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=Text=
=Text=
{{#Wiki_filter:August 3, 2009  
{{#Wiki_filter:August 3, 2009 Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA1B)
 
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, FL 34428-6708
Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, FL 34428-6708  


==SUBJECT:==
==SUBJECT:==
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)  
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)


==Dear Mr. Franke:==
==Dear Mr. Franke:==


By letter dated December 16, 2008, Florida Power Corporation submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Crystal River Unit 3 Nuclear Generating Plant, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.  
By letter dated December 16, 2008, Florida Power Corporation submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Crystal River Unit 3 Nuclear Generating Plant, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
 
Items in the enclosure were discussed with Mr. Michael Heath, and a mutually agreeable date for the response is within 45 days from the date of this letter. If you have any questions, please contact me at 301-415-3733 or by e-mail robert.kuntz@nrc.gov.
Items in the enclosure were discussed with Mr. Michael Heath, and a mutually agreeable date for the response is within 45 days from the date of this letter. If you have any questions, please contact me at 301-415-3733 or by e-mail robert.kuntz@nrc.gov. Sincerely,
Sincerely,
/RA/
                                              /RA/
 
Robert F. Kuntz, Senior Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-302
Robert F. Kuntz, Senior Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation  
 
Docket No. 50-302  


==Enclosure:==
==Enclosure:==


As stated  
As stated cc w/encl: See next page


cc w/encl:  See next page 
(s): ML091740070 OFFICE      PM:RPB2:DLR      LA:DLR        BC:CVIB:DCI        BC:RPB2:DLR      PM:RPB2:DLR MMitchell          DWrona          RKuntz NAME        RKuntz            IKing (Signature)
DATE        07/23/09          08/03/09      07/30/09            07/31/09        08/03/09


(s):  ML091740070 OFFICE PM:RPB2:DLR LA:DLR BC:CVIB:DCI BC:RPB2:DLR PM:RPB2:DLR NAME RKuntz IKing MMitchell DWrona RKuntz (Signature) DATE 07/23/09 08/03/09 07/30/09 07/31/09 08/03/09 Letter to J. Franke from R. Kuntz, dated August 03, 2009
Letter to J. Franke from R. Kuntz, dated August 03, 2009 DISTRIBUTION:
 
DISTRIBUTION:


==SUBJECT:==
==SUBJECT:==
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)
HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRer1 Resource RidsNrrDlrRer2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter  
HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRer1 Resource RidsNrrDlrRer2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter
________
RKuntz DBrittner AJones, OGC LLake, RII MSykes, RII TMorrissey, RII RReyes, RI


_ _ _ _ _ _ _ _
Crystal River Generating Plant, Unit 3 cc:
RKuntz DBrittner AJones, OGC LLake, RII MSykes, RII TMorrissey, RII RReyes, RI
Mr. R. Alexander Glenn                Senior Resident Inspector Associate General Counsel (MAC-BT15A) Crystal River Unit 3 Florida Power Corporation            U.S. Nuclear Regulatory Commission P.O. Box 14042                        6745 N. Tallahassee Road St. Petersburg, FL 33733-4042        Crystal River, FL 34428 Mr. James W. Holt                    Ms. Phyllis Dixon Plant General Manager                Manager, Nuclear Assessment Crystal River Nuclear Plant (NA2C)    Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street            15760 W. Power Line Street Crystal River, FL 34428-6708          Crystal River, FL 34428-6708 Mr. William A. Passetti, Chief        Mr. David T. Conley Department of Health                  Associate General Counsel II - Legal Dept.
Bureau of Radiation Control          Progress Energy Service Company, LLC 2020 Capital Circle, SE, Bin #C21    P.O. Box 1551 Tallahassee, FL 32399-1741            Raleigh, NC 27602-1551 Attorney General                      Mr. Daniel L. Roderick Department of Legal Affairs          Vice President, Nuclear Projects &
The Capitol                            Construction Tallahassee, FL 32304                Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Mr. Ruben D. Almaluer, Director      Crystal River, FL 34428-6708 Division of Emergency Preparedness Department of Community Affairs      Mr. Mark Rigsby 2740 Centerview Drive                Manager, Support Services - Nuclear Tallahassee, FL 32399-2100            Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Chairman                              Crystal River, FL 34428-6708 Board of County Commissioners Citrus County                        Mr. Robert J. Duncan II 110 North Apopka Avenue              Vice President, Nuclear Operations Inverness, FL 34450-4245              Progress Energy P.O. Box 1551 Mr. Stephen J. Cahill                Raleigh, NC 27602-1551 Engineering Manager Crystal River Nuclear Plant (NA2C)    Mr. Brian C. McCabe 15760 W. Power Line Street            Manager, Nuclear Regulatory Affairs Crystal River, FL 34428-6708          Progress Energy P.O. Box 1551 Mr. Daniel R. Westcott                Raleigh, NC 27602-1551 Supervisor, Licensing & Regulatory Programs Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428-6708


Crystal River Generating Plant, Unit 3  
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION


cc:
==Background:==
Mr. R. Alexander Glenn Associate General Counsel (MAC-BT15A)
Florida Power Corporation P.O. Box 14042 St. Petersburg, FL  33733-4042


Mr. James W. Holt Plant General Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL  34428-6708
By letter dated December 18, 2008, Florida Power Corporation, doing business as Progress Energy Florida, Inc., a subsidiary of Progress Energy, Inc., submitted a license renewal application (LRA) to extend the operating license for Crystal River Unit 3 Nuclear Generating Plant (CR-3), for an additional 20 year period.
Requests for Information RAI 4.2.6-1


Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, FL  32399-1741 
===Background===
 
The CR-3 LRA states that:
Attorney General Department of Legal Affairs The Capitol Tallahassee, FL  32304
The ART at the inside surface of CR-3 Lower Nozzle Belt Forging AZJ 94 is 3.0 oF higher than the ART evaluated for the previously limiting forging [from BAW-2247A, Fracture Mechanics Analysis of Postulated Underclad Cracks in B&W Designed Reactor Vessels for the Period Of Extended Operation].
 
Request Demonstrate that the reanalysis of the CR-3 Lower Nozzle Belt Forging AXJ 94 is consistent with the methodology used in BAW-2247A. Provide information, including input data, intermediate calculations, etc., as necessary, to support that the analyses performed for CR-3 are consistent with those in BAW-2274A.
Mr. Ruben D. Almaluer, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, FL  32399-2100
RAI 4.2.2-1
 
Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Inverness, FL  34450-4245   
 
Mr. Stephen J. Cahill Engineering Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL  34428-6708
 
Mr. Daniel R. Westcott Supervisor, Licensing & Regulatory Programs Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL  34428-6708
 
Senior Resident Inspector Crystal River Unit 3 U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, FL  34428
 
Ms. Phyllis Dixon Manager, Nuclear Assessment Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL  34428-6708
 
Mr. David T. Conley Associate General Counsel II - Legal Dept.
Progress Energy Service Company, LLC P.O. Box 1551 Raleigh, NC  27602-1551
 
Mr. Daniel L. Roderick Vice President, Nuclear Projects &
Construction Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Crystal River, FL  34428-6708
 
Mr. Mark Rigsby Manager, Support Services - Nuclear Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Crystal River, FL  34428-6708
 
Mr. Robert J. Duncan II Vice President, Nuclear Operations Progress Energy P.O. Box 1551 Raleigh, NC  27602-1551
 
Mr. Brian C. McCabe Manager, Nuclear Regulatory Affairs Progress Energy P.O. Box 1551 Raleigh, NC  27602-1551 ENCLOSURE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION  REQUEST FOR ADDITIONAL INFORMATION


===Background===
===Background===
:
Section 4.2.2, Upper Shelf Energy Analysis, states that, the methodology used to evaluate CR-3 beltline welds at 60 years is consistent with the equivalent margins analysis (EMA) methods reported in BAW-2192PA, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Level A & B Service Loads; BAW-2178PA, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Level C & D Service Loads; and BAW-2275A, Low Upper-Shelf Toughness Fracture Mechanics Analysis of B&W Designed Reactor Vessels for 48 EFPY.
By letter dated December 18, 2008, Florida Power Corporation, doing business as Progress Energy Florida, Inc., a subsidiary of Progress Energy, Inc., submitted a license renewal application (LRA) to extend the operating license for Crystal River Unit 3 Nuclear Generating Plant (CR-3), for an additional 20 year period.
Topical Report BAW-2275A addresses the issue of low upper-shelf toughness for Linde 80 welds in Babcock and Wilcox (B&W) reactor pressure vessels (RPVs), for an extended license period of 48 effective full-power years (EFPY). The BAW-2275A evaluation involved 5 plants of the 16 plants covered by BAW-2178PA and BAW-2192PA. CR-3 did not participate in the evaluation contained in BAW-2275A. The staffs safety evaluation of BAW-2275A concluded ENCLOSURE
 
Requests for Information
 
RAI 4.2.6-1
 
===
Background===
 
The CR-3 LRA states that:
 
The ART at the inside surface of CR-3 Lower Nozzle Belt Forging AZJ 94 is 3.0 oF higher than the ART evaluated for the previously limiting forging [from BAW-2247A, Fracture Mechanics Analysis of Postulated Underclad Cracks in B&W Designed Reactor Vessels for the Period Of Extended Operation].
 
Request Demonstrate that the reanalysis of the CR-3 Lower Nozzle Belt Forging AXJ 94 is consistent with the methodology used in BAW-2247A. Provide information, including input data, intermediate calculations, etc., as necessary, to support that the analyses performed for CR-3 are consistent with those in BAW-2274A.
 
RAI 4.2.2-1
 
===
Background===
 
Section 4.2.2, Upper Shelf Energy Analysis, states that, "the methodology used to evaluate CR-3 beltline welds at 60 years is consistent with the equivalent margins analysis (EMA) methods reported in BAW-2192PA, "Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Level A & B Service Loads;" BAW-2178PA, "Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Level C & D Service Loads;" and BAW-2275A, "Low Upper-Shelf Toughness Fracture Mechanics Analysis of B&W Designed Reactor Vessels for 48 EFPY."


Topical Report BAW-2275A addresses the issue of low upper-shelf toughness for Linde 80 welds in Babcock and Wilcox (B&W) reactor pressure vessels (RPVs), for an extended license period of 48 effective full-power years (EFPY). The BAW-2275A evaluation involved 5 plants of the 16 plants covered by BAW-2178PA and BAW-2192PA. CR-3 did not participate in the evaluation contained in BAW-2275A. The staff's safety evaluation of BAW-2275A concluded    that the Linde 80 welds have margins equivalent to those of Appendix G of Section XI of the ASME Code for the 5 RPVs analyzed in the report.
that the Linde 80 welds have margins equivalent to those of Appendix G of Section XI of the ASME Code for the 5 RPVs analyzed in the report.
Request
Request
: a. Provide a technical basis for the application of BAW-2275A to: (1) include CR-3 vessel materials, which were not included in the BAW-2275A analysis, and (2) an extended license period of 54 EFPY, as opposed to the 48 EFPY of the BAW-2275A topical report.
: a. Provide a technical basis for the application of BAW-2275A to: (1) include CR-3 vessel materials, which were not included in the BAW-2275A analysis, and (2) an extended license period of 54 EFPY, as opposed to the 48 EFPY of the BAW-2275A topical report.
: b. Upper-shelf energy analyses contained Topical Reports BAW-2178PA and BAW-2192PA for CR-3 are bounded by 32 EFPY fluence predictions for the CR-3 beltline welds. The CR-3 fluence values for the extended license period of 54 EFPY exceed these fluence values.
: b. Upper-shelf energy analyses contained Topical Reports BAW-2178PA and BAW-2192PA for CR-3 are bounded by 32 EFPY fluence predictions for the CR-3 beltline welds. The CR-3 fluence values for the extended license period of 54 EFPY exceed these fluence values.
Therefore, provide a technical basis for the application of BAW-2178PA and BAW-2192PA using the CR-3 54 EFPY fluence values.}}
Therefore, provide a technical basis for the application of BAW-2178PA and BAW-2192PA using the CR-3 54 EFPY fluence values.}}

Latest revision as of 04:41, 14 November 2019

Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
ML091740070
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 08/03/2009
From: Robert Kuntz
License Renewal Projects Branch 2
To: Franke J
Florida Power Corp
KUNTZ R, NRR/DLR/RPB2 415-2989
References
TAC ME0274
Download: ML091740070 (6)


Text

August 3, 2009 Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA1B)

ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, FL 34428-6708

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)

Dear Mr. Franke:

By letter dated December 16, 2008, Florida Power Corporation submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Crystal River Unit 3 Nuclear Generating Plant, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Mr. Michael Heath, and a mutually agreeable date for the response is within 45 days from the date of this letter. If you have any questions, please contact me at 301-415-3733 or by e-mail robert.kuntz@nrc.gov.

Sincerely,

/RA/

Robert F. Kuntz, Senior Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

As stated cc w/encl: See next page

(s): ML091740070 OFFICE PM:RPB2:DLR LA:DLR BC:CVIB:DCI BC:RPB2:DLR PM:RPB2:DLR MMitchell DWrona RKuntz NAME RKuntz IKing (Signature)

DATE 07/23/09 08/03/09 07/30/09 07/31/09 08/03/09

Letter to J. Franke from R. Kuntz, dated August 03, 2009 DISTRIBUTION:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)

HARD COPY:

DLR RF E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRer1 Resource RidsNrrDlrRer2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter

________

RKuntz DBrittner AJones, OGC LLake, RII MSykes, RII TMorrissey, RII RReyes, RI

Crystal River Generating Plant, Unit 3 cc:

Mr. R. Alexander Glenn Senior Resident Inspector Associate General Counsel (MAC-BT15A) Crystal River Unit 3 Florida Power Corporation U.S. Nuclear Regulatory Commission P.O. Box 14042 6745 N. Tallahassee Road St. Petersburg, FL 33733-4042 Crystal River, FL 34428 Mr. James W. Holt Ms. Phyllis Dixon Plant General Manager Manager, Nuclear Assessment Crystal River Nuclear Plant (NA2C) Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, FL 34428-6708 Crystal River, FL 34428-6708 Mr. William A. Passetti, Chief Mr. David T. Conley Department of Health Associate General Counsel II - Legal Dept.

Bureau of Radiation Control Progress Energy Service Company, LLC 2020 Capital Circle, SE, Bin #C21 P.O. Box 1551 Tallahassee, FL 32399-1741 Raleigh, NC 27602-1551 Attorney General Mr. Daniel L. Roderick Department of Legal Affairs Vice President, Nuclear Projects &

The Capitol Construction Tallahassee, FL 32304 Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Mr. Ruben D. Almaluer, Director Crystal River, FL 34428-6708 Division of Emergency Preparedness Department of Community Affairs Mr. Mark Rigsby 2740 Centerview Drive Manager, Support Services - Nuclear Tallahassee, FL 32399-2100 Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Chairman Crystal River, FL 34428-6708 Board of County Commissioners Citrus County Mr. Robert J. Duncan II 110 North Apopka Avenue Vice President, Nuclear Operations Inverness, FL 34450-4245 Progress Energy P.O. Box 1551 Mr. Stephen J. Cahill Raleigh, NC 27602-1551 Engineering Manager Crystal River Nuclear Plant (NA2C) Mr. Brian C. McCabe 15760 W. Power Line Street Manager, Nuclear Regulatory Affairs Crystal River, FL 34428-6708 Progress Energy P.O. Box 1551 Mr. Daniel R. Westcott Raleigh, NC 27602-1551 Supervisor, Licensing & Regulatory Programs Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428-6708

CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION

Background:

By letter dated December 18, 2008, Florida Power Corporation, doing business as Progress Energy Florida, Inc., a subsidiary of Progress Energy, Inc., submitted a license renewal application (LRA) to extend the operating license for Crystal River Unit 3 Nuclear Generating Plant (CR-3), for an additional 20 year period.

Requests for Information RAI 4.2.6-1

Background

The CR-3 LRA states that:

The ART at the inside surface of CR-3 Lower Nozzle Belt Forging AZJ 94 is 3.0 oF higher than the ART evaluated for the previously limiting forging [from BAW-2247A, Fracture Mechanics Analysis of Postulated Underclad Cracks in B&W Designed Reactor Vessels for the Period Of Extended Operation].

Request Demonstrate that the reanalysis of the CR-3 Lower Nozzle Belt Forging AXJ 94 is consistent with the methodology used in BAW-2247A. Provide information, including input data, intermediate calculations, etc., as necessary, to support that the analyses performed for CR-3 are consistent with those in BAW-2274A.

RAI 4.2.2-1

Background

Section 4.2.2, Upper Shelf Energy Analysis, states that, the methodology used to evaluate CR-3 beltline welds at 60 years is consistent with the equivalent margins analysis (EMA) methods reported in BAW-2192PA, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Level A & B Service Loads; BAW-2178PA, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Level C & D Service Loads; and BAW-2275A, Low Upper-Shelf Toughness Fracture Mechanics Analysis of B&W Designed Reactor Vessels for 48 EFPY.

Topical Report BAW-2275A addresses the issue of low upper-shelf toughness for Linde 80 welds in Babcock and Wilcox (B&W) reactor pressure vessels (RPVs), for an extended license period of 48 effective full-power years (EFPY). The BAW-2275A evaluation involved 5 plants of the 16 plants covered by BAW-2178PA and BAW-2192PA. CR-3 did not participate in the evaluation contained in BAW-2275A. The staffs safety evaluation of BAW-2275A concluded ENCLOSURE

that the Linde 80 welds have margins equivalent to those of Appendix G of Section XI of the ASME Code for the 5 RPVs analyzed in the report.

Request

a. Provide a technical basis for the application of BAW-2275A to: (1) include CR-3 vessel materials, which were not included in the BAW-2275A analysis, and (2) an extended license period of 54 EFPY, as opposed to the 48 EFPY of the BAW-2275A topical report.
b. Upper-shelf energy analyses contained Topical Reports BAW-2178PA and BAW-2192PA for CR-3 are bounded by 32 EFPY fluence predictions for the CR-3 beltline welds. The CR-3 fluence values for the extended license period of 54 EFPY exceed these fluence values.

Therefore, provide a technical basis for the application of BAW-2178PA and BAW-2192PA using the CR-3 54 EFPY fluence values.