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Category:FEDERAL REGISTER NOTICES
MONTHYEARML20199E7321998-12-24024 December 1998 Notice of Partial Withdrawal of 970919 Application for Amend to License DPR-6 for Big Rock Point Plant.Proposed Amend Would Change App A,Ts,To License to Reflect Permanently Shutdown & Defueled Conditon of Big Rock Plant Facility ML20217Q6891997-08-28028 August 1997 Notice of Withdrawal of Application for Amend to License DPR-6 Re Mod of TS Re Use of Option B Performance Based Requirements of App J to 10CFR50 for Type A,B & C Tests ML20246D2441989-08-16016 August 1989 Notice of Issuance of Amend to License DPR-6,modifying Tech Specs 6.2 & 6.5 to Reflect Replacement of Nuclear Safety Board W/Nuclear Safety Svcs Department & Elimination of Independent Safety Engineering Group ML20247F1741989-03-23023 March 1989 Notice of Consideration of Issuance of Amend to License DPR-6 & Opportunity for Hearing on 881024 Proposed Amend to Tech Specs Re Semiannual Calibr Frequency & Source Check of Gamma & Neutron dose-rate Measuring Instruments ML20247E9551989-03-21021 March 1989 Notice of Consideration of Issuance of Amend to License DPR-6 & Opportunity for Hearing on 880922 & 890117 Requests to Revise Tech Specs to Provide for New Organizational Unit (Nuclear Safety Svcs Dept) to Discharge Review Functions ML20206C1841988-11-0404 November 1988 Notice of Issuance of Amend 93 to License DPR-6,modifying Tech Specs by Replacing Quarterly partial-stroke Test for Reactor Depressurization Sys Depressurizing Valves W/ Requirement to full-stroke Test All Valves Each Outage ML20151W9211988-08-12012 August 1988 Notice of Consideration of Issuance of Amend to License DPR-6 & Opportunity for Hearing.Amend Modifies Tech Specs by Replacing Requirement to partial-stroke Test Reactor Depressurization Sys ML20154J2011988-05-17017 May 1988 Notice of Consideration of Issuance of Amend 91 to License DPR-6 & Proposed NSHC Determination & Opportunity for Hearing.Amend Revises Tech Spec to Reflect Features & Terminology Used W/New out-of-core Power Range ML20151N4461988-03-25025 March 1988 Notice of Consideration of Issuance of Amend to License DPR-6 & Opportunity for Hearing.Amend Revises Provisions in Plant Tech Specs Re Installation of New out-of-core Power Range Instrumentation ML20215M6791987-05-11011 May 1987 Notice of Proposed Corporate Restructuring Per Util ML20207S1731987-02-12012 February 1987 Notice of Denial of Portion of 861205 Application to Amend License DPR-6,modifying Tables on Reactor Operating Parameters to Support Use of Reload I-2 Fuel to Be Installed During 1987 Refueling Outage for Cycle 22 ML20133A6431985-09-26026 September 1985 Notice of Consideration of Amend to License DPR-6 & Proposed NSHC Determination & Opportunity for Hearing Re 850816 & 0924 Requests Concerning Reactor Core Reload 11 Fuel Design ML20126E1691975-12-19019 December 1975 Notice of Issuance & Availability of Amend 9 to License DPR-6 ML20126E1911974-11-0505 November 1974 Notice of Issuance & Availability of Amend 8 to License DPR-6 ML20126E1181974-07-18018 July 1974 Notice of Issuance & Availability of Amend 6 to License DPR-6 ML20126E6081964-05-0101 May 1964 Notice of Issuance & Availability of OL 1998-12-24
[Table view] Category:TEXT-CODE OF FEDERAL REGULATIONS
MONTHYEARML20199E7321998-12-24024 December 1998 Notice of Partial Withdrawal of 970919 Application for Amend to License DPR-6 for Big Rock Point Plant.Proposed Amend Would Change App A,Ts,To License to Reflect Permanently Shutdown & Defueled Conditon of Big Rock Plant Facility ML20217Q6891997-08-28028 August 1997 Notice of Withdrawal of Application for Amend to License DPR-6 Re Mod of TS Re Use of Option B Performance Based Requirements of App J to 10CFR50 for Type A,B & C Tests ML20246D2441989-08-16016 August 1989 Notice of Issuance of Amend to License DPR-6,modifying Tech Specs 6.2 & 6.5 to Reflect Replacement of Nuclear Safety Board W/Nuclear Safety Svcs Department & Elimination of Independent Safety Engineering Group ML20247F1741989-03-23023 March 1989 Notice of Consideration of Issuance of Amend to License DPR-6 & Opportunity for Hearing on 881024 Proposed Amend to Tech Specs Re Semiannual Calibr Frequency & Source Check of Gamma & Neutron dose-rate Measuring Instruments ML20247E9551989-03-21021 March 1989 Notice of Consideration of Issuance of Amend to License DPR-6 & Opportunity for Hearing on 880922 & 890117 Requests to Revise Tech Specs to Provide for New Organizational Unit (Nuclear Safety Svcs Dept) to Discharge Review Functions ML20206C1841988-11-0404 November 1988 Notice of Issuance of Amend 93 to License DPR-6,modifying Tech Specs by Replacing Quarterly partial-stroke Test for Reactor Depressurization Sys Depressurizing Valves W/ Requirement to full-stroke Test All Valves Each Outage ML20151W9211988-08-12012 August 1988 Notice of Consideration of Issuance of Amend to License DPR-6 & Opportunity for Hearing.Amend Modifies Tech Specs by Replacing Requirement to partial-stroke Test Reactor Depressurization Sys ML20154J2011988-05-17017 May 1988 Notice of Consideration of Issuance of Amend 91 to License DPR-6 & Proposed NSHC Determination & Opportunity for Hearing.Amend Revises Tech Spec to Reflect Features & Terminology Used W/New out-of-core Power Range ML20151N4461988-03-25025 March 1988 Notice of Consideration of Issuance of Amend to License DPR-6 & Opportunity for Hearing.Amend Revises Provisions in Plant Tech Specs Re Installation of New out-of-core Power Range Instrumentation ML20215M6791987-05-11011 May 1987 Notice of Proposed Corporate Restructuring Per Util ML20207S1731987-02-12012 February 1987 Notice of Denial of Portion of 861205 Application to Amend License DPR-6,modifying Tables on Reactor Operating Parameters to Support Use of Reload I-2 Fuel to Be Installed During 1987 Refueling Outage for Cycle 22 ML20133A6431985-09-26026 September 1985 Notice of Consideration of Amend to License DPR-6 & Proposed NSHC Determination & Opportunity for Hearing Re 850816 & 0924 Requests Concerning Reactor Core Reload 11 Fuel Design ML20126E1691975-12-19019 December 1975 Notice of Issuance & Availability of Amend 9 to License DPR-6 ML20126E1911974-11-0505 November 1974 Notice of Issuance & Availability of Amend 8 to License DPR-6 ML20126E1181974-07-18018 July 1974 Notice of Issuance & Availability of Amend 6 to License DPR-6 ML20126E6081964-05-0101 May 1964 Notice of Issuance & Availability of OL 1998-12-24
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7590-01
_ UNITED STATES NUCLEAR REGULATORY COMMISSION CONSUMERS POWER COMPANY DOCKET NO. 50-155
. DENIAL 0F AMENDMENT TO FACILITY OPERATING LICENSE AND OPPORTUNITY FOR HEARING The U.S. Nuclear Regulatory Commission (the Commission) has denied in part a request by Consumers Power Company (the licensee) for an amendment to Facility Operating License No. DPR-6, issued to Consumers Power Company for operation of the Big Rock Point Plant, located in Charlevoix County, Michigan.
The amendment, as proposed by the licensee in the application dated December 5,1986, would revise portions of Sections 5.1 and 5.2 of the Big Rock Point Technical Specifications. The proposed change to Section 5.1 reflects the planned use of new hybrid control rods in the core. These hybrid control rods are manufactured by NUCOM, Incorporated. The proposed change to Section 5.2 modifies two tahles on reactor operating parameters to support the use of Reload I-2 fuel which would be installed during the 1987 refueling outage -
for Cycle 22. Notice of consideration of issuance of this amendment was published in the FEDERAL REGISTER on January 14,1987(52FR1551). The proposed change to Section 5.1 concerning the planned use o'f hybrid control i
i rods in the core is being handled as a separate licensing action. The proposed !
l change to Section 5.2 concerning modification of two tables of reactor operating parameters to support the use of Reload I-2 fuel was denied.
i At present, Table 1 of Section 5.2.1(b) provides reactor operating parameters for all previous fuel reloads through Reload I-1 fuel. The request proposes to revise this table to support Reload I-2 fuel. After review of the reactor operating parameters contained in this table, the Co~ mmission found 8703190078 870212 -
PDR ADOCK 05000155 P PDR
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7590-01 this request unacceptable. This request was found unacceptable because ,
r additional information, provided at the request of the staff, indicates that operation at the existing Technical Specification limit could result in violation of the safety limit for the most limiting transients.
The licensee was notified of the Commission's denial of this portion of its request by letter dated February 12, 1987.
By March 23, 1987, the licensee may demand a hearing with respect to the denial described above and any person whose interest may be affected by this proceeding may file a written petition for leave to intervene.
A request for a hearing or petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commiss' ion, Washington, D.C. 20555 Attention: Docketing and Service Branch, or may be delivered to the Commission's Public Document Room,1717 H Street, NW, Washington, D.C., by the above date.
A copy of any petitions should also be sent to the Office of the General Counsel-Bethesda, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, ;
and to Judd L. Bacon, Esquire, Consumers Power Company, 212 West Michigan Avenue, Jackson, Michigan 49201, attorney for the licensee.
For further details with respect to this action, see (1) the application for emendment dated December 5,1986, and (2) the Commission's letter and '
Safety Evaluation dated February 12, 1987, which are available for public inspection at the Commission's Public Document Room, 1717 H Street, NW, Washington, D.C., and at the North Central Michigan College Library, 1515 Howard Street, Petoskey, Michigan 49770. A copy of item (2) may be i
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. 7590-01 obtained upon request addressed to the U.S. Nuclear Regulatory Comission, ,
Washington, D.C.
20555, Attention: Director, Division of BWR Licensing.
Dated at Pethesda, Maryland, this 12th day of February 1987 FOR THE NUCLEAR REGULATORY COMMISSION i
Rr,Jender Auluck, Acting Director ikR Project Directorate #1 Division of RWR Licensing O
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