ML19326A051
| ML19326A051 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 07/27/1972 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Sampson G TOLEDO EDISON CO. |
| Shared Package | |
| ML19326A052 | List: |
| References | |
| NUDOCS 8001310627 | |
| Download: ML19326A051 (4) | |
Text
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N J. E fenderson, R0 so g
,d UNITED STATES Id-I ATOMIC ENERGY COMMISSION DIRECTORATE OF REGULATORY OPERATIONS
^g REGION Ill
/
Ustis t' 799 ROOSEVELT ROAD ymmg GLEN ELLYN, ILLINOIS 60137 (312)858 2660 July 27, 1972 Toledo udiaa= Company Docket No. 50-346 A2TN:
Mr. Glama J. 4==p=a=
Vice President, Power 420 24=diaan Avenus Toledo, Chio 43601 Gentianen:
This refers to the inspecties conducted by Messrs. Erb, Bayes, and l
Vandel of thia offise on July 11 - 13, 1972, of construction estivities at the Davis-Besse site authorised by AEC Construction Permit 23e. CPPR-80 and to the discussion of our findings at the cosslusion of the inspection with you and Messrs. Roe, Lanardson, Wadsworth, and Slaybaugh of your staff.
Areas awa=d during the inspection includ=d (1) quality documenta-tion and fabria=*4aa proemdures relative to the coatmin===e building, the roastor pressure vessel and steam generator support structures, the reactor pressuriser, and the gaseous waste decay tanks, (2) concrete placement activitina, 'ind (3) storage of Class I components.
Within these areas, the inspection canaisted of selective examination of procedures and representative records, interviews with plant persammel, and observariaam by the inspectors.
The inspectors also====4=ad actions you have taken with respect to the item identified in your letter of June 19, 1972, relating to a mattar previously brought to your attenties. We have no further questions on this matter.
During this inspostion, it was found that certain of your activities appear to be in noncomplianos with 10 CFR Part 50, Appendix 3, and 10 CFR Part 30.55(e). The items and referessee to the pertinent requirements are listed in the maalamura to thia latter. Please provide us within 30 days, in writing, with your comments concerning these itaas, any steps which have been or ~will be takaa to correct them, any steps that have been or will be takaa-to prevent recur-rence, and the data all corrective action or preventive measures l*i L.
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l Toledo Edison Company July'27, 1972 vers or will be completed. Your reply should emphasize, in particular, say appropriate changes that have been or will be made to improve the effectiveness of your quality assurance program to prevent recurrence.
With regard to questions raised during this inspection, we understand that you intend tos (1) obtain w=1d4== procedures and qualification records relative to the facility waste gas decay tanks and aska them availabla at the site for our review, (2) review and evaluate the site receiving inspection procedures and assure that adequate quality documentation related to the Nuclear Steam Supply System components will be onsite prior to the use or installation of these componer.ts, (3) obtain HDT personnel qualificacion records common to the steam generator structural supports and make these records available for our regiew at the site, and (4) provide the results of an engineering reviser of the reactor pressure vessel structural supports, performed by an outside consultant, for our review during a subsequent inspec-tion. We will aw==ta= your action on these matters during our next routine inspection.
During this inspection, the inspectors itndicated a need for a copy of the latest edition of the Davis-Besse Quality Assurance Manual. We request that you forward this manual at your earliest conv==4=_ce.
Since our use of this manual is only to facilitate our inspection effort, it will not be placed in the Public Document Rocus and will be returned to you when it has served its purpose.
Should you have questions concerning this inspecticm, we will be glad to discuss them with you.
Sincerely yours, i
Boyce H. Grier Reg 4==1 Director
Enclosure:
bec:
J. B. Henderson. RO Description of H. D. Thornburg, RO Noncompliance Items R. H. Engelken, RO G. W. Reinmuth, RO cc:
L. E. Roe, Project Engineer P. A. Morris, RO N. L. Wadsworth, General A. Giambusso, L Superintendent DR Central Files J. D. Lanardson, Quality R0 Files Assurance Engineer PDR Local PDR NSIC DTIE
ENCLOSURE Docket No. 50-346 Certain activities under your construction permit appear to be in noncompliance with AEC regu1=Hans as indicated below:
1.
10 CFR Part 50, Appe=<Hw B, Criterion YTTI, states, in part, that:
" Measures shall be established to control the... storage...
and preservation of material and equipment in accordance with work and inspection instructions to prevent damage or deterioration."
Contrary to the above, measures had not been established to control the storage and preservation of certain material and equipment as evidenced by our observations that structural steel support members for the reactor pressure vessel and steam generators and anchor bolts for the primary coolant pumps were (1) unprotected from the weather, (2) lacked adequate support dunnage, and (3) were located adjacent to a heavily traveled roadway wherein damage from vehicles could occur.
2.
10 CFR Part 50.55(e) requires that the holder of a construction permit shall promptly notify the appropriate Atomic Energy Commission Regional Office and submit a written report within 30 days to the Director of Regulatory Operations of a significant deficiency in construction of or significant damage to a structure, system, or cog onent which will require extensive evaluation, extensive redesign, or extensive repair to meet the criteria and bases stated in the safety analysis report or construction permit or to otherwise establish adequacy of the structure system or components to perform its intended safety function.
Contrary to the above, the circumstances associated with signifi-cant damage to a primary coolant pump voluta which was lost from a truck as a result of a collision during transport to the site I
on, or about, June 2,1972, were not made known to the Directorate of Regulatory Operations Region III staff until July 12, 1972.
Moreover, a written report covering this occurrence has not been submitted.
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Dhu::CTORATE OF REGULATC>RY OPERATIOh.
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MONTHLY REPORT JULY 1972 N
i Toledo Edison Company (Davis-Besse) - An RO inspection was conducted on July 11-13 The inspection involved reviewing records and observing work in progress relative to concrete manufacture and placement, and a continuaticn of the inspection of quality documentation for the steam generators and reactor vessel support structures.
Two items of noncompliance, involv-ing improper storage of Class I components and failure to report an incident involving shipping damage to the volute of a reactor p
coolant pump in accordance with 10 CFR Part 50.55(e),were i
g'j identified during the inspection and were included in a Regional enforcement letter to the applicant.
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