ML17264A118
| ML17264A118 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Point Beach, Arkansas Nuclear, Surry, Turkey Point, Crystal River, Ginna, Zion, Crane  |
| Issue date: | 07/31/1995 |
| From: | Devan M, Gross L BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML17264A117 | List: |
| References | |
| BAW-2257, GL-92-01, GL-92-1, NUDOCS 9508040139 | |
| Download: ML17264A118 (19) | |
Text
BAW-2257 JULY 1995 RESPONSE TO PART (I) OF GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1
Prepared by M. J. DeVan L. B. Gross BWNT Document No. 43-2257-00 Prepared for B&WOwners Grou Reactor Vessel Workin Grou Commonwealth Edison Company Duke Power Company Entergy Operations, Inc.
Florida Power Corporation Florida Power & Light Company GPU Nuclear Corporation Rochester Gas and Electric Corporation Toledo Edison Company Virginia Power Wisconsin Electric Power Company B&WNUCLEAR TECHNOLOGIES Engineering and Project Services Division P. O. Box 10935 3315 Old Forest Road Lynchburg, VA 24506-0935 I
9508040139 950801 PDR ADOCK 05000244 P
- 1. INTRODUCTION 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 licensees have all ofthe data relevant to the evaluation ofthe structural integrity oftheir RVPs and that all such data is appropriately included in their assessments ofcompliance with regulatory requirements regarding RPV integrity. Response to Part (1) is required within 90 days ofthe issue date; with a deadline of August 17, 1995.
This document provides the required information in'esponse to Part (1) of the request. for the following plants:
Plant Owner Arkansas Nuclear One Unit 1 Crystal River Unit 3 Davis-Besse R. E. Ginna Oconee Unit 1 Oconee Unit 2 Oconee Unit 3 Point Beach Unit 1 Point Beach Unit 2 Surry Unit 1 Surry Unit 2 Three Mile Island Unit 1
Turkey Point Unit 3 Turkey Point Unit 4 Zion Unit 1
Zion Unit 2 Entergy Operations, Inc.
Florida Power Corporation Toledo Edison Company Rochester Gas and Electric Corp.
Duke Power Company Duke Power Company Duke Power Company Wisconsin Electric Power Co.
Wisconsin Electric Power Co.
Virginia Power Virginia Power GPU Nuclear Corporation Florida Power & Light Company Florida Power & Light Company Commonwealth Edison Company Commonwealth Edison Company 1-1
- 2. STATEMENT OF RESPONSE Part (1) of the Generic Letter requires the Addressees to provide the following information:
"a description of those actions taken or planned to locate all data relevant to the determination of RPV integrity, or an explanation of why the existing data base is considered complete as previously submitted" The B&WOwners Group's Materials Committee initiated efforts in 1977 to resolve the reactor vessel integrity issue for high copper, Linde 80, automatic submerged arc welds.
Its successor organization, the B&WOwners Group's Reactor Vessel Working Group (RVWG), has continued these efforts to acquire and document relevant data for determining reactor vessel integrity ofits member plants.
Appendix A provides a list of documents that are in the possession of the NRC and were considered in the development ofthe previous RVWG responses to Generic Letter 92-01, Revision 1 and associated requests for additional information.
Information for these documents was obtained from the following sources:
o Babcock & Wilcox fabrication documentation (e.g., weld qualification reports) o Investigations sponsored by:
B&WOwners Group Electric Power Research Institute (EPRI)
NRC (at the Oak Ridge National Laboratory) o Reactor vessel material surveillance program reports 2-1
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 ofwhere 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 ofreactor vessels fabricated by Babcock 8'c 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&WOwners RVWGwillmake efforts to obtain and evaluate the relevance ofthese data.
Nevertheless, the RVWG believes that the available data, relevant to the assessment ofits 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 This report accurately responds to the information requested in Part (I) to Generic Letter 92-01, Revision 1, Supplement 1.
M. J.
eVan, Engineer III Materials & Structural Analysis Unit Date This report has been reviewed for technical content and accuracy.
S. Fyfit, upervisory Engineer Materials & Structural Analysis Unit Date Verification of independent review.
K. E. Moore, Manager Materials & Structural Analysis Unit 7 Zl Date This report is approved for release.
D. L.Howell Program Manager Date 3-1
APPENDIX A DOCUMENT
SUMMARY
I
Perrin, J.S., et al., "Final Report on Point Beach Nuclear Plant Unit No.
1 Pressure Vessel 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 No. 2 Pressure Vessel Surveillance Program:
Evaluation of Capsule V," BMI-0675 Battelle Columbus Laboratories, 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 OC1-F from Duke Power Company Oconee Unit 1 Reactor Vessel Materials Surveillance Program," BAW-1421 Rev.
1 Babcock & Wilcox, Lynchburg, Virginia, September 1975.
Lowe, A.L., Jr., et al., "Analysis of Capsule OC1-E Duke Power Company Oconee Nuclear Station - Unit 1 Reactor Vessel Materials Surveillance Program," BAW-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," BAW-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.
Lowe, A.L., Jr., et al., "Analysis of Capsule TMI-1E from Metropolitan Edison Company Three MileIsland Nuclear Station-Unit 1 Reactor Vessel Materials Surveillance Program," BAW-1439, Babcock & Wilcox, Lynchburg, Virginia, January 1977.'owe, 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.'oore, K.E., and A.S. Heller, "Chemistry of 177-FA B&W Owners'roup Reactor'essel Beltline Welds," BAW-1500, Babcock & Wilcox, Lynchburg, Virginia, September 1978.
Harbison, L. S., "Master Integrated Reactor Vessel Surveillance Program," BAW-1543 Revision 4 B&WNuclear Technologies, Inc., Lynchburg, Virginia, February 1993.
'his report is available from B&WNuclear Technologies, Inc., Lynchburg, Virginia.
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Lowe, A.L., Jr., et al., "Analysis ofCapsule CR3-B Florida Power Corporation Crystal River Unit 3 Reactor Vessel Materials Surveillance Program," BAW-1679 Rev.
1 Babcock & Wilcox, Lynchburg, Virginia, June 1982.'owe, A.L., Jr., et al., "Analysis of Capsule OCIII-B from. Duke Power Company Oconee Nuclear Station, Unit 3 Reactor Vessel Materials Surveillance Program," BAW-1697 Babcock
& Wilcox, Lynchburg, Virginia, October 1981.'owe, A.L., Jr., et al., "Analysis of Capsule ANI-Bfrom Arkansas Power & Light Company's Arkansas Nuclear One, Unit 1 Reactor Vessel Materials Surveillance Program," BAW-1698 Babcock & Wilcox, Lynchburg, Virginia, November 1981.'owe, 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 6t Wilcox, Lynchburg, Virginia, December 1981.
Lowe, A.Lts et al., "Analyses of Capsule TE1-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 ofCapsule RS1-B Sacramento Municipal UtilityDistrict Rancho Seco Unit 1 Reactor Vessel Material Surveillance Program," BAW-1702, Babcock & Wilcox, Lynchburg, Virginia, February 1982.'owe, A.L., Jr., et al., "Analysis ofCapsule RS1-D Sacramento Municipal UtilityDistrict Rancho Seco Unit 1 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 ofNeutron Radiation on Linde 80 Submerged-Arc Welds," BAW-1803 Rev.
1, B&W Nuclear Service Company, Lynchburg, Virginia, May 1991.
Aadland, J.D., "Babcock & Wilcox Owners'roup 177-Fuel Assembly Reactor Vessel and Surveillance Program Materials Information," BAW-1820 Babcock tk Wilcox, Lynchburg, Virginia, December 1984.
Lowe, A.L., et al., "Analyses of Capsule TE1-B The Toledo Edison Company Davis-Besse Nuclear Power Station Unit 1 Reactor Vessel Material Surveillance Program," BAW-1834, Babcock & Wilcox, Lynchburg, Virginia, May 1984.'
This report is available from B&WNuclear Technologies, Inc., Lynchburg, Virginia.
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I
Lowe, A.L., Jr., et al., "Analysis ofCapsule ANI-AArkansas 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 ofCapsule OC1-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 TE1-A The Toledo Edison Company Davis-Besse Nuclear Power Station Unit 1 Reactor Vessel Material Surveillance Program," BAW-1882 Rev.
1 Babcock & Wilcox, Lynchburg, Virginia, June 1989.
Lowe, A.L., Jr., et al., "Analysis ofCapsule CR3-C Florida Power Corporation Crystal River Unit 3 Reactor Vessel Materials Surveillance Program," BAW-1898 Babcock & Wilcox, Lynchburg, Virginia, March 1986.'owe, 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.'owe, A.L., Jr., et al., "Analysis of Capsule TMI1-C GPU Nuclear Three Mile Island Nuclear Station-Unit 1 Reactor Vessel Material Surveillance Program," BAW-1901, Babcock & Wilcox, Lynchburg, Virginia, March 1986.'owe, 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.'owe, A.L., Jr., et al., "Analysis ofCapsule 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 OC1-C Duke Power Company Oconee Nuclear Station Unit-1 Reactor Vessel Materials Surveillance Program," BAW-2050, Babcock &Wilcox, Lynchburg, Virginia, October 1988.'
This report is available from B&WNuclear Technologies, Inc., Lynchburg, Virginia.
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I
Lowe, A.L., Jr., et al., "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.
Lowe, A.L., Jr., et al., "Analysis ofCapsule RS1-F Sacramento Municipal UtilityDistrict Rancho Seco Unit 1 Reactor Vessel Material Surveillance Program," BAW-2074 Babcock & Wilcox, Lynchburg, Virginia, April 1989.
Lowe, A.L., Jr., et al., "Analysis of Capsule ANI-CArkansas Power &Light Company Arkansas Nuclear One, Unit 1 Reactor Vessel Materials Surveillance Program," BAW-2075 Rev.
1 Babcock & Wilcox, Lynchburg, Virginia, October 1989.'owe, 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&WNuclear Service Company, Lynchburg, Virginia, March 1990.'ross, L.B., "Chemical Composition ofB&WFabricated Reactor Vessel Beltline Welds," BAW-2121P 77-2121-00, B&WNuclear Service Company, Lynchburg, Virginia, April 1991.
Lowe, A.L., et al., "Analysis of Capsule TE1-D The Toledo Edison Company Davis-Besse Nuclear Power Station Unit 1 Reactor Vessel Material Surveillance Program," BAW-2125 Babcock & Wilcox, Lynchburg, Virginia, December 1990.
Lowe, A.L., Jr., et al., "Analysis of Capsule OCIII-D Duke Power Company Oconee Nuclear Station Unit-3 Reactor Vessel Material Surveillance Program," BAW-2128 Rev.
1 B&WNuclear Service Company, Lynchburg, Virginia, May 1992.
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.'uellette, C.A., "Materials Information for Westinghouse-Designed Reactor Vessels Fabricated by B&W",BAW-2150 B&WNuclear Service Company, Lynchburg, Virginia, December 1990.
DeVan, M.J., Gross, L. B., and Lowe, A. L. Jr., "B&WOwners Group Response to Generic Letter 92-01," BAW-2166, B&WNuclear Service Company, Lynchburg, Virginia, June 1992.
Yoon, K. K., "Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&WOwners Reactor Vessel Working Group for Level C &D Service Loads," BAW-2178PA, B&WNuclear Technologies, Inc., Lynchburg, Virginia, April 1994.
'his report is available from B&WNuclear Technologies, Inc., Lynchburg, Virginia.
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Lowe, A.L., Jr., et al., "Evaluation of Capsules TMI2-C and TMI2-E Irradiated in Davis Besse Nuclear Power Station Unit 1 EPRI Reactor Vessel Embrittlement Program," BAW-2190 B&WNuclear Technologies, August, 1993.
Yoon, K. K., "Low Upper-Shelf Toughness Fracture Analysis of Reactor Vessels of B&W Owners Group Reactor Vessel Working Group for Level A & B Conditions," BAW-2192PA B&WNuclear Technologies, Inc., Lynchburg, Virginia, April 1994.
Yoon, K.K., "Fracture Toughness Characterization of WF-70 Weld Metal," BAW-2202, B&W Nuclear Technologies, Inc., Lynchburg, Virginia, September 1993.
DeVan, M.J., and K.K.'oon, "Response to Closure Letters to Generic Letter 92-01, Revision 1," BAW-2222, B&WNuclear Technologies, Inc., Lynchburg, Virginia, June 1994.
Palme, H.S., et alta "Methods of Compliance with Fracture Toughness and Operational Requirements of 10 CFR 50, Appendix G," BAW-10046P, Babcock & Wilcox, Lynchburg, Virginia, March 1976.'oore, K.E., et alta "Evaluation of the Atypical Weldment," BAW-10144A, Babcock & Wilcox, Lynchburg, Virginia, February 1980.'romm, E.O., et al., "Surry Unit No. 2 Nuclear Plant Reactor Pressure Vessel Surveillance Program:
Examination and Analysis of Capsule W," BCL-585-026, Battelle Columbus Laboratories, Columbus, Ohio, February 1981
~
Perrin, J.S., et alta "Zion Nuclear Plant Reactor Pressure Vessel Surveillance Program: Unit No.
1 Capsule T, and UnitNo. 2 Capsule U," BCL-585-4 Battelle Columbus Laboratories, Columbus, Ohio, March 25, 1978.
Van Der Sluys, W.A., et al., "An Investigation of Mechanical Properties and Chemistry Within a Thick MnMoNi Submerged Arc Weldment," EPRI NP-373 Prepared by Babcock & Wilcox for the Electric Power Research Institute, Palo Alto, California, 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, Pressurized Thermal Shock - Reactor Vessel Materials Data, dated February 10, 1984.
Mager, T.R., et al., "Analysis ofCapsule V from the Rochester Gas and Electric R.E. Ginna Unit No.
1 Reactor Vessel Radiation Surveillance Program,"
FP-RA-1 Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, March 1, 1973.
'his report is available from B&WNuclear Technologies, Inc., Lynchburg, Virginia.
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Nanstad, R.K., and R.G. Berggren, "Irradiation Effects on Charpy Impact and Tensile Properties of Low Upper Shelf Welds, HSSI Series 2 and 3," NUREG/CR-5696 Prepared by Oak Ridge National Laboratory for the U.S. Nuclear Regulatory Commission, Washington, DC, August 1991.
Nanstad, R.K., et al., "Chemical Composition and RT~r Determinations for Midland Weld WF-70," NUREG/CR-5914 Prepared by Oak Ridge National Laboratory for the U.S. Nuclear Regulatory Commission, Washington, DC, December 1992.
Letter from S. A. Varga, Nuclear Regulatory Commission, to J. W. Williams. Florida Power 8c Light Company,
Subject:
Evaluation of Reactor Vessel Materials Data for Turkey Point Plant Units 3 and 4 Reactor Vessels, dated April 26, 1984.
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/T) Limits (TAC Nos. 69390 and 69391), dated January 10, 1989.
Norris, E.B., "Reactor Vessel Material Surveillance Program for Turkey Point Unit No. 4 Analysis of Capsule T," SwRI-02-4221, Southwest Research Institute, San Antonio, Texas, June 14, 1976.
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.
Norris, E.B., "Reactor Vessel Material Surveillance Program for Zion Unit No. 2 Analysis of Capsule T," SwRI-06-6901-001, Southwest Research Institute, San Antonio, Texas, July 6, 1983.
Norris, E.B., "Reactor Vessel Material Surveillance Program for Zion Unit No.
1 Analysis of Capsule X,"SwRI-06-7484-001, Southwest Research Institute, San Antonio, Texas, March 1984.
Nair, P.K., and E.B. Norris, "Reactor Vessel Material Surveillance Program forTurkey Point Unit No. 3:
Analysis of Capsule V,'* SwRI-06-8575 Southwest Research Institute, San Antonio, Texas, August 1986.
Yanichko, S.E., et al., "Analysis of Capsule R from the Rochester Gas and Electric R.E. Ginna UnitNo.
1 Reactor Vessel Radiation Surveillance Program," WCAP-8421, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, November 1974.
Yanichko, S.E., et al., "Analysis of Capsule T from the Florida Power and Light Company Turkey Point Unit No.
3 Reactor Vessel Radiation Surveillance Program,"
WCAP-8631 Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, December 1975.
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I
Yanichko, S.E., and S.L. Anderson, "Analysis of Capsule S from the Wisconsin Electric Power Company and Wisconsin Michigan Power Company Point Beach Nuclear Plant Unit No.
1 Reactor Vessel Radiation Surveillance Program,"
WCAP-8739 Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, November 1976.
Davidson, J.A., et al., "Analysis ofCapsule T from the Wisconsin Electric Power Company Point Beach Nuclear Plant Unit No. 2 Reactor Vessel Radiation Surveillance Program," WCAP-9331, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, August 1978.
Yanichko, S.E., and S.L. Anderson, "Analysis of Capsule R from the Wisconsin Electric Power Company Point Beach Nuclear Plant Unit No.
1 Reactor Vessel Radiation Surveillance Program,"
WCAP-9357 Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, August 1978.
Yanichko, S.E., et al., "Analysis ofCapsule R from the Wisconsin Electric Power Company Point Beach Nuclear Plant Unit No. 2 Reactor Vessel Radiation Surveillance Program," WCAP-9635, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, December 1979.
Yanichko, S.E., et al., "Analysis of Capsule U from the Commonwealth Edison Company Zion Nuclear Plant Unit 1
Reactor Vessel Radiation Surveillance Program,"
WCAP-9890, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, March 1981.
Yanichko, S.E., et al., "Analysis of Capsule T from the Rochester Gas and Electric R.E. Ginna Nuclear Plant Reactor Vessel Radiation Surveillance Program," WCAP-10086 Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, April 1982.
Yanichko, S.E., et al., "Analysis ofCapsule T from the Wisconsin Electric Power Company Point Beach Nuclear Plant Unit No.
1 Reactor Vessel Radiation Surveillance Program," WCAP-10736, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, December 1984.
Yanichko, S.E., and V.A. Perone, "Analysis of Capsule V from the Virginia Electric and Power Company Surry Unit 1
Reactor Vessel Radiation Surveillance Program,"
WCAP-11415, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, February 1987.
Yanichko, S.E., and V.A. Perone, "Analysis of Capsule V from the Virginia Electric and Power Company Surry Unit 2 Reactor Vessel Radiation Surveillance Program,"
WCAP-11499, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, June 1987.
Terek, E., et al., "Analysis of Capsule Y from the Commonwealth Edison Company Zion Unit 2 Reactor Vessel Radiation Surveillance Program,"
WCAP-12396, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, September 1989.
Chicots, J.M., et al., "Analysis of Capsule S from the Rochester Gas and Electric Corporation R.E. Ginna Reactor Vessel Radiation Surveillance Program," WCAP-13902, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, December 1993.
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