ML20036A006

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Summary of 930414 Meeting W/Util Re Life Cycle Mgt & License Renewal Program.List of Attendees & Presentation Matl Encl
ML20036A006
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 05/03/1993
From: Anand R
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9305070193
Download: ML20036A006 (54)
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Text

{{#Wiki_filter:V v: -3 V& hke_i-Gilt.s, - ] _ f* **%'o d-UNITED STATES .-*$8 Ig NUCLEAR REGULATORY COMMISSION o g' WASHINGTON, D. C. 20555 \\.....[p May 3,1993 Docket Nos. 50-317 50-318 LICENSEE: Baltimore Gas and Electric Company FACILITY: Calvert Cliffs Nuclear Power Plant

SUBJECT:

SUMMARY

OF THE MEETING WITH BALTIM0RE GAS AND ELECTRIC COMPANY. (BG&E) CONCERNING LIFE CYCLE MANAGEMENT AND LICENSE RENEWAL ISSUES: On Wednesday, April 14, 1993, representatives from BG&E made a presentation to the U. S. Nuclear Regulatory Commission (NRC) staff and members of the public-concerning ongoing activities at Calvert Cliffs Nuclear Power Plant regarding their life cycle management-(LCM) program. Meeting participants discussed issues relating to the implementation of the license renewal rule (10 CFR Part.54) and aspects of BG&E's proposed methodology for performing the-integrated plant assessment:(IPA) as required by 10 CFR Part 54 is a list of the attendees and Enclosure 2 is a copy of the BG&E presentation muterial discussed at the meeting. BG&E described a proposed screening process for identifying systems, struct-ures, and components (SSCs) important to license renewal (ITLR). BG&E discussed preliminary results -from implementing their proposed ITLR screening methodology. The staff is currently reviewing this screening process, and stated that no. conclusions were reached concerning whether the proposed screening process would meet the current rule requirements. BG&E discussed their proposed implementation strategy for determining which SSCs are not subject to age-related degradation unique to license renewal,J and described this strategy for short-lived components. In BG&E's opinion, short-1 lived components will not experience age-related degradation unique to license .i renewal since these components are inspected and routinely' replaced.or refurbished based on a predetermined acceptance-criteria or condition. .In-l 4 addition, if the existing maintenance programs failed to prevent' equipment I failures, a root.cause analysis would be performed and corrective action taken. However, for long-lived structures and components such as reactor. vessel, cables, etc., which could be ' subject to age-related degradation uniquez - to license renewal, an aging analysis.would be performed to determine the need .for an effective program as required by 10 CFR 54~.21(a)(5). BG&E presented a status of their component _ level ITLR screening process for 1 the_~ compressed air system, auxiliary feedwater. system, feedwater system, and= { reactor coolant system. Using their proposed methodology,-23 percent of the components _in the above-mentioned systems wo'uld not be subject to' age-related j degradation' unique to license renewal. 1

BG&E and the staff discussed'briefly the status of their submittals. -BG&E

1 submitted two technical reports for NRC' review. _ These reports contain the f\\ l methodology, procedures, and results for screening SSCs ITLR for.the reactor' i l 06d122 Wf0? hh hd hhdh h ll '9305070193 930503 ~ 1, l - ') PDR ADOCK 05000317-P: PDR p ~ L W

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a. coolant, compressed air, containment, and salt water systems. The staff is currently reviewing BG&E's submittals, and will be issuing its first request for additional information- (RAI) by May 1,1993. BG&E is scheduled to submit the third and last report on component evaluation methodology and results by May 19, 1993. The staff plans to schedule a meeting with BG&E in May 1993 to discuss the status of their LCM program.

At the conclusion of BG&E's presentation, the NRC staff commented that the effort at Calvert Cliffs Nuclear Power Plant provided valuable insight into license renewal implementation issues. BG&E noted that as a result of these activities, they have achieved a better understanding of their organization's existing programs, practices, and plant safety. Raj Anand, Project Manager-License Renewal.and Environmental Review Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation t

Enclosures:

1. Attendees List 2. Meeting Handout cc: See next page DISTRIBUTION: TkcW mtral-File - PDR PDLR R/F. C1 TMurley/FMiraglia,12G18 JPartlow,12G18 WTravers, 11H21 SNewberry, 11F23 RAnand, 11F23 LLuther, llF23 OGC EJordan, MNBB3701 NRC Participants 't ACRS (10) FAkstulewicz, 11F23 / i PDLR:LA PDLR:PM PDLR:SC/[h PDLR LLuther/f kna FAkstul wicz Shderry-I 4 /#/93 4 /24/93 4/5//93 //7/93 0FFICIAL DOCUMENT COPY: ANAND BG&E

SUMMARY

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j 9 Baltimore Gas & Electric Company cc: Mr. Joseph H. Walter Engineering Division Mr. Robert E. Denton Public Service Commission of Vice President Maryland Nuclear Energy Division American Building Baltimore Gas & Electric Company 231 E. Baltimore Street 1650 Calvert Cliffs Parkway Baltimore, Maryland 21202-3486 Lusby, Maryland 20657-47027 Ms. Kirsten A. Burger, Esq. Mr. Michael Moore, President Maryland People's Counsel Calvert County Board of American Building, 9th Floor Commissioners 231 E. Baltimore Street 175 Main Street Baltimore, Maryland 21202 Prince Frederick, Maryland 20678 Ms. Patricia Birnie, Esq. D. A. Brune, Esq. Co-Director General Counsel Maryland Safe Energy Coalition Baltimore Gas and Electric Company P.O. Box 33111 P.O. Box 1475 Baltimore, Maryland 21218 Baltimore, Maryland 21203 Mr. Jay E. Silberg, Esq. Shaw, Pittman, Potts and Trowbridge 2300 N. Street, NW Washington, D.C. 20037 Mr. G. L. Detter, Director, NRM Clavert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-47027 Resident Inspector. c/o U.S. Nuclear Regulatory . Commission P.O. Box 287 Lusby, Maryland 20685 Mr. Richard I. McLean Administrator - Radioecology Department of Natural Resources 580 Taylor Avenue Tawes State Office Building B3 Annapolis, Maryland 21401 { Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of

Prussia, Pennsylvania 19406 I

-Q y E.. MEETING WITH BALTIMORE GAS & ELECTRIC-COMPANY-j CONCERNING LICENSE RENEWAL' ISSUES 1 APRIL 14, 1993 l LIST OF ATTENDEES i

i NAME AFFILIATION

~Rebecca Nease PDLR:NRR:NRC Raj Anand PDLR:NRR:NRC William Russell NRR:ADT:NRC i William Travers ADAR:NRR:NRC. -l Scott Newberry-PDLR:NRR:NRC-P.T. Kuo PDLR:NRR:NRC. .1 Eve Fotopoulos SERCH Licensing, Bechtel - Beth Doolittle'.- OCM/FR-Kevin Connaughton OCM/JC-t Gordon Clefton NUS 1 Kathleen. Hart McGraw-Hill ~ ' Charles Petrone NRR:RPLB David Tang PDLR:NRR:NRC' Tom Hiltz PDLR:NRR:NRC Tom Murley. NRR:NRC Rich Correia NRR:RPEB. - John Moulton PDLR:NRR:NRC Robert Capra NRR:PD1-Dan Mcdonald NRR:PDI-1 .i Ron'Parkhill PDLR:NRR:NRC Debbie Jackson PDLR:NRR:NRCJ ' Bob Borsum BWNSL 3 Lynn Connor -STS Tom Tai: Bechtel-Chong'Lewe NUS Barry Tilden BG&E Denne DiBello BG&E' Gary Detter BG&E' Pete Katz-- BG&E .Barth'Doroshuk BG&E ~. -John'Giddens --John Osborne WOG LCM /LR BG&E' .Tricia Heroux EPRI

Jay Silberg' Shaw~Pittman.

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km clos tLie.l c'. : Ufe Cycle Management Program PRESENTATION TO U.S. NUCLEAR REGULATORY COMMISSION. l BALTIMORE GAS & ELECTRIC LICENSE RENEWAL PROGRAM l 9 g 5 April 14,1993 l r s. $ w = %.m .m-.* -2 w-e,--*e*c-. - + + + < se-,vrr vw -- erw e-- -se w w- -., e-*w-e-* *,, - + - = c m-ww es -ae m -+w,..e-e wvs-e -w-- ,=2.---.__.-________-_2.ma___m_______-__. m

e. ..g h Life Cycle Management vl1*A;;;,a C LCM Program Activity Flow Diagram Formulate ocense Henewal Application Update tirSAR 3f License and Henmal / p Review Tech Spees Application Ctur ent Licensing Dasts J( 54.21(b bN bN U V V V U lCanswinent Aging Evalisadonl p nent EvaluaHon Costwedt-Implementation Subject Yes IILR Component ' Strategy I ' p ,, g ;,,g p p p p _p Structure g Systend Screerdng Uit H Matria Effective LCM I'lang Structure Aging program l Screerdng Evaluation Evaluations Assess. Short Med long No l 54.21(aM5) l tuent lf i le j I Prograns Adequate to Yee ensuee no eging Uttn f No ' l Modify Programs > 10 CFR 50.65 3.1-2 i l. 1 ..v.. ,.n ..n-.

.s 3 A*ff# Life Cycle Management ELECTRC V System Level y,,,,,,,,em, ITLR Screening """ *7'"'" Process nouncanes anc functionai PJfts Structures bestems .7 Dewstop screening Toots JO I i~ l i I Ruis Rule Rue Ruie Ontanon Cntenon Cntenon Cntenon 1 2. 3 4 I I Y Y Y Y Y No ~ ' DBE VW P RC Oa' ss 1 ~ 'Fiowenart Aunitanes AIWS 330' ~ LC Structur' Tod Tool PTS, P AM /s Tool ? Toots / Yes I fp' s.ys*em s ou,ec, No No No No By By By By m ?._ \\ 7. 7 ^ ? {Yes yYes yYes fYes Ac:t Add Ac= Add funct Funct Funct Funct - ggy ggy ggy ggy functon funcbon funcnon functon hst hst hst list l I I l Y ITG Funcnon L:st for Eacn System System No nave an l ITLR. l lunC2 ion ffj Y" ITLR Systems and Structures e 3.1-4 i l

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Life Cycle Management a-W Tool Development Tools are a compilation of all systems / structures that provide a safety related function or are relied upon in plant events Go through source documents ONCE and identify ALL affected system / structures Tools identify. systems / structures - Rolled upon in Design BaMs Event flow charts - Providing a vital auxiliary support function for safety-related equipment - Providing a Post Accident Monitoring function Providing Fire Protection (FP) functions - Relled upon in the CCNPP Anticipated Transients Without SCRAM (ATWS) ^ evaluation

Relied upon in response to a Station Blackout (SBo) event (coping phase only)

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LCM-12. Revision 2 I i LCO Screening Tool Revision 1 l safety injecten 52 The followmg RCS leakage catecuen systems shall be 1 3.4. 5.1 (Note 4) operable; cent atmesonere particulate and gaseous monitors and the cont. sump level alarm system. Shutcown cooiing toep(s) shall be operable. (Note 7) 3.3.8.1 3.9.8.2 Control Rod Dnve 55 The CEA Motion inhibit and all shutdown and regulating 2 3.1.3.1 Meenanism and CEAs shall be operable. Eiectncal Two of the following three CEA position indicator 2 3.1.3.3 cnanneis shall be cceracle; voltage divider reed switen. " Full Out* or ' Full in* reed switen, pulse counting. Containment Spray 61 Shutdown cooling toep(s) shall be operable. (Note 7) 3.9.3.1 3.9.8.2 Reactor Coolant 64 Both reactor cociant loops and both reactor coolant 2 3.4.1.1

Notes 415) pumps in each loco shall be in operation.

l At least one reactor ecolant toep, with one assec:sted 2 3.4.1.2 pump, shall be in operation. l At l east two of the coolant loops (i.e. reactor coolant anc 2 3.4.1.3 I snutcewn cochng leeps) listed in the T.S. snail be operacle. Shutdown cooling loop (s) snali ce operacle. (Ncte 7) 3.3.3.1 3.9.9.2 Area and Pmcess 77 The cent. gasecus and caraculate monitors shall De 3 3.3.3.1 ! Rad:auen Monttonng operaole with acequate alarm /tnp setpoints. ' lNete 4) The following RCS leakage detection systems shall be 1 3.4.6.1 crerable; cent atmospnere particulate and gaseous monitors and the cent. sump level alarm system. ! Nue: ear instrumentanon 78 The :ncore detecten sys. shall ce operable as specifiec in 2 3.3.3.2 i1 Note 5) T. S. l t 34 Two of the following tnree CEA positten incicater 2 3.1.3.3 f S ant Computer (SSS) enannels snal! ce coerable: voltage divicer reec switen. ' Full Out' or ' Full In* reed switen, outse counting. Tne incere cetection sys. snall be operable as specifiec :n 2 3.3.3.2 T. S. Sys: erns and St.uctures All A!! safety related snubcers shall be operacle. (Note 3) 3 3.7.8.1 Notes * (1) LCOs 3.3.3.7. 3.6.4. 3.7.11,3.7.12 are being ceterred (see 7PR No. 92-062) until the Tecnnical Spec:ficanons are revisec as part of the Tecn. Soec. trnorovement Program. These LCCs shoulc be ignored for screening puroeses for in:s revision. sc 3 of.1 BG&E LCM PROGRAM

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si -~ ei 4 E E E E E E 4 E E -W ni E. b g. c 2 ~ > n _e. ~ .!EI E .E .E 5 E-E. E E. 5 f f. em i 2l 2 2 2 f f f f f f f g _O l a C. m Wi-2 2 f f 2 2 'C, 2 2 2 _{,I U l 81 li le le if I.4 is 11 If Il is IO l: l5 l: If If l: lf l If lf 8!si le le le le le la la a le e c _. wi e 'kh E E E E E S E S u 4 l Il l2 l2 2 l2 l2 l2 l>g l2 l2 l2 e. n e e 14 14 IE la IE la E le 14 E !l! i l-l- l> l-l> l-l- l- { g ~ ce ie. "a m m.i 3 3 -l m e ec o ~ g p, a ~ es m 6 = '2 h a ge I. 2 2 g 1s g o _5 a =. 'S ~ ~ ~ ~ s w g IC10!n - u. w ; o $lw c; i w e_ l ol l4 ja, 6 ja j_a l4 l4 j~a ja l4 ~ _.> ~ 3, o: d,... gig g = .diw 3 w gem e mo MI R lC JG [I A wsC

  • s.w E

m E > = M u n m 3 5 2 ? i ~ E i l k .I .E et 7 T } 5" ? 5 31. E # 6 e 4 Y e T e i Td$ e 'b O" 2 2 2 2 i g E_ & ~8 ?? c e e B 2 e ect ? ? ? = ? e r 4 2-f E E e-Ey b

  • e

-E 2 2 2 7_ m8o

a-o C l l" f

M MCC C U f C f "*A c w F o w w m wcC C n ~.

n. ~.

n ~_ e. ~. e. n_ ~_ .n ~_

m. y u_ _n w e e ~_ e_ e n

o m m FC W sp ~$AE S& k$ &A 3 ,h m .. ~~ ~ ~~~ ~~ ~~ ~~ ~~ ~~ le lo e i-n n 1, e im + l~ m). l~ ~ ~ C tp { tC , C [ (C l@ ~ Oth 5 N E E 5 h l-IN = Clet o ed C C D

  • C C

sD l'J o = l= = v.- = - = = c v. e E f C E ce o 3 0 e u C 3 h O O E s h O [ r e m ? m g 'T. P B 7 = E e. 5 e a ~ e E.I:t c .= L 7 E = 5 c T C a o i f a p 5 lu E .= e ~ E .? 4 4 = h 3 "lE S E y ~e

  • E y

e. f* 2 3 I g 2 5 .m c C I'. i c y e L 5 12 w s: = u-C v. v. W = m ) i c.*: e s iu i i

t h Life Cycle Management =s aaa M Conclusions Summary Results S/S ITLR Because of... t Summary ~ 2 or Total Criteria DBE CLS1 FP LCO more criteria ITLR TOTAL ~ Systems 4 3 ' 3_ 3 47 60 98 - Structures 2 1 4 7 22 l 3.1-27 i =, ewe,-- -e- -. - +,.,, -w v -,rs.,-,m--.s e ww-- - eh, v- ,4 e e -v-- --we - - = - -, = .e i, * .w.-- w-- ---r.*.,.%=- -.v -, = , +, + ,e

I-l I 4 . Life Cycle Management 4 S/S Screening Comparison Maintenance Rule License Renewal Both Only Only l Systems 7* 11 *

  • 49 l

Structures 4*** 3-6 of'7 due to EOP

    • 3 of 11 are lTLR due to LCO
      • 2 of 4 are ITLR because they.are seismic class 1 Lessons Learned-ITLR-Screening and IPE results form an excellent foundation for initial MR scoping and for subsequent evaluations 3.5-4

- - ~..

F a SALtuoAE L*fe Cycle Management i C a iRo ELECTRIC v Component Level Screening Of Systems CITLR Systems From Sysem) Love Screenenc Resuria j N3enefv Demee. ITLR Svstem Funcoons f Pnmary ITLR 3 Functens CLBC l Fw %'S Saeonung Ace Detanea ITLR 3,g g,,,g gg Functions From ~ ITLR new s% e. n % Functons From P AM Cntanon 1

    • s o*==== *1La Aca Cetaneo ATLr4 N

wam ana**=e Pawa='s " Funcrons From PTS.

  • 8'********'*T**

ATWS, EQ $80. & c7,,a,, F.. ~,.c on T..s 2 - Ano Desanoa CLS 1,

  • E,1Ma PS ITLR Fu erons F om O L s:

Ace Detaneo ITLR ITLR n Functens Cmenon Fe LCO Toce i i i p 1 2 Consowcate Funcnons Weere Acoropriate h r.t.i irte c System Master Eowomsat g Funeens ; Las PTS. ATWS. EQ, 4 SBO,& Fwe CO*D0"'" No p.ote Toots Roowrea for 'a ""C*"' l Pam Oravangs f l CLB,0 h Yes v Deveco(TLR C-Ust - = DBE Few sneers Funcron Cataiogs

  • EC Usong

= items Renort Oooraung e 8struccons p7 q 3 [fTLA% ancton XX Funcon d 01 p.- c J l F . Lst of AN ITLR Components anc ime Docurrent ITLR Funcnons Tnat Resuits t Tan, Sunoon 4 ,sssssssssss Penorm Campon E.eius n oe, LC,e.nt g .o s 3.2-5 a wmmms d

r,:: 3, t I [.._ r4.., j 'l i ~.. = = }'-- ..-e- ,aO. L . O~ 3 ti e e ) ' N en w .=.

e..

h F'

a. s. O.

' = = f4 O C t 8 I a ,*..9 8 Wa W e.m 43 e ..) L r e. } h O es= u wo. t s .=,. -) .= ane. t O. r et 3 8 p # a. e= ,.. J f .c O. + b N ED. M M as M M M st I, .= e. h -~. M M M M M M

e. 4D.

aut M M DE M M M r N -R BE M as at 38 M as at k .5 .4 -e M at M at M M EE M M w r 5 d

e. M.

at M se M st M st M [ .= = .=.e M st as M at si M e et ~$ w ..=O M M as as M M at .Mo me o.- O - p. M us se et M st M O U g e. as er k e. u.e DE 31 M guI M at at DE '1 e. M M se er es .c at se en. M as og as as M M M 6 w. at at M M as pid M at W. 't, gate * ' edM M. M 3E M M M si M M t 'I w. M se es as as M. as at er i O 1 = a U W I' o t .K 4 E = c = a. e e. .=. O -a a .a .e -o 1 3., =- = a C O E

m..

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== =. .C..O. 8 a, t x t og u. a

2. -

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== u E5 4 4 k n w e e E EE r O-un a.a -T a=. 8, M a c =.w> .o 2 .9 em O .O W r E w en U E =0 .C. m D 2e C a. R.s# O 3 E E. o e. 'r W WE W J. tes.E. O .= .a a e .C

== .O. 3 O 9

  • D

.D 4 M .O. e a a O3 [ g-

e. A

=

.

KO >a 4 >r .= O OE E. .a ES .O.3 8 u. . s sw . 6 m. a. a. a. o .a - .C..e s ...e 2 l X W .O. Ow O - = = i g. 6 M w e. N ', 4 O O. O. O. - O. O. . w L e. O g.- w N M w w w w w ' N 2w 3 O.. w w e w - e = w w O. O. O. O. O. O. O. O. O. Oe W 3" =. 3 w W =l UR e.

e. '

e e e e .0 e e e c w '3 O O O O O O O O O O i .O .E, ..s .s,, .E, E.e .E,, .5 .E. a, 3O E .l s 4

} ,[. 3 h . Life Cycle Management 4 Component Level Screening L (Compressed Air) License Renewal Rule Components 535. Maintenance Rule Scope implementation a Components 511 13 . Lessons Learned -Component Level ITLR screening identifies the majority of . components for maintenance rule scope selection Additional information beyond ITLR. screening is'needed for MR (trip' initiators, IPE, EOP) 3.5-5 a..... ........- ~ . u

J 4 7 / Life Cycle Management. = = "o M Excerpt from10 CFR Part 54.3(a) Systems, Structures and Components (SSCs)Important to License Renewal (ITLR) PART 54_ DG&E AppLoa3h A. ' Safety related SSCs, which are those relied upon to

1. Class l Structures remain functional during and following design basis events

. to ensure: . (t) The Integtity of the reactor coolant pressure boundary. (2) The capability to shutdown the reactor and maintain it - In a safe shutdown condition. (3) The capability to prevent or mitigate the consequences of accidents that could result in potential offsite consequences comparable to the Part 100 guidelines.

2. Meet Seismic 11 over i design requirements' l

B. All non-safety related SSCs whose failure could d.rectly i or Flood Barrier prevent satisfactory accomplishment of required safety funcilons identified in A above. C. All SSCs relied on in safety' analyses or plant 3.' Hated Fire barrier evaluations to demonstrate compliance with the Commission's regulations for fire protection (10 CFR 50.48), environmental quellfication (10 CFR 50.49), l pressurlzed thermal shock (10 CFR 50.61), anticipated { transient without scram (10 CFR 50.62), and station blackout (10 CFR 50.63). D. All SSCs subject to operability requirements contained '

4. Not applicable

- In the facility technical specifications Limiting Conditions-for Operations. 3.3-5 r*' W w'trs'sF 1' =1M e 99' 4*N** 49 W' Y W W 'T -f* T 4 W f"P'% -*t'T1' W D'W-'N9

  • T-W Wi

'*'Td& W 1 e

  • v'=me-"i1**

'Vw'r-a v'r9.9 E.w e' t-er

2 E5382 O' Life Cycle Management 00I s ELECTRIC V Component Level Screening of Structures Start I i Y l identify Structure Functions (Table 1S) Y Y Determine if Generic Determine if Additional Structural Component ' Structural Component Exists in the Structu're Exists in the Structure Combine Structural y Components in 4 the Structure (Table 2S) l Y Icentity ITLR Structure Function of Each Structural Component (Table 3S) Y Add Structural Components Providing Support to Safety-Related Equipment (Table 3S) i Y ~ LCM-11S Screening Results (Tables 1S and 3S) - 3,g l

..y Cornponent I.evel 111.I1 Screctilng I'rocetlure for Sitticturen L.CM.11._S, fluv. l IlG. &E. 1.CM....l.'rogratil.- Unle: 1)ec. 30,1992 SlilUCTURE: Sitect 1 of 1 - - - -. -. - -.PhlMAl1Y CONT AINMEN1 Sil1UCIUllE (sys 059).. .A..jtliialile gi ITI,lt CI'.; siiiiiA

  • In tiiis lit INCI' ION I)I!SCitil"I ION 01: l'tlNCI' ION

~ ~~~l ~ ~ ~~~~ ~ ~ ~ structuie 7

11) Nt JMilliit 1

2 3

  • 1 YliS/NO t Il-S-0 t Provides stnicturnt and/or funellonni support to safety-selated ettu!;unent X

YES X YES l 11-S- 02 Provides shelter / protection to snfety-related e<1uipenent. I I1 03 Serves ns n pressure boundary ut fission product vetention barsler to protect public YES henith nnd safety in the everit of nny postulated DilEs insitie the contninenent X lil-S-04 Serves ns n enisslie lintrier (internal or exteenn!) X YES l.Il-S- 05 Provides structural and/or functionni support to non-safety-eninted equipinent whose failure could directly prevent satistnetory necornplishinent ol ony of the X YES requirnd safety-reinted functions II3:E.T99..._. ITI!"8 E."N I"0I"CU"" I'""I"' U"I"'""I II"T.r$ng gvyn(,,,,,,, _,_ _ X ,Ygg t.Il - S - 01 Provides tnled fire bnttlers to con!!nn or scintd n fine froin sprending to or froin YES ndjacent arms of the plant X

.,g -. - o h Life Cycle Management 4 Generic Structural Component List Concrete (including Reinforcing Steel) Structural Steel J Architectural items Additional Components 4 3.3-11 ~ ... ~.... .-...~.-.-

f ~.,...n. - + .j l 1 I l l -l i t 4 s i4 i i 1 W i t il i; = 8 i 3 i m ..l l i i i. g' J t i 41 s l i l3!313i .s i

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  • PPP ip L.

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  • 5: m..S, si 4

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si

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;; nii 2 csi. l wi iris o. :. e, ci: of -l : T p I' d oj '

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I.h, a * * y Congioneet i evel fi t il Oce mening I'socalte e foe Obisctis ce _.. a. liG & E l W ! t'2' ""1 I CM - I I D, Hev.1,.. 1 A11L E 33: I1EStil IG OI lit 11811alCIUllE SCilEEtitt4G ft.sv 0 SilltICillitAl. COMI'Ot4Et413 Willt DITCirlG lit il Ilit4Cllot43 liete: 1)ec.30,1992 311117C14fitE: l'lttMAltY CONI Alt 4MU41 Sitit)ClllitE (3Y3 Owl BilEE T 7, or 1/ lit it l'inttion Congiewient tionb e li t it i in.ction 11.eutgition inanwkellnelwencee ill S-B. Soittiv al Sieel ~ 1. Casons _ l.5' As hdglpt ol ettet s podlig sbuc tl &Iis hartre et pwi to safty73ehy g M ejg> 2. 11.anie ~ I.5 As begipt ol etitt e podhg ettent &Ior herti eigpl to getty-selnti a M ogit 3. Thsel>latee 1.5 As hdglpt ol etta.t e godhg ettetl &/es herti oigpt lo nafty-sehtf or ll/l egup _i ! k".' F!!"*_v. L5 ^* h87! P' d ** **

  • ePuh9 $?**l 8/? 'shi k

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  • v.

5t!&l<w he5 ! sigp? to matty-e tati te lt/l ept 89 II""3 gemy L5 As beg!pl o! ?gan g podtry gt: h

16. Claw.k es el linto.

l.5 As hdglpt of sttzts poetry stabl &for herbe eiyallo salty-selekt or M e]@> teat titR eenyonard 17.. Siniss ent inkiwe 1s. ! antes; __.-_L , _ __ L.. tAwe**g il

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. ; 2.,,1. 4.

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}

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o r-s.

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c. =-

c. = o e i 1. 1 - i. ., '!-i~.. r L: i i I '

= :-

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  1. i,
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  • g l.

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=

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.,j, 4 Life Cycle Management 4 Summary of LCM Evaluations LCM Eval Aging Eval D o n,, Salt Water Cooling Complete Complete in Progress Compressed Air Complete Complete Reactor Coolant System Complete Complete Complete Control Room IIVAC in Progress Containment in Progress Feed Water Complete Auxiliary Feedwater - Complete Reactor Vessel Complete Complete Complete Radiation Monitoring in Progress Reactor Protection in Progress 3.4-3

o j; 1 h Life Cycle Management 4 Purpose of Component Disposition Task is to identify components which are short-lived, and therefore not subject to aging Unique To License Renewal i e., components which are inspected or functionally tested regularly, and replaced or refurbished based on predetermined acceptance criteria 3.4-5 -a-. .-7.--. rw-e, .*-w... --c .+---,,.#-w- .c -.. - <, - * =--w, -.r-, w -~r.u-- uw+., e ---+- <*w- -~ - w ~ w+e w- -. +.. +-=w- ,-e+ v++ww w - +s %. ce -se -e <m,,,--, w-->~-

) 3, h Life Cycle Management 4 Purpose of Program Adequacy Evaluation is to determine.whether existing Programs adequately ensure that component replacement or refurbishment will occur before the component is subject to aging UTLR. i e e 3.4-6 ............ ~

.} 4 Life Cycle. Management 4 Components Not Subject to Aging UTLR Components Subject to Aging UTLR ,s Components neplaced or Refurbished Based on , Predetermined Criteria Components Not Subject to' Aging UTLR S 3.4-9

y 3 7,. 4 Life Cycle Management 4 Components Not Subject to Aging UTLR Components which are replaced or refurbished regularly will never experience any degradation which is different in character or magnitude or any new degradation mechanisms which only occur after year 40. l Inspection or functional testing governs equipment replacement or t refurbishment based on predetermined acceptance criteria. - Component performance, and, indirectly, component degradation never reach an unsatisfactory level. - Controls under 10 CFR 50.65 ensure that il maintenance programs fail to control equipment failures, a root cause analysis will be performed. The causes, be they age-related degradation, improper operations, improper maintenance, or some other reason, will be corrected as required under Section (a)1 of 10 CFR 50.65. 3.4-8 l ~

~ O ??# Life Cycle Management ELECTmc v Component Evaluation l Correlate Program Attributes to Components l Y l Determine ' if Component No Replace / Refurbish Based on I Predetermined Criteria -Y + Aging Yes Evaluation y Document Programs for . Adequacy 1. Ensure R/R Before Unacceptable Performance Occurs 2. Contain Specific Criteria for R/R 3. Implemented by Procedure l Y ' Review Performance Results with Annual Maintenance Rule Assessment 2.2-12 l i

t { T g 4 1 4 4 3 hoe e s R r e w 'T L s t s s r t s t i r o r .e s e nt m e e s st s 4 s r e a y s s r t r t U r e t medm i a. a c nt oi e i m ol l nt m m ~ l os t e r e a s s a r y sl g ct a nEInRT r min e c o n i i n d oe a e e e e ed al f l l r p s r r r r r n nCRT u u u uEI T p n i I g e e ee a a a a nnn u a t t t t r r r t r r r r r oo oS Tr ~ s A uuu u e e e eiii r w t t t l s s s s pp pp a a a el e wat s s s s mmmmb b b ome r r r o e e e e a w r r r r e e e eiii N PPPPTTTTVVVPSH w + +, s s r w e e t t er i p s s m y r r t s s n e n 4 e T l t-r a s e s s e s or l + r r s r ro e m mt T r e r 's + t o r e t gR. e l u r ni o l i ol t ms o r a oi l a st o s c c ma t t s t r l a r y s e s A C D_r T t ct i i nla n c n n e d r i v nlad o e ra o oie e e w I r r r r r p e AInCRT sC a uu uO s p e D u 'e o o al s s sV n r e s s s l l l l l l e e e e r i c c t t e e eO a v v v v v c o ou r r r + e e e e ei SL L L L LMML NPPPM e t t e n tn e s e e n v m -= s l o a e V e = g p g c r d n st i + o v s a m e nt n i. s e r p h e a n ai e D s e c mi el c l a o HP v e t ed n h o sl M i e a wl n o ct l l r ~ C l l a a vV S E i t n I t i e mmlad r r a wo n e e r l lc S SSVi o o z z e o SC s eef ni y yk s s r y C m m.l ei a a ed d e t i e al l l C s eiC s n nt i l o& u a a e R ooe oo n n r CI FHHM e SSRSP AAB f iL ~ i = a, m

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. J -nh Life Cycle Management a =+ M RCS Component Device Types - Potentially:UTLR Heat Exchangers Pipe Check Valves Control Valves Large Hand Valves MOV Valves. Pumps' Pressure Vessels TE Thermowells i ' 3.4-15. ~.., _.. _.. _. -. -... _... _ ~.. ._-..._,-_.___...-~-..__.-__.__.-_--..__,.___.u_2.-.u..._.---__._,.._._._.__.-._.-..a.__-.

x g I h Life Cycle; Management 4 Program Adequacy Attributes of an " adequate" Maintenance-Strategy: 4 - Discovery Assessment / Analyses - Corrective - Confirmation / Documentation If; program is not adequate, - recommends changes

OR

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  • wwal-

= awwmr. w-e- ne a e~ g-se ~--=-w- + -ow~ee-+ = -+--.-*A ..a-sm e

~ Life Cycle Management 4 Program Adequacy Criteria Criterion 1 - Adequate programs must ensure that the SSCs identified as important to license renewal and that contribute to the performance of a required function, or could, if they fail, prevent an SSC important to license renewal from performing its required function will be replaced or refurbished before they are subject to aging unique to license renewal. Evaluate the PA or task for adequate technical detail (s) Is the DISCOVERY PA or task frequency interval less than the shortest ITLR System Function failure time? Does the PA or task demonstrate historically that it is adequate in maintaining the important function (s) for the identified groupings (i.e., the component failures have not caused ITLR system functional failures prior to replacement)? ~ Historically, are all maintenance preventable ITLR System functional - failures detected by the PA or task? 3.4-21 --=w-r- .,nws - - - - + ~+--e-v.s m-w e r w-e'w=.w~--===,--~,-w+r w-*- .+cew.m.e-e-w,--**.--w.c--w ee- -n , eon +.,==- e w +w.e--e =we-*-e-==+was .cma-e-- e~w-*-- -e---usic w --e ve + w s ..-+<v-wag-re-e+ e- --+ - r e,eet

S .y L h Life Cycle' Management 4 Program Adequacy Criteria l (continued) Criterion 2 - Adequate programs must contain acceptance criteria against which the need for corrective action will be evaluated, and ensure that timely corrective action will be taken when these 3 acceptance criteria are not met. i For. pas or tasks that do not have a fixed interval of time for replacement: Does the PA or task have an action or alert value or condition-parameter to determine the need for corrective action? - Does the. action value or condition provide sufficient indication of -degradation to reasonably conclude that there will not be an ITLR system functional failure prior to the next PA or task? - Does the PA or task ensure that appropriate corrective action is taken? 3.4-22 ..... = -...--.:.-.-.-.....----.--.a.-.-. -----.-----.-..-

.p ..,, 7 --t 4 . Life Cycle Management 4 Program Adequacy Criteria (continued) Criterion 2 - (continued)' For All pas or tasks: Does the corrective action receive proper work prioritization, -s'cheduling and completion on schedule, or are positive alternative actions identified?- Does the PA or task-have a confirmation process that ensures corrective action is taken? 3.4-23 ...--,;..=..-.--...:..-.-.,.-..................-. ....~..a.a-.-.,-,..-. ... -... - - -.. ~. ~.. -. ~

r .y x e Life Cycle Management 4 Program Adequacy Criteria (continued) Criterion 3.- Adequate programs must be implemented by the facility operating procedures and reviewed by the onsite review committee. Evaluate the implementation and review process of the PA or task. -- Does.the PA or task.have a review process? - - - Does the PA or task have a change / revision process? -. Does the PA or task have an approval process? 3.4 _, -Awa==r-'De'ta-w=+"a 4**-a46e=e+W ee4* W e-N4-u.yge g r ggy r+ dl^ - -.y -ty>+v (w vy w e ymy$w % we-% w.ew - J; v m.-. W we m -e.:=4---',c -m % ew e".--o.-irwWT*w 9Tv*W-- W %Yw w-ay%se or-- .H. m w,, e'iapi%-_s__waww s(mmy.'ew We-spis*+__mav-44-M er-*==per-CevwSDw _m u rWevua*v'- "6. m

e c64-l'Y-l'l!-01. l.CM Cinn;>onent livaluation 1.Chl-10 Attacionent il itevision 2-Existing l'rogram Atlettuacy SYSTliM NUhllllill: '064 GitOUl* ID: 064-l'Y-l'li-01 COMPONiiNT ID Olt SilllCohlPON!!NT ID SYSTiihl NAMii: Ill!ACTOlt COOI. ANT li'Y 103, l l'Y 103-1, 21'Y l03, 21'Y l03-1 I.IST 01: Al'I'i,1CA111.l! DOCllMl!NTS (NOTli: II ADDITIONAL SI'ACli/I.INI!S AltII N1!I!Dl!D, USli A SliCOND SillitiT.) l'A/TASl( ID NAMli iti!I'I.ACliMI!NT I:ltt!QUl!NCY l'A IsilliQUliNCY ON TIMl! / ONCONDITION / NA val.Uli i DISCOVlillY STI'M-67211-l(2) l'ressuiizer ItclieI Valve l X Monthly (IlllV) MI'T Channel l Ironctional Test j j l l 1 i l l 1 1 ASSliSSMl!NT/ STI'M-672il-1(2) l'ressuiirer Itclief Valve (liRV) l l X Monthly ANAL,YSliS M PT Channel l'unctional Test l l 1 1 l l 1 l-l l l COltilliCTIVli M N-t-101 Controls coricetive maintencnce l X l As necessary initintcal ley STl* { j CCI-104 initiates Mit to connect l X l As necessney innifunction or out of tolernnec l l contlitinn iliscovercil liy STI' l l l 1 l l l l CONI lltM ATION/. CCI-104 Coinfinns cinnpletion of STI' l l X As necessary DOCLIMl!NTATION. nnit transfer of cinnpleteil STPs l l to Plant llistory l l i l l I'AUliI 0124

y. 064-PY.PE-01 LCM COMPONENT EVALUATION LCM 10 Revision 2 , 1 (cont'd) CRffERIA REVIEW: Criterion 1. Adequate programs must ensure that the SSCs identified as important to license renewal and that contribute to the performance of a required function, or could, if they fail, prevent an SSC important to license renewal from performing its required function will be replaced or refurnished before they are subject to aging unique to license renewal. 1.1 Evaluate the PA or task for adequate technical details (s) 1.1.1 Is the DISCOVERY PA or task frequency interval less than the shortest ITLR System Function failure time? X YES NO NA i Description / Basis: The Maintenance History documents the lowest known failure time as occurring to IPY103 1 over a two month pe:iod (reference W.O.19005115 and 19003585), which - is greater than the monthly task interval frequency. The failures did not cause an ITLR system functional failure. 1.1.2 Does the PA or task demonstrate historically that it is adequate in maintaining the important function (s) for the identined groupings (i.e. the component failures have not caused ITLR system functional failures prior to replacement)? X YES NO NA Description / Basis: All failures of the components in the identified grouping were discovered by the PA according to the Maintenance History. Because the f:ilures did not cause an ITLR system functional failure, the PA effectively mitigates aging degradation of the system. 1.1.3 Historically, are all maintenance preventable ITLR System functional failures detected by the PA or task? X YES ,,,,N O _ __N A Description / Basis: All failures of the components in the identified grouping were discovered by the PA according to the Maintenance History: therefore, the PA detects. all maintenance preventable ITLR component failures. Criterion 2. Adequate programs must contain acceptance criteria against which the need for corrective action will be evaluated, and ensure that timely corrective action will be taken when these acceptance criteria are.. not met. PAGE 2 OF 4 3

y 064-PY-PE-01 LCM COMPONENT EVALUATION LCM 10 Revision 2 , 1 (cont'd) 2.1 For pas or tasks that do not have a Exed interval of time for replacement: 2.1.1 Does the PA or task have an action or alert value or condition parameter to determine the need for corrective action? X YES NO _NA Action / Condition: He PA contains alert values for the operator to identify when the component has " failed to test" and corrective action should be initiated. 2.1.2 Does the action value or condition provide sitf5cient indication of degradation to reasonably conclude that there will not be an ITLR system functional failure prior to the next PA or task? X YES _ NO _ NA Basis /

Reference:

The components under test are located in independent channels. Because the system's integrity is not compromised if a single channel " fails to test" prior to th,e next PA, the alert values provide suf5cient indication of degradation to reasonably conclude no ITLR system function failures will occur prior to the next PA. l 2.1.3 Does the PA or task ensure that appropriate corrective action is taken? X YES _NO _NA Basist

Reference:

He PA initiates a maintenance order in accordance with CCI-104 to replace or refurbish as a direct result of " fail to' test". 1 2.2 For J1 pas or tasks: 2.2.1 Does the corrective action receive proper work prioritir.ation. seneduling and completion on schedule, or are positive alternative actions identiSed? t X YES NO NA Basis /Rxference: All STP-related corrective action must be performed in accordance with MN 101 which implements procedures for prioritizing, scheduling and completing corrective action. ' i -2.2.2 Does the PA or task have a countmation process that ensures corrective action is tnken? X YES NO _ NA i Bnsis/

Reference:

All STP-related corrective action must be performed in accordance 'with CCI- - PAGE 3 0F 4 i

  • 1 q

i =. 064-PY-PE-01 LCM COMPONENT EVALUATION LCM-10 Revision 2 l ! 1 (cont'd) 'F 104 which implements procedures to conSrm correenve action has been taken. f e Criterion 3'-Adequate programs must be implemented by the facility operating procedures and reviewed by the onsite review committee. i 3.1 Evaluate the implementation and review process of the PA or task. NOTE: l If the PA or task is covered by one of the following site procedures, then answers to 3.L1,3.1.2, and'3.1.3 l are YES. i CC1-100 covers implementation of all CCIs. i i PR-1-!n0 covers implementation of Administration and Tech. Spec. related programs. i pR-1101 covers implementation of PMs. ETPs. FTs. PTPs. STPs. t 3.1.1 Does the PA or task have a review process? Y YES NO NA Basis /

Reference:

The PA is an STP and is covered by PR.1-101. 3.1.2 Does the PA or task have a change / revision process? Y YES NO _NA Basis /

Reference:

The PA is an STP and is covered by PR-1-101. 3.1.3 Does the PA or task have an approval process? h Y YES NO NA-i Basis /

Reference:

The PA is an STP and is covered by PR-1-101. t - }; i i These items will apply to _ upper level EGrE procedures that. _l 3 develop, implement, and control lower: level PA(s) and' tasks. l PAGE 4 OF 2 ' i .i i '.{

O' Life Cycle Management sids ELECTRIC v Aging Evaluation Flow Chart Group components for Aging Evaluation - Design - Material - Environment i Y Subdivide component group into succomponents i T List aging mechanisms whien need to be evaluated

44. %

Resolve aging matrix for plausible aging UTLR Yes lausible No and Unicue l Aging? Effective Program Not Recuired, Does an existing No plant program address the aging? y Develop attribute of a Yes y new program to manage Evaluate effectiveness of the plant programs the plausible aging Accresses aging mechanisms . Contains alert values requiring correctiv's action . Managed by on-site processes 4.1-8

LCM COMPONENT EVALUATION LCM-10 REVISION 0 ATTACHMENT S SYSTEM NUMBER 064 SYSTEM NAME REACTOR COOLANT SYSTEM COMPONENT-ARDM MATRIX COMPONENT OR SUB-COMPONENTS APDMs 064-064-064-064-064-PUMP PUMP PUMP PUMP PUMP PB PC PD PE PF Fatigue PA PA PB PA PA Thermal Emori ttl emen-PN PN 112 PF 101 Mecnanical Wear PG PG PJ PI .102 I l Corrosion 109 109 109 109 108 !PD 111 111 104 Erosion PD A: Neutron Emori -lemen-105 105 105 105 105 Creep ,106 106 106 106 106 Stress Corrosion 107 107 107 107 107 Cracking Stress Relaxa: ion 110 110 110 110 110 l l l t PAGE OF ATTACHMENT 5

} h Life Cycle Management 4 Developing Effective Program Attributes Review list of Programs / Activities for aging mechanisms and aging management alternatives which address: Discovery. Assessment / Analyses Corrective Action Confirmation / Documentation andLsatisfy the following criteria: 4.'.28 i i i ..mm. -m. -. m .;m- ..2-= m +____m_m.-m., _ _ - m w~ u , *,,_... _ -=,- --- m m. .+ + - -.vi ws-=.-... =.-+,wer. .sw. u ..m = =.- - ..-.et-,r e -. m er

  • - m.-w-

~ e.7 4 / Life Cycle Management 4 Program Effectiveness Criteria Criterion 1 - Effective programs must ensure identification and mitigation.of age related degradation unique to license renewal for the SSCs identified as important toilicense renewal, or could, if they fail, prevent an SSC important to license renewal from performing its required function. Discovery Basis:' - Is the. DISCOVERY PA or Task frequency interval less than the shortest know-failure time?. -Does the PA or Task demonstrate historically that it is effective in 1 mitigati_ng aging degradation of components.(i.e., has the aging. mechanism. caused an ITLR functional failure)? . Does the PA or Task identify and mitigate all relevant age management issues? 4.1-29 n.,.,.... -. ..--.,..,~~.;-,...-.--:,.~....+,,.- ,---a~-. n. a.. -. ~. n a ,.., -. -,. ~,.

.:i + h Life Cycle Management 4 Program Effectiveness Criteria (continued) Criterion 2 - Effective progams must contain acceptance criteria against which the need for corrective action will be evaluated, and ensure that timely corrective action will be taken when these acceptance criteria are not met. Assessment / Analysis Basis: Does the PA or Task have an action or alert value or condition parameter to determine the need for corrective action? Does the action value or condition provide sufficient indication of degradation to ensure that there will not be an ITLR System functional failure prior to the next PA or Task? Corrective Action Basis: Does the PA or Task ensure that appropriate corrective action is taken? Does the corrective action receive proper work prioritization, scheduled and completed on schedule, or positive alternative actions identified? Does the PA or Task have a confirmation process that ensure corrective action is taken? ~ 4,i 30 m,..-... .....m.,, -- L.

? m.j,. 4W Life Cycle Management 4 Program Effectiveness Criteria -(continued) I-Criterion 3 - Effective progams must be implemented by the facility operating procedures and reviewed by the onsite -review committee. Confirmation / Documentation Basis: Does the PA 'or Task have a review process? Does the PA or Task have a change / revision process?- Does the PA or Task have an approval process? o 4,1-31 ...-._...___...._.,..-._._~m

1 .*). .? i Life Cycle Management Program = j Summary for CAS, AFW, FW and RCS Components. j Total # Components 11370 (100 %) i [ Total # ITLR Components

  1. On Hold 4742 (41%l e3 (< 1%)

.i .i ' k. r Af 't <i': k& .g 't h j = Could not be a- ~ -4 i Uniqueness Rev.iew subj.ect to 4 -= 4 79 (41 %) 5 i ARD-UTLR . sh i Q 4 "'?g g by pw g: ' 2e 3 (23%)

?

.g Ifd6$i!#14ifi@.5MS$2%In[

9. :.

-v Potent. lly Reg uj non-Reg-F ia Subject to 4 1 *1. i I 5 I, - t p, "* " **4, ARD-UTLR y g- . gggggm:4 201 ns*> ygpder $nenwn:! Main enanc,eiRUiEsf Un wn~ ~ w--w i r Aging Study- - AFW/FW Not Evaluated. l 201. nasi y 1080 (10%)/ [ m -i ' Effective Program Review - 1 i s3e ( %> 1 L Reg'_ non-Reg. No Prgm Reqd 14 (0.1%) 922 (7.9%) - 0 (0%): i b b E v v r w

7pg ALL PLANT EQUIPMENT . 54.21 {a;u'1?: SCOPE REVIEW + ~ ao* 54.21 {a;u'2?: FUNCTIONAL REVIEW ~s* p L 54.21 (a u'3}: UNIQUENESS REVIEW + lll 54.21 (a;u'<5}: EFFECTIVE L PROGRAM REVIEW ~ss 2 . ~ . ~... -

l) s 54.21(a)(3): UNIQUENESS REVIEW Not unique to is or could be unique license tenewal 54.21(a)(5): EFFECTIVF_ REQUIRES EXPLICIT.ID PROGRAM REVIEW AND EVALUATION BY . APPLICANT AND FOUND ACCEPTABLE BY THE NRC (54.3)- FUTURE ACTIONS REQUIRED NO YES , e , e NO TECHNICAL. SPECIFICATION PROGRAM NEEDED. OR LICENSE CONDITION LIC. COND..OR TS (Few SCs) PER 54.33(b) TO ENSURE NO ARDOTLR & TO MAINTAIN THE CLB Example: One-ti_me ' Inspection of tanks

  • little or no corrosion Example: tieplacement al fixed intervals 4 e.oM

... _, _,.... -,. ~ _ -... ... ~.. -,.,. - - .--,..--4 --e..

.[.,jD ~ 65% - ~* l L54.21(a)(5):iEFFECTIVE PROGRAM REVIEW ~5% Some SCs Most SCs

  • EXISTING PROGRAM
  • ACCEPTANCE CRITERIA IN L

ACCEPTABLE, BUT EXISTING TS OR REG. AND L NO ACCEPTANCE INCLUDED IN MAINT. RULE. CRITERIA IN TS Minimum information provided. .OR REGULATION Additional information provided. l Very few SCs Very few SCs 4 r

  • NEW PROGRAM
  • NO PROGRAM F

- REQUIRED NEEDED Detilled information provided. Detailed information provided.'

  • Must ensure CLB is maintained during renewal period a

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