Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: B12630, Proposed Tech Specs,Adding New Surveillance Requirement Re Control Room Habitability, ML19241B419, ML19241B427, ML19254D272, ML19263C802, ML19310A426, ML19321A695, ML19330B754, ML19339A509, ML19339A598, ML19343A382, ML19345E132, ML19347C739, ML20049H553, ML20050C507, ML20052A948, ML20053D721, ML20066D300, ML20071G129
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MONTHYEARML19256A1121978-10-27027 October 1978 Application for Amend to License DPR-35,changing Tech Specs to Accomodate New Steamline Break Protection Sys Scheduled for Installation in Spring of 1979.Fee Paid Project stage: Request ML20071G1291978-12-14014 December 1978 Forwards Addl Info Re Lic Amend Appl Covering Eval of Low Feedwater Flow Reactor Trip Setpoint Change Project stage: Other ML19263C8021979-02-0505 February 1979 Lists Individual Fee Classes for 781027 Application for Tech Spec Changes.Requests Submittal of Addl $13,500 Fee. Any Overcharges Will Be Refunded Project stage: Other ML19276E2751979-03-0707 March 1979 Forwards Addl Info Requested at 790223 Meeting Re Proposed Steam Break Protection Sys Project stage: Meeting ML19270F9971979-03-12012 March 1979 Summary of 790223 Meeting W/Westinghouse & Duquesne Light Re Steamline Break Protection Sys.W/Supporting Documentation Project stage: Meeting ML19241B4271979-07-13013 July 1979 Tech Spec Change Requests 42 & 47 Re Mod to ECCS Project stage: Other ML19241B4191979-07-13013 July 1979 Forwards Tech Spec Change Requests 42 & 47 Re Amend to App a of DPR-72.Change Is Required Prior to Startup After Completion of Planned ECCS Mod,Which Could Be Accomplished as Early as 790722 Project stage: Other ML19274G1021979-07-31031 July 1979 Forwards Request for Addl Info to Util Proposed Steam Break Protection Sys & N-1 Loop Operation Project stage: RAI ML19208B5691979-08-21021 August 1979 Forwards Safety Evaluation Re Electrical,Instrumentation & Control Aspects of Deletion of Reactor Trip on Turbine Trip Below 50% Power Project stage: Approval ML19259D6001979-10-18018 October 1979 Summary of 791009 Meeting W/Util Re Proposed Steamline Break Protection Project stage: Meeting ML19254D2721979-10-18018 October 1979 Forwards Addl Info Re Proposed Steam Break Protection Sys Per Tech Spec Change Request 35.Proposed Tech Spec Re Maint of Required Shutdown Margin & Revised Reactivity Control Sys Tech Specs Encl Project stage: Other ML19309A8581980-03-28028 March 1980 Forwards Documents Re Investigation Into Extended Outages at Facility.Documents Include Trial Staff Statement Before PA Public Util Commission,Consumer Advocate Statement & CN Dunn Testimony Project stage: Request ML19309H2151980-04-15015 April 1980 Notification of 800422 Meeting W/Util in Bethesda,Md to Discuss & Review Decay Heat Exchanger Sys Integrity & Operation Project stage: Request IR 05000302/19800181980-05-0707 May 1980 IE Insp Rept 50-302/80-18 on 800331-0411.No Noncompliance Noted.Major Areas Inspected:Previous Insp Findings,Fuel Receipt,Refueling Activities,Maint Activities & IE Bulletin 79-01B Project stage: Request IR 05000334/19800081980-05-0707 May 1980 IE Insp Rept 50-334/80-08 on 800324-28.No Noncompliance Noted.Major Areas Inspected:Qa Program Review,Qa/Qc Administrative Design Change & Mod Control,Measurement & Test & Previous Insp Items Project stage: Request ML19310A4261980-06-0909 June 1980 Responds to & Schedule for Implementation of TMI-2-related Requirements.Discusses Shift Manning,Scope & Criteria for Licensing Exam,Procedures for Feedback of Operating Experience & Control Room Habitability Project stage: Other IR 05000412/19800061980-07-0303 July 1980 IE Insp Rept 50-412/80-06 on 800602-06.Noncompliance Noted: Failure to Return Used or Damaged Welding Electrodes to Issue Station & Failure to Provide Adequate Protection for Equipment in Temporary Storage Project stage: Request ML19321A6951980-07-21021 July 1980 Forwards Schedule for Commitments to TMI-2 Related Requirements,Per NRC 800507 Request.Affidavit Encl Project stage: Other ML19330B7541980-07-31031 July 1980 Informs of Intentions to Withdraw Commitment to Adopt Guidance of IE Circular 80-02,due to Wording of IE Circular 80-02 & Application of Circular Re Work Situations Project stage: Other ML19343A3791980-09-15015 September 1980 Application to Amend App a to Ol,Changing Aspects of NUREG-0578 Including Model License Conditions & Emergency Feedwater Initiation & Flow Monitoring.Affidavit & Certificate of Svc Encl Project stage: Request ML19343A3821980-09-15015 September 1980 Tech Specs 3/4 3-38,requesting Changes Re Model License Conditions,Emergency Feedwater Initiation & Flow Monitoring, Diverse Containment Isolation & Emergency Power Supply to Pressurizer Heaters Project stage: Other ML19339A5091980-10-24024 October 1980 Withdraws Tech Specs Change Request 47,implementing Items Contained in NRC 790516 Confirmatory Order.Util Considers Specs Requested in Eisenhut & Provided in Change Request 64,Revision 1,as Representing Latest Position Project stage: Other ML19339A5981980-10-29029 October 1980 Advises of Status Re Shift Staffing,In Response to Interim Criteria in NRC Project stage: Other ML19339B2141980-10-31031 October 1980 Advises That Util Has Not Made Plans to Conduct Any Qualification Tests During Next 2 Yrs.Nrc Will Be Notified in Event of Decision to Conduct Tests Project stage: Request ML19345E1321980-12-17017 December 1980 Responds to Re Confirmation of Commitment to Meet Implementation Dates Contained in NUREG-0737.Requests Extension for Proposed Mods Re Auto Trip of Reactor Coolant Pumps Project stage: Other ML19347C7391980-12-31031 December 1980 Forwards Nonproprietary & Proprietary Versions of Response to NUREG-0737. Proprietary Version Available in Central Files Only Project stage: Other ML20049H5531982-02-24024 February 1982 Provides Info on Item II.K.3.5 Re Automatic Trip of Reactor Coolant Pumps During Loca,Per NUREG-0737 Requirements. Status Submitted in Has Not Changed Project stage: Other ML20042B9261982-03-16016 March 1982 Forwards Request for Addl Info for Review of TMI Action Items 2.A.2.1,upgrading Senior Reactor Operator & Reactor Operator Training & II.B.4,training for Mitigating Core Damage Project stage: RAI ML20050C5071982-03-24024 March 1982 Ack Commitment in to Meet Reporting Requirement Provided in NRC Re Relief & Safety Valve Failures.Info Missing from 1981 Annual Rept.Requests That Rept Be Updated W/Errata Sheet to Correct Discrepancy Project stage: Other ML20052A9481982-04-23023 April 1982 Requests Addl Info Re TMI Action Plan Item II.K.3.3, Reporting Relief Valve & Safety Valve Failures.Response within 30 Days Requested Project stage: Other ML20052G1951982-05-10010 May 1982 Informs of No Relief or Safety Valve Failures or Challenges During Apr-Dec 1980 in Response to 820423 Request for Documentation & Commitment to NUREG-0737,Item II.K.3.3, Reporting Relief & Safety Valve Failures & Challenges Project stage: Request ML20053D7211982-05-27027 May 1982 Forwards Westinghouse Transmitting SAR for Deletion of Reactor Trip Following Turbine Trip Below 50% Power.Review Requested Against NUREG-0737,Item II.K.3.10 Concerns Project stage: Other ML20066D3001982-11-0303 November 1982 Informs That Since Unit 1 Anticipatory Trip Mod Is Enveloped by Unit 2 Analysis Basis,Analysis May Be Applied to Unit 1 Per Requirements of TMI Item II.K.3.10, Proposed Anticipatory Trip Mod Project stage: Other ML20084C5841984-04-24024 April 1984 Discusses 830808 Program Plan Rept for Detailed Control Room Design Review Containing Section Entitled, Mgt & Staffing, Outlining Min Qualification for Team Members.Resumes Encl Project stage: Request A06182, Responds to 861029 Request for util-proposed Tech Spec Changes Re Reporting of Safety Valve & Relief Valve Failure & Challenges,Control Room Habitability & Secondary Water Chemistry.Schedule for Submittal of Amend Requests Encl1986-12-10010 December 1986 Responds to 861029 Request for util-proposed Tech Spec Changes Re Reporting of Safety Valve & Relief Valve Failure & Challenges,Control Room Habitability & Secondary Water Chemistry.Schedule for Submittal of Amend Requests Encl Project stage: Request B12630, Proposed Tech Specs,Adding New Surveillance Requirement Re Control Room Habitability1987-08-0303 August 1987 Proposed Tech Specs,Adding New Surveillance Requirement Re Control Room Habitability Project stage: Other ML20236N0591987-08-0303 August 1987 Application for Amend to License DPR-65,adding New Surveillance Requirement Re Control Room Habitability.Fee Paid Project stage: Request 1980-04-15
[Table View] |
Text
.
Florida Power
-o, s
July 13, 1979 File:
3-0-3-e Director Office of Nuclear Reactor Regulation U.S.
Nu clea r Regu latory Commission Washington, D.C.
20355
Dear Sir:
Enclosed are three (3) originals and forty (40) copies of Technical Specification Change Requests No. 42 and 47 requesting amendment to Appendix A of Operating License DPR-72.
As part of these requ e s t s,
proposed replacement pages for Appendix A are enclost.
Florida Power Corporation considers Change Request No. 42 to be a Class III amendment per 10 CFR 170.22 as it iuvolves a single safety is su e.
This request represents a licensing fee of four thousand dollars ($4,000).
Florida Power Corporation is requesting an expeditious review of this change.
This technical specification change is required prior to startup after completion of the planned ECCS modification.
This nodif ication cou ld be accomplished as early as Jaly 22, 1979.
Change Request No. 47 is considered to be a Class III amendment per 10 CFR 170.22 as it involves a single safety ismae.
This amendment is exempt from licensing fees becau se it resu lt s from a written Commission request for Technical Specifications (NOTE: To 10 C FR 170.22).
The Commission's requ es t is ref erenced in the Chande Requ es t.
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General Othce ro1 invovm soeu so,en. p 6 so. um si pes
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Director Page 2 Ju ly 13, 1979 Office of Miclear Reactor Regu la t ion Therefore, a total licensing f ee of f ou r thousand dollars ($4,000) is enclosed as is a signed cop / of Certificate of Service for Technical Specificat ion Change Requests No. 42 and 47 to the Chief Executive of Cit ni s Cou n t y, Florida.
Ve ry t ru ly yat rs,
FLORIDA POWER CORPORATION l
,i // (n, G.
C.
Moore Assistant Vice President Powe r Production GCMenhRb D3 n~a f].]
L' L
STATE OF FLORIDA COUNTY OF PINELLAS G.
C. Moore states that he is the Assistant Vice President, Power Produ c t i o n, of Floridt. Power Corporation; that he is au thorized on the part of said company to siga and file with the Nu c lea r Regu latory Commission the information attached hereto; and that all such statements nide and cutters set forth therein are t ru e and correct to the best of his knowledge, inf ormat ion and belief.
//
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t G.
C.
- loore Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 13th day o f Ju ly, 1979.
fj y
(U$6h
._ ' '/4 Notary Pu bli(
Notary Pu blic, State of Florida at Large,
!!y Commission Expires:
Ju ly 2 5, 1980 (CRPNotary 1 D12) c -, y I
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN TIIE MATTER OF
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DOCKET NO. 50-302 FLORIDA POWER CORPORATION
)
CERTIFICATE OF SERVICE G. C. Moore deposes and says LSat the following has been served on the Chief Execttive of Citru s Caint y, Florida by deposit in the United States mail, addressed as follows:
Chairman, Board of County Conaissioners of Citnis Cou nty Cit ru s Cou nty Cou rthou se Inverness, Florida 32650 An original copy of revisions to Technical Specification Change Requests No. 42 and 47 requesting amendment to Appendix A of Operating icense No. DPR-72.
FLORIDA POWER UORPORATION J'.!
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G.
C.
Moore Assistant Vice President Power Production SWORN TO AND SUdSCRIBED BEFORE ME THIS 13th DAY OF JULY, 1979.
kb L,
Notary Riblic /
Notary Public State of Florida at Large My Commission expires:
July 25, 1980 (NOTARIAL SEAL)
(Cert. Serv.D12) r-t