ML20205H305

Notice of Violation from Insp on 860506-0605

ML20205H305
Person / Time
Site:	Sequoyah
Issue date:	08/12/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20205H303	List: IR 05000327/1986031 ML20205H298 ML20205H305 ML20205H320
References
50-327-86-31, 50-328-86-31, NUDOCS 8608200048
Download: ML20205H305 (2)

Text

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e ENCLOSURE 1 NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-327 and 50-328 Chattanooga, TN License Nos. DPR-77 and DPR-79 The following violations were identified during an inspection conducted on May 6, 1986 - June 5, 1986. The Severity Level was assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

1. Technical Specification 6.12 states that in lieu of the control device or alarm signal required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Special (Radiation) Work Permit (SWP).

Contrary to the above, on April 30, 1986, the licensee failed to barricade and conspicuously post a high radiation area. Specifically, an entrance to a high radiation area inside the polar crane wall in lower containment was not barricaded and there was no conspicuous posting ut the area. A high radiation sign had been placed on the door to the area, however, the door had been opened to the point where the sign was not visible until after entry into the area.

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

2. 10 CFR 50, Appendix B, Section V requires that activities affecting quality be prescribed and that the applicable instructions, procedures, or drawings include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.

Contrary to the above, the configuration of trip contacts 17/18 and 21/22 on alternate breaker 58, located on shutdown board 1Al-A, was not addressed in the acceptance criteria of step 2.4.5 of Work Plan 11871. As a result, these contacts were not adequately controlled. Mispositioned contacts 17/18 caused in an interlocked trip of the normal breaker 1B, resulting in a loss of power to radiation monitor RM-90-101 and an Auxiliary Building Isolation (ABI).

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

3.Section XVI, " Corrective Action" of 10 CFR 50, Appendix B requires that significant conditions adverse to quality, such as deficiencies, deviations, defective material and equipment be promptly identified and corrective action taken be documented and reported to appropriate-levels of management.

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Tennessee Valley Authority 2 Docket Nos. 50-327 and 50-328 Chattanooga, TN License Nos. DPR-77 and DPR-79 Contrary to the above, the licensee failed to take appropriate corrective action for test deficiencies on preoperational tests. Deficiency DN-1 for Unit 1 preoperational test procedure W-11.7, Revision 0, Calibration of Steam and Feedwater Flow Instruments at Power, involved flow instrumenta-tion which did not meet the test acceptance criteria at 75% and 100%

thermal power. The test portions required to be repeated by the Office of Engineering interim approval of the deficiency were never performed.

Subsequently, the Unit 1 deficiency was not adequately addressed by the licensee in the followup deficiency resolution. In addition, the _ test deficiencies and exception noted in the performance of W-11.7 on Unit 2 were inadequately addressed in their resolution. Unit 2 Deficiency DN-1 consisted of the licensee's inability to obtain adequate zero power feed-water flow indications due to the failure to backfill the special test feedwater flow detectors. Unit 2 deficiency DN-2 was written to document the licensee's failure to meet the required test acceptance criteria for calibrating the feedwater and steam flow process instrumentation at 75% and 100% thermal power. The licensee also took exception to performing the calibration adjustments necessary to bring the flow instrumentation within specifications and to performing the calibration repeatability check specified in the W-11.7 test acceptance criteria.

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

Pursuant to 10 CFR 2.201, you are required to submit to this of fice within 30 days of the date of this Notice, a written statement or explanation in reply, including : (1) admission or denial of the alleged violatiors; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and, (5) the date when full compliance will be achieved.

Security or safeguards information should be submitted as an enclosure to facilitate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.

Date: AUG 121986