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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20206N2621999-05-11011 May 1999 Application for Amend to License DPR-6 to Delete from Defueled Ts,Subsection 1.16,change Definition of Site & Other Associated Editorial Changes ML20217F5191998-03-28028 March 1998 Application for Amend to License DPR-6,per 10CFR50.90 Re Security Plan.Encl Withheld ML20138G1961997-04-30030 April 1997 Application for Amend to License DPR-6,requesting Name Change from Consumers Power Company to Consumers Energy Company, to Reflect Broader Scope of Energy Resources Available Through Company ML20138A9061997-04-22022 April 1997 Application for Amend to License DPR-6,requesting Change to TS to Withdraw Petition to Implement Option B Performance Based Requirements to App J of 10CFR50 ML20134H6281996-11-0707 November 1996 Application for Amend to License DPR-6,adding New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys ML20129C4611996-10-15015 October 1996 Application for Amend to License DPR-3,implementing Option B to Allow Use of Type a Test (Containment) Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining Boundaries) & Type C Test ML20056G3811993-08-24024 August 1993 Application for Amend to License DPR-6,revising 930719 Original Change,Reflects Revision to 10CFR50.36(a)(2) Re Changing Reporting Requirement for Effluent Releases from Semiannual to Annual ML20128D7081993-01-29029 January 1993 Application for Amend to License DPR-6,revising TS to Reflect Administrative Changes in Engineering,Offsite Review & QA Organization ML20059A2091990-08-14014 August 1990 Application for Amend to License DPR-6,reflecting Administrative & Organizational Changes ML20247L0891989-05-25025 May 1989 Application for Amend to License DPR-6,to Align Specs to 10CFR50,App J Requirements That Permit Removal of 24 H Duration Restriction on Integrated Leak Rate Test ML20205P6231988-10-24024 October 1988 Application for Amend to License DPR-6,deleting Tech Spec Requirements to Calibr Portable Gamma & Neutron dose-rate Measuring Instruments at Least Once Every 3 Months & Instead Follow ANSI N323-1978 ML20154S6371988-09-22022 September 1988 Application for Amend to License DPR-6,allowing Independent Review & Audit Functions by Independent Organizational Unit Rather than Standing Committee.Changes Consistent W/Bwr STS, ANSI N18.7-1976 & ANS 3.1-1987.Fee Paid ML20154P2111988-09-21021 September 1988 Application for Amend to License DPR-6,revising Tech Specs to Provide Clarification & Consistency by Reflecting Administrative & Editorial Corrections.Fee Paid ML20154D4761988-09-0808 September 1988 Application for Amend to License DPR-6,proposing Removal of Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes.Fee Paid ML20150C7831988-07-0505 July 1988 Application for Amend to License DPR-6,changing Tech Specs Re Reactor Depressurization Sys (Rds) Surveillance Testing, Eliminating Quarterly Partial Stroke Exercising of Rds Depressurizing Valves ML20148H6271988-03-22022 March 1988 Application for Amend to License DPR-6,changing Tech Specs Re Frequency of Reactor Depressurization Sys Depressurizing Valve Testing ML20237B9661987-12-14014 December 1987 Application for Amend to License DPR-6,removing Numerical Designator from I-type Fuel for Fuel Operating Cycle.Fee Paid ML20236N5021987-11-0909 November 1987 Application for Amend to License DPR-6,changing Tech Specs Administratively to Reflect Features & Terminology Used W/ New out-of-core Power Range Nuclear Instrumentation ML20236B3221987-07-23023 July 1987 Application for Amend to License DPR-6,consisting of Accumulated Administrative Changes ML20210C5961987-02-0404 February 1987 Application for Amend to License DPR-6,changing Tech Spec Section 5.2.1.b by Adding Table of Uncertainty Factors Associated W/Analysis of Core thermal-hydraulic Parameters Heat Flux,Maplhgr & Max Bundle Power ML20212F0301986-12-30030 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Include Second Scram Dump Tank Vent & Drain Valve ML20207C9541986-12-22022 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reduce Station Battery Design Time Interval from 8 to 2 H. Fee Paid ML20215F9941986-12-17017 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Add Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R & Generic Ltr 81-12.Request Supersedes 860421 Application ML20210E5141986-12-17017 December 1986 Application for Amend to License DPR-6,adding Operability & Surveillance Requirements for Alternate Shutdown Sys & Revising Tech Specs for Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg ML20215C7211986-12-0505 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reflect Use of New Hybrid Control Rods Mfg by Nucom,Inc & to Include Reload I-2 Fuel.Fee Paid ML20206M5081986-08-15015 August 1986 Application for Amend to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used W/New out-of-core source-range Nuclear Instrumentation ML20203P8021986-05-0101 May 1986 Application for Amend to License DPR-6,revising Tech Specs to Ensure Consistency w/831230 Exemption from Requirement to Have Two Senior Reactor Operators on Shift ML20203F6461986-04-21021 April 1986 Application for Amend to License DPR-6,changing Tech Specs Re Alternate Shutdown Battery Sys Operability & Surveillance Requirements ML20154K0181986-03-0404 March 1986 Application for Amend to License DPR-6,changing Tech Specs by Adding Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R ML20137V9621985-09-30030 September 1985 Application for Amend to License DPR-6,adding Operability & Surveillance Requirements for Components of Alternate Shutdown Sys Installed in Accordance w/10CFR50,App R ML20132F4561985-09-24024 September 1985 Revised Application for Amend to License DPR-6,changing I1 Fuel MAPLHGR Limits,Per 850816 Request,In Order to Implement Operating Limits for Reload Il Fuel ML20135B7971985-09-0303 September 1985 Application for Amend to License DPR-6,supplementing 741101 Proposed Tech Spec Change to Eliminate Min Control Rod Withdrawal Rate Limit ML20134E3011985-08-16016 August 1985 Application for Amend to License DPR-6,changing Tech Specs to Implement Reactor Operating Limits for Reload I1 Fuel ML20133M1131985-08-0505 August 1985 Application for Amend to License DPR-6,changing Tech Specs to Implement Staff Reorganization ML20132B7311985-07-19019 July 1985 Revised Application for Amend to License DPR-6,providing Tech Specs for Containment Pressure Monitor & Containment Water Level Monitor,Per NUREG-0737,Item II.F.1 ML20128B9131985-06-27027 June 1985 Application for Amend to License DPR-6,changing Tech Specs to Allow Operation of Plant Between Refueling Shutdowns W/O Potential of Requiring Surveillance Test to Be Performed.Fee Paid ML20126A0521985-06-0707 June 1985 Application for Amend to License DPR-6,incorporating Requirement to Adhere to Encl Plan for Big Rock Point Integrated Assessment. Fee Paid ML20128E4931985-05-24024 May 1985 Revised Application for Amend to License DPR-6,revising 840730 Tech Spec Change Request by Renumbering Definition Section 1.2.8 to 1.2.14 Re Administrative Controls ML20058E4011982-07-20020 July 1982 Application to Amend License DPR-6,changing Tech Specs Re Safety Mgt Function ML20058E3881982-07-20020 July 1982 Application to Amend License DPR-20,revising Tech Specs Re Safety Mgt Function ML20054J7321982-06-25025 June 1982 Application to Amend License DPR-6,changing Tech Specs to Change Technical Advisor from Shift to 24-h on-call Schedule 1999-05-11
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20206N2621999-05-11011 May 1999 Application for Amend to License DPR-6 to Delete from Defueled Ts,Subsection 1.16,change Definition of Site & Other Associated Editorial Changes ML20198K6581998-12-24024 December 1998 Amend 120 to License DPR-6,changing License DPR-6 & App a, TS to Reflect Permanetly Shutdown & Defueled Status of Plant ML20217F5191998-03-28028 March 1998 Application for Amend to License DPR-6,per 10CFR50.90 Re Security Plan.Encl Withheld ML20141J8651997-08-14014 August 1997 Amend 119 to License DPR-6,revising Plant License & TS to Reflect Company Name Change from CPC to Consumers Energy Co ML20138G1961997-04-30030 April 1997 Application for Amend to License DPR-6,requesting Name Change from Consumers Power Company to Consumers Energy Company, to Reflect Broader Scope of Energy Resources Available Through Company ML20138A9061997-04-22022 April 1997 Application for Amend to License DPR-6,requesting Change to TS to Withdraw Petition to Implement Option B Performance Based Requirements to App J of 10CFR50 ML20137J9321997-04-0202 April 1997 Amend 118 to License DPR-6,revising TS 4.2.9,to Add Additional Air Compressor ML20134H6281996-11-0707 November 1996 Application for Amend to License DPR-6,adding New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys ML20129C4611996-10-15015 October 1996 Application for Amend to License DPR-3,implementing Option B to Allow Use of Type a Test (Containment) Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining Boundaries) & Type C Test ML20058A1511993-11-15015 November 1993 Amend 112 to License DPR-6,changing TS to Implement Reorganization of Plant Staff ML20057E1951993-10-0505 October 1993 Amend 111 to License DPR-6,changing Reporting Requirements for Effluent Releases from Semiannual to Annual ML20056G3811993-08-24024 August 1993 Application for Amend to License DPR-6,revising 930719 Original Change,Reflects Revision to 10CFR50.36(a)(2) Re Changing Reporting Requirement for Effluent Releases from Semiannual to Annual ML20056E1651993-08-16016 August 1993 Amend 110 to License DPR-6,clarifying TS Re Undervoltage Breakers in RPS ML20128D7081993-01-29029 January 1993 Application for Amend to License DPR-6,revising TS to Reflect Administrative Changes in Engineering,Offsite Review & QA Organization ML20059A2091990-08-14014 August 1990 Application for Amend to License DPR-6,reflecting Administrative & Organizational Changes ML20246D2351989-08-16016 August 1989 Amend 100 to License DPR-6,revising Tech Specs to Provide for New Organizational Unit Entitled Nuclear Safety Svcs Dept to Discharge Offsite Safety Review Functions Instead of Nuclear Safety Board ML20245H8341989-07-28028 July 1989 Amend 98 to License DPR-6,requiring Compliance W/Amended Physical Security Plan ML20248C0571989-05-31031 May 1989 Amend 97 to License DPR-6,adding Operability & Surveillance Requirements for Alternate Shutdown Sys to Tech Spec Sections 11 & 12 & Including Tech Specs for Active Fire Barriers & Fire Detection Instrumentation ML20247L0891989-05-25025 May 1989 Application for Amend to License DPR-6,to Align Specs to 10CFR50,App J Requirements That Permit Removal of 24 H Duration Restriction on Integrated Leak Rate Test ML20246L8191989-05-0202 May 1989 Amend 96 to License DPR-6,revising OL to Allow for Increase in Amount of Byproduct Matl Plant May Possess & Use from 10.5 to 45 Ci Cs-137,as Sealed Sources ML20245F8251989-04-14014 April 1989 Amend 95 to License DPR-6,changing Tech Specs to Include Second Vent & Second Drain Valve to Scram Dump Tank ML20235J0231989-02-15015 February 1989 Amend 94 to License DPR-6,revising Station Battery Surveillance Test Time from 8 to 2 H ML20205S1241988-11-0404 November 1988 Amend 93 to License DPR-6,modifying Tech Specs by Replacing Requirements to partial-stroke Test Reactor Depressurization Sys Depressurizing Valves Quarterly W/Requirement to full- Stroke Test for Depressurizing Valves Each Outage ML20205P6231988-10-24024 October 1988 Application for Amend to License DPR-6,deleting Tech Spec Requirements to Calibr Portable Gamma & Neutron dose-rate Measuring Instruments at Least Once Every 3 Months & Instead Follow ANSI N323-1978 ML20154S6371988-09-22022 September 1988 Application for Amend to License DPR-6,allowing Independent Review & Audit Functions by Independent Organizational Unit Rather than Standing Committee.Changes Consistent W/Bwr STS, ANSI N18.7-1976 & ANS 3.1-1987.Fee Paid ML20154P2111988-09-21021 September 1988 Application for Amend to License DPR-6,revising Tech Specs to Provide Clarification & Consistency by Reflecting Administrative & Editorial Corrections.Fee Paid ML20154G1081988-09-14014 September 1988 Amend 92 to License DPR-6,modifying Paragraph 2.C.(5) of License Re Physical Security ML20154D4761988-09-0808 September 1988 Application for Amend to License DPR-6,proposing Removal of Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes.Fee Paid ML20150C7831988-07-0505 July 1988 Application for Amend to License DPR-6,changing Tech Specs Re Reactor Depressurization Sys (Rds) Surveillance Testing, Eliminating Quarterly Partial Stroke Exercising of Rds Depressurizing Valves ML20154J1871988-05-17017 May 1988 Amend 91 to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used W/New out-of-core Power Range Instrumentation ML20154H5251988-05-17017 May 1988 Amend 90 to License DPR-6,allowing Inclusion of All Reloads of I Fuel Design in Tech Specs ML20148H6271988-03-22022 March 1988 Application for Amend to License DPR-6,changing Tech Specs Re Frequency of Reactor Depressurization Sys Depressurizing Valve Testing ML20237B9661987-12-14014 December 1987 Application for Amend to License DPR-6,removing Numerical Designator from I-type Fuel for Fuel Operating Cycle.Fee Paid ML20236N5021987-11-0909 November 1987 Application for Amend to License DPR-6,changing Tech Specs Administratively to Reflect Features & Terminology Used W/ New out-of-core Power Range Nuclear Instrumentation ML20236B3221987-07-23023 July 1987 Application for Amend to License DPR-6,consisting of Accumulated Administrative Changes ML20211P1321987-02-19019 February 1987 Amend 89 to License DPR-6,revising Tech Spec Section 5.2.1.b to Add Table of Uncertainty Factors Re Analysis of Core Thermal Hydraulic Parameters for Reload I-2 Fuel & to Provide Footnotes Delineating Use of Values ML20211N5181987-02-17017 February 1987 Amend 88 to License DPR-6,revising Tech Spec Section 5.1 to Reflect Use of New Nucom,Inc Hybrid Control Rods in Cycle 22 Core ML20210C5961987-02-0404 February 1987 Application for Amend to License DPR-6,changing Tech Spec Section 5.2.1.b by Adding Table of Uncertainty Factors Associated W/Analysis of Core thermal-hydraulic Parameters Heat Flux,Maplhgr & Max Bundle Power ML20209H0481987-01-28028 January 1987 Amend 87 to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used in Conjunction W/Installation of New source-range Monitoring Instrumentation ML20212F0301986-12-30030 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Include Second Scram Dump Tank Vent & Drain Valve ML20207C9541986-12-22022 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reduce Station Battery Design Time Interval from 8 to 2 H. Fee Paid ML20215F9941986-12-17017 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Add Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R & Generic Ltr 81-12.Request Supersedes 860421 Application ML20210E5141986-12-17017 December 1986 Application for Amend to License DPR-6,adding Operability & Surveillance Requirements for Alternate Shutdown Sys & Revising Tech Specs for Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg ML20215C7211986-12-0505 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reflect Use of New Hybrid Control Rods Mfg by Nucom,Inc & to Include Reload I-2 Fuel.Fee Paid ML20206M5081986-08-15015 August 1986 Application for Amend to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used W/New out-of-core source-range Nuclear Instrumentation ML20211P3751986-07-11011 July 1986 Amend 86 to License DPR-6,adding Tech Spec Table Sentence Establishing Min Requirements for Shift Crew Composition During Various Operating Conditions ML20198A3801986-05-12012 May 1986 Amend 85 to License DPR-6,adding Definition for Reportable Event & Deleting Reporting Requirements Included in 10CFR50.72 & 50.73 ML20210P1651986-05-0606 May 1986 Amend 84 to License DPR-6,adding Condition to CRD Surveillance Testing Requiring Testing Prior to Startup Following Outages of More than 120 Days ML20203P8021986-05-0101 May 1986 Application for Amend to License DPR-6,revising Tech Specs to Ensure Consistency w/831230 Exemption from Requirement to Have Two Senior Reactor Operators on Shift ML20203F6461986-04-21021 April 1986 Application for Amend to License DPR-6,changing Tech Specs Re Alternate Shutdown Battery Sys Operability & Surveillance Requirements 1999-05-11
[Table view] |
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'
. CONSUMERS ENERGY COMPANY
, D0CKET 50-155 Request for Change to the Facility Operating License License DPR-6 For the reasons hereinafter set forth, it is requested that the Facility Operating License DPR-6, Docket 50-155, issued to Consumers Power Company on May 1,1964, for the Big Rock Point Plant be changed as described in Section I below:
Revised License pages are attached. Proposed changes are shown by a back-slash in the right-hand margin.
I. CHANGES License No DPR-6 The first page of the Operating License requires replacing Consumers Power Company with Consumers Energy Company in the heading, paragraph A., paragraph B, and the Note at the bottom of the page. If Consumers Power Company (a.k.a. CPCo) is clearly used as a reference, it will not.be revised to read Consumers Energy Company.
Technical Specifications 7.2.4(b) Revise " Consumers Power Company General Office" to read " Consumers Energy Company General office".
7.2.4(c)(2) Revise " Consumers Power Company" to read " Consumers Energy Company".
6.5.2.6.b Revise " Consumers Power Company" to read " Consumers Energy Company".
II. DISCUSSION On January 1, 1997, Consumers Power Company began doing business under an assumed name of Consumers Energy Company. On March 11, 1997, the shareholders of Consumers Power Company approved the name change from " Consumers Power Company" to
" Consumers Energy Company". The name change reflects the broader scope of energy resources available through the company which is important as the company enters a competitive market place under impending electric utility deregulation.
The proposed changes are administrative and involve only the name change; the corporate structure remains the same, and all legal characteristics remain the same. Thus there is neither a change in the ownership, state of incorporation, registered agent, registered office, directors, officers, rights or liabilities of the Company nor the function of the Company or the way in which it does business.
The Company's financial responsibility for the Big Rock Point Plant and its sources of funds to support the facility remain the same. Further, this name change does not impact the Company's ability to comply with any of its obligations or responsibilities under the license. The change of the company name from
" Consumers Power Company" to " Consumers Energy Company" is clearly an administrative change. It does not require a technical, financial qualification, or an antitrust review. Therefore, this change does not reduce the level of safety imposed by the current Facility Operating License, Technical Specifications, the or Updated Final Hazards Summary Report.
9705060212 970430 l PDR ADOCK 05000155 !
P PDR ,
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BIG ROCK POINf TECH SPEC CHANGE REQUEST 2
, April 30, 1997 III. ANALYSIS OF N0 SIGNIFICANT HAZARDS CONSIDERATI0E In accordance with 10 CFR 50.92, Consumers Energy Company has made a determination that the proposed amendment involves no significant hazards considerations. To l make this determination, Consumers Energy Company has established that operation
' in accordance with the proposed amendment will not : 1) involve a significant increase in the probability or consequences of an accident previously evaluated, or 2) create the possibility of a new or different kind of accident from any 1
accident previously evaluated, or 3) involve a significant reduction in a margin of safety.
The proposed changes do not- i l
l 1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes alter the company name in the Facility Operating License and Technical Specifications to reflect the change from " Consumers Power Company" to
" Consumers Energy Company". The company will continue to own all of the same assets, will continue to serve the same customers, and will continue to honor all exi:: ting obligations and commitments.
Since the proposed changes do not alter the technical content of any Facility Operating License or Technical Specifications requirements, they do not alter the design, function, or operation of any plant structure, system, or component.
Therefore, the changes will not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes alter the company name in the Facility Operating License and Technical Specifications to reflect the change from " Consumers Power Company" to i
" Consumers Energy Company". The company will continue to own all of the same '
assets, will continue to serve the same customers, and will continue to honor all existing obligations and commitments.
Since the proposed changes do not alter the technical content of any Facility Operating License or Technical Specifications requirements, they do not alter the design, function, or operation of any plant structure, system, or coc onent.
Therefore, the changes will not create the possibility of a new or different kind
- of accident from any previously evaluated.
1 I
i I
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BIG ROCK POINT TECH SPEC CHANGE REQUEST
~ 3 April 30, 1997 l
- 3) Involve a significant reduction in a margin of safety ,
l l Since the proposed changes do not alter the technical content of any Facility i Operating License or Technical Specifications requirements, they do not alter the l design, function, or operation of any plant structure, system, or component.
Therefore, the changes will not involve a reduction in a margin of safety.
IV. CONCLUSION The Big Rock Point Plant Review Committee has reviewed this Technical Specification Change Request and has determined this change does not involve an l unreviewed safety question and, therefore, involves no significant hazards consideration. This change has been reviewed by the Nuclear Performance Assessment Department. A copy of this change request has been sent to the State of Michigan I official designated to receive such Amendments to the Operating License.
CONSUMERS ENERGY COMPANY To the best of my knowledge, information and belief, the contents of this submittal are truthful and complete.
gG 5 Robert J Addy Plant Manger 4 1
Sworn and subscribed to before me this 30th day of April 1997.
0 n nJbs, a nw han%
Jesifer,1ynn Helms, Notary Public ,
C)iarlevoix County, Michigan My commission expires August 29, 1999. '
l (SEAL) i
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ATTACHMENT 1 ,
CONSUMERS ENERGY COMPANY BIG ROCK POINT PLANT >
DOCKET 50-155 ;
As Proposed Submitted April 30, 1997 1
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l 3 Pages i
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. UNITED STATES NUCLEAR REGULATORY COMMISSION I WASHINGTON, DC 20555 I
CONSUMERS ENERGY I
/
DOCKET N0 50-155 BIG ROCK POINT PLANT FACILITY OPERATING LICENSE License No DPR-6 A. This license applies to the Big Rock Point Plant, a boiling water reactor l and associated equipment (the facility), owned by the Consumers Energy /
Company (the licensee). The facility is located in Charlevoix County, Michigan, and is described in the licensee's application dated January 14, 1960, and the Final Hazards Summary Report; as supplemented and amended j by subsequent filings by the licensee. ;
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Consumers Energy Company: /
(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, " Licensing of Production and Utilization Facilities" to possess, use and i operate the facility at the Asignated location in Charlevoix County, '
Michigan, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material,"
to receive, possess, and use at any one time up to (a) 2500 kilograms of contained uranium 235 as fuel, (b) 10.32 grams of uranium 235 as contained in fission counters, (c) 150* kilograms of plutonium contained in Pu0,-00, fuel rods, and. (d) 5 curies of plutonium encapsulated as a plutonium-beryllium neutron source, all in connection with operation of the facility, subject to the following conditions:
(a) A technical specification will be instituted to assure that the plant will not operate if the capacity of the makeup line to remove heat from the spent fuel pool is insufficient for the heat generating capacity of the pool inventory, considering the power history of each assembly in the pool, the number of assemblies in the pool and the effect of lake temperature on the heat-removal capacity of the makeup water system.
- Note: (For internal Consumers Energy Company clarification.) Amendment /
No 4 dated 12/6/72 established that CP Co could have 150 Kg of Pu in mixed-oxide fuel bundles. However, this was limited to 50 Kg until the GESMO question was finalized. Reference 10/13/75 letter and NRC order dated 8/11/75.
AS PROPOSED
, 7.0 OPERATING PROCEDURES i
'This section describes those basic operating principles and procedural i i safeguards which have a potential effect on safety. Operating :
principles and procedures are presented for normal and emergency operation of the plant, for Phase II testing within the Research and Development Program, and for operational testing of the nuclear safeguards systems of the plant. i t (Section 7.1 through 7.2.3 deleted by Amendment No. 9 dated 12/19/75) !
t 1 l 7.2.4 Administrative and Procedural Controls Relatina to Hiah Performance Fuel l l In addition to normal operating procedures, the following additional '
precautions shall be observed during irradiation of the centermelt fuel :
l assemblies:
I (a) In the event of suspected coolant system leaks, reactor power will be immediately reduced to permit entry for inspection purposes and an evaluation of the suspected leak will be made. If the evaluation reveals leakage in the primary cooling system, the ,
reactor shall be shut down immediately, except when it has been !
established that the leaks are in valves, packing or pumps where some leakage can be tolerated. q (b) The Plant Manager or his designated alternate shall be j notified immediately of all reactor scrans and shall approve !
subsequent start-ups. Start-up of the reactor following a scram shall not proceed until the cause of the scram has been determined !
and the necessary corrective action taken. The evaluation and '
approval of the Consumers Energy Company General Office shall be /
required for all start-ups following and unexplained scram.
(c) Technical Specialists On-Site:
(1) The General Electric Company shall have a physicist familiar with the Big Rock Point Plant present at the facility for. each initial start-up following refueling. He shall be present during the initial approach to criticality and shall remain until at least 10% of rated power is reached.
(2) Consumers Energy Company shall have a Reactor Engineer or /
his designated alternate who shall be a licensed senior operator in the control room for all start-ups, special tests or significant power changes.
7.3 NORMAL OPERATION 7.3.1 General Detailed operating procedures for each normal mode of plant operation shall be prepared prior to operation.
61 AS PROPOSED l
. ADMINISTRATIVE CONTROLS j
6.5.2.4.2 (Continued) I
- 1. The Process Control Program and implementing procedures for processing and packaging of radioactive wastes at ;
least once per 24 months. '
Audit reports encompassed by 6.5.2.4.2 above shall be forwarded to the Director, NPAD, and management positions j responsible for the areas audited within thirty (30) days i after completion of the audit. I 6.5.2.4.3 NPAD review of the subjects in Specifications 6.5.2.4.1 and '
6.5.2.4.2 shall be performed by an assigned Nuclear Performance Specialist selected on the basis of technical expertise relative to the subject on the basis of technical expertise i being reviewed. If the assigned Nuclear Performance Specialist determines the need for interdisciplinary review, a committee consisting of the Director, NPAD, or his designate, and at least four Nuclear Performance Specialists, shall be assigned. Such committee shall meet as conditions requiring interdisciplinary review arise, but no less than twice yearly. ;
J AUTHORITY 6.5.2.5 The NPAD shall report to and advise the Vice President - Nuclear Operations of significant findings associated with those areas of responsibility specified in Section 6.5.2.4.1 and Section 6.5.2.4.2.
RECORDS 6.5.2.6 Records of NPAD activities shall be maintained. Reports shall be prepared and distributed as indicated below:
- a. The results of reviews performed >ursuant to Section 6.5.2.4.1 and Section 6.5.2.4.2 s tall be reported to the Vice President - Nuclear Operations at least monthly,
- b. A report assessing the overall nuclear safety performance of the Big Rock Point Plant shall be provided to senior Consumers Energy Company management annually. /
6.,.1 (Deleted) 6.7 SAFETY LIMIT VIOLATIQN 6.7.1 The following actions shall be taken in the event a safety limit is violated:
- a. The reactor shall be shut down immediately and not restarted until the Commission authorizes resumption of operation (10 CFR 50.36(c)(1)(1)(A)).
80 AS PROPOSED