ML14300A218
| ML14300A218 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 11/06/2014 |
| From: | Robinson L License Renewal Projects Branch 1 |
| To: | Exelon Generation Co |
| Robinson L, 301-415-4115 | |
| References | |
| TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882 | |
| Download: ML14300A218 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 6, 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 OCTOBER 7, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 41, 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 October 7, 2014, to discuss and clarify the staffs draft request for additional information (DRAI),
Set 41, 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 staffs DRAIs.
provides a listing of the participants, and Enclosure 2 contains the DRAI 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
- concurred via email OFFICE LA:RPB1:DLR PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME
- YEdmonds LRobinson YDiazSanabria LRobinson DATE 11/5/14 11/5/14 11/6/14 11/6/14
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 7, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION, SET 41, 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 October 7, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC)
Angela Buford NRC John Hufnagel Exelon Generating Company, LLC (Exelon)
Al Fulvio Exelon Don Warfel Exelon Jim Annett Exelon Albert Piha Exelon Don Brindle Exelon Ralph Wolen Exelon Gary Becknell Exelon
ENCLOSURE 2 DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION October 7, 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 October 7, 2014, to discuss and clarify the following draft request for additional information (DRAI), Set 41, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA).
DRAI B.2.1.31-4 Applicability:
Byron Station and Braidwood Station (BBS), Units 1 and 2
Background:
In a letter dated August 29, 2014, the applicant submitted a revision to the BBS LRA for the American Society of Mechanical Engineers (ASME)Section XI, Subsection IWF Program. The applicant stated that the program is revised to include the control rod drive mechanism (CRDM) seismic support assembly in the scope of license renewal and that these components will be managed by performing VT-3 examinations in accordance with the ASME Section XI, Subsection IWF program requirements for Class 1 component supports during every ten (10) year ISI inspection interval. The applicant also revised LRA table 3.5.2-3 to include the CRDM support components in the aging management review (AMR) tables. The revised LRA states that these supports include carbon and low alloy steel bolting exposed to an air with borated water leakage environment.
Issue:
The detection of aging effects program element of the Generic Aging Lessons Learned (GALL)
Report ASME Section XI, Subsection IWF program recommends that high strength steel bolting (actual yield strength greater than 150 ksi) in sizes greater than 1 be age-managed using volumetric examinations in addition to the VT-3 visual inspections for the aging effect of cracking due to stress corrosion cracking (SCC). The GALL Report also states that the recommendation to use ultrasonic testing may be waived with adequate plant-specific justification. The applicants ASME Section XI, Subsection IWF AMP contains an exception from the provision of the GALL Report for certain high strength structural bolts and provides a justification to waive volumetric examination for each type of high strength bolts within the scope of the ASME Section XI, Subsection IWF program. The applicant applied different justifications for its exception to the GALL Report for each of the different types of high strength bolts identified. The staff noted that the applicants LRA revision does not state what types of bolts are used for the CRDM seismic supports. If the bolts used are high strength bolts, it is not clear whether the applicant will take an exception to the GALL Report recommendations as was done for the previously identified high strength bolts or whether the bolts will be managed for cracking due to SCC using the GALL Report-recommended volumetric examinations. The staff needs additional information on (1) whether high strength bolts (actual yield strength greater than ENCLOSURE 2 150 ksi) in sizes greater than 1 are used in the CRDM seismic supports, (2) the type and grade of the material if high strength bolts are used, and (3) how visual inspections will be adequate to detect cracking due to SCC if high strength bolts are used.
Request:
State whether high strength bolts (actual measured yield strength greater than or equal to 150 ksi) in sizes greater than 1 are used in the CRDM seismic supports. If so, provide additional information on the type and grade of the material. If these bolts are used in CRDM seismic supports, explain how visual inspections will be adequate to detect cracking due to SCC.
Discussion: The applicant requested clarification on the staffs request. No edits were made or suggested. This DRAI was formally sent to the applicant on October 9, 2014, titled: RAI B.2.1.31-4.