ML20039D116
| ML20039D116 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/08/1981 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20039D115 | List: |
| References | |
| 50-313-81-30, 50-368-81-29, NUDOCS 8112310332 | |
| Download: ML20039D116 (3) | |
Text
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DESIG"ATED ORIGIllAL Certific? Ty_
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' NOTICE OF VIOLATION Arkansas Power and Light Company Dockets: 50-313/81-30 50-368/81-29 Arkansas Nuclear One, Units 1 and 2 Licenses:
DPR-51 NPF-6 Based on the results of an NRC inspection conducted during the period of October 22 - November 21, 1981, and in accordance with the Interim Enforcement Policy 45 FR 66754 (October 7, 1980), the following violations were identified:
1.
Unit 2 Technical. Specification 6.8.1 requires that, " Written procedures shall be established, implemented, and maintained covering... a.
The applicable procedures recommended in Appendix "A" Regulatory Guide 1.33."
Operating Procedure 2102.01, Attachment E, " Category E Valve Position Verification," has been established in accordance with this Technical Specification.
Attachment E of Operating Procedure 2102.01 requires that manual valve 25W-3B be locked open.
This valve is the "B" Service Water Pump discharge valve.
Contrary to the above, on October 27, 1981, the NRC inspector found that valve 2SW-38 was open as required, but was not locked.
This is a Severity Level V Violation.
(Supplement I.E) (368/8129-04) 2.
10 CFR 19.11 requires, in part, that the licensee post current copies of the license, license conditions, or documents incorporated into a license by reference, and amendments thereto.
Contrary to the above, on November 4,1981, the licensee did not have cur-rent copies of the Facility Operating Licenses posted or available else-where at the plant site.
This is a Severity Level V Violation.
(Supplement I.E) (313/8130-03; 368/8129-03) 3.
Criterion V to Appendix B of 10 CFR 50 states: " Activities affecting quality shall be prescribed by documented instructions, procedures or drawings, of a type appropriate to the circumstances and shall be accomplished in accord-ance with these instructions, procedures or drawings."
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. Design drawing 6600-E-16-3-5 shows the design configyration of the Unit 1 station battery racks. The seismic calculations for these racks are on drawing 6600-E-16-7-2.
Contrary to the above, on October 27, 1981, the NRC inspector found the following discrepancies in the north upper rack of the Unit 1 #1 Station Battery Bank:
Three polystyrene cell spacers missing One end rail missing One end rail secured at only one end Three of six required tie rods missing The other three tie rods not connected to rack This is a Severity Level IV Violation.
(Supplement I.D.3) (313/8130-04) 4 Criterion V to Appendix B of 10 CFR 50 states:
" Activities affecting qual-ity shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings."
Small pipe isometric drawing 2HCC-241-1 shows the locations of the seismic Class I critical pipe hangers on line number 2HCC-241-1.
Drawings M2807 and M2808 show the design configuration of hanger H-001-5 on this line.
This hanger was installed in early October 1981, under Job Order 15557, in response to violation 368/8128-04 Line 2HCC-241-1 is the service water return line from 2E52A, the "A" low pressure safety injection pump seal cooler.
Contrary to the above, on October 29, 1981, the NRC inspector found that the pipe clamp bolts on this hanger were all loose.
This is a Severity Level IV Violation.
(Supplement I.D.3) (368/8129-05) 5.
Unit 1 and Unit 2 Technical Specification 6.8.1 require that, " Written' procedures shall be established, implemented, and maintained covering... a.
The applicable procedures reccmmended in Appendix "A" Regulatory Guide 1.33."
Station Administrative Procedure 1000.06, " Procedure Review, Approval and Revision Control," has been established in accordance with this Technical Specification. of Administrative Procedure 1000.06 requires the independent reviewer for s3fety-related procedures to complete Form 1013.02M, " Deletion to Station Procedures," if the procedure reviewed supersedes any other procedure.
i
. Contrary to the above, the licensee issued the following Health Physics procedures without completion and issuance of Form 1013.02M for the superseded procedures:
New Procedure Superseded Procedure a.
1632.008 " Portal 1602.31 Monitors" b.
1632.009 " Condenser 1602.26 R-Meter" c.
1632.006 " Continuous 1602.22 Air Monitors" d.
1622.004 " Radiological 1602.17 and Survey Methodology" 1602.18 e.
1632.005 " Portable 1602.19 Air Samplers" f.
1612.010 " Decontamination" 1602.67 g.
1632.013 "Harshaw 2271 1602.50 TLD System Operation" This constitutes a Severity Level V Violation (Supplement I.E) (313/8130-02; 368/8129-02)
Pursuant to the provisions of 10 CFR 2.201, Arkansas Power and Light Company is hereby required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply, including (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved.
Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
Consideration may be given to extending your response time for good cause shown.
i Date:
December 8, 1981
/pg/)g S. L. Madsen, Chief Reactor Projects Branch 3