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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 ML20078P8251995-02-10010 February 1995 Proposed Tech Specs 2.10 to Relocate Requirements for Incore Instrumentation Sys ML20077S1691995-01-0909 January 1995 Proposed Tech Specs,Reflecting Deletion of Requirements for Toxic Gas Monitoring Sys ML20078G8981994-11-11011 November 1994 Proposed Tech Specs 5.2 & 5.5,reflecting Administrative Changes ML20024J3921994-10-0707 October 1994 Proposed Tech Specs,Deleting SRs in TS 3.6(3)a for Eight Raw Water Backup Valves to Containment Cooling Coils,Deleting SRs in TS 3.2,Table 3-5,item 6 for 58 Raw Water Valves & Revising Basis of TS 2.4 to Reflect Changes ML20069H9261994-06-0606 June 1994 Proposed Tech Specs Incorporating Changes to Credit Leak Before Break Methodology to Resolve USI A-2, Asymmetrical Blowdown Loads on Rcps ML20069D8451994-05-25025 May 1994 Proposed Tech Specs Requesting one-time Schedular Exemption from 10CFR50.36a(2) ML20062N4211993-12-28028 December 1993 Proposed TS Tables 3-1 & 3-2 Re Min Frequencies for Checks, Calibrs & Testing of RPS & Min Frequencies for Checks, Calibrs & Testing of ESFs & Instrumentation & Controls, Respectively LIC-93-0228, Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys1993-08-20020 August 1993 Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys ML20045H1791993-07-12012 July 1993 Proposed TS 2.14,Table 2-1,Item 6.b Re ESF Sys Initiation, Degraded Voltage Setting Limits LIC-93-0159, Proposed Tech Specs Incorporating Administrative Changes1993-06-17017 June 1993 Proposed Tech Specs Incorporating Administrative Changes ML20128E5341993-02-0808 February 1993 Proposed Tech Specs Deleting Section 5.9.4 Re Radioactive Effluent Release Rept.Draft Chemistry Manual Procedure Encl ML20128C0461993-02-0101 February 1993 Proposed TS Figures 2-1A & 2-1B Re pressure-temp Limits for Heatup & Cooldown,Respectively 1999-05-26
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR LIC-98-0141, SG Eddy Current Test Rept for 1998 Refueling Outage. with1998-10-27027 October 1998 SG Eddy Current Test Rept for 1998 Refueling Outage. with ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20211N7591997-10-0202 October 1997 Rev 0 to Fort Calhoun Station Unit 1 Operating Instruction, OI-ES-3, Engineered Safeguard Controls Normal Mode 1,2 & 3 Alignment Check ML20211N7521997-09-21021 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-04, Annunciator Marking ML20211N7471997-09-12012 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-08, Plastic Label Usage ML20211N7661997-08-25025 August 1997 Rev 4 to Fort Calhoun Station Unit 1 Annunciator Response Procedure ARP-1, APR-1 Annunciator Response Procedure ML20211N7411997-08-24024 August 1997 Rev 0 to Fort Calhoun Operations Dept Policy & Directive OPD-5-14, Test Monitor Program ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134J6841997-01-20020 January 1997 Rev 5,Change a to Security Training & Qualification Program LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20129C5351996-03-0101 March 1996 Rev 0 to Incore Instrumentation Operability Requirements ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20108A7161995-12-19019 December 1995 Rev 7 to CH-ODCM-0001, ODCM, Incorporating TS Amend 171 for Section 3.1 Update/Reflect Changing Environ ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20091P4011995-09-0101 September 1995 Rev 3 to Fort Calhoun Station ISI Program Plan Third Ten-Yr Interval 1993-2003 ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20085M0081995-06-15015 June 1995 Rev 2 to ISI Program Plan for 1993-2003 Interval ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20108A7121995-03-15015 March 1995 Rev 6 to CH-ODCM-0001, ODCM, Incorporating New TS Amend 164 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 1999-05-26
[Table view] |
Text
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ATTACHMENT A l
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9is)1080137 901220 PfiR ADOCK 05000283 P PDR
2.0 LIMITING CONDITIONS FOR OPERATION 2.6 Containment System (Continued)
- b. Modification of Minimum Reauirements After the reactor has been made critical, the minimum requirements may be modified to allow either or both of the following statements (i.ii) to be applicable at any one time, if the operability of the component (s) is not restored to meet the minimum requirements within the time specified below, the reactor shall be placed in a hot shutdown condition within six hours.
(i) One of the hydrogen purge fans, VA-80A or VA-8%, with associated valves and piaing may, be inoperable provided the fan is restored to opera)le status within 30 days.
(ii)Thehydrogenpurgefiltersystem,VA-82,maybeinoperable
)rovided the system is restored to operable status within 72 lours.
Basis The reactor coolant system conditions of cold shutdown assure that no steam will be formed and, hence, there would be no pressure buildup in the containment.if the reactor coolant system ruptures. The shutdown margins are selected based on the type of activities that are being carried out.
The refueling boron concentration provides a shutdown margin which precludes criticality under any circumstances. Each CEDM must be tested and some have two CEA's attached.
Regarding internal pressure limitations, the containment design pressure of 60 psi would not be exceeded if the intern of-coo $antaccidentwereasmuchas3psig.f})pressurebeforeamajorloss-The containment integrity will be protected if the visua' check of all " locked closed" manual isolation valves to verify them closed is made-prior to plant start-up after an extended outage where one or more valves could inadvertently be left open. .0peration of the purge isolation valves is prevented during normaloperationsduetothesizeofthevalves(42 inches)andaconcern about-their ability to close against the differential pressure that could result from a-LOCA or MSLB.
The Hydrogen Purge System is required to be operable in order to control thequantit)ofcombustiblegasesincontainmentinapost-LOCA condition. The containment integrity will be 3rotected by ensuring
.the penetration valves VA-280 and VA-289 are "locced closed" while HCV-881 and HCV-882 are normally closed during )ower operation. The applicable surveillance testing requirements of Taale 3-5 will ensure that the system is capable of performing ;its design function. The blowers (VA-80A and VA-808), associated valves, and piping are single failure proof, have been l -designed as a Seismic Class I System, and are redundant to the VA-82 filter header. VA-80A or VA-80B is capable of providing sufficient hydrogen removal capabilities as required by the USAR to prevent-the hydrogen concen ggtion inside of containment from exceeding the 4% flammability limit. / Electrical Equipment qualification was not required as the radiation doses in the area of belowtheminimumrequirements.gHydrogenPurgeSystemequipmentwere Amendment No. 68 2-31 I
l ATTACHMENT B 1
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-JUSTIFICATION, DISCUSSION, AND i
NO SIGNIFICANT HAZARDS CONSIDERATIONS i
Justification and Discussion The proposed amendment-to the Technical Specifications.would add a Limiting
-Condition:of-Operation to Section 2.6 Containment System, revise the basis accordingly,_ add surveillance test requirements per Table 3-5 Item 17 for the hydrogenpurgesystem(HPS)andrevisethebasisaccordingly.
.The-Limiting Conditions of 0)eration (LCO) listed in Section 2.6 of the Technical Specification esta)lish the hydrogen purge system configuration in 3 order to meet.the.10CFR50.44 requirements for combustible gas control.
The LC0 lists the minimum requirements for criticality and the modifications of minimum requirements that will be allowed for maintenance and testing activities. The
- containment integrity is protected by ensuring the outside containment L penetration. valves are normally " locked closed" during power operation. The Surveillance Testing, as described below, ensures the system is capable of performing;its post-LOCA hydrogen control function in accordance with the
- guidelines-of Regulatory Guide 1.7. The hydrogen purge vstem is designed as a :'
Seismic' Class:1 system, meeting-the single failure critei j with redundant L blower units with associated valves:and piping to the common header for VA-82 filter.
Should the HEPA or charcoal filters in the VA-82. filter unit become obstructed,
-theiHPS would not maintain purge capability. The filter media is tested under-more! adverse conditions then-have been calculated during the accident to where no_ credible failure mode could be identified. A modification request has been. !
issued to place a:bypassLline around the filters to ensure full compliance with ,
the-redundancy requirements.
The LC0 conditions will ensure that the 10CFR100 radiological consequences for ,
!the-event are not1 exceeded in a_ post-LOCA situationby maintaining and i verifying the hydrogen purge system as operable.
The amendment is conservative since it adds surveillance test requirements 'or thelhydrogen purge system-to,the Technical Specifications; The'h
. system (HPS)isclassifiedasanEngineeredSafety_ Features-(ESF)ydrogenpurge System in Section 6.1.2.1 of the Fort Calhoun Updated Safety Analysis Report (USAR)'.- As an ESF' system, periodic surveillance tests are requiredcto assure operability of!the system in accordance with the design basis. The HPS is utilized!to Emaintain the hydrogen gas concentration in containment below the 4%
h4 .f.lammability.limitoin accordance'with the design. basis specified in Section
-14.17 Eof 1the USAR. =The surveillance intervals were chosen-based on standard E -technical specif_ication intervals. The HPS was designed and installed prior to the requirements'of-10CFR50.44-and was not required to meet automatic '
e ntainment isolation criteria.
The requirements--toLcycle;all manual valves ensures that when the vaives are required to be repositioned they will operate as required. The manual valves
'have remote operators due to the-potentially high radiation fields in the area Lof the HPS inia post-LOCA: environment. The valves are required to make one complete cycle during each refueling outage.
0 1._
,The remotely; operated valves.in'the system are located on the containment penetrations'and are locally-leak rate tested to ensure the. containment
-isolatica function?is maintained. The proposed test also requires the valves
. demonstrate.the; ability to com>lete one cycle of operation from a remote (Al-43)1operatinglocation.- T1is ensures the ability to open and close the ;
valvesias required to perform a purge of the containment.
~
LThe flow through VA-80A or VA-808 is measured to be greater than 80 scfm and less_than 230 scfm. A flow rate greater than 80 scfm will ensure more hydrogen is removed from containment than is being generated during the event. The flow values include instrument: uncertainties. The maximum flow will limit flow to below the flow rate used'in the. design-basis radiological calculations. The
- abilities of'the blowers-to provide the minimum flow and maintain the flow for
- (
a-test period of_10 hours-during refueling serves to demonstrate the ;
operab.ility.in order to fulfill the se)arate_and redundant requirement. The
' blowers units will take suction from tie containment during the refueling flow test. sDuring power operation the blower units will take suction _from Room 59 i of the Auxiliary Building.in order to reduce the potential for inadvertent
-radiation release and th_e 30 minute test period will verify key operating parametersp The: basis for Sections'2.6 and 3.2 were revised to be consistent with the changes in the Sections due to the addition of the hydrogen purge system. This will verify.that.the offsite doses are less than those calculated in the safety 1 analysis report..
.No Sionificant-Hazards Considerations The proposed amendment'to the Technical-Specifications does.not involve a
=significant hazards consideration because operation of Fort Calhoun Station JUnit'l in accordance with this amendment would not
- (1)- ; Involve a,significant-increaseLin the probability of occurrence or. '
Lconsequences of.an accident or: malfunction of equipment important-to-
- safety previously evaluated in the safety. analysis report. The-proposed surveillance. tests wilL be; conducted during refueling
. operations,-in accordanceiwith' approved: procedures, to verify input-assumptions and equipment operation assumed in the safety analysis.
report: remain v'alidgand the hydrogen purge, system is-considered '
o)erable. The' limiting conditions of operation-ensure the abilityLof L .tle hydrogen purge _ system.to meet the requirements of.10CFR50.44 and-L :10CFR100.- Therefore, the proposed change does not increase the-
! probability or._. consequences-of an accident or malfunction of equipment; important to-safety.
L '(2); LCrea'te the: possibility for an accident or malfunction of a' new or-differentJtyperthan previously evaluated in the safety analysis L
1 report. -The proposed change does not physically alter the configuration of-the plant and no new or different mode of operation has-been > implemented. Therefore, the possibility of an accident of a- '
new or different type than previously evaluated in the safety analysis report is not created.
t .
(3) Involve a significant reduction in the margin of safety as defined in the basis for any Technical Specification. The proposad change maintains the basis of the safety analysis. In addition, the surveillance tests will serve to verify that the margin of safety for the hydrogen purge system is maintained. Therefore, the margin of safety as defined in the basis for the Technical Specifications is not reduced.
Based on the above considerations, OPPD does not believe that this amendment involves a significant hazards consideration as defined by 10CFR50.92 and the proposed changes will not result in a condition which significantly alters the impact of the :tation on the environment. Thus, the proposed changes meet the eligibilitycriteriaforcategoricalexclusionsetforthin10CFR51.22(c)(9) and pursuant to 10CFR51.22(b) no environmental impact or environmental assessment need be prepared.
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