ML19316A329
| ML19316A329 | |
| 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 | |
| ML19316A322 | List: |
| References | |
| NUDOCS 7912050899 | |
| Download: ML19316A329 (3) | |
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ATOMIC ENERGY COMMISSION l
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DIVISloN oF COMPLIANCE 3
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Ar ' A NT A. GEOncia 30303 In Beply Refer To:
October 1, 1971 CO :II:CE'I 50-269/71-7 l
Duke Power Company Atta:
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A. C. Thies, Senior Vice President
. Production and Tran: mission i
Power Building 422 South Church Street Charlotte, :!crth Carclina 26201 Gentleren:
a This refers to the inspection conducted by "r. :!urphy of this office and other Division of Cc=pliance staff cenbors on June 28 and 29,1971, July 29 to August 1,1971, and Augut.t 4,1971, of activities authorized by AEC Con-structic Ferrit 'o. CPPT-33 cnd to the discuscions of our findincs held l
by I'r. !:urphy with Mr. Smith end other members of your staff at the con-clusion of the inspection.
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Areas examined during this inspection included vitnessing the reactor bui'iding structural integrity test, a review of operations prior to and at the tire the centrol red drive rechenie== vere d maged, a review of your
[j investigaticus of this occurrence and of your plans to prevent recurrence.
In addition, quality centrol recordn, turbine building velding, and safety feature valves vere inspected. 'Jithin these areas, the inspection con-sisted of interviews with plant and vendor personnel, selective examina-i tions of procedures and representative records, and observations by the j
l inspector.
4 During this inspection, it was found that certain of your activitics appeared to be in nonccmpliance with AEC requirenents.
The iten and ref-erence to pertinent requirements is listed in the enclosure to this letter, l
Please provide us,rithin 30 days, in vriting, with your co== ento concerning this itec, any steps.-hich have been or vill be taken to correct it, any steps that have been or vill be taken to prevent recurrence, and the date all corrective action or preventive ceasures were or vill be ecmpleted.
During this inspection, our inspector was advised that additional nondes-tructive tests vill be cade of turbine building structural velds and that those velds found not to meet applicable code requirements vill be repaired.
This matter vill be examined by us during a subsequent inspection.
7912050
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J Duke Power Company
-2 October 1, 1971 Concerning the problems with the control rod drive mechanisms, it is our understanding that you vill submit a report to the Division of Reactor Licensing including the details of the events leading to the occurrence, the analyses of the effects of the improper operation on the mechanisms, and the steps being taken to prevent recurrence of this type occurrence.
Should you hava any questions concerning this letter, you may communicate directly with this office.
Very truly yours,
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((o\\nG. Davis
Enclosure:
I Director Description of Item of Noncompliance 1
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DOC'r2T 30 50-269 4
Certain activities under your license appear to be in noncompliance with license requirements as listed belev:
1 Criterion 'TIII of Appendix B to 10 CFR 50, " Identification and Con-trol of Iiaterials, Parts, and Components," requires that measures shall be established to assure that identification of materials, parts and ecmponents is =aintained by heat number or other appro-priate means as required throughout the fabrication, erection, in-stallation and use of the item. These control =easures shall be designed to prevent the use of incorrect or defective materials, parts and components.
Contrary to the above, our inspector's review of the quality centrol records shoved that the records are insufficient to per=it identi-fying pipinE and pipe fittings to assure that incorrect or defective ec=ponents were not used.
In particular, when the inspector exsmined Isometric Drawing 51A, Sheets 1 and 7, it was observed that no heat nu=bers vere available for numerous pipe sections and fittings.
Additionally, eight recorded heat numbers were not traceable to quality data packages.
(Isometric Drawing 51A is the control docu-
=ent which is used to correlate quality records to installed parts and cc=ponents.) Discussions by !-Ir. Iturphy with Messrs. Hunnicutt and Sibley of your staff indicate that the observed deficiencies are typical of other tortions of the high pressure injection system and other safety-related systems.
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