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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
[Table view] |
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ATTACHMENT I CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET 50-155 TECHNICAL SPECIFICATION CHANGE REQUEST AS PROPOSED PAGES b
d 2 PAGES 9308160239 930806 iN PDR ADOCK 05000150 PDR
'?1 P
I ADMINISTRATIVE CONTROLS 6.3 PLANT STAFF OUALIFICATIONS 6.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
6.3.2 Either the Chemistry and Health Physics Manager or the Chemistry
/
l and Radiation Protection Supervisor shall meet or excee qualifications of Regulatory Guide 1.8, September 1975.f the r
6.3.3 The On-call Technical Advisor (OTA) shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.3.4 The Operations Manager shall hold a Senior Reactor Operator License.
/
The Operations Manager shall be responsible for directing the activities /
of licensed operators.
/
A 6.4 TRAINING l
6.4.1 A retraining and replacement training program for the plant staff shall be maintained and implemented and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971
~
and 10 CFR 55.
L 6.4.2 A fire brigade training program shall be maintained and implemented and shall, as practicable, meet or exceed the requirements of l
Section 27 of the NFPA Code-1975.
Fire Brigade training drills shall be held at least quarterly.
I For the purpose of this section, " Equivalent," as utilized in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following:
(a) Formal schoolir.g in science engineering, or (b) operational or technical experience / training in. nuclear power.
?
74 AS PROPOSED
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ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)
^
FUNCTION 6.5.1.1 The Plant Review Committee (PRC) shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PRC is composed of nine regular members from the Big Rock Point Staff. The PRC members shall meet or exceed the minimum qualifica-tions described in Sections 4.2 and 4.4 of ANSI NI8.1-1971 for comparable positions. The PRC shall include representatives from the Operations, Chemistry / Health Physics, Maintenance, Engineering,
/
and Safety and Licensing Departments. The member shall be designated
/
in administrative procedures by the Plant Manager who is the Chairman of the PRC. The Plant Manager shall also designate an Alternate Chairman in writing.
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 FRE0VENCY 6.5.1.4 The PRC shall meet at least once per calendar month, with special meetings as required.
000 RUM 6.5.1.5 A quorum for PRC shall consist of the Chairman or alternate Chairman and four (4) voting members (including alternates).
T 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 Manager to affect. nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to Appendix "A" Technical Specifications.
75 AS PROPOSED
k l
ATTACHMENT 2 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET 50-155 9
TECHNICAL SPECIFICATION CHANGE REQUEST EXISTING PAGES 3
f 2 PAGES
c
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ADMINISTRATIVE COWTROLS 6.3 PLANT STAFF QUALIFICATI0WS
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6.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
O i
Either the Chemistry and Health Physics Copo n, N Tnte. vent or the Chemistry 6.3.2 and Radiation Protection Supervisor shall meet or exceef the l
qualifications of Regulatory Guide 1.8, September 1975.
t 6.3.3 The On-call Technical Advisor (OTA) shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transienta and accidents.
gWs c
6.3.4 The Operations Superi aden& shall hold a Senior Reactor Operator i
i License. The Operations *upe-inte.Ma.r shall be responsible for directing the activities of licensed operators.
-Z..Lell e t th. -
..athar-requirement-smidecttefrt3 Mas appticaele iv Operations
-Manager-in LMSI MISrl4v--
i 6.4 TRAINING L
I 6.4.1 A retraining and replacement training program for the plant staff shall be maintained and implemented and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI M18.1-1971 and 10 CFR 55.
A fire brigade training program shall be maintained and"im'lemented l
p 6.4.2 and shall, as practicable, meet or exceed the requirements of Section 27 of the NFPA Code-1975. Fire Brigade training drills shall be held at least quarterly.
l h
i IFor the purpose of this section, " Equivalent," as utilized in Regulatory Cuide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following: (a) Formal schooling in science i
l engineering, or- (b) operational or technical experience / training in nuclear power.
74 Amendment 107' February 19, 1992 l
TS.SECTION 10
I
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ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)
FUNCTION 6.5.1.1 The Plant Review Committee (PRC) shall function to advise the Plant Manager on all matters related to nuclear safety.
COMP 0SITION 6.5.1.2 The PRC is composed of nine regular members from the Big Rock Point
/
Staff.
The PRC members shall meet or exceed the minimum qualifica-
/
tions described in Sections 4.2 and 4.4 of ANSI N18.1-1971 for
/
comparable positions. The PRC shall include representatives from
/
the Operations, Chemistry / Health Physics, Maintenanceded Engineering,
/
Departments. The member shall be designated in administrative
/
and bfc p d u % y The
/
procedures by the Plant Manager who is the Chairman of the PRC.
Plant Manager shall also designate an Alternate Chairman in writing.
/
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 alternau s shall participate as voting members at any one time in PRC activities.
M_EETING FREOUENCY 6.5.1.4 The PRC shall meet at least once per calendar month, with special meetings as required.
DUORUM i
6.5.1.5 A quorum for PRC shall consist of the Chairman or alternate Chairman
/
j and four (4) voting members (including alternates).
/
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 Manager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
'l Review of all proposed changes to Appendix "A" Technical c.
Specifications.
75 Amendment 109 i
May 24, 1993
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