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{{#Wiki_filter:IScott L. BatsonbDUKE Vice President Oconee Nuclear StationENERGY. Duke EnergyONOIVP 1 7800 Rochester lHySeneca, SC 29672o: 864.873.3274 ONS-2014-014
: f. 864.873.4208 Scott. Batson@duke-energy.com January 30, 2014ATTN: Document Control Desk 10 CFR 50.54 (f)U.S. Nuclear Regulatory Commission Washington, DC 20555Duke Energy Carolinas, LLC (Duke Energy)Oconee Nuclear Station (ONS), Unit Nos. 1, 2, and 3Docket Nos. 50-269, 50-270, and 50-287Renewed License Nos. DPR-38, DPR-47, and DPR-55
==Subject:==
Response to Request for Additional Information Regarding Near-Term Task Force(NTTF) Recommendation 2.3, Flooding Walkdowns
-Review of Available PhysicalMargin (APM) Assessments
==References:==
: 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54(f)
Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident; dated March 12,2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340).
: 2. NEI 12-07, Guidelines for Performing Verification Walkdown of Plant Flood Protection
: Features, Revision 0-A, dated May 2012.3. NRC Letter to Nuclear Energy Institute (NEI), Endorsement of Nuclear Energy Institute (NEI) 12-07, Guidelines for Performing Verification Walkdowns of Plant Flood Protection
: Features, dated May 31, 2012, (ADAMS Accession No. ML12144A142).
: 4. Duke Energy Letter, Flooding Walkdown Information Requested by NRC Letter, Requestfor Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review ofInsights from the Fukushima Dai-ichi Accident; dated November 27, 2012.5. NRC letter, Request for Additional Information associated with Near-Term Task ForceRecommendation 2.3, Flooding Walkdowns; dated December 23, 2013 (ADAMSAccession No. ML13325A891).
Ladies and Gentlemen:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 requesting information pursuant to 10 CFR 50.54(f).
Enclosure 4 of that letter requested information associated with NTTF Recommendation 2.3 for Flooding Walkdowns.
Nuclear Energy Institute (NEI) 12-07 (Reference
: 2) provided walkdown guidance which was endorsed by NRC via letterdated May 31, 2012 (Reference 3). Oconee submitted its flooding walkdown report (Reference
: 4) modeled after Appendix D of the NEI 12-07 guidance document.
Following the initial review of walkdown
: reports, the NRC staff conducted audits at a sampling ofplant sites, These reviews and site audits, determined that additional information wasnecessary for the NRC to complete its assessments.
United States Nuclear Regulatory Commission Flood Walkdown APM RAIJanuary 30, 2014Page 2By letter dated December 23, 2013 (Reference 5), the NRC requested additional information regarding the determination and documentation of Available Physical Margin (APM) duringflooding walkdowns.
This letter requests that the response be provided no later thanJanuary 31, 2013.The response for Oconee Nuclear Site is enclosed.
This letter contains no new, or revised, Regulatory Commitments.
If you have any questions regarding this submittal, please contact David Haile, OconeeRegulatory Affairs at 864-873-4742.
I declare under penalty of perjury that the foregoing is true and correct.
Executed onJanuary 30, 2014.Sincerely, Scott L. BatsonVice President Oconee Nuclear Station
==Enclosure:==
Oconee Nuclear Station Units 1, 2 and 3, Response to the NRC Request for Additional Information (RAI) Regarding Available Physical Margin (APM) during Flooding Walkdowns United States Nuclear Regulatory Commission Flood Walkdown APM RAIJanuary 30, 2014Page 3cc:Mr. Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission
-Region IIMarquis One Tower245 Peachtree Center Ave., NE Suite 1200Atlanta, Georgia 30303-1257 Mr. Eric Leeds, Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 13-H16M11555 Rockville PikeRockville, MD 20852-2738 Mr. Richard Guzman, Project Manager (ONS)(by electronic mail only)U.S. Nuclear Regulatory Commission 11555 Rockville PikeMail Stop O-8C2Rockville, MD 20852Mr. Eddy CroweNRC Senior Resident Inspector Oconee Nuclear Station Enclosure Oconee Nuclear Station Units 1, 2 and 3Response to the NRC Request for Additional Information (RAI)Regarding Available Physical Margin (APM) during Flooding Walkdowns E1 Enclosure Oconee Nuclear Station Units 1, 2, and 3Response to the NRC Request for Additional Information Regarding Seismic Walkdowns Determination and documentation of available Physical margin (APM)
==Background:==
The NRC staff observed that several licensees did not consistently determine and/or documentavailable physical margin (APM) in a manner that met the expected interpretation of NEI 12-07during audits associated with review of the NTTF Recommendation 2.3 report submittals.
APMis defined in Section 3.13 of NEI 12-07 and the process for obtaining and evaluating APMvalues is described in Section 5.8 of NEI 12-07. Consistent with NEI 12-07, a numerical valuefor APM should be determined and documented for every applicable flood protection feature(e.g., wall, penetration, berm, door, etc.). This would normally be a numerical value reflecting the difference between the licensing basis flood height at the location of the feature and thepoint at which the function of the flood protection feature is compromised (e.g., the top of abarrier or the height of the first unsealed penetration in a barrier) such that the resulting floodcan affect a structures,
: systems, and components important to safety. Next, in accordance withSection 5.8 of NEI 12-07, if the APM appears to be small and the consequences of floodingappear to be significant, the licensee should enter the condition into the CAP and appropriate action be taken.While NEI 12-07 does not require that a specific numerical threshold value for "small" APM bedefined for each site, doing so establishes a consistent basis for determining what instances need to be entered into the CAP. If a numerical APM value cannot be determined for any floodprotection
: feature, the licensee should perform an assessment of the ability of the barrier towithstand the licensing basis flood plus the contribution of the additional water corresponding tothe pre-established small-margin threshold value. If the barrier can withstand this flood, theAPM for the feature is "not small" and further evaluation in accordance with Section 5.8 of NEI12-07 is not required.
It is further noted that conclusions regarding "large" values of APMshould be based on engineering evaluations or existing design documents.
Licensees should ensure that the process for APM determination and evaluation used duringtheir flooding walkdowns is consistent with the guidance in NEI 12-07. The intent of thisRequest for Additional Information (RAI) is not to repeat the flooding walkdowns or perform anextensive revision of the walkdown record forms and other paperwork.
Instead the purpose is toverify or modify the process used to determine APM such that every site is aware of the marginat each of its flood protection features and take appropriate interim actions when the APM issmall and the consequences are significant.
Instances where numerical values for APM werenot determined, or where the basis for the APM was found to be questionable, should berectified by either the documentation of a specific value or an explanation of why a non-numerical value is appropriate.
Requested Additional Information Please provide the following:
NRC RAI 1:Confirmation that the process for evaluating APM was reviewed; Response to RAI 1:A review of the process used to evaluate APMs at Oconee Nuclear Station has been completed.
E2 Enclosure Oconee Nuclear Station Units 1, 2, and 3Response to the NRC Request for Additional Information Regarding Seismic Walkdowns NRC RAI 2:Confirmation that the APM process is now or was always consistent with the guidance inNEI 12-07 and discussed in this RAI;Response to RAI 2:The original walkdown effort did follow the guidance provided in NEI 12-07 and employed aconsistent approach to evaluating if "small" margins existed.
: However, the approach for "small"margin was not defined and documented, as discussed in this RAI, at that time. The approachfor "small" margin, as it was used to assess Available Physical Margin at Oconee NuclearStation, has since been documented, and thus, the APM process is now consistent with bothNEI 12-07 and the information discussed in this RAI.NRC RAI 3:If changes are necessary, a general description of any process changes to establish thisconsistency; Response to RAI 3:The change of incorporating a definition for small margin into the APM process was necessary to become consistent with the "Background" discussion in this RAI. Also, seals that were notevaluated in accordance with Approach A or B, as described in RAI 4, were entered into CAPfor further evaluation of their APM. This action establishes consistency with the direction provided in RAI 4 below.It should be noted that documenting the definition of small margin did not change theassessment of margin classifications established in the original flooding walkdown report. Themargin classification for seals did change, as discussed in RAI 4.NRC RAI 4:As a result of the audits and subsequent interactions with industry during public meetings, NRCstaff recognized that evaluation of APM for seals (e.g., flood doors, penetrations, flood gates,etc.) was challenging for some licensees.
Generally, licensees were expected to use eitherApproach A or Approach B (described below) to determine the APM for seals:A. If seal pressure ratings were known, the seal ratings were used to determine APM (similar toexample 2 in Section 3.13 of NEI 12-07). A numerical value for APM was documented.
No furtheraction was performed if the APM value was greater than the pre-established small-margin threshold value. If the APM value was small, an assessment of "significant consequences" was performed and the guidance in NEI 12-07 Section 5.8 was followed.
B. If the seal pressure rating was not known, the APM for seals in a flood barrier is assumed to begreater than the pre-established small-margin threshold value if the following conditions were met:(1) the APM for the barrier in which the seal is located is greater than the small-margin threshold value and (2) there is evidence that the seals were designed/procured, installed, and controlled asflooding seals in accordance with the flooding licensing basis. Note that in order to determine thatthe seal has been controlled as a flooding seal, it was only necessary to determine that the sealconfiguration has been governed by the plant's design control process since installation.
In thiscase, the APM for the seal could have been documented as "not small".E3 Enclosure Oconee Nuclear Station Units 1, 2, and 3Response to the NRC Request for Additional Information Regarding Seismic Walkdowns As part of the RAI response, state if either Approach A or Approach B was used as part of theinitial walkdowns or as part of actions taken in response to this RAI. No additional actions arenecessary if either Approach A or B was used.If neither Approach A or B was used to determine the APM values for seals (either as part of thewalkdowns or as part of actions taken in response to this RAI), then perform the following twoactions:" Enter the condition into the CAP (note: it is acceptable to utilize a single CAP entry tocapture this issue for multiple seals). CAP disposition of "undetermined" APM values forseals should consider the guidance provided in NEI 12-07, Section 5.8. The CAPdisposition should confirm all seals can perform their intended safety function againstfloods up to the current licensing basis flood height. Disposition may occur as part of theIntegrated Assessment.
If an Integrated Assessment is not performed, determine whether there are significant consequences associated with exceeding the capacity ofthe seals and take interim action(s),
if necessary, via the CAP processes.
These actionsdo not need to be complete prior to the RAI response.
" Report the APM as "undetermined" and provide the CAP reference in the RAI response.
Response to RAI 4:Neither Approach A nor B, as described above, were used to determine the APM values forseals and trench covers. The seals and trench covers described in the walkdown report aredesigned to minimize leakage but are not designed to be water tight. Also, the seals and trenchcovers were not specifically documented as licensing basis flood protection features for theOconee Nuclear Station.
If accessible, seals were inspected for degradation as part of theoriginal walkdowns, and corrective actions were initiated if required.
In accordance with the RAIdirections above, the seals have now been assigned an APM value of "undetermined" andentered into the CAP process (PIP 0-14-00268) for further evaluation of their available physicalmargin.E4}}

Revision as of 23:38, 2 July 2018

Oconee, Units 1, 2, and 3 - Response to Request for Additional Information Regarding Near-Term Task Force (NTTF) Recommendation 2.3, Flooding Walkdowns - Review of Available Physical Margin (APM) Assessments
ML14034A105
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 01/30/2014
From: Batson S L
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ONS-2014-014
Download: ML14034A105 (7)


Text

IScott L. BatsonbDUKE Vice President Oconee Nuclear StationENERGY. Duke EnergyONOIVP 1 7800 Rochester lHySeneca, SC 29672o: 864.873.3274 ONS-2014-014

f. 864.873.4208 Scott. Batson@duke-energy.com January 30, 2014ATTN: Document Control Desk 10 CFR 50.54 (f)U.S. Nuclear Regulatory Commission Washington, DC 20555Duke Energy Carolinas, LLC (Duke Energy)Oconee Nuclear Station (ONS), Unit Nos. 1, 2, and 3Docket Nos. 50-269, 50-270, and 50-287Renewed License Nos. DPR-38, DPR-47, and DPR-55

Subject:

Response to Request for Additional Information Regarding Near-Term Task Force(NTTF) Recommendation 2.3, Flooding Walkdowns

-Review of Available PhysicalMargin (APM) Assessments

References:

1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54(f)

Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident; dated March 12,2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340).

2. NEI 12-07, Guidelines for Performing Verification Walkdown of Plant Flood Protection
Features, Revision 0-A, dated May 2012.3. NRC Letter to Nuclear Energy Institute (NEI), Endorsement of Nuclear Energy Institute (NEI) 12-07, Guidelines for Performing Verification Walkdowns of Plant Flood Protection
Features, dated May 31, 2012, (ADAMS Accession No. ML12144A142).
4. Duke Energy Letter, Flooding Walkdown Information Requested by NRC Letter, Requestfor Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review ofInsights from the Fukushima Dai-ichi Accident; dated November 27, 2012.5. NRC letter, Request for Additional Information associated with Near-Term Task ForceRecommendation 2.3, Flooding Walkdowns; dated December 23, 2013 (ADAMSAccession No. ML13325A891).

Ladies and Gentlemen:

On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 requesting information pursuant to 10 CFR 50.54(f).

Enclosure 4 of that letter requested information associated with NTTF Recommendation 2.3 for Flooding Walkdowns.

Nuclear Energy Institute (NEI) 12-07 (Reference

2) provided walkdown guidance which was endorsed by NRC via letterdated May 31, 2012 (Reference 3). Oconee submitted its flooding walkdown report (Reference
4) modeled after Appendix D of the NEI 12-07 guidance document.

Following the initial review of walkdown

reports, the NRC staff conducted audits at a sampling ofplant sites, These reviews and site audits, determined that additional information wasnecessary for the NRC to complete its assessments.

United States Nuclear Regulatory Commission Flood Walkdown APM RAIJanuary 30, 2014Page 2By letter dated December 23, 2013 (Reference 5), the NRC requested additional information regarding the determination and documentation of Available Physical Margin (APM) duringflooding walkdowns.

This letter requests that the response be provided no later thanJanuary 31, 2013.The response for Oconee Nuclear Site is enclosed.

This letter contains no new, or revised, Regulatory Commitments.

If you have any questions regarding this submittal, please contact David Haile, OconeeRegulatory Affairs at 864-873-4742.

I declare under penalty of perjury that the foregoing is true and correct.

Executed onJanuary 30, 2014.Sincerely, Scott L. BatsonVice President Oconee Nuclear Station

Enclosure:

Oconee Nuclear Station Units 1, 2 and 3, Response to the NRC Request for Additional Information (RAI) Regarding Available Physical Margin (APM) during Flooding Walkdowns United States Nuclear Regulatory Commission Flood Walkdown APM RAIJanuary 30, 2014Page 3cc:Mr. Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission

-Region IIMarquis One Tower245 Peachtree Center Ave., NE Suite 1200Atlanta, Georgia 30303-1257 Mr. Eric Leeds, Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 13-H16M11555 Rockville PikeRockville, MD 20852-2738 Mr. Richard Guzman, Project Manager (ONS)(by electronic mail only)U.S. Nuclear Regulatory Commission 11555 Rockville PikeMail Stop O-8C2Rockville, MD 20852Mr. Eddy CroweNRC Senior Resident Inspector Oconee Nuclear Station Enclosure Oconee Nuclear Station Units 1, 2 and 3Response to the NRC Request for Additional Information (RAI)Regarding Available Physical Margin (APM) during Flooding Walkdowns E1 Enclosure Oconee Nuclear Station Units 1, 2, and 3Response to the NRC Request for Additional Information Regarding Seismic Walkdowns Determination and documentation of available Physical margin (APM)

Background:

The NRC staff observed that several licensees did not consistently determine and/or documentavailable physical margin (APM) in a manner that met the expected interpretation of NEI 12-07during audits associated with review of the NTTF Recommendation 2.3 report submittals.

APMis defined in Section 3.13 of NEI 12-07 and the process for obtaining and evaluating APMvalues is described in Section 5.8 of NEI 12-07. Consistent with NEI 12-07, a numerical valuefor APM should be determined and documented for every applicable flood protection feature(e.g., wall, penetration, berm, door, etc.). This would normally be a numerical value reflecting the difference between the licensing basis flood height at the location of the feature and thepoint at which the function of the flood protection feature is compromised (e.g., the top of abarrier or the height of the first unsealed penetration in a barrier) such that the resulting floodcan affect a structures,

systems, and components important to safety. Next, in accordance withSection 5.8 of NEI 12-07, if the APM appears to be small and the consequences of floodingappear to be significant, the licensee should enter the condition into the CAP and appropriate action be taken.While NEI 12-07 does not require that a specific numerical threshold value for "small" APM bedefined for each site, doing so establishes a consistent basis for determining what instances need to be entered into the CAP. If a numerical APM value cannot be determined for any floodprotection
feature, the licensee should perform an assessment of the ability of the barrier towithstand the licensing basis flood plus the contribution of the additional water corresponding tothe pre-established small-margin threshold value. If the barrier can withstand this flood, theAPM for the feature is "not small" and further evaluation in accordance with Section 5.8 of NEI12-07 is not required.

It is further noted that conclusions regarding "large" values of APMshould be based on engineering evaluations or existing design documents.

Licensees should ensure that the process for APM determination and evaluation used duringtheir flooding walkdowns is consistent with the guidance in NEI 12-07. The intent of thisRequest for Additional Information (RAI) is not to repeat the flooding walkdowns or perform anextensive revision of the walkdown record forms and other paperwork.

Instead the purpose is toverify or modify the process used to determine APM such that every site is aware of the marginat each of its flood protection features and take appropriate interim actions when the APM issmall and the consequences are significant.

Instances where numerical values for APM werenot determined, or where the basis for the APM was found to be questionable, should berectified by either the documentation of a specific value or an explanation of why a non-numerical value is appropriate.

Requested Additional Information Please provide the following:

NRC RAI 1:Confirmation that the process for evaluating APM was reviewed; Response to RAI 1:A review of the process used to evaluate APMs at Oconee Nuclear Station has been completed.

E2 Enclosure Oconee Nuclear Station Units 1, 2, and 3Response to the NRC Request for Additional Information Regarding Seismic Walkdowns NRC RAI 2:Confirmation that the APM process is now or was always consistent with the guidance inNEI 12-07 and discussed in this RAI;Response to RAI 2:The original walkdown effort did follow the guidance provided in NEI 12-07 and employed aconsistent approach to evaluating if "small" margins existed.

However, the approach for "small"margin was not defined and documented, as discussed in this RAI, at that time. The approachfor "small" margin, as it was used to assess Available Physical Margin at Oconee NuclearStation, has since been documented, and thus, the APM process is now consistent with bothNEI 12-07 and the information discussed in this RAI.NRC RAI 3:If changes are necessary, a general description of any process changes to establish thisconsistency; Response to RAI 3:The change of incorporating a definition for small margin into the APM process was necessary to become consistent with the "Background" discussion in this RAI. Also, seals that were notevaluated in accordance with Approach A or B, as described in RAI 4, were entered into CAPfor further evaluation of their APM. This action establishes consistency with the direction provided in RAI 4 below.It should be noted that documenting the definition of small margin did not change theassessment of margin classifications established in the original flooding walkdown report. Themargin classification for seals did change, as discussed in RAI 4.NRC RAI 4:As a result of the audits and subsequent interactions with industry during public meetings, NRCstaff recognized that evaluation of APM for seals (e.g., flood doors, penetrations, flood gates,etc.) was challenging for some licensees.

Generally, licensees were expected to use eitherApproach A or Approach B (described below) to determine the APM for seals:A. If seal pressure ratings were known, the seal ratings were used to determine APM (similar toexample 2 in Section 3.13 of NEI 12-07). A numerical value for APM was documented.

No furtheraction was performed if the APM value was greater than the pre-established small-margin threshold value. If the APM value was small, an assessment of "significant consequences" was performed and the guidance in NEI 12-07 Section 5.8 was followed.

B. If the seal pressure rating was not known, the APM for seals in a flood barrier is assumed to begreater than the pre-established small-margin threshold value if the following conditions were met:(1) the APM for the barrier in which the seal is located is greater than the small-margin threshold value and (2) there is evidence that the seals were designed/procured, installed, and controlled asflooding seals in accordance with the flooding licensing basis. Note that in order to determine thatthe seal has been controlled as a flooding seal, it was only necessary to determine that the sealconfiguration has been governed by the plant's design control process since installation.

In thiscase, the APM for the seal could have been documented as "not small".E3 Enclosure Oconee Nuclear Station Units 1, 2, and 3Response to the NRC Request for Additional Information Regarding Seismic Walkdowns As part of the RAI response, state if either Approach A or Approach B was used as part of theinitial walkdowns or as part of actions taken in response to this RAI. No additional actions arenecessary if either Approach A or B was used.If neither Approach A or B was used to determine the APM values for seals (either as part of thewalkdowns or as part of actions taken in response to this RAI), then perform the following twoactions:" Enter the condition into the CAP (note: it is acceptable to utilize a single CAP entry tocapture this issue for multiple seals). CAP disposition of "undetermined" APM values forseals should consider the guidance provided in NEI 12-07, Section 5.8. The CAPdisposition should confirm all seals can perform their intended safety function againstfloods up to the current licensing basis flood height. Disposition may occur as part of theIntegrated Assessment.

If an Integrated Assessment is not performed, determine whether there are significant consequences associated with exceeding the capacity ofthe seals and take interim action(s),

if necessary, via the CAP processes.

These actionsdo not need to be complete prior to the RAI response.

" Report the APM as "undetermined" and provide the CAP reference in the RAI response.

Response to RAI 4:Neither Approach A nor B, as described above, were used to determine the APM values forseals and trench covers. The seals and trench covers described in the walkdown report aredesigned to minimize leakage but are not designed to be water tight. Also, the seals and trenchcovers were not specifically documented as licensing basis flood protection features for theOconee Nuclear Station.

If accessible, seals were inspected for degradation as part of theoriginal walkdowns, and corrective actions were initiated if required.

In accordance with the RAIdirections above, the seals have now been assigned an APM value of "undetermined" andentered into the CAP process (PIP 0-14-00268) for further evaluation of their available physicalmargin.E4