ML20138D004
| ML20138D004 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/03/1991 |
| From: | Anthony Mendiola Office of Nuclear Reactor Regulation |
| To: | Verrelli D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20138D008 | List: |
| References | |
| NUDOCS 9104080074 | |
| Download: ML20138D004 (4) | |
Text
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April 3, 1991
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s Docket No. 50-261 %
~ w jt DISTRIBUTION Docket File Q
MEMORANDUM FOR: David M. Verrelli Chiefa n m,;t yRobinson File a
E. Adensam
. Project Branch #1aLut, taie n < @/R. Lo.
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, Region II 9*
J.M.
A g,mm c FROM:
Anthony J. Mendiola, Ac' ting Director A'
Project Directorate II-I Division of Reactor Projects
.I/II SUBJECT 50.59 SAFETY REVIEW AUDIT FEEDER REPORT - H. B. ROBINSON STEAM ELECTRIC PLANTPUNIT. N0c 2 enE w y.og Qy g m y M W&rs %M x-a.a.m.n,% n,,e t n.,,,%
OnMarchgand
'1991, the NRR! Project Managerr(PM)nRonnie Lo, performed a Electric Plant Unit Nov 2'(HBR-2)y review process-at the H. B. Robinson Steam follow-up aud o the 50.59 safet
.TThetresultsraredn the enclosed feeder j
report for the resident' inspector's report.
i During the week'of bgust 27c1990, the PM did ~an audit of the HBR-2 50.59 review process, documenting his findings in a memorandum to you dated September 196 1990(Enclosure 1). As noted'in the memorandum, in July 1990',
the licensee began implementing a new procedure'(Plant Procedure PLP-032) fpr i
50.59 review. 'The new procedure' closely followsithetguidance'of NSAC-125,..
I
" Guidance for 10 CFR'50.59 SafetyiEvaluationsf spreparediby: Nuclear Managenent i
Resources. The PM'noted that'stherlicensee'stcorporate-widertraining and qualification program for the new'50.59freviewiprocesstcovering Harris and Brunswick *as'well as HBR-21seems to<betboth comprehensiveland: thorough. '
However, at'the time of the Augustd1990! audit,Ftheiavailablersamplecof,50.59 reviews actually performed'under*theinew!proceduretWasitoo smallato:show c.
whether the improvement:was consistent M Dering^theslastirefueling outager (September 1990 ' March 1991),uthe911censee: performed:arsubstantialtnumber of modifications, producing a'significant'samplebstrenforcthesfollow-up audit. :, t 4, r mm H
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The report on the follow-up audit: concludes *that<t esnew 50.59ereview procedure has been consistent 1y' implemented.andethat theiqualityrohthe safetytreview is signifi cantly 'improvedi over f thoseidone ibefore rthernew.: procedure, was;, m implemented.
w i r t o htmu% whouer' tarety revNa bd actwi u y
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da e m AnthonyiJJ Mendiola rActing! Director S
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Enclosure:
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UATE di 0FFICIAL RECORD COPY j
Document Name: MEMO VERRELLI/ SAFETY REVIEW s.
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1.
10 CFR 50.59 Safety Review Audit '
On March 5 and 6, 1991 the headquarters Project Mana er audited the H.B.RobinsonSteamElectricPlant with the provisions of 10 CFR 50.59., Unit No. 2 (HBR- ), for conformance A summary of the audit follows.
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a.
Persons contacted
.4, rAo Licensee employees.,
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J. J. Sheppard, Plant Manager.,,..,,.
- J.. Koosterman, Director, Regulatory' Compliance
- D. Crook,= Senior Specialist,; Regulatory, Compliance.
D. Stadler, Senior Engineering,7 Nuclear' Licensing
D. Makosky, System,. Engineer,;gTegicaf $upport, t
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Other licensee' employees contacted during*the audit \\ included engineers gy Q gQ,[
and administrative.personne1 %,
a
- Attended exit' interview,
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b.
Approach..
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' w r. 9 y The audit was a follow-up,of'andudit conducted during' the week cf August 27, 1990.. In part, that' audit revjewed: Plant Procedure i
PLP-032,"10CFR,50.591ReviewsiofChangesCTestsandExperiments,"
y 3
newly adopted by the'11censeeifor, implementation in June 1990.
J PlantProcedurePLP-032providesluidel.inssl,hd'the'HBR-2Technicalfor/pe safety reviews as required by-10.CFR'50159 a S)ecifications-(TS) Sections,6.51.1.'.and.6.5.1.2..,The.auditnoted t1at this new procedure was the' result"of a' corporate-wide effort to followtheindustryguidance(NSAC-125);for/ performing 10.CFR50.59 reviews. Theauditconcludedthat;the?,newl procedure'isasubstantiala.
improvement over.the one.it replaces!and provides~ adequate guidance for the performance of. safety' reviews.'?Howeverf the. audit'also available,that'a ~, follow-up revie%s,kould:be',he'c ssary"because the concluded sample,of 50.59. review performed:Under;the wastoosmallutodeterginclwhe,theg,saf,etgpvjews,;had,newproced actually,
improved..
b W 0 a M or onc r elac m.nt with i.
s The present audit was conducted;at the en,d of Refueling Outage o
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h.13, which began in September 1990.g During,,the outage, the licensee performed a significant numbef of' plant' modifications.
The following four were chosen as a, basis on,which to judge how well the licensee has., implemented,thepef s,afe,tygeview process.
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M-1004 - Current.Limitersjo,n D,B-5,0 Br,eakers g
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.-,o M-1049 - Radiation.; M,o,ni,to,ri,ng System ~ Upgrade
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M-1050 - Condensate' S,torage,,,Ta,n,k,,. n
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l L, eve ( e,Po,nt, H-1056 - Auto-Load Shedding Feature of MCC-5 and -6 A
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Discussion and Results~
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y,+ t m p-vers w Abriefdescription'ofeachimodif.icationiisifo11owedbya. discussion of the licensee's safety review.un,. head conmnt (1) M-1004'- Current Limitersdp DB-50f Breakers-Thismodificationaims'topreclude!theipossibilitythatthe short circuit fault currentsi.for/ver:ious; plant conditions;could exceed the' published' circuit 51nterrupting< ratings (50 kA symmetrical) for theiE1:and E2, emergency > buses (Westinghouse DB-50 circuit breakers)m Asinotedibnthe staff duHng the SSFI, the plant configurationsisisuch,that a failure of the 08-50 breakers'would compromiseitheiindependence of the two emergency busese Therplansto;modifyithe bus work on the load side of the DB-50ibreakers;wastraviewediand approved by the i
staff'in aoletter datediNovember43Yy1989.IvThe licensee states Y
that this modification'would*re M1ve the RC' unresolved item (URI'50-261/87-06-20)aidentifie#underothe SSFI. The safety evaluation-points;out"that(the)aVailable?short-circuit currents could~ approach 80.kAsymmetrica1EJffan(emergencybuswere a aligned with its emergencyidieseVgenerator,and either the standby or the unit auxi.11aryatransformer:Was., connected. The o
hm;-
+ O capacity of the breakers 1toTaiminisiuin/jincrease,the interrupting installation of,currentSlimiterslW111 of 100 kA symmetrical.
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(2) M-1044 - Radiation MonitoHnglu$ystem!(RMS)? Upgrade -
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- I The licensee dnitiatedithisiupgradehtonreplace' the RMS of an
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.ar ' analog-based system.with'asstate-of-the-artsmicroprocessor-based,
i digital system.mTheireplacemen,t would'be,more reliable, i
efficient," accurate,4andleasier,ttoicalibrate,and maintain., e,
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-It is also more availableiandi6thusi.decredsing,LCOsa and Atransients4andikeep. maintenance 4Workersbexposureaslowas reasonably achievable. Theisafety evaluation emphasized that j
the modification'is a one-for-one replacement with no changes in functionalrequirementsand" design { criteria.
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y-(3) H-1050 - Condensate Storage l Tank 1(CST)) Level Alarm Set Points 3
e.
, w, Thepurposeofthismodificationlis)totadjustthealarmset points to correspond lto FSAR'and TS' requirements for auxiliary feedwater(AFW)pumpprotection.'The~10w-levelalarmissetto correspond to the 35,000! gallon CSTiinventory requirement in the TS as well as to the 20 minute AFW' operation stated in the FSAR. The low-low-level alarm is set to' alert the operator to take action (shut the AFW pumps'or switch water sources) to prevent pump damage from; cavitation.fThef safety review is based x.
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e on revalidated.calculationsLfor the~CWSElevels'and AFW pump operations; these'9 calculations were done'during'the Design Basis l
Documentation and recent modifications 4ofi the AFW system to l
resolvenet-positiv% suction-head, concerns.(
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(4) M-1056 - Auto-Load.,S.he.dd_ing Featu,re,of MCC-5 and -6 s,
c The control room habitability modification would add a net electrical load of'aboutj60'hp[to?e'ichfof.'the two emergency electrical system trainsMThe additional? load creates unacceptable conditions'forlthelemergency' power distribution system, exceedingiparameters for'systeurca sacity, voltage levels,andshort-circuit;capabilitiesdT1emodificationwould allowMCC-5and,-6,onreceivjngraisafety:injectionsignal, f
automatically 'to shed Icertaininon-essential' loads (50 kw or abcut 67 hp) to' accommodate thernew control room habitability q system. loads and ma.intainithescag.acity,. margin.-
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s 4The sa ety reviews of these;four, mo, a dN%jcadons,Wereperformedin f
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-accordancewith~ previous;P.lant'ProcedureT'H0D-013. Furthermore. -
PLP-032addressesissuasith&t'are'especidilyfimportantatHBR-2:'
design basis issues, environmental?qualific&tions'and electrical requirements. Finally,3the'procedureitaket*FSAR updates into account as a line item in the checkhlist
.noted,by.the staff.4 ;4 Q,1 correcting [a,(gj'] ness'previously Weak s
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s Conclusion o u
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Thelicenseehasmadeasignificant:numbetf[;plantmodihcationssince c
adoptingPLP-032.<This' follow-upaudit;hasrevi6wed,aisample;ofthesafety i
reviews done on these recent=modificationt! nd?found that the licensee'has 6
i sconsistentlyconformedwiththe. guidance'ofgPLP-032v!thoseldonelunderplant As;a result, the quality
.of the safety reviews,has substantia 11 mproVed over procedure M00-013 and meetst the indust,.stahd.a.t 'f,o,iMperforming.5,0.59 reviews.
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