ML22174A323

NRC Presentation: Harvesting, an Overview and Historical Perspective

ML22174A323
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Issue date:	06/27/2022
From:	Robert Tregoning NRC/RES/DE
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J. Poehler
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Harvesting An Overview and Historical Perspective Rob Tregoning NRC Public Meeting on Harvesting NRC Headquarters, Rockville, MD June 27, 2022

June 27, 2022 Public Meeting on Harvesting Definitions and meeting scope

Harvesting (v, adj) - removal of materials, components, or structures (MCS) from a commercial nuclear power plant (NPP) for the purpose of performing subsequent evaluations

Mock-ups (n, adj) - Components produced to simulate NPP component geometries, fabrication, or repair techniques

Surveillance Specimens (n) - Sacrificial test articles placed within an operating NPP that are intended for subsequent removal to evaluate age-related degradation

Archival Material (n) - Remaining excess material from the fabrication of an NPP component Page 2

Effective Aging Management June 27, 2022 Public Meeting on Harvesting Role of harvesting in aging management Page 3 Knowledge gained through harvesting is but one facet that can support effective aging management

Harvesting can occur in one of three phases of an MCSs life

Pre-Service

Motivation: Understand initial performance and/or characteristics of an as-fabricated MCS

Possible when NPPs have been partially or fully constructed, but not operated

During Service

Motivation: Evaluate current performance and/or characteristics of an MCS or evaluate the root cause of service-induced degradation

Possible when an MCS is removed from service prematurely due to unanticipated age-related degradation

Post-Service

Motivation: Evaluate an MCS at the end of its service life to understand the progression of age-related degradation

Possible when components are replaced or when NPPs permanently shut-down June 27, 2022 Public Meeting on Harvesting Types of harvesting Page 4

June 27, 2022 Public Meeting on Harvesting An abbreviated history of nuclear harvesting Page 5 Harvesting Eras

In the Beginning (1970 - 1990)

Limited opportunities

Some prematurely replaced components

Mature Operations (1990 - 2010)

Several canceled plants

Occasional degraded components

Current Situation (after 2010)

Supply outstrips demand

Increased importance of partnering 1960 1970 1980 1990 2000 2010 2020 Commercial NPP Operation Begins First Subsequent License Renewal Granted First License Renewal Granted Shippingport Aging Evaluation Program Surry Steam Generator Project Midland NPP Nine-Mile Point Cracked Piping Shoreham NPP Reactor Pressure Vessel Head Materials Washington Nuclear Power Station Pulled SGTs PWR Vessel Head and Piping Cracking STG Cracking BWR Piping and Internals Cracking Steam Generator Tube (STG) Wastage Baffle Bolt Cracking SMILE Project Zorita NPP Crystal River NPP Zion NPP Baffle Bolts Canceled NPPs Degraded/Replaced Components Shut-Down NPPs Timeline Legend

Surry Steam Generator Project

Objectives:

Validate integrity assessment by burst testing service-degraded specimens

Evaluate reliability of techniques to detect, characterize and size degradation

International consortium of government and industry organizations

More Information: NUREG/CR-5117

Shippingport Aging Evaluation Program

Objective: Evaluate aging effects of components and specimens from the decommissioned Shippingport PWR

Evaluated over 200 components (e.g., battery chargers, valves, a motor control center) and specimens (e.g., from neutron shield tank, concrete, cast stainless steel components, piping)

More Information: NUREG-1144, Rev. 2

Midland Reactor Pressure Vessel

Objective: Evaluate unirradiated and irradiated properties of a low-upper-shelf energy reactor pressure vessel weld material

RPV head was used as an interim replacement for Davis-Besse head

More Information: NUREG/CR-5736 June 27, 2022 Public Meeting on Harvesting A few early harvesting vignettes Page 6

June 27, 2022 Public Meeting on Harvesting Some regulatory success stories

Generic Aging Lessons-Learned report (LR, SLR)

Identifies which existing plant programs are adequate for aging management and recommends specific areas where these programs should be augmented

One acceptable way to manage aging effects for long-term operation

Role of harvesting: Supported development of mechanical, structural, electrical AMPs and identification of those areas needing further evaluation

Alternate Pressurized Thermal Shock (PTS) Rule (10 CFR 50.61a)

Voluntary rule provides alternative fracture toughness requirements for demonstrating adequate protection against PTS events

Role of harvesting: Underpinned much of the basis for underlying flaw distribution, crack initiation, through-wall cracking, and nucleonics models

Reactor pressure vessel head inspections (10 CFR 50.55a)

Requirements for visual, volumetric, and surface examinations of penetrations

Role of harvesting: Provided confirmation that inspection frequencies are adequate to manage degradation Page 7

June 27, 2022 Public Meeting on Harvesting Summary

Nuclear stakeholders have actively employed harvesting since the inception of commercial nuclear power plant operation to better understand performance of important materials, components, and structures

Knowledge gained through harvesting is one facet that can support effective aging management

While we are entering a new phase where harvesting supply is greater than demand, strategic use of harvesting will continue to play an important role to support long-term nuclear power plant operation Page 8

June 27, 2022 Public Meeting on Harvesting A sampling of harvesting related reports Page 9 1.

J.R. Hawthorne and A.L. Hiser, Experimental Assessments of Gundremmingen RPV Archive Material for Fluence Rate Effects Studies, NUREG/CR-5201 (MEA-2286), U.S. Nuclear Regulatory Commission, October 1988.

2.

Kurtz, R. J., et al. 1990. Steam Generator Integrated Program/Stream Generator Group Project, Final Project Summary Report, NUREG/CR-5117, PNL-6226. Prepared for the U.S. Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory, Richland, Washington.

3.

O.K. Chopra, and W.J. Shack, Mechanical Properties of Thermally Aged Cast Stainless Steels from Shippingport Reactor Components, NUREG/CR-6275 (ANL-94/37), U.S. Nuclear Regulatory Commission, April 1995.

4.

G. J. Schuster, S. R. Doctor, S.L. Crawford, and A. F. Pardini, Characterization of Flaws in U.S. Reactor Pressure Vessels:

Density and Distribution of Flaw Indications in the Shoreham Vessel, NUREG/CR-6471 Volume 3, U.S. Nuclear Regulatory Commission, November 1999.

5.

G. J. Schuster, S. R. Doctor, A.F. Pardini, and S.L. Crawford, Characterization of Flaws in U.S. Reactor Pressure Vessels:

Validation of Flaw Density and Distribution in the Weld Metal of the PVRUF Vessel, NUREG/CR-6471 Volume 2, U.S.

Nuclear Regulatory Commission, August 2000.

6.

D.E. McCabe, et al. Evaluation of WF-70 Weld Metal From the Midland Unit 1 Reactor Vessel, NUREG/CR-5736 (ORNL/TM-13748), U.S. Nuclear Regulatory Commission, November 2000.

7.

A.B. Johnson, Jr., S.K. Sundaram, F.A. Garner, Program Plan for Acquiring and Examining Naturally Aged Materials and Components for Nuclear Reactors, PNNL-13930, Pacific Northwest National Laboratory, December 2001. (Prepared for the U.S. Department of Energy).

8.

B. Alexandreanu, O.K. Chopra, and W.J. Shack, Crack Growth Rates in a PWR Environment of Nickel Alloys from the Davis-Besse and V.C. Summer Power Plants, NUREG/CR-6921 (ANL-05/55), U.S. Nuclear Regulatory Commission, November 2006.

9.

S.E. Cumblidge, et al. Nondestructive and Destructive Examination Studies on Removed-from-Service Control Rod Drive Mechanism Penetrations, NUREG/CR-6996, U.S. Nuclear Regulatory Commission, July 2009.

June 27, 2022 Public Meeting on Harvesting A further sampling of harvesting related reports Page 10 10.

S.E. Cumblidge, et al. Evaluation of Ultrasonic Time-of-Flight Diffraction Data for Selected Control Rod Drive Nozzles from Davis Besse Nuclear Power Plant, PNNL-19362, Pacific Northwest National Laboratory, April 2011.

11.

S.L. Crawford, et al. Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Validation, NUREG/CR-7142 (PNNL-21547), U.S. Nuclear Regulatory Commission, August 2012.

12.

R. Fuentes, et al. Characterization and Analysis of Boral from the Zion Nuclear Power Plant Spent Fuel Pool, SRNL-TR-2018-00244, Rev. 0, Savannah River National Laboratory, March 2019 (ML19155A215).

13.

P. Ramuhalli, et al. Criteria and Planning Guidance to Ex-Plant Harvesting to Support Subsequent License Renewal, PNNL-27120, Rev. 1, Pacific Northwest National Laboratory, March 2019 (ML19081A006).

14.

Y. Chen, et al. Crack Growth Rate and Fracture Toughness Tests on Irradiated Ex-Plant Materials. ANL-19/45, Argonne National Laboratory, July 2020 (ML20198M503).

15.

Chen, Y., W-Y. Chen, and B. Alexandreanu, Irradiated Microstructure of Zorita Materials, ANL-20/50, Argonne National Laboratory, Lemont, IL, August 2020. (ML20269A143) 16.

Kombaiah, B., C. Judge, J. Charboneau, S. Smith, L. Gimenes Rodrigues Albuquerque, and V. Montes de Oca Carioni, Chemical Compositional Analysis and Microstructural Characterization of Harvested Zorita Reactor Pressure Vessel (RPV) Internals, INL/EXT-21-62220, Idaho National Laboratory, Idaho Falls, ID, March 2021. (ML21124A112) 17.

Le Pape., Y., et al, Assessment of San Onofre Concrete Susceptibility Against Irradiation Damage, Research Information Letter (RIL) 2022-07. Prepared for the U.S. Nuclear Regulatory Commission (NRC) by Oak Ridge National Laboratory, Oak Ridge, TN, 2022.

18.

Hiser, M., P. Purtscher, R.Tregoning, NRC Technical Assessment of Zorita Materials Testing Results, Research Information Letter (RIL) 2022-05. U.S. Nuclear Regulatory Commission (NRC), May 2022.