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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20198K6581998-12-24024 December 1998 Amend 120 to License DPR-6,changing License DPR-6 & App a, TS to Reflect Permanetly Shutdown & Defueled Status of Plant 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 ML20137J9321997-04-0202 April 1997 Amend 118 to License DPR-6,revising TS 4.2.9,to Add Additional Air Compressor 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 ML20056E1651993-08-16016 August 1993 Amend 110 to License DPR-6,clarifying TS Re Undervoltage Breakers in RPS ML20044G4871993-05-24024 May 1993 Amend 170 to License DPR-6,revising Administrative Control Section to Reflect Restructuring of Nuclear Operations Dept 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 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 ML20154G1081988-09-14014 September 1988 Amend 92 to License DPR-6,modifying Paragraph 2.C.(5) of License Re Physical Security 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 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 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 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 ML20141N6561986-03-10010 March 1986 Amend 83 to License DPR-6,revising Tech Specs to Incorporate Name Change & Revised Staff Organization Chart & to Correct Typo ML20154A0781986-02-12012 February 1986 Amend 82 to License DPR-6,incorporating Requirement to Adhere to Plan for Big Rock Point Integrated Assessment & Terms for Implementing Changes to Plan Contents ML20205F6001985-11-0101 November 1985 Amend 81 to License DPR-6,revising Tech Specs Re Reload I1 Fuel MAPLHGR Limits & Min Critical Power Ratio to Support Fuel Reloading ML20133N3881985-10-22022 October 1985 Amend 79 to License DPR-6,re Changes to Several Tech Spec Surveillance Frequencies to Provide for Operation Between Refueling Shutdowns W/O Potential Surveillance Test Performance Interruptions ML20137W3101985-10-0202 October 1985 Amend 78 to License DPR-6,modifying Tech Specs by Implementing Definition of Operability & Incorporating Limiting Conditions for Operation for Redundant Safety Sys ML20134K1891985-08-26026 August 1985 Amend 77 to License DPR-6,incorporating Radiological Effluent Tech Specs Which Meet Requirements of 10CFR50,App I & Including Administrative Changes Which Relocate & Reformat Tech Specs ML20128H8151985-07-0101 July 1985 Amend 76 to License DPR-6,approving Administrative Control Tech Spec Changes Re Offsite Corporate Reorganizations of Util QA & Nuclear Activities Plant Organizations ML20126A4331985-06-10010 June 1985 Amend 75 to License DPR-6,incorporating Description of & Operating Requirements for New Stack Gas Monitoring Sys ML20126E7001985-06-0707 June 1985 Amend 74 to License DPR-6,modifying Tech Specs to Include Modified Reactor Encl Treated Waste Line Isolation Valve in List of Local Leak Rate Tested Automatic Containment Isolation Valves ML20024E5131983-08-11011 August 1983 Amend 60 to License DPR-6,revising Tech Specs to Institute Procedure for Use During Startup in Event Neutron Source Strength Too Low to Provide Min Specified Count Rate ML20054B2531982-04-0808 April 1982 Amend 53 to License DPR-6,revising Tech Specs for Core Thermal Limits to Accommodate Deuterium Fuel ML20041C0181982-02-0404 February 1982 Amend 50 to License DPR-6,replacing Tech Spec Figure 4-1 w/810918 Proposed Table 4-1 Re Pressure Temp Limits Until Plant Is Shutdown for Refueling ML20031G2151981-10-0909 October 1981 Amend 49 to License DPR-6,incorporating TMI Lessons Learned Category a Requirements Re Emergency Power Supply/Inadequate Core Cooling,Valve Position Indication,Containment Isolation & Iodine Monitoring ML20049A6991981-09-21021 September 1981 Amend 48 to License DPR-6,authorizing Operation W/One Recirculation Loop Out of Svc ML20010B9951981-08-0505 August 1981 Amend 45 to License DPR-6,revising Tech Specs to Incorporate Modified High Encl Pressure Scram Setpoints ML20050E1221981-06-0909 June 1981 Amend 44 to License DPR-6,authorizing Change in Reactor Operating Limits Based on New LOCA Analysis ML20031C2571979-03-23023 March 1979 Amend 24 to License DPR-6,changing Description of Control Rod Assemblies as Stated in Tech Spec 5.1.2 ML20031C5151978-06-0808 June 1978 Amend 18 to License DPR-6 Reflecting New Duties of Operators & Maint Superintendent & Elimination of Instrument & Control Engineer ML20031C3601978-03-0606 March 1978 Amend 17 to License DPR-6,incorporating Fire Protection Tech Specs on Existing Fire Protection Equipment & Adding Administrative Controls Re Fire Protection ML20126E1851974-11-0505 November 1974 Amend 8 to License DPR-6,adding Interim Surveillance Requirements Pending Completion of High Energy Fluid Piping Sys Mods ML20126E1111974-07-18018 July 1974 Amend 6 to License DPR-6,permitting Removal of Four Lower Rollers on Each Remaining 15 Peripheral Control Rods 1998-12-24
[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 ML20046D1661993-08-0606 August 1993 Application for Amend to License DPR-6,revising TS to Change Superintendent Titles to Manager ML20045C7341993-06-11011 June 1993 Application for Amend to License DPR-6,revising TS to Add ECCS Acceptance Criteria for Eletric & Diesel Fire Pumps & Remove Portion of Fire Protection Requirements,In follow-up to NOV & Unresolved Item Noted in Insp Rept 50-155/92-06 ML20044G4871993-05-24024 May 1993 Amend 170 to License DPR-6,revising Administrative Control Section to Reflect Restructuring of Nuclear Operations Dept 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 ML20011D2941989-12-21021 December 1989 Application for Amend to License DPR-6,correcting Editorial Errors in Section 7.3.2(e) Re Use of source-range Monitors for Critical Approaches 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 ML20154H5251988-05-17017 May 1988 Amend 90 to License DPR-6,allowing Inclusion of All Reloads of I Fuel Design in Tech Specs 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 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 1999-05-11
[Table view] |
Text
_ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _
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i UNITE 3 STATEU g
g NUCLEAR REULATCRY COMMISSION WASHINGTON, D.C. 30006 4 001
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CONSUMERS ENERGY COMPANY DOCKET NO. 50155 BIG ROCK POINT PLANT AMENDMENT TO FACILITY OfERATING LICENSE l
Amendment No.119 License No. DPR-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
- The application for amendment by Consumers Power Company (now renamed Consurr,ers Energy Company) (the licensee) dated April 30,1997, complies with the standards and requirements of the Atomic Energy Act of 195-4, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;
- C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis.fied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR 6 is hereby amended to read as fo!!ows:
Technical Soecifications The Technic.al Specifications contained in Appendix A, as revised through Amendment No.119, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
9708210374 970014
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PDR ADOCK 05000155 W
PDR
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2-Si Furthermore, the following paragraphs of Facility Operating License No. DPR 20 are hereby amended to read as follows:
1 1
.1.A.
.The application for amendment by Consumers Power, Company (renamed Consumers Energy Company by Amendment No.119, the licensee) dated January 13,1g75, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 2.
Facility Operating License No. DPR4, issued to the Consumers Energy 3
Company, is hereby amended in its entirety to read as follows:
i A.
This license applies to the Big Rock Point Plant, a boiling water reactor and associated equipment (the facility), owned by the Consumers Energy Company (the licensee). The facility is located in Charlevoix l
County, Michigan, and is described in the licensee's application dated January 14,1960, and the Final Hazards Summary Report, as supplemented and amended by subsequent filings by the licensee.
l B.
Subject to the conditions and requirements incorporated hereinc the Commission hereby licenses Consumers Energy Company:
4.
This license amendment is effective as of the date of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION MTv Linh N. Tran, Project Manager Project Directorate Ill.1 Division of Reactor Projects - lil/lV Office of Nuclear Reactor Regulation
. Attachments: (1) Pages 1 and 2 of License No. DPR4' (2) Changes to the Technical Specifications Date of lasuance: August 14, 1997 Pages 1 and 2 are attached, for convenience, for the composite license to reflect these changes.
n
,n,,
ATTACHMENT TO LICENSE AMENDMENT NO.119 FACILITY OPERATING LICENSE NO. DPR-8 1
i DOCKET NO. 50-155 i
LICENSE REMOVE INSERT 1
1 2
2 1
Revise Appendix A Technical Specifications by removing the pages identified below and 1
inserting the attached pages. The revised pages cre identified by amendment number and contain vertical lines indicating the areas of change.
61 61 80 80
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-1 UNITED STATES
,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006 0001
's,..... f CONSUMERS ENERGY COMPANY l
DOCKET NO. 50155 BIG ROCK POINT PLANT FACILITY OPERATING LICENSE License No. DPR-6
. 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumens Power Company (renamed Consumers Energy Company by Amendment No.119, the licensee) dated January 13,1975, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
Construction of the Big Rock Point Plant (the facility) has been substantially completed in conformity with Construe'Jon Permit No. CPPR-9 and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the n.las and regulations of the Commission; D.
There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; E.
The licensee is technically and financially qualified to engage in the activities authorized by this operating license in accordance with the rules and regulations of the Commission:
F.
,The licensee has satisfied the applicable provisions of 10 CFR Part 140,
" Financial Protection Requirements and indemnity Agreements," of the Commission's regulations; G.
The issuance of this operating license will not be inimical to the common defense and security or to the heeth and safety of the public; and Big Rock Point Amendment No.119
2 H.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30,40, and 70, including 10 CFR Sections 30.33,40.32, and 70.23 and 70.31.
2.
Facility Operating License No. DPR 6, issued to the Consumers Energy Company, is j
hereby amended in its entirety to read as follows:
A.
This license applies to the Big Rock Point Plant, a bolling water reactor and associated equipment (the facility), owned by the Consumers Energy Company l (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 by subsequent filings by the licensee.
l B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Consumers Energy Company:
l (1)
Pursuant to Section 104b of the Act and 10 CFR Part 50," Licensing of Production and Utilization Facilities," to possess, use, and operate the facility at the designated 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 PuO,-UO, fuel rods, and (d) 5 curies of plutonium encapsulated as a plutonium beryllium neutron source, allin 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 poolinventory, 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.
(b)
The storage of materials in the area between rack B and the east wall of the spent fuel pool is prohibited.
(c)
The use of the gantry crane over the pool for loads of over 24 tons is prohibited.
Big Rock Point Amendment No.119
- 7.0 OPERATING PROCEDURES This section describes those basic operating principles and procedural safeguards which have a potential effect on safety. Operating principles and procedures are presented for normal and emergency operation of the olant, for Phase !! testing within the Research and Development Progna, and for operational testing of the nuclear safeguards systems of the plant.
(Section7.1through7.2.3deletedbyAmendmentNo.9 dated 12/19/75) 7.2.4 Administrative and Procedural Controls Relatina to Hiah Performnce Fuel In addition to normal operating procedures, the following additional precautions shall be observed during irradiation of the centermelt fuel I
assembliest (a)
In the event of suspected coolant system leaks, reactor power will be timediately reduced to permit entry for inspection purposes and an evaluation of the suspected leak will be made.
If the evaluation reveals leakage in the primar reactor shall be shut down immediately, y cooling system, the except when it has been established that the leaks are in valves, packing or pumps where some leakage can be tolerated.
(b) The Plant Manager or his designated alternate shall be notified timediately 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 n6cessary corrective action taken. The evaluation and approval of the (.onsumers Energy Company General office shall be
/
required for all start ups following an 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 E)fMAL OPERATION 7.3.1 General Detailed operating procedures for each normal mode of plant operation shall be prepared prior to operation, fel TS SECTION 7 AMENDMENT NO. 107. 119 1/
^ AtMINISTRATIVt rnMTROLE 6.5.2.4.1(Continued) 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.t.4.2 above shall be forwarded to the Director NPAD, and management positions 1
responsible for the areas, audited within thirty (30) days after completion of the audit.
6.5.2.4.3 NPAD review of the subjects in Specifications 6.5.t.4.1 and 6.5.2.4.2 shall be perfomed by an assigned Nuclear Perfomance Specialist selected on the basis of technical expertise relattve to the subject on the basis of technical expertise l
being reviewed.
If the assigned Nuclear Performance i
l Specialist determines the need for interdisciplinary review, a committee consisting of the Director, NPAD, or his designate.
and at least four Nuclear Performance Specialists, shal be assigned.
Such committee shall meet as conditions requiring interdisciplinary review arise, but no less than twice year y.
AUTHORITY 6.5.t.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.t.4.1 and Section 6.5.t.4.2.
E QBR1 6.5.t 6 Records of WPAD activities shall be maintained.
Reports shall be prepared and distributed as indicated below:
a.
The results of reviews performed pursuant to Section 6.5.t.4.1 and Section 6.5.2.4.2 shall 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.
/
Li (Deleted) 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit.is violated:
a.
The reactor shall be shut down insediately and not restarted until the Commission authorizes resumption of operation (10 CFR 50.36(c)(1)(1)(A)).
80 AMENDMENT NO. 109,119
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