ML20205P407

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Notice of Violation from Insp on 860303-14
ML20205P407
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 04/23/1986
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20205P381 List:
References
50-327-86-20, 50-328-86-20, NUDOCS 8605210399
Download: ML20205P407 (2)


Text

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ENCLOSURE 1 NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-327 and 50-328 Sequoyah Units 1 and 2 License Nos. DPR-77 and DPR-79 i

The following violations were identified during an inspection condected on March 3-14, 1986. The severity levels were assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

1. Technical Specification (TS) 6.8.1.c requires that written procedures be established and implemented for surveillance of safety related equipment.

Contrary to the above, a written procedure was not established for surveil-  !

lance requirement of TS 4.3.1.1.1, Table 4.3-1, item 19, note (4), which requires a manual engineered safety feature (ESF) functional input check of the reactor trip system every 18 months. This involved one missed relay on each of two multicon*act switches. As such, a functional check of these relays was not conducted.

This is a Severity Level IV violation (Supplement I). (Both unit 3)

2. Technical Specification 4.6.1.1.a requires verifying the proper positioning of all containment isolation valves, with the exception of energized automatic isolation valves, while operating in mode 4 _or above. This verification is required at least every 31 days and prior to heat up to mode 4 from mode 5 for each cold shutdown.

Contrary to the above, in Unit 1, 20 vent, drain and test Containment Isolation Valves were not verified to be in the proper position when SI-14, Verification of Containment Integrity - Unit 1, was performed on May 20, 1985 prior to heat up to mode 4 and while in mode 4 on May 17,1985; June 3, 6,19 and 27,1985; and July 25, 1985. This involved Containment Isolation Valves62-707, 70-735,70-737, 70-678B, 70-691B, 70-702B,C,E & F,70-703, 70-760,70-762, 70-763, 72-546, 72-554, 72-543, 72-545, 78-226A, 78-228A and 87-523.

This is a Severity Level IV violation (Supplement I). (Unit 1 only)

3. Technical Specification 6.5.1.2 requires that the Plant Operations Review Committee (PORC) be composed of the Chairman, and six other members. TS 6.5.1.3 states that no more than two alternates shall participate as voting members in PORC activities at one time. TS 6.5.1.5 states that the minimum quorom of the PORC necessary for the performance of the PORC responsibility and authority ... shall consist of the chairman or his designated alternate and four members including alternates.

8605210399 860423 7 PDR ADOCK 0500 G

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Tennessee Valley Authority Docket Nos. 50-327 and 50-328 Sequoyah Units 1 and 2 2 License Nos. OPR-77 and DPR-79 4

Contrary to the above, the Sequoyah procedure implementing the above

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requirements, SQA21, provided for a PORC composition of the Chairman and eight members. The two " extra members," beyond the TS required composition,-

could legally function as alternates, but were recognized by the licensee as members. The two " extra members" resulted in the quorum requirements being violated with respect to PORC members present during Meetings 3351, 3364, 3367, 3378, 3381, 3389 in May 1985. The persons serving as the " extra 4

members" do meet ANSI N18.1 qualifications.

l This is a Severity Level V violation (Supplement I). (Both units) i Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply, 1 including: (1) adr-ission or denial of the alleged violations; (2) the reasons for l 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 l facilitate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.

Date: APR 2 3 E86 1

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