ML20050B618
| ML20050B618 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/22/1982 |
| From: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0694, RTR-NUREG-0737, RTR-NUREG-694, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.A.1.3, TASK-1.B.1.2, TASK-TM NUDOCS 8204060137 | |
| Download: ML20050B618 (23) | |
Text
{{#Wiki_filter:_ THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P o Box 5000 m CLEVEL AND. OHlo 44101 e TELEPHONE (216) 622 9800 m ILLUMINATING BLDG e 55 PUBLIC SoVARE Serving The Best Location in the Nation Dalwyn R. Davidson VICE PHES4Df hi SYSit M E NGINEFFilNG AND CONSTRUCTION \\M, b N@ c March 22, 1982 10 6 A. Schwencer I Chief, Licensing P anch No. 2 p,F R b, gp 22 7,. p,3 Division of Licensing e y :9 @h i ,*e r /' U. S. Nuclear Regulatory Commission t y'd Washington, D. C. 20555 / 6 f. Nl,, Perry Nuclear Power Plant N Docket Nos. 50-440; 50-441 Response to Request for Additional Informat, ion - Management Organization
Dear Mr. Schwencer:
This letter transmits our responses to a January 6 letter in which 18 questions were posed by the NRC Licensee Qualification Branch on the Perry Nuclear Power Plant Site and CEI Corporate organization. We are currei.tly revising Chapter 13 of the FSAR to incorporate our responses to the LQB's questions. An amended Chapter 13 will be transmitted to you as soon as it is completed. Very Truly Yours, / Dalwyr R. Davidson Vice President System Engineering and Construction DRD: mlb I ,200 cc: Jay Silberg yy John Stefano Max Gildner / l Eric Pedersen 8204060137 820322 PDR ADOCK 05000440 A PDR
- = i 630.1 Ex;:and figure 13.1.1 "CEI Com;.any Or;;1nizat ion" to include j (13.1.1) -the Independent Enginering Review Group as required by NUREG - 0694 Item I.B.I.2. i l I ?!2 P nyte l 1 i Figure 13.1.1 "CEI Company Organization" will be revised to include the Independent Safety Engineering Group. l i f r "v--r----w- -,o,
i o 630.2 It is our position that a corporate officer sh:,uld cicarly (13.1.1) be responsible for nuclect activities, without hwing ::ncillary responsibilities that night detract from his attention to nuclear safety matters. The System Engineering & Construction Group Vice President appears to have anc.illary duties which conflict with our position. Pl<ase elaborate on his current ancillary duties and plans to rneet our above position. Resnonse Six months prior to fuel load of Perry Unit 1, the Nuclear Group Vice President will be named whose total responsibility will be r.uclear power activities. I l l t I l l l l l { i t I l E v
g _. f i 1 630.3 Perry Plant Department's respcusibilities or imiirect lines i (13.1.1) 'of conmunication with the Power Supply Group Vice President need'to be explained as far as the interface between the System j Engineering and Construction Group and the Power Supply Gsoup i as relates to.the Perry Plant De,;artment. -{ i
Response
Perry Plant Department's responsibilities or indirect lines of communication f with the Power Supply Group Vice President are through the Systems Dispatcher I l1 in the System Operation and Test Dcpartment, similar. to the lines --of ccmmuni-l cation involving other CAPCO generating units. Outage scheduling is coordi-nated through the Maintenance Planning and Scheduling Section in the Production f Engineering Department, likewise under the Pcwer Supply. Group Vice President. Other regular communications between the Power Supply Group and System Engineering l and Construction Group as-they relate to Perry Plant Department are disseminated i through cormaunications councils or directly between group vice-presidents. { i f l t i I l t .\\ I I i t l i l i f i \\
630.4 Elaborat e on the support services provided by the (13.1.1) NSSS supplier during the fuel loading and startup testing phases of operations. l
Response
Initial fuel loading and nucicar system start-up and operational testing will be performed by CEI. General Electric field representation will provide technical direction on a continuous three-shift basis from the loading of the first fuel assemblics into the reactor vessel until the full load warranty run. As part of technical direction, General Electric will provide start-up test specifications, start-up test analyses and start-up test instructions for the nuclear boiler system. The start-up test specifications define the minimum test program for safe and efficient start-up of the nucicar system. The specifications specify the performance of the described tests. Start-up test specifications provided include: chemical and radiochemical, control rod drives, fuel loading, shut-down margin, radiation measurements, vibration measurements, control rod sequence, source range monitor performance, intermediate range monitor _ cal-culations, reactor vessel temperatures, system expansion, main steam isolation valves, process computer, r eactor core isolation cooling, high pressure core spray, recirculation pumps and jet pumps, flow control, turbine trip, generator trip, pressure regulators, bypass valves, feedwater pumps, flux response to rods, local power range monit or and average power range monitor calculations, calibration of rods, axial power distribution, rod pattern exchange, steam flow, and heat rate. The start-up test analysis contains the data needed to carry out the start-up testing activities. The start-up 7nalynis includes (1) methods, data, and calculations: aids for use in the control room to determine critical core performance parameters such as fuel assembly flow, pc.er, quality, etc.; (2) calculated core power distributions and control rod patterns; (3) control rod worths for use in determining shutdown reactivity margins; and (4) methods and l data for calibrating in-core nuc! car instruments. The start-up test instructions present the recommended test method and describe the steps for performing the test defined in the start-up test specifications. The start-up test instructions also contain criteria for judging the test results, where applicabic, and planned data and calculation sheets which provide for site analysis of the data. Instructions will be provided as a complete set for each test required by the start-up test specifications.
630.5
- GEG - W37 Sec ion 1. A.1.1 establishes the requirer.ernt (13.1.2) for a Shift Technical Advisor..In the future, this pos' tion may be phased out as operator training and experience are upgraded to a level 1.hich has not yet been established by the Commission.
Based on the lack of operating commerical nuclear plant experience of the operating sinf f arad the Commission's position, your" proposal to fulfill the STA function with the Shift Supervisor is unacceptable at this time. . Provide a position descriptian for the STA and include a description of the STA training program. F3spansg The Shift Technical Advisor position description and training program are as follows: P si_t_!pn_A scrjptfon_- Shift Technical Advisor P _B a s_ i c _Fu_n c. t i o. _n s_ l l Provide shift technical support to the Shift Supervisor. I Supervisor on 11 e saf ety status of the plant, diagnose plant Advises the Shift 3 accidents and recommend actions to mitigate the consequences of accidents. ggporting Re_la_tionships l Reports to the Shift Supervisor in an advisory capacity. As such, has no direct supervisory responsibility or authority over any employee, j Primary Responsibilities { 1. Maintain an awarener.s of the safety status of the plant.. l i l 2. Assist the Shift Supervisor in the areas of thermal hydraulics, reactor l engineering, plant transients and power response, emergency procedures and plant Technical Specifications. 3. }'eep informed and updated on all problerts, changes or trends important to I the operation and safety of the plant including periodically reviewing ( specified documents. 4. Assist in the accident assessment function. I i i i i I
S. "aintain a log of events that-includes stat.aemts of t.atch relief and turnover, significant plant ch onys, dvice ;;!ven to Le Shif t Supervisor and any~other information of historical or training value. 6. participate in shif t turnover br iefings of the Shift Supervir.or. ~ 7. Assure capability for ' reporting to Control Room within ten minutes of notification of an event requiring STA attention. Qualifications 1. Bachelor Degree in Engineering or related sciences or High School diploma and sixty (60) senester hours of-college-level education in mathematics, reactor physics, chemi st ry, r.. ate ria l s, reactor thermodyr.amics, fluid nechanics, heat transfer, elect rical and reactor control theory. 4 2. One.(1) year professional level nucicar power plant experience. Six (6) nonths experience shall be on site, i 5.0 E_Ub.. _Q$Tp,,,_ h f h [p,CInit'a}_,A d_V i_s,o_r, J The STA will complete instruction designed to provide the expertise delineated in the STA posit ion descript ion. This will be accomplished through completion of various 1cvels of inst.ruction (as. indicated in FSAR Figure 13.2-1) including Perry BWR Technology (38) and pertinent portions of On-Site Training (X1) dealing with FSAR accident analyses, Technical Specifications, normal and off-normal operating procedures, and Perry systems construction and operating modes. Additionally, the STA will receive training in the areas of: 1) Mitigating Core Damage (AS). 2) Emergency plan provisions and procedures detailing the STA's actions and the act ions _ of cont rol room personnel in the event of a site emergency. l l 3) Formal instrnction in the areas of reactor physics, thermal hydraulics, core flow, and tore pm.er response. i 4) Specialized instruction in the theoretical subject areas of thermo-dynamics, beat transfer, fluid dynamics, and reactor theory. (This academic instruction shall not be repeated if the individual has com-l pleted college instruction in each area or is previously NRC licensed or qualified as a U.S. Navy Engineering Of f icer of the Watch (E00k')). l 5) Control Room Simulator instruction designed to provide familiarity with control room instrumentation, controls, p:oceiures, and plant systems i response. i l l 1 -. = ~ - -
o 630.6 Operating experience has shown that units with five operating (13.1.2) shifts have experienced problems with accomplishing training during their "tcaining period" due to the use of personnel to cover on shift vacancies caused by sickness, vacations, etc. Explain in detail those measures taken to ensure uninterrupted training periods or go to six operating shifts.
Response
The Perry goal is to staff the operating positions to support a six shift operation. In spite of the industry manning shortage, the experience requirements, and the' unknowns of the future (i.e., retention and licensing success rates), attainment of this goal is not viewed as impossible.
- liowever, adequate training periods can be provided at Perry through the u e of five operating shifts plus two extra personnel.
Since the operating crew is com-prised of relatively young employees, most are entitled to only two weeks of vacation per year; in addition the sick absence rate of this group have been very low. Two extra operators, therefore, would be alle to provide vacation and sick relief. This would allow the fifth shift to achieve four days of training per week. Ilonce, any one individual would receive 40 days per year of training;, which is judged adequate. i I ,e- -rw--,..,-,,.--+,,a --,,r-n,-,,.r --.--..,,,n, ,- + -e-- .-.--,--r--
3 i i. } 630.7 T..'. p. u 13.1.2.5 to d.n 'ldit o.Ir:g for i m,,' nit i 5 (13.1.2)
- nd Unit 2 to encorpast op through full oporaticos cf L: th 4
units. EOSPODSS In the attached "anning Table, the column headed " Units 1 6 2" lists the l intcaded manning levels with both units in operation. Note that. this,anning l exceeds that specified in NUREG - 0737 for a two-unit plant with one control room. Whereas 0737 wot.1d require a total of 1 Unit Supervisor and 3 Super-vising Operators, CEI intends to provide 2 Unit Supervisors and 3 Supervisin;; Operators. } The shift staffing described in the FSAR Sect. ion 13.1.2.3 for the Perry Plant control room, with two units operating, provides for six licensed personnel for the two units; three SRO's and three RO's. This. staffing oxceeds the i SUREG 0737 Interim guidance staffing icvel for Two Units, One Control Room configuration by one SHO license and is less than the interim guidance staffing icvel for Two Units, 'Two Control Rooms by one R0 license. .The original Perry Plant cont rol room design was arranged for optimizing the 4 human factors impact for operators moving from one unit to the other in the single control room. This was he basis for arranging the two control boards i side by side with identical positioning of all operating devices located on each control board. Ar, a result of fire prote: tion considerat. ions, a perti-tion was installed between the two control boards with a normally closed door in the part it ion. To accommodate the impact of this partition.and for more j effective command and control during emergency operation, an SHO has been added to each shift crew. I For starting up or shutting down a generating unit, two R0 licensed operators are normally required. With three RO's available each shift, one RO will be regularly assigned to each unit with the third R0 availabic for assignment to the unit which may be starting up or shutting down, It is not normally expected that both units would be in that mode of operation at the same time. If such would be the case, an additional RO will be provided by-calling out or holding over an extra person if not available on shift. Thus, it does not r ep r e r.c nt the proper utilization of critically skilled manpower to require fulI time on shift the fourth RO 1icensed operator for those rare instances when he or she would be needed. Therefore, exception is taken to the interim i staffing guidance for Two Units, Two Control Rooms as tabulated in NUREG 0737 1.A.1.3-4. 6 ,-m.<- w w-.. -, . -...., - - +, n n .,p
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. ~ - - .... ~. J d j j 630.6 NW:EC - 065t-r m;u i ., 'Mt to amat the minimus. st :sifin!; (13.1.2) require.m nts for a r.uclear power plant.cmergency, an eier.trical i rna int enan ce/ ins t ru.r.cnt and control technician be on shift. Explain how this requirement is going to be implemented. E spon.sj! ll As required by.NUREG - 0654, the Perry Plant Department staff manning require-3 ments have been revised to include an Instrument and Control Unit Technician-on shift. This technician will be qualified to ANS 3.1-1978 requirements. t i r I L I T C I f i i 4 't 4 .,_,,.,..-]__.,_,. _,._,,,s ,,.r_y.,_,. _,,.,.,,,,.o
7 _ __ %._ _._ _. _ _...._. _. _ __ _._--- - _ _. _.. _ _ _ _. _. _ _ _ _ _ _. ~. _. _ _ _ _ _. -.. _ _ _. _ _.. _.. _ i Ip* ( ? I s-t i "r.ERY M ?NT iiEP/.i:r;ENT I i t-S!ilFT STAITING ) ?10 DES 1,.2, 3 i l [ l l i l. UNIT 1 UNITS 1 & 2 .j Shift Supervisor (SRO) 1 1 y. 1 f Unit Supervisor-(SRO) 1 2 f } Supervising Operator (RO) 2 3 l Perry Plant Operator (AO) 1 2 l Perry Plant Attendant (AO) 1 2 Radwaste Technician 1 1 lb alth Physics Tecimician 1 1 i l Chemistry Technician 1 1 I i 1 6 C Technician 1 1 j-Shif t Tecimical Advisor-1 1 1 3 I. i Total 11 15 l 1 i i f i t } 3R0 - Licensed Senior Reactor Operator l 1 RO - Licensed Reactor Gperator E i AO - Auxiliary 0;ierator i I 1 4 h k i t i l l kI l
. - _ _ _. _ = _. _. _ _. _ _ _. _ _ _ _ _ _ _ _ _ _! 1 r z c< fi30.9 A review of the re m.ca of.the Perry staf f indicat es a i s (13.1;2). gross lack of.cpers.1ing nucicar plant experience. 4 t I In such cases, it is.our position that the staff be augumented with personnel expericnced with EE start-up and power i escalation. Present your-plans in this regard detailing the. staf fing and' qualification requirements you intend to l l Inplement. i 1 i f.f i ( j -t l Rosnonse j A person with operating nuclear poser plant experiences will be obtained in' l l either an advisory capacit.y or. integrated into the plant organization as l l. Superintendent, Plant Operations for at least cao year in advance of fuel load. This person will serve as a member of the Plant Operation Review Committee, and if not a permanent nember of the Plant Staff, will remain in l place at least for 12 months following fuel load. In addition, cach operating shift will have assigned to it'a person with l cc::cercial BWR start-up experience during the period from fuel 1 cad until 100*l,. power is attained or for one year, whichever comes first. i i l l i J i I s ( I-i f l i I l I-i t 1- _., - - -.. ~ - -, _,, _ -.,---.-,..~.-.m._.,_~._____ -..-- u -.
6'30.10 s.p i c3 i r. p :m for r.:affing support y m itions at.: t: (13.1.2) of poc.t start-up of Unit 1 when rescortes will br: split bet
- een operational sup;, ort on Unit I and, tart-up support for Unit 2.
i ES5P!B53" 'The Perry ;uclear Power Plant Site Organization will reorganize prior to fuel load for Perry 1 to separate the nupport functions for Perry I start-up and epnration from the support functions for construction of Perry 2. Six m:nths prior to fuel load for Perry 1, the site organization will be as fo1}ows: Nuclear Gioup VP administrative Services Group VP l l 1 1
- nclear Engineering Nucinar Quality Perry Plant Perry Project Dept. !!anager Assurance Dept.
Dept. !!anager Services Dept.
- anager
!!anager Nuclear Con,truction Dopt. !!anager Engineering support for Perry 1 will be provided by the Nuclear En;;i n ee r i ng Depart e nt; engineering support for Perry 2 construction will be provided by the Nuclear Construction Department. Similarly, Nuclear Quality Ansurance Department st af f will be riivided into two sections: the Construction Quality section will support Perry 2 ccustruction and tl:e Operational Quality section will support Perry 1 start -up and operat ion. . __~
.. ~ _ 4 4 j 1y e n j i I ..630.11 in., order t o properly determine the ty;re of tr aining requi real j . (13.2.3) for eb:h st af f \\ position, a task or job analysis' of that I position r:;nst he r:.ade and training requirements defined. } ~- Picase make t'dse position analyses available for NRC staff a { revJew prior.Ui SER issuance. s. 4 f y r
Response
Job / position descriptions for each Perry plant position have been prepared and are in use to determine training requirements in conjunction with cott.mitments .j . in the Perry FSAR. Institute of Nucicar Power Operat ion (IN.:,;O,) is preparing l generic job and t,:sk analyses for nuclear power pihnt posit [ons. Upon com-i pletion of the INPO effort, :,pecific task analyses for Perry poaitions will be prepared and appropriate modification to individual training programs will be l ir.pl emen t ed. l { / e l, 4 i 4 I i t 1 i L. 1 1 I j 1 4 1 l-4 / i r j i i t a / ? i I. d l ' +' t i N e ) 'e i \\ i _ ~ j L---..-....x ?
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__ _____..___ _ _.. ~. _.-.._ _. e j t i i [ 6'0.12. Add Fire Portr.ction Training to the PSPP Training J j (13.2.3) Schedule ffgurc 13.2.1. j a i l i-l t
Response
+ i i i' Fire Portection training will be added to the training schedule for PNPP, t Figure 13 '. 2.1. 1 I P i I t 4 1 I e h 6 i ? L 1 l l, I i 1 I i i l I l 5 i l i i l i f t I
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c 3 0.' 13 Expand the description of the initial' fire brigade described (13;2.3) in Section 13.2.5.1.
Response
A fire brigade conristing of a licensed Senior Reactor Operator, who functions as the brigade leader, a Nuclear Plant Attendant f rom the Operations Secticn, a-Radiation Protection Technician and two Security personnel will be-availabic on all shifts. The fire brigade. members will have no duties.during a fire except those directly related to manual fire-fi hting. Prior to assigni,ent t o -the fire 12rigade and annually thereaf ter, each member will-receive a physical examination that will ensure that no pirjsical condition exists that would prevent proper performance of' strenuous fire-fighting activities. The fire' brigade will be equipped with sufficient quantities of personal protective equipment, manual suppression equipment and other-equipment necessary for offective fire-fighting. Equipment will meet criteria stipulated in 10CFR Part 50, Appendix R, Section h (1)_(2) (3). The fire bri;;ade training program provides for classroom training, practice sessions and drills. The fire brigade training program will r.eet criteria stipulated in 10CFR Part'50, Appendix R, Section I. A sufficient number of on-shift personnel will receive the same basic training and retraining as'that ieceived by the fire brigade. These on-shift personnel will be availabic and trained to assist or replace designated members of the-fire brigade as necessary.
,..... - ~ _..., _ _- - -.~ - ~.- -. ~. - -. -. -. -. ~ - .--.~ j-630.14 2 0CFE SC, A; pondix-.R has recently then diemed to be the (13.2.3)' Cc~ ission's' requirements in the area of Fire Protection. -Review the PSPP Fire Protection Program agaiast 10CFR 50,- Appendix R and incorporate any provision presently missing from P ;PP Fire Protection Program. i
Response
i .PNPP will follow Appendix R guidelines pertaining to the Fire Brigade organization,
- t. raining and administrative cont rols.
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.._..-..~.._.- I~ j. i-MO.15 - I'- _.11.e t h t r ai:. :g-)o o ; ram for STA's 'ind indude sase ~ - (13.2.3) inc t!.( I".'?P - t : a i r, i t #g s c.h r. du l e. P t I 1, :
Response
i-The. training program for Shift Technical Advisor will be as described in Item
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_ __ ~ _, .i 630.16
- nt. ail the..:te:r ;on u :',i r t aining to mu :s s tre (13.2.3) for Unit 2 ;ddit2c C p: sc.nne.-1 ad/or pipeline path of
{ Unit 1 persc:mel to Unit' 2 with subsequent replac m"nts training. i f 1 E9sppyis,e j Unit 2 will require an additional six (5) licensed Reactor Operators and six (6) licensed Senior Reactor Operators. These licensed operators shall be a blend of personnel licensed en Unit 1 end non-licensed Plant Operators l reassigned as licensed operat or cand Mates on Unit 2. To support this program, I sufficient personnel to provide for progression from the non-1icensed job of i Plant Assistant to licensed candidate shall be recruited with hiring expected to begin in 1982. All Unit 2 license candidates, including sufficient candi-l dates to allow for attrition, should be n n.ed two years before the Unit 2 j scheduled fuel load date. j Due t o the syc:r,etry between Unit 1 and l' nit 2, the majority of the training completed by Unit 1 personnel shall not need to be repeated for Unit 2 j licensing. Candidates not previously licensed on Unit I shall complete the j same programs as were required of Unit 1 personnel except that technical systems instruction shall be Unit 2 specific. Previously licensed personnel l shall receive intense instruction on the design and operational differences l and the. Technical Specifications, Emergency plan, and procedural differences i for Unit 2 compared to Unit 1. Furthermore, they shall be provided simulator ref resher and exam pa eparat ion inst ructions prior to the licensing examination. j All site personnel shall receive training as appropriate to perform the transition to a two-operating unit site. Specifically, non-licensed personnel 4 assigned to Unit 2 and those assigned to both Units shall receive training l which shall upgrade their required training as shown in the FSAR for Unit 2 l specifics. k'he r e non-licensed personnel are specifically ass'igned to Unit 2 there shall be a blend of previous Unit I and newly hired personnel such that sufficient expertise is maintained for safe and efficient plant operation. l t i o h r ~ _ _. _. - -
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i i i t t b ri es "*:st ' -fi r - 2 y r:eip-ti-j- 630.1, ,xpl.u r.. chat would be cu:s l' (13.4) 'ble for plant operations" or "I f u g. : _:.. res.cnsibility for operat. ion of. the pinnt" for purposes of sun ing as-a -..b e r .l of the Nuclear Safety Review Co.nittee. l t i I. a ' Response i 5. "Not directly responsible.for plant operations" pertaining to the Nuclear Safety Review Committee means the'. individuals required to have this degree of 3i- ' independence must not report to the Perry Plant Department 'unager. e l e i l 1 i i i l 1 i t i f i i i L i i \\ 1 l 1 i l i i i r
630.16 M REG - 0737 Stction 1.$.1.2 establishes the requirca. mat (13.4) for an Independent Safety Engineering Group. Present your plans for complying with this requirement. Resanse The Perry Nuclear Power Plant will have an on-site Independent Safety Engineering Group (SEG) which will meet the intent of NUREG 0737, I.B.1.2. The ISEG will form a part of the Nuclear Engineering Department. The group will be staffed by engineers and other technically oriented perscnnel, all of -whom will have qualifications comparable to the s eguirea. cat s set forth in ANSI /ANS 3.1, Sections 4.1 and 4.2 (December-1781). The staf f will consist of 5 individuals f rom Mechanical, Elect.rical, Che nical/ Environmental and Quality Assurance disciplines, one of whom will be designated as chairman. The chairman of the ISEG will report directly to the Manager of Nuclear Engineering Department. The group will not be dedicated full time to the activities of ISEG, however, - other assignments will be minimized to assure that time expenditure required to meet the intent of NUREG 0737 will not be impacted. The charter of the ISEG will include the following scope: 1. The principal function of the ISEG is to examine plant operating characteristics, NRC issuances, LIS advisories, and other functions of design and operating experience information that indicate areas for improving plant safety. 2. The ISEG is to perform periodic, independent review of plant activities including maintenance modifications, operational p:oblems and operational analyses. As deemed necessary by the-ISEG, detailed recommendations regaiding improvements will be presented to management. 3. Periodic surveillance of operations and maintenance audits will be conducted to verify that these activities are_ performed correctly. These activities do not include detailed audits of plant operations; but rather, represent an overview function. 4. The ISEG will evaluate the effectiveness of the operational Quality Assurance program independent. of normal functions of the Quality !sssurance Department. Nuclear Engineering Department procedures will be developed to assure that the requirements of the charter and the intents of NUREG 0737 are met. I 197/1/20/kf i -. -}}