ML19291F142
| ML19291F142 | |
| Person / Time | |
|---|---|
| Site: | McGuire, 05000000, 05000428, 05000337 |
| Issue date: | 01/19/1982 |
| From: | Vollmer R Office of Nuclear Reactor Regulation |
| To: | Lafleur J NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP) |
| Shared Package | |
| ML19291F143 | List: |
| References | |
| FOIA-82-167 NUDOCS 8202100065 | |
| Download: ML19291F142 (3) | |
Text
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' [%' g* h2 MEMORANDUM FOR: Joseph D. Lafleur, Jr. L /,. 2 /gg R Deputy Director l'; Office of International Programs FROM: Richard H. Vollmer, Director C Division of Engineering \\m.y
SUBJECT:
COMENTS RELATING TO STEAM GENERATOR TUBE FAILURES AT RINGHALS 3 AND ACTIONS TAKEN BY SWEDISH AUTHORITIES In response to your December 22, 1981 memorandum for Harold R. Denton, we have reviewed the recent decision by the Swedish Nuclear Poer Inspectorate (SKT) to reject an application by the Swedish Sta!a Power Board (SSPB) to p.ug steam generator tubes affected y vibration-induced wear at Ringhals Unit 3 and to resume operation at reduced power for a limited period. Ringhals 3 and a similar Spanish facility (Almaraz 1) have experienced significant degradation of the steam generator tubes as a result of a vibration problem in the preheater section. fhe Ringhals and Almaraz plants employ Westinghouse Model D steam generators which are similar in design to Model D steam generators at several domestic facilities. McGuire Unit 1 is currently the only operating domestic facility with liodel D steam generators. As a result of the vibration difficulties encounts ed at Ringhals 3 and Almaraz 1, ration of licGuire Unit 1, which the staff is closely monitoring the or is still in the power ascension phase. A cautious power escalation / test program has been implenented at McGuire to determine its susceptability to these difficulties. This program includes shutdowns and eddy current inspections of the tubing after short operating periods at various operating power plateaus. Inspections to date, following two weeks at 50% power and four days at 75% power respectively, revealed no indications of vibration damage similar to those observed at the foreign units. p f or r ic t > sunmr y 8202100065 820119 om) CF SUBJ .- RD-7-2B CF oc,ouu 3 e no w ocm ordo OFFICIAL RECORf) COPY ' ""'o *- 3 >": a
W e g Joseph D. Lafleur, Jr. JAN 191982 SKI noted in its rejection of the SSPB application that, in its opinion, the power escalation / test program at McGuire, where no vibration damage has yet been encountered, is more cautious than that proposed by SSPB and Westinghouse for plants with damaged stesm generators. The NRC staff has closeiy followed the operation and FMtus of the McGuire steam generators to date, and believes the test pren currently in progress at McGuire to be appropriately cautious in re. Reting the adverse experience at Ringhals and Almaraz. Under the planned test program, operating periods to be spent at various power levels prior to perfoming t:ie next eddy current inspection will be less than the corresponding operating periods already accumulated at Ringhals and Almaraz. In addition, the test program provides for plant shutdown or power deescalation should any indication of vibration damage develop during the planned period of operation (e.g., via external transducers mounted on steam generator vessel or any primary to secondary leakage). For your inforenation, we have attached a more detailed staff assessment of the McGuire Power Escalation / Test Program. Origind doe 3 by: Richard H. WHmer Richard H. Vollmer, Director Division of Engineering
Attachment:
Distribution: ESullivan MTEB Reading As stated RVollmer BSnyder MTEB Steam Generator DEisenhut WJohnston SCavanaugh NRR 81-630 RMattson SPawlicki HThompson SHanauer J Kni ght LMiller RDeYoung RBosnak CMichaelson JRajan RMinogue CMcCracken VStello EMurphy JShea CCheng ECase PPAS HDenton Central File
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a v-Joseph D. Lafleur, Jr. SKI noted in its rejection of the SSPD application that, in its opinion, the power escalation / test program at McGuire, where no vibration damage has yet been encountered, is more cautious than that proposed by SSPB and Westinghouse for plants with damaged steam generators. ThejNRC staff has closely followed the operation and status of the McGuire steam generators to _date, and believes the test program currently,in progress at McGuire to be appropriately cautious in reflecting the adverse experience at Ringhals and Almaraz. Under the planned test program, operating periods 'to be spent at various power levels prior to performing the next eddy current inspection will be less than the corresponaing operating periods already accumulated at Ringhals anV Almaraz. In addition, the test program provides for plant shutdown or power deescalation should any indication of vibrati6n damage develop during the planned period of operation (e.g., via external, transducers mounted on steam generator vessel or any primary to secondary leakage)y N / We are con ~tinuing to closely monitor developments at McGuire,4nd have been in commun'ication with the Spanish a'uthorities regarding the status of the Almaraz facil'ity.s In edditionKthe staff will be meeting with /,(b the licensee for McGuire (Du'.% .er'Co'mpany)'and Westinghouse on J January 15, 1982 to discuss the latest' developments at McGuire and the .Q'~ other operating facilities (fsreigii ahdxiomestic) with Model D steam i generators, results of recer,t'arialyses and Pests regarding the vibration phenomenon, and interim-and 1.ong term measuresxwhich<an be taken to deal with this problem., -If dictated by further developments'orgew information, ~ the staff will take appropriate action on McGuire'and other potqntially affected domestic facilities. \\y \\ For your information,,w,/e have attached a more detailed' staff assessment of the McGuire Power Es,c'alation/ Test Program. N / \\ / \\)R i r Li / Harold'R.-Denton, Director ,/ Office of l{uclear Reaclor Regulation / ~ \\
Attachment:
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