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MONTHYEARML19319D3861977-07-11011 July 1977
Forwards Info Re Potential Moderator Dilution Incident Due to Unterminated Injection of Sodium Hydroxide Into Primary Coolant Sys.Evaluation of Situation & Recommendations Re Licensing Action Requested
Project stage: Other
ML20037A6071977-08-17017 August 1977
Discusses Unreviewed Safety Question Re 770207 Boron Dilution Incident.Licensees Should Be Directed to Investigate Potential for Boron Dilution W/Rept on Findings within 60 Days
Project stage: Other
ML19308D1561977-09-0202 September 1977
Forwards Rept as Suppl to RO-77-52 Re Unterminated Sodium Hydroxide Dilution of RCS
Project stage: Other
ML19308D1621977-09-30030 September 1977
Re-evaluation of Moderator Dilution Accident
Project stage: Other
ML19276E8301979-03-0505 March 1979
Responds to 770902 Submittal Re Boron Dilution & Requests Addl Info Identified in Encl
Project stage: Other
IR 05000302/19790151979-05-25025 May 1979
IE Insp Rept 50-302/79-15 on 790507-11.Noncompliance Noted: Failure to Prepare Procedures for Identifying Containers of Radioactive Matl & Improper Shipments of Solid Wastes
Project stage: Request
ML19225D1361979-07-0303 July 1979
Safety Evaluation Supporting Amend 20 to License DPR-72
Project stage: Approval
ML19225D1421979-07-0303 July 1979
Notice of Issuance & Availability of Amend 20 to License DPR-72
Project stage: Other
ML19225D1191979-07-0303 July 1979
Amend 20 to License DPR-72,changing Required Sodium Hydroxide Concentration in Reactor Bldg Spray Chemical Additive Tank & Increasing Required Shutdown Margin
Project stage: Other
ML17212B5751982-04-26026 April 1982
Informs That NRC No Longer Requires Installation of Startup Fast Flux Alarms for Detection of Boron Dilution Events.Info Re Util Intent Concerning Alarm Installation Requested by 820528.Basis for Revised Alarm Position Encl
Project stage: Approval
1977-09-30
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"' '#.Ta"ha"u'38" September 2,.1977 ib' Mr. J. P. O'Reilly, Director Office of Inspection & Enforcement U.S. fluclear Regulatory Commission 230 Peachtree Street, N.W., Suite 818 Atlanta, GA 30303 2,
Dear Mr. O'Reilly:
On June 20, 1977, Florida Power Corporation submitted to the Commission, Licensee Event Report 77-52, which identified an unreviewed safety question as defined by 10 CFR 50.59 (b) concerning unterminated sodium hydroxide dilution of the Reactor Coolant System.
The attached report is being submitted as supplemental information to Licensee Event Report 77-52 and contains the results and conclusions of our review of this. safety question.
Upon review and acceptance of this supplemental report by the Comission, appropriate revisions to the CR#3 FSAR will be initiated and submitted at a later date.
Please advise if further discussion is desired.
Very truly yo'urs, 2 B3
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W. P. Stewart WPC/ECS/mcmS/10 Attachment File:
3-0-3-a-1 8002 270 b30 O
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General Office 3201 Tmrty-sounn saec soum. P O Box 14o42. St Peterstug. Flonda 33733 e 813-866-515 t
