ML18019A809

From kanterella
Revision as of 03:05, 22 October 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Forwards Response to NRC 860221 Request for Addl Info Re Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Concerning Reactor Trip Breakers.Program to Trend Results of Periodic Maint & Surveillance Test Procedures Will Be Implemented
ML18019A809
Person / Time
Site: Harris 
Issue date: 05/06/1986
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
GL-83-28, NLS-86-136, NUDOCS 8605120108
Download: ML18019A809 (8)


Text

b<<t REQULATORY INFORNATION DISTRIBUTION SYSTEl'i (R IDS) 4 ACCESSION NBR: 8605i20i08 DOC. DATE: 86/05/06 NOTARIZED: NO DOCKET 0 FACIL: 50-400 Shearon Harris Nuclear Power Planti Unit ii Carolina 05000400 AUTH. NANE AUTHOR AFFILIATION ZINMERNANiS. R. Carolina Power Rc Light Co.

RECIP. NANE REC IP I ENT AFFILIATION DENTONp H. R. Office of Nuclear Reactor Regulation. Director (post 85ii25 SUBJECT; Forwards response to NRC 86022i request for addi info re Qeneric Ltr 83-28'tems 4. 2. i 0 4. 2. 2 concerning reactor trip breakers. Program to trend result of periodic maint 5 surveillance test procedures wi 11 be implemented.

DISTRIBUTION CODE A055D COPIES RECEIVED LTR ENCL SIZE:

TITLE: OR/Licensing Submittal: Salem ATWS Events QL-83-28 NOTES:Application for permiC renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NANE LTTR ENCL ID CODE/NANE LTTR ENCL PWR-A ADTS i i PWR-A EB i PWR-A EICSB 2 2 PWR-A FOB i i PWR-A PD2 PD Oi 3 3 BUCKLEY'S B i i PWR-A I

PSB PWR-A RSB i INTERNAL: ADN/LFNB i 0 ELD/HDSi 0 IE/DI i i IE/DGAVT i.

NRR BWR ADTS i NRR LASHER' i NRR PWR-A ADTS i i NRR PWR-B ADTS i R/%SR,O/RSI B i i NRR/TANB i QQ~FI 04 i i RQN2 EXTERNAL: 24X i i LPDR 03 i NRC PDR 02 i 'SIC 05 i i TOTAL NUBBER OF COPIES REQUIRED: LTTR 27 ENCL 25

~ - + r

('~'(f J <]) f'I'>7r.VP, f",f< p'),P~jg~ j>> ) Q f~jgp'g..",:, "~~% i'4'gl gJ f,'qJ!3.'s', f Huff; N a". ~(-.'C)%68 .3<'>6. I '~> t~(, <,".LV4>>l ".6Ã tl Jrf~V..."")0 '6'<.~>

~pi ) ' '"

j'l3lJ q') <>i~P 9 'TBU<l) s

" 6'.$ g > '4f"'".'p,""f(f~<f QO~>~~< glj~ aji3P=-

f"~.K ~;.~E ff. ) ." .",<P'ff]w '8'~',Hl f.

r4 ) 7 f 5~ -3 '3"'ltl f <<~')' 5)"%usa) ~ H c i')ATE AY. 3< f fA "I'I'f l .'fK.) ~H "<<'i.~.<f 'aX') 8$ f

+~;;g) (ay f' ; ~ qi'(<,o~~,,;.,fuess3 -,o f-a..9 zc.>.', >0'4 f~~ >>rR'jP.

av y'g[ f y '0 f) U g, >> g f ~ ~ ~a'< ",> -<f/) g),f g~, ff>l lg,~ ',$ ~

f ~~ b K'e i4IQQ '5 Q.f 'y l .9lf Ct< f');t)l4~:) ~ 9 e- .3 s .~ '~ <<"~11'g" L e$ ~a lleC ~4 f;jt "~'0t~ >f?

P>f K'~ iE.>>v r s'.iq 'f v <.,~ .=:v h>t.aa" o8 r<>c,wp ax"i .~-.,>0,. r4 >

>> k~, >'ft.~ ~q ~f .~v f i Iv e":evbaav"rq -a~~.f s>>radii l'i;fv"r".> ~

1 f'Ã>3 ~ i 3;u'dV 'H&.fFJ Bwi "~f.', ~'inc.()A,"l('l".i f <Df, I i)><XA'fi';) 9

, ~.n~a>>3 8~3TA i",efe8:fa 5 iedvi.'n ~,".Al;>i .'~)gf HJY3 f'(),

~O .b8lx t fcd~3tf'.1 f 'flap c6q tu"i fto L~h <<if qq/<.'..~ i~3'~f

'if)~ N 'L'lkÃ3R 8~K~<QQ <'f~f f t;,lf'33 fff') 'f'll t'<%,3QGD 6 X .33'1>> >lf'~'

f.'.RK:K>>'f'fhfA'-'lGtiD

~:i 1 63 A-Ai~! f 1r r ~Cih

~ UU"-~ A-A~4 f ir,31'.g  !'.; P! f G <<Y3JNDJG gl J 0 ( <g ~~/ f "q cf)fsf 68'H A- $ Nq pffft<

Lr30HXFJ~ f j%~

fvACG'i'll t.

h

~f 83fb.~'td ')IVAN i, f 'P>> Af06 <<gf/f 6-A)A '"AN ~ISA i, >'R f'$N i f5+~T ~ "j9>", I 6 >.',=",f'<<",P.'30,'.iSfIf F~P~3R f.

t,f)

>fed

'

!. fIf>:. j g '3 Jp'Q3g 2, f "'l ~ ~ f'h',l;4 J!> l >

@ST, Carolina Power & Light Company SERIAL: NLS-86-136 MAY 6 1S86 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 - DOCKET NO.50-000 GENERIC LETTER 83-28

Dear Mr. Denton:

Enclosed is the Carolina Power R Light Company response to your staff's February 21, 1986 request for additional information for the Shearon Harris Nuclear Power Plant (SHNPP). Additional information was requested regarding the SHNPP response to Items 0.2.1 and 0.2.2 of Generic Letter 83-28.

If you have any questions please contact Mr. Gregg A. Sinders at (919) 836-8168.

Yours very truly, S . Zi merman nager Nuclear Licensing Section SRZ/GAS/pgp (3705GAS)

Enclosure CC: Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell ..(NRC-SHNPP) Mr. 3ohn D. Runkle Dr. 3. Nelson Grace (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. J. H. Carpenter (ASLB)

Wake County Public Library Mr. 3. L. Kelley (ASLB)

Sb05120108 Sb050b PDR ADOCK 05000400 A PDR, 411 Fayettevilte Street ~ P. O. Box 1551 ~ Raleigh, N. C. 27602

I S

'

QUESTION \:

Item 0.2.1 - Periodic Maintenance Program for Reactor Trip Breakers Criteria for Evaluatin Com liance with Item 0.2.1 The Shearon Harris Nuclear Power Plant Reactor Trip System utilizes Westinghouse DS-016 circuit breakers. The primary criteria for an acceptable maintenance PW S-S + PP ( TES P P W~i Maintenance Manual for the DS-016 Reactor Tri Circuit Breaker, Revision 0, October 1980. The NRC staff, Equipment Qualification Branch, has reviewed this document and endorsed the maintenance program described in it. More specifically, the criteria used to evaluate compliance include those items in this document that relate to the safety function of the breaker, supplemented by those measures that must be taken to accumulate data for trending.

Issues Relatin to Item 0.2.1 The applicant response states that he will implement a comprehensive planned maintenance program covering the reactor trip breakers by December 1980. This program will be based on the latest results of the life cycle testing program and the Westinghouse recommendation(s).

As of April 1, 1985, the NRC has not received any applicant's correspondence addressing this issue. The Shearon Harris Nuclear Power Plant Periodic Maintenance Program for the reactor trip breakers should include, on a six-month basis (or when 500 breaker operations have been counted, whichever comes first):

1. General inspection to include checking of breaker's cleanliness, all bolts and nuts, pole bases, arc chutes, insulating link, wiring and auxiliary switches;
2. The retaining rings inspection, including those on the undervoltage trip attachment (UVTA) and shunt trip attachment (STA);
3. Arcing and main contacts inspection as specified by the Westinghouse Maintenance Manual;
0. UVTA check as specified by the Westinghouse Maintenance Manual, including replacement of UVTA if dropout voltage is greater than 60 percent or less than 30 percent of rated UVTA coil voltage;
5. STA check as specified by the Westinghouse Maintenance Manual;
6. Lubrication as specified by the Westinghouse Maintenance Manual;
7. Functional check of the breaker's operation prior to returning it to service.

The Shearon Harris Nuclear Power Plant Periodic Maintenance Program for the reactor trip breakers should include, on a refueling interval basis (or when 500 breaker operations have been counted, whichever comes first):

1. Pre-cleaning insulation resistance measurement and recording;
2. RTB dusting and cleaning; (3745GAS/pgp )

lt 4 ~

k 1 . ~~ w. < t.'. *~ " .

(~

i"i

\ I V

3. Post-cleaning insulation resistance measurement and recording, as specified by the Westinghouse Maintenance Manual;
0. Inspection of main and secondary disconnecting contacts, bolt tightness, secondary wiring, mechanical parts, cell switches, instruments, relays, and other panel mounted devices;
5. UVTA trip force and breaker load check as specified by the Westinghouse Maintenance Manual;
6. Measurement and recording RTB response time for the undervoltage trip;
7. Functional test of the breaker prior to returning to service as specified by the Westinghouse Maintenance Manual; The maintenance procedure should include a caution to the maintenance personnel against undocumented adjustments or modifications to RTBs.

The applicant is to confirm that the periodic maintenance program will include these 10 items at the specified intervals or commit to their inclusion.

RESPONSE

The SHNPP procedures for the periodic maintenance (PM) of the reactor trip breakers is in accordance with the recommendations of the Westinghouse Maintenance Manual for the DS-016 Reactor Trip Circuit Breakers, Revision 0, dated October 1980. The 10 items listed in the question above are included in either the PM or the Technical Specification Surveillance Test procedures for the reactor trip breakers with the following clarifications: 1) the replacement of the UVTA will be performed under a maintenance work request instead of as a specific step of the PM procedure and, 2) the PM frequency after the first PM interval will be at 500 breaker operations or at a refueling outage, whichever comes first. The Westinghouse Owners'roup is in the process of revising the Maintenance Manual, and CPRL will review any revisions to the Maintenance Manual and will determine if changes to the PM program are necessary.

With regard to the undocumented adjustments of the reactor trip breakers, the administrative procedures for implementation of maintenance activities clearly state that undocumented adjustments should not be made since they are considered to be modifications outside the scope of specific procedures. However, the PM procedure for the reactor trip breakers will include a caution to remind maintenance personnel to not perform undocumented adjustments or modifications to the reactor trip breakers.

In summary, CPRL has implemented a program to meet the items specified in the NRC's request with the clarifications noted above and considers this matter closed.

(3745GAS/pg p )

UESTION 2 Item 0.2.2 - Trending of Reactor Trip Breaker Parameters to Forecast Degradation of Operability Criteria for Evaluatin Com liance with Item 0.2.2 Four parameters have been identified as trendable and are included in the criteria for evaluation. These are: a) undervoltage trip attachment dropout voltage, b) trip force, c) breaker response time for undervoltage trip, and d) breaker insulation resistance.

Issues Relatin to Item 0.2.2 The applicant states that he will incorporate a review of the parameters necessary to be trended with his planned maintenance program. These parameters will then be included under the overall plant trending program, which will be in operation by December 1980.

As of April 1, 1985, the NRC has not received any applicant's correspondence addressing this issue.

The applicant is to commit to inclusion of trip force, breaker response time and dropout voltage for undervoltage trip and breaker insulation resistance as trending parameters. The applicant should also identify the organization which will perform the trend analysis, how often the analysis will be performed, and how the information derived from the analysis will be used to affect periodic maintenance.

RESPONSE

Carolina Power R Light Company will implement a program to trend the results of the PM and Surveillance Test procedures. Initially, the parameters which will be trended are as follows: trip force, breaker response time, dropout voltage for undervoltage trip and breaker insulation resistance. The evaluation of the data will be performed after the performance of each scheduled surveillance test and after the performance of the PM procedure. This trending will be performed by the Technical Support Unit at the SHNPP. Based on the results of the evaluation, the Technical Support Unit will determine if changes to the PM program are necessary. Also, CPdcL will continue to review industry trending information through participation in the Westinghouse and will revise the trending program considering vendor recommendations and Owners'roup industry trending experience.

(3745GAS/pgp)