View source for L-2021-200, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response

{{Adams
| number = ML21298A090
| issue date = 10/25/2021
| title = Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response
| author name = Maher W
| author affiliation = NextEra Energy Point Beach, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000266, 05000301
| license number = DPR-024, DPR-027
| contact person = 
| case reference number = L-2021-200
| document type = Letter type:L, Response to Request for Additional Information (RAI)
| page count = 9
| project = 
| stage = Other
}}

=Text=
{{#Wiki_filter:NEXTera ENERGY ~
POINT BEACH October 25, 2021                                                                                L-2021-200 10 CFR 54.17 U.S. Nuclear Regulatory Commission Attention: Document Control Desk 11545 Rockville Pike One \V'hite Flint North Rockville, J:vID 20852-2746 Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 SUBSEQUENT LICENSE RENEWAL APPLICATION -AGING MANAGEMENT REQUESTS FOR ADDITIONAL INFORMATION (RAI) SET 11 RESPONSE

==References:==
: 1. NextEra Energy Point Beach, LLC (NEPB) Letter NRC 2020-0032 dated November 16, 2020, Application for Subsequent Renewed Facility Operating Licenses (ADAMS Package Accession No. ML20329A292)
: 2. NRC Email and Attachment dated September 29, 2021, Point Beach SLRA Safety RAI Set 11 Final (ADAMS Accession Nos. ML21287A085, lvIL21287A086)
NEPB, owner and licensee for Point Beach Nuclear Plant (PBN) Units 1 and 2, has submitted a subsequent license renewal application (SLRA) for the Facility Operating Licenses for PBN Units 1 and 2 (Reference 1).
The attachment to this letter provides the response to the NRC's Set 11 RAI (Reference 2).
For ease of reference, the index of attached information is provided on page 3 of this letter. The attachment includes associated revisions to the SLRA (Enclosure 3 Attachment 1 of Reference 1) denoted by strikethrough (deletion) and/ or bold red underline (insertion) text. Previous SLRA revisions are denoted by bold black text. SLRA table revisions are included as excerpts from each affected table.
Should you have any questions regarding this submittal, please contact me at (561) 304-6256 or William.Maher@fpl.com.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 25th day of October 2021.
Sincerely, Digitally signed by William Maher William              DN: cn =William Maher, o=Nuclear, ou =Nuclear Licensing Projects, emall=william.maher@fpl.com, Maher               c= US Date: 2021.10.25 11 :10:00 ~04'00' William D. Maher Licensing Director - Nuclear Licensing Projects NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241

Document Control Desk L-2021-200 Page 2 Cc:    Administrator, Region III, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Public Service Commission \"X!isconsin

Document Control Desk L-2021-200 Page 3 Attachments Index Attacluuent RAINo.                                       Subject No.
1        B.2.3.15-3 Inspection of Penetration Seals and Fire Damper Assemblies

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.15-3 L-2021-200 Attachment 1 Page 1 of 6 SLRA Section B.2.3.15, "Fire Protection" RAI 8.2.3.15-3 (Inspection of penetration seals and fire damper assemblies)
Regulatory Basis:
Section 54.21 (a)(3) of Title 10 of the Code of Federal Regulations (10 CFR) requires an applicant to demonstrate that the effects of aging for structures and components will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. One of the findings that the U.S. Nuclear Regulatory Commission (NRC) staff must make to issue a renewed license (10 CFR 54.29(a)) is that actions have been identified and have been or will be taken with respect to managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21, such that there is reasonable assurance that the activities authorized by the renewed license will continue to be conducted in accordance with the current licensing basis. In order to complete its review and enable it to make a finding under 10 CFR 54.29(a), the staff requires additional information in regard to the matters described below.

==Background:==

The "corrective actions" program element in GALL-SLR Report AMP Xl.M26, "Fire Protection," states, in part, that "During the inspection of penetration seals, if any sign of degradation is detected within that sample [emphasis added], the scope of the inspection is expanded to include additional seals in accordance with the plant's approved fire protection program."
SLRA Appendix A, Section 16.2.2.15, "Fire Protection," and Appendix B, Section B.2.3.15, "Fire Protection," state, in part, that "During the inspection of penetration seals and fire damper assemblies, if any sign of abnormal degradation is detected within the sample [emphasis added], the inspection sample size is expanded, in accordance with the approved PBN fire protection program, to include an additional 10 percent of each
~[emphasis added] of sealed penetration or fire damper assembly."
The enhancement to the "monitoring and trending" and "corrective actions" program elements in SLRA Section B.2.3.15 states, "Enhance plant procedures to require an inspection of an additional 10 percent of a type of seal when more than 15 percent of the sample population does not meet any acceptance criteria [emphasis added] during the 18-month inspection period."
The NRC staff notes that Routine Maintenance Procedure (RMP) 9057, "Fire Barrier Penetration Fire Seal Surveillance," states, for fire dampers, that an additional 10 percent will be tested due to damper failure and that the additional testing continues until failures is less than 15 percent.
Issue:
The NRC staff is unclear on whether the additional 10 percent is of each type of penetration seal or of a type of penetration seal, what is meant by "abnormal

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.15-3 L-2021-200 Attachment 1 Page 2 of 6 degradation," and whether the additional 10 percent sample is inspected when any sign of degradation within the sample is detected or only when more than 15 percent of the sample does not meet any acceptance criteria.
Request:
: 1. Please discuss, including the basis/justification, whether the Fire Protection program will include inspection of an additional 10 percent of each type of penetration seal or an additional 10 percent of a type of penetration seal.
: 2. Given that GALL-SLR AMP Xl.M26 states "any sign of degradation," please discuss what is meant by "abnormal degradation."
: 3. Please discuss whether the additional 10 percent sample is inspected when any sign of degradation within the sample is detected or only when more than 15 percent of the sample does not meet any acceptance criteria. If the later, then provide the basis/justification for "more than 15 percent." In addition, discuss the basis/justification for continuing additional testing for fire dampers until failures are less than 15 percent.
NEPB Response:
: 1. Each inspection sample comprises multiple penetration seal types. If degradation is detected in more than 15 percent of a given penetration seal type in the inspection sample, then the Fire Protection program will require an expanded sample. The expanded sample will include an additional 10 percent of the remaining population of the fire penetrations seal type(s) that exceeded the 15 percent threshold in the initial inspection sample.
[Note: Basis for the 15 percent failure threshold I 10 percent scope expansion values above is discussed in the response to request #3.]
Limiting scope expansion in this manner will focus the inspection on the extent of condition for the seal type(s) of concern. This is similar to the approach used for other sample inspection programs described in NUREG-2191 where components of different materials are grouped separately to establish populations and sample sizes. The Appendix A and Appendix B Fire Protection sections in the SLRA will be revised to clarify that the additional inspections will include the penetration seal type(s) that exceeded the 15 percent threshold.
: 2. The word abnormal should not have been used. It will be removed from Appendix A, Section 16.2.2.15 and Appendix B, Section B.2.3.15. The acceptance criteria for seal inspections currently are no visual indications of cracking, separation of seals from building structures and components, rupture, or puncture. Following incorporation of commitment 19.a of this subsequent license renewal application, the acceptance criteria will include no indications of hardness, shrinkage and loss of strength as well.
: 3. The intent was that the latter threshold (i.e., the additional 10 percent sample is inspected only when more than 15 percent of the sample does not meet any

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.15-3 L-2021-200 Attachment 1 Page 3 of 6 acceptance criteria) would be used to determine when an increase in the inspection sample size for fire barrier penetration seals would occur.
The basis for selecting this threshold was that it is consistent with the approach used for increasing the sample inspection size for fire dampers that is part of the plant's approved fire protection program as documented in ML20149E960 and ML20245A450. The same NRC-accepted sample population and acceptable failure rate for fire dampers (Reference ML20245A450) is considered to provide an equivalent standard of acceptability for fire barrier penetration seals to ensure that degradation is detected prior to loss of function.
The basis for continuing additional testing of fire dampers until failures are less than 15 percent is that this is in accordance with the plant's approved fire protection program as documented in ML20149E960 and ML20245A450.

==References:==
: 1. Letter from USN RC to Wisconsin Electric Power Company, Subj: NRC Receipt of Technical Evaluation of Fire Damper Tests for Point Beach Nuclear Plants, Units 1 and 2 in Response to Inspection Reports No. 50-266/87007 and No. 50-301187007 (ADAMS Accession No. ML20149E960)
: 2. NRC Inspection Reports No. 50-266/89006 and No. 50-301/89006 (ADAMS Accession No. ML20245A450)
: 3. NextEra Energy Point Beach, LLC (NEPB) Letter to NRC L-2021-081 dated April 21, 2021, Subsequent License Renewal Application -Aging Management Supplement 1 (ADAMS Accession No. ML21111A155)
Associated SLRA Revisions:
SLRA Appendix A, Section 16.2.2.15, last paragraph (page A-23), is revised as follows:
The results of inspections and functional testing of the in-scope fire protection equipment are collected, analyzed, and summarized by engineers in health reports. The system and program health reporting procedures identify adverse trends and prescribe preemptive corrective actions to prevent further degradation or future failures. When performance degrades to unacceptable levels, the PBN CAP is utilized to drive improvement. During the inspection of penetration seals and fire damper assemblies, if more than 15 percent of a type of penetration seal or fire damper assembly have any sign of abnormal degradation-+s detected within the sample, the inspection sample size is expanded, in accordance with the approved PBN fire protection program, to include an additional 10 percent of each type of sealed penetration or fire damper assembly that exceeded the 15 percent threshold .
SLRA Appendix A, Table 16-3, Commitment No. 19 k) (page A-77), as amended by Reference 3 is revised as follows:

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 8.2.3.15-3 L-2021-200 Attachment 1 Page 4 of 6 19 Fire Protection   Xl.M26         Continue the existing PBN Fire Protection AMP, including enhancement to:             No later than 6 months prior (16.2.2.15)                          a) Enhance plant procedures to specify that penetration seals will be            to the SPEO, i.e. :
inspected for indications of increased hardness, shrinkage and loss of        PBN1 : 04/05/2030 strength,                                                                     PBN2: 09/08/2032 b) Enhance plant procedures to specify that any loss of material to the fire damper assembly is unacceptable, c) Enhance plant procedures to specify that well-sealed and robustly secured components and fully enclosed cable tray covers credited to prevent internal fires from propagating outside of the component, and fire proofing material sprayed onto structural steel will be inspected for loss of material , cracking, and changes to elastomer properties as appropriate, d) Enhance plant procedures to add spalling and scaling to the degradation effects for which masonry block walls are inspected, e) Enhance plant procedures to indicate that personnel preforming FP inspections will be qualified to do so, f) Enhance plant procedures to state that at least 10% of each type of seal will be visually inspected every 18 months, g)  Enhance plant procedures to include inspecting, monitoring, and trending of oil collection channels, trenches, and skids credited to mitigate the spread of combustible liquids for cracking and loss of material at least once every 18 months. The acceptance criteria will be no indication of cracking or loss of material, h) Enhance plant procedures to specify that well-sealed and robustly secured components and fully enclosed cable tray covers credited to prevent internal fires from propagating outside of the component, and fire proofing material sprayed onto structural steel will be inspected every 4.5 years (33% of the population every 18 months) ,
i) Enhance plant procedures to specify that the dry chemical fire extinguishing systems will be inspected semi-annually, j) Enhance plant procedures to specify that the dry chemical fire extinguishing system inspections will be monitored and trended, and k) Enhance plant procedures to require an inspection of an additional 10% of a-each type of seal when more than 15% of that type of seal within the sample population does not meet any acceptance criteria during the 18-month inspection period.

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.15-3 L-2021-200 Attachment 1 Page 5 of 6 SLRA Appendix B, Section B.2.3.15, Program Description subsection, last paragraph on page B-123, is revised as follows:
The results of inspections and functional testing of the in-scope fire protection equipment are collected, analyzed, and summarized by engineers in health reports. The system and program health reporting procedures identify adverse trends and prescribe preemptive corrective actions to prevent further degradation or future failures. When performance degrades to unacceptable levels, the PBN CAP is utilized to drive improvement. During the inspection of penetration seals and fire damper assemblies, if more than 15 percent of a type of penetration seal or fire damper assembly have any sign of abnormal degradation is detected vvithin the sample, the inspection sample size is expanded, in accordance with the approved PBN fire protection program, to include an additional 10 percent of each type of sealed penetration or fire damper assembly that exceeded the 15 percent threshold .
SLRA Appendix B, Section B.2.3.15, Enhancements subsection, portion shown on page B-124, as amended by Reference 3 is revised as follows:
Element Affected                                       Enhancement
: 1. Scope of Program               Enhance plant procedures to specify that penetration seals will
: 3. Parameters Monitored or        be inspected for indications of increased hardness, shrinkage Inspected                     and loss of strength .
: 4. Detection of Aging Effects
: 5. Monitoring and Trending
: 6. Acceptance Criteria
: 1. Scope of Program               Enhance plant procedures to specify that any loss of material
: 3. .Parameters Monitored or       to the fire damper assembly is unacceptable.
Inspected
: 4. Detection of Aging Effects
: 5. Monitoring and Trending
: 6. Acceptance Criteria
: 1. Scope of Program               Enhance plant procedures to specify that well-sealed and
: 3. Parameters Monitored or        robustly secured components and fully enclosed cable tray Inspected                         covers credited to prevent internal fires from propagating
: 4. Detection of Aging             outside of the component, and fire proofing material sprayed Effects                           onto structural steel will be inspected for loss of material,        I
: 5. Monitoring and Trending        cracking, and changes to elastomer properties as appropriate.        ~
: 6. Acceptance Criteria

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.15-3 L-2021-200 Attachment 1 Page 6 of 6 Element Affected                                 Enhancement
: 1. Scope of Program        Enhance plant procedures to add spalling and scaling to the
: 3. Parameters Monitored or degradation effects for which masonry block walls are Inspected                  inspected.
: 4. Detection of Aging Effects
: 5. Monitoring and Trending
: 6. Acceptance Criteria
: 1. Scope of Program        Enhance plant procedures to include inspecting, monitoring,
: 3. Parameters Monitored    and trending of oil collection channels, trenches, and skids or Inspected               credited to mitigate the spread of combustible liquids for
: 4. Detection of Aging      cracking and loss of material at least once every 18 months.
Effects                    The acceptance criteria will be no indication of cracking or
: 5. Monitoring and Trending loss of material.
: 6. Acceptance Criteria
: 4. Detection of Aging      Enhance plant procedures to indicate that personnel Effects                 preforming FP inspections will be qualified to do so.
: 4. Detection of Aging      Enhance plant procedures to state that at least 10 percent of Effects                each type of seal will be visually inspected every 18 months.
: 4. Detection of Aging      Enhance plant procedures to specify that well-sealed and Effects                robustly secured components and fully enclosed cable tray covers credited to prevent internal fires from propagating outside of the component, and fire proofing material sprayed onto structural steel will be inspected every 4.5 years (33% of the population every 18 months).
: 4. Detection of Aging      Enhance plant procedures to specify that the dry chemical fire Effects                extinquishinq systems will be inspected semi-annually.
: 5. Monitoring and Trending Enhance plant procedures to specify that the dry chemical fire extinguishing system inspections will be monitored and trended.
: 5. Monitoring and Trending Enhance plant procedures to require an inspection of an
: 7. Corrective Actions      additional 10 percent of a-each type of seal when more than 15 percent of that type of seal within the sample population does not meet any acceptance criteria during the 18-month inspection period.
Associated 

==Enclosures:==

None.}}