-time system, the equipment drain sump pump-run-time system, and the drywell equipment sump level.

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

3. 10 CFR 50 Appendix B, Criterion XVI, as implemented by the licensee's Operational Quality Assurance Program Requirements' Document QAPR-18 and Nuclear Quality Assurance Procedure NQAP-1601, requires that measures be established to assure that conditions adverse to quality are promptly identified and corrected.

Contrary to the above, the licensee failed to take prompt and timely corrective action on 25 audit findings that have been open from 6 to 18 months. Typical examples include audit finding Nos. A-QS-84-27-01 (18 months), A-QS-84-34-01 (17 mcnths), A-QS-84-34-02 (17 months),

A-QS-85-10-10 (12 months), and A-QS-85-35-01 (6 months).

This is a Severity Level IV violation (Supplement I). -

Pursuant to the provisions of 10 CFR 2,201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation: (1) corrective action taken and the results achieved, (2) corrective action to be taken to avoid further violations, and (3) the date when full compliance will be achieved.

Consideration may be given to extending your response time for good cause shown, h l} hhI

/ W't<.L Y Dated / CarlJ.[/ Paper $110, Director Division of Reactor Safety