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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
[Table view] |
Text
.
.. w ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 eT l
PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES July 19, 1985 l
l t
1 1
8507250108 850719 PDR ADOCK 05000155 p PDR 3 Pages IC0785-0239-NLO4
60
~6.3.2 Refueling Operation Controls Interlocks shall be provided to prevent all motion with any of the refueling cranes (namely, jib cranes, transfer cask winch) which are positioned over the reactor vessel whenever any control rod is not fully inserted in the core and the mode selector switch is in the " refuel" position.
6.3.3 Operating Requirements (a) All reactor refueling safet'y system sensors and trip devices shall be functionally tested at each major refueling shutdown and shall be maintained in the specified condition during all refueling operations.
(b) The refueling operation controls including position interlocks shall be functionally tested at each major refueling shutdown.
.6.4 PLANT MONITORING SYSTEMS The plant monitoring systems include the process radiation monitoring systems, the area monitoring system, the reactor water level monitors in the Reactor Depressurizing System, and the containment pressure and water level monitoring systems.
6.4.1 Process Radiation Monitoring Systems (a) Air Ejector Off-Gas Monitoring System (see Section 13.1)
(b) Stack-Gas Monitoring System (see Section 13.1)
(c) Emergency Condenser Vent Monitor The emergency condenser vent shall be monitored to detect a significant release of radioactive material. Monitoring shall be supplied by two independent gamma sensitive instrumentation channels employing scintillation crystal sensing devices. These channels shall have a range of 0.1 to 100 mr/hr and shall be provided with an alarm which shall annunciate in the control room to inform the operator of a release of radioactive material.
One of the emergency condenser vent monitors shall be in service at all times during power operation. The monitors shall be set to alarm at approximately 10 mr above the maximum expected background during operation of the emergency condenser. The calibration shall be checked at least monthly.
Proposed 1/7/85 !
Proposed 7/19/85 ll TSB0585-00208-NLO2
62 6.4.2 (Contd)
(c) The containment atmosphere shall be monitored by two high range gamma monitors. The monitors are designed to measure gamma radiation in containment under accident conditions from I R/hr to IE+06 R/hr. The monitors are located external to the containment sphere. The readouts of the monitors are located in the control room.
Both high range containment atmosphere gamma monitors shall normally be in service during power operation. If either monitor is inoperable, restore to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or, in lieu of any other report required by Specification 6.9.2 (administrative controls), prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3 (administrative controls) within the next 30 days outlining the cause of the inoperability and the plans for restoring the system to operable status. A channel check shall be performed for each monitor at least once per month, and channel calibration shall be performed at each refueling outage.
The channel calibration for all ranges above 10R/hr may be performed by electronic signal substitution.
(d) Portable gamma dose-rate measuring instruments and portable neutron dose-rate measuring instruments shall be provided for establishing permissible working limits. These instruments shall be calibrated at least once every three months. Portable high range gamma measuring instruments shall be calibrated from 0-20 R/hr every three months and on all scales every six months.
6.4.3 Reactor Water Level Monitors in the Reactor Depressurization System Four narrow range water level monitors are provided in the main control room as part of the Reactor Depressurizing System to be used for detection of adequate core cooling during accident situations.
At least two reactor water level indicators in the Reactor Depressurization System shall be operable during power operation.
6.4.4 Containment Pressure and Water Level Monitoring Systems Two containment pressure monitors and two containment water level monitors are provided with readouts in the main control room for accident monitoring. The containment pressure and water level monitors shall be operable during power operations. Plant shutdown is required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following a 7 day period when one monitor of either type is inoperable. Plant shutdown is required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period when both monitors of one type are inoperable. A channel check of each monitor shall be done at least once per month and a channel calibration shall be performed at each major refueling shutdown but not less frequently than once every 18 months.
Proposed 1/7/85 l TSB0585-0020B-NLO2
76b 7.6(Contd)
Reference Procedure System or Function Frequency of Within These Undergoing Test Routine Tests Specifications Calibration of area One month or less Section 6.4.2 monitoring system Channel comparison check One mo' nth or less Section 6.4.3 of reactor level indicating instruments in the Reactor Depressurization System Calibration of reactor At each major Section 6.4.3 level indicating instru- refueling shutdown ments in the Reactor Depressurizing System Steam drum safety valve One month or less Section 4.1.2 position monitor check Calibration of steam drum At each major refueling Section 4.1.2 safety valve position shutdown monitors High radiation trip closure At each major refueling Section 6.4.2 of the containment shutdown ventilation isolation valves Channel Check of High One month or less Section 6.4.2 Range Containment Gamma Monitors Channel calibration of At each major Section 6.4.2 High Range Containment refueling shutdown Gamma Monitors Channel Check of One month or less Section 6.4.4 containment pressure and water level monitors Channel Calibration of At each major Section 6.4.4 containment pressure refueling shutdown
- But no less than once every 18 months Proposed 1/7/85 I Proposed 7/19/85 ll TSB0585-00205-NLO2
