ML14164A446: Difference between revisions

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| document type = Meeting Summary
| document type = Meeting Summary
| page count = 6
| page count = 6
| project = TAC:MF1879, TAC:MF1880, TAC:MF1881, TAC:MF1882
}}
=Text=
{{#Wiki_filter: UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001  June 25, 2014 
LICENSEE: Exelon Generation Company, LLC FACILITY: Byron Station, Units 1 and 2  Braidwood Station, Units 1 and 2 SUBJECT: SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON JUNE 11, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 34, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)  The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 11, 2014, to discuss and clarify the staff's draft request for additional information (DRAI),
Set 34, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's DRAIs.
Enclosure 1 provides a listing of the participants, and Enclosure 2 contains a listing of the DRAIs discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary. 
      /RA/  Lindsay Robinson, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-454, 50-455, 50-456, and 50-457  Enclosures:
1. List of Participants 2. List of Draft Request for Additional Information cc w/encls:  Listserv 
June 25, 2014  LICENSEE: Exelon Generation Company, LLC 
FACILITY: Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2 SUBJECT: SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON JUNE 11, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 34, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 11, 2014, to discuss and clarify the staff's draft request for additional information (DRAI), Set 34, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's DRAIs.
Enclosure 1 provides a listing of the participants, and Enclosure 2 contains a listing of the DRAIs discussed with the applicant, including a brief description on the status of the items. The applicant had an opportunity to comment on this summary.      /RA/ Lindsay Robinson, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-454, 50-455, 50-456, and 50-457
Enclosures:  1. List of Participants 2. List of Draft Request for Additional Information
cc w/encls:  Listserv DISTRIBUTION: See next page ADAMS Accession No.:  ML14164A446    *concurred via email  OFFICE  LA:DLR PM:RPB1:DLR  BC:RPB1:DLR  PM:RPB1:DLR NAME YEdmonds LRobinson YDiazSanabria LRobinson DATE 6/24/14 6/25/14 6/25/14 6/25/14 OFFICIAL RECORD COPY SUBJECT: SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON JUNE 11, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 34, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)
DISTRIBUTION  EMAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsOgcMailCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource ---------------------------------- LRobinson DMcIntyre, OPA EDuncan, RIII JBenjamin, RIII AGarmoe, RIII JMcGhee, RIII JRobbins, RIII VMitlyng, RIII PChandrathil, RIII ENCLOSURE 1 TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION  LIST OF PARTICIPANTS June 11, 2014  PARTICIPANTS                                                AFFILIATIONS  Lindsay Robinson                                              U.S. Nuclear Regulatory Commission (NRC) William Holston NRC Naeem Iqbal NRC John Hufnagel Exelon Generating Company, LLC (Exelon) Don Warfel Exelon Casey Muggleston Exelon Jim Annett Exelon ENCLOSURE 2  DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION  June 11, 2014 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 11, 2014, to discuss and clarify the following draft request for additional information (DRAI), Set 34, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA).
DRAI 2.3.3.12-4  Applicability:  Byron Station (Byron) and Braidwood Station (Braidwood), Units 1 and 2
Background:  For Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, the staff reviewed the combined license renewal application (LRA), drawings, and several other applicable documents.
LRA Section 2.3.3.12 discusses requirements for the fire water supply system but does not mention suction screens for the fire pump suction water supply. The intake traveling screens Suction screens were not included in the license renewal boundaries; however, they appear to have fire protection intended functions required for compliance with Title 10 of the Code of Federal Regulations (CFR) 50.48, "Fire protection," as stated in 10 CFR 54.4. Intake traveling screens Suction screens are located upstream of the fire pump suctions to remove any major debris from the fresh or raw water. Intake traveling screens Suction screens are necessary to remove debris from and prevent clogging of the fire protection water supply system and have a passive intended function of filter. These screens, typically constructed of carbon steel, are typically considered to be passive, long-lived components and are located in a fresh or raw water environment or water/air environment. Carbon steel in a fresh or raw water environment or a water or air environment is subject to loss of material, pitting, crevice formation, and microbiologically influenced corrosion and fouling. Issue:
Tables 2.3.3-12 and 3.3.2-12 of the LRA do not include the intake traveling screens. following fire protection component: fire water source suction screens Request:  The staff requests that the applicant verify whether the intake traveling screens suction screens are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an aging management review (AMR) in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.
Discussion:  The applicant requested clarification on the staff's concern regarding the suction screens. It was identified during the discussion that the staff's concern related specifically to the 
- 2 -  intake traveling screens. The applicant understood the staff's concern and requested that the staff edit the request to specify intake traveling screens vice suction screens. Deleted portions of the original request are annotated with strikethrough and additions are annotated with underline. This question will be sent as a formal request titled:  "RAI 2.3.3.12-4."   
}}
}}

Revision as of 05:17, 22 March 2018

Summary of Telephone Conference Call Held on June 11, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 34, Pertaining to the Byron Station and B
ML14164A446
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 06/25/2014
From: Robinson L R
License Renewal Projects Branch 1
To:
Exelon Generation Co
Robinson L R, 415-4115
References
TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882
Download: ML14164A446 (6)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 25, 2014

LICENSEE: Exelon Generation Company, LLC FACILITY: Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2 SUBJECT: SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON JUNE 11, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 34, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882) The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 11, 2014, to discuss and clarify the staff's draft request for additional information (DRAI),

Set 34, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's DRAIs.

Enclosure 1 provides a listing of the participants, and Enclosure 2 contains a listing of the DRAIs discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA/ Lindsay Robinson, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-454, 50-455, 50-456, and 50-457 Enclosures:

1. List of Participants 2. List of Draft Request for Additional Information cc w/encls: Listserv

June 25, 2014 LICENSEE: Exelon Generation Company, LLC

FACILITY: Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2 SUBJECT: SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON JUNE 11, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 34, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 11, 2014, to discuss and clarify the staff's draft request for additional information (DRAI), Set 34, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's DRAIs.

Enclosure 1 provides a listing of the participants, and Enclosure 2 contains a listing of the DRAIs discussed with the applicant, including a brief description on the status of the items. The applicant had an opportunity to comment on this summary. /RA/ Lindsay Robinson, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-454, 50-455, 50-456, and 50-457

Enclosures: 1. List of Participants 2. List of Draft Request for Additional Information

cc w/encls: Listserv DISTRIBUTION: See next page ADAMS Accession No.: ML14164A446 *concurred via email OFFICE LA:DLR PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds LRobinson YDiazSanabria LRobinson DATE 6/24/14 6/25/14 6/25/14 6/25/14 OFFICIAL RECORD COPY SUBJECT: SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON JUNE 11, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 34, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)

DISTRIBUTION EMAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsOgcMailCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource ---------------------------------- LRobinson DMcIntyre, OPA EDuncan, RIII JBenjamin, RIII AGarmoe, RIII JMcGhee, RIII JRobbins, RIII VMitlyng, RIII PChandrathil, RIII ENCLOSURE 1 TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS June 11, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC) William Holston NRC Naeem Iqbal NRC John Hufnagel Exelon Generating Company, LLC (Exelon) Don Warfel Exelon Casey Muggleston Exelon Jim Annett Exelon ENCLOSURE 2 DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION June 11, 2014 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on June 11, 2014, to discuss and clarify the following draft request for additional information (DRAI), Set 34, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA).

DRAI 2.3.3.12-4 Applicability: Byron Station (Byron) and Braidwood Station (Braidwood), Units 1 and 2

Background: For Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, the staff reviewed the combined license renewal application (LRA), drawings, and several other applicable documents.

LRA Section 2.3.3.12 discusses requirements for the fire water supply system but does not mention suction screens for the fire pump suction water supply. The intake traveling screens Suction screens were not included in the license renewal boundaries; however, they appear to have fire protection intended functions required for compliance with Title 10 of the Code of Federal Regulations (CFR) 50.48, "Fire protection," as stated in 10 CFR 54.4. Intake traveling screens Suction screens are located upstream of the fire pump suctions to remove any major debris from the fresh or raw water. Intake traveling screens Suction screens are necessary to remove debris from and prevent clogging of the fire protection water supply system and have a passive intended function of filter. These screens, typically constructed of carbon steel, are typically considered to be passive, long-lived components and are located in a fresh or raw water environment or water/air environment. Carbon steel in a fresh or raw water environment or a water or air environment is subject to loss of material, pitting, crevice formation, and microbiologically influenced corrosion and fouling. Issue:

Tables 2.3.3-12 and 3.3.2-12 of the LRA do not include the intake traveling screens. following fire protection component: fire water source suction screens Request: The staff requests that the applicant verify whether the intake traveling screens suction screens are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an aging management review (AMR) in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

Discussion: The applicant requested clarification on the staff's concern regarding the suction screens. It was identified during the discussion that the staff's concern related specifically to the

- 2 - intake traveling screens. The applicant understood the staff's concern and requested that the staff edit the request to specify intake traveling screens vice suction screens. Deleted portions of the original request are annotated with strikethrough and additions are annotated with underline. This question will be sent as a formal request titled: "RAI 2.3.3.12-4."