Letter Sequence Approval |
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MONTHYEARML19319C2211976-12-15015 December 1976
Notifies of Results of NRC 761006-08 Site Visit.Requires Mod of Reactor Coolant Flow Parameters to Meet Single Failure Criterion to Preclude Loss of Reactor Coolant Flow/Axial Power Protection.Response Required in 15 Days
Project stage: Other
ML19319C2281977-01-0505 January 1977
Responds to NRC Re Reactor Coolant Flow Monitoring.Requests Addl 45 Days to Submit Design Mod & Installation Schedule
Project stage: Other
ML19319B9721977-02-25025 February 1977
Notifies That Resolution of Reactor Coolant Flow Monitoring Will Be Scheduled After Meeting W/Nrc to Clarify Scope of Problem
Project stage: Meeting
ML19276F6731979-03-15015 March 1979
Requests to Be Notified of Util Intentions Re Mod to Reactor Coolant Sys Flow Indication.Nrc Feels Installation of Redundant Set of Sensing Lines for Each Reactor Coolant Loop Is Acceptable
Project stage: Other
ML19274E8011979-04-17017 April 1979
Ack Re Reactor Coolant Sys Flow Instrumentation. Review Is in Progress & Expected to Be Complete by 790503
Project stage: Other
ML19263E7681979-05-11011 May 1979
Responds to Re Proposed Mods to Reactor Coolant Flow Sensing Sys.Forwards Safety Evaluation Mods.Mods Must Be Implemented Prior to Restart from Current Refueling Outage
Project stage: Approval
ML19263E7701979-05-11011 May 1979
Safety Evaluation Supporting Mod of Design of Redundant Instrument Sensing Lines for Reactor Coolant Flow
Project stage: Approval
ML19326E0071980-07-21021 July 1980
Informs That Util Modifying Current RCS Flow Indication Scheme in Manner Similar to NRC Acceptable Method.Effort Will Be Completed Prior to Startup Following Current Refueling Outage
Project stage: Other
ML19330B9821980-08-0404 August 1980
Forwards Addl Info Re Reactor Coolant Loop Flow Indicators, Per 800730 Discussion.Notes Error in 800721 Response. Correct Min Separation for New Sensing Lines Should Be 3 Ft
Project stage: Other
ML19344D9191980-08-18018 August 1980
Requests Info by 800825 Re High Energy Line Break Effects on Flow Sensing Lines Inside Secondary Shielding & on Flow Transmitters.Request Prompted by Questions Arising from Review of 800804 Submittal Re RCS Sensing Lines
Project stage: Approval
ML19344E3531980-08-25025 August 1980
Responds to NRC Requesting Discussion of High Energy Line Break Effects on Flow Sensing Lines Inside Secondary Shielding & Flow Transmitter for Redundant RCS Flow Sensing Lines
Project stage: Other
1979-04-17
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4 UNITED STATES yi NUCLEAR REGULATORY COMMISSION j l ?, D ) j WASHINGTON, D. C. 20555 lf'/
May ll, 1979 O
Docket No. 50-302 Mr. W. P. Stewart Director, Power Production Florida Power Corporation P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733
Dear Mr. Stewart:
Your letter of March 29, 1979 provides details of a proposed modification to the reactor coolant flow sensing system at Crystal River 3.
This modification was proposed pursuant to paragraph 2.C.(7) of your license (DPR-72). We have reviewed your proposed modification and find it acceptable. Our safety evaluation is enclosed.
As per paragraph 2.C.(7) of your license this modification must be installed prior to restart from your current refueling outage.
Sincerely,
,,,,C
/
7 J
/' iq. & d e
E5[. :Reid,dhief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page 7 9 0 6 25 O lTG,
[,/7 [3
r Florida Power Corporation cc: fir. S. A. Brandimore Vice President and General Counsel P. O. Box 14042 St. Petersburg, Florida 33733 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Cryst'al River Public Library Crystal River, Flori fa 32629 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304
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