ML20199E442

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Summary of 971028 Meeting W/Fpc in Rockville,Md Re EDG Test Plan & Amend Request Involving EDG Protective Relays.List of Meeting Attendees & Copy of Matl Distributed at Meeting Encl
ML20199E442
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/12/1997
From: Scott Flanders
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9711210207
Download: ML20199E442 (26)
v • d • e


Text

{{#Wiki_filter:_ _ _. LICENSEE: Florida Power Corporation PLANT: Crystal River Unit 3

SUBJECT:

SUMMARY

OF MEETING WITH THE FLORIDA POWER CORPORATION

On October 28,1997, the Nuclear Regulatory Commission (NRC) staff met with representatives of the Florida Power Corporation (FPC) in Rockville, Maryland, to discuss the Emergency Diesel Generator (EDG) test plan and an amendment request involving the EDG protective relays. is a list of the meeting attendees and Enclosure 2 is a copy of the material distributed at the meeting. In the meeting, the NRC staff identified additional information that it r.eeds to complete tho review of the EDG protective relays amendment. Specifically, the staff requested the follownig:
1. Pl.nt specific and industry experience, including failure data, with specific vintage of 51 \\/ relays to confirm the reliability of the relays.
2. Documentation that the protective relays are in a surveillance program, and the specifics of the surveillance program.

- 3. A description of the type of indication (alarm) that is given to the operator when the output breaker opens.

4. The staff would also like confirmation that the diesel cverspeed trip is not challenged when the output breaker opens.

FPC also made a presentation which clarified the EDG test plan. During the presentation FPC stated EDG-A is scheduled for 16 starts and 13 load runs with the new turbocharger, intercooler, and radiator installed. EDG-B is scheduled for 10 starts and 9 load runs with the new turbocharger, intercooler, and radiator installed. To date the licensee has completed 8 of the 13 runs on EDG-A and none on EDG-B. The staff requested that FPC commit to completing 22 (total for EDG-A & EDG-B) successful start and load run tests. The staff is continuing to evaluate the EDG test plan to determine if it is adequate to fully qualify the EDGs prior to restart. FPC requested that, by November 8,1997, the staff approve the EDG protective relays amendment and the EDG Uprate Technical Specification amendment part of TSCRN 210 (subject amendment cf the EDG test plan issue). The staff stated that it would not be possible to complete these reviews by that date given the outstanding questions that remain for these amendments. However, the staff did agree to provide some feedback as to the adequacy of the EDG test plan by November 8,1997, original signed by S. Flanders Scott C. Flanders, Project Manager Project Directorate PD ll-3 I Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-302 - l

Enclosures:

1. Attendees List a

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2. Meeting Handout M9 e u, Q C PGjf cc w/ enclosures: See next page Document Name: G:\\CBY_17AL\\EDG. SUM Ofrv:e PM h

LAPDil-3 PD PDil-3 s Name SFle ers BClayton FHebdon Date 11 /97 ~ 111( % 7 M 11/b7 Copy Yes/No ho UOFFICIAL RECoRDToPY ~ 9711210207 971112 l ' H. goa aoocx o m== ' @ as:q

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k - UNITE 3 STATES 8 y NUCLEAR REGULATORY COMMISSION WAsHINeToN D.C. SN06 GAM \\.... - November 12, 1997 - ) LICENSEE: Florida Power Corporation l PLANT: Crystal River Unit 3

SUBJECT:

SUMMARY

_ OF MEETING WITIC T':.0".TA POWER CORPORATION i - On October 28,1997, the Nuclear Regulatory Commission (NRC) staff met with representatives

of the Florida Power Corporation (FPC) in Rockville, Maryland, to discuss the Emergency Diesel-Generator (EDG) test plan and an a nondment request involving the EDG protective relays. is a. list of the meeting attendees and Enclosure 2 is a copy of the material-distributed at the meeting. In the meeting, the NRC staff identified additional information that it

. needs to complete the review of the EDG protective relays amendment. Specifically, the staff requested the following:

1. Plant specific and industry experience, including failure data, with specific vintage of 51 V relays to confirm the reliability of the relays.

' 2. Documentation that the protective relays are in a surveillance program, and the _ specifics of the surveillance program.

3. A description of the type of indication (alarm) that is given to the operator when the output breaker opens.
4. The staff would also Gke confirmation that the diesel overspeed trip is not challenged when the output breaker opens.-

FPC also made a presentation which clarified the EDG test plan. During the presentation FPC stated EDG-A is scheduled for 16 starts and 13 load runs with the new turbocharger, intercooler, and radiator installed. EDG-B is scheduled for 10 starts and 9 load runs with the new turbocharger, intercooler, and radiator installed. To date the licensee has completed 8 of the 13 runs on EDG-A and none on EDG-B. The staff requested that FPC commit to completing 22 i - (total for EDG-A & EDG-B) successful start and load run tests. The staff is continuing to evaluate the EDG test plan to determine if it is adequate to fully qualify the EDGs prior to restart. FPC requested that, ty November 8,1997, the staff approve the EDG protective relays amendment and the EDG Uprate Technical Specification amendment part of TSCRN 210 (subject 4 amendment of the EDG test plan issue). The staff stated that it would not be possible to complete these reviews by that date given the outstanding questions that remain for these amendments. However, the staff did agree to provide sorne feedback as to the adequacy of the EDG test plan by November 8,1997. 7 + tt C. Flanders, Project Manager-Project Directorate PD 11-3 Division of Reactor Projects.1/ll Office of Nuclear Reactor Regulation Docket No. 50-302' l

Enclosures:

1.- Attendees List -2. Meeting Handout cc w/ enclosures: See next page d - - -, + + - - eor =siw+- ,-mweww-- w w5=<s*----ewr-=m++in-- - - v -,w'en. e-**- e 'w-me-gr-ri e T-- e y"-- --w-

Florida Power Corporation CRYSTAL RIVER UNIT NO. 3 GENERATING PLANT Cc: Mr. R. Alexander Glenn Mr. Robert E. 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 j Mr. Charles Pardee, Director Senior Resident Inspector Nuclear Plant Operations (NA2C) Crystal River Unit 3 Florida Power Corporation U.S. Nuclear Regulatory Commission Crystal River Energy Complex 6745 N. Tallahassee Road 15760 W. Power Line Street Crystal River, Florida 34428 Crystal River, Florida 34428-6708 Mr. James S. Baumstark \\ 11r. Bruce J. Hickle, Director Director, Quality Programs (SA20) ) Director, Restart (NA2C) Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Regional Administrator, Region 11 Mr. Robert B. Borsum U.S. Nuclear Regulatory Commission t Framatome Technologies Inc. 61 Forsyth Street, SW., Suite 23T85 1700 Rockville Pike, Suite 525 Atlanta, GA 30303-3415 h 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 Attarney Generel Mr. Roy A. Anderson Department of Legal Affairs Senior Vice President The Capitol Nuclear Operations Tallahassee, 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 32399-2100 Mr. Kerry Landis U.S. Nuclear Regulatory Commission Chairman 61 Forsyth Street, SW., Suite 23T85 Board of County Commissioners Atlanta, GA 30303-3415 Citras County 110 North Apopka Avenue Iverness, Florida 34450-4245

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-4 s g,.* Distribution HARD COPY 4 Docket File :

  • PUBLIC1 Crystal River Reading OGC

=ACRS y - L.; Raghavan: . J. Johnson, Ril -

  • . E-Mail 51; S, Collins /F. Miraglia (SJC1,FJM) r;.

R. Zimmerman (RPZ) B. Boger (BAB2,RCN). J. Zwolinski(JAZ) - 4 ? K. Landis (KDL) -o F;Hebdon (FJH) B. Clayton (BAC2) J. Jaudon' Rll (JPJ) T. Martin (e-mail to SLM3) M. Gameroni, EDO (MKG) J. Calvo

i U. Zwolinski S. Saba S. Flanders M. Pratt 5

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8 g MEETING ATTENDEES OCTOBER 28.1997 MEETING WITH FLORIDA POWER CORPORATION NAME ORGANIZATION

1. L. Raghavan NRC/NRR
2. Jose Calvo NRC/NRR
3. Fred Hebdon NRC/NRR
4. John Zwolinski NRC/NRR
5. Saba Saba NRC/NRR
6. Scott Flanders NRC/NRR
7. Mark Pratt NRC/NRR
8. CarlWoodard FPC/CR3
9. Jerry Campbell FPClCR3
10. Dave Kunesmiller FPC/CR3
11. Mike Rencheck FPC/CR3
12. Jim Andrews FPC/CR3
13. Jim Warren FPC/CR3

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W EDG Power U rate 2 i P e $g a e r.,= s 414 EDG Licensing Action Items s

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+,, + = t '~y ~ . ~ [ NRC PRESENTATION 2 _m OCTOBER 28,1997 m e," k l m; x I ~$ f j i O' l w v. I i l L$.Y 'j ~+ ; i l 72 DESIGN CRITERLA 2 i 4 f v. j aY USED FOR i ,a,=. 17 PROTECTIVE RELAYING s w m w Os OF EDG BUS l 4., 6 i u u s#f I l S te N b 'JJ. PRESENTED BY: JERRY CAMPBELL 5 l ,m .x 2 l

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i ~ \\ 'z. .: w,..- ,e ^ ,s / 4 -m PROBLEM STATEMENT C ^ c'

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l Y5 m A modification performed in 1987 to the i i 4 .c VE protective relay design of the EDG's was s 1 m D NRC identified as a USQ and a violation. e ,s The added relays do not meet Reg. Guide i e 9)! 4;;7 1.9, Revision 2. 9a at y -,Q

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.p',[ z ,, tl, ,,.g MAR INSTALLATION IN 1987 i -m ' Q l t !bs l j ~/ REASON FOR INSTALLATION t i

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1 g i ]' ']. 4 m Over-current protection of the source breakers only aj N tripped the source breakers, but did not prevent the lg x y su EDG Breaker from closing onto a faulted ES bus. m w a

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a M Breaker for a faulted ES bus. p ) 2si 3 l / r1 l M a No over-power protection when the EDG was %p n Q operated in parallel with the switchyard. } ~ ~ l (M* [i -k p

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DESIGN CRITERIA REVIEWED .g: . is g FOR 1997 MODIFICATION y m a l A + ~ Reg. Guide 1.9, Revision 2 E i c e 4 m IEEE 387-1984-Standard Criteria for Diesel-Generator Units ? e m i g Applied as Standby Power Supplies for Nuclear Generating ) Stations. 3 e .4,, IEEE 741 1090-Standard Criteria for the Protection of Class IE ,4 i E?. m ce fR Power Systems and Equipment in Nuclear Power Generating e l = m a Stations.

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@n g 3 m IEEE 242-1986-Recommended Practice for Protection and yi u@. Coordination ofIndustrial and Commercial Power Systems. 3

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4 m Evaluated protective relay design practices used at other W y X Nuclear Stations for Bus Protection on Diesel-Generators used d 13 BW 4 as standby power supplies. g m 2, .m c. s. w - 1 a'Y 4 g.? ' ".)g \\ h f' r ,n' V e 6_._' ^

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SUMMARY

OF DESIGN CRITERIA U~ SED -_rm ((' AT OTHER NUCLEAR STATIONS f m ? %1 a r c-a m

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m No redundant or coincidental Bus Protective Relay ?g trip logsc. .x W;. s a u $p m No bypassing of Bus Protective Relay trips during pj ff normal or ES actuation. E:s n'iti k'> is a Bus Protective Relay logic either trips or prevents fk m rC the closing of the diesel breaker and associated Bo @+: feeder breakers for the ES Bus. a C.. _,,C kJ

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~ l DE I N RITERIA F R 1 7 _c. l MODIFICATIONS TO i g PROTECTIVE RELAYING ON EING s,, a G* ?? y;, y -[ ),,l 5 g:

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fu a Original plant design criteria. h ?# l n Q f N: s IEEE 242-1986 for bus relay protection schemvfs. j a .s u. l 4*2 y(w l 'i? l yi a Industry practices. q' l x, s s 2 i j ,N [

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,n x ;' ( ~ -= f 1997 CHANGES TO THFm 1987 7 cs MODIFICATION g .g $e 1 u a, @vj u The over-current relays (51Vs) installed in 1987 for ES f[ g Bus protection will be rewired to trip and/or prevent i,

  1. 5 closing the diesel breaker for a fault on the ES Bus.

3,; l . c.. w n.w? sz,;;% wE a Original Protective Relaying modified in 1987 will be 3,, n y-rewired to only trip and/or prevent closing the diesel g E breaker. n W ?? W ?! ~ i,s a The over-power relays only trip the Bus source breaker g a &F and do not trip the diesel breaker under normal or ES P mW actuation conditions. Wn v ^

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  • Trip Trip BYPASSED

(( I t% EDG EDG DURING 1.S i i X. Unit Breaker ES ACT. 2.; .5 A S S S N/A N Y N 'n' B S S S N/A N Y N 2 n t pgi C S N/A S N/A N Y N pi D S N/A S S N Y N 3 i $y ED E S S S N/A N Y N i 7 72 CR-3 S S S N/A N Y N D l t1 ?) S-SINGLE CIIANNEL LOGIC i DJ' Oft l Y-YES 45 i s -Y; ..&a -s t A,, N-NO pp

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  • -ALL PLANTS TRIP DIESEL UNIT FOR A GENERATOR DIFFERENTIAL l

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s cp 2 .,);, m The design is consistent with Reg. Guide 1.9, Rev 2. E !$ i Nf l t t; A 31 m The design is consistent with IEEE 242-1986. Si W w a;; i .w p i iR m Protective relaying is used extensively throughout the / A w iy power industry and is considered highly reliable. w ss M = Single channel, non-bypassed bus protective relay logic y i l is consistent with the CR-3 original design philosophy y a M and is also consistent with other contacted nuclear E l r x is utilities. S .e l -N m}; l [ M ?, G., b s 'nM ~ mm.,19. gg>;g g k f -- a %.uu, ,m, .g.g. g, g,,, ;g j g3_3, q-g, g f

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l ~ m- ~ ,,- o .e 1 ~ l 1 i l .. -n 32 l ff EDG Qualification el m T A 4 m Engine Modifications - Si i %w n: +. = Testing by vendor (Coltec) v sr f. l "S = Onsite testing by BG&E, including 25 starts b e 3 years operation by BG&E, including monthly i = i c -: 1 I 9 surveillance testing starts 6 w u - s -; a

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  1. .c-m Radiator Modifications -

= Similarity to original radiator configuration i l m FPC site testing [ 9 m w -%S " 5 g .y f* ~, , a,,.,, -g;,;.ww.w; & x,png m m- _, _ -, _ -, - - - - - - - - - - =,, - - - - - - - - - - - - - - - - - - -

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  1. f EDG Te. sting Profile i

l 1 l 5 -f 3500 ~ c" 3300 kW f: P~ f 200 Hr ratsg Fun Load [ 3100 kW 7 Encaer Testing - f 2000 Hr rat.ng i p 3000 g,. 1, b M'u n; 27ook w e -4 e u e o -; e menes E g 3 ~; 2500 x r n 3 V"'- o 3 5 4 a r 25 hours

34 nou,s. 22 hours 3

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r e ^ - l !. Radiator I ? I l 5 <$-24 Hour Power Uprate Test } 3000 i 4 = i l --1 g a Rm i, E ~ n i- + U O f g ?} e e ~ 500 2 0

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.is q 3 3 3 r-s i W i 3 3 l , J.., 2 2 2 E l x x x a o 1 2 A a ? ? 2 3 R 2 2 8 3 0' R. 2 k.4 2 8 3 .s l [lj-- Time in Hours Sage Largest Load Regecten J t <;..r.im, ? lg ! ,,._-2'. g,: ,e g +.. t g. u' Anu x ' g,, .k a., ; A e 33 -3g, . ; _,, g y p., ,g 3, w,_q y _,, l _ g. '; yy. Qy e ,-*,. - - - - m -eu.--,.-.w.mm,m-------w

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~ 'Q .e t r l ,3 Summary of EDG Reliability ; 7 499~ Testing After Radiator i l I Replacement 0 ys m --ics v. p; A EDG Train Total Starts Load Runs Ooer. Hours C i O. 1 l !!? "A" 21 17 82.5 $u u M he_ "B" 13 9 50 f 3.: .3h ' Tj[ ] f)$; i/ 1 kL,{} { i,f$- = Includes starts and load runs since installation of new h 9 turbochargers and intercoolers.

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5 uA,, train values are actual, uB,, train values are ~r a n i f estimates. m f g bl .x e l$WAa g.-- 1,~a. .g., 3,, _ gg r; - gy g..g gg, Q f $3,... _, .gu, ~g,-? i

~ ~. e 4 ~ ~ s: l t ~& ff ummary of EDG Reliability J... esting After Uprate Testing i i Y.,. ~ ( ~ t er ,.c j sp. EDG Train Total Starts Loac Runs Ooer. Hours _ e.. cs +4 Ei "A" 24 20 145.5 a -s i G "B" 17 12 113 4 i e .3 i n eg.; a 8 5O' l; gy; a A a Includes starts and load runs since installation of new a turbochargers, intercoolers, and radiators. p;;j m3 = Values are estimates. c i w U~i9 s..; y, . +. ~ q.;,, a, .m_,, ,,w.j a _ ; ,,,3y.y,,y,- ,.,.,.g y 9,,,_,; 4.g yg;gjg;;pg ;gg ) p,g,._r,.,j p g

I i m, t .ty-' r [ ' a-W I w E> l l -g ,. s EDG Historical Reliability l + s: o a q w; i M, m Number of start failures since 1990 - 1 n; W 1991 - fuel header check valve leak %x = im

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l% e .n w $9 7' i% m Number ofload run run failures since 1990 - O s = W: i ~6. 9 l l ecr;; rg. 'I.$$ ~6 q":: l

4.. m EDG availability since 1990 - 99.06 %

? 5 = Includes 1997 YTD y .+ y y y i 'E y I 1 ih .. -ar n.m 2 Q ga g.g g.g.;j;.g, ; A.a;,., fg j,_,.g ;,., y,.gjpg. O ggy y, g;g,,, w;,3 g l l P I i i l l

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,n. 4 . j , y% j s O y* Third Party Review of j: EDG Test Plan s ~ v;; Y* l NQ7 , Q' x r C l .- A% ,: - - a: r i-$7 l m-l l 6 Review performed by: g w bi i EU. i 84 MPR Associates Inc. W m m 6:s. 1 2r i 3 m The Woodard CoTPoration s n w i w 3+ l ig u IEEE 387 Working Group Members j r. s G' gy- 'ma y hl j s,p; O. ,c '_I : [ * ]Eg r ,p> w* b e n... c lN' N '*b ~ W q - ~ ________.--.----.-,,..--...-....---.--.__--..--.--,.----------.-,-..----~~-~~,~.---~---~,-------wm-- - - - - = ~ ' ~ - - -~ -' = -'

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~ =s ,_a .X__ mE5 EMERGENCY DIESEL GENERATOR _rA k. LICENSING ACTIONS h a i El a Temporary Tech. Spec. Amendment y -J (LOPS Relay Testing Surveillance) N 7 ]g a EDG Room Fans (USQ) + n FSAR Amendment (LAR 216) ~ a ~ a EDG Protective Relays (USQ) l% FSAR Amendment (LAR 219) 4, e j j .-tl m EDG Uprate Tech. Spec. Amendment W m l (Part of TSCRN 210) 3 Or a Approvals Needed by November 8,1997 l [ 'B' Diesel Modifications will be Complete ] - Ready to Start Testing 7 -g., h e r -{ g -- .e, '*3 E' E f - _ _ _ -, _ _ _ - _ _ _. - -. - - - - _. - - -.., -.. - ~. - .}}

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