ML19322B986
| ML19322B986 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/01/1971 |
| From: | Jennifer Davis US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Thies A DUKE POWER CO. |
| Shared Package | |
| ML19322B984 | List: |
| References | |
| NUDOCS 7912200703 | |
| Download: ML19322B986 (4) | |
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[gN,%h'Mb ATOMIC ENERGY COMMISSION UNITED S*ATES
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ATaANY4 In Eeply Refer To:
Cctober 1, 1971 CO :II:CIM 50-269/71-7 Duke Power Cc=pany Atta:
Mr. A. C. Thies, Senior Vice President Production and Trans=issica Power 32ilding k2? South Church Street Charlotte, North Carolina 28201 Gentle =rn:
This re.fers to the inspection ecnducted t/ Mr. Murphy of this office and other Division of Cc=p31ance staff =e=bers en June 28 and 29,- 1971, July 29 to August 1,1971, and August h,1971, of activities authorized by AEC Cen-struction Per=it No. CPPR-33 and to the discussiens of our findings held by Mr. Murphy with Mr. S=ith and other =e=bers of your staff at the cen-clusion of the inspection.
Areas exanined during this inspectien included witnessing the reactor building: structural integrity test, a review of cperations prior to and at the ti=e :the control rod drive =echanis=s were de= aged, a review cf your investigations of this occurrence and of your plans to prevent recurrence.
In additien, quality control records, turbine building velding, and safety feature valves were inspected. Within these areas, the inspection con-sisted of interviews with plant a=d vender personnel, selective exa-Ma-tiens of procedures and representative records, and observations by the inspector.
Curing this inspection, it was found thr_t certain of your activities appeared to be in nonco=pljance with AIO require =ents.
"he ite: and ref-erence to pertinent require =ents is listed in the enclosure to this letter.
Please provide us within 30 days, in writing, with your ec=ents eencerning this ite=, any steps which have been er vill be taken to correct it, a:r/
steps that have been or vill te taken to prevent recurrence, a=d the date all corrective action or preventive measures were or vill te cc=pleted.
i Curing this inspecticn, cur inspector was advised that additional nendes-tructive: tests will be =ade of turbine building structural velds and that these velds found not to =eet applicable ccde -require =ents vill te repaired.
Sis =atter vill be exa=ined by us during a subsequent inspection.
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- Mr s
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Duke Power Cc=pany Cetcher 1, 1971 Concerning the proble=s 4th the control red drive =ech::.nis=s, it is our understanding that you vill suh=it a repcrt to the Divi.11cn of Reactor Licensing including the details of the events leading to the occurrence, the analyses of the effects of the improper cperation en the =echanis=s, and the steps being taken to prevent recurrence of this type occurrence.
Should you have any questions concerning this letter, you =ay cc==unicate directly with this office.
Very truly yours,
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John G. Davis
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Enclosure:
Description of Itc=
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e ENCILSURE Dccr.ET NO. 50-269
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Certain activities under your license appear to be in noncempliance with license require =ents as listed belev:
Criterion VIII of Appendix 3 to 10 CFR 50, " Identification and Con-trol of Materials, Parts, and Components," requires that =easures shall be established to assure that identification of materials, parts and components is maintained by heat number or other appro-priate means as required throughout the fabrication, erection, in-stallation and use of the ites. These control reasures shall be designed to prevent the use of incorrect or defective =aterials, parts and components.
Contrary to the above, our inspector's review of +he quality control records showed that the records were insufficient to permit identi-fying piping and pipe fittings to assure that incorrect or defective eo=ponents were not used. In particular, when the inspector exc=ined Isometric Draving 51A, Sheets 1 and 7, it was observed that no heat numbers were available for numerous pipe sections and fittings.
Additionally, eight recorded heat nu=bers were not traceable to quality data packages. (Isc=etric Draving 51A is the control docu-ment vhich is us#ed to correlate quality records to installed parts and components.) Discussions by Mr. Murphy with Messrs. Hunnicutt and Sibley of your staff indicate that the observed deficien_ies are typical of other portions of the high pressure injection syste= and otner safety-related syste=s.
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