Graded Approach to Dry Storage Cask and ISFSI Licensing

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Graded Approach to Dry Storage Cask and ISFSI Licensing Brian Gutherman for the Nuclear Energy Institute October 28, 2016 • Rockville, MD

Transcript of Graded Approach to Dry Storage Cask and ISFSI Licensing

Page 1: Graded Approach to Dry Storage Cask and ISFSI Licensing

Graded Approach to Dry Storage Cask and ISFSI Licensing

Brian Gutherman for the Nuclear Energy Institute

October 28, 2016 • Rockville, MD

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Overview

• RIRP I-16-01 purpose: Document NRC/Industry agreement that the Part 72 regulatory framework would benefit from implementation of a graded approach to better focus resources on nuclear safety and provide a plan to accomplish this

- Part 72 licenses and CoCs currently contain a level of detail not commensurate with the associated risk

- Currently there is little guidance governing what information is included in the licenses and CoCs

- NRC’s inspection program should have a bigger role

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CoC Content

• Unnecessary CoC content is costly - CoC amendments and revisions – both number and

scope • Preparation (CoC holder)

• Review fees (CoC holder)

• Implementation (Licensee)

- Fuel selection package complexity

- 72.212 Report complexity, revisions • Every applicable CoC requirement needs to be addressed in

the site 72.212 Report

• Requirements invoking other rules seem innocuous, but are not; each one needs to be addressed in the 212 Report

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Precedents

• Industry submitted a petition for rulemaking in 2012 in an effort to codify improvements to the Part 72 licensing framework (PRM 72-7)

- Founded on 1993 NRC policy statement on Improved Technical Specifications (ITS) for power reactors

- ITS successfully sharpened power reactor safety focus

- The fundamental principles of the policy statement transcend just power reactors

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Part 50 Improved Tech Spec History

• From the NRC’s 1993 Policy Statement on Improved Technical Specifications (ITS):

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Part 50 ITS History (cont’d) • Further from the ITS Policy Statement:

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RIRP Problem Statement

• NRC and Industry agree • Industry believes we can use the work done in support of

the PRM to establish the graded approach

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Graded Approach to Part 72 Regulatory Framework

• PRM 72-7 provides a strong foundation on which development of a graded approach to improving the license framework and having the correct information in the licenses and CoCs can be built - Includes selection criteria which should be applied

• Documenting a split of important-to-safety (ITS) and not-important-to-safety (NITS) structures, systems, and components (SSCs) is not the right place to start

• Consistent with NRC Part 50 policy and practice, content of dry storage licenses and CoCs should be based on SSC function, not safety classification

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Graded Approach to Part 72 Regulatory Framework

• SSCs included in operating plant TS are based on the detection, initial conditions, and mitigation of design basis accidents described in the SAR, plus risk significant items

• PRM 72-7 describes selection criteria based on these principles, modified appropriately for casks

- Accident mitigation excluded based on passive design

- Additional, unique criteria proposed for cask contents

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Graded Approach to Part 72 Regulatory Framework

• In addition to accident-related SSC function, control of the SSC should relate to “immediate concern to the health and safety of the public” - i.e., protection of the fission product

boundaries • Confinement boundary

• Fuel cladding

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Proposed SSC Selection Criteria

• Criterion S1: Installed instrumentation that is used to detect, and indicate a significant abnormal degradation of the cask confinement boundary;

• Criterion S2: An initial condition of a design basis accident that either assumes the failure of or presents a challenge to the integrity of a fission product barrier;

• Criterion S3: A structure, system, or component which operating experience or risk considerations have been shown to be significant to public health and safety.

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Proposed Approved Contents Selection Criteria

• Criterion C1: The characteristic or parameter is identified in 10 CFR 72.236(a);

• Criterion C2: A characteristic or parameter for which verification is a necessary condition to provide reasonable assurance that the cask safety functions of confinement, sub-criticality, and shielding will be performed;

• Criterion C3: A characteristic or parameter which operating experience or risk considerations have been shown to be significant to ensure public health and safety.

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SSC Example

• SSC in a CoC not meeting proposed SSC selection criteria - Standardized NUHOMS®, Attachment A, TS 5.3.3 - TC Alignment with HSM or HSM-H

• Includes a +/- 1/8-inch tolerance for alignment during DSC transfer to and from the HSM

• Not used to detect confinement boundary degradation • Not an initial condition for a DBA • Not risk-significant for storage operations or retrievability

- TC alignment is an operational parameter that should be managed by the licensee and available for adjustment under 72.48, if needed

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Contents Example

• Contents in a CoC not meeting proposed SSC selection criteria - HI-STORM 100, Appendix B, TS 2.4 - Individual fuel storage locations have limits on decay

heat - With individual fuel assembly limits on burnup and

cooling time, heat load is already defined - Non-fuel hardware also has burnup and cooling time

limits - Maximum heat load for the cask is what 72.236(a)

specifies, not individual fuel assembly

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Other Issues of Concern

• Repeating Regulations in the CoC

• Items subject to QA program requirements

• Items governed by other programs

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Example of CoC Content Repeating Regulations

• CoC 1004, Amendment 13, Attachment A, Section 5.2.4.a:

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Repeating Regulations Example (cont’d)

• Because they are part of the CoC, licensees must separately address both of these requirements in the 72.212 Report

- Analyses to demonstrate compliance with 72.104 are already required and documented in the 212 Report

- Part 20 is not a regulation for which compliance is demonstrated by analysis – it’s performance-based

- Additional, site-specific dose assessments for these events by general licensees are contrary to the GL concept

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Examples of Other Issues

• QA program scope

- Neutron absorber manufacturing and testing

- Canister helium leak testing

- ASME Code compliance/alternatives

• Training

• Radiation protection/ALARA

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Industry Summary of Graded Approach

• Based on design functions as described in the ISFSI or cask FSAR, SSCs should be evaluated for inclusion in the CoC/TS against the “S” criteria, irrespective of ITS classification

• Approved contents’ characteristics or parameters should be evaluated for inclusion in the CoC/TS against the “C” criteria, irrespective of ITS classification

• Other license and CoC requirements should be governed by the regulations and licensee programs

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Industry Proposed Changes to RIRP Screen

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Industry Proposed Changes to Action Plan

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Industry-Proposed Changes to Action Plan

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Path Forward

• Finalize RIRP documents

• Industry and NRC discuss and refine selection criteria given what we have learned since PRM submittal

• Agree upon appropriate selection criteria

• Use the pilot CoC amendment to test implementation of the selection criteria

• Modify selection criteria per lessons learned from the pilot

• Develop industry guidance for NRC endorsement

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QUESTIONS?