ML19289G251
| ML19289G251 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/21/1977 |
| From: | Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Murphy C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19289G243 | List: |
| References | |
| FOIA-79-214 NUDOCS 7908080720 | |
| Download: ML19289G251 (2) | |
Text
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March 21, 1977 MEM0?AiDC1 FOR:
C. E. Murphy, Chief, Reactor Construction and Engineering Support Branch, Inspection and Enforcement, Region II i
FROM:
A. R. Hordt, Chief, Engineering Support Section No. 2, Reactor Construction and Engin'cering Support 3 ranch, Region II
SUBJECT:
VIRGINIA ELECTRIC A'iD PCWER CCMPANY (VEPC0) - ::0RTM ANNA CiITS 1 AND 2 - INVESTIGATCR'S EVAL"ATION -
REFCRT N0. 50-338/77-3, 50-339/77-2 (SUN SHI?3UILDING AND DRY DOCK CCM?.'.NY ALLEGATI055)
The subject investigation report has been ccepleted.
The SUN allega-tien that "VEPCO and/or its agents did not disclose to the Com:issicn the full extent of VEPC0's knowledge" regarding the fracture rechanics-study is substantiated.
This fr,cture mechanics study primarily invelves the Stone and 'a'ebster report kntin as DC-81 and its associtted data (Exhibits 3, C and D of the subject report).
As stated in paragraph IV,3,3 (Conclusions), VEPCO did not report to the NRC the information contained in DC-Sl.
Even though the DC-81 report was initiated to evaluate ultrasonic examination acceptable flaw size in repaired welds not the mechanical properties of the base caterials used (which cicuds the issues), the investigator is of the opinion that this, is related to the original 50.55(e) ite2.
VEPCO should have reported this infor:ation in a titely canner (Parch, 1974) by updating their Final 50.55(e) report dated November 14, 1973, since in VE?CO's Final 50.55(e) report, Section 4 (Repair Program), ultrasonic inspection of selected welds was stated and the procedure was under development.
Therefore, the investigator is of the opinion that VEPCO's failure to report sufficient information to permit analysis and evaluation of the deficiency and of the corrective action is an integral part of the reports that were submitted.
Marcover, the inspector's opinion is that VEPCO is in violation of Title 10, Code of Federal Eegulations, Part 50.55(e) specifically:
Title 10, Code of Federal Regulations, Part 30.55(e) states in part that the holder of a Construction Fer=it shall notify the Cocaission of each deficiency found in design and construc-tion, which, were it to have remained uncorrected, could have CONTACT:
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affected adversely the caf'ety of operations of the nuclear power plant at any time throughout the c>.pected lifetime of the plant, and which represents a significant damage to a structure, which will require extensive evaluation, extensive redesign, or exten-sive repair to establich the adequacy of the structure, to perfcrm its intended safety function.
The report shall include a descrip-tion of the deficiency, an analysis of the safety,inplications and the corrective action taken, and sufficicat information to perait analysis and evaluation of the deficiency a'nd of the corrective action.
The investigator recognizes that the final determination whether a violation exists hinges on the legsl significance of the deficiency nnd the extensiveness of evaluation, repair or redesign.
He' ever, in su=cary, it is recc= mended that an enforcecent action to 10 lFR 30.35(e) be issued against VEPC0 for their failure to report t r.
- information contained in DC-81 to the NRC in a timely canner.
r-hW A. R. Eerdt, Chief Engineering Support Section :;o. 2 Reactor Construction cad Engineering Support Branch I
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