ML14043A105
ML14043A105 | |
Person / Time | |
---|---|
Site: | Comanche Peak ![]() |
Issue date: | 01/30/2014 |
From: | Flores R, McCool T P Luminant Generation Co, Luminant Power |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
CP-201400125, TXX-14013 | |
Download: ML14043A105 (5) | |
Text
Rafael Flores Luminant PowerSenior Vice President P 0 Box 1002& Chief Nuclear Officer 6322 North FM 56Rafael.Flores@Luminant.com Glen Rose, TX 76043LuminantT 254 897 5590C 817 559 0403F 254 897 6652CP-201400125 TXX-14013 10 CFR 50.54(f)January 30, 2014U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, DC 20555-001
SUBJECT:
Comanche Peak Nuclear Power Plant (CPNPP) Docket Nos. 50-445 And 50-446 Submittal of Requested Information Regarding Near-Term Task ForceRecommendation 2.3 Flooding
-Review of Available Physical Margin(APM) Assessments
References:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54(o Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident; dated March 12,2012, Accession No. ML12073A348.
- 2. NRC Letter to Nuclear Energy Institute, Endorsement of Nuclear Energy Institute (NEI)12-07, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features,"
dated May 31, 2012, Accession No. ML12144A142.
- 3. Luminant Generation Company LLC's Letter TXX-12177, 120-Day Response to NRCRequest for Information Pursuant to 10CFR50.54(f)
Regarding the Flooding Aspects ofRecommendation 2.3 of the Near-Term Task Force Review of Insights from theFukushinma Dai-Ichi
- Accident, dated November 27, 2012 Accession No. ML12340A433
- 4. NRC Letter, Request for Additional Information Associated with Near-Term Task ForceRecomunendation 2.3, Flooding Walkdowns; dated December 23, 2013, Accession No.ML13325A891
Dear Sir or Madam:
On March 12, 2012, the U. S. Nuclear Regulatory Conmmission (NRC) staff issued Reference 1 requesting information pursuant to 10 CFR 50.54(f).
In Enclosure 4 of Reference 1, the NRC staff requested thatlicensees perform flood protection walkdowns associated with Near-Term Task Force Recommendation 2.3 for Flooding, and report the results to the NRC. By Reference 2, the NRC endorsed Nuclear EnergyInstitute (NEI) 12-07 as providing acceptable guidelines for performing waLkdowns of plant floodprotection features.
By Reference 3, Luminant Generation
- Company, LLC (Luminant Power) submitted afinal walkdown report for Comanche Peak Nuclear Power Plant (CPNPP) Units 1 & 2 in response to theReference 1 request for information.
Following the NRC staffs initial review of reports documenting the results of licensee flood protection walkdowns, regulatory site audits were conducted at a sample of plants. Based on the walkdown reportreviews and site audits, the staff identified additional information necessary to allow the staff to completeA member of the STARS Alliance 14P pCallaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- Wolf Creek U. S. Nuclear Regulatory Commission TXX-14013 Page 2 of 201/30/2014 its assessments.
The NRC observed that several licensees did not always determine and documentAvailable Physical Margin (APM) in a consistent manner that met the expected interpretation of NEI 12-07. Reference 4 transmitted an NRC request for additional information (RAI) regarding thedetermination and documentation of APM. Luminant Power's response to the Reference 4 RAI forComanche Peak Nuclear Power Plant (CPNPP) Units 1 & 2 is attached to this letter.This letter contains no new regulatory commitments.
If there are any questions regarding this plan, please contact Mr. Carl B. Corbin at (254) 897-0121carl.corbin@luminant.com.
I state under penalty of perjury that the foregoing is true and correct.Executed on January 30, 2014.Sincerely, Luminant Generation Company LLCRafael FloresBy: _ _ _ __Thomas P. cCoolVice President, Station Support
Attachment:
Comanche Peak Nuclear Power Plant (CPNPP) Response toRequest for Additional Information Regarding Flooding Wa]ikdown APMAssessments c -E. J. Leeds, Director, Office of Nuclear Reactor Regulation Marc L. Dapas, Region IVJessica A. Kratchman, NRR/JLD/PMB Balwant K. Singal, NRRResident Inspectors, Comanche Peak Attachment to TXX-14013 Page 1 of 3Comanche Peak Nuclear Power Plant (CPNPP) Response toRequest for Additional Information Regarding Flooding Walkdown APM Assessments The specific information requests as stated in the Reference 1 RAI are presented in italics below, followedby the corresponding Luminant Generation
- Company, LLC (Luminant Power) response.
The list ofreference is provided at the end of this attachment.
Please provide the following:
- 1. Confirmation that the process for evaluating APM was reviewed; Response
-Luminant Power confirms that it has reviewed the process for evaluating APM.2. Confirmation that the APAM process is now or was always consistent with the guidance in NEI 12-07 anddiscussed in this RAI;Response
-Luminant Power confirms that the APM evaluation process was, and remains,consistent with the guidance provided in NEI 12-07 (Reference
- 2) and discussion in the Reference 1 RAI.3. If changes are necessary, a general description of any process changes to establish this consistency; Response
-No changes are necessary to establish consistency with the guidance in NEI 12-07 anddiscussion in the Reference 1 RAI.4. [First Part] As a result of the audits and subsequent interactions with industny during public meetings, NRC staff recognized that evaluation of APM for seals (e.g.,flood doors, penetrations, flood gates, etc.) waschallenging for some licensees.
Generally, licensees were expected to use either Approach 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 ofNE1 12-07). A numerical value for APM was documented.
Nofirtlher action 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" wasperformed and the guidance in NEI 12-07 Section 5.8 was followed.
b) If the seal pressure rating was not known, the APMfor 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 bar-ier in which the seal is located is greater than the small-margin threshold value and 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".As part of the RAI response, state if either Approach A or Approach B was used as part of the initialwalkdowns or as part of actions taken in response to this RAI. No additional actions are necessary if eitherApproach A or B was used.Response
-Luminant Power inspected penetrations in below-grade exterior walls, floors andceilings of safety related buildings as part of the flood protection walkdowns.
As detailed below,the determination of APM for subgrade penetration seal locations is not required for ComanchePeak Nuclear Power Plant (CPNPP) Units I & 2 by NEI 12-07.
Attachment to TXX-14013 Page 2 of 3Details -The flood protection features that are within the scope of the NEI 12-07 walkdowns arethose features credited for protection and mitigation from external flood events in a plant'scurrent licensing basis (CLB). This is explicitly stated in several sections of NEI 12-07 (e.g. Section4.1.1). As stated in NEI 12-07 Section 3.13, APM describes the flood margin available forapplicable flood protection features.
Based on the stated scope of NEI 12-07, the "applicable flood protection features" for which APM determinations are required are those credited in theplant's CLB.The CLB for CPNPP conforms to the guidelines of Regulatory Guide 1.102 (Reference 3). Asdocumented in CPNPP FSAR (Reference
- 4) Section 1.0, Appendix iA(B) regarding conformance to NRC Regulatory Guides, plant grade for the CPNPP site is located above the PMF level, andCategory I structures, with the exception of the Service Water Intake Structure and the Electrical and Control Building, are not subject to flooding.
The operating deck and safety-related equipment in the Service Water Intake Structure are located above the PMF level. Flooding of theElectrical and Control Building is prevented by the use of incorporated barriers (i.e., isolation valves and/or stop-gates) and operating procedures to verify credited flood protection features/barriers are in place.As discussed in FSAR Section 3.4.1 regarding external flood events and flood protection, seismicCategory I equipment,
- systems, and components are enclosed within structures that are either:* Located above the probable maximum flood (PMF) level and do not require protection fromflooding, or* Located within structures where the plant grade is at a higher elevation than the PMF level orground flooding condition and doors and entries into these structures are located above plantgrade, or* Protected from flooding by administrative controls to verify flood protection features that areout of service for maintenance are installed in their credited configuration to precludeflooding propagation to any plant area located below the PMF.Consistent with CPNPP design, subgrade penetration seals located in the exterior walls, floorsand ceilings of seismic Category I structures are not required to be leak tight at full designdifferential pressure.
Therefore, no credit was taken for the seals' pressure retaining capability and APM values were not required by NEI 12-07. Such seal locations are required to maintaintheir structural integrity to ensure that the seal itself does not provide a flow path for thetransmission of sufficient fluid to an adjacent area to substantially change the environment in thatadjacent area. Where seismic Category I equipment,
- systems, and components are located belowplant grade, the design relies on gravity flow and the existing floor drain and sump pump systemto handle the minute amounts of water which could leak into the structures due to groundwater seepage.The Flooding Walkdown Report transmitted by Reference 5 noted that, although not explicitly credited in the CLB as a flood protection
- feature, subgrade penetration locations were considered within the scope of CPNPP flood protection walkdowns.
The penetration locations were visuallyinspected for seal material degradation and integrity and for evidence of water penetration.
Subgrade penetrations found to be in a condition where seal integrity was questionable or wherethere was evidence of groundwater seepage were entered into the Corrective Action Program forfurther evaluation.
No conditions were observed that indicated rooms in seismic Category Istructures below the design groundwater levels or the equipment contained within them could Attachment to TXX-14013 Page 3 of 3be inundated by groundwater.
Below grade seismic Category I design features including penetration seals are designed, installed and controlled in accordance with the plant's designconfiguration control processes.
- 4. [Second Part] If neither Approach A or B was used to determine the APM values for seals (either as part ofthe walkdowns or as part of actions taken in response to this RAI), then perform the following two actions:Enter the condition into the CAP (note: it is acceptable to utilize a single CAP entry to capturethis issue for multiple seals). CAP disposition of "undetermined" APM values for seals shouldconsider the guidance provided in NEI 12-07, Section 5.8. The CAP disposition should confirm allseals can perform their intended safety fitction against floods up to the current licensing basisflood height. Disposition may occur as part of the Integrated Assessment.
If an Integrated Assessment is not performed, determine whether there are significant consequences associated zoith exceeding the capacity of the seals and take interim action(s),
if necessary, via the CAPprocesses.
These actions do 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
-As described above, determination of seal APM values for Comanche Peak NuclearPower Plant (CPNPP) Units 1 & 2 is not required by NEI 12-07. Luminant Power therefore considers that no condition adverse to quality exists with respect to the processes used todetermine and document APM values for penetration seals, and that a Corrective ActionProgram entry is not required.
References:
- 1. NRC Letter, Request for Additional Information Associated with Near-Term Task ForceRecommendation 2.3, Flooding Walkdowns; dated December 23, 2013, Accession No.ML13325A891
- 2. Nuclear Energy Institute (NEI) 12-07, Revision 0, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features,"
dated May 2012, Accession No. ML12144A401.
- 3. NRC Regulatory Guide 1.102, "Flood Protection for Nuclear Power Plants,"
Revision 1,September 19764. CPNPP Final Safety Analysis Report5. Luminant Generation Company LLC's Letter TXX-12177, 120-Day Response to NRC Request forInformation Pursuant to 10CFR50.54(f)
Regarding the Flooding Aspects of Recommendation 2.3of the Near-Term Task Force Review of Insights from the Fukushin.ma Dai-Ichi
- Accident, datedNovember 27, 2012 Accession No. ML12340A433