ML19323H498
| ML19323H498 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/20/1980 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19323H495 | List: |
| References | |
| NUDOCS 8006130053 | |
| Download: ML19323H498 (2) | |
Text
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Q DUKE POWER COMPANY r7' Powen Dunwswo 422 Socrn Cnencu STarzT, CRAnwTTz, N. C oa4a
' [ ' ' 'i '/ / 5ll*.$b WILLIAM O. PA R M E R,.J R.
Wer Passierwt Tttre c=c Anta 704
$vtano PacowCTiON 373-4083 May 20, 1980 J. P. O'Reilly, Director U.S. Nuclear Regulatory Commission Region II 101 Marietta St., Suite 3100 Atlanta, GA 30303 RE: RII:WPK 50-413/80-06 50-414/80-06
Dear Mr. O'Reilly:
Please find attached a response to Deficiency 50-413/80-06-01 which was identified in the above referenced Inspection Report. Duke Power Company does not consider any information contained in this inspection report to be proprietary.
In the exit interview conducted by W. P. Kleinsorge of your office following his in-spection of April 1-4, 1980, we committed to supply a supplemental response to In-fraction 50-413/79-23-01. This infraction dealt primarily with inadequate controls over rigging from permanent tubular steel cable tray support steel. In this regard, a site construction. procedure has been generated to control rigging by the crafts from permanent tubular steel cable tray support steel. This procedure provides a
" permit system" approach to rigging such that proposed loads and rigging arrange-ments are approved prior to rigging. This additional procedure has been fully im-plemented.
Very truly your j
W. O. Parker, Jr.
Vice President, Steam Production ROS/mp Attachment ec:
Mr. G. F. Maxwell (NRC, Catawba Const.)
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S 0 0 618 0 C O i
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o DUKE POWER COMPANY CATAWBA NUCLEAR STATION RESPONSE TO DEFICIENCY 50-413/80-06-01
" Failure to Provide Identifiable Heat Number On Weld Report" Deficiency As required by 10 CFR 50, Appendix B, Criterion XVII and as implemented by Duke Power Company (DPC) Topical Report " DUKE l-A" Section 17 paragraph 17.1.17 "---Records shall te maintained to furnish evidence of activities affecting quality.---Records shall be identifiable and retrievable."
Contrary to the above, on April 4, 1980 the heat number for a one inch special welding flow orifice boss installed into the reactor coolant system by weld 1-NC-33-7 was not identifiable on the " Weld Process Control Sheet" for that weld joint.
Response
The weld process control sheet identified a problem with an illegible heat code for adjacent piping material for weld number 1-NC-33-7.
The subject record has been re-examined and a legible heat code has been re-established.
Personnel involved in the recording, inspection, and approval of weld j
process control records in the area of material traceability shell be in-1 structed in the importance of traceability requirements and legible record-ing of alpha and numeric characters. Full compliance will be achieved by June 20, 1980.
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