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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20195D0451999-06-0303 June 1999 Proposed Tech Specs,Revised to Agree with Current Facility Defueled TS Format ML20206N2751999-05-11011 May 1999 Proposed Tech Specs Deleting Figure 5.1-1 BRP Site Map from Defueld TS Subsection 1.16,changing Definition of Site & Other Associated Editorial Changes ML20154M5431998-10-14014 October 1998 Proposed Defueled Tech Specs & Bases for Big Rock Plant ML20236T6681998-07-21021 July 1998 Proposed Defueled Tech Specs for Big Rock Nuclear Plant ML20248L5511998-06-0505 June 1998 Draft Proposed Tech Specs Rev,Incorporating Changes Responsive to 980416 RAI ML20138G2021997-04-30030 April 1997 Proposed Tech Specs,Illustrating Change to Current Facility License DPR-6 ML20138A9131997-04-22022 April 1997 Proposed Tech Specs,Withdrawing Petition to Implement Option B Performance Based Requirements to App J of 10CFR50 ML20134H6411996-11-0707 November 1996 Proposed Tech Specs Re New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys ML20129C4871996-10-15015 October 1996 Proposed Tech Specs Allowing Use of Option B for Type a Test (Containment),Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining, leakage-limiting Boundaries) & Type C Tests ML20056G3931993-08-24024 August 1993 Proposed Tech Specs Reflecting Revision to 10CFR50.36(a)(2) Changing Reporting Requirement for Effluent Releases from Semiannual to Annual ML20046D1671993-08-0606 August 1993 Proposed Tech Specs Supporting Change of Superintendent Titles to Manager ML20045F2401993-07-0101 July 1993 Proposed Tech Specs Requesting Addition of New Requirement, Table & Bases & Deletion of 4.7.11.1.1.b & 4.7.11.1.1.d from Surveillance Section ML20044G7881993-05-24024 May 1993 Proposed Tech Specs Supporting Replacement of Reactor Protection Sys CB-RE11 Undervoltage Breakers & Rev of Release Device Trip Range ML20035F2441993-04-14014 April 1993 Proposed TS Section 6.3.2 Re Qualifications of Either Chemistry & Health Physics Supervisor ML20034G4201993-03-0404 March 1993 Proposed Tech Specs Reflecting Implementation of Revised 10CFR20 Re Administrative Controls ML20128D7251993-01-29029 January 1993 Proposed Tech Specs Re Administrative Controls ML20059A2181990-08-14014 August 1990 Proposed Tech Specs,Reflecting Administrative & Organizational Changes ML20011D2991989-12-21021 December 1989 Proposed Tech Specs Re Hot startup,source-range Monitor channel,power-range Monitor Channel & in-core Flux Monitors ML20245K6991989-06-30030 June 1989 Corrected Proposed Tech Specs Paragraph 3.7 Re Containment Sphere Leakage Testing ML20247L1141989-05-25025 May 1989 Proposed Tech Specs Aligning Specs to Current 10CFR50 App J Requirements That Permits Removal of 24 H Duration Restriction of Integrated Leak Rate Test ML20204F8321988-10-10010 October 1988 Proposed Tech Specs Change Re Partial Stroke Testing Following Main Valve Seat Leakage Repairs ML20154S6481988-09-22022 September 1988 Proposed Tech Specs,Allowing Independent Review & Audit Functions to Be Accomplished by Independent Organizational Unit Rather than Standing Committee ML20154P2191988-09-21021 September 1988 Proposed Tech Specs Reflecting Editorial & Administrative Corrections to Provide Clarification & Consistency ML20154D4821988-09-0808 September 1988 Proposed Tech Specs,Removing Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes ML20150C7921988-07-0505 July 1988 Proposed Tech Specs Re Reactor Depressurization Sys Isolation Valves ML20148H6331988-03-22022 March 1988 Proposed Tech Specs Re Reactor Depressurization Sys ML20237B9691987-12-14014 December 1987 Proposed Tech Specs,Removing Numerical Designator from I-type Fuel for Each Subsequent Fuel Operating Cycle ML20236N5501987-11-0909 November 1987 Proposed Tech Spec Figure 5.1 & Sections 6.1,6.2,6.3 & 7.3, Making Administrative Changes to Reflect Features & Terminology Used W/New out-of-core Power Range Nuclear Instrumentation.Power Range Monitor Sys Description Encl ML20236B1201987-07-22022 July 1987 Proposed Tech Specs Changes Consisting of Administrative Corrections ML20210V2981987-02-10010 February 1987 Corrected Page 11 to Tech Spec,Reflecting New Signature Dates ML20210E5601987-02-0606 February 1987 Proposed Tech Specs,Adding Operability & Surveillance Requirements for Alternate Shutdown Sys & Revising Specs for Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg ML20210C6341987-02-0404 February 1987 Proposed Tech Spec Changes,Adding Table of Uncertainty Factors Associated W/Core thermal-hydraulic Parameters Heat Flux,Maplhgr,Max Bundle Power & Min Critical Power Ratio ML20212F0361986-12-30030 December 1986 Proposed Tech Specs Adding Second Scram Dump Tank Vent & Drain Valve ML20207C9801986-12-22022 December 1986 Proposed Tech Specs,Reducing Station Battery Design Time Interval from 8 to 2 H ML20215G0101986-12-17017 December 1986 Proposed Tech Spec Page Changes,Adding Operability & Surveillance Requirements for Alternate Shutdown Sys ML20215C7391986-12-0505 December 1986 Proposed Tech Specs Re Reactor Core & Controls ML20206M5151986-08-15015 August 1986 Proposed Tech Specs,Reflecting Features & Terminology Used W/New out-of-core source-range Nuclear Instrumentation. Source-range Monitor Sys Description & Block Diagram Encl ML20203P8041986-05-0101 May 1986 Proposed Tech Spec Table 6.2-1,reflecting Exemption from Requirement to Have Two Senior Reactor Operators on Shift ML20203F6521986-04-21021 April 1986 Proposed Tech Specs Re Operability & Surveillance Requirements for Alternate Shutdown Sys,Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg ML20154K0261986-03-0404 March 1986 Proposed Tech Specs,Adding Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R ML20138B2531985-10-0909 October 1985 Proposed Tech Specs,Revising Calibr of Portable Gamma & Neutron dose-rate Measuring Instruments ML20137V9891985-09-30030 September 1985 Proposed Tech Spec Changes,Adding Operability & Surveillance Requirements for Components of Alternate Shutdown Sys Installed in Accordance w/10CFR50,App R ML20132F4891985-09-24024 September 1985 Proposed Tech Specs,Revising Fuel MAPLHGR Limits,Per 850816 Request,In Order to Implement Operating Limits for Reload I1 Fuel ML20135B8141985-09-0303 September 1985 Proposed Changes to Tech Spec 5.2.2.a,eliminating Min Control Rod Withdrawal Rate Limit ML20134E3111985-08-16016 August 1985 Proposed Tech Specs Implementing Reactor Operating Limits for Reload I1 Fuel ML20133N1551985-08-0505 August 1985 Proposed Tech Spec,Implementing Staff Reorganization ML20132B7361985-07-19019 July 1985 Proposed Tech Specs for Containment Pressure Monitor & Containment Water Level Monitor ML20128B9291985-06-27027 June 1985 Proposed Tech Spec Changes Re Operation of Plant Between Refueling Shutdown W/O Potential of Requiring Surveillance to Be Performed That May Affect Plant Availability ML20125B4111985-06-0707 June 1985 Proposed Correction to Tech Spec Page 110,adding Section 6.5.2.2,inadvertently Omitted from 850130 Change Request ML20128E5141985-05-24024 May 1985 Proposed Revised Tech Specs Renumbering Definition Section 1.2.8 to 1.2.14 Re Administrative Controls 1999-06-03
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195D0451999-06-0303 June 1999 Proposed Tech Specs,Revised to Agree with Current Facility Defueled TS Format ML20206N2751999-05-11011 May 1999 Proposed Tech Specs Deleting Figure 5.1-1 BRP Site Map from Defueld TS Subsection 1.16,changing Definition of Site & Other Associated Editorial Changes ML20154M5431998-10-14014 October 1998 Proposed Defueled Tech Specs & Bases for Big Rock Plant ML20238E8141998-08-31031 August 1998 Revised Big Rock Point Defueled Emergency Plan ML20236T6681998-07-21021 July 1998 Proposed Defueled Tech Specs for Big Rock Nuclear Plant ML20248L5511998-06-0505 June 1998 Draft Proposed Tech Specs Rev,Incorporating Changes Responsive to 980416 RAI ML20217P3811998-02-28028 February 1998 Revised Defueled Emergency Plan ML20138G2021997-04-30030 April 1997 Proposed Tech Specs,Illustrating Change to Current Facility License DPR-6 ML20138A9131997-04-22022 April 1997 Proposed Tech Specs,Withdrawing Petition to Implement Option B Performance Based Requirements to App J of 10CFR50 ML20216A9611997-01-0101 January 1997 Rev 13 to Big Rock Point Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program ML20134H6411996-11-0707 November 1996 Proposed Tech Specs Re New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys ML20129C4871996-10-15015 October 1996 Proposed Tech Specs Allowing Use of Option B for Type a Test (Containment),Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining, leakage-limiting Boundaries) & Type C Tests ML20199J7411995-10-0303 October 1995 Rev 6 to Users Guide for Vectora CL-200 Polyethylene High Integrity Containers ML20058N6421993-10-11011 October 1993 Rev 16 to Vol of Administrative Procedures,Procedure 3.2.1, Maint Order Processing, Pages 21 & 22 ML20056G3931993-08-24024 August 1993 Proposed Tech Specs Reflecting Revision to 10CFR50.36(a)(2) Changing Reporting Requirement for Effluent Releases from Semiannual to Annual ML20046D1671993-08-0606 August 1993 Proposed Tech Specs Supporting Change of Superintendent Titles to Manager ML20058N6401993-07-15015 July 1993 Rev 20 to Procedure T7-28, Emergency Diesel Generator Auto Test Start ML20058N6331993-07-15015 July 1993 Rev 142 to Vol 3 of Operating Procedure - Sys SOP-14, Substation ML20045F2401993-07-0101 July 1993 Proposed Tech Specs Requesting Addition of New Requirement, Table & Bases & Deletion of 4.7.11.1.1.b & 4.7.11.1.1.d from Surveillance Section ML20044G7881993-05-24024 May 1993 Proposed Tech Specs Supporting Replacement of Reactor Protection Sys CB-RE11 Undervoltage Breakers & Rev of Release Device Trip Range ML20035F2441993-04-14014 April 1993 Proposed TS Section 6.3.2 Re Qualifications of Either Chemistry & Health Physics Supervisor ML20034G4201993-03-0404 March 1993 Proposed Tech Specs Reflecting Implementation of Revised 10CFR20 Re Administrative Controls ML20128D7251993-01-29029 January 1993 Proposed Tech Specs Re Administrative Controls ML20127N4321993-01-11011 January 1993 Third Interval ISI Program ML20141M5531992-03-10010 March 1992 Rev 8 to Vol 25 to Procedure Big Rock Point Radiological Effluent TS Required Documents,Offsite Dose Calculations & Process Control Program ML20059A2181990-08-14014 August 1990 Proposed Tech Specs,Reflecting Administrative & Organizational Changes ML20011D2991989-12-21021 December 1989 Proposed Tech Specs Re Hot startup,source-range Monitor channel,power-range Monitor Channel & in-core Flux Monitors ML20246J1841989-08-25025 August 1989 Rev 4,Vol 25 to, Big Rock Point Radiological Effluent Tech Spec Required Documents for Offsite Dose Calculation Manual & Process Control Program ML20245K6991989-06-30030 June 1989 Corrected Proposed Tech Specs Paragraph 3.7 Re Containment Sphere Leakage Testing ML20247L1141989-05-25025 May 1989 Proposed Tech Specs Aligning Specs to Current 10CFR50 App J Requirements That Permits Removal of 24 H Duration Restriction of Integrated Leak Rate Test ML20204F8321988-10-10010 October 1988 Proposed Tech Specs Change Re Partial Stroke Testing Following Main Valve Seat Leakage Repairs ML20154S6481988-09-22022 September 1988 Proposed Tech Specs,Allowing Independent Review & Audit Functions to Be Accomplished by Independent Organizational Unit Rather than Standing Committee ML20154P2191988-09-21021 September 1988 Proposed Tech Specs Reflecting Editorial & Administrative Corrections to Provide Clarification & Consistency ML20154D4821988-09-0808 September 1988 Proposed Tech Specs,Removing Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes ML20207C2291988-07-13013 July 1988 Rev 7 to Suitability,Training & Qualification Plan. W/ ML20150C7921988-07-0505 July 1988 Proposed Tech Specs Re Reactor Depressurization Sys Isolation Valves ML20154L7961988-05-26026 May 1988 Simulation Facility Plan for Big Rock Point to Meet 10CFR55.45(b) ML20153G0861988-04-13013 April 1988 Rev 2 to Procedure Change Form, Offsite Dose Calculations Manual ML20153G1041988-04-12012 April 1988 Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program ML20155A5221988-04-0606 April 1988 Rev 30 to Procedure T30-22, ECCS Valve Tests ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20148H6331988-03-22022 March 1988 Proposed Tech Specs Re Reactor Depressurization Sys ML20147E3701988-01-14014 January 1988 Rev 6 to Suitability,Training & Qualification Plans ML20215M3281987-12-31031 December 1987 Emergency Plan Exercise Scenario ML20237B9691987-12-14014 December 1987 Proposed Tech Specs,Removing Numerical Designator from I-type Fuel for Each Subsequent Fuel Operating Cycle ML20236P0671987-11-13013 November 1987 Rev 1 to Big Rock Point IGSCC Insp Program ML20236N5501987-11-0909 November 1987 Proposed Tech Spec Figure 5.1 & Sections 6.1,6.2,6.3 & 7.3, Making Administrative Changes to Reflect Features & Terminology Used W/New out-of-core Power Range Nuclear Instrumentation.Power Range Monitor Sys Description Encl ML20236B1201987-07-22022 July 1987 Proposed Tech Specs Changes Consisting of Administrative Corrections ML20214N9801987-05-29029 May 1987 Rev 0 to Health Physics Procedure HP 10.9, Big Rock Point Radiological Environ Program Sample Collection & Shipment ML20213A1761987-04-22022 April 1987 Rev 5 to Suitability Training & Qualification Plan 1999-06-03
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b-ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 PROPOSED TECHNICAL SPECIFICATIONS PAGE CHANGES May 24, 1985 I
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1.2.14 Reportable Event - any of those conditions specified in Section 50.73 to 10 CFR Part 50.
2.0 SITE 2.1 LOCATION - shall be in Charlevoix County, Michigan, shall be about 4 miles northeast of Charlevoix, Michigan, and shall be about 11 miles west of Petoskey, Michigan.
2.2 BOUNDARIES - shall surround about 600 acres, and the nearest landside property line shall be about 2680 feet, and the nearest shoreline property line shall be about 200 feet from the plant's containment sphere.
2.3 PRINCIPAL ACTIVITIES - shall be those associated with the operation of the Big Rock Point Nuclear Plant and may include other activities directly connected with the generation, transmission and distribution of electric energy.
Proposed TSB0505-0201C-NLO4
i ADMINISTRATIVE CONTROLS
).
ALTERNATES 6.5.1.3 Alternate members of the PRC shall be appointed in writing by the PRC Chairman to serve on a temporary basis. However, no more than two alternates shall participate as voting members at any one time in PRC activities.
MEETING FREQUENCY 6.5.1.4 The PRC shall meet at least once per calendar month, with special meetings as required.
QUORUM 6.5.1.5 A quorum for PRC shall consist of the Chairman and four (4) voting members.
RESPONSIBILITIES 6.5.1.6 The PRC shall be responsible for:
a.
Review of:
(1) all procedures required by Technical Specification 6.8 and changes thereto and (2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes to Appendix "A" Technical c.
Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical e.
Specifications. (A report shall be prepared covering evaluation and recommendations to prevent recurrence and forwarded to the Vice President Nuclear Operations and to the Executive Engineer, NAPO.)
f.
Review of plant operations to detect potential nuclear safety hazards.
g.
Review of reportable events as defined in Section 1.2.14.
h.
Performance of special reviews and investigations and reports thereof as requested by the Plant Superintendent or Chairman of NSB.
- i. Review of the Site Emergency Plan and implementing procedures.
PRC review may be performed through a routing of the item subject to the requirements of Specification 6.5.1.7.
108 Proposed TSB0585-0201D-NLO4
9 ADMINISTRATIVE CONTROLS b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety, c.
Reportable events as defined in Section 1.2.14.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of changes made to the Operating Procedures.
f.
Records of radioactive shipments.
g.
Records of sealed source leak tests and results.
h.
Records of annual physical inventory of all source material of record.
6.10.2 The following records shall be retained for the duration of the facility operating license:
a.
Record and drawing changes reflecting facility design modifications made to systems and equipment described in the FHSR.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of monthly facility radiation and contamination surveys.
d.
Records of radiation exposure for all individuals entering radiation control areas.
e.
Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
g.
Records of inservice inspections performed pursuant to these Technical Specifications.
h.
Records of Quality Assurance activities required by the QA Manual to be retained for the duration of the Facility Operating License.
- i. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
J.
Records of meetings of the PRC and NSB.
121 Proposed TSB0585-0201D-NLO4