ML16327A604

Operating Corp. - Supplement to the Expedited Seismic Evaluation Process Report

ML16327A604
Person / Time
Site:	Wolf Creek
Issue date:	11/17/2016
From:	Mccoy J Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ET 16-0020
Download: ML16327A604 (42)

Text

W$LFCREEK 'NUCLEAR OPERATING CORPORATION Jaime H. McCoy Vice President Engineering 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"

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"

Subject:

Docket No. 50-482: Supplement to the Expedited Seismic Evaluation Process Report Gentlemen:

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 An Equal Opportunity Employer M/F/HC/VET A lV f(

(I (\.

{JJ 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.

By~~--'--~~--=~~~=.::~~~~

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 '1JJ..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 1

No. ID Description Bldg Elev HCLPF 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 2

No. ID Description Bldg Elev HCLPF 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- ~NG03 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 3

No. ID Description Bldg Elev HCLPF 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 Beyond-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.

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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 (g, PGA) Mode Number Tank and anchorage capacity evaluated in 14C4257-CAL-Condensate VAR 2000- Equipment 002.Anchorage evaluated per 1 TAPOl Storage 0.3 D 00 Capacity 14C4257-CAL-004. Block wall Tank evaluated per 14C4257-CAL-003.

Component per se screened.

TDAFW 2000- Equipment 2 PAL02 AUX 0.38 Anchorage evaluated per Pump 00 Capacity 14C4257-CAL-004.

1988-3 ALHV0034 MOV AUX >RLGM Screened SRT disposition 00 1988-4 ALHV0035 MOV AUX >RLGM Screened SRT disposition 00 Flow 2000-5 ALFE0049 AUX >RLGM Screened SRT disposition Element 00 Air 2004-6 ALHV0012 Operated AUX >RLGM Screened SRT disposition 07 Valve Flow 2000-7 ALFE0004 AUX >RLGM Screened SRT disposition Element 00 Flow 2016-8 ALFT0004 AUX >RLGM Screened SRT disposition Transmitter 01 Flow 2000-9 ALFTOOll AUX >RLGM Screened SRT disposition Transmitter 00 Air 2002-10 ALHVOOlO Operated AUX >RLGM Screened SRT disposition 09 Valve Flow 2000-11 ALFE0003 AUX >RLGM Screened SRT disposition Element 00 Flow 2016-12 ALFT0003 AUX >RLGM Screened SRT disposition Transmitter 00 Flow 2000-13 ALFT0009 AUX >RLGM Screened SRT disposition Transmitter 00 Air 2004-14 ALHV0008 Operated AUX >RLGM Screened SRT disposition 00 Valve Flow 2000-15 ALFE0002 AUX >RLGM Screened SRT disposition Element 00 Flow 2016-16 ALFT0002 AUX >RLGM Screened SRT disposition Transmitter 00 Flow 2000-17 ALFT0007 AUX >RLGM Screened SRT disposition Transmitter 00 Air 2001-18 ALHV0006 Operated AUX >RLGM Screened SRT disposition 06 Valve

Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis (g, PGA) Mode Number Flow 2000-19 ALFEOOOl AUX >RLGM Screened SRT disposition Element 00 Flow 2015-20 ALFTOOOl AUX >RLGM Screened SRT disposition Transmitter 00 Air 2027-21 ABHV0005 Operated AUX >RLGM Screened SRT disposition 10 Valve Air 2026-22 ABHV0048 Operated AUX >RLGM Screened SRT disposition 00 Valve Air 2027-23 ABHV0006 Operated AUX >RLGM Screened SRT disposition 10 Valve Air 2026-24 ABHV0049 Operated AUX >RLGM Screened SRT disposition 00 Valve Level 25 FCFV0310 Control >RLGM Screened SRT disposition Valve Level 26 FCLTOOlO >RLGM Screened SRT disposition Indicator Trip and 2000-27 FCHV0312 Throttle AUX >RLGM Screened SRT disposition 00 Valve Item is ROB to PAL02.

Speed Speed 2000- Equipment Component per se screened.

28 AUX 0.38 Governor Governor 00 Capacity Anchorage evaluated per 14C4257-CAL-004.

Item is ROB to PAL02.

Speed 2000- Equipment Component per se screened.

29 FCFV0313 Governor AUX 0.38 00 Capacity Anchorage evaluated per Valve 14C4257-CAL-004.

Item is ROB to PAL02.

AFW Pump 2000- Equipment Component per se screened.

30 KFC02 AUX 0.38 Turbine 00 Capacity Anchorage evaluated per 14C4257-CAL-004.

Boron 1974-31 TEMOl Injection AUX >RLGM Screened SRT disposition 00 Tank BIT Outlet 1974-32 EMPT0947 Pressure AUX >RLGM Screened SRT disposition 00 Transmitter Item is ROB to RL018.

BIT Outlet 2047- Equipment Component per se screened.

33 EMPI0947 Pressure CB 0.29 06 Capacity Anchorage evaluated per Indicator 14C4257-CAL-004.

Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis (g, PGA) Mode Number MOTOR-EMHV8801 OPERATED 2002-34 AUX >RLGM Screened SRT disposition B VALVE 00 EMHV8801B ECCS FLOW 1998-35 EMFE0924 TO RCS RB >RLGM Screened SRT disposition 06 COLD-LEG 1 ECCS FLOW 1998-36 EMFE0925 TO RCS RB >RLGM Screened SRT disposition 06 COLD-LEG 2 ECCS FLOW 1998-37 EMFE0926 TO RCS . RB >RLGM Screened SRT disposition 06 COLD-LEG 3 ECCS FLOW 1998-38 EMFE0927 TO RCS RB >RLGM Screened SRT disposition 06 COLD-LEG 4 Tank and anchorage capacity 2000- Equipment evaluated in 14C4257-CAL-39 TBNOl RWST YRD 0.32 00 Capacity 002.Anchorage evaluated per 14C4257-CAL-004.

RWST Level 1993-40 BNLT0930 YRD >RLGM Screened SRT disposition Transmitter 00 RHR PUMP A 1968-41 EJFCV0610 AUX >RLGM Screened SRT disposition MINI FLOW 01 VALVE Boric Acid 1974-42 TBG03A AUX >RLGM Screened SRT disposition Tank 00 BORIC ACID 2047-43 BGLT0102 CB >RLGM Screened SRT disposition TANKA LEV 06 Item is ROB to RL002.

BORIC ACID 2047- Equipment Component per se screened.

44 BGLI0102 CB 0.29 TANKA LEV 06 Capacity Anchorage evaluated per 14C4257-CAL-004.

BBPV8702 2007-45 RHR TO RCS RB >RLGM Screened SRT disposition A 09 Equipment capacity evaluated 4.16KV in 14C4257-CAL-005.

SWGR 2000- Equipment Anchorage evaluated per 46 NBOOl NBOOl CB 0.36 00 Capacity 14C4257-CAL-005. Block wall (Class lE, evaluated per 14C4257-CAL-Train A) 003.

Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis (g, PGA) Mode Number 4.16 kV FDR Item is ROB to NBOOl.

BKR FOR Equipment capacity evaluated RH RP-A in 14C4257-CAL-005.

DPEJOlA 2000- Equipment 47 NB00101 CB 0.36 Anchorage evaluated per (Residual 00 Capacity 14C4257-CAL-005. Block wall Heat evaluated per 14C4257-CAL-Removal 003.

Pump A) 4.16 kV FDR Item is ROB to NBOOl.

BKR FOR Equipment capacity evaluated CCWP-A in 14C4257-CAL-005.

DPEGOlA 2000- Equipment 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 in 14C4257-CAL-005.

2000- Equipment 49 NBOOllO XNG03 CB 0.36 Anchorage evaluated per 00 Capacity (4160 Vto 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 in 14C4257-CAL-005.

2000- Equipment so NB00113 XNGOl CB 0.36 Anchorage evaluated per 00 Capacity (4160 Vto 14C4257-CAL-OOS. Block wall 480 Vfor LC evaluated per 14C4257-CAL-NGOOl) 003.

Item is ROB to NBOOl.

Equipment capacity evaluated 4.16 kV FLEX in 14C4257-CAL-005.

GEN TIE-IN 2000- Equipment 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-KVI 480 VLOAD CENTER Component per se screened.

CB/C 2000- Equipment 52 XNGOl TRANS FOR 0.38 Anchorage evaluated per MERXNGOl c 00 Capacity 14C425 7-CAL-004.

FOR LC NGOOl Equipment capacity evaluated 480 V LOAD CB/C 2000- Equipment in 14C4257-CAL-OOS.

53 NGOOl CENTER 0.29 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 (g, PGA) Mode Number Item is ROB to NGOOl.

MAIN BKR Equipment capacity evaluated 2000- Equipment 54 NG00101 FOR LC CB 0.29 in 14C4257-CAL-005.

00 Capacity NGOl Anchorage evaluated per 14C4257-CAL-005.

FDR BKR Item is ROB to NGOOl.

FOR 125 V Equipment capacity evaluated VITAL 2000- Equipment 55 NG00103 CB 0.29 in 14C4257-CAL-005.

BATTERY 00 Capacity Anchorage evaluated per CHARGER 14C4257-CAL-005.

NK021 Item is ROB to NGOOl.

Equipment capacity evaluated FLEX 350 kW 2000- Equipment 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 (CONNECTS 2000- Equipment 57 NG00116 CB 0.29 in 14C4257-CAL-005.

NGOl AND 00 Capacity Anchorage evaluated per NG03) 14C4257-CAL-005.

4.16-KV/480 VLOAD CENTER Component per se screened.

CB/C 2000- Equipment 58 XNG03 TRANS FOR 0.38 Anchorage evaluated per MER XNG03 c 00 Capacity 14C4257-CAL-004.

FOR LC NG003 Equipment capacity evaluated in 14C4257-CAL-005.

480V LOAD CB/C 2000- Equipment Anchorage evaluated per 59 NG003 CENTER 0.29 NG03 c 00 Capacity 14C4257-CAL-005. Block wall evaluated per 14C4257-CAL-003.

Item is ROB to NG003.

Equipment capacity evaluated MAIN BKR in 14C4257-CAL-005.

2000- Equipment 60 NG00301 FOR LC CB 0.29 Anchorage evaluated per 00 Capacity NG03 14C4257-CAL-005. Block wall evaluated per 14C4257-CAL-003.

Item is ROB to NG003.

FDR BKR Equipment capacity evaluated FOR 125 V in 14C4257-CAL-005.

VITAL 2000- Equipment 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 (g, PGA) Mode Number Component per se screened.

125 v Anchorage evaluated per BATTERY CB/C 2016- Equipment 62 NK021 0.38 14C4257-CAL-004. Block wall CHARGER c 00 Capacity evaluated per 14C4257-CAL-NK021 003.

TRANSFER SWITCH BUS NKOl CB/C 2016-63 NK071 >RLGM Screened SRT disposition BATTERY c 00 CHARGER NK21/NK25 Equipment capacity evaluated 125 VDC in 14C4257-CAL-005.

BUS CB/C 2016- Equipment Anchorage evaluated per 64 NKOOl 0.32 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 in 14C4257-CAL-005.

CB/C 2016- Equipment 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 in 14C4257-CAL-005.

AND DIST CB/C 2016- Equipment 66 NK00104 0.32 Anchorage evaluated per PNL NK041 c 00 Capacity 14C4257-CAL-005. Block wall (PART OF evaluated per 14C4257-CAL-SWBD 003.

NKOOl)

MAIN Item is ROB to NKOOl.

BREAKER Equipment capacity evaluated FOR CNTRL in 14C4257-CAL-005.

AND DIST CB/C 2016- Equipment 67 NK00105 0.32 Anchorage evaluated per PNL NK051 c 00 Capacity 14C4257-CAL-005. Block wall (PART OF evaluated per 14C4257-CAL-SWBD 003.

NKOOl)

Equipment capacity evaluated in 14C4257-CAL-005.

125 v CB/C 2016- Anchorage evaluated per 68 NKOll BATTERY 0.44 Anchorage NKOll c 00 14C4257-CAL-004. Block wall evaluated per 14C4257-CAL-003.

Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis (g, PGA) Mode Number Item is ROB to NKOOl.

Equipment capacity evaluated ISOLATION in 14C4257-CAL-005.

BKR FOR CB/C 201G- Equipment 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 in 14C4257-CAL-005.

CB/C 201G- Equipment 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 Anchorage evaluated per (FED FROM CB/C 201G- Equipment 71 NNOll 0.38 14C4257-CAL-004. Block wall BATT c 00 Capacity evaluated per 14C4257-CAL-CHARGER 003.

NK021)

Class lE AC

-

DISTSWBD CB/C 201G-72 NNOOl >RLGM Screened SRT disposition NNOl (SEP c 00 GRP 1)

ESFAS CHl CB/C 2047-73 SA03GA >RLGM Screened SRT disposition TERM c 00 NEUTRON FLUX MONITORIN 202G-74 SENYOOGOA G SYSTEM AUX >RLGM Screened SRT disposition 00 DETECTOR AMPLIFIER SENY GOA NEUTRON FLUX MONITORIN 202G-75 SENYOOGOB G SYSTEM AUX >RLGM Screened SRT disposition 00 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 (g, PGA) Mode Number 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 Component per se screened.

WNUC CB/C 2047- Equipment 80 SE054A 0.29 Anchorage evaluated per INSTM NIS 1 c 06 Capacity 14C4257-CAL-004.

SSPS TRNA 2047-81 SB030A CB >RLGM Screened SRT disposition

1. 1 TEST 06 BOP INSTRUMEN Component per se screened.

TATION 2047- Equipment 82 RP053AC CB 0.29 Anchorage evaluated per RACK 06 Capacity 14C425 7-CAL-004.

(TERM I NATI ON AREA)

RPV LEVEL INSTR SYS 2047-83 SB078 (RVLIS) CB >RLGM Screened SRT disposition 06 PROC PROT SYS CABINET T/C SUBCOOLIN 2047-84 RP081A CB >RLGM Screened SRT disposition G MONITOR 06 CABINET CNTRL & Equipment capacity evaluated INSTR DIST in 14C4257-CAL-005.

.SWBD CB/C 2016- Equipment Anchorage evaluated per 85 NK041 0.32 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 CB 0.29 Anchorage evaluated per AND FW 06 Capacity 14C4257-CAL-004.

CONSOLE TURBINE Component per se screened.

GENERATOR 2047- Equipment 87 RL006 CB 0.29 Anchorage evaluated per ANDFW 06 Capacity 14C4257-CAL-004.

CONSOLE B AUXILIARY 2000-88 RP139 RELAY RACK CB >RLGM Screened SRT disposition 00 RP139

Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis (g, PGA) Mode Number CNTRL &

INSTR DIST SWBD CB/C 2016-89 NK051 >RLGM Screened SRT disposition NK051 c 00 (CLASS lE 125 VDC)

BBPCV0455 APORV BBPCV0455 SOLENOID 2070-90 RB >RLGM Screened SRT disposition A FAILS TO 00 OPEN ON DEMAND REACTOR Component per se screened.

2047- Equipment 91 RL021 AUX CNTRL CB 0.29 Anchorage evaluated per 06 Capacity PANEL 14C4257-CAL-004.

REACTOR Component per se screened.

2047- Equipment 92 RL022 AUX CNTRL CB 0.29 Anchorage evaluated per 06 Capacity PANEL 14C4257-CAL-004.

B AUXILIARY 2000-93 RP209 AUX >RLGM Screened SRT disposition RELAY RACK 00 DC DIST PNL 2047-94 RP289 AUX >RLGM Screened SRT disposition RP289 06 AUX RELAY 2000-95 RP330 AUX >RLGM Screened SRT disposition RACK RP330 00 B AUXILIARY 2000-96 RP332 AUX >RLGM Screened SRT disposition RELAY RACK 00 EM'CY LIGHTING DISTSWBD CB/C 2016-97 NK051A >RLGM Screened SRT disposition NK051A c 00 (SUBPNL OF NK051)

Component per se screened.

125 v Anchorage evaluated per BATTERY CB/C 2016- Equipment 98 NK023 0.38 14C4257-CAL-004. Block wall CHARGER c 00 Capacity evaluated per 14C4257-CAL-NK023 003.

\

TRANSFER SWITCH BUS NK03 CB/C 2016-99 NK073 >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 (g, PGA) Mode Number Equipment capacity evaluated 125 VDC in 14C4257-CAL-005.

BUS CB/C 2016- Equipment Anchorage evaluated per 100 NK003 0.32 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 in 14C4257-CAL-005.

CB/C 2016- Equipment 101 NK00302 CHGR 0.32 Anchorage evaluated per NK023 TO c 00 Capacity 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.

AND DIST CB/C 2016- Equipment 102 NK00304 0.32 Anchorage evaluated per PNL NK043 c 00 Capacity 14C4257-CAL-005. Block wall (PART OF evaluated per 14C4257-CAL-SWBD 003.

NK003)

Equipment capacity evaluated in 14C4257-CAL-005.

125 v CB/C 2016- Anchorage evaluated per 103 NK013 BATTERY 0.44 Anchorage NK013 c 00 14C4257-CAL-004. Block wall evaluated per 14C4257-CAL-003.

Item is ROB to NK003.

Equipment capacity evaluated ISOLATION in 14C4257-CAL-005.

BKR FOR CB/C 2016- Equipment 104 NK00301 0.32 Anchorage evaluated per BATTERY c 00 Capacity 14C4257-CAL-005. Block wall NK013 evaluated per 14C4257-CAL-003.

FDR BKR Item is ROB to NK003.

FOR Equipment capacity evaluated INVERTER in 14C4257-CAL-005.

CB/C 2016- Equipment 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 Anchorage evaluated per (FED FROM CB/C 2016- Equipment 106 NN013 0.38 14C4257-CAL-004. Block wall BATT c 00 Capacity evaluated per 14C4257-CAL-CHARGER 003.

NK023)

Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis (g, PGA) Mode Number Class lE AC DISTSWBD CB/C 2016-107 NN003 >RLGM Screened SRT disposition NN03 (SEP c 00 GRP 3)

BOP INSTR Component per se screened.

2047- Equipment 108 RP053DB RACK CB 0.29 Anchorage evaluated per 06 Capacity 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.

SWBD CB/C 2016- Equipment Anchorage evaluated per 110 NK043 0.32 NK043 c 00 Capacity 14C4257-CAL-005. Block wall (CLASS lE evaluated per 14C4257-CAL-125 VDC) 003.

Aux Relay 2026-111 AB007 CB >RLGM Screened SRT disposition Rack 00 FDR BKR Item is ROB to NGOOl.

FOR 125 V Equipment capacity evaluated SWING 2000- Equipment 112 NG00109 CB 0.29 in 14C4257-CAL-005.

BATIE RY 00 Capacity Anchorage evaluated per CHARGER 14C4257-CAL-005.

NK025 125 v BATIERY CHARGER Component per se screened.

CB/C 2000- Equipment 113 NK025 NK025 0.38 Anchorage evaluated per (Swing c 00 Capacity 14C4257-CAL-004.

Battery Charger)

Equipment capacity evaluated in 14C4257-CAL-005.

480 V LOAD 2000- Equipment Anchorage evaluated per 114 NG002 CENTER CB 0.29 00 Capacity 14C4257-CAL-005. Block wall NG02 evaluated per 14C4257-CAL-003.

Item is ROB to NG002.

FLEX 500 kW Equipment capacity evaluated TIE IN BKR in 14C4257-CAL-005.

from FD201 2000- Equipment 115 NG00212 CB 0.29 Anchorage evaluated per (Phase 2 00 Capacity 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 (g, PGA) Mode Number Item is ROB to NG002.

FDR BKR Equipment capacity evaluated FOR 125 V in 14C4257-CAL-005.

VITAL 2000- Equipment 116 NG00203 CB 0.29 Anchorage evaluated per BATTERY 00 Capacity 14C4257-CAL-005. Block wall CHARGER evaluated per 14C4257-CAL-NK024 003.

Component per se screened.

125 v Anchorage evaluated per BATTERY 2016- Equipment 117 NK024 CB 0.38 14C4257-CAL-004. Block wall CHARGER 00 Capacity evaluated per 14C4257-CAL-NK024 003.

TRANSFER SWITCH BUS NK04 2016-118 NK074 CB >RLGM Screened SRT disposition BATTERY 00 CHARGER NK24/NK26 Equipment capacity evaluated 125 VDC in 14C4257-CAL-005.

BUS 2016- Equipment Anchorage evaluated per 119 NK004 CB 0.32 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 in 14C4257-CAL-005.

2016- Equipment 120 NK00402 CHGR CB 0.32 Anchorage evaluated per 00 Capacity NK024 TO 14C4257-CAL-005. Block wall NK004 evaluated per 14C4257-CAL-003.

Equipment capacity evaluated in 14C4257-CAL-005.

125 v 2016- Anchorage evaluated per 121 NK014 BATTERY CB 0.44 Anchorage 00 14C4257-CAL-004. Block wall NK014 evaluated per 14C4257-CAL-003.

Item is ROB to NK004.

Equipment capacity evaluated ISOLATION in 14C4257-CAL-005.

BKR FOR 2016- Equipment 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 (g, PGA) Mode Number FDR BKR Item is ROB to NK004.

FOR Equipment capacity evaluated INVERTER in 14C4257-CAL-005.

2016- Equipment 123 NK00411 NN011 CB 0.32 Anchorage evaluated per 00 Capacity (PART OF 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 CB 0.38 Anchorage evaluated per BATI 00 Capacity 14C4257-CAL-004.

CHARGER NK024)

Class 1E AC DISTSWBD 2016-125 NN004 CB >RLGM Screened SRT disposition NN04 (SEP 00 GRP4)

ESFAS CH4 2047-126 SA036B CB >RLGM Screened SRT disposition TERM 06 BOP lnstrumenta 2000-127 RP147B CB >RLGM Screened SRT disposition tion Rack 00 RP147B NEUTRON FLUX MONITORIN 2047-128 SENY0061A G SYSTEM AUX >RLGM Screened SRT disposition 00 DETECTOR AMPLIFIER SENY 61A NEUTRON FLUX MONITORIN 2047-129 SENY0061B G SYSTEM AUX >RLGM Screened SRT disposition 00 DETECTOR AMPLIFIER SENY 61B WSSPS 2047-130 SB032D Train B #2 CB >RLGM Screened SRT disposition 06 Output SSPS Train B 2047-131 SB033A CB >RLGM Screened SRT disposition

1. 1 Test 06 W PROCESS ANALOG 2047-132 SB041 PROTECTIO CB >RLGM Screened SRT disposition 06 N SET CAB-04

Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis (g, PGA) Mode Number BOP Component per se screened.

lnstrumenta 2047- Equipment 133 RP053BC CB 0.29 Anchorage evaluated per tion Rack 06 Capacity 14C4257-CAL-004.

RP053BC RVLIS Process 2047-134 SB079 CB >RLGM Screened SRT disposition Cabinet 06 SB079 Subcooling 2047-135 RP081B Monitor CB >RLGM Screened SRT disposition 06 Cabinet W PROCESS PROTECTIO 2000-136 SB148B CB >RLGM Screened SRT disposition N (Fire 00 Isolation)

STATUS See 2047-SA066B INDICATING CB >RLGM Screened SRT disposition Note 5 06 SYS RHR PMP PEJOlA See 2002-EJFIS0610 Miniflow AUX >RLGM Screened SRT disposition Note 5 00 Control Discharge Equipment capacity evaluated LOCAL in 14C4257-CAL-005.

CONTROL See 2002- Anchorage evaluated per FC0219 PANEL FOR AUX 0.61 Anchorage Note 5 00 14C4257-CAL-005. Relay TDAFW functionality evaluated per PUMP 14C4257-CAL-005.

Equipment capacity evaluated in 14C4257-CAL-005.

Anchorage evaluated per Relay See MCC NG01A 2000- 14C4257-CAL-005. Block wall NG001A CB 0.44 Functional-Note 5 BUS 00 evaluated per 14C4257-CAL-ity 003. Relay functionality evaluated per 14C4257-CAL-005.

Equipment capacity evaluated in 14C4257-CAL-005.

Relay See MCC NG02B 2026- Anchorage evaluated per NG002B AUX 0.44 Functional-Note 5 BUS 00 14C4257-CAL-005. Relay ity functionality evaluated per 14C4257-CAL-005.

Equipment capacity evaluated in 14C4257-CAL-005.

Relay See MCC NG03C 2047- Anchorage evaluated per NG003C AUX 0.44 Functional-Note 5 BUS 00 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 (g, PGA) Mode Number Equipment capacity evaluated in 14C4257-CAL-005.

Relay See MCC NG04C 2047- Anchorage evaluated per NG004C AUX 0.44 Functional-Note 5 BUS 00 14C4257-CAL-005. Relay ity functionality evaluated per 14C4257-CAL-005.

See LOCKOUT 2000-RP334 CB >RLGM Screened SRT disposition Note 5 RELAY RACK 00 ESFAS CH2 See 2047-SA036C LOGIC/TER CB >RLGM Screened SRT disposition Notes 06 M CABINET W SS PROT See 2047-SB029C SYS OUT 1 CB >RLGM Screened SRT disposition Note 5 06 TRN Steam Generator A Pressure 2030-137 ABPT0514 Transmitter AUX >RLGM Screened SRT disposition 00 (Steam Generator Pressure)

Steam Generator B Pressure 2029-138 ABPT0524 Transmitter AUX >RLGM Screened SRT disposition 10 (Steam Generator Pressure)

Steam Generator C Pressure 2029-139 ABPT0534 Transmitter AUX >RLGM Screened SRT disposition 01 (Steam Generator Pressure)

Steam Generator D Pressure 2029-140 ABPTOS44 Transmitter AUX >RLGM Screened SRT disposition 00 (Steam Generator Pressure)

~~-

Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis (g, PGA) Mode Number Steam Generator A Atmospheric Steam Valve functionality Dump 2046-141 ABPV0001 AUX >RLGM Screened demonstrated to screen per (Steam 00 analysis in 1SC4353-CAL-001.

Generator Atmospheric Relief Valves)

Steam Generator B Atmospheric Steam Valve functionality Dump 2042-142 ABPV0002 AUX >RLGM Screened demonstrated to screen per (Steam 00 analysis in 15C4353-CAL-001.

Generator Atmospheric Relief Valves)

Steam Generator B Narrow Range Level 2026-143 AELT0529 RB >RLGM Screened SRT disposition Transmitter 00 (Steam Generator Water Level)

Steam Generator C Narrow Transmitter anchorage shown Range Level 2026-144 AELTOS39 RB >RLGM Screened to screen per analysis in Transmitter 00 1SC4353-CAL-001.

(Steam Generator Water Level)

RCS Reactor Vessel Head Vent A Valve functionality BBHV8001 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 (g, PGA) Mode Number RCS Reactor Vessel Head Vent A Valve functionality BBHV8002 146 Downstrea RB 2047 >RLGM Screened demonstrated to screen per A

m Valve analysis in 15C4353-CAL-001.

(Reactor Head Vent)

Pressurizer Power BBPCV455 Operated 2070-147 RB >RLGM Screened SRT disposition A Relief Valve 00 (Pressurizer PORV)

RCS Pressurizer Pressure 2026-148 BBPT0455 RB >RLGM Screened SRT disposition Channel 1 00 (RCS Pressure)

RCS LOOP 1 Wide Range Hot Leg Prat. A 2000-149 BBTE0413A Temperatur RB >RLGM Screened SRT disposition 00 e Element (RCS Temperatur e)

RCS LOOP 1 Wide Range Cold Leg Prat. A 2000-150 BBTE0413B Temperatur RB >RLGM Screened SRT disposition 00 e Element (RCS Temperatur e)

RCS LOOP 2 Wide Range Hot Leg Prat. A 2000-151 BBTE0423A Temperatur RB >RLGM Screened SRT disposition 00 e Element (RCS Temperatur e)

Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis (g, PGA) Mode Number RCS LOOP 2 Wide Range Cold Leg Prot. A 2000-152 BBTE0423B Temperatur RB >RLGM Screened SRT disposition 00 I

e Element (RCS Temperatur e)

Accumulator TankA Outlet Valve functionality EPHV8808 Isolation 1998-153 RB >RLGM Screened demonstrated to screen per A Valve 06 analysis in 15C4353-CAL-001.

(Accumulato r Isolation Valves)

Accumulator Tank B Outlet Valve functionality Isolation 1998-154 EPHV8808B RB >RLGM Screened demonstrated to screen per Valve 06 analysis in 15C4353-CAL-001.

(Accumulato r Isolation Valves)

Accumulator Tank C Outlet Valve functionality Isolation 1998-155 EPHV8808C RB >RLGM Screened demonstrated to screen per Valve 06 analysis in 15C4353-CAL-001.

(Accumulato r Isolation Valves)

Accumulator Tank D Outlet Valve functionality EPHV8808 Isolation 1998-156 RB >RLGM Screened demonstrated to screen per D Valve 06 analysis in 15C4353-CAL-001.

(Accumulato r Isolation Valves)

Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Failure Item ID Description Bldg Elev Basis (g, PGA) Mode Number Containmen t

Atmospheric Pressure 2026-157 GNPT0936 Channel2 AUX >RLGM Screened SRT disposition 00 Pressure Transmitter (Contain me nt Pressure)

Contain men t

Atmospheric Pressure 2026-158 GNPT0937 Channell AUX >RLGM Screened SRT disposition 00 Pressure Transmitter (Contain me nt Pressure)

Safety Injection Accumulator Anchorage Tank and anchorage evaluated 159 TEPOlA RB 1998 0.53 TankA Capacity per 15C4353-CAL-001.

(Accumulato rs)

Safety Injection Accumulator Anchorage Tank and anchorage evaluated 160 TEPOlB RB 1998 0.53 Tank B Capacity per 15C4353-CAL-001.

(Accumulato rs)

Safety Injection Accumulator Anchorage Tank and anchorage evaluated 161 TEPOlC RB 1998 0.53 Tank C Capacity per 15C4353-CAL-001.

(Accumulato rs)

Safety Injection Accumulator Anchorage Tank and anchorage evaluated 162 TEPOlD RB 1998 0.53 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.