ML18312A407: Difference between revisions

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| author name = Tobin J
| author name = Tobin J
| author affiliation = NRC/NRR/DORL/LPLI
| author affiliation = NRC/NRR/DORL/LPLI
| addressee name = Helker D P
| addressee name = Helker D
| addressee affiliation = Exelon Nuclear
| addressee affiliation = Exelon Nuclear
| docket = 05000277, 05000278
| docket = 05000277, 05000278
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:From: Tobin, Jennifer To: "Helker, David P:(GenCo-Nuc)" Cc: "Gropp Jr, Richard W:(GenCo-Nuc)"  
{{#Wiki_filter:From:           Tobin, Jennifer To:             "Helker, David P:(GenCo-Nuc)"
Cc:             "Gropp Jr, Richard W:(GenCo-Nuc)"


==Subject:==
==Subject:==
Peach Bottom Units 2 and 3 - Request for Additional Information (public)- LAR to Allow 2SRV/SVs OOS at High Pressure (EPID L-2018-LLA-0151)
Peach Bottom Units 2 and 3 - Request for Additional Information (public)- LAR to Allow 2SRV/SVs OOS at High Pressure (EPID L-2018-LLA-0151)
Date: Thursday, November 08, 2018 3:49:00 PM
Date:           Thursday, November 08, 2018 3:49:00 PM


==Dear Mr. Helker,==
==Dear Mr. Helker,==
By letter dated September 29, 2017 (Agencywide Documents Access and Management System (ADAMS)
By letter dated September 29, 2017 (Agencywide Documents Access and Management System (ADAMS)
Accession No.
Accession No. ML18150A388), Exelon Generation Company, LLC (EGC, the licensee) requested changes to the Technical Specifications (TSs) for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, to allow continued operation with two Safety Relief Valves/Safety Valves (SRVs/SVs) out-of-service and to increase the Reactor Coolant System Pressure Safety Limit.
ML18150A388), Exelon Generation Company, LLC (EGC, the licensee) requested changes to the Technical Specifications (TSs) for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, to allow continued operation with two Safety Relief Valves/Safety Valves (SRVs/SVs) out-of-service and to increase the Reactor Coolant System Pressure Safety Limit.
The Nuclear Regulatory Commissions (NRC) staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific request for additional information (RAI) our question is provided below (non-public version will be sent separately under separate cover). A clarification phone call will be held if needed. A response to these RAIs is requested by December 10, 2018.
The Nuclear Regulatory Commission's (NRC) staff is reviewing your submittal and has determined that additional information is needed to complete its review.
If you have any questions, please contact me at (301) 415-2328. A copy of this e-mail will be made publicly available in ADAMS.
The specific request for additional information (RAI) our question is provided below (non-public version will be sent separately under separate cover).
: Thanks, Jenny Jenny Tobin Project Manager NRR/DORL/LPL-1 Office O9-C12 Phone 301-415-2328 OFFICE OF NUCLEAR REACTOR REGULATION REACTOR SYSTEMS BRANCH REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS 2.1.2 AND 3.4.3 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 INTRODUCTION By application, dated May 30, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18150A388), Exelon Generating Company, LLC submitted a License Amendment Request (LAR) for Peach Bottom Atomic Power Station, Units 2 and 3 (PBAPS). The proposed LAR would revise PBAPS Technical Specifications to allow continued operation with two Safety Relief Valves/Safety Valves (SRVs/SVs) out-of-service and to increase the Reactor Coolant System Pressure Safety Limit (SL).
A clarification phone call will be held if needed.
Please note that the proprietary information in this request for additional information (RAI) is identified by underlined text enclosed within double square brackets ((( ))). ((This sentence is an example.))
A response to these RAIs is requested by December 10, 2018.
RAI-SRXB-1: ASME Overpressure Analysis with New Reactor Pressure Safety Limit Draft GDCs 9, 33 and final GDC 31 require overpressure protection during power operation be provided by relief/safety valves (SRVs/SVs) and protection system. The LAR proposed to raise a new reactor coolant system pressure safety limit so that the impact of the ASME overpressure analysis with 2 SRVOOS can be accepted. To facilitate the staff to review, provide the following information associated with the analysis as provided in the LAR:
If you have any questions, please contact me at (301) 415-2328.
: 1. Peach Bottom technical specification bases 2.1.1 indicates the RCS pressure SL is selected to be the lowest transient overpressure allowed by the applicable codes. Please verify the locations for the peak vessel pressure as reported in Tables 1 and 2 of the LAR are consistent with the TS bases.
A copy of this e-mail will be made publicly available in ADAMS.
: 2. A verification of whether a ((TRACG statistical pressure adder)) had been applied to the peak vessel pressure as reported in the Tables 1 and 2 of LAR. Note that it is known that an adder will be applied to the peak steam dome pressure. However, it is not clear if an adder will also be applied to the peak vessel pressure to be reported. Provide justification if the ((TRACG statistical pressure adder)) is not applied,
Thanks, Jenny Jenny Tobin Project Manager NRR/DORL/LPL-1 Office O9-C12 Phone 301-415-2328
: 3. A calculation or calculations with TRACG demonstrating that when the steam dome pressure approaching to or exceeding the proposed reactor steam dome limit of 1340 psig the corresponding peak vessel pressure will still be below the ASME limit of 1375 psig with margin.}}
  ***********************************************************************************************************************************
OFFICE OF NUCLEAR REACTOR REGULATION REACTOR SYSTEMS BRANCH REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS 2.1.2 AND 3.4.3 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 INTRODUCTION By application, dated May 30, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No.
ML18150A388), Exelon Generating Company, LLC submitted a License Amendment Request (LAR) for Peach Bottom Atomic Power Station, Units 2 and 3 (PBAPS).
The proposed LAR would revise PBAPS Technical Specifications to allow continued operation with two Safety Relief Valves/Safety Valves (SRVs/SVs) out-of-service and to increase the Reactor Coolant System Pressure Safety Limit (SL).
Please note that the proprietary information in this request for additional information (RAI) is identified by underlined text enclosed within double square brackets ([[
      ]]). [[This sentence is an example.]]
RAI-SRXB-1:
ASME Overpressure Analysis with New Reactor Pressure Safety Limit Draft GDCs 9, 33 and final GDC 31 require overpressure protection during power operation be provided by relief/safety valves (SRVs/SVs) and protection system.
The LAR proposed to raise a new reactor coolant system pressure safety limit so that the impact of the ASME overpressure analysis with 2 SRVOOS can be accepted.
To facilitate the staff to review, provide the following information associated with the analysis as provided in the LAR:
: 1.     Peach Bottom technical specification bases 2.1.1 indicates the RCS pressure SL is selected to be the lowest transient overpressure allowed by the applicable codes. Please verify the locations for the peak vessel pressure as reported in Tables 1 and 2 of the LAR are consistent with the TS bases. 2.     A verification of whether a [[TRACG statistical pressure adder]] had been applied to the peak vessel pressure as reported in the Tables 1 and 2 of LAR. Note that it is known that an adder will be applied to the peak steam dome pressure.
However, it is not clear if an adder will also be applied to the peak vessel pressure to be reported. Provide justification if the [[TRACG statistical pressure adder]] is not applied, 3.     A calculation or calculations with TRACG demonstrating that when the steam dome pressure approaching to or exceeding the proposed reactor steam dome limit of 1340 psig the corresponding peak vessel pressure will still be below the ASME limit of 1375 psig with margin.}}

Latest revision as of 03:46, 17 March 2020

Request for Additional Information (Public) - LAR to Allow 2SRV/SVs OOS at High Pressure
ML18312A407
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 11/08/2018
From: Jennifer Tobin
Plant Licensing Branch 1
To: David Helker
Exelon Nuclear
Tobin J, NRR/DORL/LPL1, 415-2328
References
EPID L-2018-LLA-0151
Download: ML18312A407 (2)
v • d • e


Text

From: Tobin, Jennifer To: "Helker, David P:(GenCo-Nuc)"

Cc: "Gropp Jr, Richard W:(GenCo-Nuc)"

Subject:

Peach Bottom Units 2 and 3 - Request for Additional Information (public)- LAR to Allow 2SRV/SVs OOS at High Pressure (EPID L-2018-LLA-0151)

Date: Thursday, November 08, 2018 3:49:00 PM

Dear Mr. Helker,

By letter dated September 29, 2017 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML18150A388), Exelon Generation Company, LLC (EGC, the licensee) requested changes to the Technical Specifications (TSs) for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, to allow continued operation with two Safety Relief Valves/Safety Valves (SRVs/SVs) out-of-service and to increase the Reactor Coolant System Pressure Safety Limit.

The Nuclear Regulatory Commissions (NRC) staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific request for additional information (RAI) our question is provided below (non-public version will be sent separately under separate cover). A clarification phone call will be held if needed. A response to these RAIs is requested by December 10, 2018.

If you have any questions, please contact me at (301) 415-2328. A copy of this e-mail will be made publicly available in ADAMS.

Thanks, Jenny Jenny Tobin Project Manager NRR/DORL/LPL-1 Office O9-C12 Phone 301-415-2328 OFFICE OF NUCLEAR REACTOR REGULATION REACTOR SYSTEMS BRANCH REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS 2.1.2 AND 3.4.3 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 INTRODUCTION By application, dated May 30, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18150A388), Exelon Generating Company, LLC submitted a License Amendment Request (LAR) for Peach Bottom Atomic Power Station, Units 2 and 3 (PBAPS). The proposed LAR would revise PBAPS Technical Specifications to allow continued operation with two Safety Relief Valves/Safety Valves (SRVs/SVs) out-of-service and to increase the Reactor Coolant System Pressure Safety Limit (SL).

Please note that the proprietary information in this request for additional information (RAI) is identified by underlined text enclosed within double square brackets ((( ))). ((This sentence is an example.))

RAI-SRXB-1: ASME Overpressure Analysis with New Reactor Pressure Safety Limit Draft GDCs 9, 33 and final GDC 31 require overpressure protection during power operation be provided by relief/safety valves (SRVs/SVs) and protection system. The LAR proposed to raise a new reactor coolant system pressure safety limit so that the impact of the ASME overpressure analysis with 2 SRVOOS can be accepted. To facilitate the staff to review, provide the following information associated with the analysis as provided in the LAR:

1. Peach Bottom technical specification bases 2.1.1 indicates the RCS pressure SL is selected to be the lowest transient overpressure allowed by the applicable codes. Please verify the locations for the peak vessel pressure as reported in Tables 1 and 2 of the LAR are consistent with the TS bases.
2. A verification of whether a ((TRACG statistical pressure adder)) had been applied to the peak vessel pressure as reported in the Tables 1 and 2 of LAR. Note that it is known that an adder will be applied to the peak steam dome pressure. However, it is not clear if an adder will also be applied to the peak vessel pressure to be reported. Provide justification if the ((TRACG statistical pressure adder)) is not applied,
3. A calculation or calculations with TRACG demonstrating that when the steam dome pressure approaching to or exceeding the proposed reactor steam dome limit of 1340 psig the corresponding peak vessel pressure will still be below the ASME limit of 1375 psig with margin.
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