ML20138N166

Notice of Violation from Insp on 851006-1105

ML20138N166
Person / Time
Site:	Sequoyah
Issue date:	12/10/1985
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20138N155	List: ML20138N150 ML20138N166 ML20138N206
References
50-327-85-35, 50-328-85-35, NUDOCS 8512230397
Download: ML20138N166 (2)

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. ENCLOSURE 1

>+ NOTICE OF VIOLATION

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. Tennessee; Valley Authority Docket Nos. 50-327 and 50-328

Sequoyah

Units 11--and 2 License Nos. DPR-77 and DPR-79<

1Thei:following' violation was identified during -an inspection conducted on

- October 6, - 1985 ~-. November 5,. 1985. The?SeverityH Level was assigned -in

. accordan'ce~with,the NRC Enforcement Policy (10CFR Part.2 Appendix C).

~ * (Technical _: Specification - 6.8.1 -requires that written procedures .be

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• simplemented and' maintained covering -safety-related activities stated in

. Appendix'A'of' Regulatory Guide'1.33, Revision 2. ,

fa. LIn~strument Maintenance.. Instructions IMI-99 RT' 611A, . Response Time

. .  : Testing Engineered Safety Feature Actuation, IMI-99 RT 7.23,' Response

.-Time Test Loop 4 Steam Generator Level Channel . III (L-548) andl IMI-99

' lRTo7.17, - Response Time oTest Loop. 2 Steam Generator Level Channel III

-(L-528),were established to perform reactor trip response time testing.  !

?RT 611A Step 5.5.6. requires that: components which are not returned to -

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- normal? position 'be listed in the data - sheet cover page as _ discre- ,

spancies; .RT 7.17 and RT 7.23 require that status 111ghts be verified in '

a'non" illuminated condition except.as allowed ~under Step 2.

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Contrary to Lthe ' above, ^ the subjectfprocedures were 4not adequately

-implemented in that' components required to be returned, to a normal a' . position _ by) Step .5.5.6 ..in ' procedure; IMI-99 RT 611A had not been -

returned <to; normal, position and-had not been.!isted as discrepancies in the data _~ sheet. Also, verification.of status lights' had not been. made

'in accordance with: procedures IMI-99 RT 7.17 and IMI-99 RT 7.23.

b .~ : Administrative Instruction _ AI-19, . Part 4 . Plant Modifications Af ter s Licensing, was established to . implement the use of Work Plans on major modification efforts 'on safetyrelated fequipment. Work Plan .11802

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provided the procedure for .~ assembly and- testing of safety-related

containment penetrations and -required the .use 'of a validated vendor's

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4 , imanual'in the assembly of the feedthru tubes.

'; , - Contrary- to the Labove, Work Plan- 11802 was not adequately established -

or" implemented in'that;the licensee-assembled the penetration without n

'?x . the'use of a validated vendor manual.

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c.  ; Surveillance Instruction, SI-82.2 - Functional- Tests for the Radiation Monitoring System, was; established to implement Technical Specification radiation monitoring surveillance requirements.

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Tennessee Valley ~ Authority 2 Docket Nos. 50-327 and 50-328 Sequoyah Units 1 and 2 License Nos. DPR-77 and DPR-79 Contrary to - the above, S1 -82.2 was not implemented in that the technician did not insert a test signal into the Unit 2 radiation monitor identified by the procedure. Instead, the technician inserted the test' signal into the Unit 1 monitor causing a containment ventilation isolation,

d. . Instrument Maintenance Instruction IMI-134, Configuration Control . of Instrument Maintenance Activities, was established to control ~ work

. activities during safety related maintenance. ,

Contrary to the above, IMI-134 was not implemented in that a technician failed to adequately identify' the power . source for removal and

reinstallation of spent fuel pool radiation monitor 0-RM-90-103 on the-configuration control sheet. This resulted in plugging the monitor into a non-safety-related power source.

lThis is a . Severity Level' IV violation (Suppiement I). This violation applies to both units.

o 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 o'r explanation in reply, including : (1) admission or denial of the alleged violations; (2) the reasons

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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: DEC 101985

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