|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20141B7741997-05-0909 May 1997 Proposed Tech Specs,Changing LACBWR Controlling Documents ML20059L6271993-11-0505 November 1993 Proposed Tech Specs Per Requirements of Revised 10CFR20 Regulations for Radiation Protection ML20247G0001989-03-28028 March 1989 Proposed Tech Specs Re Controlled Area,Effluent Release Boundary,Exclusion Area,Frequency Notation,Fuel Handling & Process Control Program ML20235G8761989-02-15015 February 1989 Proposed Tech Spec 5.4.2.2.a,reflecting Revised Proposed Min Inventory of 150 Gallons Per Fuel Storage Tank ML20204H1641988-10-13013 October 1988 Proposed Tech Specs,Revising Radiological Environ Monitoring Program for Checking for Prescence of I-131 ML20149N1011988-02-22022 February 1988 Revised Tech Specs Pages for 870930 Application for Amend to License DPR-45 ML20147B7791988-02-22022 February 1988 Proposed Tech Specs,Revising LACBWR Tech Specs ML20149D7141988-01-29029 January 1988 Proposed Tech Specs Changing Sentence in Section 6.2.2.d Such That Individual Qualified in Radiation Protection Procedures Will Be Either Qualified Health Physics Technician or Shift Supervisor ML20236Q6441987-11-12012 November 1987 Proposed Tech Specs,Revising Administrative Section Due to Permanent Shutdown of Plant on 870430 ML20235V6851987-09-30030 September 1987 Proposed Tech Specs Eliminating Sections That Do Not Apply as Result of Plant Shutdown on 870430 ML20237F7801987-08-21021 August 1987 Proposed Tech Specs,Deleting Requirements Re Type a Leak Rate Tests ML20237J3031987-08-18018 August 1987 Proposed Tech Spec Sections 6.2.2.f,6.4.1,6.4.2,6.5.1.2 & Figure 6.2.2-1 Reflecting Permanent Shutdown ML20205P8311987-03-24024 March 1987 Proposed Tech Specs Figures 6.2.1-1,6.2.2-1 & Page 6-8, Revising Facility Organization ML20207J8161986-12-19019 December 1986 Proposed Tech Specs Re Nuclear Instrumentation,Reflecting Replacement of Aging Equipment & Provision of Shutdown Functions for Reactor W/Numac Instruments from GE ML20212B3641986-12-17017 December 1986 Proposed Tech Specs Altering Requirements for Partial Scram on Low Oil Level or Low Gas Pressure in CRD Mechanism Accumulator & Instituting Limiting Condition for Operation as Tech Spec 4.2.7.1 ML20205M5831986-04-0707 April 1986 Proposed Tech Specs Reflecting Reorganization of Offsite Mgt Staff ML20203B2831986-04-0707 April 1986 Proposed Tech Specs Re Reporting of Primary Coolant Iodine Spikes & Elimination of 800 H Per 12-month Period Cap for Exceeding Activity Limits ML20202A9151986-04-0101 April 1986 Proposed Tech Specs Changing Surveillance Requirements for HPCS Pumps.Functional Test Will Verify That Each Pump Operates at Flow Rate Greater than or Equal to 50 Gpm Design Flow Rate ML20153G1321986-02-21021 February 1986 Proposed Tech Specs,Clarifying & Correcting Description of Electrical Power Sys ML20210B8701986-02-0404 February 1986 Proposed Changes to Tech Spec Sections 4.2.3 & 2.6, Describing Replacement & Mod of Noninterruptible Bus 1C ML20138J8981985-12-12012 December 1985 Proposed Tech Specs 4.2.4.2.5 & 5.2.17.5,increasing Max Average Fuel Assembly Exposure Limit from 16,800 to 18,000 Mwd/Mtu in Operational Condition 1 ML20138J7751985-12-12012 December 1985 Proposed Tech Specs,Incorporating Use of Design AA Replacement Control Rods & Deleting Tech Spec 4.2.4.10 ML20132C6271985-09-17017 September 1985 Proposed Tech Spec Changes,Clarifying Actions Required When Both Containment Ventilation Dampers in Penetration Inoperable ML20133C2441985-09-16016 September 1985 Proposed Tech Specs,Deleting Section 2.4.7 & Simplifying & Making More Stringent Applicable Conditions for Low Pressure Core Spray ML20129A8901985-06-25025 June 1985 Proposed Tech Spec Changes to Section 4.1 Requiring Reactor Shutdown to Condition 4 Prior to Mississippi River Level Exceeding 640 Ft at Facility ML20058G2191982-07-28028 July 1982 STS Pages 3/4 9-8 & 3/4 9-9 Re Refueling Operations ML20054F2171982-06-0909 June 1982 Proposed Tech Spec 5.2.1.6 Re Containment Ventilation Isolation Valve Leakage Tests ML20126F9471981-03-0404 March 1981 Model Tech Specs 3/4.0 & 3/4.4 Re RCS Operational Leakage 1997-05-09
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20207C2801998-11-11011 November 1998 Rev 7 to LACBWR Pcp ML20207C2871998-11-11011 November 1998 Rev 5 to LACBWR Odcm ML20141B7741997-05-0909 May 1997 Proposed Tech Specs,Changing LACBWR Controlling Documents ML20059L6271993-11-0505 November 1993 Proposed Tech Specs Per Requirements of Revised 10CFR20 Regulations for Radiation Protection ML20247G0001989-03-28028 March 1989 Proposed Tech Specs Re Controlled Area,Effluent Release Boundary,Exclusion Area,Frequency Notation,Fuel Handling & Process Control Program ML20235G8761989-02-15015 February 1989 Proposed Tech Spec 5.4.2.2.a,reflecting Revised Proposed Min Inventory of 150 Gallons Per Fuel Storage Tank ML20204H1641988-10-13013 October 1988 Proposed Tech Specs,Revising Radiological Environ Monitoring Program for Checking for Prescence of I-131 ML20149N1011988-02-22022 February 1988 Revised Tech Specs Pages for 870930 Application for Amend to License DPR-45 ML20147B7791988-02-22022 February 1988 Proposed Tech Specs,Revising LACBWR Tech Specs ML20149D7141988-01-29029 January 1988 Proposed Tech Specs Changing Sentence in Section 6.2.2.d Such That Individual Qualified in Radiation Protection Procedures Will Be Either Qualified Health Physics Technician or Shift Supervisor ML20236Q6441987-11-12012 November 1987 Proposed Tech Specs,Revising Administrative Section Due to Permanent Shutdown of Plant on 870430 ML20235V6851987-09-30030 September 1987 Proposed Tech Specs Eliminating Sections That Do Not Apply as Result of Plant Shutdown on 870430 ML20237F7801987-08-21021 August 1987 Proposed Tech Specs,Deleting Requirements Re Type a Leak Rate Tests ML20237J3031987-08-18018 August 1987 Proposed Tech Spec Sections 6.2.2.f,6.4.1,6.4.2,6.5.1.2 & Figure 6.2.2-1 Reflecting Permanent Shutdown ML20205P8311987-03-24024 March 1987 Proposed Tech Specs Figures 6.2.1-1,6.2.2-1 & Page 6-8, Revising Facility Organization ML20207J8161986-12-19019 December 1986 Proposed Tech Specs Re Nuclear Instrumentation,Reflecting Replacement of Aging Equipment & Provision of Shutdown Functions for Reactor W/Numac Instruments from GE ML20212B3641986-12-17017 December 1986 Proposed Tech Specs Altering Requirements for Partial Scram on Low Oil Level or Low Gas Pressure in CRD Mechanism Accumulator & Instituting Limiting Condition for Operation as Tech Spec 4.2.7.1 ML20205M5831986-04-0707 April 1986 Proposed Tech Specs Reflecting Reorganization of Offsite Mgt Staff ML20203B2831986-04-0707 April 1986 Proposed Tech Specs Re Reporting of Primary Coolant Iodine Spikes & Elimination of 800 H Per 12-month Period Cap for Exceeding Activity Limits ML20202A9151986-04-0101 April 1986 Proposed Tech Specs Changing Surveillance Requirements for HPCS Pumps.Functional Test Will Verify That Each Pump Operates at Flow Rate Greater than or Equal to 50 Gpm Design Flow Rate ML20153G1321986-02-21021 February 1986 Proposed Tech Specs,Clarifying & Correcting Description of Electrical Power Sys ML20210B8701986-02-0404 February 1986 Proposed Changes to Tech Spec Sections 4.2.3 & 2.6, Describing Replacement & Mod of Noninterruptible Bus 1C ML20138J8981985-12-12012 December 1985 Proposed Tech Specs 4.2.4.2.5 & 5.2.17.5,increasing Max Average Fuel Assembly Exposure Limit from 16,800 to 18,000 Mwd/Mtu in Operational Condition 1 ML20138J7751985-12-12012 December 1985 Proposed Tech Specs,Incorporating Use of Design AA Replacement Control Rods & Deleting Tech Spec 4.2.4.10 ML20132C6271985-09-17017 September 1985 Proposed Tech Spec Changes,Clarifying Actions Required When Both Containment Ventilation Dampers in Penetration Inoperable ML20133C2441985-09-16016 September 1985 Proposed Tech Specs,Deleting Section 2.4.7 & Simplifying & Making More Stringent Applicable Conditions for Low Pressure Core Spray ML20129A8901985-06-25025 June 1985 Proposed Tech Spec Changes to Section 4.1 Requiring Reactor Shutdown to Condition 4 Prior to Mississippi River Level Exceeding 640 Ft at Facility ML20211J9761985-06-18018 June 1985 Revised Emergency Plan Implementing Procedures,Including Issue 20 to EPP-2, Organization & Operations During Emergencies, Issue 9 to EPP-5, Estimate of Offsite Dose & Issue 5 to EPP-6 Re Sample Collection & Analysis ML20062K2461982-07-29029 July 1982 Seismic & Structural Analysis for Lacrosse BWR Turbine Bldg ML20062F9951982-07-28028 July 1982 Seismic & Structural Analysis for LACBWR Containment Bldg, Revision 0 ML20058G2191982-07-28028 July 1982 STS Pages 3/4 9-8 & 3/4 9-9 Re Refueling Operations ML20062K2901982-07-27027 July 1982 Seismic & Stress Analysis of LACBWR 14-Inch Shutdown Condenser Vent Piping Sys ML20062E0371982-07-0101 July 1982 Public Version of Issue 5 to Radiological Emergency Response Plan Implementing Procedure EPP-2, Organization & Operations During Emergencies ML20054F2171982-06-0909 June 1982 Proposed Tech Spec 5.2.1.6 Re Containment Ventilation Isolation Valve Leakage Tests ML20054H4501982-05-21021 May 1982 Public Version of Issue 1 to Emergency Plan Implementing Procedure EPP-21, Prompt Public Notification Sys ML20062K3171982-01-22022 January 1982 Seismic & Structural Analysis for Lacrosse BWR 1-B Diesel Generator Bldg ML20062K3221982-01-20020 January 1982 Seismic & Structural Analysis for Lacrosse BWR Shutdown Condenser Platform ML20126F9471981-03-0404 March 1981 Model Tech Specs 3/4.0 & 3/4.4 Re RCS Operational Leakage ML20126F7471980-12-31031 December 1980 Reactor Containment Bldg Integrated Leak Rate Test (ILRT) for La Crosse Boiling Water Reactor (Lacbwr),Dec 1980 ML20126B3911979-12-21021 December 1979 Test Rept on Allis-Chalmers 6-Inch Streamseal Butterfly Valve in Air Re Nuclear Containment Isolation Valves 1998-11-11
[Table view] |
Text
..
DAIRYLAND POWER COOPERATIVE OFFSITE MANAGEMENT l BOARD OF. DIRECTORS l l GENERAL MANAGER l l SECRETARY & l l ADMINISTRATIVE l l ASSISTANT l I l I u . n l DIRECTOR l l ASSISTANT l l ASSISTANT l l ASSISTANT l l ASSISTANT l l EXTERNAL l l GENERAL MANAGER l l GENERAL MANAGER l l GENERAL MANAGER l l GENERAL MANAGER l l RELATIONS l l FOR OPERATIONS l l FOR ENGINEERING l l FOR l l & CONTROLLER l l AND l l ADMINISTRATIVE j l TECHNICAL SERVICES l FIGURE 6.2.1-1 0FFSITE ORGANIZATION 40 [ h S p -
P
1 I r' -l GENERAL MANAGER b - - - - - -l SAFETY REVIEW CO I I l ASSISTANT GENERAL l l l MANAGER FOR OPERATIONS l l
l l l TECHNICAL SUPPORTj - -l LACBWR l --
l OPERATIONS l
- PLANT SUPERINTENDENT l- - ~ -
l ll CONTRACTORS l IREVIEW COMMITTEE l l i i i i l QUALITY ASSURANCE l l ADMINISTRATIVE l l HEALTH & SAFETY l l0NSITE-TECHNICAL l SUPERVISOR ASSISTANT l l SUP_ERVISOR l l SUPPORT l l
l l l l l ENGINEERS
- l l l AND -l l HEALTH l l TECHNICAL l l TRAINING l l PHYSICS l l SUPPORT l l QA/QC l lTECHNICIANSj l STENOGRAPHERS l l SPECIALIST l l TECHNICIANS l l SECURITY & SAFETY l l SUPERVISOR l t
i i
jMECHANICAL j l INSTRUMENT & l l MAINTENANCE l l ASSISTANT MECHANICAL l l0PERATIONS SUPERVISOR l l ELECTRICAL SUPERVISOR l l SUPERVISOR l l MAINTENANCE SUPERVISOR l l l l MECHANICAL l l ASSISTANT TO l l INSTRUMENT AND l lMAINTENANCEj i ! OPERATIONS SUPERVISOR l l ELECTRICAL TECHNICIANS l l SHIFT l l AND TRAINING l l SUPERVISORS l l PLANT OPERATORS l l RELIEF SUPERVISOR l l FIRE PROTECTION l Note
- Mechanical Engineer is Designated Engineer Responsible for Fire DAIRYLAND POWER COOPERATIVE Protection Program A LACBWR FACILITY ORGANIZATION Technical Support Engineer is designated Emergency FIGURE 6.2.2-1 Planning Coordinator
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The SRC shall be composed of the:
Chairman: Consultant-Members: Consultant-Plant Superintendent Director External Relations General Manager- }
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities-at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert' advice to the SRC.
MEETING FREQUENCY 6.5.2.5 The SRC shall meet at least once per six months.
QUORUM 6.5.2.6 The minimum quoru. of the SRC necessary for the performance of the'SRC review and audit functions iif these Technical Specifications'shall consist of the Chairman, or his designated .t1 ternate, and at least 3 SRC members, including alternates. No more than a minority of the quorma shall have line responsibility for operation ot' the unit.
REVIEW 6.5.2.7 The Safety Review Committee shall review:
- a. The safety evaluations for 1) changes to procedures, equipment or systems and.2) tests or experiments completed under the provisions of.
Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
LACBWR 6-8 PCI-19 i