ML20009G638
| ML20009G638 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 05/22/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20009G635 | List: |
| References | |
| 50-327-81-07, 50-327-81-7, NUDOCS 8108040502 | |
| Download: ML20009G638 (2) | |
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4 APPENDIX A I
Tennessee Valley Authority Docket No. 50-327 j
Sequoyah 1 License No. DPR-77 As a result of the inspection conducted on February 11-19, 1981. and in i
accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980),
j the foilowing violations were identified.
A.
Technical Specification 6.4.1 requires that a retraining and replacement training program be established and implemented for the unit staff, including non-licensed personnel, which meets or exceeds the requirements and recommendations of Section 5.5 of ANSI N18.1-1971.
Contrary to the above, as of February 19., 1981, adequate training was not provided to Auxiliary Unit Operators (AUO's) prior to AUO's being permitted to perform independently on watch without first demonstrating proficiency for the watchs+ation.
On February 11, 1981, with the reactor at cold q
shutdown inadequate on-the-job training for an on-watch AVO contributed to j
inadvertent actuation of containment spray from the RHR system, i
l This is a Severity Level IV Violation (Supplement I.D.3.).
B.
Technical Specification 6.8.1.a, requires that procedures be established and implemented in accordance wi th..the recommendations of Appendix A of Regulatory Guide 1.33, Revision 2, dated February 1978.
Item 3.C of Appendix A identifies plant procedures to be established and implemented for changing the status of the Residual Heat Removal (RRR) Systen.
This i
procedure requires RHR containment spray valve 72-40 to be normally closed i
except during post accident conditions 1
Contrary to the abcve, on February 11, 1981, the appropriate procedures were not implemented / utilized as re auired as a result during realignment of the RHR system, RHR spray valve 72-d was misaligned in the open position by the I
on-watch Auxiliary Unit Operator, which in turn resulted in the inadvertent actuation of containment spray, causing approximately 105,000 gallons of water to be sprayed into contain.nent.
J This is a Severity Level V Violation (Supplement I.E.).
C.
Technical Speci fic.atiun 6.8.1.a. requires that procedures be established and implemented in accorcance with the recommendations of Appendix A of l
Regulatorv Guide 1.30, Revision 2, dated February 1978.
Item 1.8 of i
Appendix A identifies procedures to be established and implemented that specify personnel authorities and responsibilities for the safe. operation and shutdown of the plant.
8108040502 810522 DR ADOCK 05000327 PDR
s Tennessee Valley Authority Docket No. 50-327 Notice of Violation License No. DPR-77 Contrary to the above, as of February 11, 1981, administrative procedures did not clearly delineate authorities and responsibilities for all operations personnel, specifically AUO's, involved in safety-related activities.
This is a Severity Level V Violation (Supplement I.E.).
Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within twenty-five days of the date of this Notice, a written state-ment or explanation in reply, including: (1) admissica or denial of the alleged violations; (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. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this resporise shall be submitted under oath or affirmation.
MAY 2 21981 Date:
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