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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 ML20128D7251993-01-29029 January 1993 Proposed Tech Specs Re Administrative Controls ML20059A2181990-08-14014 August 1990 Proposed Tech Specs,Reflecting Administrative & Organizational Changes 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 ML18047A6651982-11-0505 November 1982 Proposed Tech Spec Changes to Licenses DPR-6 & DPR-20 Re Administrative Controls,Providing coordinated,company-wide Safety Mgt Program.Proposed Tech Specs Supersede 820720 Submittal ML20058E4071982-07-20020 July 1982 Proposed Tech Spec Pages Re Safety Mgt Function ML20058E3981982-07-20020 July 1982 Proposed Tech Spec Pages Re Safety Mgt Function ML20054J7391982-06-25025 June 1982 Tech Spec Table 6.2-1 Re Min Shift Crew Composition ML20126E6131964-05-0606 May 1964 Tech Specs Re Principal Design Features & Operating Limits & Requirements Which Have Effect on Safety of Operation of Plant 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 ML20058N6331993-07-15015 July 1993 Rev 142 to Vol 3 of Operating Procedure - Sys SOP-14, Substation ML20058N6401993-07-15015 July 1993 Rev 20 to Procedure T7-28, Emergency Diesel Generator Auto Test Start 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 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 ML20206B4211987-03-12012 March 1987 Public Version of Rev 3 to General Ofc Emergency Planning Procedure GEN-1, Overview, Rev 9 to Copyholders List & Index & Rev 3 to App G, Emergency Telephone Numbers ML20207T5511987-03-12012 March 1987 Rev 91 to Site Emergency Plan Implementing Procedure EPIP-4B, Operations Personnel. W/Rev 91 to Table of Contents/Effective Pages 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 ML20207L7031986-12-30030 December 1986 Rev 0 to Emergency Operating Procedure,Validation Procedure 1999-06-03
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ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 PROPOSED TECHNICAL SPECIFICATIONS PAGE CHANGES August 5, 1985 l
P
! kb 55 PDA 3 Pages IC0885-0260-NLO4
ADMINISTRATIVE CONTROLS l
- g. Administrative procedures shall be developed and implemented to limit the working hours of plant staff who perform safety-related operation functions; ie, senior reactor operators, reactor operators, auxiliary operators, health physicists and key maintenance personnel. ;
{
Adequate shift coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems l
require substantial amounts of overtime to be used, the following guidelines shall be followed:
(1) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover. time.
(2) An individual should not be permitted to work more than 16 !
hours in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, l all excluding shift turnover time. j 1
(3) A break, including shift turnover time, of at least eight hours should be allowed after continuous work periods of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> duration.
(4) Except during entended shutdown periods, the use of overtime' s should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the Plant Superintendent or his alternate (Production and Performance or Engineering and Maintenance Superintendents), or higher levels of Management, in accordance with established procedures and with documentation of the basis for granting the deviation.
l Controls shall be included in the procedures such that individual overtime will be reviewed monthly by the Plant Superintendent or his designee to assure that excessive hours have not been assigned.
Routine deviations from the above guidelines is not authorized.
U Proposed TSB0885-0260-NLO4
CONSUMERS POWER COMPANY PLANT ORGANIZATION Plant Superintendent (a)
Nuclear -
Assurance Off-Site I
QA _ _ _.. _ , _ . . _ . , Plant Review S,uperintendent Committee QC Supervisor I l Chem /HP Production and Engineering & Planning and Admin Superintendent Performance Maintenance Services Superintendent Superintendent Superintendent Other Operations Supervisor Services SR0(b)
Shift Supervisors - SRO Figure 6.2-2 A. To support the above Plant organization, personnel knowledgeable in the following areas identified in ANSI N18.7-1976/ ANS 3.2 will report at the discretion of the Plant Superintendent:
- 1. Nuclear Power Plant Mechanical, Electrical and Electronic Systems
- 2. Nuclear Engineering i 3. Chemistry and Radiochemistry
- 4. Radiation Protection (Reports to C: em/HP Superintendent)
A single individual may be qualified and perform in more than one discipline.
B. The Security Force will be supervised as described in the Plant Security Plan.
C. Quality Assurance / Control activities will be in accordance with Consumers Power Company's Quality Assurance Program Description for Operational Nuclear Power Plants (CPC-2A, as revised).
(a) Responsible for the Plant Fire Protection Program implementation.
(b)Either the Production and Performance Superintendent or the Operations Supervisor will hold an SRO and meet the other requirements of 6.3.1 of these Technical Specifications (as applicable to Operations Manager in ANSI N18.1).
The individual holding an SRO shall be responsible for directing the activities of licensed operators.
(SRO - Senior Reactor Operator License)
Proposed 105 TSB0785-0243A-NLO4
ADMINISTRATIVE CONTROLS 6.3 PLANT STAFF QUALIFICATIONS 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 Superintendent or the -
Chemistry and Radiation Protection Supervisor shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.1 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.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Director of Nuclear Operations Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR 55, Appendix "A."
6.4.2 The Director of Property Protection is responsible for the development, revision, approval and implementation of the Fire Brigade i training program. This training 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 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 Superintendent on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PRC shall be composed of: !
Chairman: Plant Superintendent or Designated Alternate Appointed by the Plant Superintendent Member: Production & Performance Superintendent l Member: Planning & Admin Services Superintendent Member: Engineering & Maintenance Superintendent Member: Operations Supervisor ,
Member: Instrument and Control Supervisor !
Member: Reactor Engineer Member: Chemistry and Health Physics Superintendent l Member: Shift Supervisor j
Member: Technical Engineer
'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 schooling in science engineering,or(b)operationalortechnicalexperience/trainindinnuclear power.
Proposed 107 TSB0885-0260A-NLO4