ML19340A472

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Responds to NRC 780814 Request for Info Re Possibility That Atypical Weld Wire Used in Mfg of Reactor Vessel.Until Determination Is Made,Util Will Operate on Assumption That Wire Was Used & Start Corrective Action
ML19340A472
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 08/18/1978
From: Stewart W
FLORIDA POWER CORP.
To: Reid R
Office of Nuclear Reactor Regulation
Shared Package
ML19340A473 List:
References
TAC-08884, TAC-8884, NUDOCS 8004070475
Download: ML19340A472 (4)


Text

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6 I REGULATORY INFORMATION DISTRIDUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50- 302

EC: REID R W ORG: STEWART W P DOCDATE: 09/18/78 NRC FL PWR DATE RCVD: 08/24/79

'OC TYPE: LETTER NOTARIZED: YES COPIES RECEIVED LTR 3 ENCL 40

.UBJECT:

ESPONSE TO NRC REQUEST OF 03/14/7G.. FURNISHING INFO CONCERNING POSSIBILITY

' HAT ATYPICAL WELD WIRE WAS USED IN THE MANUFACTURE OF UNIT 3 REACTOR

'ESSEL. NOTARIZED 08/18/73.. W/ATT SUPPORTING AND RELATING INFO.

REVIEWER INITI AL: XJM

'LANT NAME: CRYS. T AL RIVER -#3 DISTRIBUTOR INITI AL: %

onannn***x******* DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS

    • x***************

REACTOR VESSEL MATERIAL SURVEILLANCE (DISTRIDUTION CODE A021)

FOR ACTION: BR C .F ORUM4 BC**W/O ENCL ZWETZIG**W/ ENCL INTERNAL: a_G FILF *W/ ENCL NRC PDR**W/ ENCL J"s a /2 ENCL OELD**LTR ONLY MIPC**W/ ENCL HANAUER**W/ ENCL '

MATERIAL ENO BR**W/ ENCL AD FOR SYS 8e PROJ**W/ ENCL ENGINEERING DR**W/ ENCL REACTOR SAFETY BR**W/ ENCL PLANT SYSTEMS BR**W/ ENCL EEB**W/ ENCL HAZELTON**W/ ENCL HOGE**W/ ENCL R GAMBLE **W/ ENCL RANDALL**W/ ENCL EXTERNAL: LPDR'S CRYSTAL RIVER, FL**W/ ENCL TERAN*W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL DIS TION: LTR 40 ENCL 39 CONTROL NBR: 754_. a m s 9T7 +2P+0P jj l conoc*x**************************** THE END *********************************

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W.P G EWART. DIRECTOR POWER PRODUCTION yg c o a e e a a eg

. Mr. Robert W. Reid, Branch Chief Operating Reactors Branch 14 Division of Operating Reactors U.S. Nuclear Regulatory Commission

-- Washington, D.C. 20555

SUBJECT:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 4

Reactor Vessel Atypical Weld Material

Dear Sir:

Your. telecopy of August 14, 1978 requested that Florida Power Corporation provide you with certain information by Friday, August 18, 1978 concerning the possibility that atypical weld wire was used in the manufacture of the Crystal River Unit 3 reactor vessel. That information is provided below and is in the same order as your questions.

1. In the event that the atypical weld wire was used in the manufacture of the Crystal-River Unit 3 reactor vessel, Florida Power Corporation is administratively employing revised pressure-temperature heatup, cooldown and inservice leak and hydrostatic test curves to ensure the reactor vessel integrity. These operating curves are based on the assumption that the atypical weld wire was used in our reactor vessel.
2. The revised. operating curves, assuming the atypical weld material is present, are based on the same criteria as the

' original operating curves , that is, the RTNDT of the most  ;

restrictive vessel region is equal to the temperature at which a lateral expansion of 35 mils is. obtained from 50 f t-lbs force on 'a Charpy specimen minus 60*F or the nil ductility transition temperature, whichever is greater. The curves are still extrapolated to 5 EFPY since this

- extrapolation is based on the copper and phosphorous content, which was within limits.

Based on these-interim measures, we feel that= the. continued l operation of Crystal River Unit 3 does not; endanger the 1 a  !

- - health'a'nd

.i,- ' safety of the plant personnel and the public.

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,y General Office 320f T,yrty-fourtn street soutn . P.O. Box 14042. St. Petersburg. Florida 33733 e 813-866-5151 ' 91 l

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August ~ 18,.1978

-Page 2-t

. 3.- The revised pressure-temperature . operating curves will be applied to Crystal River-Unit 3. administrative 1y until 1)~ it is determined that the ' atypical weld wire was - not used in the manufacture of our reactor vessel or 2) until a license amendment is. issued that inserts the revised curves into the Technical Specifications. If it' is determined that atypical weld wire was used in the manufacture of our rector vessel, a Technical Specification Change Request will be submitted as soon as

, possible.

If you require any furth'er information, please contact this office.

Sincerely, FLORIDA POVER CORPORATION

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&Q W.P. Stewart WPC/RMB/ emf File: 3-B-1 R5 ~.(8/17)

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STATE OF FLORIDA

- COUNTY OF PINELLAS IW.P. Stewart states that he is .the Director, Power Production. of Florida ~ Power Corporation; that he is authorized on the part o1 said. company to sign and file with the Nuclear Regulatory

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' Commission the information attached hereto; and that all such s'tatements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.

. \- 00 /L.A W.P. stewart

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Subscribed. and sworn to before me, a Notary Public in. and for the State and County above named, this 18th day of August, 1978

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k J fc.$ /' Y J!w Notary Public.

Notary Public,' State of Florida at Large,

  • My Commission. Expires: . July 25, 1980.

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