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| issue date = 08/07/2014
| issue date = 08/07/2014
| title = Draft RAIs for Beaver Valley Unit 1 Alternate Pressurized Thermal Shock 50.61a Rule License Amendment Request
| title = Draft RAIs for Beaver Valley Unit 1 Alternate Pressurized Thermal Shock 50.61a Rule License Amendment Request
| author name = Whited J A
| author name = Whited J
| author affiliation = NRC/NRR/DORL/LPLI-2
| author affiliation = NRC/NRR/DORL/LPLI-2
| addressee name =  
| addressee name =  
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| docket = 05000334
| docket = 05000334
| license number =  
| license number =  
| contact person = Whited J A
| contact person = Whited J
| document type = Request for Additional Information (RAI)
| document type = Request for Additional Information (RAI)
| page count = 2
| page count = 2
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=Text=
=Text=
{{#Wiki_filter:DRAFT DRAFT  REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO IMPLEMENT 10 CFR 50.61a "ALTERNATE FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS" BEAVER VALLEY POWER STATION UNIT 1 FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-334
{{#Wiki_filter:DRAFT REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO IMPLEMENT 10 CFR 50.61a ALTERNATE FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS BEAVER VALLEY POWER STATION UNIT 1 FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-334 By letter dated July 30, 2013,1 FirstEnergy Nuclear Operating Company (FENOC, the licensee),
 
submitted a license amendment request for Beaver Valley Power Station, Unit No. 1 (BVPS-1).
By letter dated July 30, 2013, 1 FirstEnergy Nuclear Operating Company (FENOC, the licensee), submitted a license amendment r equest for Beaver Valley Power Station, Unit No. 1 (BVPS-1). The proposed amendment would authorize the implementation of Title 10 of the Code of Federal Regulations (10 CFR) 50.61a, "Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS) Events," in lieu of 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."  To complete its review, the Nuclear Regulatory Commission (NRC) staff requests a response to the Request for Additional Information (RAI) questions below.  
The proposed amendment would authorize the implementation of Title 10 of the Code of Federal Regulations (10 CFR) 50.61a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS) Events, in lieu of 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.
 
To complete its review, the Nuclear Regulatory Commission (NRC) staff requests a response to the Request for Additional Information (RAI) questions below.
Under Section 3.4, Neutron Fluence Values, the license amendment request indicates that neutron fluence values at 50 Effective Full Power Years (EFPY) were interpolated from the 48 and 54 EFPY data available in WCAP-15571-NP, Supplement 1, Revision 2, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program ."  Regarding WCAP-15571-NP, Supplement 1, Revision 2, the fluence methodology is not described in much detail.  
Under Section 3.4, Neutron Fluence Values, the license amendment request indicates that neutron fluence values at 50 Effective Full Power Years (EFPY) were interpolated from the 48 and 54 EFPY data available in WCAP-15571-NP, Supplement 1, Revision 2, Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program .
 
Regarding WCAP-15571-NP, Supplement 1, Revision 2, the fluence methodology is not described in much detail.
RAI 1 Please provide details of the fluence methodology to enable the U. S. Nuclear Regulatory Commission (NRC) staff to verify that the calculations are in accordance with Regulatory Guide 1.190 (RG 1.190), 2 "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence."
RAI 1 Please provide details of the fluence methodology to enable the U. S. Nuclear Regulatory Commission (NRC) staff to verify that the calculations are in accordance with Regulatory Guide 1.190 (RG 1.190),2 Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence.
When performing the statistical tests required by the Alternate PTS Rule, all heats of steel from the reactor pressure vessel (RPV) of interest for which 10 CFR 50 Appendix H surveillance data exist should be evaluated. The statistical tests should be performed separately for each heat.
When performing the statistical tests required by the Alternate PTS Rule, all heats of steel from the reactor pressure vessel (RPV) of interest for which 10 CFR 50 Appendix H surveillance data exist should be evaluated. The statistical tests should be performed separately for each heat.
For each heat for which data are available, the T 30 values used in the statistical tests should include data from both of the following sources:  
For each heat for which data are available, the T30 values used in the statistical tests should include data from both of the following sources:
 
1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML13212A027.
1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML13212A027.
2 ADAMS Accession No. ML010890301.
2 ADAMS Accession No. ML010890301.
DRAFT
DRAFT
* Data obtained for the heat of material in question as part of a 10 CFR 50 Appendix H surveillance program conducted for the plant in question, and
* Data obtained for the heat of material in question as part of a 10 CFR 50 Appendix H surveillance program conducted for the plant in question, and
* Data obtained for the heat of material in question as part of a 10 CFR 50 Appendix H surveillance program conducted for any other PWR that is operating, or has operated, under a license issued by the NRC. Data from this source is often referred to as having come from a "Sister Plant." 
* Data obtained for the heat of material in question as part of a 10 CFR 50 Appendix H surveillance program conducted for any other PWR that is operating, or has operated, under a license issued by the NRC. Data from this source is often referred to as having come from a Sister Plant.
 
RAI 2 Identify the plants and heats of material which will provide sister plant data.
RAI 2 Identify the plants and heats of material which will provide "sister plant" data.}}
DRAFT}}

Latest revision as of 02:43, 4 November 2019

Draft RAIs for Beaver Valley Unit 1 Alternate Pressurized Thermal Shock 50.61a Rule License Amendment Request
ML14219A177
Person / Time
Site: Beaver Valley
Issue date: 08/07/2014
From: Jeffrey Whited
Plant Licensing Branch 1
To:
Whited J
References
Download: ML14219A177 (2)
v • d • e


Text

DRAFT REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO IMPLEMENT 10 CFR 50.61a ALTERNATE FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS BEAVER VALLEY POWER STATION UNIT 1 FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-334 By letter dated July 30, 2013,1 FirstEnergy Nuclear Operating Company (FENOC, the licensee),

submitted a license amendment request for Beaver Valley Power Station, Unit No. 1 (BVPS-1).

The proposed amendment would authorize the implementation of Title 10 of the Code of Federal Regulations (10 CFR) 50.61a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS) Events, in lieu of 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.

To complete its review, the Nuclear Regulatory Commission (NRC) staff requests a response to the Request for Additional Information (RAI) questions below.

Under Section 3.4, Neutron Fluence Values, the license amendment request indicates that neutron fluence values at 50 Effective Full Power Years (EFPY) were interpolated from the 48 and 54 EFPY data available in WCAP-15571-NP, Supplement 1, Revision 2, Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program .

Regarding WCAP-15571-NP, Supplement 1, Revision 2, the fluence methodology is not described in much detail.

RAI 1 Please provide details of the fluence methodology to enable the U. S. Nuclear Regulatory Commission (NRC) staff to verify that the calculations are in accordance with Regulatory Guide 1.190 (RG 1.190),2 Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence.

When performing the statistical tests required by the Alternate PTS Rule, all heats of steel from the reactor pressure vessel (RPV) of interest for which 10 CFR 50 Appendix H surveillance data exist should be evaluated. The statistical tests should be performed separately for each heat.

For each heat for which data are available, the T30 values used in the statistical tests should include data from both of the following sources:

1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML13212A027.

2 ADAMS Accession No. ML010890301.

DRAFT

  • Data obtained for the heat of material in question as part of a 10 CFR 50 Appendix H surveillance program conducted for the plant in question, and
  • Data obtained for the heat of material in question as part of a 10 CFR 50 Appendix H surveillance program conducted for any other PWR that is operating, or has operated, under a license issued by the NRC. Data from this source is often referred to as having come from a Sister Plant.

RAI 2 Identify the plants and heats of material which will provide sister plant data.

DRAFT

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