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Category:Meeting Briefing Package/Handouts
MONTHYEARML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23262B2602023-09-19019 September 2023 Slides - Constellation - Pre-Application EP 9/25/2023 Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23103A4072023-04-13013 April 2023 Presentation Slides for Information Call on 4/13/23 N2E Recirc Discharge Nozzle Weld Repair 2nd Request for Alternative ML22301A0132022-11-0303 November 2022 Pre-Submittal Meeting Presentation Slides - Risk Informed Completion Time (TSTF-505) and Risk Informed Categorization and Treatmentof SSCs (10 CFR 50.69) Proposed License Amendments ML22305A5922022-11-0303 November 2022 Pre-Submittal Meeting Presentation Slides - Risk Informed Completion Time (TSTF-505) and Risk Informed Categorization and Treatmentof SSCs (10 CFR 50.69) Proposed License Amendments-Updated ML22222A1122022-08-0404 August 2022 NMP1 Torus Corrosion Presentation for August 2022 Final ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20098D5082020-04-0909 April 2020 AST LOCA Approach to Elemental Iodine Removal - NRC Public Meeting on RAI 6 - April 9, 2020 ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19158A1202019-06-10010 June 2019 Rict & 50.69 LARs NRC Pre-submittal Meeting ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19133A0912019-04-22022 April 2019 Supplement to Containment Oxygen Concentration License Amendment Request ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17325A2772017-11-28028 November 2017 November 28, 2017 Pre-Submittal Teleconference Re Planned TSTF-542 LAR Presentation ML17306A0842017-11-0606 November 2017 Meeting Slide for Teleconference with Exelon Generation Company, LLC - Criticality Analysis for NMP1 Boraflex Racks: No Boraflex Credit, 3 Out of 4 Loading, and Cell Blockers ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML16153A3452016-06-0101 June 2016 Sign in Sheet and Handout ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML14084A5342014-03-26026 March 2014 Nrc/Nei Presentation Slides: 13-02 OIP Template Update ML13340A0912013-11-0101 November 2013 Regulatory Conference/Public Meeting - Loss of Shutdown Cooling - Ceng Presentation/Slides ML13059A3742013-03-13013 March 2013 Summary of Category 1 Public Meeting with Nine Mile Point Nuclear Station, Unit 2 Representatives to Discus Planned Amendment Request on Implementation of Mellla+ ML1212100442012-04-0303 April 2012 Meeting Slides - NFPA-805 Pre-Application Meeting with NRC Staff April 3, 2012 ML1113605612011-05-16016 May 2011 NRC Meeting Slides, Nine Mile Point & Fitzpatrick 2011 Annual Assessment Meeting ML0926506592009-09-15015 September 2009 Slides from the Public Meeting with Constellation Energy - Nine Mile Point ISFSI Presentation ML0913400442009-05-14014 May 2009 Annual Assessment Meeting Sign-in Sheet, April 30, 2009 ML0827705652008-10-27027 October 2008 Extended Power Uprate Pre-Application Meeting Slides ML0634800282006-12-0404 December 2006 Slides, Nine Mile Point 1 Alternate Source Term, from Nrc/Constellation Energy Meeting ML0619102902006-03-27027 March 2006 03/27/2006 Powerpoint Presentation - Nine Mile Point License Renewal NMP1 Drywell 2024-05-16
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24310A0672024-11-0505 November 2024 Constellation NRC Pre-Submittal Meeting Slides - Proposed Alternative for Reactor Vessel Closure Stud Exam Optimization ML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23262B2602023-09-19019 September 2023 Slides - Constellation - Pre-Application EP 9/25/2023 Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23103A4072023-04-13013 April 2023 Presentation Slides for Information Call on 4/13/23 N2E Recirc Discharge Nozzle Weld Repair 2nd Request for Alternative ML23080A2972023-03-21021 March 2023 Presentation Slides for Information Call on 3/21/23 N2E Recirc Discharge Nozzle Weld Repair Request for Alternative NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML22305A5922022-11-0303 November 2022 Pre-Submittal Meeting Presentation Slides - Risk Informed Completion Time (TSTF-505) and Risk Informed Categorization and Treatmentof SSCs (10 CFR 50.69) Proposed License Amendments-Updated ML22301A0132022-11-0303 November 2022 Pre-Submittal Meeting Presentation Slides - Risk Informed Completion Time (TSTF-505) and Risk Informed Categorization and Treatmentof SSCs (10 CFR 50.69) Proposed License Amendments ML22222A1122022-08-0404 August 2022 NMP1 Torus Corrosion Presentation for August 2022 Final ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20098D5082020-04-0909 April 2020 AST LOCA Approach to Elemental Iodine Removal - NRC Public Meeting on RAI 6 - April 9, 2020 ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML19158A1202019-06-10010 June 2019 Rict & 50.69 LARs NRC Pre-submittal Meeting ML19133A0912019-04-22022 April 2019 Supplement to Containment Oxygen Concentration License Amendment Request ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17325A2772017-11-28028 November 2017 November 28, 2017 Pre-Submittal Teleconference Re Planned TSTF-542 LAR Presentation ML17306A0842017-11-0606 November 2017 Meeting Slide for Teleconference with Exelon Generation Company, LLC - Criticality Analysis for NMP1 Boraflex Racks: No Boraflex Credit, 3 Out of 4 Loading, and Cell Blockers ML16153A3442016-06-0101 June 2016 Oswego Chamber of Commerce Assessment Meeting Presentation ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML14084A5342014-03-26026 March 2014 Nrc/Nei Presentation Slides: 13-02 OIP Template Update ML13340A0912013-11-0101 November 2013 Regulatory Conference/Public Meeting - Loss of Shutdown Cooling - Ceng Presentation/Slides ML13059A3742013-03-13013 March 2013 Summary of Category 1 Public Meeting with Nine Mile Point Nuclear Station, Unit 2 Representatives to Discus Planned Amendment Request on Implementation of Mellla+ ML1212100442012-04-0303 April 2012 Meeting Slides - NFPA-805 Pre-Application Meeting with NRC Staff April 3, 2012 ML1113605612011-05-16016 May 2011 NRC Meeting Slides, Nine Mile Point & Fitzpatrick 2011 Annual Assessment Meeting ML0926506592009-09-15015 September 2009 Slides from the Public Meeting with Constellation Energy - Nine Mile Point ISFSI Presentation ML0827705652008-10-27027 October 2008 Extended Power Uprate Pre-Application Meeting Slides ML0827503872008-09-29029 September 2008 Enclosure 2 Meeting Slides ML0811403012008-04-23023 April 2008 NRC Annual Performance Assessment Meeting ML0807901872008-03-18018 March 2008 NRC Annual Performance Assessment Slides, 2007 Reactor Oversight Program ML0712704232007-04-24024 April 2007 Constellation Slides - Nine Mile Point Meeting Annual Assessment Summary 2006-07 ML0710100842007-04-10010 April 2007 Slides for 04/24/2007 Nine Mile Point Annual Assessment Meeting ML0634800282006-12-0404 December 2006 Slides, Nine Mile Point 1 Alternate Source Term, from Nrc/Constellation Energy Meeting 2024-05-16
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Text
NEI 13-02 NMP2 Overall Integrated Plan Template for NRC OrderEA OrderEA-13-109 13 109 NRC Public Meeting March 26 26, 2014
Agenda
- OIP Template Development Schedule
- NMP2 2 OIP O Development/Staff l /S ff C Comments
Meeting Objectives
- Review of NRC Staff comments
- Proposed responses
- Clarifications 3
Template Development Information and d Key Dates
- Pilot plant(s) identified - Hatch as MK I & NMP2 as MK II
- Draft template by January 20, 2014 - Presented on Jan 15
- Final Draft template March 15, 2014 - After Pilots
- NEI 13-02 13 02 Revision for OIP template and FAQs by April 21, 21 2014
- NRC-NEI Joint Template Meetings
- January 15, 2014 - Complete (Draft Template & 3 FAQ)
- January 29 29, 2014 - (Template Elements & FAQs)
- February 19, 2014 (Pilot Plant Hatch, FAQs & White Papers)
- March 5, 2014 (NMP2 Pilot Differences, FAQ & White Paper)
- March 26, 2014 ((NRC Feedback on OIP Pilots/Workshop p Prep) p)
- Industry Template Workshop, April 9-10 in Baltimore
- NRC-NEI Check-up Conference Call Proposed for May 7 3/26/2014 4
Nine Mile Point Unit 2 SA HCVS Pilot OIP Comment Discussion and Reponses
Containment Ventilation Branch Applicable EA-12-049 Assumptions Assumptionp 049-8 All activities associated with EA-12-049 ((FLEX)) that are not specific to implementation of the HCVS (i.e., HCVS valves, instruments and motive force) can be credited as having been p
accomplished.
The assumption is not clear in the context of its need or its intended usage.g The activities associated with EA-12-049 that are not specific p to the implementation of the HCVS have no bearing on the HCVS implementation, expect when credit is taken for such actions after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, in which case the actions should be shown to be accomplishable under severe accident conditions. If there are any actions that are relied upon, beyond what were described in the OIP, they should be spelled out.
3/26/2014 6
Containment Ventilation Branch Response - assumption R ti 049 049-8 8 addresses dd FLEX actions ti associated i t d with ith debris removal, communication, notifications, SFP level and makeup, security response, opening doors for cooling and plant condition assumptions applicable to FLEX FLEX. Assumption 049 049-8 8 will be revised to make this clarification. A plant specific NMP2 assumption will be added to the OIP to address the assumption that FLEX strategies will provide power to HCVS support instrumentation shown on Page 18 of the OIP Plant Specific Assumption: EA-12-049 (FLEX) actions to restore power are sufficient to ensure continuous operation of non-dedicated containment instrumentation shown on Page 18 of the OIP OIP Key Parameter Component Identifier Indication Location Drywell pressure 2CMS*PI2A MCR 2CMS*PR2B Suppression Chamber pressure 2CMS*PI7A MCR 2CMS*PR7B Suppression Pool level 2CMS*LI9A MCR 2CMS*LR9B 2CMS*LI11A 2CMS*LI11B 2CMS LI11B 3/26/2014 7
Containment Ventilation Branch Assumption 109-10 Permanent modifications installed p per EA-12-049 are assumed implemented and may be credited for use in p
Order EA-13-109 response.
What are p permanent modifications are beingg referenced here? In order to take credit, the OIP p
needs to list the specific modifications, for staff to review and concur 3/26/2014 8
Containment Ventilation Branch Response - This assumption addresses the fact that plant modifications will be made to support FLEX implementation that may not be reflected in plant design documents reviewed for the HCVS order, but the assumed plant configuration includes all of the modifications made under the FLEX order order. These modifications will be part of the existing plant with the HCVS order is required to be completed.
Assumption 109-10 will be revised to make this clarification Where specific FLEX modifications will be used to support HCVS implementation implementation, these relationships will be explained in the OIP. For the NMP2 OIP example, the only FLEX modification that will directly support the HCVS function is to allow a FLEX generator to be connected to a 600 volt safety related bus, and it is assumed to be installed such that a FLEX g generator can be credited for HCVS operation beyond the initial 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sustained operational period. The ability to use of this modification and equipment during severe accident conditions to support HCVS functions will be confirmed.
Plant Specific Assumption: Modifications that allow a FLEX generator to be connected to a 600 volt safety related bus are assumed to have been installed such that a FLEX generator can be credited for HCVS operation beyond the initial 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sustained operational period 3/26/2014 9
Containment Ventilation Branch Reactor Building Track Bay - Is this a qualified seismic structure? Include a discussion in the OIP Response - The adjoining Reactor Building and Standby Gas Treatment rooms are Seismic Category 1 structures. The Reactor Building Track Bay is not classified as such but was built to the same standards as the adjoining buildings. This will be described in the OIP 3/26/2014 10
Containment Ventilation Branch Vent Path and Discharge - Include a sketch
((simplified, p , non-dimensional)) to depict p the vent routing and discharge.
Response - NMP2 requests clarification of what is being requested. A sketch of the proposed HCVS system is provided on Sketch 2 on page 37 of the OIP.
3/26/2014 11
Containment Ventilation Branch General Comment: Provide open items at the end of each discussion,, number them consecutively and capture them all in one of the Attachments at the end, similar to what was done in Hatch OIP template.
Response - There are three Open Items identified on the table in Attachment 7 like the Hatch OIP. There are four other activities to be completed during detailed design that are not considered to be open items 3/26/2014 12
Containment Ventilation Branch There is no condensation drain valve in NMP-2 y
vent line as in Hatch. Whyy is it not necessary?
Response - The NMP2 proposed HCVS design does include a condensate drain valve outside the Reactor Building. The purpose of this drain is to remove condensate downstream of the PCV at the piping low point. The HCVS piping is also sloped so that condensate in the system will drain back to the containment during operation.
3/26/2014 13
I&C Branch The 2nd last paragraph on page 17 states HCVS instrumentation accuracy qualifications need only be gross values, and yet the discussion at our previous meeting was the sites would select instruments of an easy procurement plant level quality quality. What would be a way to state the level of accuracy, which is best for the transmitters function and reflects the discussion?
Response
p - The instrument accuracy,y, in terms of % of full scale,, will be defined during detailed design and will be available during the HCVS implementation audit. The % accuracy will be commensurate with similar instrumentation in similar applications for the plant (pressure, temperature and radiation) radiation). The radiation monitor accuracy may vary over the range of the instrument and % accuracy is not expected to be the same as it will be for pressure and temperature. HCVS instrumentation is for indication only and will not provide system controll ffunctions.
i 3/26/2014 14
I&C Branch On page 18 will the criteria for intrinsic safe barriers be added to the I&C table and show manufacture with specifications?
Response - new instrumentation installed for the HCVS Order will be procured as intrinsically safe. This will be added to the NMP2 OIP.
3/26/2014 15
I&C Branch Is this a cycle time typo between pages 15,(1),
which saysy twelve and page p g 24,(i),
,( ), which states 13?
Response - NMP2 HCVS design is for at least 12 vent cycles in the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3/26/2014 16
I&C Branch The first sentence on the last paragraph of page 20 needs some clarity, and possibly answer what the instrument requires after a potential seismic event. Can this sentence be improved?
Response - Proposed revised wording: For the HCVS instruments that h are required d after f a potentiall seismic event, the following methods will be used to verify that the design and installation is reliable /
rugged and thus capable of ensuring HCVS functionality following a seismic event.
3/26/2014 17
I&C Branch What instrument details will be provided for the List instrumentation credited for the HCVS Actions?
Actions?
Response - location of instrument display, parameter being monitored and component identifier (when established during detailed design).
It is not intended that instrument loop diagrams will be provided in the OIP. There is really no instrument loop since this is not a control system b a manuall action system. The but h instrument string includes sensor, transmitter and indicator.
3/26/2014 18
I&C Branch Will all of the HCVS instrumentation component identifiers be included on ppage g 41,, Sketch 2.
Response - HCVS instrument component identifiers will be established later in the design process and included on plant P&ID drawings drawings.
They will be included on OIP Sketch 2 if available at the time of OIP submittal on June 30 30, 2014 2014.
3/26/2014 19
I&C Branch Follow up: would the I&C functional loop design description of the design be provided separately from the operation p of the HCVS,, ERGO: Table 2-1 HCVS Remote Manual Actions.
Response - HCVS instrument loop diagrams will not be provided as part of the OIP. All HCVS instruments are indication only (e.g., pressure, temperature, radiation) and dd do nott provide id system t control t l ffunctions ti ((e.g., alarms l
or valve modulating control). A functional diagram for how HCVS valves operate is provided on sketch 2. There i really is ll no iinstrument t t lloop since i thi this iis nott a control t l system but a manual action system. The instrument string includes a sensor, transmitter and indicator.
3/26/2014 20