ML20087K487
| ML20087K487 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/16/1995 |
| From: | Stetz J CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2314, GL-92-01, GL-92-1, NUDOCS 9508230327 | |
| Download: ML20087K487 (4) | |
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ENERGY v
< 300 m W John P. Slett foledo OH 436524001 Vice Pteeldent - Nuclear l- 419 249-2300 m-sesse g
Docket Number 50-346 ,
License Number NPF-3 i Serial Number 2314 August 16, 1995 United States Nuclear Regulatory Commission -
Document' Control Desk Vashington, D. C. 20555-0001 j
l Subj ect : -Response to Generic Letter 92-01, Revision 1, Supplement 1, )
Reactor Vessel Structural Integrity, for the Davis-Besse Nuclear Power Station i
Ladies and Gentlemen: a i
This letter provides Toledo Edison's (TE) response for the Davis-Besse i Nuclear Power Station, Unit 1 (DBNPS), to the Nuclear Regulatory Commission !
(NRC) Generic Letter 92-01, Revision 1, Supplement 1, Reactor Vessel j Structural Integrity, dated May 19, 1995. The Generic Letter requires the following information be provided.to the NRC by August 17, 1995:
i "a description of those actions taken or p?anned to locate all data- i relevant to the determination of RPV integrity, or an explanation of. l why the existing data base is considered complete as previously submitted" By letter dated July 1, 1992, (TE Serial Number 2060), Toledo Edison pro-vided information requested by Generic Letter 92-01, Revision 1, including the location of requested detailed information' applicable.to the DBNPS. 1 By letter dated June 30, 1994, (TE Serial Number 2233), Toledo Edison pro-vided its response to NRC Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity, for Davis-Besse Nuclear Power Station (TAC No. .i H83732). This response included confirmation of the applicability of R Topical Reports BAV-2178P, Low. Upper-Shelf Toughness Fracture Mechanics i Analysis of Reactor Vessel of B&W Owners Reactor Vessel Vorking Group for n Level C & D Service Loads, and BAV-2192P, Lov Upper-shelf Toughness Fracture Analysis of Reactor Vessels of B&V Owners Group Reactor Vessel Vorking Group for Level A & B Conditions, to the DBNPS and verification of the information
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entered in the summary data files for the DBNPS. In addition Toledo Edison provided acceptance of the B&V Owners Group Topical Report BAV-2222, Reactor Vessel Vorking Group Response to Closure Letters to NRC Generic Letter 92-01, Revision 1.
Toledo Edison believes that our previous submittals (Serial Number 2060 and Serial Number 2233) provide a complete listing of relevant information re-garding the DBNPS reactor vessel. Regardless, Toledo Edison vill support .; '
the B&W Owners Reactor Vessel Working Group efforts to obtain additional
( data which could be relevant to the determination of RPV integrity. Toledo Edison vill provide the results of these efforts to the NRC as part of the required response to parts 2, 3 and 4 of Generic Letter 92-01, Revision 1, Supplement 1.
Toledo Edison has accepted the attached B&V Owners Group Topical Report BAV-2257, Response to Part (1) of Generic Letter 92-01, Revision 1, Supp-lement 1, submitted to the NRC by letter dated August 1, 1995 (reference:
OG-95-1527). This response was prepared by the B&W Nuclear Technologies ,
Company for the B&V Owners Group Reactor Vessel Working Group.
Should you have any questions or require additional information, please. I contact Mr. Villiam T. O'Connor, Manager - Regulatory Affairs, at (419) 249-2366.
Very truly yours,.
DHL Enclosure Attachment cc: L. L. Gundrum, DB-1 NRC/NRR Project Manager H. J. Miller, Regional Administrator, NRC Region III S. Stasek, DB-1 NRC Senior Resident inspector Utility Radiological Safety Board
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, Dockst Nuhbar 50- 346
- Lic:nca Nu;ber NPF-3
. Serial'. Number 2314
' Enclosure.
Page 1 RESPONSE TO SUPPLEMENT NO. 1 TO GENERIC LETTER 92-01 REVISION 1 FOR e
DAVIS-BESSE NUCLEAR POWER STATION
. UNIT NUMBER 1 This letter is submitted in comformance with Section 182a of the Atomic Energy Act of 1954 as amended, and 10CFR50.54(f). Enclosed is Toledo Edison's response to Part 1 of Supplement No. 1 to Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity.
'By:
J. P.frMti, Vi(e Prksident - Nuclear Sworn and subscribed before me this 16th day of August, 1995.
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Notar Publig, State of Ohio EVELYN L DRESS Notary Public. State of Ohio My Commission Empires 7/28/99 4
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'Dockat Nuzber 50-346 l Licensa Nu2b:;r NPF-3 l Serial Number 2314 Attachment-f
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Topical Report BAV-2257 Response to Part'(1) of Generic Letter 92-01 Revision 1, Supplement 1 i
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":, @WNERS CR2 UP n
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Oconee 1,2,3 Davis Besse Cue Power Cornpany Toseod Edison Cornpany Entergy Operations, Inc. Ah0-1 Tennessee Valley Authon~ty Bettelbare 1,2 F
Tkvida Power Corpexetxus CrystatImer 3 B&WNudear Technoaogies GPU Nudear Corporaterr TMI-1 ll gml Working Together to Economically Provide Reliable and Safe Electrical Power Suite 525 e 1700 Rockville Pike
- Rockville. MD 20852 * (301) 230-2100 :
l JHT/95-77 August 1,1995 i OG-95-1527 U.S. Nuclear Regulatory Commission Washington, DC 20555 g
Attention: Document Control Desk
Subject:
B&W Owners Group Reactor VesselIntegrity Program
Reference:
NRC I2tter dated May 19,1995
Subject:
NRC Generic Ietter 92-01 Revision 1, Supplement 1: Reactor Vessel Stmetural Integrity
Attachment:
BAW-2257 Response To Part (1) of Generic Ietter 92-01, Revision 1, Supplement 1 :
Gentlemen:
Five copies of BAW-2257 are submitted for your use and information on behalf of the B&
Owners Group Reactor Vessel Working Group.
This report provides the response to Part (1) as requested in the reference letter for eac following Reactor Vessel Working Group plants:
Arkansas Nuclear One Unit 1 Crystal River 3 Davis-Besse RB Ginna
' Oconce 1, 2, 3 '
Point Beach 1,2 Surry 1,2 Three Mile Island 1 ,
Turkey Point 3,4 !
Zion 1,2
&$WD l2S 2 f f.,
Utilitj Owners of these plants may reference BAW-2257 in their docketed msponses to the reference letter. ,
Very truly yours, ,
E 4-< J H TA1 W i J. H. Taylor, Manager Licensing Services ;
JHT/DLH/mcl Enclosure co c: B. J. Elliot - NRC Reactor Vessel Workine Gmup '
R. W. Clark - Entergy Operations, Inc. t T. D. Spry - Commonwealth Edison Company W. F. Brady - Duke Power Company D. N. Miskiewicz - Florida Power Corporation :
S. A. Collard - Florida Power & Light Company G. L. I2hmann - GPU Nuclear Corporation i W. S. Galloway, Jr. - Rochester Gas & Electric K. C. Prasad - Toledo Edison Company J. Harrell - Virginia Power ,
J. R. Pfefferle - Wisconsin Electric Power Company W. S. Hazelton - Consultant Utility Licensine Mananers D. C. Mims - Entergy Operations, Inc.
G. A. _Copp ' - Duke Power Company K. R. Wilson - Florida Power Corporation l J. S. Wetmore - GPU Nuclear Corporation ,
J. E. Blackbum - Tennessee Valley Authority l
W. T. O'Connor - Toledo Edison Company 't l
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I BAW-2267 JULY 1995 g
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- "AOWNERS GROUP
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' MATERIALS COMMITTEE
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g RESPONSE TO PART (1) OF GENERIC LETTER 92-01, REVISION 1, l SUPPLEMENT 1 I
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'E TECHNOLOGIES l 99gouw W- mf ,l, '
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. JULY 1995 I
RESPONSE TO PART (1) OF GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1 l
.I Prepared by M. J. DeVan E L. B. Gross BWNT Document No. 43-2257-00 l
Prepared for E B&W Owners Groun Reactor Vessel Workinn Groun Commonwealth Edisan Company !
Duke Power Company :
l Entergy Operations, Inc.
Florida Power Corporation Florida Power & Light Company GPU Nuclear Corporation Rochester Gas and Electric Corporation l Toledo Edison Company Virginia Power Wisconsin Electric Power Company q@
B&W NUCLEAR TECHNOLOGIES Engineering and Project Services Division P. O. Box 10935 3315 Old Forest Road Lynchburg, VA 24506-0935 s .
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-l 1. INTROLUCTION
.h This document provides the Owners Group response to Part (1) of Nuclear Regulatory Commission (NRC) Generic Letter 92-01, Revision 1, Supplement 1, for the B&W Owners Group Reactor Vessel Working Group member plants as listed below.
Generic Letter 92-01, Revision 1, Supplement 1, was issued by the NRC on May 19,1995 to holders of nuclear power plant operating licenses. The generic letter was issued to ensure that all licensecs have all of the data relevant to the evaluation of the structural integrity of their RVPs and that all such data is appropriately included in their assessments of compliance with regulatory requirements regarding RPV integrity. Response to Part (1) is required within 90 days of the issue date; with a deadline of August 17,1995. This document provides the requirt information in I response to Part (1) of the request. for the following plants: I Plant Owner Arkansas Nuclear One Unit 1 Entergy Operations, Inc.
l Crystal River Unit 3 Florida Power Corporation ,
Davis-Besse Toledo Edison Company
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R. E. Ginna Rochester Gas and Electric Corp.
Oconee Unit 1 Duke Power Company Oconce Unit 2 P te Power Company l Oconee Unit 3 Dae Power Company l l Point Beach Unit I heonsin Electric Power Co. I Point Beach Unit 2 Wisconsin Electric Power Co.
Surry Unit i Virginia Power Surry Unit 2 Virginia Power
,g Three Mile Island Unit 1 GPU Nuclear Corporation l5 Turkey Point Unit 3 Florida Power & Light Company Turkey Point Unit 4 Florida Power & Light Company fg Zion Unit 1 Commonwealth Edison Company IW Zion Unit 2 Commonwealth Edison Company
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- 2. STATEMENT OF RESPONSE Part (1) of the Generic Letter requires the Addressees to provide the following information: l l
"a description of those actions taken or planned to locate all data relevant to the i determination of RPV integrity, or an explanation of why the existing data base l m
i is considered complete as previously submitted" Lw The B&W Owners Group's Materials Committee initiated efforts in 1977 to resolve the reactor I vessel integrity issue for high copper, Linde 80, automatic submerged arc welds. Its successor organization, the B&W Owners Group's Reactor Vessel Working Group (RVWG), has continued l these efforts to acquire and document relevant data for determining reactor vessel integrity ofits a member plants. Appendix A provides a list of documents that are in the possession of the NRC.
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g and were considered in the development of the previous RVWG responses to Generic Letter 92-9 01, Revision 1 and associated requests for additional information.
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Lgl Information for these documents was obtained from the following sources:
o Babcock & Wilcox fabrication documentation (e.g., weld qualification re' ports) l l
o Investigations sponsored by-
- B&W Owners Group l
Electric Power Research Institute (EPRI)
- NRC (at the Oak Ridge National Laboratory) o Reactor vessel material surveillance program reports g
The RVWG's Master Integrated Reactor Vessel Material Surveillance Program (MIRVP) links all the operating PWRs that contain high copper, Linde 80 welds and makes careful note of where the same weld, or its surrogate, is used in more than one reactor vessel. These data are shared for regulatory analyses regarding reactor vessel integrity.
A review of the list of reactor vessels fabricated by Babcock & Wilcox indicates that additional weld chemistry and initial Charpy V-notch and Drop Weight impact toughness data from a few domestic BWR and foreign PWR vessels may be available. The B&W Owners RVWG will make efforts to obtain and evaluate the relevance of these data. Nevertheless, the RVWG believes that the available data, relevant to the assessment of its member plant vessels, have been appropriately considered in the submitted reactor vessel integrity evaluations.
Written responses to Parts (2), (3), and (4) of Generic Letter 92-01, Revision 1, Supplement 1, shall be provided within 6 months of the issue date of the Generic Letter (May 19, 1995).
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- 3. CERTIFICATION l ,
This report accurately responds to the information requested in Part (1) to Generic Letter 92-01,-
Revision 1, Supplement 1.
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M. J. D1IVan, Engineer III
]l3llW Date Materials & Structural Analysis Unit I
This report has been reviewed for technical content and accuracy.
}l 7f S.'Fyfitc6, Supervisory Engineer Date Materials & Structural Analysis Unit E
Verification ofindependent review.
E EG7hou K. E. Moore, Manager z&u'or
' Date l Materials & Structural Analysis Unit E This report is approved for release.
7hlh5 g D. L. .llowell ' Date R Program Manager 3-1 .
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APPENDIX A DOCUMENT
SUMMARY
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Perrin, J.S., et al..'" Final Report on Point Beach Nuclear Plant Unit No.1 Pressure Vessel l Surveillance Program: Evaluation of Capsule V," BMI-0673, Battelle Columbus Laboratories, Columbus, Ohio, June 15, 1973.
Perrin, J.S., et al., " Final Report on Point Beach Nuclear Plant Unit Fo. 2 Pressure Vessel I Surveillance Program: Evaluation of Capsule V," BMI-0675. Battelle Columbus Laboratories, i Columbus, Ohio, June 10,1975.
Perrin, J.S., et al., "Surry Unit No.1 Pressure Vessel Irradiation Capsule Program: Examination and Analysis of Capsule T," Battelle Columbus Laboratories, Columbus, Ohio, June 24,1975.
Lowe, A.L., Jr., et al., " Analysis of Capsule OCl-F from Duke Power Company Oconee Unit 1 Reactor Vessel Mrerials Surveillance Program," BAW-1421. Rev.1. Babcock & Wilcox, Lynchburg, Virginia, September 1975.*
Lowe, A.L., Jr., et al., " Analysis of Capsule OCl-E Duke Power Company Oconee Nuclear Station - Unit 1 Reactor Vessel Materials Surveillance Program," B AW-1436. Babcock & Wilcox, Lynchburg, Virginia, September 1977.*
Lowe, A.L., Jr., et al., " Analysis of Capsule OCII-C from Duke Power Company Oconee Nuclear Station, Unit 2 Reactor Vessel Material Surveillance Program," B AW-1437, Babcock & Wilcox, ,
Lynchburg, Virginia, May 1977.*
Lowe, A.L., Jr., et al., " Analysis of Capsule OCIII-A from Duke Power Company Oconee Nuclear Station, Unit 3 Reactor Vessel Materials Surveillance Program," BAW-1438. Babcock
& Wilcox, Lynchburg, Virginia, July 1977.* i Lowe, A.L., Jr., et al., " Analysis of Capsule TMI-lE from Metropolitan Edison Company Three Mile Island Nuclear Station-Unit 1 Reactor Vessel Materials Surveillance Program," BAW-1439.
Babcock & Wilcox, Lynchburg, Virginia, January 1977.*
Lowe, A.L., Jr., et al., " Analysis of Capsule ANI-E from Arkansas Power & Light Company ,
Arkansas Nuclear One - Unit 1 Reactor Vessel Materials Surveillance Program," BAW-1440, Babcock & Wilcox, Lynchburg, Virginia, April 1977.*
Moore, K.E., and A.S. Heller, " Chemistry of 177-FA B&W Owners' Oroup Reactor Vessel Beltline Welds," BAW-1500, Babcock & Wilcox, Lynchburg, Virginia, September 1978.* ;
I Harbison, L. S., " Master Integrated Reactor Vessel Surveillance Program," BAW-1543. Revision l 4, B&W Nuclear Technologies, Inc., Lynchburg, Virginia, February 1993.
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~ Lowe, A.L., Jr., et al., " Analysis of Capsule CR3-B Florida Power Corporation Crystal River Unit 3 Reactor Vessel Materials Surveillance Program," BAW-1679. Rev.1. Babcock & Wilcox, Lynchburg, Virginia, June 1982.*
Lowe, A.L., Jr., et al., " Analysis of Capsule OCIll-B from Duke Power Company Oconee Nuch,ar Station, Unit 3 Reactor Vessel Materials Surveillance Program," BAW-1697. Babcock
& Wilcox, Lynchburg, Virginia, October 1981.*
Lowe, A.L., Jr., et al., " Analysis of Capsule ANI-B from Arkansas Power & Light Company's Arkansas Nuclear One, Unit 1 Reactor Vessel Materials Surveillance Program," BAW-1698, Babcock & Wilcox, Lynchburg, Virginia, November 1981.*
Lowe, A.L., Jr., et al., " Analysis of Capsule OCII-A from Duke Power Company's Oconee Nuclear Station, Unit 2 Reactor Vessel Material Surveillance Program," BAW-1699. Babcock &
Wilcox, Lynchburg, Virginia, December 1981.*
Lowe, A.L., et al., " Analyses of Capsule TEl-F The Toledo Edison Company Davis-Besse Nuclear Power Station Unit 1 Reactor Vessel Materials Surveillance Program," BAW-1701.
Babcock & Wilcox, Lynchburg, Virginia, January 1982.*
Lowe, A.L., Jr., et al.," Analysis of Capsule RSI-B Sacramento Municipal Utility District Rancho Seco Unit 1 Reactor Vessel Material Surveillance Program," BAW-1702, Babcock & Wilcox, Lynchburg, Virginia, February 1982.*
Lowe, A.L., Jr., et al., " Analysis of Capsule RSI-D Sacramento Municipal Utility District Rancho Seco Unit i Reactor Vessel Material Surveillance Program," BAW-1792, Babcock & Wilcox, Lynchburg, Virginia, October 1983.*
Lowe, A.L., Jr., and J.W. Pegram, " Correlations for Predicting the Effects of Neutron Radiation on Linde 80 Submerged-Arc Welds," BAW-1803. Rev.1, B&W Nuclear Service Company, Lynchburg, Virginia, May 1991.*
Ardland, J.D., " Babcock & Wilcox Owners' Group 177-Fuel Assembly Reactor Vessel and Surveillance Program Materials Information," BAW-1820. Babcock & Wilcox, Lynchburg, Virginia, December 1984.*
Lowe, A.L., et al., " Analyses of Capsule TEl-B The Toledo Edison Company Davis-Besse Nuclear Power Station Unit 1 Reactor Vessel Material Surveillance Program," BAW-18)_4, Babcock & Wilcox, Lynchburg, Virginia, May 1984.*
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' Lowe, A.L., Jr., et al.," Analysis of Capsule ANI-A Arkansas Power & Light Company Arkansas Nuclear One, Unit 1 Reactor Vessel Materials Surveillance Program," BAW-1836. Babcock &
Wilcox, Lynchburg, Virginia, July 1984.*
Aadland, J.D., et al.," Analysis of Capsule OCl-A Duke Power Company Oconee Nuclear Station +
- Unit 1 Reactor Vessel Materials Surveillance Program," BAW-1837. Babcock & Wilcox, Lynchburg, Virginia, August 1984.*
Lowe, A.L., et al., " Analyses of Capsule TEl-A The Toledo Edison Company Davis-Besse Nuclear Power Station Unit i Reactor Vessel Material Surveillance Program," BAW-1882. Rev.
1, Babcock & Wilcox, Lynchburg, Virginia, June 1989.*
Lowe, A.L., Jr., et al., " Analysis of Capsule CR3-C Florida Power Corporation Crystal River Unit 3 Reactor Vessel Materials Surveillance Program," BAW-1898. Babcock & Wilcox, Lynchburg, Virginia, March 1986.*
Lowe, A.L., Jr., et al., " Analysis of Capsule CR3-D Florida Power Corporation Crystal River Unit 3 Reactor Vessel Materials Surveillance Program," BAW-1899, Babcock & Wilcox, Lynchburg, Virginia, March 1986.*
Lowe, A.L., Jr., et al., " Analysis of Capsule TMIl-C GPU Nuclear Three Mile Island Nuclear Station-Unit 1 Reactor Vessel Material Surveillance Program," BAW .901, Babcock & Wilcox, Lynchburg, Virginia, March 1986.*
Lowe, A.L., Jr., et al., " Analysis of Capsule CR3-LG1 - Babcock & Wilcox Owners Group Integrated Reactor Vessel Materials Surveillance Program," BAW-1910P. Babcock & Wilcox, Lynchburg, Virginia, August 1986.*
Lowe, A.L., Jr., et al., " Analysis of Capsule DB1-LG1 - Babcock & Wilcox Owners Group Integrated Reactor Vessel Materials Surveillance Program," BAW-1920P. Babcock & Wilcox, Lynchburg, Virginia, October 1986.*
Lowe, A.L., Jr., et al., " Analysis of Capsule CR3-F Florida Power Corporation Crystal River Unit 3 Reactor Vessel Materials Surveillance Program," BAW-2049. Babcock & Wilcox, Lynchburg, Virginia, September 1988.*
Lowe, A.L., Jr., et al., " Analysis of Capsule OCl-C Duke Power Company Oconee Nuclear Station Unit-1 Reactor Vessel Matcrials Surveillance Program," BAW-2050, Babcock & Wilcox, Lynchburg, Virginia, October 1988.*
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o 1Lowe, A.Li,' Jr., et al.,L" Analysis of Capsule OCII-E Duke Power Company Oconee Nuclear
- Station Unit-2 Reactor Vessel Material Surveillance Program," BAW-2051. Babcock & Wilcox, - -
- Lynchburg, Virginia, October 1977.*
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? Lowe, A.L., Jr., et 'al.," Analysis of Capsule RS1-F Sacramento Municipal Utility District Rancho ;
g
- Seco Unit'l Reactor Vessel Material Surveillance Program," BAW-2074. Babcock & Wilcox,
'Lynchburg, Virginia, April 1989.*
j i b Lowe, A.L., Jr., et al.," Analysis of Capsule ANI-C Arkansas Power & Light Company Arkansas
. Nuclear One, Unit 1 Reactor Vessel Materials Surveillance Program," BAW-2075.' Rev.1. l Babcock & Wilcox, Lynchburg, Virginia, October 1989.* i Lowe, A.L., Jr., et al., " Analysis of Capsule Y Commonwealth Edison Company Zion Nuclear .
Plant Unit 1 Reactor Vessel Material Surveillance Program," BAW-2082, B&W Nuclear Service .
l Company, Lynchburg, Virginia, March 1990.*
Gross, L.B., " Chemical Composition of B&W Fabricated Reactor Vessel Beltline Welds," BAW- ;
2121P, 77-2121-00, B&W Nuclear Service Company, Lynchburg, Virginia, April 1991.* -
Lowe, A.L., et al., " Analysis of Capsule TEl-D The Toledo Edison Company Davis-Besse Nuclear Power Station Unit 1 Reactor Vessel Material Surveillance Program," BAW-2R5, J Babcock & Wilcox, Lynchburg, Virginia, December 1990.* !
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'Lowe, A.L., Jr., et al., " Analysis of Capsule OCIII-D Duke Power Company Oconee Nuclear j Station Unit-3 Reactor Vessel Material Surveillance Program," BAW-2128. Rev.1. B&W Nuclear
, Service Company, Lynchburg, Virginia, May 1992.*
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Lowe, A.L., Jr., et al., " Analysis of Capsule S Wisconsin Electric Power Company Point Beach . !
Nuclear Plant Unit No.1 Reactor Vessel Material Surveillance Program," BAW-2140.- B&W ;
Nuclear Service Company, Lynchburg, Virginia, August 1991.* !
Ouellette, C.A.," Materials Information for Westinghouse-Designed Reactor Vessels Fabricated.
by B&W", BAW-2150. B&W Nuclear Service Company, Lynchburg, Virginia, December 1990.* -
.t DeVan, M.J., Gross, L. B., and Lowe, A. L. Jr., "B&W Owners Group Response to Generic -
j Letter 92-01," BAW-2166, B&W Nuclear Service Company, Lynchburg, Virginia, June 1992.
Yoon, K. K., " Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of
- B&W Owners Reactor Vessel Working Group for Level C & D Service Loads," BAW-2178PA.'
B&W Nuclear Technologies, Inc., Lynchburg, Virginia, April 1994. l l
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Lowe, A.L:, Jr., et al., " Evaluation of Capsules TMI2-C and TMI2-E Irradiated in Dav Nuclear Power Station Unit 1 -- EPRI Reactor Vessel Embrittlement Program, BAW-B&W Nuclear Technologies, August,19f Yoon, K. K., " Low Upper-Shelf Toughness Fracture Analysis of Reactor Vessels of B& .
Owners Group Reactor Vessel Working Group for Level A & B Conditions," BAW-B&W Nuclear Technologies, Inc., Lynchburg, Virginia, April 1994.
Yoon, K.K., " Fracture Toughness Characterization of WF-70 Weld Metal," BAW-22 Nuclear Technologies, Inc., Lynchburg, Virginia, September 1993.
DeVan, M.J., and K.K. Yoon, " Response to Closure Letters to Generic Letter 92-01, R 1," BAW-2222. B&W Nuclear Technologies, Inc., Lynchburg, Virginia, June 1994.
Palme, H.S., et al., " Methods of Compliance with Fracture Toughness and Operationa Requirements Virginia, March 1976.*of 10 CFR 50, Appendix G," BAW-10046P. Babcock & Wilcox, L ,
Moore, K.E., et al., " Evaluation of the Atypical Weldment," BAW-10144A, Babcock &
Lynchburg, Virginia, February 1980.* ,
Fromm, Program: E.O., et al., "Surry Unit No. 2 Nuclear Plant Reactor Pressure Vessel Surveil Examination and Analysis of Capsule W," BCL-585-026. ,
Izboratories, Columbus, Ohio, February 1981. Battelle Columbus P::rrin, J.S., et al., " Zion Nuclear Plant Reactor Pressure Vessel Surveillance Progra 1 Ccpsule T, and Unit No. 2 Capsule U," BCL-585-4. Battelle Columbus Laboratories Ohio, March 25,1978. ,
Van Der Sluys, W.A., et al., "An investigation of Mechanical Properties and Chem a Thick MnMoNi Submerged Arc Weldment," EPRI NP-373. Prepared by Babcock &
for the Electric Power Research Institute, Palo Alto, Califomia, February 1977. #
Letter from J. W. Williams, Florida Power & Light Company, to D. G. Eisenhut, Nuclear Regulatory Commission, Turkey Point Units 3 & 4, Docket Nos. 50-250 & 50-251, P Thermal Shock - Reactor Vessel Materials Data, dated February 10,1984.
Mager, T.R., et al., " Analysis of Capsule V from the Rochester Gas and Electric R.E !
No.1 Reactor Vessel Radiation Surveillance Program," FP-RA-1, Westinghouse El{
0:rporation, Pittsburgh, Pennsylvania, March 1,1973.
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- ' ? Nanstad, R'K., a d R.G Berggren, " Irradiation Effects on Charpy Impact and Ten of Low Upper Shelf: Welds,' HSSI Series 2 and 3," NUREG/CR-5696. Prepared by Oak R National Laboratory for the U.S. Nuclear Regulatory Commission, Washington, DC,- Aug 21991.
Nanstad, R.K.,'et al., " Chemical Composition and RTm Determinations for Midland Weld WF- g'
- 70," NUREG/CR-5914. Prepared by Oak Ridge National Laboratory for the U.S. Nuclear Regulatory Commission, Washington, DC, December 1992.~ ~
a f Letter from S.~ A. Varga, Nuclear Regulatory Commission, to J. W. Williams. Florida Power &
Light Company,
Subject:
Evaluation of Reactor Vessel Materials Data for Turkey Point Plant Units 3 and 4 Reactor Vessels, dated April 26,1984. q
- Letter from G.E. Edison, Nuclear Regulatory Commission, to W.F. Conway, Florida Power and
~ Light Company, Turkey Point Units'3 and 4 - Issuance of Amendment RE: Pressure and Temperature (P/F) Limits (TAC Nos. 69390 and 69391), dated January 10,1989.
'Norris, E.B., " Reactor Vessel Material Surveillance Program for Turkey Point Unit No. 4'
'.:14, Analysis 1976. of Capsule T," SwRI-02-4221. Southwest Research Institute, San Antonio, Texas, Jun Norris, E.B., " Reactor Vessel Material Surveillance Program for Capsule S - Turkey Point Unit '
No. 3, Capsule S -- Turkey Point Unit No. 4," SwRI-02-5131. SwRI-02-5380. Southwest '
- Research Institute, San Antonio,~ Texas, May 1979.
i (Ccpsule T, SwRI-06-6901-001. Southwest Research Insti , , . :
Norris, E.B., " Reactor Vessel Material Surveillance Program for Zion Unit No.1 Analysis o Capsule X," SwRI-06-7484-001, Southwest Research Institute, San Antonio, Texas, March 1984.j Nair, P.K.,'and E.B. Norris," Reactor Vessel Material Surveillance Program for Turkey Point# Ul
' Tex:.s, No. 3:August Analysis 1986. of Capsule V," SwRI-06-8575. Southwest Research Institute, San Antoni 3
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- Yanichko, S.E., et al., " Analysis of Capsule R from the Rochester Gas and Electric R.E. Ginna
. Unit No.1 Reactor Vessel Radiation Surveillance Program," _WCAP-8421. Westinghouse Elec
' Corporation, Pittsburgh, Pennsylvania, November 1974. q
- Yanichko, S.E., et al., " Analysis of Capsule T from the Florida' Power and Light Compa -
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