ML20010F303
| ML20010F303 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/09/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20010F300 | List: |
| References | |
| 50-327-81-22, NUDOCS 8109100022 | |
| Download: ML20010F303 (2) | |
Text
,-
APPENDIX A NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-327 Sequoyah 1 License No. OPR-77 As a result of tne inspection conducted on May 19-22, 1981, and in accordance with the Int"
'forcement Policy, 45 FR 66754 (October 7,1980), the following violations t
..ntified.
A.
10 CFR 50, Appendix B, Criterion V, and Section 17.2.5 cf the accepted QA program require that procedures and instructions prescribing operarional activities that affect safety-related functions provide applicable quanti-tative and qualitative acceptance criteria. Section 4.5 of Part_II of the Operational Quality Assurance Manual requires that acceptance criteria shall be included in the surveillance instruction, and test or inspection data shall be compared with these criteria as a basis for acceptance or rejec-tion.
Contrary to the above, instructions prescribing ooerational activities that affect safety-related functions did not provide applicable quantitative and qualitative acceptance criteria in that surveillance instruction SI-2 did not include quantitative and qualitative acceptance criteria.
Conse-quently, pressurizer level channel LI-68-339A was inoperable on April 2, 1981, but was not placed into trip, as required by Technical Specification 3.3.1.1, until the inoperable condition was identified by an NRC inspector.
This is a Severity Level IV Violation (Supplement I.F).
B.
10 CFR 50, Appendix B, Criterion V requires that activities affecting quality shall be accomplished in accordance with instructions.
Section 17.2.3 of the accepteci QA program requires that instructions shall be implemented to assure that modifications meet quality assurance standards at least equal to those of the original installation. The safety evaluation for Work Plan 9117 which recalibrated pressurizer level channel LT-68-339 included special requirement 2 which required that the level indication of channel 68-339 to be compared once per shift to the other two level channels (335 & 320) to confirm that the relationship was unchanged.
Contrary to the above, the safety evaluation was inadequate in that it assumed without confirmation that adequate, quantified surveillance instruc-tions existed when in fact they did not.
This is a Severity Level IV Violation (Supplement I.F).
O meetA esooowi 9OS
- g Tcnnessee Valley Authority 2
Docket Nos. 50-327 S:quoyah 1 License No.' DPR-77 Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within thirty days of the date of this Notice, a writt6n statement or cxplanation in reply, including: (1) admission or denial of the alleged viola-tions; (2) the reasons for the violations if admitted; (3) the correctivo steps which have been taken and the results achieved; (4) corrective steps which will be taken tc avoid further violations; and_(5) the date when full compliance will l
be achieved. Consideration may be given to ex.anding your response time for good cause shown.
Under the authority of Section 162 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under cath or affirmation.
Date:
l I
k a
9 9
9
+
-, - -.,