ML20040B849
| ML20040B849 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/16/1981 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20040B845 | List: |
| References | |
| 50-382-81-28, NUDOCS 8201260472 | |
| Download: ML20040B849 (2) | |
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X/ /A&Q APPENDIX A NOTICF 0F 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 October 16-November 15, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980), the following violations were identified.
1.
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.
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, from September 23-October 28, 1981, the NRC inspectors observed that both the suction and discharge lines for Fuel Pool Pump A had not been sealed.
Further investigation by the NRC inspectors revealed that the piping had been open since August 29, 1981, and that on September 25, and again on October 9, 1981, that Tompkins-Beckwith inspectors had completed surveillance reports indicating that all component openings in the area were capped or covered.
This is a Severity Level IV Violation.
(Supplement II.D.)
2.
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.
a.
Ebasco Procedure ASP-IV-18, " Receiving, Storage, Issuing and Control of Welding Electrodes and Filler Materials," requires that low hydrogen 0
type welding electrodes (7018) shall be stored in ovens at 225 F, +25 F, for a minimum of eight hours prior to issue or reissue.
At the end of each shift, or if the electrodes are exposed to ambient temperature for more than four hours, the undamaged electrodes are to be returned to the ovens.
Contrary to the above, the NRC inspectors observed that unused 7018 welding electrodes (about 50) had not been returned to the storage ovens after the end of the work shift.
Several of the unused 7018 welding electrodes were found on October 20, 1981, on a work platform by the Reactor Coolant Pump 2A and more were found adjacent to the Control Element Drive Mechanism Motor Generator A.
8201260472 811216 PDR ADOCK 05000382 PDR G
2 Also, on October 27, 1981, the NRC inspectors observed unused 7018 welding electrodes on a work platform and on the floor in the pipe i
chase area of the Fuel Handling Building on the +1-foot level after the end of the work shift.
b.
Section 6.4.6 of Ebasco Procedure ASP-IV-18, " Receiving, Storage, Issuing and Control of Welding Electrodes and Filler Materials,"
requires that electrode or rod stubs and damaged electrodes be deposited in designated, controlled containers.
Contrary to d.e above, (1) on October 20, 1981, the NRC inspectors observed that several damaged electrodes and stubs had been left on 4
a work platform by the Reactor Coolant Pump 2A.
Several damaged i
electrodes and stubs had been disposed of in a trash can by the equipment hatch in the Reactor Building on the +21-foot level.
(2) On October 27, 1981, the NRC inspectors observed damaged electrodes and stubs laying on a work platform and on the floor in the pipe chase area in the Fuel Handling Building on the +1-foot level.
This is the fourth instance where NRC has identified problems related to a failure to properly control weldir.g electrodes.
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 i
steps which will be taken to avoid further items of noncompliance; 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.
1 December 16, 1981 jg DM G. L. Madsen, Chief Reactor Projects Branch
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