IR 05000316/1979016
| ML17318A361 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/27/1979 |
| From: | Fiorelli G, Heishman R, James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17318A360 | List: |
| References | |
| 50-316-79-16, NUDOCS 7910250205 | |
| Download: ML17318A361 (4) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
A Report No. 50-316/79-16 Docket No. 50-316 Licensee:
Americ License No. DPR-74 an Electric Power Service Corporation Indiana and Michigan Power Comapny 2 Broadway New York, NY 10004 Personnel:
J.
G. Keppler Facility Name:
Donald C.
Cook Nuclear Power Plant, Unit 2 Meeting At:
AEPSC Office, New York, New York Meeting Conducted:
July 31, 1979
. F. Heishman G. Fiorelli D. H. Danielso gz.l p R. E.
Ma se V. J.
Key K. D. Mard Approved By: gJ.
,
ler Director Meetin Summar Meetin on Jul
1979 (Re ort No. 50-316/79-16)
Areas Discussed:
Interpretation of radiographs taken of feedwater system piping repair welds.
'Ehe meeting involved a total of 27 man-hours by seven NRC individuals.
Results:
No items of noncompliance or deviations were disclose DETAII.S Cor orate Meetin This meeting was held between. RIII and licensee personnel to resolve differences in radiographic interpretation and required corrective actions.
The following personnel participated in this meeting:
American Electric Power Service Cor oration (AEPCS)
J. Dolan, Vice Chairman, Engineering and Construction R. Hunter, Senior Vice President, Construction R. Hering, Vice President, Mechanical Engineering J.
Markowsky, Section Head Analytical and Research J. Castresana, Section Head Nuclear Safety and Licensing R. Jurgensen, Chief Nuclear Engineer D. Patience, Staff Metallurgist Indiana and Michi an Power Com an (I&NPCo)
A. Papai, ISI Coordinator United States Nuclear Re ulato Commission Re ion III (RIII)
J. Keppler, Director, Region IIl R. Heishman, Chief, Reactor Operations and Nuclear Support Branch" G. Fiorelli, Chief, Reactor Construction and Engineering Support Branch D. Danielson, Chief, Engineering Support Section No.
R. Masse, Reactor Inspector (Resident Site)
W. Key, Reactor Inspector K. Ward, Reactor Inspector The RIII construction staff explained their interpretation of the radiographs of repair welds on the Unit 2 feedwater system piping as per Report No. 50-315/79-15; 50-316/79-12.
The staff indicated that the following actions are needed to achieve and document a successful repair of welds No.
1 and No.
2 for each of the four steam generators.
1.
All eight of the welds will be reradiographed and meet the require-ments of the ASME Section III, 1974 Edition with Summer 1975 Addenda.
This includes:
a
~
Correct density limitations of radiographs.
(ASME Section Y, Paragraph T-233.)
b.
Film identification, R (for repair)
R2, etc., if more than one repair.
(Superior X-Ray Procedure, R.T.1, Rev. 2, Paragraph 5.1.8.)
c.
Correct Code, year and addenda documented on report.
d.
Acceptable radiographs that do not vary more than minus 15 or plus 30 percent.
(ASME Section V, Paragraph T-262.3.)
e.
The penetrameters will be placed adjacent to the weld seam.
(ASME Section V, Paragraph T-262.2.)
f.
All reports will give disposition of weld examined.
(ASME Section V, Paragraph T-283(a).)
2.
Steam generator 3, Weld 2.
The report sheet will document that the 1/2" linear indication across the root is a surface indication, as was determined during a visual inspection by the NDE examiner.
3.
Steam generator 3, Weld 1, will be repaired to remove the questionable dark lines that, could be lack of penetration.
(ASME Section III, Paragraph NC-5320.)
4.
Steam generator 4, Weld 2, will be repaired deleting any type of patching that will interfere with the interpretation of the radiograph.
(ASME Section III, Paragraph NC-4424.)
The licensee's staff offered their basis for interpreting the welds to be acceptable without further corrective action.
In addition, the radiographs in question were reviewed and the areas where differences in interpretation occurred were discussed in detail.
The AEPSC staff stated, in context, that while there were differences of opinion and some documentation errors have occurred, it is their intent to meet the requirements necessary to achieve a successful repair of the feedwater system piping.
Moreover, they agreed to complete and document the RIII actions outlined above during the next Vnit 2 refueling outag ~'