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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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- TECHNICAL SPECIFICATIONS >
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NOTE The BASES contained in this document summarize the reasons for the Technical Specifications in Sections 3 and 4/5 but, in accordance with 10CFR50.36, are not part of Technical Specifications.
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May 1997 l
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ADOCK 05000409 l PDR1 i
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' TECHNICAL SPECIFICATION BASES Safety Analysis in Accordance with Decommissionino Plan and Technical f Specifications: l
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(1) Will the probability of occurrence or the consequences of an accident or malfunction of equipment necessary for SAFSTOR previously evaluated eitherin the Decommissioning Plan or FSAR be increased? NO Justification For Answer: j The License Amendment Request for Technical Specification (T.S.) improve- '
ments proposed to remove the Bases section of Technical Specifications and maintain the T.S. Bases as a separate document governed by plant i administrative controls. Amendment No. 69 has been issued by the Commission and the T.S. Bases as included with the License Amendment Request is being issued as a new document under the control of ACP-07.1.
This change is administrative in nature and does not affect the assumptions contained in the SAFSTOR accident analysis, the physical plant design or the operation of the plant. Therefore, this change does not affect the probability or consequences of accidents previously analyzed.
(2) Is there a possibility of an accident or malfunction of a different type than previously evaluated in the Decommissioning Plan or FSAR being created?
g NO
(]
Justification For Answer:
This proposed change is administrative in nature. This change does not involve the addition of, or modification to, equipment nor does it alter the design of operation of the plant. Therefore, no new failure modes are introduced and the possibility of a new or different kind of accident is not created.
(3) Is the margin of safety as defined in the Bases for any Technical Specifications reduced? NO Justification For Answer: ,
The operating limits and functional capabilities of plant systems are unaffected by this change. Therefore, the proposed change does not reduce the margin of safety maintained.
l (4) Will the proposed change result in a significant environmentalimpact not previously evaluated in the Environmental Assessraent in suriport of the August 7,1991, Decommissioning Order or the Final Environmental Statement (FES) related to operation of LACBWR, dated April 21,1980 (NUREG-0191)? NO (A) Justification For Answer:
There is no environmenta impact associated with this change.
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- The BASES in this section provide the general requirements applicable to each of the Limiting Conditions for Operation and Surveillance Requirements within Section 4/5.
3.1 This specification defines the applicability of each specification in terms of specified applicability conditions and is provided to delineate specifically when each specification is applicable.
i 3.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for Operation and ,
I associated ACTION requirement.
3.3 This specification provides that entry into specified applicability condition must be made with (a) the full complement of required systems, equipment or components OPERABLE and (b) all other parameters as specified in the Limiting .
Conditions for Operation being met without regard for allowable deviations and out i of service provisions contained in the ACTION statements.
The intent of this provision is to ensure that activities are not initiated with either i E required equipment or systems inoperable or other specified limits being .i exceeded.
Exceptions to this provision have been provided for a limited number of specifications when performance of activities with inoperable equipment would not i affect plant safety. These exceptions are stated in the ACTION statements of the ;
appropriate specifications. I 3.4 This specification provides that surveillance activities necessary to ensure that the Limiting Conditions for Operation are met and will be performed during the specified applicability conditions for which the Limiting Conditions for Operation are applicable. Provisions for additional surveillance activities to be performed without regard to the specified applicability conditions are provided in the individual Surveillance Requirements.
3.5 The provision of this specification provides an allowable tolercnce for i performing surveillance activities beyond those specified in the nominal surveillance interval. This tolerance is necessary to provide flexibility because of '
f scheduling and performance considerations. The phrase "at least" associated with l a surveillance frequency requirement does not negate these allowable tolerances for performing surveillance activities.
The tolerance value is sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not significantly degraded beyond that obtained from the nominal specified interval.
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TS BASES 1 May 1997
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C) 3.6 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Condition for Operation. Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements. l 3.7 This specification ensures that the surveillance activities associated with a .
Limiting Condition for Operation have been performed within the specified time l interval prior to entry into specified applicability condition. The intent of this provision is to ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirements of the Limiting Condition for Operation. j l
4/5.1 Fuel Storaae and Handlina l 4.1.1 General Fuel Storaae and Handlina Reauirements Spent fuel storage is provided in the spent fuel storage racks located in the Fuel fO Element Storage Well within the Containment Building. The spent fuel storage.
V racks are designed with a nominal 7.0 inch center-to center distance between fuel assemblies in each individual rack assembly with a boron impregnated poison plate between each storage location to ensure K, of 10.95 when flooded with unborated water. Fuel stored in the storage well is restricted to fuel with stainless steel cladding which has a U-235 loading of 5 22.6 grams per axial centimeter of fuel assembly. A fuel hanciling system is provided which is capable of remotely handling fuel assemblies one at a time.
4.1.2 Fuel Element Storaae Well The Fuel Element Storage Well System is capable of maintaining water temperature i150 F and maintaining water quality within the established limits.
Minimu'm water coverage limits above fuel stored in the storage racks and fuel being handled have been established to provide adequate shielding to protect personnel and to provide adequate cooling. Limits to the handling of heavy objects over the Fuel Element Storage Well have been established to reduce the probability of a heavy load drop into the storage well.
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TS BASES 2 May 1997