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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
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DEFINITIONS - (Cant'd)
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- b. The freight door is closed,
- c. Each air lock is OPERABLE, 1
1 d. The containment leakage rates are within the limit, and
- e. The sealing mechanism associated with each penetration (e.g.,
welds, bellows, o-rings) is OPERABLE.
CONTROLLED AREA A Controlled Area is an area for which access shall be controlled because of actual presence of uncontained radioactive material. Controlled areas shall be designated by radiation control signs and markers in accordance with 10CFR20.203. These controlled areas shall include the Turbine Building i beyond the change room door, the containment Building, the Waste Treatment l Building, and any other areas so marked by radiation signs and markers.
1 EFFLUENT RELEASE BOUNDARY The Dairyland power Cooperative property line within the 1109 ft. (338m) radius EXCLUSION AREA is the EFFLUENT RELEASE BOUNDARY. See Figure 1, Section 4.
EXCLUSION AREA The EXCLUSION AREA is defined as the area within an 1109 ft. (338m) radius from the centerline of the Containmer t Building. This was the area established per 10 CFR 100 as the EXCLUSION AREA for plant siting and operation.
FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table of Surveillance Frequency Notation.
FUEL HANDLING FUEL HANDLING shall be the movement of any irradiated fuel within the Containment Building. Suspension of FUEL HANDLING shall not preclude completion of movement of the fuel to a safe conservative position.
MEMBEi[(S_) 0F THE PUBLIC MEMBER (S) 0F THE PUBLIC shall include any person who is not occupationally associated with the utility. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or make deliveries. This category does include persons who use portions of the site for recreational or other purposes not associated with the utility.
8904040092 890328 22 PDR ADOCK 05000409 ,
P PDC
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( -
l-t DEFINITIONS -'(Cont'd)
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OFFSITE DOSE CALCULATION MANUAL- (ODCM) l An OFFSITE DOSE CALCULATION MANUAL (ODCM) shall be a manual containing the methodology and parameters to be used for the calcule. tion of offsite doses due to radioactive gaseous and . liquid effluents and for the calculation of l
geseous and liquid effluent monitoring instrumentation alarm / trip setpoints.
' It shall describe the radiological environmental monitoring program.
1 OPERABLE-OPERABILITY l
A system, subsystem, train, component or device shell be OPERABLE or have OPERABILITY when it is capable of. performing its specified function (s) and .
when all necessary attendant instrumentation, controls, a normal or an emergency electrical power so"rce, cooling-or seal water, lubrication or other auxiliary equipment that are required for the' system, subsysten, train, component or device to perf orm its function (s) are also capable of performing their related support function (s).
I PROCESS CONTROL PROGRAM (PCP) f The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing o#
actual or simulated solid wastes will be accomplished in such a way as to .
assure compliance with 10 CFR Part 20, 10 CFR Part 61 and Federal and State regulations and other requirements governing the transportation and disposal
.of the radioactive waste.
REPORTABLE EVENT l A REPORTABLE EVENT shall be any of those conditions specified in Section-6.8.3. A Licensee-Event Report shall be submitted for REPORTABLE b/ENTS..
RESTRICTED AREA A RESTRICTED AREA shall be any area within the EXCLUSION' AREA, access to which is controlled by the licensee for purposes of protection of individuals from exposure to ionizing radiation and radioactive materials.
l SOLIDIFICATION SOLIDIFICATION shall be the conversion'of wet wastes into a form that meets shipping and burial ground requirements.
SOURCE CRECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
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t l
c .. . .
l DEFINITIONS - (Cont'd)
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STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of:
1
- n. A test schedule.for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals. ]
- b. The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
1 UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area not controlled by'the licensee for purposes of protection of MEMBERS OF THE PUBLIC from exposure to ionizing radiation and radioactive materials.
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SURVEILLANCE FICQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At le'ast once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
SA At least once per 6 months.
A At least once per 12 months.
R At least once per 18 months.
P Completed prior to each use or release.
N.A. Not applicable.
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