ML20287A198
| ML20287A198 | |
| Person / Time | |
|---|---|
| Issue date: | 01/01/2021 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| SJG1 | |
| Shared Package | |
| ML20287A197 | List: |
| References | |
| RG 1.191, Rev 1 | |
| Download: ML20287A198 (7) | |
Text
Response to Public Comments on Draft Regulatory Guide DG-1370, Fire Protection Program for Nuclear Power Plants During Decommissioning, Proposed Revision 1 of Regulatory Guide 1.191 On August 11, 2020, the U.S. Nuclear Regulatory Commission (NRC) published a notice in the Federal Register (85 FR 48573) announcing the availability for public comment of Draft Regulatory Guide (DG)-1370, Fire Protection Program for Nuclear Power Plants During Decommissioning, proposed Revision 1 of Regulatory Guide (RG) 1.191. The public comment period ended on October 13, 2020. The NRC received comments from the following organization:
Mr. Gerard van Noordennen EnergySolutions 299 South Main Street, Suite 1700 Salt Lake City, UT 84111 gpvannoordennen@energysolutions.com Dated: October 5, 2020 Agencywide Documents Access and Management System Accession No. ML20281A526 The table below shows the public comments and the NRC staffs responses.
Commenter Specific Comments NRC Resolution Mr. Gerard van There are two major issues implied within this draft Regulatory Guide that The NRC staff agrees with the comment in part. As Noordennen were not associated with Rev 0. Specifically; described in more detail in response to a comment below, there was text in the draft RG that suggested
-It appears that the transition from an operating plants fire protection an approval is required for all plants that did not program (FPP) to a FPP that complies with 10 CFR 50.48(f) requires transition to an NFPA 805 fire protection program approval of the new plan by the NRC; and, (FPP) during operations. The NRC staff revised the RG to clarify that it is not required for plants to
-A FPP that complies with 10 CFR 50.48(f) must be maintained until the transition to NFPA 805 to decommission.
license is terminated. The NRC staff does not understand the second issue raised by the comment. Title 10 of the Code of Federal Regulations (10 CFR) 50.48(a)(3) states, The licensee shall retain the fire protection plan and each change to the plan as a record until the
Commenter Specific Comments NRC Resolution Commission terminates the reactor license.
Paragraph 50.48(a) applies to Each holder of an operating license issued under this part or a combined license issued under part 52 of this chapter. Paragraph 50.48(f) provides the requirements for FPPs during decommissioning, and the license is in decommissioning status until the it is terminated. Thus, it is the case that a FPP that complies with 10 CFR 50.48(f) must be maintained until the license is terminated. However, the contents of the FPP will be determined by the radiological hazard remaining on site.
The NRC staff has revised the final RG to ensure that the RG clearly describes the applicability of 10 CFR 50.48(a).
A secondary issue of the draft is that it implies that the entire content of The NRC staff agrees with the comment in part and 10 CFR 50.48 applies to decommissioned sites. This appears contrary to disagrees with the comment in part. The NRC Regulatory Guide 1.184. disagrees with comment to the extent the comment suggests that only 10 CFR 50.48(f) applies to decommissioning reactors. The NRC staff also disagrees that there is any conflict with RG 1.184.
The NRC staff agrees with the comment that the applicability of paragraphs (b) and (c) to decommissioning reactors could be clarified.
The key difference between operating and decommissioning reactors is that 10 CFR 50.48(f) applies only to decommissioning reactors and authorizes changes to the fire protection plans that would not be permitted under paragraphs (a) through (c). Thus, although 50.48(f) is not relevant to RG 1.184, which addresses fire protection at operating reactors, the rest of 10 CFR 50.48 remains relevant, 2
Commenter Specific Comments NRC Resolution if not controlling, for decommissioning reactors. In particular, 10 CFR 50.48(a)(3) states, The licensee shall retain the fire protection plan and each change to the plan as a record until the Commission terminates the reactor license.
The NRC staff made changes to the final RG to clarify the applicable regulations.
Mr. Gerard van Section A
Introduction:
Applicability (Page 1) The NRC agrees with the comment that the Noordennen 1. As stated in draft Rev. 1: applicability of the RG to ISFSIs could be clarified.
This RG does not apply to independent spent fuel storage installations There are no spent fuel storage facilities licensed (ISFSIs), except for the fire exposure risk to an ISFSI from a reactor during under Part 50. 10 CFR 50.48 does not apply to any decommissioning. ISFSI, whether generally or specifically licensed. The The applicability of FP programs to an ISFSI licensed under Subpart K of RG has been revised to more clearly state this point.
Part 72 (i.e. 10 CFR 50 License) needs to be clarified. Since these ISFSIs are licensed under a 10 CFR 50 license per 10 CFR 72.210, and the ISFSIs are typically located on the decommissioned site, the provisions of 10 CFR 50.48(f) for making changes to an ISFSI FPP appear to be applicable.
It should be noted here, that Revision 0 has the statement:
This guide does apply to spent fuel storage facilities licensed under 10 CFR Part 50.
Mr. Gerard van 2. Define Radiological Hazards consistently. In Definitions, Radiological The NRC agrees with the comment and has revised Noordennen Hazard is defined: the definition of radiological hazard in the final RG to Radiological hazard. The presence of radioactive material, including include dose limits to members of the public.
sources, contamination, wastes, and spent fuel, that presents a radiological exposure hazard that may be released in the event of a fire and that is in excess of the dose limits to plant personnel specified in 10 CFR Part 20.
In the Introduction and other sections of the RG, it is implied, and makes more sense, that Radiological Hazard also includes dose limits to members of the public:
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Commenter Specific Comments NRC Resolution The objectives of the fire protection program are to (1) reasonably prevent fires from occurring, (2) rapidly detect, control, and extinguish fires that do occur, and (3) minimize the risk of fire-induced radiological hazards to the public, the environment, and plant personnel.
Mr. Gerard van Section B Discussion: Background (Page 4) The NRC staff agrees with the comment. A license Noordennen Licensees that have an approved NFPA 805 program under 10 CFR amendment is needed to transition to an NFPA 805-50.48(c) can use Chapter 5 of NFPA 805 to comply with 10 CFR 50.48(f). based program. However, an NFPA 805-based A licensee that does not have an approved NFPA 805 program under 10 program is not required to meet the requirements of CFR 50.48(c) can request approval to implement NFPA 805 or other 10 CFR 50.48(f). For example, a fire protection performance- based standards to meet the requirements of 10 CFR program based on Appendix R to 10 CFR Part 50 50.48(f). can be used to satisfy the requirements of 10 CFR 50.48(f).
This statement implies that you have to request approval of a FP program for decommissioning if you didnt previously have an approved NFPA 805 The staff revised the final RG to remove the sentence program. That appears contrary to the requirements of 50.48(f)(3) which that suggested an NFPA 805 program is required to states: meet the requirements of 10 CFR 50.48(f).
(3) The licensee may make changes to the fire protection program without NRC approval if these changes do not reduce the effectiveness of fire protection for facilities, systems, and equipment that could result in a radiological hazard, taking into account the decommissioning plant conditions and activities.
Mr. Gerard van Section B Discussion: Documents Discussed in Staff Regulatory Guidance The NRC staff disagrees with the comment. The text Noordennen (Page 6) This entire paragraph is confusing with respect to the applicability on page 6 of DG-1370, under Documents Discussed of secondary references. It needs to be revised for greater specificity and in Staff Regulatory Guidance, is standard language clarity. that the NRC staff routinely uses in updated regulatory guides, and it has not resulted in confusion when used in other regulatory guides. To the extent that secondary references have particular application to the subject of this RG, fire protection at decommissioning sites, the NRC staff has addressed those issues in the appropriate sections of the RG providing specific guidance.
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Commenter Specific Comments NRC Resolution The staff has not made any changes to the final RG as a result of this comment.
Mr. Gerard van Section 1.4 (Page 9: first 2 paragraphs) The NRC staff agrees that the RG could benefit from Noordennen In general, this section, as drafted, now states that a FPP pursuant to 10 clarification in these points.
CFR 50.48(f) shall be maintained until the part 50 license is terminated.
This needs to be clarified since 50.48(a), (b), (c), (d) and (e) all appear to There are no regulations in 10 CFR 50.48(d) or (e);
be applicable to operating plants. This is based on the classification of these paragraphs have been reserved but contain no important to safety as described in Criterion 3 of Appendix A. At some requirements. However, the regulations in point in time during 10 CFR 50.48(a) are applicable to all reactor decommissioning, there are no longer any SSC important to safety; and licensees. The regulations in paragraphs (b) and (c) the radiological content of the site is no longer sufficient to result in establish the baseline requirements for fire protection radiological releases that would exceed the ALARA limits stated in programs that exist when a reactor enters Appendix I of part 50. decommissioning, which licensees are may be permitted to change either through a license 10CFR50.48(a)(1) Each holder of an operating license issued under this amendment or under 10 CFR 48(f)(3). 10 CFR part or a combined license issued under part 52 of this chapter must have 50.48(f) contains regulations specifically applicable to a fire protection plan that satisfies Criterion 3 of appendix A to this part. decommissioning reactors.
10CFR50, Appendix A, Criterion 3-Fire protection. Structures, systems, The text in DG-1370, Section 1.4, is consistent with and components important to safety shall be designed and located to 10 CFR 50.48, Fire protection. In particular, the minimize, consistent with other safety requirements, the probability and regulation in 10 CFR 50.48(a)(3) states, The effect of fires and explosions. licensee shall retain the fire protection plan and each change to the plan as a record until the Commission The first paragraph has deleted the statement that exists in Revision 0 terminates the reactor license. However, as the regarding property loss: regulations and the RG make clear, the scope and content of the fire protection plan can and should be Rev 0: The licensee alone will determine fire protection requirements for revised commensurate with the remaining plant areas that the licensee's fire hazards analysis has shown to have radiological hazard as appropriate to achieve the property loss concerns. objectives listed in 10 CFR 50.48(f)(1).
The first sentence of the second paragraph has been modified to require As decommissioning progresses and the spent fuel is the FPP pursuant to 10 CFR 50.48(f) to be maintained as long as the part moved to an independent spent fuel storage 50 license is in force. Revision 0 has the provision for not maintaining a installation or permanent repository, the fire protection requirements for the plant will be scaled 5
Commenter Specific Comments NRC Resolution FPP (per 50.48(f)) based on no radiological hazards or the license is down in accordance with the diminishing radiological terminated: hazard. In the absence of spent fuel in the spent fuel storage pool, a fire protection program should be Rev 0: The licensee should maintain a fire protection program as long as maintained that ensures adequate protection from the there are radiological hazards on the site or until the Part 50 license is fire-induced release of radioactive material only from terminated and the site is released for restricted or unrestricted use. contaminated plant areas, equipment, and combustible waste products.
The NRC staff has revised the final RG to clarify the
- 1. The new statements, as written, will require significantly more effort for statement about property loss and to clarify the those structures and areas that do not contain (or ever had) any applicability of 10 CFR 50.48(a).
radiological materials; e.g., PWR turbine buildings. The objectives of 10 CFR 50.48(f) require FPPs to maintain mitigating capability to deal with The NRC staff also agrees with this comment about fires that could result in a radiological hazard: clarifying the word rapidly. While the performance-based requirement should ensure sufficient fire detection and control systems or personnel are in (ii) Rapidly detect, control, and extinguish those fires that do occur and that place to prevent the scenario described in the could result in a radiological hazard; and comment from occurring, licensees may benefit from clarification about what rapidly means. The final RG (iii) Ensure that the risk of fire-induced radiological hazards to the public, includes the following text for clarification:
environment and plant personnel is minimized.
Rapidly means detecting fires quickly and suppressing those fires that occur, thereby limiting damage. This can be achieved by
- 2. Clarify the word rapidly as it applies to extinguish in this draft language. preventing significant fires from occurring, This becomes an issue for sites that want to use municipal fire given the inadvertent or purposeful departments for their emergency response, as most of those fire introduction of an ignition source. In the departments are reluctant to enter a burning building unless life safety is at event of a significant fire, its spread might stake. At some point in time during decommissioning, fire protection for the be limited by early human detection and decommissioned areas can be similar to typical industrial sites where the manual suppression, provision and safety of the responders results in controlling the fire, as opposed to maintenance of adequate fire detection and rapidly extinguish a fire just because it is on a nuclear site. automatic fire suppression systems, and a combination of manual and automatic detection and suppression systems.
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Commenter Specific Comments NRC Resolution Mr. Gerard van Section 6.0 NFPA 805 (Page 21)
Noordennen This section states that FPPs will comply with 10 CFR 50.48(f) by The NRC staff disagrees with the comment. The demonstrating compliance with NFPA 805, Chapter 5. It is not apparent section cited by the comment provides guidance on that the licensee may make changes to the fire protection program without how to demonstrate conformance with NFPA 805 as NRC approval if these changes do not reduce the effectiveness of fire a method for compliance with 10 CFR 50.48(f).
protection for facilities, systems, and equipment that could result in a Changes to the fire protection program that do not radiological hazard, taking into account the decommissioning plant conform to NFPA 805 might be permissible without a conditions and activities. Based on the language license amendment, but Section 6 of the RG only of the second paragraph on page 21, it appears that any changes to the provides guidance that conform to NFPA 805.
plants previously approved NFPA 805 licensing basis, would require a Licensees that have changed their plans in ways that submittal to the NRC. dot conform to NFPA 805 should ensure that their plans continue to meet the objectives stated in 10 CFR 50.48(f)(1).
The staff has made no changes to the final RG as a result of this comment.
Mr. Gerard van Additional Comment The NRC staff disagrees with this comment. Whether Noordennen Provide examples of reduction in effectiveness a particular change results in a reduction in effectiveness is a highly case-specific enquiry that should take into account the existing fire protection plan, the particular circumstances of the decommissioning activities at the site, the whole package of changes being considered, and the performance-based objectives of 10 CFR 50.48(f)(1).
Licensees should consider any and all factors appropriate to their particular circumstances in determining whether a change does not result in a reduction in effectiveness based on any factors appropriate to their particular circumstances.
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