Letter Sequence Other |
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Results
Other: 05000302/LER-1978-037, Forwards LER 78-037/01T-1, 05000302/LER-1978-037-01, /01T-0:on 780804,B&W Reported That Atypical Weld Matl May Have Been Used in Constructing Plant Reactor Vessel.No Hazard to Health and Safety Determined, ML19308D758, ML19317G782, ML19317G791, ML19319D197, ML19340A474, ML19340A475, ML20062C376
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MONTHYEARML19319D9191978-08-0202 August 1978 Proposed Amend 59 to License DPR-54,revising Tech Specs Re Pressurization,Heatup & Cooldowm Limitations Per App 6 10CFR50.Class III Fee Encl Project stage: Request 05000302/LER-1978-037-01, /01T-0:on 780804,B&W Reported That Atypical Weld Matl May Have Been Used in Constructing Plant Reactor Vessel.No Hazard to Health and Safety Determined1978-08-11011 August 1978 /01T-0:on 780804,B&W Reported That Atypical Weld Matl May Have Been Used in Constructing Plant Reactor Vessel.No Hazard to Health and Safety Determined Project stage: Other ML19308D7581978-08-14014 August 1978 Confirms 780814 Telcon Re Possible Use of Atypical Weld Filler Wire.Requests Info Re Interim Measures,Operational Safety Assessment & Commitment to Maintain Interim Measures Pending Resolution of Issue Project stage: Other ML19317G7821978-08-16016 August 1978 Amend 22 to License DPR-54,revises Tech Specs Re RCS Pressure Temp.Tech Specs Encl Project stage: Other ML19317G7761978-08-16016 August 1978 Forwards Amend 22 to License DPR-54,safety Evaluation & Notice of Issuance Project stage: Approval ML19317G7871978-08-16016 August 1978 Safety Evaluation Supporting Amend 22 to License DPR-54 Project stage: Approval ML19317G7911978-08-16016 August 1978 Notice of Issuance & Availability of Amend 22 to License DPR-54 Project stage: Other ML19340A4721978-08-18018 August 1978 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 Project stage: Request ML19308D9381978-08-18018 August 1978 Forwards Response to NRC 780517 Request for Addl Info Re Movement of Heavy Loads Near Spent Fuel Project stage: Request ML19340A4741978-08-22022 August 1978 Forwards Revised Operating Curves,Tech Specs Promised in Util Re Reactor Vessel Atypical Weld Matl & Bases for Tech Specs Project stage: Other ML19340A4751978-08-22022 August 1978 Revised Tech Specs 3/4.4.9 Re Operating Curves.Curve Diagrams & Bases for Tech Specs Encl Project stage: Other ML19319D1971978-08-31031 August 1978 Notifies of 781101 Possible Completion Date for B&W Chemical Analysis of Reactor Vessel Surveillance Matl to Determine Whether Atypical Weld Matl Used.Outlines Action to Be Taken on Results Project stage: Other 05000302/LER-1978-037, Forwards LER 78-037/01T-11978-09-0101 September 1978 Forwards LER 78-037/01T-1 Project stage: Other ML19308D8331978-09-0101 September 1978 Provides Review of Revised pressure-temp Operating Limits & Finds Them Acceptable.Amend Classification Form Encl Project stage: Approval ML20062C3761978-10-31031 October 1978 Forwards Tech Spec Change Requests 27 & 34,requesting Amend to App a of License DPR-72.Changes Concern Reactor Coolant Pump Power Monitors & Revisions to Heatup,Cooldown & Inservice Leak & Hydrostatic pressure-temp Curves Project stage: Other ML19257C7951980-01-28028 January 1980 Requests Withdrawal of 781031 Tech Spec Change Request 34 & Licensing Fee,Due to NRC Approval of BAW-1566, Evaluation of Atypical Weldment. Certificate of Svc & Affidavit Encl Project stage: Withdrawal 1978-08-18
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L PDR AUGUST 1 4 1978 ORB #4 Reading RWReid RIn
=m C % sun Docket No.: 50-302 rtile DIAE(3)
DEisenbut
^
-TAbernathy JBuchanan Florida Power Corporation BGrimes/TCarter ATTN: Mr. W. P. Stewart Director
- ACRS(16)
Power Production Gray file P.O. Box 14042. Hail Stop C-4 St. Petersburg, Florida 33733 Gentlemen:
RE: REACTOR VESSEL ATYPICAL WELD MATERIAL This letter confirms our telephone conversation with your staff of August 14, 1978.
The NRC was advised by Babcock & Wilcox (B&W) on August 4,1978, that a chemical analysis of an archive wendment performed as part of the program for evaluation of reactor vessel material properties indicated 1
that the nickel and silicon content of the weld material were outside the
.specified range. It has been detemined that the weld filler wire used for that particular Wld was atypical.
As of this date, it is not known whether or not this atypical weld wire was used in the manufacture of your reactor vessel. Therefore, we request-that you provide the following information to us by Friday, August 18, 1978 (a telecopy of your signed response is adequate):.
1.
What interim ocasures, such as revised pressure / temperature l'imits, you are taking to ensure reactor vessel integrity in the event that the atypical weld wire was used, 2.
Your assessment as to the continued safe operation of your facility based on these, interim measures, and fff f
6 0 03130 )N L
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, 3.
Your cormitment tnat these measures will continue in forr.e pending the resolution of this issue.
Your submittal should be three signed originals plus 37 additional copies.
Sincerely, Robe' t it. Reid, Chief j
r Operating Reactors Bri.nch 44
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Division of Operating Reactors
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Florida Power Corporation ec: Mr. S. A. Brandimore Vice President and General Counsel
- r. O. Box 14042 St. Petersburg, Florida 33733 Crystal River Public Library Crystal River, F1.orida 32629 e
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