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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days ML20196F6451998-11-30030 November 1998 Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc ML20078E2051995-01-20020 January 1995 Proposed Tech Specs Re Snubber Visual Insp Intervals ML20078Q6061994-12-12012 December 1994 Proposed TS Section 3.4/4.4 Re Standby Liquid Control Sys ML20064J3181994-03-11011 March 1994 Proposed Tech Specs Re Snubber Visual Insp Intervals ML20059A7321993-12-20020 December 1993 Proposed Tech Specs 1.1/2.1-1 Increasing MCPR Safety Limit from 1.06 to 1.07 for Units 1 & 2 ML20059A8301993-10-21021 October 1993 Proposed Tech Specs Deleting Requirements for Demonstrating Operability of Redundant Equipment When ECCS Equipment Is Found Inoperable or Made Inoperable for Maint ML20125D6381992-12-0808 December 1992 Proposed Tech Specs 3/4.1 Re Reactor Protection Sys ML20116J7091992-11-0606 November 1992 Corrected Proposed TS 3.2/4.2-8 Re Administrative Changes ML20106A6221992-09-15015 September 1992 Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits ML20099D7791992-07-29029 July 1992 Proposed Tech Specs Sections 1.0, Definitions, 3/4.0, Applicability & 3/4.3, Reactivity 1999-08-13
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20196K1941999-06-30030 June 1999 Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days ML20196F6451998-11-30030 November 1998 Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document ML20196K5861998-11-0505 November 1998 Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20195J9041998-09-24024 September 1998 Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K ML20129K3321996-10-18018 October 1996 Cycle 15 Startup Test Results ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20216H8841996-06-30030 June 1996 Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F ML20116F3971996-06-30030 June 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20100C0441996-01-24024 January 1996 Secondary Containment Leak Test Summary ML20093K7721995-10-12012 October 1995 Quad-Cities Nuclear Power Station Unit 2 Cycle 14 Startup Test Results Summary ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc 1999-08-13
[Table view] |
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AUACHMENEB PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS OF FACILITY OPERATING LICENSES DPR-29 AND DPR-30 f1EVISEQRAGES
' UNIT Oi4E (DPR 20) UNIT TWO (DPR 30)
. 0.8/4.8 3.8/4.8 - 14b
SUMMARY
_OF_ CHANGES Page 3,8/4.8-20 (DPR+29)-
Page 3.8/4,8-14b (DPR-30)
To section 4,8.H.2,b(2) - change the A T requirement to read " Operability of inlet heater demonstra'es heater A T determined by the following formula:
A T x 28,5 - (0,0075F);
where A T is the diiferential temperature and F is the flow (cfm) at which the test is performed.
'This change reflects technical analyses which demonstrate that the heater can maintain relative humidity to less than 70% at all flows, l
I. 9109300218 910924 PDR- ADOCK 05000254 P PDR
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I
. l l
l QUAD-C111ES DPR-29
- 2) In place test the charcoal adsorber banks with halogenated hydrocarbon tracer to verify leak tight '
integrity,
- 3) Remove one carbon test canister from the charcoal adsorber, Subject this sample to a laboratory analysis to verify methyl iodide removal efficiency.
- b. The results of in place b. At least once per operating halogenated hydrocarbon cycle, but not to exceed 18 tests at 2000 cfm (+ 10%) on months, the following the charcoal banks shall conditions shall be show 1-l% penetration, demonstrated:
- 1) Pressure drop across the combined filters is less than 6 incher, of water at 2000 cfm O 101) Ilow rate.
- 2) Opetability of inlet heater demonstrates heat er ai ' '.' E
- c. The results of laboratory gefern7thect by The -0ll0 W'Q Nrbon sample analysis shall formu/n l show > 90% methyl iodide or 2 26.f-Id*0073~8 ,. .
removal etficiency when . agpe 47 , gg ggerean4/ .
. tested at 130*C and 95% R.H. 7emperaru re ,W p is rht fl0W (CImb sr u>nk;r th e rese is per-fo rm ed.
.. 3. Postmaintenance Requirements 3. Postmaintenance Testing
- a. After any maintenance or a. After any maintenance or heatina that could affect testing that could af fect u
the HEPA filter or HEPA .the leak Light integrity of filter mounting frame. the HEPA filters, perform leaked tight integrity, the- in place DOP tests on the results of the in place 00P HEPA filters in accordance
! tests at 2000 cfm (+ 10%) on with specification 3.8.H.J. t HEPA filters shall show (~ -1%
DOP penetration.
l lL l
l 3.8/4.8-20 Amendment No lla
,. - ~ _... _ . ,, . _ - - . _ _ _ , _ _ _ _ ~_ _ . _ , _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,
. QUAD CITIES DPR-30
- 3) Remove carbon test canister from the charcoal absorber.
Subject this sample to a laborat.,ry analysis to verify methyl iodine removal efficiency. >
- b. At least once per operating cycle, but not to exceed 18 months, the following conditions shall be demonstrated:
- 1) Pressure drop across the combined filters is less than 6 inches of water at 2000 cfm (110%) flow rate.
- 2) Operability of inlet heater demonstrates heater AT determined by the following formula:
AT 2 28.5-(0.0075F);
where AT is the differential temp)erature (cfm at which the and testFisis the flow performed.
- 3. Postmaintenance Requirements 3. Postmaintenance Testing
- a. After any maintenance or a. After any maintenance or testing heating that could affect the that could affect the leaktight HEPA filter or HEPA filter integrity of the HEPA filters, mounting frame leak tight perform in place DOP tests on integrity, the results of the the HEPA filters in accordance in-place DOP tests at 2000 cfm with Specification 3.8.H.2.a.
(+ 10%) on HEPA filters shall show s 1% DOP penetration, b. After any maintenance or testing
. that could affect the leaktight
- b. After any maintenance or testing integrity of the charcoal that could affect the charcoal absorber banks, perform absorber leaktight integrity, the halogenated hydrocartnn tests results of in-place halogenated on the charcoal absorbers in hydrocarbon tests at 2000 cfm accordance with Specification
(+ 10%) shall show s 1% 3.8.H.2.b.
penetration.
i 3.8/4.8-14b Amendment No. 90 l
t
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4 AUACHMENLO EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evalue.ted the proposed Technical Specification and has determined that it does not represent a significant hazards consideration. Based on the criteria which detines a significant hazards consideration established in 10 CFR 50.92(c):
- 1. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The safety objectiva of the control room air filtration unit is to provide filtered air to pressurize the control room after a design basis accidant to limit control room doses within the limits of GDC-19. To accomphsh this objective, outside air is passed through a roughing filter, heated to assure that relative humidity is below 70%, filtered through a HEPA filter / charcoal adsorber combination and routed to a booster f an and the "B" train of the control room HVAC. The 70% relative humidity criteria assures that the charcoal adsorbers will function efficiently to limit contro! room doses.
The proposed amendment provides revised operability criteria for the differential temperature requirement of the CREF System heater, This revised criteria is based upon the flow at which the heater operability test is performed.
The proposed Technical Specification does not involve any new operation oi the plant or atfact any accident initiators or precursors. The change does not involve the new installation of equipment. As such, the probability of the accident remains unchanged.
The proposed amendment does not affect the consequences of the accident. The design bases for the heater is to reduce the relative humidity of the atmosphere to the inlet of the charcoal adsorbers to less than 70% to assure efficient charcoal adsorber aarformanc% To achieve a relative humidity of less than 70%, assuming that the ncoming air supply is less than 95'F wet-bulb temperature, a 12*F A T is required.
The Technical Specification requirement of 15'F A T ensures that the relative humidity of the inlet ak to the charcoal adsorbers is less than 70% under all flow conditions.
This is unnecescarily conservative when the system is successfully tested at flows greater than 1800 cfm. The proposed amendment revises the differential temperature requirement to establish a A T range of 15'F to 12 F based on a system flow of 1800 cfm to 2200 cfm, respectively. This proposed differential temperature and associated flow requirement wili ensure that the relative humidity at the cliarcoal adsorber inlet remains below 70%, arovided that the incoming air supply remains below 95* wet-bulb temperature. As suc1, the proposed differential temperature requirement will ensure that relative bumidity will be maintained at less than 70% This in turn will ensure efficient charcoal adsorber performance and thus maintain control room doses below the requirements of GDC-19.
2, The proposed amendment does not create the possibility of a new or different kind of accident from any previously evaluated.
/scl:9411:9
The design objective of tha CREF System is to provide filtered outside air to 3ressurize the control room to limit the control room dose during and after the design aasis accident. The control room air filtration unit does not affect any accident precursors or accident irstiators. The proposed amendment requests revised differential temperature criteria based on flow conditions, in oider to assure that relative humidity to the inlet of the charcoal adsorbers is maintained below 70%, thereby assuring control rcom doses are maintained below GDC 19 requirements. As such, the proposed amendment does not involve any new modes of operation and does not involve the installation of new equipment. Consequently, the proposed amendment does not create the possibility of a new or different kind of a accident from any previously evaluated.
- 3. The proposed chang 9 does not involve a significant reduction in the margin of safety.
The CREF System is designed to ensure that control room occupants are not subject to excessive radiation doses during an accident. The limiting dose which can be received by corstrol room occupants is defined in GDC- 19. The control room dose is dependent on the efficiency of the charcoal adsorbers which in turn is dependent upon the relative humidity at the inlet of the charcoal adsorbers. Regulatory Guide 1.52," Design, Testing and Maintenance Criteria for Post Accident Engineereo-Safety Feature Atmosphere Cleanup Air Filtration and Adsoration Units of Light-Water-Cooled Nuclear Power Plants" requires that the relative hum dity is maintained at less than 70%.
The existing Technical Specification requires that the heater maintain a 15" A T to assure that tSe atmosphere at the inlet of the charcoal adsorber is maintained at less than 70% to assure efficient charcoal adsorber performance thereby maintaining control room doses within the limits of GDC-19. The 15 A T is valid for the range of all temperature / humidity conditions up to an outside air temperature of 95 F wet-bulb temperature.
The proposed amendment requests a revised criteria for the differential temperature requirement which will ensure that inlet relative humidity will be limited to less than 70%, based on outside air temperature / humidity conditions which correspond to 95 wet-bulb temperature. The requested differential temperature criteria provides a range of A Ts required for the range of operable flows. As a result, control room doses will remain below GDC-19 limits.
The margin of safety is not significantly reduced with this proposed changa since control room doses will be maintained below GDC-19 limits.
The proposed amendment does not involve a significant relaxation of the criteria used to establish safety limits, a significant relaxation of the bases for the Limiting Safety System Settings or a significant relaxation of the bases for the Limiting Conditions for Operation. Therefore, based on the criteria of 10 CFR 50.92(c), the proposed change does not constitute a significant hazards consideration.
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l ATTActiMENED
\
ENVIRONMENTAL ASSESSMENT Commonwealth Edison has verified through meteorological data and analytical calculations, that decreasing the differential temperature cliteria of the Control Room Emergency Filtration System would not result in any increase in dose to control room personnel; therefore, the environmental consequences remain unchanged.
The request does not involve a change in the installation or use of the f acilities or components located within the restricted areas as defined in 10 CFR 20. This Technical Specification amendment does not affect the operation of the reactor or core cooling mechanism following a postulated loss-of-cooling accident, and therefore will not increase the fission product source term. As a result of the analysis which demonstrates that the Control Room Emergency Filtration System will function as designed, Commonwealth Edison has determined that this request does not involve a significant increase in the amounts or change in the types of effluents that may be released offsite. The analysis also demonstrates that there is no increase in individual or cumulative occupational radiation exposure. Accordingly, this Technical Specification Amendment meets the eligibility criteria for categorical exclusion as defined in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with granting of this Technical Specification Amendment.
J
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