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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20216E6051999-09-0707 September 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20210H0631999-07-28028 July 1999 Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, by Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4131999-07-27027 July 1999 Application for Amend to License NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G8831999-07-26026 July 1999 Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5251999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G4631999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumention & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20195F9121999-06-10010 June 1999 Application for Amend to License NPF-3,changing TS 3/4.6.4.4 Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20205E4961999-03-19019 March 1999 Application for Amend to License NPF-3,requesting Withdrawal of Proposed New Action B to TS 3.6.5.2,previously Submitted in 981027 Application ML20204F1691999-03-0909 March 1999 Application for Amend to License NPF-3,adopting Changes in Frequency & Scope of Volumetric Exams Justified by W TR WCAP-14535A ML20196F3791998-11-30030 November 1998 Supplemental Application for Amend to License NPF-3, Proposing Changes to License Conditions 2.C(6) & 2.E by Transferring Operating Authority for DBNPS from Toed & Centerior Svc Co to Firstenergy Nuclear Operating Co ML20155E3181998-10-28028 October 1998 Application for Amend to License NPF-3,revising Various Sections of TS 6.0, Administrative Controls, Including Relocation of Contents of 6.11 to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E0701998-10-27027 October 1998 Application for Amend to License NPF-3,revising TSs 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation by Providing Potential Reduction in Spurious Trip Rate to Provide Cost Savings in Excess of $50,000 ML20155D7731998-10-27027 October 1998 Application for Amend to License NPF-3,relocating Existing TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8481998-10-27027 October 1998 Application for Amend to License NPF-3,revising Existing TS SRs 4.8.2.3.2.d,4.8.2.3.2.e,4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2811998-09-0808 September 1998 Application for Amend to License NPF-3,permitting Use of Framatome Cogema Fuels M5 Advanced Alloy Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20236G6461998-06-29029 June 1998 Application for Amend to License NPF-3,transferring Operating Authority for DBNPS from TE & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments Included ML20236R2301998-06-29029 June 1998 Resubmitted Application for Amend to License NPF-3, Transferring Operating Authority for DBNPS from Teco & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Safety Assessment & EA Included ML20217P8671998-04-24024 April 1998 Application for Amend to License NPF-3,modifying Existing TS 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases by Relocating Tables of Response Time Limits from TS to Plant USAR Technical Requirements Manual ML20217P8251998-04-24024 April 1998 Application for Amend to License NPF-3,clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20203L0861998-02-26026 February 1998 Application for Amend to License NPF-3 to Revise TS 3/4.4.5 & TS 3/4.4.6.2,incorporating New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2511997-12-23023 December 1997 Application for Amend to License NPF-3.Amend Changes TS Definitions 1.12,TS 3/4.9.5 & New TS 3.0.6 ML20197J5861997-12-23023 December 1997 Application for Amend to License NPF-3,revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2801997-08-26026 August 1997 Application for Amend to License NPF-3,clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2831997-08-26026 August 1997 Application for Amend to License NPF-3,modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5931997-07-29029 July 1997 Suppl 950929 to Application for Amend to License NPF-3, Change TS 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating & Associated Bases 3/4.4.2 & 3/4.4.3 ML20141F1051997-06-24024 June 1997 Application for Amend to License NPF-3,deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138A3201997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Conversion to 24-month Fuel Cycle ML20138C3131997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Rev to TS 3/4.7.6 to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20137M1061997-03-31031 March 1997 Application for Amend to License NPF-57,revising TS to Improve Consistency Between TS & Plant Configuration, Operation & Testing & Complete Required CA to Resolve TS Discrepancies Identified in CA Program ML20138M1251997-02-14014 February 1997 Application for Amend to License NPF-3,requesting Delay of Heat Removal Sys Valve Pit Surveillance Requirements ML20134D7461997-01-30030 January 1997 Application for Amend to License NPF-3,revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0561997-01-20020 January 1997 Application for Amend to License NPF-3,involving TS 3/4.5.3 Re ECCS Subsystems ML20132C7771996-12-13013 December 1996 Application for Amend to License NPF-3,authorizing Transfers of Control ML20132B6871996-12-11011 December 1996 Application for Amend to License NPF-3,revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle ML20134F1851996-10-28028 October 1996 Application for Amend to License NPF-3,requesting Revisions to 3/4.8.1.1,3/4.8.1.2,3/4.8.2.3,3/4.8.2.4 & 3/4.8 Re Electrical Power Systems ML20117P5301996-09-17017 September 1996 Application for Amend to License NPF-3,supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8441996-09-12012 September 1996 Application for Amend to License NPF-3,revising Reactivity Control Systems & Emergency Core Cooling Systems ML20117M1971996-09-0404 September 1996 Application for Amend to License NPF-3,App A,Modifying TS 6.2.3 by Removing Specific Overtime Limits & Working H from TS Consistent W/Nrc Recent Determination,On Generic Basis, That Limits Need Not Be Specified ML20116K2601996-08-0707 August 1996 Application for Amend to License NPF-3,changing Tech Specs 1.0, Definitions, Bases 3/4.0, Applicability & 3/4.6.2.1, Containment Sys - Depressurization & Cooling Sys - Containment Spray Sys ML20117K1871996-05-28028 May 1996 Application for Amend to License NPF-3,revising TS 3/4.3.1.1 RPS Instrumentation & TS 3/4.3.2.2 - Anticipatory RTS Instrumentation to Increase Trip Device Test Interval ML20107L3541996-04-18018 April 1996 Application for Amend to License NPF-3,requesting NRC Review & Approval to Use Alternate Electrical Lineup.Station Blackout DG as Standby Emergency Power Source to Supply Loads Normally Supplied by EDG 1,while Being Reworked ML20101M1601996-03-29029 March 1996 Application for Amend to License NPF-3,App A,Re Surveillance Requirements for Charcoal Filter Lab Testing to Revise Testing Methodology Used to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20101C6911996-03-0606 March 1996 Application for Amend to License NPF-3,revising TS 3/4.5.2 to Allow Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI 1-2 Pump Until 10th Refueling Outage, Scheduled to Begin 960408 ML20100E0051996-02-0505 February 1996 LAR 93-0003 to License NPF-3,revising Table 3.3-3 of TS 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation to More Accurately Reflect Design & Actuation Logic of Plant Sequencers & Undervoltage Relays ML20095F5861995-12-12012 December 1995 Application for Amend to License NPF-3,revising TSs Re Containment Sys ML20098C5131995-10-0202 October 1995 Application for Amend to License NPF-3,revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C1071995-09-29029 September 1995 Application for Amend to License NPF-3,modifying TS 3.4.3 & Associated Bases for Pressurizer Code Safety Valve Lift Setpoint Tolerances ML20098C3931995-09-29029 September 1995 Application for Amend to License NPF-3,revising Tech Spec 3/4.1.2.8, Reactivity Control Sys - Borated Water Sources - Shutdown, Tech Spec 3/4.1.2.9, Reactivity Control Sys - Operating & TS 3/4.5.1, ECCS - Core Flooding Tanks 1999-09-07
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20216E6051999-09-0707 September 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20210H0631999-07-28028 July 1999 Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, by Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4131999-07-27027 July 1999 Application for Amend to License NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G8831999-07-26026 July 1999 Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5251999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G4631999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumention & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20212H9901999-06-22022 June 1999 Amend 233 to License NPF-3,relocating TS Surveillance Requirement from TS 3/4.6.5.1, Shield Building - Emergency Ventilation Sys to TS Section 3/4.6.5.2, Shield Building Integrity ML20195F9121999-06-10010 June 1999 Application for Amend to License NPF-3,changing TS 3/4.6.4.4 Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20207G6591999-06-0808 June 1999 Amend 232 to License NPF-3,revising TSs in Response to 990309 Application.Changes Increase Inservice Insp Interval & Reduce Scope of Volumetric & Surface Examinations for Reactor Coolant Pump Flywheels ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20206U7301999-05-19019 May 1999 Amend 231 to License NPF-3,revising Administrative Requirements Re TS 6.5.1.6,TS 6.8.4.d,TS 6.10,TS 6.11, TS 6.12 & TS 6.15 ML20205E4961999-03-19019 March 1999 Application for Amend to License NPF-3,requesting Withdrawal of Proposed New Action B to TS 3.6.5.2,previously Submitted in 981027 Application ML20204F1691999-03-0909 March 1999 Application for Amend to License NPF-3,adopting Changes in Frequency & Scope of Volumetric Exams Justified by W TR WCAP-14535A ML20206U2381999-02-0909 February 1999 Amend 229 to License NPF-3,revising TS 3/4.8.2.3 & Associated Bases & SRs for Battery Testing ML20196F3791998-11-30030 November 1998 Supplemental Application for Amend to License NPF-3, Proposing Changes to License Conditions 2.C(6) & 2.E by Transferring Operating Authority for DBNPS from Toed & Centerior Svc Co to Firstenergy Nuclear Operating Co ML20155E3181998-10-28028 October 1998 Application for Amend to License NPF-3,revising Various Sections of TS 6.0, Administrative Controls, Including Relocation of Contents of 6.11 to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D8481998-10-27027 October 1998 Application for Amend to License NPF-3,revising Existing TS SRs 4.8.2.3.2.d,4.8.2.3.2.e,4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155D7731998-10-27027 October 1998 Application for Amend to License NPF-3,relocating Existing TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155E0701998-10-27027 October 1998 Application for Amend to License NPF-3,revising TSs 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation by Providing Potential Reduction in Spurious Trip Rate to Provide Cost Savings in Excess of $50,000 ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20151W2811998-09-0808 September 1998 Application for Amend to License NPF-3,permitting Use of Framatome Cogema Fuels M5 Advanced Alloy Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20236M9321998-07-0707 July 1998 Amend 225 to License NPF-3,relocating TS Tables of Response Time Limits to Davis-Besse Technical Requirements Manual ML20236K4231998-06-30030 June 1998 Amend 224 to License NPF-03,revises TS Section 1.0, Definitions, to Clarify Meaning of Core Alteration, Relocates TS Section 3/4.9.5 & Associated Bases to Technical Requirements Manual ML20236G6461998-06-29029 June 1998 Application for Amend to License NPF-3,transferring Operating Authority for DBNPS from TE & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments Included ML20236R2301998-06-29029 June 1998 Resubmitted Application for Amend to License NPF-3, Transferring Operating Authority for DBNPS from Teco & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Safety Assessment & EA Included ML20249A7511998-06-11011 June 1998 Amend 223 to License NPF-3,revising TS Section 3/4.6.1.3 & Associated Bases ML20249A7611998-06-11011 June 1998 Amend 222 to License NPF-3,revising TS Section 3/4.2 ML20217P8671998-04-24024 April 1998 Application for Amend to License NPF-3,modifying Existing TS 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases by Relocating Tables of Response Time Limits from TS to Plant USAR Technical Requirements Manual ML20217P8251998-04-24024 April 1998 Application for Amend to License NPF-3,clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20216B8291998-04-14014 April 1998 Amend 220 to License NPF-3,revising TS 3/4.4.5,TS 3/4.4.6.2 & Associated Bases to Allow Use of Repair Roll SG Tube Repair Process ML20203L0861998-02-26026 February 1998 Application for Amend to License NPF-3 to Revise TS 3/4.4.5 & TS 3/4.4.6.2,incorporating New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20202C6011998-02-0303 February 1998 Amend 219 to License NPF-3,revising TS Sections 3/4.8.1, AC Sources, TS Section 3/4.8.2, Onsite Power Distribution Sys, TS Table 4.8.1, Battery Surveillance Requirements, & Associated Bases ML20197J5861997-12-23023 December 1997 Application for Amend to License NPF-3,revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20197J2511997-12-23023 December 1997 Application for Amend to License NPF-3.Amend Changes TS Definitions 1.12,TS 3/4.9.5 & New TS 3.0.6 ML20203C1491997-12-0202 December 1997 Amend 216 to License NPF-3,revising TS 3/4.5.2,TS 3/4.5.3 & TS 3/4.7.Several Surveillance Intervals Changed from 18 Months to Once Each Refueling Interval ML20203B1851997-12-0202 December 1997 Amend 218 to License NPF-3,extending SR Intervals from 18 to 24 Months Based on Results of Plant Instrument Drift Study ML20203C1341997-12-0202 December 1997 Amend 217 to License NPF-3,revising Surveillance Interval from 18 Months to Each Refueling Interval for TS 3/4.5.2, TS 3/4.6.5.1,TS 3/4.7.6.1,TS 3/4.7.7.2,TS 3/4.9.12 & TS Bases 3/4.7.7 ML20217R2801997-08-26026 August 1997 Application for Amend to License NPF-3,clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2831997-08-26026 August 1997 Application for Amend to License NPF-3,modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5931997-07-29029 July 1997 Suppl 950929 to Application for Amend to License NPF-3, Change TS 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating & Associated Bases 3/4.4.2 & 3/4.4.3 ML20141F1051997-06-24024 June 1997 Application for Amend to License NPF-3,deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138A3201997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Conversion to 24-month Fuel Cycle ML20138C3131997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Rev to TS 3/4.7.6 to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20137M1061997-03-31031 March 1997 Application for Amend to License NPF-57,revising TS to Improve Consistency Between TS & Plant Configuration, Operation & Testing & Complete Required CA to Resolve TS Discrepancies Identified in CA Program ML20138M1251997-02-14014 February 1997 Application for Amend to License NPF-3,requesting Delay of Heat Removal Sys Valve Pit Surveillance Requirements ML20134D7461997-01-30030 January 1997 Application for Amend to License NPF-3,revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0561997-01-20020 January 1997 Application for Amend to License NPF-3,involving TS 3/4.5.3 Re ECCS Subsystems ML20132C7771996-12-13013 December 1996 Application for Amend to License NPF-3,authorizing Transfers of Control ML20132B6871996-12-11011 December 1996 Application for Amend to License NPF-3,revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle ML20134J7741996-11-0808 November 1996 Amend 212 to License NPF-3,revising TS 6.2.3, Facility Staff Overtime. Procedural Control Requirement Added to TS That Will Ensure Monthly Review of Overtime for Personnel Who Perform Safety Related Functions 1999-09-07
[Table view] |
Text
-. ~. _ _ _ _ _ _ _.
i Docket-Numbar 50-346 i
Liesnse Numb 3rLNPF-3 Serial Number 2071 p=
Enclosure Page 1 i.
i 9'
i i
j..
APPLICATION FOR AMENDMENT i
TO j
. FACILITY OPERATING LICENSE NUMBER NPF-3 l
DAVIS-BESSE NUCLEAR POVER STATION f
UNIT NUMBER 1 I
l Attached are the requested' changes to the Davis-Besse' Nuclear Power 4'
Station, Unit. Number.1 Facility Operating License Number NPF-3.,
Als o..
i'
. included is the Safety Assessment and Significant Hazards l
Consideration.
4 The proposed changes (submitted under cover letter Serial Number 2071) concerns a
Appendix A, Technical Specification Section 3/4.6.4.3, containment Hydrogen Dilution System f
. Appendix A, Technical Specification Bases 3/4.6.4, Combustible Gas L
Control i
By:
D. C.-Shelton-Vice President - Nuclear--
[
Sworn and Subscribed before me this' 21st day of December. :
I Y//@
/A/Sll9A -
~
i NotaryP/11c,BtateofOhio 1l' CW L WOOD, f!atary PutJ'c
- 2:e ciOhio MyCommidon EgitesJuly1.1996 i
s
+
9212280204-921221 PDR ADOCK 05000346 P-PDR
Docket Numbar 50-346 Licensa Number NPF-3 Serial Number 2071 Enclosure Page 2 The following information is provided to support issuance of the requested changes to the Davis-Besse Nuclear Power Station. Unit Number 1 Operating License Number NPF-3, Appendix A, Technical Specification (TS) 3/4.6.4.3, Containment Hydrogen Dilution System, and its associated Bases.
A.
Time Required to Implement: This change is to be implemented 4
within 90 days after the NRC issuance of the License Amendment.
B.
Reason for Change (License Amendment Request Number 92-0009):
The addition of the Action statement to the Technical Specifications to allov both containment hydrogen dilution systems to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> vill avoid a potential unwarranted entry into TS 3.0.3 and subsequent plant shutdown.
C.
Safety Assessment and Significant Hazards Consideration See Attachment.
4 i
t
Docket Number 50-346
. License Number NPF-3:
Serial Number 2071 Attachment Page 1 l
SAFETY ASSESSMENT AND SIGNIFICANT. HAZARDS CONSIDERATION
~
l TITLE:
Addition of an-Action Statement to Technical Specification (TS) 3/4.6.4.3, Containment Hydrogen Dilution System., Addressing Two-i Inoperable Containment Hydrogen Dilution Systems; and Related Change to Bases 3/4.6.4, Combustible Gas Control, Adding a Discussion of the j
llydrogen Recombination System.
DESCRIPTION:
i l
The purpose of the proposed changes is to modify-the Davis-Besse l'
Nuclear Power Station (DBNPS) Operating License NPF-3, Appendix A TS 3/4.6.4.3 (Containment Hydrogen Dilution (CHD) System) and its
{_
associated Bases.
l The. proposed change-to TS 3/4.6.4.3 vill add an additional Action 1
statement which vill state: "With both containment hydrogen. dilution l
systems inoperable, restore at least one dilution system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in~at least HOT STANDBY vithin the next'6 J
hours." This vill provide a reasonable time period under-most circumstances to-restore at least one containment hydrogen dilution system to operable status, and therefore, avoid putting the plant through an unwarranted shutdown.
A proposed change to TS-Bases 3/4.6.4 clarifies that the-Containment Hydrogen Purge System Filter Unit functions in conjunction with the CHD System.
An additional proposed change to TS Bases 3/4.6.4 vill add a paragraph l
vhich vill states "As a backup to the CHD System and the Containment Hydrogen Purge System, the capability to install an external hydrogen
[
recombination system has been provided." This vill provide a description of the alternative means of contro111ng' hydrogen
[
concentration.
I SYSTEMS, COMPONENTS,-AND ACTIVITIES AFFECTED:
l l
Combustible Gas Control System (Including Hydrogen Recombination l
System)
SAFETY FUNCTIONS OF THE AFFECTED SYSTEMS, COMPONENTS,' AND ACTIVITIES:-
The Combustible Gas Control System is described in the DBNPS Updated Safety Analysis Report (USAR)-Subsection 6.2.5, combustible Gas Control in Containment Vessel. The Combustible Gas Control System is designed to control the concentration of hydrogen which may be released vithin the Containment Vessel' atmosphere following a-Loss of Coolant. Accident-(LOCA). The system is composed of the Containment Hydrogen Dilution (containment atmosphere dilution) System and the Hydrogen Purge System.
2.
Docket Number 50-346.
I.
License Numbar NPF-3 i
Serial Number 2071 Attachment Page 2
(
The Containment Hydrogen Dilution System is designed to add air to the-l Containment Vessel to effectively maintain hydrogen concentrations within acceptable limits.
i The Hydrogen Purge System is designed to release air from the Containment Vessel atmosphere through High Efficiency. Particulate. Air 3
(HEPA) filters and charcoal filters to the station vent.
The Hydrogen l
Purge System operates in conjunction with the Containment Hydrogen i
Dilution System. The Hydrogen Purge System is addressed by TS l
3/4.6.4.4 which provides for a 30-day allowed outage time.
I j
Post-accident hydrogen mixing is adequately accomplished by natural l
convective currents along with the turbulence created by-the combined action of the containment spray and the containment air cooler fans.
l As a backup to the Containment Hydrogen Dilution System and the Hydrogen Purge System,.the capability to install an external hydrogen l
recombination system has been provided at DBNPS in accordance with l~
10 CFR 50.44, Section(c)(3)(li).
Following a LOCA, hydrogen gas may accumulate within the Containment j
Vessel from various sources. If a sufficient amount of hydrogen.is generated, it may react with oxygen present in the Containment Vessel
[
atmosphere at rates rapid enough to lead to high temperatures and significant overpressurization of the Containment Vessel..As stated in AEC Safety Guide Number 7, the lover flammability limit for hydrogen in i
air saturated with water vapor at room temperature and atmospheric j
pressure is assumed to be four volume percent.
i The Combustible Gas Control System components are designed to be operated as necessary to maintain the maximum. hydrogen concentration in i
the Containment Vessel at or below-three volume percent following a l
LOCA. The limit of three volume percent was chosen to reflect a reasonable margin to alleviate problems such as nonhomogeneous mixing, etc.
Using the conservative assumptions of AEC Safety Guide Number 7, j
a concentration of three volume percent is reached at approximately 21 i
days after the LOCA.
L The Containment Hydrogen Dilution (CHD) System consists of two full L.
capacity, redundant, rotary, positive displacement type blowers to supply air to the containment. The CHD system controls the hydrogen concentration by-the addition of air to the Containment Vessel.
resulting in a pressurization of the containment and suppression of the hydrogen volume fraction.
The Hydrogen Recombination System functions as a means of reducing any i
hydrogen concentration in the Containment Building.
The air containing.
hydrogen is pumped from containment-through the recombiner.
The' air is l
heated electrically within the recombiner-until recombination occurs-i between the hydrogen and oxygen to form vater vapor. The hydrogen free effluent is then returned to containment. The installed system includes piping, manual remote operated valves, and electrical hookups L
for the self-contained Hydrogen Recombiner that would-be brought on-site if the need should arise.
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Docket Number 50-346 License Number NPF-3 Serial Number 2071 Attachment Page 3 EFFECTS ON SAFETY:
The proposed change to TS 3/4.6.4.3 adding an additional Action statement allowing both containment hydrogen dilution-systems to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, is acceptable because, as noted above, the lover flammability limit is assumed to be four volume percent (hydrogen). As shown in USAR Figure 6.2-50, Post-LOCA Hydrogen Percent By Volume, and reiterated in Section 6.2.5, Combustible Gas Control l
Systems, of the NRC Safety Evaluation Report for the Operating License J
(NUREG-0136, December 1976), this concentration vould not be reached until approximately 37 days following a postulated LOCA. This provides ample time to either restore at least one containment hydrogen dilution system to functionality (depending on the location and nature of the cause for inoperability), or to install the external hydrogen recombination system, in the highly unlikely event that a LOCA occurs during the 72-hour allovable outage time allotted by the proposed nev Action statement. Therefore, it is concluded that this proposed change has no adverse effect on plant safety.
The proposed changes to TS Bases 3/4.6.4 provide additional clarifying information, and have no adverse effect on plant safety.
SIGNIFICANT_ HAZARDS CONSIDERATION:
The Nuclear Regulatory Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazard exists due to a proposed amendment to an Operating License for a facility.
A proposed amendment to an Operating License for a facility involves no i
significant hazards consideration if operation of the facility in accordance with the proposed changes would (1) Not involve a significant increase in the probability or consequences of an accident previously evaluated; (2) Not create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Not involve a significant reduction in a margin of safety. Toledo Edison has reviewed the proposed change and determined that a significant hazards consideration does not exist because operation of the Davis-Besse Nuclear Power Station, Unit Number 1, in accordance 1
with these changes vould la. Not involve a significant increase in the probability of an accident previously evaluated because no Updated Safety Analysis Report (USAR) accident initiators are affected by the proposed changes. The proposed change to TS 3/4.6.4.3 adding an additional Action statement allowing both containment hydrogen dilution J
systems to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> has no bearing on the probability of an accident previously evaluated. The proposed changes to TS Bases 3/4.6.4 provide additional clarifying inf rmation regarding the containment Hydrogen Purge System Filter Unit and the Hydrogen Recombiner System, and have no adverse effect on the probability of experiencing an accident previously evaluated.
Docket.Numbar 50-346 License Number NPF-3 Serial Number 2071 Attachment Page 4 J
lb. Not involve a significant increase in the consequences of an accident previously evaluated because the proposed changes do not invalidate accident conditions or assumptions used in evaluating the radiological consequences of any accident. The proposed change to TS 3/4.6.4.3 adding an additional Action statement allowing both containment hydrogen dilution systems to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> does not alter the source term, containment isolation, or allovable releases, and therefore vill not increase the radiological consequences of a previously evaluated accident. The proposed changes to TS Bases 3/4.6.4 provide additional clarifying information regarding the Containment Hydrogen Purge System Filter Unit and the Hydrogen Recombiner System, and have no adverse effect on the consequences of an accideat previously evaluated.
2a. Not create the possibility of a new kind of accident from any i
1 accident previously evaluated because no ne / types of failures or accident initiators are introduced by the ;roposed changes.
2b. Not create the possibility of a different kind of accident from any accident previously evaluated because no different accident initiators or failure mechanisms are introduced by the proposed changes.
3.
Not involve a significant reduction in the margin of safety.
The proposed change to TS 3/4.6.4.3 adding an additional Action statement allowing both containment hydrogen dilution systems to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> will not have an adverse effect on the margin of safety because as shown in USAR Figure 6.2-50, Post-LOCA Hydrogen Percent by Volume, the lover flammability limit of four volume percent hydrogen vould not be reached until approximately 37 days following a postulated Loss of Coolant Accident (LOCA). The hydrogen concentration control function can be established in the event of a LOCA via the hydrogen recombination system within this timeframe. All accident analyses will remain valid. The proposed changes to TS Bases 3/4.6.4 provides additional clarifying information and have no adverse impact on the margin of safety.
CONCLUSION:
On the basis of the above, Toledo Edison has determined that the License Amendment Request does not involve a significant hazards consideration.
As this License Amendment Request concerns a proposed change to the Technical Specifications that must be reviewed by the Nuclear Regulatory Commission, this License Amendment Request does not constitute an unreviewed safety question.
ATTACHMENT:
Attached are the proposed marked-up changes to the Operating License.
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