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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
MONTHYEARML20207C2871998-11-11011 November 1998 Rev 5 to LACBWR Odcm ML20207C2801998-11-11011 November 1998 Rev 7 to LACBWR Pcp 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 ML20147B7791988-02-22022 February 1988 Proposed Tech Specs,Revising LACBWR Tech Specs ML20149N1011988-02-22022 February 1988 Revised Tech Specs Pages for 870930 Application for Amend to License DPR-45 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 ML20138J7751985-12-12012 December 1985 Proposed Tech Specs,Incorporating Use of Design AA Replacement Control Rods & Deleting Tech Spec 4.2.4.10 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 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 ML20058G2191982-07-28028 July 1982 STS Pages 3/4 9-8 & 3/4 9-9 Re Refueling Operations ML20062F9951982-07-28028 July 1982 Seismic & Structural Analysis for LACBWR Containment Bldg, Revision 0 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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REACTOR COOLANT SYSTE]
4.2.2.22 ACTIVITY LIMITING CONDI_TI_0N FOR OPERA _TI_0_N 4.2.2.22 The activity of the:
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- a. Reactor coolant shall be limited to:
- 1. 1 0.2 pCi/ gram DOSE EQUIVALENT I-131,
- 2. 1 100/E VCi/ gram, and
- 3. 1 5.0 x 10-6 pCi/ gram gross alpha activity.
- b. Off-gas emission, measured at the 150 cu. ft. off-gas holdup tank effluent monitor, shall be limited to j[ 750 Ci/d (P/Pp) +
l AT (1-0.018t)(P/Pp), where:
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- 1. (P/Pp) = fraction of RATED THERMAL POWER between 33 MWt and 165 i MWt, l
- 2. AT = tramp activity, Ci/d, not to exceed 1500, at THERMAL POWER l (Pg) as determined upon initial power escalation after each l refueling.
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- 3. t = days after the determination of AT with the limitation that t < 50.
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- 4. Activity values shall be normalized for correlation with previous cycles due to changes in monitoring, sampling and/or analysis methods.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3 and 4.
i ACTION:
l A. In OPERATIONAL CONDITION 1, 2 or 3, with the activity of the reactor coolant:
- 1. > 0.2 pCi/ gram DOSE EQUIVALENT I-131 but i 4.0 uCi/ gram, entry to OPERATIONAL CONDITION 1, 2, 3 or 4 is permitted and operation may
- continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
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- 2. > 0.2 pCi/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or > 4.0 pCi/ gram be in at least HOT SHUTDOWN with the main steam line isolation valve closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (CONTINUED)
ACTION (Continued):
- 3. > 100/E VCi/ gram or > 5.0 x 10-6 pCi/ gram gross alpha activity, be in at least HOT SHUTDOWN with the main steam line isolation valve closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN withir. the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. IN OPERATIONAL CONDITION 1, with off-gas activity:
- 1. > 750 Ci/ day (P/Pp) + AT (1.0.018t)(P/Pp) but i 1000 Ci/ day (P/Pp) ;
+AT (1-0.018t)(P/Pp). POWER OPERATION may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- 2. > 750 Ci/ day (P/Pp) + AT (1-0.018t)(P/Pp) for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or > 1000 Ci/ day be in at least HOT SHUTDOWN with the main steam line ioslation valve closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. With the reactor required to be shutdown as a result of ACTION a.3 or b.2 above, obtain Commission approval prior to increasing reactor coolant system temperature above 212*F.
- d. Ir. OPERATIONAL CONDITION 1, with THERMAL POWER increased by more than 25% of RATED THERMAL POWER since the last performance of Table 4.2.2.22-1, Item 4, perform Table 4.2.2.22-1, Items Ic and 4c.
- e. In OPERATIONAL CONDITION 1 or 2, with off-gas activity increased by more than 1000 pCi/see within one hour, perform Table 4.2.2.22-1, Item Ic and 4c. Off-gas activity values shall be normalized for corrrelation with previous cycles due to changes in monitoring, sampling and/or analysis methods.
- f. In OPERATIONAL CONDITION 1, 2, 3 or 4 with the activity _of the primary ,
coolant > 0.2 pCi/ gram DOSE EQUIVALENT I-131, or > 100/E pCi/ gram, or !
> 5.0 x 10-6 pCi/ gram gross alpha activity, or with the off-gas i activity > 750 Ci/ day (P/Pp) + AT (1-0.018t)(P/Pp) perform the sampling I and analysis requirements of Items Ib, 4b, and 6b of Table 4.2.2.22-1. i l
- g. In OPERATIONAL CONDITION 1 or 2, with THERMAL POWER changed by more ,
than 15% of RATED THERMAL POWER within one hour, perform the sampling '
and analysis requirements of Item Ic and 4c of Table 4.2.2.22.-l.
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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS
.m 5.2.16 The activity of the reactor coolant and off-gas emission shall be demonstrated to be within the limits by the performance of the sampling and analysis program of Table 4.2.2.22-1.
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ADMINISTRATIVE CONTR_0_LS _ . _ ,
, ANNUAL OPERATING REPORT (Continued):
- c. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 4.2.2.22. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2)
Results of the last analysis performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one anlaysis after the activity was reduced to less than limit. Each result should include date and time of sampling and the concentration; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> :
prior to the first sample in which the limit was exceeded; (4) Graph of the specific activity concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the limit.
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