IR 05000029/1975015
| ML20148H470 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/11/1975 |
| From: | Haynes R, Sanders W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20148H468 | List: |
| References | |
| 50-029-75-15, 50-29-75-15, NUDOCS 8011180535 | |
| Download: ML20148H470 (5) | |
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% S. NUCLEAR REGULATORY CC.tilSSION OTTICE OF INSPECTION AND C. 0RCDfCIT
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REGION I
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Docket No:
50-20
- Inspection Report No
50-29/79-15 License No:.y q
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Yankee Atonic Elcetric Corenny
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_s R. C. liayner, Senior Reactor inspector
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SUM'iARY OF FI!iDINGS i
Enforcement Action A.
Items of Noncompliance None B.
Deviations Monc Licensec's Action on Previousiv Identified Enforcement It eri:
A.
In-Service Inceection (ISI)
P opr m l
During the inspection of July 10-12, 1975, it e.pruered that the 11cene,ee had not perf ormed cer tain ISI Program e
,"in.it :c c s as cot:=1 ticd to the NP.C.
Ar: a rerult of thia innpcetien and the additienal inf ornation provir.:cd by the licensee in 1.js ietter of September 3, 1975 to the n'.C F.ction 1 Office, ti.e d :.< tor found that the licensee had perfcrmd the require e:ca.. :tions md had, therefore, met his con.:aitr.en t s.
(De tail.;, Pa r 3rnph 4).
Desien Cl..m es
?:ene Identified Unuso:i1 & :rrenree None Identified
Othe-Sienificant F!nd4mc A.
Current F i nd in o.;
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Acceptable
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a.
In-Serv ic e Inceection of Steam Canerr.cor Tubes The mencuring of the tube wall thickneun by Eddy Current methods was found to conply with the technical requirements outlined in the licenace's inspection prccedure.
(Details, Taragraph 3)
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Unresolved Items None B.
Status of Previously Reported Unresolved Items
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Not Inspected Management In't e rview At the conclusion of the inspection the inspecto?: held a cecting at the I
site with Mr. H. A. Autio, Plant Superint endent to discuss the inspcetion findings.
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A.
Itees Discussed
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The inspector stated that this inspection was made to review and observn the activitics relative to the measurrent of steam generator
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tubes for wall thickness using Eddy Current rathods and to rcview the additienal inf ornation pertinent to the resoluticu of an apparent deviation documented in IE Inspection F.cport 50-29/75-03.
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The inspector stated that the steam generator tube censuring activities conducted while the inspector was on site were found to be acceptable.
The. inspector also stated that his review of records tc date sha.eed th it the licensee had cat ISI Progran cotritments and that there did
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not cepear te be e deviatica f rom these cennittents as reperted in the afore.2t.tioned inspe: tion report.
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DETAILS
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Persons Contacted Yankee Atomic Electric Compsnv 11. Autio, I'lant Superintendent W. Jones, Assistant Superintendent M. Ebert, Plant Reactor Engineer J. Staub, Technical Assistant
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A. Lucero, Test Engineer 2.
General The purpose of this inspection was to inspect the activities related to the acasu'.cment of steam generator tube wall thickness using Eddy Currcnt ter.hniques and to review additientl information pcrtinent to the apparent deviation identified fu IE Inspection Report 50-29/75-03.
3.
T'n-Solvice Inc.coction of Stcra Generator Tubes
- he re.<:urinr, of tube wall thickness bv ::ddy Current methcds was found to cc..
1;, wi t h the technical recuirerents cutline in the licensee's props; ?. ch nge Mo. 119 to the Technical Specificaticas.
Call' rution records for the f ollcwing equipment and standards were examined :
a.
Eddy Current instr ut..ent "12-7 Seri al //3 b.
Vector Analyzer 007 c.
M.'in Frate P062316 Zetec 4 d.
Lrush neuerder 11614 Zetec 2 Calibration Standards (2) Tube 3/4" 0.D. x.072 Wall Material MIL' T e.
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8504 Type - 304 !!T No. 27264 x f.
Personnel Qualifications - ZQA5 These records were found to be acceptable.
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Subsequent to the conduct of this inspection, the it.censee decided to
- test an additional sample of tubes in the steam generators under ecst.
'The licensee informed Region 1 of this decision on November 6, 1975, in
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a telephone conversation between Mr. J. Streeter of this office and Mr. J. French, : tanager of Operations, Yankee Atomic Electric Cc=pany.
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This decision was based on the results of the first two sampic lots and
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the provisions of Regulat;ry Guide 1.83, Paragraph 5, " Supplementary Sampling Requirements." The results of the first two sample lots were
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reported to Region I as Reportable Occurrence A0-75-11 on November 7, 1975.
t The I'ddy Current testing results will be reviewed further during a sub-sequent inspection.
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In-Scrvice Insocction Procram (Ret: Deviation, IE Inspection Report 50-29/75-08)
During the inspection of July 10-11, 1975, it was concluded that certain exaninations had not been perfor ed, nacely; a volumetric examinatien of integrally welded pressurizer supports, a visual examinatica of reactor pressure vessel penetrations, and a visual and surface examination of the primary nozzle to vessel head welde of the sten: generators. The licensee.provided additional inforration to the MRC Region I office in his letter of September 3, 1975 which disclosed'that records were available on site showing that two of these inspections had been performed.
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During this inspection of October 13-24, 1975, the inspector cade the f ollowing findings :
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Records si.:
that a volumetric exanination was performed on two integt 11y welded pressuri:er supports by Southwest F ascarch L stitute persor.nel in !;ovember,1970, b.
iMenrds show that a visual inspection of reactor pressure vcasel penetrations was perforced during a hydrostatic test of the vessel on August 9, 1974.
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A revicu of the detail drawing of the steam generator primary nozzle area showed the no: le to be a part of the steam gener-ator heed forging and not a separate forging.
The only welds
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associa:ed with the nozzles were to ale-to-safe-end welds which had been examined as required for that type of weld.
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Based on the above findings, the inspector found that the licensee had net his ISI Program cctaiteents to the NRC and that no deviation
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existed as had been previously reported.
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