ML14133A639: Difference between revisions
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==SUBJECT:== | ==SUBJECT:== | ||
SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON MAY 12, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 26, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882) | |||
==SUMMARY== | |||
OF TELEPHONE CONFERENCE CALL HELD ON MAY 12, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 26, 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 May 12, 2014, to discuss and clarify the staff's draft request for additional information (DRAI), | 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 May 12, 2014, to discuss and clarify the staff's draft request for additional information (DRAI), | ||
Set 26, 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. | Set 26, 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. | ||
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==SUBJECT:== | ==SUBJECT:== | ||
SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON MAY 12, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 26, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882) | |||
==SUMMARY== | |||
OF TELEPHONE CONFERENCE CALL HELD ON MAY 12, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 26, PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882) | |||
DISTRIBUTION | DISTRIBUTION | ||
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Issue: During its review of the applicant's response to RAI 3.1.1.80-1 and related information, the staff noted that LRA Table 3.1.2-1 for the reactor coolant system does not include a specific AMR line item for GALL Report item IV.C2.RP-383 to manage cracking due to SCC of pressurizer relief tanks in accordance with LRA item 3.1.1-80. Therefore, the staff cannot determine how the applicant will manage cracking due to SCC of pressurizer relief tanks. | Issue: During its review of the applicant's response to RAI 3.1.1.80-1 and related information, the staff noted that LRA Table 3.1.2-1 for the reactor coolant system does not include a specific AMR line item for GALL Report item IV.C2.RP-383 to manage cracking due to SCC of pressurizer relief tanks in accordance with LRA item 3.1.1-80. Therefore, the staff cannot determine how the applicant will manage cracking due to SCC of pressurizer relief tanks. | ||
Request: | Request: | ||
Clarify why LRA Table 3.1.2-1 does not include a specific AMR line item which manages cracking due to SCC of stainless steel or steel with stainless steel pressurizer relief tanks using LRA item 3.1.1-80. Alternatively, revise the LRA to identify an AMR line item which is associated with LRA item 3.1.1-80 to manage cracking due to SCC for these components. | Clarify why LRA Table 3.1.2-1 does not include a specific AMR line item which manages cracking due to SCC of stainless steel or steel with stainless steel pressurizer relief tanks using LRA item 3.1.1-80. Alternatively, revise the LRA to identify an AMR line item which is associated with LRA item 3.1.1-80 to manage cracking due to SCC for these components. | ||
Discussion | Discussion | ||
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During its review of the applicant's response and related information, the staff noted that LRA Table 3.1.2-1 for the reactor coolant system does not include a specific aging management review (AMR) line item for GALL Report item IV.C2.RP-41, which manages cracking due to SCC of stainless steel pressurizer spray heads in accordance with LRA item 3.1.1-81. Therefore, the staff cannot determine how the applicant will manage cracking due to SCC of pressurizer spray heads. | During its review of the applicant's response and related information, the staff noted that LRA Table 3.1.2-1 for the reactor coolant system does not include a specific aging management review (AMR) line item for GALL Report item IV.C2.RP-41, which manages cracking due to SCC of stainless steel pressurizer spray heads in accordance with LRA item 3.1.1-81. Therefore, the staff cannot determine how the applicant will manage cracking due to SCC of pressurizer spray heads. | ||
Request: | Request: Clarify why LRA Table 3.1.2-1 does not include a specific AMR line item which manages cracking due to SCC of stainless steel pressurizer spray heads using LRA item 3.1.1-81. | ||
Clarify why LRA Table 3.1.2-1 does not include a specific AMR line item which manages cracking due to SCC of stainless steel pressurizer spray heads using LRA item 3.1.1-81. | |||
Alternatively, revise the LRA to identify an AMR line item which is associated with LRA item 3.1.1-81 to manage cracking due to SCC for these components. | Alternatively, revise the LRA to identify an AMR line item which is associated with LRA item 3.1.1-81 to manage cracking due to SCC for these components. | ||
Revision as of 15:56, 9 July 2018
| ML14133A639 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 05/23/2014 |
| 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: ML14133A639 (6) | |
Text
May 23, 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 MAY 12, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 26, 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 May 12, 2014, to discuss and clarify the staff's draft request for additional information (DRAI),
Set 26, 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
ML14133A639 *concurrence via email OFFICE LA:DLR* PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds LRobinson YDiazSanabria LRobinson DATE 5/16/14 5/19/14 5/23/14 5/23/14
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 12, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 26, 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 May 12, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC) Seung Min NRC Bart Fu NRC Chris Wilson Exelon Generating Company, LLC (Exelon)
Al Fulvio Exelon Albert Piha Exelon Phil O'Donnell Exelon Gary Becknell Exelon Ralph Wolen Exelon Don Brindle Exelon
ENCLOSURE 2 DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION May 12, 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 May 12, 2014, to discuss and clarify the following draft request for additional information (DRAI), Set 26, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA).
DRAI 3.1.1.80-1a
Applicability
Byron and Braidwood
Background
- By letter dated March 28, 2014, the applicant responded to RAI 3.1.1.80-1, which addressed LRA item 3.1.1-80. This LRA item states that the Water Chemistry program and One-Time Inspection program are used to manage cracking due to stress corrosion cracking (SCC) for stainless steel or steel with stainless steel pressurizer relief tanks (none-ASME-Section-XI tank shells, heads, flanges and nozzles) exposed to treated borated water > 60°C (>140°F). LRA item 3.1.1-80 corresponds to NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants" (SRP-LR), Table 3.1-1, item 80, which contains Generic Aging Lessons Learned (GALL) Report item IV.C2.RP-383.
Issue: During its review of the applicant's response to RAI 3.1.1.80-1 and related information, the staff noted that LRA Table 3.1.2-1 for the reactor coolant system does not include a specific AMR line item for GALL Report item IV.C2.RP-383 to manage cracking due to SCC of pressurizer relief tanks in accordance with LRA item 3.1.1-80. Therefore, the staff cannot determine how the applicant will manage cracking due to SCC of pressurizer relief tanks.
Request:
Clarify why LRA Table 3.1.2-1 does not include a specific AMR line item which manages cracking due to SCC of stainless steel or steel with stainless steel pressurizer relief tanks using LRA item 3.1.1-80. Alternatively, revise the LRA to identify an AMR line item which is associated with LRA item 3.1.1-80 to manage cracking due to SCC for these components.
Discussion
- The applicant requested clarity on the staff's concern. The applicant informed the staff that the explanation for not including the pressurizer relief tanks was listed in the updated final safety analysis report (UFSAR). After further review of the UFSAR, the staff agreed that this information was docketed and made the determination to withdraw this question. This question will not be sent as part of the formal request. DRAI 3.1.1.81-1a Applicability
- Byron and Braidwood
Background
By letter dated March 28, 2014, the applicant responded to RAI 3.1.1.81-1, which addressed LRA item 3.1.1-81. This LRA item states that the Water Chemistry program and One-Time Inspection program are used to manage cracking due to SCC for stainless steel pressurizer spray heads exposed to reactor coolant. LRA item 3.1.1-81 corresponds to SRP-LR Table 3.1-1, item 81, which contains GALL Report item IV.C2.RP-41.
Issue:
During its review of the applicant's response and related information, the staff noted that LRA Table 3.1.2-1 for the reactor coolant system does not include a specific aging management review (AMR) line item for GALL Report item IV.C2.RP-41, which manages cracking due to SCC of stainless steel pressurizer spray heads in accordance with LRA item 3.1.1-81. Therefore, the staff cannot determine how the applicant will manage cracking due to SCC of pressurizer spray heads.
Request: Clarify why LRA Table 3.1.2-1 does not include a specific AMR line item which manages cracking due to SCC of stainless steel pressurizer spray heads using LRA item 3.1.1-81.
Alternatively, revise the LRA to identify an AMR line item which is associated with LRA item 3.1.1-81 to manage cracking due to SCC for these components.
Discussion
- The applicant requested clarity on the staff's concern. No edits were proposed. This question will be sent as part of the formal request titled: "RAI 3.1.1.81-1a."