ML072430292: Difference between revisions

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| author name = Haney C
| author name = Haney C
| author affiliation = NRC/NRR/ADRO/DORL
| author affiliation = NRC/NRR/ADRO/DORL
| addressee name = Crane C M
| addressee name = Crane C
| addressee affiliation = Exelon Generation Co, LLC
| addressee affiliation = Exelon Generation Co, LLC
| docket = 05000457
| docket = 05000457

Revision as of 21:12, 12 July 2019

Evaluation of Finite Element Analysis in Support of Alloy 82/182 Pressurizer Butt Weld Inspections in 2008 as Provided by Completion of Analysis Required by CAL NRR-07-008
ML072430292
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 09/07/2007
From: Catherine Haney
Plant Licensing Branch III-2
To: Crane C
Exelon Generation Co
kuntz, Robert , NRR/DORL, 415-3733
References
TAC MD4135, NRR-07-008
Download: ML072430292 (6)


Text

September 7, 2007Mr. Christopher M. CranePresident and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BRAIDWOOD STATION, UNIT 2 - EVALUATION OF FINITE ELEMENTANALYSIS IN SUPPORT OF ALLOY 82/182 PRESSURIZER BUTT WELD INSPECTIONS IN 2008 AS PROVIDED BY CONFIRMATORY ACTION LETTER NRR-07-008 (TAC NO. MD4135)

Dear Mr. Crane:

On March 22, 2007, the U.S. Nuclear Regulatory Commission (NRC) issued ConfirmatoryAction Letter (CAL) No. NRR-07-008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML070740294) regarding dissimilar metal welds in the pressurizer surge, spray, and safety/relief nozzle-to-safe end welds at Braidwood Station, Unit 2. The CAL and the supporting commitment letter (ADAMS Accession No. ML070520499) indicate that inspection and mitigation actions may be conducted during your spring 2008 refueling outage, contingent on the industry providing an analysis that demonstrates an acceptable level of safety to the NRC for the operation of these welds until the spring of 2008.

This letter acknowledges receipt of your letter dated August 3, 2007 (ADAMS Accession No.

ML072150585), informing the NRC that the analysis referred to by this CAL and the supportingcommitment letter has been completed, and that the analysis is applicable to your plant.The NRC received MRP-216, Rev. 1, "Materials Reliability Program: Advanced FEA [FiniteElement Analysis] Evaluation of Growth of Postulated Circumferential PWSCC [Primary Water Stress-Corrosion Cracking] Flaws in Pressurizer Nozzle Dissimilar Metal Welds" on August 13,2007 (ADAMS Accession No. ML072410235). Based on our review of this report, the NRC concludes that the analysis provides adequate justification to permit inspections during yourspring 2008 refueling outage, and that the analysis is applicable to Braidwood Station, Unit 2.

The results of the staff's review are contained in a safety assessment dated August 31, 2007, 2007 (ADAMS Accession No. ML072400199) and the associated contractor report (ADAMS Accession No. ML072470394). Based on the above, the NRC concludes that a plant shutdown by December 31, 2007, is nolonger required. Therefore, the pressurizer surge, spray, and safety/relief nozzle-to-safe end Alloy 82/182 butt weld inspections for Braidwood Station, Unit 2 must be performed prior to exiting your scheduled spring 2008 refueling outage. All other requirements of the CAL and the supporting commitment letter regarding enhanced inspection and leakage monitoringrequirements for the reactor coolant system and associated reports remain valid.

C. Crane-2-The CAL will remain open until all CAL commitments pertaining to Braidwood Station, Units 1and 2 are complete. Current NRC guidance regarding CALs is contained in the NRC Enforcement Policy and theNRC Enforcement Manual, which are available at the NRC web site at http://www.nrc.gov/about-nrc/regulatory/enforcement.html (click on Enforcement Policy orEnforcement Guidance) or by contacting the Government Printing Office (GPO) toll-free at 1-888-293-6498. The GPO is open from 7:00 a.m. to 9:00 p.m. EST, Monday through Friday (except Federal holidays).In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will bemade available electronically for public inspection in the NRC Public Document Room or from the NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm.html.Sincerely,/RA/Catherine Haney, Director Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. STN 50-457 cc: See next page

ML072430292*by e-mailNRR-106 OFFICEDCI/CPNBDCI/CPNBLPL3-2/PMLPL3-2/LALPL3-2/BCNAMETLupoldTChanRKuntzEWhittRGibbs DATE9/6/07 9/6/079/5/07 9/5/07 9/6/07 OFFICEDCI/DDRP/D, RGN3DORL/D NAMEMEvansCPederson*CHaney DATE 9/7/079/4/079/7/07 Braidwood Station, Units 1 and 2 cc:Document Control Desk - Licensingvia e-mailMr. Dwain W. Alexander, Project ManagerWestinghouse Electric Corporation via e-mailMs. Bridget Little RoremAppleseed Coordinator via e-mailHoward A. LearnerEnvironmental Law and Policy Center of the Midwest 35 East Wacker Dr., Suite 1300 Chicago, IL 60601-2110Braidwood Senior Resident InspectorU.S. Nuclear Regulatory Commission via e-mailMs. Lorraine CreekRR 1, Box 182 Manteno, IL 60950Illinois Emergency Management AgencyDivision of Disaster Assistance &

Preparedness via e-mailCounty Executive via e-mailAttorney General500 S. Second Street Springfield, IL 62701Plant Manager - Braidwood Station via e-mail Site Vice President - Braidwoodvia e-mailSenior Vice President - Operations Supportvia e-mailChairman, Ogle County BoardPost Office Box 357 Oregon, IL 61061Manager Regulatory Assurance - Braidwoodvia e-mailDirector - Licensing and Regulatory Affairsvia e-mailAssociate General Counselvia e-mailSenior Vice President - Midwest Operationsvia e-mailVice President - Regulatory Affairsvia e-mailManager Licensing - Braidwood, Byron and LaSalle via e-mail