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{{Adams
#REDIRECT [[ET 16-0020, Operating Corp. - Supplement to the Expedited Seismic Evaluation Process Report]]
| number = ML16327A604
| issue date = 11/17/2016
| title = Wolf Creek Nuclear Operating Corp. - Supplement to the Expedited Seismic Evaluation Process Report
| author name = McCoy J H
| author affiliation = Wolf Creek Nuclear Operating Corp
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000482
| license number = NPF-042
| contact person =
| case reference number = ET 16-0020
| document type = Letter, Operating Report
| page count = 42
}}
 
=Text=
{{#Wiki_filter:Jaime H. McCoy Vice President Engineering W$LFCREEK 'NUCLEAR OPERATING CORPORATION November 17, 2016 ET 16-0020 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
 
==References:==
1) Letter dated March 12, 2012, from E. J. Leeds and M. R. Johnson, USNRC, to M. W. Sunseri, WCNOC, "Request for Information Pursuant to Title 10 of the Code of Federal Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident"
 
==Subject:==
Gentlemen: 2) Letter WO 14-0095 dated December 23, 2014, from C. 0. Reasoner, WCNOC, to USNRC 3) Letter ET 15-0015 dated June 24, 2015, from J. H. McCoy, WCNOC, to USNRC 4) Electronic Mail dated August 6, 2015, from S. M. Wyman, USNRC, to T. W. Solberg, WCNOC 5) Letter ET 15-0026 dated November 11, 2015, from J. H. McCoy, WCNOC, to USNRC 6) Letter dated January 4, 2016, from N. J. DiFrancesco, USNRC, to A. C. Heflin, WCNOC, "Wolf Creek Generating Station-Staff Review of Interim Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1" Docket No. 50-482: Supplement to the Expedited Seismic Evaluation Process Report On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to Wolf Creek Nuclear Operating Corporation (WCNOC). The Enclosure of Reference 2 provided the Wolf Creek Generating Station (WCGS) Expedited Seismic Evaluation Process (ESEP) Report requested in Enclosure 1 of Reference 1. Reference 3 provided a response to a request for additional information related to the ESEP Report in Reference 2. Reference 4 provided a request for additional information related to the WCGS ESEP Report. Reference 5 provided WCNOC's response to the request for additional information. Reference 6 provided the NRC staff review of the WCNOC ESEP report, concluding implementation of the interim evaluation /) / (J P.O. Box 411 /Burlington, KS 66839 /Phone: (620) 364-8831 A lV f( {JJ An Equal Opportunity Employer M/F/HC/VET (I (\. f\.
ET 16-0020
* Page 2 of 3 met the intent of the guidance. This letter provides the information and updates requested in Reference 6. Enclosures I-VI of this letter serve as a supplement to References 2 and 5. The enclosures identify changes to four sections and one attachment of the Wolf Creek Generating Station's Expedited Seismic Evaluation Process (ESEP) Report (Enclosure to letter WO 14-0095). Enclosure VI of this letter is a new attachment. The changes made to the enclosures are designated by revision bars. The enclosures replace in their entirety the following sections in the ESEP Report: I. Update to Section 6.2.2, "Generic Screening Results," Table 6-1: "Summary of Generic Screening per NP-6041-SL, Table 2-4, 1.2g Screening Level" II. Update to Section 6.3, "Seismic Walkdown Approach" Ill. Update to Section 6.6, "Tabulated ESEL HCLPF Values (Including Key Failure Modes)," Table 6-3:"HCLPF Analysis Results" IV. Update to Section 9, "References" V. Update to Attachment B. ESEP HCLPF Values and Failure Modes Tabulation VI. Insertion of Attachment C. Seismic Review Team As requested in Reference 6, Sections 7.0 and 8.0 of the WCGS ESEP final report remain unchanged, all walkdowns have been performed, and no modifications are needed. This letter also serves as closure to a commitment (Regulatory Commitment Management System 2015-500) provided in Attachment I of Reference 5; no further regulatory commitments exist. If you have any questions concerning this matter, please contact me at (620) 364-4156, or Cynthia R. Hafenstine (620) 364-4204. Sincerely, JHM/rlt
 
==Enclosures:==
Section 6.2.2, "Generic Screening Results," Table 6-1: "Summary of Generic Screening per NP-6041-SL, Table 2-4, 1.2g Screening Level" II Section 6.3, "Seismic Walkdown Approach" Ill Section 6.6, "Tabulated ESEL HCLPF Values (Including Key Failure Modes)," Table 6-3:"HCLPF Analysis Results" IV Section 9, "References" V Attachment B. ESEP HCLPF Values and Failure Modes Tabulation VI Attachment C. Seismic Review Team cc: K. M. Kennedy (NRC), w/e, B. K. Singal (NRC), w/e, N. H. Taylor (NRC), w/e, Senior Resident Inspector (NRC), w/e, ET 16-0020 Page 3 of 3 STATE OF KANSAS ) ) SS COUNTY OF COFFEY ) Jaime H. McCoy, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief. J aime . McCoy Vice resident Engineering SUBSCRIBED and sworn to before me this / 7'/£ day of /Jo llem b-er , 2016. GAYLE SHEPHEARD My Appointment Expires July 24, 2019 Expiration Date '1 J J..r-f( d.o /Cr Enclosure I to ET 16-0020 Section 6.2.2, "Generic Screening Results," Table 6-1: "Summary of Generic Screening per NP-6041-SL, Table 2-4, 1.2g Screening Level" (2 Pages)
Wolf Creek Generating Station ESEP Final Report Table 6-1: Summary of generic screening per NP-6041-SL, Table 2-4, 1.2g Screening Level Equipment Type Generic Screening Criteria Screening Result Active valves Note (f) applies. Although there are no extremely large extended motor operators on 2-inch or smaller piping, valves EPHV8808A/B/C/D are large MOVs with extended, heavy operators falling outside the NP-6041-SL Figure F-26 criteria and require evaluation. Passive valves No evaluation required. Atmospheric storage tanks Evaluation required. HCLPF analyses required for the atmospheric storage tanks. Pressure vessels Notes (h), (i) apply For the pressurized tanks on the ESEL, anchorage and load path were verified by bounding calculations using qualification reports during screening. Potential failure modes of the vessel bodies were addressed by walkdown and design review. The Safety Injection Tanks (Accumulators) were designed satisfactorily to Note (i) requirements; however, the anchorage requires evaluation. Batteries and racks Note (k) applies. Batteries are in plastic shell frames braced for overturning by steel rods and are designed for seismic loads. HCLPF analyses are required for the battery rack structure and anchorage. Horizontal pumps No evaluation required. Although no evaluation is required for the component per se, a HCLPF evaluation for the auxiliary feedwater turbine-driven pump is required. Active electrical power Notes (s) and (t) apply. Note (s) was addressed by walkdown and distribution panels design review. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required. Relays are evaluated separately per Reference 5. Passive electrical power Note (s) applies. Note (s) was addressed by walkdown and distribution panels design review. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required. Transformers Notes (u) and (v) apply. The ESEL includes dry-type transformers. A design review verified coil restraint. HCLPF analysis of anchorage is required.
Wolf Creek Generating Station ESEP Final Report Battery chargers & inverters Note (w) applies. Per walkdown and tlesign review, the items on the ESEL are solid state units. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required. Instrumentation and control Notes (s) and (t) apply. Note (s) was addressed by walkdown and panels and racks design review. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required. Relays are evaluated separately per Reference 5. Temperature sensors; pressure Note (x) applies. Note (x) was addressed by walkdown and and level sensors. design review. Sensors in the scope were typically mounted in-line on piping. Relevant notes from NP-6041-SL Table 2-4 f. Evaluation recommended for MOVs in piping lines of 2 inches diameter or less. h. Margin evaluation only needs to consider anchorage and supports. i. For vessels designed by dynamic analysis or equivalent static analysis enveloping vessel inertial and piping loading, only the anchorage and supports require evaluation. For vessel not meeting these criteria, all potential failure modes require evaluation. k. Batteries mounted in braced racks designed for seismic loads or qualified by dynamic testing do not require evaluation. Rigid spacers between batteries and end restraints are required. Batteries should be tightly supported by side rails. s. Walkdown should be conducted to verify that the instruments are properly attached to the cabinets. t. Relays, contactors, switches, and breakers must be evaluated for chatter and trip if functionality during strong shaking is required. u. Anchorage evaluation required. v. Liquid-filled transformers require evaluation of overpressure safety switches. The transformer coils should be restrained within the cabinet for dry transformers. w. Solid state units require anchorage checks. Others require evaluation. x. Insufficient data are available for screening guidelines. Emphasis should be on attachments. 1 to ET 16-0020 Section 6.3, "Seismic Walkdown Approach" (5 Pages)
Wolf Creek Generating Station ESEP Final Report 6.3 Seismic Walkdown Approach 6.3.1 Walkdown Approach Walkdowns were performed by two-person seismic review teams (SRTs) consisting of engineers with seismic experience. Walkdowns followed the guidance of Section 5 of EPRI 3002000704 and Section 2 of NP-6041-SL. The SRT used NP-6041-SL, Appendix F to evaluate item-specific equipment caveats. The SRT also recorded notes and took photographs of the items under review. Four walkdown sessions have been performed as indicated below. Walkdown Date SRT Plant Support Week of June 13, 2013 Hunter Young (S&A) Tim Solberg (WCNOC) Apostolos Karavoussianis (S&A) Week of March 24, 2014 Hunter Young (S&A) Tim Solberg (WCNOC) Timothy Nealon (S&A) Bud Freeman (WCNOC) Week of July 20, 2014 Hunter Young (S&A) Tim Solberg (WCNOC) Samer El-Bahey (S&A) Week of November 3, 2014 Hunter Young (S&A) Tim Solberg (WCNOC) Apostolos Karavoussianis (S&A) The walkdown findings for each item are documented in screening evaluation work sheets (SEWS). The SEWS notes also identify evaluations and reviews performed to support screening. The SEWS are included in Appendix C of Reference lOf. Also, Appendix A [lOf] provides a concise summary of screening results in tabular format. 6.3.2 Application of Previous Walkdown Information New seismic walkdowns were performed for ESEL equipment. Walkdown data ascertained in recent walkdowns of items as part of a seismic probabilistic risk assessment (S-PRA) were re-evaluated by the SRT and used for certain items. The results of the previous seismic margin evaluation, performed for the Seismic IPEEE program (11], were reviewed and used for background purposes only. 6.3.3 Significant Walkdown Findings The walkdown and screening results are summarized in Table 6-2.
Wolf Creek Generating Station ESEP Final Report Table 6-2: Items Selected for HCLPF Analysis No. ID Description Bldg Elev Basis for Selection 1. NBOOl 4.16KV SWGR NBOOl {Class CB 2000 Cabinet Anchorage could not be readily screened out for RLGM. Perform lE, Train A) -00 HCLPF analysis for anchorage. 2. NGOOl 480 V LOAD CENTER NGOl CB 2000 Cabinet Anchorage could not be readily screened out for RLGM. Perform -00 HCLPF analysis for anchorage. Apply results to similar items NG002 and NG003. 3. NKOOl 125 voe Bus CB 2016 Cabinet Anchorage could not be readily screened out for RLGM. Perform SWITCHBOARD NKOOl -00 HCLPF analysis for anchorage. Apply results to similar items NK003, NK004, NK041 and NK043. 4. NK011 125 V BATTERY NK011 CB 2016 Battery rack is not comprised of steel bracing. Perform HCLPF analysis for -00 plastic frame. Apply results to similar items NK013 and NK014. 5. NK011 125 V BATTERY NK011 CB 2016 Rack Anchorage could not be readily screened. Perform HCLPF analysis for -00 anchorage. Apply results to similar items NK013 and NK014. 6. NK021 125 V BATTERY CHARGER CB 2016 Cabinet Anchorage could not be readily screened out for RLGM. Perform NK021 -00 HCLPF analysis for anchorage. Apply results to similar items NK023, NK024, and NK025.
Wolf Creek Generating Station ESEP Final Report No. ID Description Bldg Elev Basis for Selection 7. NNOll 7.SKVA INVERTER (FED CB 2016 Cabinet Anchorage could not be readily screened out for RLGM. Perform FROM BATI CHARGER -00 HCLPF analysis for anchorage. NK021) Apply results to similar items NN013 and NN014. 8. PAL02 TDAFW Pump AB 2000 Pump Anchorage could not be readily screened out for RLGM. Perform HCLPF -00 analysis for anchorage. 9. RL021 REACTOR AUX CNTRL CB 2047 Console embedded plate could not be readily screened out for RLGM. Perform PANEL -06 HCLPF analysis for embedded plate. Apply results to similar items RL002, RLOOS, RL006, RL018, RL022. 10. RP053DB BOP INSTR RACK RP053DB CB 2047 Cabinet Anchorage could not be readily screened out for RLGM. Perform -06 HCLPF analysis for anchorage. Apply results to similar items RP053AC, RP053BC, and RP053DA. 11. RP081A T/C SUBCOOLING MONITOR CB 2047 Door cutout sizes exceed threshold of experience database in NP-6041-SL. CABINET -06 Evaluate component structure (including anchorage) and functionality via HCLPF analysis. Apply results to similar item RP081B. *12. SE054A W NUC INSTM NIS 1 CB 2047 Cabinet Anchorage could not be readily screened out for RLGM. Perform -06 HCLPF analysis for anchorage.
Wolf Creek Generating Station ESEP Final Report No. ID Description Bldg Elev Basis for Selection 13. TAPOl Condensate Storage Tank YARD 2000 Per NP-6041-SL Table 2-4 seismic capacity cannot be screened and HCLPF -00 analysis is required for overall seismic capacity. In addition, HCLPF evaluation required for block wall doghouse adjacent to tank. 14. TBNOl REFUELING WATER YARD 2000 Per NP-6041-SL Table 2-4 seismic capacity cannot be screened and HCLPF STORAGE TANK -00 analysis is required for overall seismic capacity. 15. XNGOl 4.16-KV/480 V LOAD CB 2000 Transformer Anchorage could not be readily screened out for RLGM. Perform CENTER TRANSFORMER -00 HCLPF analysis for anchorage. XNGOl FOR LC NGOOl Apply results to similar item XNG03. 16. Generic BLOCK WALLS AB/CB Var. Per NP-6041-SL Table 2-4 seismic capacity cannot be screened and HCLPF analysis is required for block wall seismic capacity. Affected components include NBOOl, NG003, TAPOl, NK043, NN003, NN013, NK041, NNOOl, NK021, NNOll, NKOSl, NKOOl, NK023, NK071, NK073, NKOll, NK013, AB007, NK003, RP209, NGOOlA, NG002, RP334, RP147A/B, NK004, NK074, NN004, NN014, NK024, and NK014. 17. Generic Cabinets containing AB/CB Var. Per 14C4257-RPT-003 [Ref. SJ, the following components contain essential essential relays relays that do not screen and require HCLPF evaluation: NGOOlA, NG002B, NG003C, NG004, and FC0219.
Wolf Creek Generating Station ESEP Final Report No. ID Description Bldg Elev Basis for Selection . 18. TEP01A Safety Injection RB 1998 Pressure vessel with circular skirt anchored to concrete foundation. Perform Accumulator Tank HCLPF analysis of the accumulator anchorage. (Accumulators) Additional item(s) bounded by evaluation: TEPOlB, TEPOlC, and TEPOlD 19. ABPVOOOl Steam Generator A AB 2046 AOV meets criteria per Figure F-25 of NP-6041-SL. However, the valve is Atmospheric Dump (Steam located more than 40 feet above grade; therefore further assessment of Generator ARV) capacity versus demand at base of component required. Additional item(s) bounded by evaluation: ABPV0002 20. AELT0539 Steam Generator Narrow RB 2026 The concrete expansion anchors (CEAs) were noted to have substantial offset, Range Water Level from which the anchorage cannot be readily screened against the RLGM. Transmitter Therefore, an evaluation of the transmitter's anchorage is required. 21. BBHV8001A RCS Reactor Vessel Head RB 2047 SOV meets criteria per Figure F-26 of NP-6041-SL. However, the valve is Vent A Upstream Valve located more than 40 feet above grade; therefore further assessment of (Reactor Head Vent) capacity versus demand at base of component required. Additional item(s) bounded by evaluation: BBHV8002A 22. EPHV8808A Accumulator Tank A Outlet RB 1998 Large MOV does not screen per Figure F-26 of NP-6041-SL and an evaluation Isolation Valve showing margin against the RLGM is required. (Accumulator Isolation Valves) Additional item(s) bounded by evaluation: EPHV8808B, EPHV8808C, and EPHV8808D  11 to ET 16-0020 Section 6.6, "Tabulated ESEL HCLPF Values (Including Key Failure Modes)," Table 6-3:"HCLPF Analysis Results" (3 Pages)
Wolf Creek Generating Station ESEP Final Report Table 6-3: HCLPF Analysis Results No. ID Description Bldg Elev HCLPF1 Failure Mode Basis Related Components (g, PGA) !Analyzed 1. NBOOl 4.16KV SWGR CB 2000-0.37 Equipment 14C4257-n/a NBOOl (Class lE, 00 capacity and CAL-005 Train A) anchorage 2. NGOOl 480 V LOAD CENTER CB 2000-0.29 Equipment 14C4257-NG002, NG003 NGOl 00 capacity and CAL-005 anchorage 3. NKOOl 125 voe Bus CB 2016-0.32 Equipment 14C4257-NK003, NK004, NK041, SWITCHBOARD 00 capacity and CAL-005 NK043, NN003 NKOOl anchorage 4. NKOll 125 V BATTERY CB 2016-0.45 Anchorage 14C4257-NK013, NK014 NKOll 00 CAL-004 5. NKOll 125 V BATTERY CB 2016-0.69 Equipment 14C4257-NK013, NK014 NKOll 00 capacity CAL-005 6. NK021 125 V BATTERY CB 2016-2.24 Anchorage 14C4257-NK023, NK024, NK025 CHARGER NK021 00 CAL-004 7. NNOll 7.5KVA INVERTER CB 2016-0.68 Anchorage 14C4257-NN013, NN014 (FED FROM BATT 00 CAL-004 CHARGER NK021) 8. PAL02 TDAFW Pump AB 2000-1.70 Anchorage 14C4257-n/a 00 CAL-004 9. RL021 REACTOR AUX CB 2047-0.32 Anchorage 14C4257-RL002, RL005, RL006, CNTRLPANEL 06 CAL-004 RL018, RL022 10. RP053DB BOP INSTR RACK CB 2047-0.56 Anchorage 14C4257-RP053AC, RP053BC, RP053DB 06 CAL-004 RP053DA 11. RP081A T/C SUBCOOLING CB 2047-0.61 Equipment 14C4257-RP081B MONITOR CABINET 06 capacity and CAL-005 anchorage 12. SE054A W NUC INSTM NIS 1 CB 2047-0.86 Anchorage 14C4257-n/a , -06 CAL-004 13. TAPOl Condensate Storage YARD 2000-0.30 Equipment 14C4257-n/a Tank 00 capacity and CAL-002 anchorage 1 HCLPFs based upon RLGM (PGA=0.29g) as the seismic margins earthquake with the exception of TAPOl, TBNOl, and the CST pipe house block walls, which are based upon the GMRS (PGA=0.29g).
Wolf Creek Generating Station ESEP Final Report No. ID Description Bldg Elev HCLPF2 Failure Mode Basis Related Components (g, PGA) lAnalyzed 14. TBNOl REFUELING YARD 2000-0.32 Equipment 14C4257-n/a WATER STORAGE 00 capacity and CAL-002 TANK anchorage 15. XNGOl 4.16-KV/480 V CB 2000-0.47 lAnchorage 14C4257-LOAD CENTER 00 CAL-004 TRANSFORMER XNGOl FOR LC NGOOl 16. Generic BLOCK WALLS AB/ Var. CB CTRL2000' All block walls on CB 2000-2.66 !Seismic 14C4257-NBOOl, NG003, CTRL 2000' elev 00 interaction CAL-003 NGOOlA, NG002, RP334, RP147A/B, CTRL 2016' All block walls no CB 2016-1.85 !Seismic 14C4257-NK043, NN003, NN013, CTRL 2016' elev 00 interaction CAL-003 NK041, NNOOl, NK021, NNOll, NK051, NKOOl, NK023, NK071, NK073, NKOll, NK013, AB007, NK003, NK004, NK074, NN004, NN014, NK024, NK014 AUX2000' 2000' elev wall on AUX 2000-1.15 !Seismic 14C4257-RP209 column line AF 00 interaction CAL-003 north of Stair A-2 CST House CST Pipe house YARD 2000-0.37 !Seismic 14C4257-[TAPOl masonry walls 00 interaction CAL-003 17. Generic Cabinets AB/C Var. containing B essential relays NG003C MCC NG03C BUS CB 2047-0.44 Functional 14C4257-NGOOlA, NG002B, 06 capacity and CAL-005 NG004C host component capacity FC0219 LOCAL CONTROL AB 2000-0.61 Functional 14C4257-n/a PANEL FOR TD 00 capacity and CAL-005 AFW PUMP host component capacity 18 TEPOlA Safety Injection RB 1998 0.53 lAnchorage 15C4353-TEPOlB,TEPOlC,and Accumulator Tank CAL-001 TEPOlD (Accumulators)
Wolf Creek Generating Station ESEP Final Report No. ID Description Bldg Elev HCLPF3 Failure Mode Basis Related Components (g, PGA) !Analyzed 19 ABPVOOOl Steam Generator A AB 2046 >RLGM Equipment 15C4353-ABPV0002 Atmospheric Dump Capacity CAL-001 (Steam Generator ARV) 20 AELT0539 Steam Generator RB 2026 >RLGM !Anchorage 15C4353-n/a Narrow Range CAL-001 Water Level Transmitter 21 BBHV8001 RCS Reactor Vessel RB 2047 >RLGM Equipment 15C4353-BBHV8002A A Head Vent A Capacity CAL-001 Upstream Valve (Reactor Head Vent) 22 EPHV8808 Accumulator Tank RB 1998 >RLGM Equipment 15C4353-EPHV8808B, A A Outlet Isolation Capacity CAL-001 EPHV8808C,and Valve EPHV8808D, (Accumulator Isolation Valves)
Enclosure IV to ET 16-0020 Section 9, "References" (2 Pages) ---------------------
Wolf Creek Generating Station ESEP Final Report 9.0 References 1. Letter from E. J. Leeds and M. R. Johnson, USN RC, to M. W. Sunseri, WCNOC, "Request for 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 of Insights from the Fukushima Dai-lchi Accident," March 12, 2012. ADAMS Accession No. M L12053A340. 2. Letter from E. J. Leeds, USN RC, to J. E. Pollock, NEI, "Electric Power Research Institute Final Draft Report XXXXXX, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations," May 7, 2013. 3002000704; ADAMS Accession No. ML13106A331. 3. WCNOC Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA-12-049 a. WCNOC Letter WO 13-0014, "Wolf Creek Nuclear Operating Corporation Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Design-Basis External Events (Order Number EA-12-049)," February 28, 2013. ADAMS Accession No. ML13070A026. b. WCNOC Letter ET 13-0027, "Wolf Creek Nuclear Operating Corporation's First Six-Month Status Report for the Implementation cif Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," August 28, 2013. ADAMS Accession No. ML13247A277. c. WCNOC Letter ET 14-0011, "Wolf Creek Nuclear Operating Corporation's Second Six-Month Status Report for the Implementation of Order EA-12-049, 'Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," February 26, 2014. ADAMS Accession No. ML14064A190. d. WCNOC Letter ET 14-0024, "Wolf Creek Nuclear Operating Corporation's Third Six-Month Status Report for the Implementation of Order EA-12-049, 'Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," August 28, 2014. ADAMS Accession No. ML14246A191. 4. SAP-15-78, Revision 1, "Transmittal of the Revised Expedited Seismic Equipment List (ESH) Update," October 2015. 5. S&A Report 14C4257-RPT-003 Rev. 0, "Wolf Creek ESEL Relay Assessment," December 2014. 6. WCNOC USAR, "Wolf Creek Updated Safety Analysis Report (USAR)," Revision 27, March 2014. 7. WCNOC Letter WO 14-0042, "Wolf Creek Nuclear Operating Corporation's Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," March 31, 2014. ADAMS Accession No. ML14097A020. 
---------------------Wolf Creek Generating Station ESEP Final Report 8. Electric Power Research Institute Report, NP-6041-SLRl, Revision 1, "A Methodology for Assessment of Nuclear Power Plant Seismic Margin," 1991. 9. Electric Power Research Institute Report, TR-103959, "Methodology for Developing Seismic Fragilities," 1994. 10. S&A Documents: a. 14C4257-CAL-001, Revision. 2, "Generation of Scaled In-Structure Response Spectra for WCGS," December 2014. b. 14C4257-CAL-002, Revision 0, "Seismic Capacity of CST (TAP01) and RWST (TBN01)," December 2014. c. 14C4257-CAL-003, Revision 0, "HCLPF Analyses for Block Walls," December 2014. d. 14C4257-CAL-004, Revision 0, "HCLPF Seismic Capacity Evaluations of Anchorage for Selected Equipment," December 2014. e. 14C4257-CAL-005, Revision 0, "HCLPF Analysis of Components Based on Seismic Test Data," December 2014. f. 14C4257-RPT-002, Revision 1, "Seismic Evaluation of Equipment at WCGS for the Expedited Seismic Evaluation Process," December 2014. g. 15C4353-CAL-001, Revision 1, "Screening and HCLPF Evaluations for ESEP Supplemental Items," January 2015. h. 15C4353-RPT-001, Revision 1, "Seismic Evaluation of ESEP Supplemental Items for WCGS," January 2015. 11. Wolf Creek Generating Station Individual Plant Examination of External Events (IPEEE), June 1995. 12. Electric Power Research Institute Report, NP-5223-SL, Revision 1, "Generic Seismic Ruggedness of Power Plant Equipment," 1991. 13. Electric Power Research Institute Technical Report, TR-1019200, "Seismic Fragility Applications Guide Update," 2009. 14. Letter from A. R. Pietrangelo, NEI, to E. J. Leeds, USN RC, "Seismic Risk Evaluations for Plants in the Central and Eastern United States," March 12, 2014. ADAMS Accession No. ML14083A584. 15. NRC (E Leeds) Letter to All Power Reactor Licensees et al., "Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(F) Regarding Seismic Hazard Re-Evaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights From the Fukushima Dai-lchi Accident," May 9, 2014. ADAMS Accession No. ML14111A147. 16. Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic. EPRI, Palo Alto, CA: February 2013. 1025287. 17. Letter from A. R. Pietrangelo, NEI, to D. L. Skeen, USN RC, "Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations," April 9, 2013. ADAMS Accession No. ML13107B386.
Enclosure V to ET 16-0020 Attachment B. ESEP HCLPF Values and Failure Modes Tabulation (21 Pages) 
.. Wolf Creek Generating Station ESEP Final Report Attachment B. ESEP HCLPF Values and Failure Modes Tabulation HCLPF values are listed in Table B-1. These notes are applicable: 1. The listed HCLPF value is for comparison to the horizontal PGA at the surface. 2. Items covered by the NP-6041-SL "rule of the box" (ROB) are identified in Table A-2 [9]. In each case, the HCLPF value for the parent item applies. 3. Where an anchorage HCLPF is performed but the component per se is screened, the equipment capacity is assigned based upon the 1.2g peak spectral acceleration coinciding with the 2nd screening lane of NP-6041-SL, Table 2-4. Since the WCGS RLGM has a peak spectral acceleration *of 0.93g and PGA of 0.29g [Reference lOe], the 1.2g peak spectral acceleration corresponds with a PGA of 0.38g (witness 1.2g/0.93g*0.29g=0.38g). For equipme.nt located above 40', the equipment capacity is conservatively assigned at the RLGM level of 0.29g. 4. For the CST and RWST only (TAPOl and TBNOl, respectively), the applied ground motion was based on the GMRS (PGA = 0.29). 5. As a result of the relay chatter evaluation, additional items were added to the ESEL list for evaluation.
Wolf Creek Generating Station ESEP Final Report Table B-1: HCLPF Values ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode Tank and anchorage capacity Condensate evaluated in 14C4257-CAL-1 TAPOl Storage VAR 2000-0.3 Equipment 002.Anchorage evaluated per D 00 Capacity 14C4257-CAL-004. Block wall Tank evaluated per 14C4257-CAL-003. TDAFW 2000-Equipment Component per se screened. 2 PAL02 AUX 0.38 Anchorage evaluated per Pump 00 Capacity 14C4257-CAL-004. 3 ALHV0034 MOV AUX 1988->RLGM Screened SRT disposition 00 4 ALHV0035 MOV AUX 1988->RLGM Screened SRT disposition 00 5 ALFE0049 Flow AUX 2000->RLGM Screened SRT disposition Element 00 Air 2004-6 ALHV0012 Operated AUX 07 >RLGM Screened SRT disposition Valve 7 ALFE0004 Flow AUX 2000->RLGM Screened SRT disposition Element 00 8 ALFT0004 Flow AUX 2016->RLGM Screened SRT disposition Transmitter 01 9 ALFTOOll Flow AUX 2000->RLGM Screened SRT disposition Transmitter 00 Air 2002-10 ALHVOOlO Operated AUX 09 >RLGM Screened SRT disposition Valve 11 ALFE0003 Flow AUX 2000->RLGM Screened SRT disposition Element 00 12 ALFT0003 Flow AUX 2016->RLGM Screened SRT disposition Transmitter 00 13 ALFT0009 Flow AUX 2000->RLGM Screened SRT disposition Transmitter 00 Air 2004-14 ALHV0008 Operated AUX 00 >RLGM Screened SRT disposition Valve ALFE0002 Flow AUX 2000->RLGM Screened SRT disposition 15 Element 00 ALFT0002 Flow AUX 2016->RLGM Screened SRT disposition 16 Transmitter 00 ALFT0007 Flow AUX 2000->RLGM Screened SRT disposition 17 Transmitter 00 Air 2001-18 ALHV0006 Operated AUX 06 >RLGM Screened SRT disposition Valve Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode 19 ALFEOOOl Flow AUX 2000->RLGM Screened SRT disposition Element 00 20 ALFTOOOl Flow AUX 2015->RLGM Screened SRT disposition Transmitter 00 Air 2027-21 ABHV0005 Operated AUX >RLGM Screened SRT disposition Valve 10 Air 2026-22 ABHV0048 Operated AUX 00 >RLGM Screened SRT disposition Valve Air 2027-23 ABHV0006 Operated AUX 10 >RLGM Screened SRT disposition Valve Air 2026-24 ABHV0049 Operated AUX 00 >RLGM Screened SRT disposition Valve Level 25 FCFV0310 Control >RLGM Screened SRT disposition Valve 26 FCLTOOlO Level >RLGM Screened SRT disposition Indicator Trip and 2000-27 FCHV0312 Throttle AUX 00 >RLGM Screened SRT disposition Valve Item is ROB to PAL02. 28 Speed Speed AUX 2000-0.38 Equipment Component per se screened. Governor Governor 00 Capacity Anchorage evaluated per 14C4257-CAL-004. Speed Item is ROB to PAL02. 29 FCFV0313 Governor AUX 2000-0.38 Equipment Component per se screened. Valve 00 Capacity Anchorage evaluated per 14C4257-CAL-004. Item is ROB to PAL02. 30 KFC02 AFW Pump AUX 2000-0.38 Equipment Component per se screened. Turbine 00 Capacity Anchorage evaluated per 14C4257-CAL-004. Boron 1974-31 TEMOl Injection AUX 00 >RLGM Screened SRT disposition Tank BIT Outlet 1974-32 EMPT0947 Pressure AUX 00 >RLGM Screened SRT disposition Transmitter BIT Outlet Item is ROB to RL018. 33 EMPI0947 Pressure CB 2047-0.29 Equipment Component per se screened. Indicator 06 Capacity Anchorage evaluated per 14C4257-CAL-004.
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode MOTOR-34 EMHV8801 OPERATED AUX 2002->RLGM Screened SRT disposition B VALVE 00 EMHV8801B ECCS FLOW 1998-35 EMFE0924 TO RCS RB 06 >RLGM Screened SRT disposition COLD-LEG 1 ECCS FLOW 1998-36 EMFE0925 TO RCS RB 06 >RLGM Screened SRT disposition COLD-LEG 2 ECCS FLOW 1998-37 EMFE0926 TO RCS . RB 06 >RLGM Screened SRT disposition COLD-LEG 3 ECCS FLOW 1998-38 EMFE0927 TO RCS RB 06 >RLGM Screened SRT disposition COLD-LEG 4 Tank and anchorage capacity 39 TBNOl RWST YRD 2000-0.32 Equipment evaluated in 14C4257-CAL-00 Capacity 002.Anchorage evaluated per 14C4257-CAL-004. 40 BNLT0930 RWST Level YRD 1993->RLGM Screened SRT disposition Transmitter 00 RHR PUMP 41 EJFCV0610 A AUX 1968->RLGM Screened SRT disposition MINI FLOW 01 VALVE 42 TBG03A Boric Acid AUX 1974->RLGM Screened SRT disposition Tank 00 43 BGLT0102 BORIC ACID CB 2047->RLGM Screened SRT disposition TANKA LEV 06 Item is ROB to RL002. BGLI0102 BORIC ACID CB 2047-0.29 Equipment Component per se screened. 44 TANKA LEV 06 Capacity Anchorage evaluated per 14C4257-CAL-004. 45 BBPV8702 RHR TO RCS RB 2007->RLGM Screened SRT disposition A 09 4.16KV Equipment capacity evaluated SWGR in 14C4257-CAL-005. 2000-Equipment Anchorage evaluated per 46 NBOOl NBOOl CB 0.36 (Class lE, 00 Capacity 14C4257-CAL-005. Block wall Train A) evaluated per 14C4257-CAL-003.
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode 4.16 kV FDR Item is ROB to NBOOl. BKR FOR Equipment capacity evaluated RH RP-A DPEJOlA 2000-Equipment in 14C4257-CAL-005. 47 NB00101 CB 0.36 Anchorage evaluated per (Residual 00 Capacity 14C4257-CAL-005. Block wall Heat evaluated per 14C4257-CAL-Removal Pump A) 003. 4.16 kV FDR Item is ROB to NBOOl. BKR FOR Equipment capacity evaluated CCWP-A DPEGOlA 2000-Equipment in 14C4257-CAL-005. 48 NB00107 CB 0.36 Anchorage evaluated per (Component 00 Capacity 14C4257-CAL-OOS. Block wall Cooling evaluated per 14C4257-CAL-Water Pump 003. A) 4.16 kV FDR Item is ROB to NBOOl. BKR FOR Equipment capacity evaluated XFMR 2000-Equipment in 14C4257-CAL-005. 49 NBOOllO XNG03 CB 0.36 Anchorage evaluated per (4160 Vto 00 Capacity 14C4257-CAL-OOS. Block wall 480 Vfor LC evaluated per 14C4257-CAL-NG003) 003. 4.16 kV FDR Item is ROB to NBOOl. BKR FOR Equipment capacity evaluated XFMR 2000-Equipment in 14C4257-CAL-005. so NB00113 XNGOl CB 0.36 Anchorage evaluated per (4160 Vto 00 Capacity 14C4257-CAL-OOS. Block wall 480 Vfor LC evaluated per 14C4257-CAL-NGOOl) 003. Item is ROB to NBOOl. 4.16 kV FLEX Equipment capacity evaluated GEN TIE-IN 2000-Equipment in 14C4257-CAL-005. 51 NB00109 CB 0.36 Anchorage evaluated per POINT (BKR) 00 Capacity 14C4257-CAL-OOS. Block wall FOR TRAIN A evaluated per 14C4257-CAL-003. 4.16-KV I 480 VLOAD CENTER CB/C 2000-Equipment Component per se screened. 52 XNGOl TRANS FOR c 00 0.38 Capacity Anchorage evaluated per MERXNGOl 14C425 7-CAL-004. FOR LC NGOOl 480 V LOAD Equipment capacity evaluated 53 NGOOl CENTER CB/C 2000-0.29 Equipment in 14C4257-CAL-OOS. NGOl c 00 Capacity Anchorage evaluated per 14C4257-CAL-005.
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode Item is ROB to NGOOl. MAIN BKR 2000-Equipment Equipment capacity evaluated 54 NG00101 FOR LC CB 0.29 in 14C4257-CAL-005. NGOl 00 Capacity Anchorage evaluated per 14C4257-CAL-005. FDR BKR Item is ROB to NGOOl. FOR 125 V Equipment capacity evaluated 55 NG00103 VITAL CB 2000-0.29 Equipment in 14C4257-CAL-005. BATTERY 00 Capacity Anchorage evaluated per CHARGER NK021 14C4257-CAL-005. Item is ROB to NGOOl. FLEX 350 kW 2000-Equipment Equipment capacity evaluated 56 NG00112 CB 0.29 in 14C4257-CAL-005. TIE IN BRK 00 Capacity Anchorage evaluated per 14C4257-CAL-005. Item is ROB to NGOOl. TIE BKR Equipment capacity evaluated 57 NG00116 (CONNECTS CB 2000-0.29 Equipment in 14C4257-CAL-005. NGOl AND 00 Capacity Anchorage evaluated per NG03) 14C4257-CAL-005. 4.16-KV/480 VLOAD CENTER CB/C 2000-Equipment Component per se screened. 58 XNG03 TRANS FOR c 00 0.38 Capacity Anchorage evaluated per MER XNG03 14C4257-CAL-004. FOR LC NG003 Equipment capacity evaluated 480V LOAD in 14C4257-CAL-005. 59 NG003 CENTER CB/C 2000-0.29 Equipment Anchorage evaluated per NG03 c 00 Capacity 14C4257-CAL-005. Block wall evaluated per 14C4257-CAL-003. Item is ROB to NG003. Equipment capacity evaluated MAIN BKR 2000-Equipment in 14C4257-CAL-005. 60 NG00301 FOR LC CB 0.29 Anchorage evaluated per NG03 00 Capacity 14C4257-CAL-005. Block wall evaluated per 14C4257-CAL-003. FDR BKR Item is ROB to NG003. FOR 125 V Equipment capacity evaluated VITAL 2000-Equipment in 14C4257-CAL-005. 61 NG00303 CB 0.29 Anchorage evaluated per BATTERY 00 Capacity 14C4257-CAL-005. Block wall CHARGER evaluated per 14C4257-CAL-NK023 003.
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode 125 v Component per se screened. BATTERY CB/C 2016-Equipment Anchorage evaluated per 62 NK021 0.38 14C4257-CAL-004. Block wall CHARGER c 00 Capacity evaluated per 14C4257-CAL-NK021 003. TRANSFER SWITCH BUS 63 NK071 NKOl CB/C 2016->RLGM Screened SRT disposition BATTERY c 00 CHARGER NK21/NK25 Equipment capacity evaluated 125 VDC in 14C4257-CAL-005. BUS CB/C 2016-0.32 Equipment Anchorage evaluated per 64 NKOOl SWITCH BOA c 00 Capacity 14C4257-CAL-005. Block wall RD NKOOl evaluated per 14C4257-CAL-003. Item is ROB to NKOOl. FDR BKR Equipment capacity evaluated FROM BATT CB/C 2016-Equipment in 14C4257-CAL-005. 65 NK00102 CHGR 0.32 Anchorage evaluated per NK021 TO c 00 Capacity 14C4257-CAL-005. Block wall NKOOl evaluated per 14C4257-CAL-003. MAIN Item is ROB to NKOOl. BREAKER Equipment capacity evaluated FOR CNTRL AND DIST CB/C 2016-Equipment in 14C4257-CAL-005. 66 NK00104 0.32 Anchorage evaluated per PNL NK041 c 00 Capacity 14C4257-CAL-005. Block wall (PART OF evaluated per 14C4257-CAL-SWBD NKOOl) 003. MAIN Item is ROB to NKOOl. BREAKER Equipment capacity evaluated FOR CNTRL AND DIST CB/C 2016-Equipment in 14C4257-CAL-005. 67 NK00105 0.32 Anchorage evaluated per PNL NK051 c 00 Capacity 14C4257-CAL-005. Block wall (PART OF evaluated per 14C4257-CAL-SWBD NKOOl) 003. Equipment capacity evaluated 125 v in 14C4257-CAL-005. 68 NKOll BATTERY CB/C 2016-0.44 Anchorage Anchorage evaluated per c 00 14C4257-CAL-004. Block wall NKOll evaluated per 14C4257-CAL-003.
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode Item is ROB to NKOOl. ISOLATION Equipment capacity evaluated BKR FOR CB/C 201G-Equipment in 14C4257-CAL-005. G9 NKOOlOl 0.32 Anchorage evaluated per BATTERY c 00 Capacity 14C4257-CAL-005. Block wall NKOll evaluated per 14C4257-CAL-003. FDR BKR Item is ROB to NKOOl.. FOR Equipment capacity evaluated INVERTER CB/C 201G-Equipment in 14C4257-CAL-005. 70 NKOOlll NNOll 0.32 Anchorage evaluated per {PART OF c 00 Capacity 14C4257-CAL-005. Block wall SWBD evaluated per 14C4257-CAL-NKOOl) 003. 7.SKVA Component per se screened. INVERTER (FED FROM CB/C 201G-Equipment Anchorage evaluated per 71 NNOll 0.38 14C4257-CAL-004. Block wall BATT c 00 Capacity evaluated per 14C4257-CAL-CHARGER NK021) 003. Class lE AC DISTSWBD CB/C 201G--72 NNOOl NNOl (SEP c 00 >RLGM Screened SRT disposition GRP 1) 73 SA03GA ESFAS CHl CB/C 2047->RLGM Screened SRT disposition TERM c 00 NEUTRON FLUX MONITORIN 202G-74 SENYOOGOA G SYSTEM AUX 00 >RLGM Screened SRT disposition DETECTOR AMPLIFIER SENY GOA NEUTRON FLUX MONITORIN 202G-75 SENYOOGOB G SYSTEM AUX 00 >RLGM Screened SRT disposition DETECTOR AMPLIFIER SENY GOB W SS PROT CB/C 2047-7G SB032A SYS INPUT >RLGM Screened SRT disposition TRN B c 00 W SS PROT CB/C 2047-77 SB029A SYS INPUT >RLGM Screened SRT disposition TRNA c OG Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode W PROCESS ANALOG CB/C 2047-78 SB038 PROTECTIO >RLGM Screened SRT disposition N SET CAB-c 06 01 W SS PROT CB/C 2047-79 SB029D SYS OUT 2 >RLGM Screened SRT disposition TRNA c 06 WNUC CB/C 2047-Equipment Component per se screened. 80 SE054A INSTM NIS 1 c 06 0.29 Capacity Anchorage evaluated per 14C4257-CAL-004. 81 SB030A SSPS TRNA CB 2047->RLGM Screened SRT disposition #1 TEST 06 BOP INSTRUMEN Component per se screened. TATION 2047-Equipment 82 RP053AC RACK CB 06 0.29 Capacity Anchorage evaluated per (TERM I NATI 14C425 7-CAL-004. ON AREA) RPV LEVEL INSTR SYS 2047-83 SB078 (RVLIS) CB 06 >RLGM Screened SRT disposition PROC PROT SYS CABINET T/C 84 RP081A SUBCOOLIN CB 2047->RLGM Screened SRT disposition G MONITOR 06 CABINET CNTRL & Equipment capacity evaluated INSTR DIST in 14C4257-CAL-005. 85 NK041 .SWBD CB/C 2016-0.32 Equipment Anchorage evaluated per NK041 c 00 Capacity 14C4257-CAL-005. Block wall (CLASS 1E evaluated per 14C4257-CAL-125 VDC) 003. TURBINE Component per se screened. GENERATOR 2047-Equipment 86 RL005 AND FW CB 06 0.29 Capacity Anchorage evaluated per CONSOLE 14C4257-CAL-004. TURBINE Component per se screened. GENERATOR 2047-Equipment 87 RL006 ANDFW CB 06 0.29 Capacity Anchorage evaluated per CONSOLE 14C4257-CAL-004. B AUXILIARY 2000-88 RP139 RELAY RACK CB 00 >RLGM Screened SRT disposition RP139 Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode CNTRL & INSTR DIST 89 NK051 SWBD CB/C 2016->RLGM Screened SRT disposition NK051 c 00 (CLASS lE 125 VDC) BBPCV0455 APORV 90 BBPCV0455 SOLENOID RB 2070->RLGM Screened SRT disposition A FAILS TO 00 OPEN ON DEMAND REACTOR 2047-Equipment Component per se screened. 91 RL021 AUX CNTRL CB 0.29 Anchorage evaluated per PANEL 06 Capacity 14C4257-CAL-004. REACTOR 2047-Equipment Component per se screened. 92 RL022 AUX CNTRL CB 06 0.29 Capacity Anchorage evaluated per PANEL 14C4257-CAL-004. 93 RP209 B AUXILIARY AUX 2000->RLGM Screened SRT disposition RELAY RACK 00 94 RP289 DC DIST PNL AUX 2047->RLGM Screened SRT disposition RP289 06 95 RP330 AUX RELAY AUX 2000->RLGM Screened SRT disposition RACK RP330 00 96 RP332 B AUXILIARY AUX 2000->RLGM Screened SRT disposition RELAY RACK 00 EM'CY LIGHTING 97 NK051A DISTSWBD CB/C 2016->RLGM Screened SRT disposition NK051A c 00 (SUBPNL OF NK051) 125 v Component per se screened. BATTERY CB/C 2016-Equipment Anchorage evaluated per 98 NK023 0.38 14C4257-CAL-004. Block wall CHARGER c 00 Capacity evaluated per 14C4257-CAL-NK023 003. \ TRANSFER SWITCH BUS 99 NK073 NK03 CB/C 2016->RLGM Screened SRT disposition BATTERY c 00 CHARGER NK23/NK25 Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode Equipment capacity evaluated 125 VDC in 14C4257-CAL-005. 100 NK003 BUS CB/C 2016-0.32 Equipment Anchorage evaluated per SWITCH BOA c 00 Capacity 14C4257-CAL-005. Block wall RD NK003 evaluated per 14C4257-CAL-003. Item is ROB to NK003. FDR BKR Equipment capacity evaluated FROM BATT CB/C 2016-Equipment in 14C4257-CAL-005. 101 NK00302 CHGR c 00 0.32 Capacity Anchorage evaluated per NK023 TO 14C4257-CAL-005. Block wall NK003 evaluated per 14C4257-CAL-003. MAIN Item is ROB to NK003. BREAKER Equipment capacity evaluated FOR CNTRL in 14C4257-CAL-005. NK00304 AND DIST CB/C 2016-0.32 Equipment Anchorage evaluated per 102 PNL NK043 c 00 Capacity 14C4257-CAL-005. Block wall (PART OF evaluated per 14C4257-CAL-SWBD NK003) 003. Equipment capacity evaluated in 14C4257-CAL-005. 125 v CB/C 2016-Anchorage evaluated per 103 NK013 BATTERY c 00 0.44 Anchorage 14C4257-CAL-004. Block wall NK013 evaluated per 14C4257-CAL-003. Item is ROB to NK003. ISOLATION Equipment capacity evaluated BKR FOR CB/C 2016-Equipment in 14C4257-CAL-005. 104 NK00301 BATTERY c 00 0.32 Capacity Anchorage evaluated per 14C4257-CAL-005. Block wall NK013 evaluated per 14C4257-CAL-003. FDR BKR Item is ROB to NK003. FOR Equipment capacity evaluated INVERTER CB/C 2016-Equipment in 14C4257-CAL-005. 105 NK00311 NN013 0.32 Anchorage evaluated per (PART OF c 00 Capacity 14C4257-CAL-005. Block wall SWBD evaluated per 14C4257-CAL-NK003) 003. 7.5KVA Component per se screened. INVERTER (FED FROM CB/C 2016-Equipment Anchorage evaluated per 106 NN013 0.38 14C4257-CAL-004. Block wall BATT c 00 Capacity evaluated per 14C4257-CAL-CHARGER NK023) 003.
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode Class lE AC 107 NN003 DISTSWBD CB/C 2016->RLGM Screened SRT disposition NN03 (SEP c 00 GRP 3) BOP INSTR 2047-Equipment Component per se screened. 108 RP053DB RACK CB 06 0.29 Capacity Anchorage evaluated per RP053DB 14C4257-CAL-004. W PROCESS ANALOG CB/C 2047-109 SB037 PROTECTIO >RLGM Screened SRT disposition N SET CAB-c 06 03 CNTRL & Equipment capacity evaluated INSTR DIST in 14C4257-CAL-005. 110 NK043 SWBD CB/C 2016-0.32 Equipment Anchorage evaluated per NK043 c 00 Capacity 14C4257-CAL-005. Block wall (CLASS lE evaluated per 14C4257-CAL-125 VDC) 003. AB007 Aux Relay CB 2026->RLGM Screened SRT disposition 111 Rack 00 FDR BKR Item is ROB to NGOOl. FOR 125 V Equipment capacity evaluated 112 NG00109 SWING CB 2000-0.29 Equipment in 14C4257-CAL-005. BATIE RY 00 Capacity Anchorage evaluated per CHARGER NK025 14C4257-CAL-005. 125 v BATIERY CHARGER CB/C 2000-Equipment Component per se screened. 113 NK025 NK025 0.38 Anchorage evaluated per (Swing c 00 Capacity 14C4257-CAL-004. Battery Charger) Equipment capacity evaluated 480 V LOAD in 14C4257-CAL-005. 114 NG002 CENTER CB 2000-0.29 Equipment Anchorage evaluated per NG02 00 Capacity 14C4257-CAL-005. Block wall evaluated per 14C4257-CAL-003. FLEX 500 kW Item is ROB to NG002. TIE IN BKR Equipment capacity evaluated from FD201 2000-Equipment in 14C4257-CAL-005. 115 NG00212 (Phase 2 CB 00 0.29 Capacity Anchorage evaluated per 14C4257-CAL-005. Block wall connection evaluated per 14C4257-CAL-point) 003.
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode FDR BKR Item is ROB to NG002. FOR 125 V Equipment capacity evaluated VITAL 2000-Equipment in 14C4257-CAL-005. 116 NG00203 CB 0.29 Anchorage evaluated per BATTERY 00 Capacity 14C4257-CAL-005. Block wall CHARGER evaluated per 14C4257-CAL-NK024 003. 125 v Component per se screened. BATTERY 2016-Equipment Anchorage evaluated per 117 NK024 CB 0.38 14C4257-CAL-004. Block wall CHARGER 00 Capacity evaluated per 14C4257-CAL-NK024 003. TRANSFER SWITCH BUS 118 NK074 NK04 CB 2016->RLGM Screened SRT disposition BATTERY 00 CHARGER NK24/NK26 Equipment capacity evaluated 125 VDC in 14C4257-CAL-005. 119 NK004 BUS CB 2016-0.32 Equipment Anchorage evaluated per SWITCH BOA 00 Capacity 14C4257-CAL-005. Block wall RD NK004 evaluated per 14C4257-CAL-003. Item is ROB to NK004. FDR BKR Equipment capacity evaluated FROM BATT 2016-Equipment in 14C4257-CAL-005. 120 NK00402 CHGR CB 0.32 Anchorage evaluated per NK024 TO 00 Capacity 14C4257-CAL-005. Block wall NK004 evaluated per 14C4257-CAL-003. Equipment capacity evaluated 125 v in 14C4257-CAL-005. 121 NK014 BATTERY CB 2016-0.44 Anchorage Anchorage evaluated per 00 14C4257-CAL-004. Block wall NK014 evaluated per 14C4257-CAL-003. Item is ROB to NK004. ISOLATION Equipment capacity evaluated BKR FOR 2016-Equipment in 14C4257-CAL-005. 122 NK00401 CB 0.32 Anchorage evaluated per BATTERY 00 Capacity 14C4257-CAL-005. Block wall NK014 evaluated per 14C4257-CAL-003.
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode FDR BKR Item is ROB to NK004. FOR Equipment capacity evaluated INVERTER 2016-Equipment in 14C4257-CAL-005. 123 NK00411 NN011 CB 0.32 Anchorage evaluated per (PART OF 00 Capacity 14C4257-CAL-005. Block wall SWBD evaluated per 14C4257-CAL-NK004) 003. 7.SKVA INVERTER Component per se screened. (FED FROM 2016-Equipment 124 NN014 BATI CB 00 0.38 Capacity Anchorage evaluated per CHARGER 14C4257-CAL-004. NK024) Class 1E AC 125 NN004 DISTSWBD CB 2016->RLGM Screened SRT disposition NN04 (SEP 00 GRP4) 126 SA036B ESFAS CH4 CB 2047->RLGM Screened SRT disposition TERM 06 BOP 127 RP147B lnstrumenta CB 2000->RLGM Screened SRT disposition tion Rack 00 RP147B NEUTRON FLUX MONITORIN 2047-128 SENY0061A G SYSTEM AUX 00 >RLGM Screened SRT disposition DETECTOR AMPLIFIER SENY 61A NEUTRON FLUX MONITORIN 2047-129 SENY0061B G SYSTEM AUX 00 >RLGM Screened SRT disposition DETECTOR AMPLIFIER SENY 61B WSSPS 2047-130 SB032D Train B #2 CB 06 >RLGM Screened SRT disposition Output 131 SB033A SSPS Train B CB 2047->RLGM Screened SRT disposition #1 Test 06 W PROCESS ANALOG 2047-132 SB041 PROTECTIO CB 06 >RLGM Screened SRT disposition N SET CAB-04 Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode BOP Component per se screened. 133 RP053BC lnstrumenta CB 2047-0.29 Equipment Anchorage evaluated per tion Rack 06 Capacity 14C4257-CAL-004. RP053BC RVLIS 134 SB079 Process CB 2047->RLGM Screened SRT disposition Cabinet 06 SB079 Subcooling 2047-135 RP081B Monitor CB >RLGM Screened SRT disposition Cabinet 06 W PROCESS 136 SB148B PROTECTIO CB 2000->RLGM Screened SRT disposition N (Fire 00 Isolation) See STATUS 2047-Note 5 SA066B INDICATING CB 06 >RLGM Screened SRT disposition SYS RHR PMP See PEJOlA 2002-Note 5 EJFIS0610 Miniflow AUX 00 >RLGM Screened SRT disposition Control Discharge LOCAL Equipment capacity evaluated CONTROL in 14C4257-CAL-005. See FC0219 PANEL FOR AUX 2002-0.61 Anchorage Anchorage evaluated per Note 5 TDAFW 00 14C4257-CAL-005. Relay PUMP functionality evaluated per 14C4257-CAL-005. Equipment capacity evaluated in 14C4257-CAL-005. Relay Anchorage evaluated per See MCC NG01A 2000-14C4257-CAL-005. Block wall Note 5 NG001A BUS CB 00 0.44 Functional-evaluated per 14C4257-CAL-ity 003. Relay functionality evaluated per 14C4257-CAL-005. Equipment capacity evaluated Relay in 14C4257-CAL-005. See NG002B MCC NG02B AUX 2026-0.44 Functional-Anchorage evaluated per Note 5 BUS 00 ity 14C4257-CAL-005. Relay functionality evaluated per 14C4257-CAL-005. Equipment capacity evaluated Relay in 14C4257-CAL-005. See MCC NG03C 2047-Anchorage evaluated per Note 5 NG003C BUS AUX 00 0.44 Functional-14C4257-CAL-005. Relay ity functionality evaluated per 14C4257-CAL-005.
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode Equipment capacity evaluated Relay in 14C4257-CAL-005. See MCC NG04C 2047-Anchorage evaluated per Note 5 NG004C BUS AUX 00 0.44 Functional-14C4257-CAL-005. Relay ity functionality evaluated per 14C4257-CAL-005. See RP334 LOCKOUT CB 2000->RLGM Screened SRT disposition Note 5 RELAY RACK 00 See ESFAS CH2 2047-Notes SA036C LOGIC/TER CB 06 >RLGM Screened SRT disposition M CABINET See W SS PROT 2047-Note 5 SB029C SYS OUT 1 CB 06 >RLGM Screened SRT disposition TRN Steam Generator A Pressure 2030-137 ABPT0514 Transmitter AUX 00 >RLGM Screened SRT disposition (Steam Generator Pressure) Steam Generator B Pressure 2029-138 ABPT0524 Transmitter AUX 10 >RLGM Screened SRT disposition (Steam Generator Pressure) Steam Generator C Pressure 2029-139 ABPT0534 Transmitter AUX 01 >RLGM Screened SRT disposition (Steam Generator Pressure) Steam Generator D Pressure 2029-140 ABPTOS44 Transmitter AUX 00 >RLGM Screened SRT disposition (Steam Generator Pressure) 
-------------------------------------------------Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode Steam Generator A Atmospheric Steam Valve functionality Dump 2046-141 ABPV0001 (Steam AUX 00 >RLGM Screened demonstrated to screen per Generator analysis in 1SC4353-CAL-001. Atmospheric Relief Valves) Steam Generator B Atmospheric Steam Valve functionality Dump 2042-142 ABPV0002 (Steam AUX 00 >RLGM Screened demonstrated to screen per Generator analysis in 15C4353-CAL-001. Atmospheric Relief Valves) Steam Generator B Narrow 143 AELT0529 Range Level RB 2026->RLGM Screened SRT disposition Transmitter 00 (Steam Generator Water Level) Steam Generator C Narrow Transmitter anchorage shown Range Level 2026-144 AELTOS39 Transmitter RB 00 >RLGM Screened to screen per analysis in (Steam 1SC4353-CAL-001. Generator Water Level) RCS Reactor Vessel Head BBHV8001 Vent A Valve functionality 145 Upstream RB 2047 >RLGM Screened demonstrated to screen per A Valve analysis in 15C4353-CAL-001. (Reactor -Head Vent)
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode RCS Reactor Vessel Head BBHV8002 Vent A Valve functionality 146 A Downstrea RB 2047 >RLGM Screened demonstrated to screen per m Valve analysis in 15C4353-CAL-001. (Reactor Head Vent) Pressurizer Power 147 BBPCV455 Operated RB 2070->RLGM Screened SRT disposition A Relief Valve 00 (Pressurizer PORV) RCS Pressurizer 148 BBPT0455 Pressure RB 2026->RLGM Screened SRT disposition Channel 1 00 (RCS Pressure) RCS LOOP 1 Wide Range Hot Leg Prat. A 2000-149 BBTE0413A Temperatur RB 00 >RLGM Screened SRT disposition e Element (RCS Temperatur e) RCS LOOP 1 Wide Range Cold Leg Prat. A 2000-150 BBTE0413B Temperatur RB 00 >RLGM Screened SRT disposition e Element (RCS Temperatur e) RCS LOOP 2 Wide Range Hot Leg Prat. A 2000-151 BBTE0423A Temperatur RB 00 >RLGM Screened SRT disposition e Element (RCS Temperatur e)
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode RCS LOOP 2 Wide Range Cold Leg Prot. A 2000-152 BBTE0423B Temperatur RB >RLGM Screened SRT disposition e Element 00 I (RCS Temperatur e) Accumulator TankA Outlet Valve functionality EPHV8808 Isolation 1998-153 A Valve RB 06 >RLGM Screened demonstrated to screen per (Accumulato analysis in 15C4353-CAL-001. r Isolation Valves) Accumulator Tank B Outlet Valve functionality Isolation 1998-154 EPHV8808B Valve RB 06 >RLGM Screened demonstrated to screen per (Accumulato analysis in 15C4353-CAL-001. r Isolation Valves) Accumulator Tank C Outlet Valve functionality Isolation 1998-155 EPHV8808C Valve RB 06 >RLGM Screened demonstrated to screen per (Accumulato analysis in 15C4353-CAL-001. r Isolation Valves) Accumulator Tank D Outlet Valve functionality EPHV8808 Isolation 1998-156 D Valve RB 06 >RLGM Screened demonstrated to screen per (Accumulato analysis in 15C4353-CAL-001. r Isolation Valves)
Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis Number (g, PGA) Mode Containmen t Atmospheric Pressure 2026-157 GNPT0936 Channel2 AUX 00 >RLGM Screened SRT disposition Pressure Transmitter (Contain me nt Pressure) Contain men t Atmospheric Pressure 2026-158 GNPT0937 Channell AUX 00 >RLGM Screened SRT disposition Pressure Transmitter (Contain me nt Pressure) Safety Injection 159 TEPOlA Accumulator RB 1998 0.53 Anchorage Tank and anchorage evaluated TankA Capacity per 15C4353-CAL-001. (Accumulato rs) Safety Injection 160 TEPOlB Accumulator RB 1998 0.53 Anchorage Tank and anchorage evaluated Tank B Capacity per 15C4353-CAL-001. (Accumulato rs) Safety Injection 161 TEPOlC Accumulator RB 1998 0.53 Anchorage Tank and anchorage evaluated Tank C Capacity per 15C4353-CAL-001. (Accumulato rs) Safety Injection 162 TEPOlD Accumulator RB 1998 0.53 Anchorage Tank and anchorage evaluated Tank D Capacity per 15C4353-CAL-001. (Accumulato rs)
Enclosure VI to ET 16-0020 Attachment C. Seismic Review Team (1 Page)
Wolf Creek Generating Station ESEP Final Report Attachment C. Seismic Review Team The Seismic Review Team (SRT) consisted of seismic engineers from Stevenson & Associates (S&A). Brief resumes for team members are provided below. Apostolos Karavoussianis Mr. Karavoussianis is a senior consultant in the S&A Phoenix office. He has performed seismic walkdowns of structures and components at numerous facilities for the GIP A-46 and IPEEE programs. Mr. Karavoussianis has also managed, led, or participated in several seismic walkdown initiatives associated with NTTF Recommendation 2.1 and NTTF Recommendation 2.3. He has also prepared, reviewed, and approved seismic evaluations for electrical and mechanical equipment. Mr. Karavoussianis is a qualified Seismic Capable Engineer (SCE) and has completed the Seismic Qualification Utility Group (SQUG) Walkdown Screening and Seismic Evaluation Training Course. Hunter A. Young, P.E. Mr. Young is a Senior Engineer and qualified SCE in the S&A Phoenix office with specialization in structural dynamic analysis of structures and equipment for natural and man-made phenomena hazards. He has managed, led, or participated in over 20 seismic walkdown initiatives associated with NTTF Recommendation 2.1 (including WCGS), NTTF Recommendation 2.3 (including WCGS), EPRI NP-6695, and various
* S-PRA fragility endeavors. Mr. Young has a Master of Engineering in Structural Engineering from the Massachusetts Institute of Technology and Bachelors of Science in Civil Engineering (BSCE) from the University of Notre Dame. He is a licensed P.E. (civil) in California, Kansas, and Missouri and has completed the SQUG Walkdown Screening and Seismic Evaluation Training Course. 
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