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| | number = ML12264A320 | | | number = ML12264A320 |
| | issue date = 10/11/2012 | | | issue date = 10/11/2012 |
| | title = South Texas Project, Units 1 and 2 - Meeting Handout for 10/11/12 Pre-licensing Meeting License Amendment Request to Revise the Fire Protection Program (TAC Nos. ME9182 and ME9183) | | | title = Meeting Handout for 10/11/12 Pre-licensing Meeting License Amendment Request to Revise the Fire Protection Program |
| | author name = Taplett K | | | author name = Taplett K |
| | author affiliation = South Texas Project Nuclear Operating Co | | | author affiliation = South Texas Project Nuclear Operating Co |
| | addressee name = Singal B K | | | addressee name = Singal B |
| | addressee affiliation = NRC/NRR/DORL/LPLIV | | | addressee affiliation = NRC/NRR/DORL/LPLIV |
| | docket = 05000498, 05000499 | | | docket = 05000498, 05000499 |
| | license number = NPF-076, NPF-080 | | | license number = NPF-076, NPF-080 |
| | contact person = Singal B K | | | contact person = Singal B |
| | case reference number = TAC ME9182, TAC ME9183 | | | case reference number = TAC ME9182, TAC ME9183 |
| | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs |
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| {{#Wiki_filter:Pre-licensing Meeting for License AmendmentRequesttoRevise Amendment Request to Revise the Fire Protection Program at the South Texas ProjectOctober11,2012 October 11, 2012 1 Agenda Agenda*Introductions*PurposeBkd*B ac k groun d*Fire Protection Program Change | | {{#Wiki_filter:Pre-licensing Meeting for License Amendment Request to Revise the Fire Protection Program at the South Texas Project October 11, 2012 1 |
| *BasesofChange
| | |
| *Bases of Change*Additional Information to be Developed | | Agenda |
| *Summar y y*Questions 2 | | * Introductions |
| SouthTexasProject(STP)Representatives South Texas Project (STP) Representatives*Mike Murray -Manager, Regulatory Affairs
| | * Purpose |
| *KenTaplett | | * B k Background d |
| -LicensingEngineer Ken Taplett Licensing Engineer*Frank Cox -Fire Safe Shutdown Engineer
| | * Fire Protection Program Change |
| *Charles Albur y -Thermal-H y draulic Anal y sis Su p erviso r yyyp*Donald Rohan -Operations Procedure Writer -Responsible for plant off-normal procedures in response to fire | | * Bases of Change |
| -PreviouslylicensedasaSeniorReactorOperator 3 Previously licensed as a Senior Reactor Operator Purpose PurposeDescribe the STP Nuclear O p eratin g Com p an y p ro p osal pgpyppto revise the South Texas Project, Units 1 and 2, Fire Protection Program 4 | | * Additional Information to be Developed |
| | * Summaryy |
| | * Questions 2 |
| | |
| | South Texas Project (STP) Representatives |
| | * Mike Murray - Manager, Regulatory Affairs |
| | * Ken Taplett - Licensing Engineer |
| | * Frank Cox - Fire Safe Shutdown Engineer |
| | * Charles Alburyy - Thermal-Hydraulic y Analysis y Supervisor p |
| | * Donald Rohan - Operations Procedure Writer |
| | - Responsible for plant off-normal procedures in response to fire |
| | - Previously licensed as a Senior Reactor Operator 3 |
| | |
| | Purpose Describe the STP Nuclear Operating p g Company p yp proposal p |
| | to revise the South Texas Project, Units 1 and 2, Fire Protection Program 4 |
|
| |
|
| ===Background=== | | ===Background=== |
| Background*The change involves revising the STP Licensing Basis ftithlttihtdbilit f or mee ti ng th e a lt erna tive s h u td own capa bilit y.*STP is required by their licensing basis to meet the itf10CFR50AdiRStiIIIL requ i remen t s o f 10 CFR 50 , A ppen di x R , S ec ti on III.L , Alternative and dedicated shutdown capability.STPiscurrentlyrelyingoncompensatorymeasuresto
| | * The change involves revising the STP Licensing Basis f meeting for ti the th alternative lt ti shutdown h td capability. |
| *STP is currently relying on compensatory measures to meet their licensing basis. | | bilit |
| *STPrecentlywithdrewalicenseamendmentrequest
| | * STP is required by their licensing basis to meet the requirements i t off 10 CFR 50 50, A Appendix di RR, S Section ti III III.L, L |
| *STP recently withdrew a license amendment request because insufficient information was provided to the NRC staff to approve the amendment request. | | Alternative and dedicated shutdown capability. |
| 5 FireProtectionProgramChange Fire Protection Program Change*In order to meet the regulatory requirements of Appendix R, Section III.L, the proposed amendment request:-Credits the performance of operator actions in the control room, in addition to tripping the reactor, prior to evacuation due to a fire fire. -Credit the automatic trip of the main turbine in response to a reactortrip reactor trip.6 BasesofChange Bases of Change*Regulatory Guide 1.189, Fire Protection for Nuclear Power Plants, usuallycreditsareactortrippriortocontrolroomevacuation usually credits a reactor trip prior to control room evacuation | | * STP is currently relying on compensatory measures to meet their licensing basis. |
| .In order to credit additional control room actions:Thlitdttthtibfd
| | * STP recently withdrew a license amendment request because insufficient information was provided to the NRC staff to approve the amendment request. |
| -Th e li censee mus t d emons t ra t e th e ac ti ons can b e per f orme d-The licensee should ensure that such actions cannot be negated by subsequent spurious actuation signals resulting from the postulated fire.-The licensee should consider one spurious actuation to occur before tlfthltihidthhthlttidditd con t ro l o f th e p l an t i s ac hi eve d th roug h th e a lt erna ti ve or d e di ca t e d shutdown system. *Both (1) the loss of offsite power and (2) maintainin g offsite p ower ()p()gpscenarios should be considered.*Automatic functions of circuits in the control room fire should not be creditedifthefunctionwouldmitigatetheconsequences 7 credited if the function would mitigate the consequences | | 5 |
| .
| | |
| BasesforChange(continued)
| | Fire Protection Program Change |
| Bases for Change (continued)*The feasibility and reliability of the additional operator actions have been demonstrated.*A single spurious actuation analysis demonstrates that no single spurious actuation could negate a control room actioninmannerthatAppendixR,SectionIII.L action in manner that Appendix R, Section III.L requirements are not met. | | * In order to meet the regulatory requirements of Appendix R, Section III.L, the proposed amendment request: |
| *Theautomaticturbinetripanalysisprovidesreasonable
| | - Credits the performance of operator actions in the control room, in addition to tripping the reactor, prior to evacuation due to a fire. |
| *The automatic turbine trip analysis provides reasonable assurance that the turbine will trip when actuated by a reactor trip and would not subsequently be negated by a fireinducecircuitfailure 8 fire-induce circuit failure. | | fire |
| BasesforChange(continued)
| | - Credit the automatic trip of the main turbine in response to a reactor trip trip. |
| Bases for Change (continued)*Defense-in-De p th Anal y sis addresses the py following: | | 6 |
| -FirePreventionMeasures Fire Prevention Measures-Capability to detect, control and extinguish fires-Protection of structures, systems and components so thatfireswillnotpreventsafeshutdown that fires will not prevent safe shutdown-Safety margin analyses*Analysis for those actions with small time margins shows the plantcanachievesafeshutdownconditionswhen plant can achieve safe shutdown conditions when considering instrument uncertainties.*Analysis to justify plant safe shutdown is achievable in event all the requested actions are not completed. | | |
| 9 Additional InformationtbDld t o b e D eve l ope dAddress the following scenario: | | Bases of Change |
| -S p urious actuation of p ressurizer p owe r-o p erated relief valve ppp p (PORV), and | | * Regulatory Guide 1.189, Fire Protection for Nuclear Power Plants, usually credits a reactor trip prior to control room evacuation evacuation. |
| -Pressurizer PORV block valve cannot be closed due to fire-induced circuit failure, and | | In order to credit additional control room actions: |
| -No actions credited in the c ontrol room other than manual reactor trip and automatic turbine trip, and | | - Th The licensee li mustt d demonstrate t t th the actions ti can bbe performed f d |
| -Loss of offsite p ower. 10 p Additional InformationtbDld t o b e D eve l ope d*Scenario will address the following:-Ability to maintain and/or restore natural circulation-Impact on sub-cooling marginItflitit-I mpac t on f ue l i n t egr it y 11 AddiilIfi Addi t i ona l I n f ormat i on to be DevelopedAddthittltll | | - The licensee should ensure that such actions cannot be negated by subsequent spurious actuation signals resulting from the postulated fire. |
| *Add ress th e i mpac t on reac t or vesse l wa t er l eve l for a spuriously opened steam generator PORV.*Address the impact of a control room fire on the initiationofsafetyinjection. | | - The licensee should consider one spurious actuation to occur before control t l off the th plant l t is i achieved hi d th through h ththe alternative lt ti or ddedicated di t d shutdown system. |
| initiation of safety injection. | | * Both ((1)) the loss of offsite power p and ((2)) maintaining g offsite p power scenarios should be considered. |
| 12 Summary Summary*License Amendment Request will be resubmitted Requestapprovalofsameoperatoractionsandautomatic | | * Automatic functions of circuits in the control room fire should not be credited if the function would mitigate the consequences consequences. |
| -Request approval of same operator actions and automatic turbine trip as the previously withdrawn request.-Bases for approval are the actions can be performed and that theactions cannot be negated by subsequent spurious actuation signals resulting from the postulated fire.-Automatic turbine trip relies on success of reactor trip.-Sufficient defense-in-depth/safety margin exists to demonstrate safe shutdown conditions can be achieved based on analyses previously performed and additional information to be developed. | | 7 |
| 13 Questions? | | |
| | Bases for Change (continued) |
| | * The feasibility and reliability of the additional operator actions have been demonstrated. |
| | * A single spurious actuation analysis demonstrates that no single spurious actuation could negate a control room action in manner that Appendix R, Section III.L requirements are not met. |
| | * The automatic turbine trip analysis provides reasonable assurance that the turbine will trip when actuated by a reactor trip and would not subsequently be negated by a fire induce circuit failure fire-induce failure. |
| | 8 |
| | |
| | Bases for Change (continued) |
| | * Defense-in-Depth p Analysis y addresses the following: |
| | - Fire Prevention Measures |
| | - Capability to detect, control and extinguish fires |
| | - Protection of structures, systems and components so that fires will not prevent safe shutdown |
| | - Safety margin analyses |
| | * Analysis for those actions with small time margins shows the plant can achieve safe shutdown conditions when considering instrument uncertainties. |
| | * Analysis to justify plant safe shutdown is achievable in event all the requested actions are not completed. |
| | 9 |
| | |
| | Additional Information t be to b Developed D l d Address the following scenario: |
| | - Spurious p actuation of ppressurizer p power-operated p relief valve (PORV), and |
| | - Pressurizer PORV block valve cannot be closed due to fire-induced circuit failure, and |
| | - No actions credited in the control room other than manual reactor trip and automatic turbine trip, and |
| | - Loss of offsite p power. |
| | 10 |
| | |
| | Additional Information t be to b Developed D l d |
| | * Scenario will address the following: |
| | - Ability to maintain and/or restore natural circulation |
| | - Impact on sub-cooling margin |
| | - Impact I t on fuel f l integrity i t it 11 |
| | |
| | Additional Addi i l IInformation f i to be Developed |
| | * Add Address th the iimpactt on reactor t vessell water t llevell for a spuriously opened steam generator PORV. |
| | * Address the impact of a control room fire on the initiation of safety injection. |
| | 12 |
| | |
| | Summary |
| | * License Amendment Request will be resubmitted |
| | - Request approval of same operator actions and automatic turbine trip as the previously withdrawn request. |
| | - Bases for approval are the actions can be performed and that the actions cannot be negated by subsequent spurious actuation signals resulting from the postulated fire. |
| | - Automatic turbine trip relies on success of reactor trip. |
| | - Sufficient defense-in-depth/safety margin exists to demonstrate safe shutdown conditions can be achieved based on analyses previously performed and additional information to be developed. |
| | 13 |
| | |
| Questions? | | Questions? |
| 14}} | | 14}} |
Letter Sequence Meeting |
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MONTHYEARML12243A4042012-09-25025 September 2012 Notice of Prelicensing Meeting with STP Nuclear Operating Company to Discuss Proposed Amendment for Approval of Revised Fire Protection Program Related to Alternate Shutdown Capability for South Texas, Units 1 and 2 Project stage: Meeting ML12264A3202012-10-11011 October 2012 Meeting Handout for 10/11/12 Pre-licensing Meeting License Amendment Request to Revise the Fire Protection Program Project stage: Meeting ML12297A3312012-11-27027 November 2012 Summary of Prelicensing Meeting with STP Nuclear Operating Company to Discuss Proposed Amendment for Approval of Revised Fire Protection Program Related to Alternate Shutdown Capability for South Texas, Units 1 and 2 Project stage: Meeting 2012-11-27
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Category:Meeting Briefing Package/Handouts
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MF2400-MF2409) ML15111A0562015-04-15015 April 2015 Licensee Handouts (1 of 2) for 4/22/2015 Public Meeting Revised Roverd Section on Large Early Release Frequency Change for Large Break Loss-of-Coolant Accident(Tac Nos. MF2400-MF2409) ML15056A3862015-02-25025 February 2015 NRC Slides for February 25, 2015 Public Meeting with STPNOC Concerning GSI-191 ML15049A4882015-02-18018 February 2015 Slides for February 25, 2015 Public Meeting ML15034A1512015-02-0505 February 2015 Integrated Leak Rate Test (ILRT) from 10 Years to 15 Years. 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[Table view] Category:Slides and Viewgraphs
MONTHYEARML22243A1312022-08-31031 August 2022 STP Nuclear Operating Company August 31, 2022 Presentation - Pre-Submittal Meeting for Updated Main Steam Line Break and Locked Rotor Dose Consequence Analysis to Address Extended Cooldown Timelines ML22214A0972022-08-0202 August 2022 Presentation by South Texas Project ML22153A2942022-06-17017 June 2022 richardsd-hv-th28 ML21203A2702021-07-26026 July 2021 Presentation - 7-26-21 Meeting with STPNOC Proposed South Texas Project Moderator Temperature Coefficient TS Change ML20248H5322020-09-0404 September 2020 STP Nuclear Operating Company September 14, 2020, Presentation - Pre-Submittal Meeting for Proposed South Texas Project Moderator Temperature Coefficient Surveillance Requirement Technical Specification Change ML20125A3362020-05-0404 May 2020 STP Presubmittal Meeting Exigent Accumulator LAR 2020-05-05 Presentation L-2020-LRM-0039 ML20034E8192020-02-0606 February 2020 Pre-Application Public Meeting for Proposed License Amendment Request to Revise the STPEGS Emergency Plan ML19095A6562019-04-0404 April 2019 NRR E-mail Capture - (External_Sender) Handout for 4/10/19 Meeting to Discuss a Proposed Request for South Texas Project, Units 1 and 2, Regarding Repair of Piping Using Carbon Fiber Repair Methods ML17004A0292017-01-0404 January 2017 Slides for January 4, 2017, Public Meeting on South Texas Project's Resposne to Aluminum Bronze Aging Management Request for Additional Information ML16356A0612016-12-21021 December 2016 12/21/2016 South Texas Project Aluminum Bronze Aging Management Request for Additional Information ML16350A3272016-11-17017 November 2016 Transcript of Advisory Committee on Reactor Safeguards Plant License Renewal Subcommittee Meeting - November 17, 2016 ML16264A3632016-09-20020 September 2016 Pre-Application Public Meeting for Proposed License Amendment Request to Revise the STPEGS Emergency Plan Staff Augmentation Times ML16172A0192016-07-25025 July 2016 STP Aluminum Bronze Selective Leaching Public Meeting - June 21, 2016 ML16188A3682016-07-0606 July 2016 Audit Presentation - Westinghouse Methodology for South Texas Unit 1 LAR: Operation with 56 Control Rods ML16062A3042016-03-0202 March 2016 TS 5.3.2 LAR Pre-Submittal Meeting Presentation - March 2, 2016 ML16033A0042016-01-19019 January 2016 Applicant's Slides for STP Meeting on Aluminum Bronze Aging Management ML15334A3972015-11-30030 November 2015 TS 5 3 2 Emergency LAR Pre-Submittal Meeting Presentation ML15274A5992015-10-0101 October 2015 10-01-15 Public Phone Call ML15034A1512015-02-0505 February 2015 Integrated Leak Rate Test (ILRT) from 10 Years to 15 Years. 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Halpin Re Participation in Commission Meeting on the Resolution of Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized Water Reactor (PWR) Performance on 09/29/10 2022-08-31
[Table view] |
Text
Pre-licensing Meeting for License Amendment Request to Revise the Fire Protection Program at the South Texas Project October 11, 2012 1
Agenda
- Additional Information to be Developed
South Texas Project (STP) Representatives
- Mike Murray - Manager, Regulatory Affairs
- Ken Taplett - Licensing Engineer
- Charles Alburyy - Thermal-Hydraulic y Analysis y Supervisor p
- Donald Rohan - Operations Procedure Writer
- Responsible for plant off-normal procedures in response to fire
- Previously licensed as a Senior Reactor Operator 3
Purpose Describe the STP Nuclear Operating p g Company p yp proposal p
to revise the South Texas Project, Units 1 and 2, Fire Protection Program 4
Background
- The change involves revising the STP Licensing Basis f meeting for ti the th alternative lt ti shutdown h td capability.
bilit
- STP is required by their licensing basis to meet the requirements i t off 10 CFR 50 50, A Appendix di RR, S Section ti III III.L, L
Alternative and dedicated shutdown capability.
- STP is currently relying on compensatory measures to meet their licensing basis.
- STP recently withdrew a license amendment request because insufficient information was provided to the NRC staff to approve the amendment request.
5
Fire Protection Program Change
- In order to meet the regulatory requirements of Appendix R,Section III.L, the proposed amendment request:
- Credits the performance of operator actions in the control room, in addition to tripping the reactor, prior to evacuation due to a fire.
fire
- Credit the automatic trip of the main turbine in response to a reactor trip trip.
6
Bases of Change
In order to credit additional control room actions:
- Th The licensee li mustt d demonstrate t t th the actions ti can bbe performed f d
- The licensee should ensure that such actions cannot be negated by subsequent spurious actuation signals resulting from the postulated fire.
- The licensee should consider one spurious actuation to occur before control t l off the th plant l t is i achieved hi d th through h ththe alternative lt ti or ddedicated di t d shutdown system.
- Both ((1)) the loss of offsite power p and ((2)) maintaining g offsite p power scenarios should be considered.
- Automatic functions of circuits in the control room fire should not be credited if the function would mitigate the consequences consequences.
7
Bases for Change (continued)
- The feasibility and reliability of the additional operator actions have been demonstrated.
- A single spurious actuation analysis demonstrates that no single spurious actuation could negate a control room action in manner that Appendix R,Section III.L requirements are not met.
- The automatic turbine trip analysis provides reasonable assurance that the turbine will trip when actuated by a reactor trip and would not subsequently be negated by a fire induce circuit failure fire-induce failure.
8
Bases for Change (continued)
- Defense-in-Depth p Analysis y addresses the following:
- Fire Prevention Measures
- Capability to detect, control and extinguish fires
- Protection of structures, systems and components so that fires will not prevent safe shutdown
- Safety margin analyses
- Analysis for those actions with small time margins shows the plant can achieve safe shutdown conditions when considering instrument uncertainties.
- Analysis to justify plant safe shutdown is achievable in event all the requested actions are not completed.
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Additional Information t be to b Developed D l d Address the following scenario:
- Spurious p actuation of ppressurizer p power-operated p relief valve (PORV), and
- Pressurizer PORV block valve cannot be closed due to fire-induced circuit failure, and
- No actions credited in the control room other than manual reactor trip and automatic turbine trip, and
- Loss of offsite p power.
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Additional Information t be to b Developed D l d
- Scenario will address the following:
- Ability to maintain and/or restore natural circulation
- Impact on sub-cooling margin
- Impact I t on fuel f l integrity i t it 11
Additional Addi i l IInformation f i to be Developed
- Add Address th the iimpactt on reactor t vessell water t llevell for a spuriously opened steam generator PORV.
- Address the impact of a control room fire on the initiation of safety injection.
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Summary
- License Amendment Request will be resubmitted
- Request approval of same operator actions and automatic turbine trip as the previously withdrawn request.
- Bases for approval are the actions can be performed and that the actions cannot be negated by subsequent spurious actuation signals resulting from the postulated fire.
- Automatic turbine trip relies on success of reactor trip.
- Sufficient defense-in-depth/safety margin exists to demonstrate safe shutdown conditions can be achieved based on analyses previously performed and additional information to be developed.
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Questions?
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