ML20041A298
| ML20041A298 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/01/1982 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20041A296 | List: |
| References | |
| 50-382-81-30, NUDOCS 8202190394 | |
| Download: ML20041A298 (2) | |
Text
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APPENDIX A NOTICE OF VIOLATION Louisiana Power and Light Company Docket No. 50-382 CPPR-103 Based on the results of an NRC inspection conducted during the period of November 16-December 15, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7,1980), the following violations were identified:
Criterion V of 10 CFR 50, Appendix B, states that activities affecting quality shall be prescribed by instructions, procedures or drawings of a type appropriate to the circumstances and that these activities shall be accomplished in accordance with these instructions, procedures or drawings.
1.
Section 6.3.1.1 of Tompkins-Beckwith Procedure TBP-29, " Piping System Cleanliness Procedure," requires that during receipt, transportation, handling, and installation, openings and pipe ends shall be sealed at all times except when they must be unsealed to carry out necessary operations.
Contrary to the above, on December 3, 1981, the NRC inspectors observed the following:
a.
Component Cooling Water Pipe 3CC4-56A2-1 had not been sealed after being disconnected from Reactor Coolant Pump 2A. The corresponding pipe ends on the Reactor Coolant Pump 2A had also not been sealed.
b.
The openings on Pressurizer Spray Pipe IRC3-138, which had not been completed, were not sealed on the +46-foot level in the pressurizer room.
This is a Severity Level V Violation.
(SupplementII.E.)
2.
Ebasco Care and Maintenance Instruction #31 R7 requires that a dry nitrogen blanket or purge be maintained on the pressurizer.
Ebasco Care and Maintenance Instruction #32 R7 requires that a dry nitrogen purge be established on the secondary side of the steam generators after the main steamand feedwater piping has been connected to the secondary side nozzles.
Contrary to the above, on November 24, 1981, the NRC inspectors observed the following:
a.
The pressurizer had neither a nitrogen blanket or purge established.
b.
The steam generators did not have a nitrogen purge established after the main steam nd feedwater piping was connected to the secondary side a
nozzles.
This is a Severity Level V Violation.
(SupplementII.E.)
8202190394 820201 PDR ADOCK 05000382 G
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3.
Startup administrative procedure SAP-10. " Temporary System Modification,"
in section 4.4.1.1 requires that electrical jumpers, bypasses, and lifted electrical leads be documented as. temporary modifications if the modifi-cation is to be left in place beyond a single shift.
Contrary to the above, on November 11, 1981, the NRC inspectors observed the following where an electrical jumper, bypass, and lifted electric leads had not been identified by a temporary modification tag:
a.
A temporary electric receptacle had been connected to Power Distribution Panel 362-SAB in 480V MCC3AB 311-S.
b.
Cable 3256X-SAB leads had been lifted in Power Distribution Panel 3AB-DC-S and a jumper from a temporary panel connected to the terminals from which the leads had been lifted.
In each case stated above, the modification had not been returned to the original condition at the end of the shift.
This is a Severity Level IV Violation.
(Supplement II.D.)
Pursuant to the provisions of 10 CFR 2.201, Louisiana 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 items of noncompliance; and (3) the dcta 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.
Dated February 1, 1982
'G.
L. Madsen, Chief Reactor Projects Branch
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