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Category:FEDERAL REGISTER NOTICES
MONTHYEARML20206K4731999-04-27027 April 1999 Notice of Withdrawal of 981016 Application for Amend to FOL DPR-72 to Change CR-3 Fsar,Improved TSs & ITS Bases to Resolve Unreviewed Safety Question ML20196C3031998-11-24024 November 1998 Notice of Withdrawal of Application for Amend to Facility Operating License.Amend Would Revise CR3 TS Re Decay Heat Removal Requirements in Mod 4 ML20128H3981996-10-0707 October 1996 Notice of Issuance of Director'S Decision Re Action Taken on 960328 Petition for Action Under 10CFR2.206 Filed on Behalf of Bl Bennett Re Plant ML20125A4661992-11-27027 November 1992 Notice of Withdrawal of Application for Amend to License DPR-72.Proposed Amend Would Have Revised TS to Add New Action to Containment Air Lock Spec ML20248E7991989-09-25025 September 1989 Notice of Consideration of Issuance of Amend to License DPR-72 & Proposed NSHC Determination & Opportunity for Hearing.Amend Permits one-time Delay of 18-month Diesel Generator full-load Test Until Next Refueling Outage ML20245C8461989-04-20020 April 1989 Notice of Withdrawal of 840116 & 850329 Applications for Amends to License DPR-72 to Modify Tech Specs to Include silicon-controlled Rectifiers in Appropriate Surveillance & Test Sections ML20236T3031987-11-24024 November 1987 Notice of Consideration of Issuance of Amend to License DPR-72 & Proposed NSHC Determination & Opportunity for Hearing.Amend Changes Surveillance Requirement for Emergency Diesel Generator Loading DD-87-18, Notice of Issuance of Director'S Decision DD-87-18 Under 10CFR2.206 Denying Ucs Petition to Suspend B&W OLs & CPs1987-10-19019 October 1987 Notice of Issuance of Director'S Decision DD-87-18 Under 10CFR2.206 Denying Ucs Petition to Suspend B&W OLs & CPs ML20210Q0551986-05-0202 May 1986 Notice of Consideration of Issuance of Amend to License DPR-72 & Proposed NSHC Determination & Opportunity for Hearing.Amend Permits Plant Operation W/Redesigned Reactor Coolant Pump Supports ML20128G3701985-06-18018 June 1985 Notice of Consideration of Issuance of Amend to License DPR-72 & Proposed NSHC Determination & Opportunity for Hearing.Amend Resolves Conflicts Between Current Tech Specs & Commitments Re Low Temp Overpressurization Protection ML20062B2321978-07-24024 July 1978 Notice of Issuance of Amend 15 to License DPR-72 & Negative Declaration 1999-04-27
[Table view] Category:TEXT-CODE OF FEDERAL REGULATIONS
MONTHYEARML20206K4731999-04-27027 April 1999 Notice of Withdrawal of 981016 Application for Amend to FOL DPR-72 to Change CR-3 Fsar,Improved TSs & ITS Bases to Resolve Unreviewed Safety Question ML20196C3031998-11-24024 November 1998 Notice of Withdrawal of Application for Amend to Facility Operating License.Amend Would Revise CR3 TS Re Decay Heat Removal Requirements in Mod 4 ML20128H3981996-10-0707 October 1996 Notice of Issuance of Director'S Decision Re Action Taken on 960328 Petition for Action Under 10CFR2.206 Filed on Behalf of Bl Bennett Re Plant ML20125A4661992-11-27027 November 1992 Notice of Withdrawal of Application for Amend to License DPR-72.Proposed Amend Would Have Revised TS to Add New Action to Containment Air Lock Spec ML20248E7991989-09-25025 September 1989 Notice of Consideration of Issuance of Amend to License DPR-72 & Proposed NSHC Determination & Opportunity for Hearing.Amend Permits one-time Delay of 18-month Diesel Generator full-load Test Until Next Refueling Outage ML20245C8461989-04-20020 April 1989 Notice of Withdrawal of 840116 & 850329 Applications for Amends to License DPR-72 to Modify Tech Specs to Include silicon-controlled Rectifiers in Appropriate Surveillance & Test Sections ML20236T3031987-11-24024 November 1987 Notice of Consideration of Issuance of Amend to License DPR-72 & Proposed NSHC Determination & Opportunity for Hearing.Amend Changes Surveillance Requirement for Emergency Diesel Generator Loading DD-87-18, Notice of Issuance of Director'S Decision DD-87-18 Under 10CFR2.206 Denying Ucs Petition to Suspend B&W OLs & CPs1987-10-19019 October 1987 Notice of Issuance of Director'S Decision DD-87-18 Under 10CFR2.206 Denying Ucs Petition to Suspend B&W OLs & CPs ML20210Q0551986-05-0202 May 1986 Notice of Consideration of Issuance of Amend to License DPR-72 & Proposed NSHC Determination & Opportunity for Hearing.Amend Permits Plant Operation W/Redesigned Reactor Coolant Pump Supports ML20128G3701985-06-18018 June 1985 Notice of Consideration of Issuance of Amend to License DPR-72 & Proposed NSHC Determination & Opportunity for Hearing.Amend Resolves Conflicts Between Current Tech Specs & Commitments Re Low Temp Overpressurization Protection ML20062B2321978-07-24024 July 1978 Notice of Issuance of Amend 15 to License DPR-72 & Negative Declaration 1999-04-27
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l 7590-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION l I
FLORIDA POWER CORPORATION DOCKET NO. 50-302 NOTICE OF WITHDRAWAL OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE The U.S. Nuclear Regulatory Commission (the Commission) has granted a request by the Florida Power Corporation (FPC) to withdraw its October 31,1997, application for an amendment to Facility Operating License No. DPR 72, issued to FPC for operation of the Crystal River Nuclear Generating Unit 3 (CR3) located in Citrus County, Florida. Notice of consideration of i
issuance of this amendment was published in the Federa/ Registeron November 12,1997 l
l (62 FR 60735).
The proposed amendment would have revised the CR3 Technical Specifications (TS) relating to decay heat removal requirements in Mode 4. The proposed modification would have revised the TS and associated Bases to require in Mode 4, one operable emergency feedwater l l
(EFW) train and associated equipment, including the EFW tank, emergency feedwater initiation and control ar,tuation instrumentation for EFW, post accident monitoring instrumentation, and the turbine bypass vaives. Additionally, the TS and associated Bases would have been revised to require in Mode 4, a low-pressure injecton (LPI) train, dedicated to the borated water storage tank, and to reflect that the available loops for decay heat removal do not include this dedicated LPI train. Editorial changes would also have been made to clarify the description of Mode 4 accidents requiring emergency core cooling system injection, and to revise the title of TS limiting condition for operation 3.7.5.
9812O20027 901124 l PDR ADOCK 05000302 l P PDR l l
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FPC's letter of November 18,1998, informed the staff that the request was being withdrawn because the NRC staff had indicated that the subject of reactor decay heat removal l
requirements during Mode 4 operation would be treated as a generic industry issue. In this letter, FPC committed to continue to maintain administrative controls for the additional equipment and capability to remove decay heat identified in the October 31,1997, request during Mode 4
, operation of CR-3. '
For further details with respect to this action, see the application for amendment dated
- October 31,1997, and FPC's withdrawal letter dated November 18,1998, which are available for public inspection at the Commission's Public Document Room, the Gelman Building,2120 L Street, NW., Washington, DC and at the local public document room located at the Coastal Region Library,8619 W. Crystal Street, Crystal Rwer, Florida.
Dated at Rockville, Maryland, this 24 th day of November 1998.
For the Nuclear Regulatory Commission f
Leonard A. Wiens, Senior Project Manager Project Directorate II-3 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation o
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