ML20198B234

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Summary of 971202 Meeting W/Fpc in Rockville,Md Re Seismic Qualification of Mechanical & Electrical Equipment & Large Bore Piping & Pipe Support Calculations.List of Attendees & Meeting Handout Encl
ML20198B234
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 12/11/1997
From: Raghaven L
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR NUDOCS 9801060236
Download: ML20198B234 (70)
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Text

{{#Wiki_filter:-- Decemb:r 11, 1997 LICENSEE: Florida Power Corporation j FACILITY: Crystal River Unit 3 (CR-3)

SUBJECT:

SUMMARY

OF MEETING ON DECEMBER 2. 1997 TECHNICAL ISSUES RELATING TO SEISMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT (A-46 ISSUE) AND LARGE BORE PIPING AND PIPE SUPPORT CALCULATIONS On December 2. 1997, representatives of the Florida Power Corporation (FPC). licensee for Crystal River Nuclear Plant. Unit 3 (CR3), met with U.S. Nuclear Regulatory Commission (NRC) staff members at their Headquarters 1 in Rockville. Maryland. . Enclosure 1 is a list of attendees. is a copy of the handouts presented at the meeting. The meeting involved working level technical discussions relating to seismic qualification of mechanical and electrical equipment (A461ssue) and large bore piping and pipe support calculations. The discussions were general working level in nature and did not result in specific action items. L.Rakavan.ProjectManager Project Directorate 11-3 Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. Attendees List 2. Meeting handout cc w/ enclosures: See next page A!RC FEE Emal[,wpy Document Name: G:\\ CRYSTAL \\971120. SUM Office PM:PDIl-3 LA:PDil-3 PD:PDil-3 Name LRaghavan { M 'BClayton/A D FHebdon Date 12/10/97 12/10/97 12/li/97 Copy [Yek/No Yes Yes((NM OFFICIAL RECORD CUn [ b b Sb00302

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w a,- p,,oseg ge UNITED STATES P] NUCLEAR REGULATDRY COMMi&SION j' WASHINGTON. D.C. 306tH001 i December 11, 1997 t i i LICENSEE: Florida Power Corporation FACILITY: Crystal. River Unit 3

SUBJECT:

SUMMARY

OF MEETING ON DECEMBER 2. 1997 TECHNICAL ISSUES RELATING TO SEISMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT (A-46 ISSUE) AND LARGE BORE PIPING AND PIPE SUPPORT CALCULATIONS On December 2. 1997. representatives of the Florida Power Corporation (FPC). licensee for Crystal River Nuclear Plant. Unit 3 (CR3), met with U.S. Nuclear Regulatory Commission (NRC) staff members at their Headquarters in Rockville. Maryland. is a list of attendees. is a copy of the handouts presented at the meeting. The meeting involved working level technical discussions relating to seismic qualification of mechanical and electrical equipment (A46 isst'e) and large bore piping and pipe support calculations. The discussions were general work'.ng-level in nature and did not result in specific action items. [ L. Raghavan. Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50 302

Enclosures:

1. Attendees List-2. Meeting handout cc-w/ enclosures:.See next:page

i ? 1

SUBJECT:

$UMARY'0F MEETING OF-DECEMBER'2.-1997cSEISMIC QUALIFICATION OF i

MECHANICAL'AND ELECTRICAL EQUIPMENT (A-46 ISSUE);AND LARGE BORE rj PIPING AND PIPE SUPPORT CALCULATIONS -, Distribution' .HARD..C9M w Docket: File w

.PUBLIC.

Crystal _; River Reading OGC Li ACRS L. Raghavan j J. ' Johnsor.,- Ril 'E-Mail' w/ Enclosure -1__ S. Collins /F. Miraglia (SJC1,FJM) -R. Zimmerman-(RP?)- 1BL Boger (BAB2,RCN)?

J.!Zwolinski (JAZ)'

K. Landis-(KDL) F.-Hebdon-(FJH) B. Clayton.' J. ' Joudan, L Ril.. .T. Martin (e-mail to-SLM3)l L. Trocine, EDO (LXT): -' 4 S.> Flanders- -S.-Cahill-S.]LeVai E. Connell ~ 1 b L t, J -1 i-l _-1' . ~.

= 4 Florida Power Corporation ' CRYSTAL RIVER UNIT N0. 3 GENERATING PLANT cc: Mr. R. Alexander Gl~enn-Mr. Robert L. Grazio Director Corporate Counsel Nuclear Regulatory Affairs (SA2A) Florida Power Corporation Florida Power Corporation MAC-ASA Crystal River Energy Complex P.O. Box 14042 15760 W. Power Line Street St. Petersburg, Florida 33733-4042 Crystal River, Florida 34428-6708 Senior Resident Inspector Mr. Charles Pardee, Director Nuclear-P1 ant Operations (NA20) Crystal River Unit 3 Florida Power Corporation U.S. Nuclear Regulatory Commission Crystal River Energy Complex 6745 H. Tallahassee Road 15760 W. Power Line Street Crystal River, Florida 34428 Crystal River, Florida 34428-6708 Mr. James S. Baumstark Mr. Bruce J. Hickle, Director Director, Quality Programs (SA2C) Director, Restart (NA20) Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Line Street 15760 W. Power Lina Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Regional Administrator, Region II -Mr. Robert B. Borsum U.S. Nuclear Regulatory Commission Framatome Technologies Inc'. 61 Forsyth Street, SW., Suite 23T85 1700 Rockville Pike, Suite 525 Atlanta, GA 30303-3415 Rockville, Maryland 20852 Mr. John P. Cowan Mr. Bill Passetti Vice President - Nuclear Production Office of Radiation Control (NA2E) Department of Health and_ Florida Power Corporation Rehabilitative Services Crystal River Energy Complex 1317 Winewood Blvd. 15760 W. Power Line Street . Tallahassee, Florida 32399-0700 Crystal River, Florida 34428-6708 Attorney General Mr. Roy A. Anderson Department-of Legal Affairs-Senior Vice President The Capitol .luclear Operations -Tal_lahassee, Florida 32304 Florida Power Corporation ATTN: Manager, Nuclear Licensing Mr. Joe Myers, Director - Crystal River Energy Complex (SA2A) Division of Emergency Preparedness 15760 W. Power Line Street Department-of Community Affairs Crystal River, Florida 34428-6708 2740 Centerview Drive Tallahassee, Florida 32599-2100 Mr. Kerry Landis U.S. Nuclear Regulatory Commission Chairman: 61 Forsyth Street,'SW., Suite 23T85 -Board of County Commissioners Atlanta, GA 30303-3415 Citrus County 110 North _Apopka Avenue -Iverness, Florida 34450-4245

CRYSTAL RIVER 3 MEETING NOVEMBER 20. 1997 lum.g Oroanization L. Raghavan NRC/NRR Steve Cahill NRC/ SRI Kerry'Landis NRC/RII Scott Flanders NRC/NRR Steve LeVri NRC/NRR Ed Connell NRC/NRR J. Holden Florida Power Corp. A. Petrowskey Floricia Power Corp. M. Rencheck Florida Power Corp. R. Grazio Florida Power Corp. M. Van Sicklen Florida Power Corp. T. Baumstark Florida Power Corp. l

I s_t:e Florida Power Corporation ~ _m l 1 j t l Overview of 1 1 U.S.I. A-46 Program for Crystal River 3 q December 2,1997 I

o .i Xe Agenda j l '-6fi$ 1 l I l m Introduction a A-46 Program Implementation l > Results of Nov. 4-7,1997 USI A-46 Audit l > PSP Implementation Plan > Restart Outlier Plan > Non-Restart Outlier Resolution > Schedule m SupplementalInformation and Clarification m Confirmatory Evaluation of Selected Safe j Shutdown Equipment m Summary i

l gd Results of November 4-7 USI A-46 Audit ~ l dyjs m Overall Results of the Audit Were Viewed as L Positive l Im FPC Has Implemented Additional Processes and Programs for Resolution ofIssues Since the RAI Responses u Resolved Many RAIIssues a Supplemental Response to Be Submitted for Remaining RAI Issues > Clarification > AdditionalInformation > Resolution ofIssues from NRC A-46 Audit )

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PSP Implementation Plan j i i i m Over 800 Equipment Reviews Performed j i i i m 113 Outliers Identified for Resolution i > 70 Outliers Committed for Resolution Prior to Restart > 43 Outliers to Be Resolved by Refueling Outage 11 1 (Early,1999)

i MN Restart Outlier Resolution ~ un 1 s a Seventy (70) Outliers: i > Thirty-two (32) Require Field Modifications. Seventeen (17) Maintenance Work Requests t a c.g., Repair Broken Cabinet Latches, Add Missing Supports Twelve (12) FPC's MAR Process a c.g., Battery Racks, Diesel Day Tanks Three (3) Being Resolved by the Control Room Upgrade l Project > Thirty-Eight (38) Being Resolved by: Re-Inspection and Approval >> Analysis or Engineering Evaluation ce. W '~N l " Housekeeping" l . + .-c

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  • !Lg-SCHEDULE v.,

5 1 A-46 Outlier Resolution Action Plan i 1997 1998 1999 i Current Outage l i ) Submit Supplemental RAI Response I j Operating Cyclej1;gg,' ~ g, ~;;fu3 }..gyjjy,; ~ Safety Related Outliers e.e_ 70 Completed Refuel 11 Outage -W Non-Safety Related Outliers 100% Completion of l 43 Completed During Cycle 11 A-46 Outliers i

.t i SuPP ementalInformation and l .c. t 7413Ett Clarification j - p m Seismic NIargin Evaluation Based on IPEEE-Method Verifies Adequacy of Plant Structures i i > Electrical Raceways LAR Using GIP > Oversight by Third Party i m Inspection of CR-3 Anchorage > 100% of Accessible Anchorage l > Hands-On Check of All Non-Energized Equipment > All Energized Equipment with External Anchorage i 4 l m Structural Maintenance Rule Inspection i > Wrench Tightness Test of193 Expansion Anchors > Methods Based on GIP .s c -.

SupplementalInformation and ~ F =y A i g* Clarification i

v.,

l e. I i 4 Electrical Relays i l e '24 Bad Actor Relays Identified Which Were Susceptible to Chatter 1 i i e Top Level Procedure Being Developed for l Coping with Consequences of Relay Chatter l l

SuPP ementalInformation and l >_']>,n Clarification g-v.3 1 ( l } Tanks l m Preliminary Results Indicate Qualification by t l Calculation i > Waste Disposal Tanks WDT-3A, B, C & WDT-5 > Condenser Hot Wells CJHE-4A & B m Qualification of Condensate Storage Tank (CDT-1) per GIP Requirements Is Expected i l I > Calculation To Be Performed i l m Preliminary Results Indicate Emergency Feedwater Tank (EFT-2) Is Qualified l

i Confirmatory Evaluation of Selected I. 3tA o .gs'* Safe Shutdown Equipment l u Third Party Assessment Evaluated Completeness of USI A-46 Issue Resolution i l m AssessmentIncluded ~ l > CR-3 Plant Specific Procedure (CRPSP) l versus GIP > GIP Caveats 4 l > Anchorage Assessment j > Resolution of Outliers 1 i

i

1 Results of Selected Safe Shutdown 1 h "!g;* Equipment Confirmatory Evaluation j m GIP Caveat 1 i L > 10% Equipment Sample (85;i of Safe Shutdown Equipment List (SSEL) 1 > No Additional Outlier Issues Identified m Specific Anchorage Assessments > Four (4;i Equipment Items Reviewed MTMC-18,480 V Reactor MCC-3A2 >> MTMC-21, MCC >> VBIT-1E, Dual Input Inverter 3E AHCP-4, SCR Cabinet for AHHE-4A,-4B i I e a c -c. ,e -,. =,., s-. g. e w, =,. -.,

ig Results of Selected Safe Shutdown Equipment-g":gs, Confirmatory Evaluation (Cont'd) v. ii.- m MTMC-18,480 V Reactor MCC-3A2 (MCC Located at Elevation 95' of Auxiliary Building) > Issue: No Anchorage Along the Back of Any Cabinet > Results: Evaluation Indicates Side Welds Are Sufficient [

Conclusion:

Anchorage Is Acceptable i u MTMC-21, MCC (MCC Located at Elevation 119' of Auxiliary Building) > Issue: Bolts Attaching Cabinets to Anchorage Steel > Results: Anchorage Shown to Be Robust

Conclusion:

No Further Calculations or Review of the Anchorage Are Necessary i d ,s

.c i gg Results of Selected Safe Shutdown Equipment-

e;6, Confirmatory Evaluation (Cont'd)

. o. l l m VBIT-1E, Dual Input Inverter 3E j l (Inverter Located at Elevation 108' of the Control Complex) i > Issue: Anchorage Not Installed in Accordance with j Specifications l > Results:. Anchorage Is Adequate for SSE i

Conclusion:

Calculations Show Anchorage Acceptable m AHCP-4, SCR Cabinet for AHHE-4A,-4B l (Control Cabinet Located at Elevation 164' of the Control Complex) > Issue: Flexibility of Base Due to Thin Base Plate l > Results: Declared an Outlier Due to Poor Design

Conclusion:

Modification Wiil Be Implemented to i Address the Concern

"g g Results of Selected Safe Shutdown Equipment- ,.gI'* Confirmatory Evaluation (Cont'd) ~ l m Nine (9) Additional Anchorage Evaluations Were l Performed i > Electrical Equipment Located at the Highest 1 Elevations Chosen for Bounding Purposes ~ l > Seven (7) Items Demonstrated Compliance with GIP l Allowables > Two (2) Electrical Cabinets Previously Evaluated as Outliers Due to Lack of Anchorage Evaluated to Demonstrate That No Short Term Operability Concerns Exist ~ >> Identified on Post-Restart Outlier Resolution List

Results of Selected Safe Shutdown Equipment- ]gg .gs'* Confirmatory Evaluation (Cont'd) 1 i IR Conclusion > Evaluation of Equipment Sampled Shows j Complete GIP Caveat Compliance Without j 1 Exception j >No Additional Outliers Other than SCR Cabinet (AHCP-4) >No Conclusions Different Than Those Given in CRPSP-Based SEWS

l ' 1=; g; &

SUMMARY

) l m The Action Plan for Resolution of A-46 Outliers Is Systematic and Sound a Supplemental Reppnns_e_t_olRC_RAI Will l Be Submitted by@ecember 12,1997j u Identified Safety Related Outliers Will Be Resolved Prior to Restart m Remaining Non-Safety Related Outliers Will Be Resolved Prior to R11

l 'l l 24 Florida Power Corporation e t/-) l l i l Overview of l CS.I. A-46 Program 1 for i i [ Crystal River 3 l j December 2,1997 i t 6 3 i

i S c. ey 4 Agenda li E' t wm j m Introduction j u A-46 Program Implementation l > Results of Nov. 4-7,1997 USI A-46 Audit j > PSP Implementation Plan ~ > Restart Outlier Plan > Non-Restart Outlier Resolution > Schedule i e SupplementalInformation and Clarification i 1 m Confirmatory Evaluation of Selected Safe Shutdown Equipment a Summary err =-w---t" --e* -m-- -v-w -*-- -m

{ l gk Results of November 4-7 USI A-46 Audit ~ L 425 ' a{i .f L m u OveraII Results of the Audit Were Viewed as i Positive i j u FPC Has Implemented Additional Processes and Programs for Resolution ofIssues Since the RAI i i j Responses m Resolved Many RAIIssues l u Supplemental Response to Be Submitted for Remaining RAIIssues j > Clarification 4 i >AdditionalInformation > Resolution ofIssues from NRC A-46 Audit i l

p d'sf PSP Implementation Plan y->. i l m Over 800 Equipment Reviews Performed l m 113 Outliers Identified for Resolution > 70 Outliers Committed for Resolution Prior to Restart l > 43 Outliers to Be Resolved by Refueling Outage 11 l (Early,1999) i i

b.

4<c.9 Restart Outlier Resolution l m Seventy (70) Outliers: i i > Thirty-two (32) Require Field Modifications. i Seventeen (17) Maintenance Work Requests m c.g., Repair Broken Cabinet Latches, Add Missing Supports Twelve (12) FPC's MAR Process a c.g., Battery Racks, Diesel Day Tanks >> Three (3) Being Resolved by the Control Room Upgrade L Project i e l > Thirty-Eight (38) Being Resolved by: Re-Inspection and Approval l >> Analysis or Engineering Evaluation " Housekeeping" i i i

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l ",T101 i l g" Post-Restart Outlier Resolution

v.,

i i i l m Forty-three (43) Outliers i j > Eleven (11? Complete >Six (6) In Progress (Approx. 80% Complete) > Twenty-six (26) Complete by R11 m Post Restart Outliers Are Non-Safety j Related Equipment In Action Plan and Schedule Developed for Resolution

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1 J v;a l ";p SCHEDULE 1 9 __-m..-, A-46 Outlier Resolution Action Plan i I 1997 1998 1999 l l } t l l Current Outage l l l Submit Supplemental RAI Response ( 3 Operating Cycle 1f' ~( - ,-f 7 4 j?;{ Safety Related Outliers [ r I 70 Completed Refuel 11 Outage ; j Non-Safety Related Outliers 100% Completion of I 43 Completed During Cycle 11 A-46 Outliers i i l t i i i

7 SupplementalInformation and 'l MA l Msg

  • Clarification j

L/-) l M-M l l m Seismic Margin Evaluation Based on IPEEE Method Verifies Adequacy of Plant Structures l > Electrical Raceways LAR Using GIP l > Oversight by Third Party ~ 4 a Inspection of CR-3 Anchorage > 100% of Accessible Anchorage j 4 l > Hands-On Check of All Non-Energized Equipment > All Energized Equipment with External Anchorage a Structural Maintenance Rule Inspection > Wrench Tightness Test of193 Expansion Anchors j > Methods Based on GIP

i SupplementalInformation and i 3 t k_ - .gg* Clarification v., = m I i l Electrical Relays i I m 24 Bad Actor Relays Identified Which Were Susceptible to Chatter { 4 l m Top Level Procedure Being Developed for j l Coping with Consequences of Relay Chatter il i l

SupplementalInformation and ~ \\ - xt,1" i l $2 Clarification \\ Y".. - L i l Tanks j u Preliminary Results Indicate Qualification by i Calculation l > Waste Disposal Tanks WDT-3A, B, C & WDT-5 > Condenser Hot Wells CDHE-4A & B n Qualification of Condensate Storage Tank i l (CDT-1) per GIP Requirements Is Expected i > Calculation To Be Performed i m Preliminary Results Indicate Emergency Feedwater Tank (EFT-2) Is Qualified i

.I _w % Confirmatory Evaluation of Selected l "$m Safe Shutdown Equipment p* i i u Third Party Assessment Evaluated Completeness of USI A-46 Issue Resolution m AssessmentIncluded ~ [ > CR-3 Plant Specific Procedure (CRPSP) versus GIP i > GIP Caveats l > Anchorage Assessment ~ i > Resolution of Outliers i i i

i Results of Selected Safe Shutdown 3 tin j

  • g*

Equipment Confirmatory Evaluation l m GIP Caveat l \\ l >10% Equipment Sample (85) of Safe I Shutdown Equipment List (SSEL) >No Additional Outlier Issues Identified l l m Specific Anchorage Assessments l l >Four (4) Equipment Items Reviewed l MTMC-18,480 V Reactor MCC-3A2 l >> MTMC-21, MCC >> VBIT-1E, Dual Input Inverter 3E AHCP-4, SCR Cabinet for AHHE-4A,-4B

1 I yg Results of Selected Safe Shutdown Equipment-E.gs" Confirmatory Evaluation (Cont'd) l t/-) ____ __ _ _ _ _ _. ___ l l i a MTMC-18,480 V Reactor MCC-3A2 i [ (MCC Located at Elevation 95' of Auxiliary Building) l > Issue: No Anchorage Along the Back of Any Cabinet l > Results: Evaluation Indicates Side Welds Are Sufficient

Conclusion:

Anchorage Is Acceptable a MTMC-21, MCC (MCC Located at Elevation 119' ofAuxiliary Building) l > Issue: Bolts Attaching Cabinets to Anchorage Steel l > Results: Anchorage Shown to Be Robust l

Conclusion:

No Further Calculations or Review of the 4 j Anchorage Are Necessary i. I

i ++ m% Results of Selected Safe Shutdown Equipment

Nhs, Confirmatory Evaluation (Cont'd) v.

l l u VBIT-1E, Dual Input Inverter 3E [ (Inverter Located at Elevation 108' of the Control Complex) L > Issue: Anchorage Not Installed in Accordance with j Specifications l > Results: Anchorage Is Adequate for SSE l

Conclusion:

Calculations Show Anchorage Acceptable [ u AHCP-4, SCR Cabinet for AHHE-4A,-4B i (Control Cabinet Located at Elevation 164' of the Control Comp:ex) l > Issue: Flexibility of Base Dne to Thin Base Plate l l > Results: Declared an Outlier Due to Poor Design j l

Conclusion:

Modification Will Be Implemented to l Address the Concern j = L A

_ ;g,. Results of Selected Safe Shutdown Equipment-p ~hb Confirmatory Evaluation (Cont'd) L/.-). i u Nine (9) Additional Anchorage Evaluations Were Performed > Electrical Equipment Located at the Highest j Elevations Chosen for Bounding Purposes i j > Seven (7) Items Demonstrated Compliance with GIP j Allowables i l > Two (2) Electrical Cabinets Previously Evaluated as Outliers Due to Lack of Anchorage Evaluated to Demonstrate That No Short Term l Operability Concerns Exist >> Identified on Post-Restart Outlier Resolution List i I

i yn Results of Selected Safe Shutdown Equipment. ~ gji* Confirmatory Evaluation (Cont'd) 1 i = i l m Conclusion > Evaluation of Equipment Sampled Shows Complete GIP Caveat Compliance Without Exception l \\ l >No Additional Outliers Other than SCR j Cabinet (AHCP-4) l >No Conclusions Different Than Those Given in CRPSP-Based SEWS t,

\\ tea "?Lg*

SUMMARY

j . r->. i l l m The Action Plan for Resolution of A-46 l Outliers Is Systematic and Sound m Supplemental Response to NRC RAI Will l Be Submitted by December 12,1997 i l l m Identified Safety Related Outliers Will Be l Resolved Prior to Restart u Remaining Non-Safety Related Outliers l Will Be Resolved Prior to R11 i i i 1 I

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um P %-v% BsPM L* 6 - -11' Large Bore Piping 4 i 1 l Issue Statement Lack of Documentation l Identified Discrepancies with Ar.alysis i i Safety Significance i No Safety Concern e { Regulatory Compliance i l Documentation does not meet expectations I il

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M_ Da. QF Large Bore Piping =__ Issue Statement l Lack of Documentation Identified Discrepancies with Analysis Safety Significance No Safety Concern i Regulatory Compliance Documentation does not meet expectations l i ' 49tiiD%w., L =::. "%%CMMfMR5NM@t&:G%5th' ~ ^ ~ i

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