ML20004D023
| ML20004D023 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/24/1981 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20004D022 | List: |
| References | |
| 50-368-81-05, 50-368-81-5, 50-513-81-06, 50-513-81-6, NUDOCS 8106080174 | |
| Download: ML20004D023 (3) | |
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APPENDIX A NOTICE OF VIOLATION Arkansas Power and Light Company Docket Nos: 50-313; 50-368 Arkansas Nuclear One License Nos: DPR-51; NPF-6 Based on the results of the NRC inspection conducted during the period March 2-13, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980), the following violations were identified:
A.
Failure to Review Emergency Procedures Criterion V of 10 CFR Part 50, Appendix B, states that activities affecting quality shall be prescribed by documented instructions or procedurec and shall be accomplished in accordance with these instructions or procedures.
Licensee Procedure 1023.08 requires that licensed operators shall review the abnormal and emergency operating procedures not less than twice each year.
Contrary to the above, for Unit 1, one licensad operator had not completed a review of abnormal and emergency operating procedures in 16 months; another operator had not completed the review in 28 months; and two other operators had not completed the review in 33 months.
For U:it 2, one operator had not reviewed abnormal and emergency operating i rocedures in 13 months, and another operator had not completed the review u 1; months.
This is a Severity Level V violation (Supplement I.E.).
(313/8106-01; 368/8105-01)
B.
Failure to Perform Surveillance Testing For Unit 1, Licensee Technical Specification 4.10.2 covering surveillance of the Control Room Emergency Air Conditioning and Isolation System states:
"At intervais not to exceed 18 months, automatic initiation of the Control Room Emergency Air Conditioning and Isolation System shall be demonstrated to meet the requirements of Specification 3.9."
Subsection 3.9.1.f of Specification 3.9 states:
"The dampers shall isolate the Control Room within 10 seconds after receipt of a high radiation signal."
Contrary to the above, Licensee Procedure 1104.34, Revision 2, governing the conduct of this test does not specify or document that the dampers isolate the control room within 10 seconds.
The procedure does document that air is available to operate the dampers to isolate the Control Room, and that the dampers are closed, but not the timing of closure within 10 seconds.
810608017y
Arkansas Power and Light Company 2
This is a Severity Level V violation (Supplement I.E.). (313/8106-02)
C.
Failure to Follow Procedures Criterion V of 10 CFR Part 50, Appendix B states that activities affecting quality shall be prescribed by documented instructions and shall be accomplished in accordance with these instructions.
1.
For Unit 1, Licensee Procedure 1004.12A states that, "all surveillance calibration, checks, inspections, tests required by Section 4 of the Technical Specifications are specified on the Master Test Control List" (Attachment A to Procedure 1004.12).
Contrary to the above, certain surveillances required by Section 4 of the Technical Specifications are not specified on the Master
. Test Control List, but are specified on the Unit 1 Reactor Plant Tests and Frequency List.
2.
Licensee Procedure 1000.06, Revision 2, " Procedure Review, Approval and Revision Control," requires the independent reviewer for safety-related procedures to complete Form 1013.02M, " Deletion to Station Procedures," if the procedure reviewed supersedes any other procedure.
Contrary to the above, the licensee issued Procedure 1305.06, Revision 0, " Integrated Engineered Safety System Test," for Unit 1 without completion and issuance of Form 1013.02M for superseded Procedure 1304.08, Revision 3.
3.
For Unit 1, Licensee Procedure 1004.12A, Revision 6, Change 2, in Attachment B, limits the surveillance test periodicity for calibra-tion of the hydrogen concentration instrument to an " interval not to exceed 18 months."
Contrary to the above, at the time of the inspection these instruments had not been calibrated since April 19, 1979, an interval exceeding 18 months.
This is a Severity Level V violation (Supplement I.E.).
(313/8106-03)
D.
Failure to Perform Surveillance Testinq Within Prescribed Frequency j
For Unit 1, Technical Specification 4.11, " Penetration Room Ventilation System Surveillance," subparagraphs 4.11.1 and 4.11.4a state:
l "4.11.1 At intervals not to exceed 18 months, the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 6 inches of water at system design flow rate (+ 10%).
IArkansas-Power and Light Company-3-
"4.11.4a.The tests and sample analysis of Specification 3.13.la, b,
& c. shallibe performed at intervals not to exceed 18 months or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation and following significant painting, fire or chemical release in any ventilation zone communi-cating with the: system."
Contrary to.the above, the licensee had these tests performed on or about August.31, 1977, April.24, 1979 and January 19, 1981; the resulting intervals
.between tests exceeds the requirement of "not to exceed 18 months."
This is:a Severity Level IV violation (Supplement I.D.2.).
(313/8106-04)
Pursuant to the provisions of 10 CFR Part 2.201, Arkansas Power and Light Company is hereby required to submit to this office within 25 days of the date of this Notice, a written statement or explanation in-reply, including:
~(1) the' corrective steps which have been taken at.a the results achieved; (2) corrective steps which will be taken to avoid further violations; and
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(3).the date when full compliance will be achieved.
Under the authority of Section 182 of the Atomic Energy Act of 1954, lui amended, this~ response shall be' submitted under oath or affirmation.
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Dated G. L. Madsen, Chief Reactor Projects Branch 4
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