ML20126F240

Forwards Schedule for Environ & Safety Reviews of OL Application Intended to Meet NRC 810222 Memo.Describes Scope & Status of Reviews.Requests Reviewers Be Assigned to Applicable Review Branches

ML20126F240
Person / Time
Site:	Fermi
Issue date:	02/14/1981
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Check P, Muller D, Noonan V Office of Nuclear Reactor Regulation
References
NUDOCS 8103110767
Download: ML20126F240 (9)

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FEB 2 41981 Decket peo. 50-3/1 t;Ef:0RAfDtlP FOR: D. flu 11er, Assistant Director for Envirornental Technology, DE V. I;oonan, Assistant Director for Itaterials & Ouelificatiens Enoineering, DE F. Check, Assistert Director for Plant Systers, DI g,7 g W. Vrecer, Assistant Director

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for Radiation Prctection, DSI 3 L. Rubenstein, Assistant Director for Reactor Systers, DSI

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J. F. rarer, Deputy Director (q ,,,..0 .9

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Division of Huran factors Sefety L. .-

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E. Crires, Directer $\ :l$g rivision of Inspecticn I Enforcement Q 4 FFCf': f., L. Tedesce, Assistert Director fer Licensing, CL kM SLTJECT: FErf:10 OPETATIt:0 LICEf SE REVIEL:

Enclosure 1 is a scheoule for the environrntal review and the sefety review of the Ferri ? OL erplication intended to meet the detes in H. Denton's February 22, lof 1 rercrandur .

Status anc Score of Envirenrental Review The envircrrental review wes corpleted by Arcenne Petional Laboratory (LPL) to the extert of preparing a craf t of the Draf t Envircrrental Staterent (DES) at'out twc years ago, except for those sections addressine radiologicel impacts and radioactive waste ranacement systers. This traft DES was reviewed ty the staf f but recuires a re-review to urdate it, including " Class f

• accident consideratiorv0pidelines for the review are:

(1) The text should focus on new operatint phase inferretion and revised reculatory procedures, es reouired oy law or as undertaken in accord-ance with re,culatory procedures. Repetition of dete or unchanned eralysis fror the Cp review is unnecessery because the FES-CP will be circuleted with DES-OL.

THIS DOCUMENT CONTAINS POOR QUAUTY PAGES m .j. i e l. .I .i.

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P,ultiple /,doressees FEB 2 41981 (2) Purely descriptive raterial, should be severly 11rited. Species liste should be elirinated; such lists should be acknowledoed as references in the FFES-Cp or the Applicant's ER.

(3) All sections recuiring conclusions should contain the staff's judorent. Insufficient data fror the Applicant is not an adeouste basis for crittine conclusions.

(4) Staff "recorrendetions" to reduce environrental inpacts should be changed to indicate conditions on the license.

You are requested to essign reviewers in applicable review branches (EEB, SAP, llF0, HGEP, AEB, RAC and ETS0) and send this inferration to the licensing project ranaper, L. Kintner, and the enviromentel review coordinator f'. kaltran.

Status and Score of the Safety Pevier The revier of the rinti Safety Analysis ferort was corpleted, except for reviev cf reertor systers (Charter 4), ECCS (Chapter f.3) end Safety /nalysis (Chapter 10). Due te o thret year deley in plant construction, the review was also deleyed and the status of the reviev was repcrted in H! LEG-0314 "Interir Safety Eveluatien Eercrt (Septerber 1077)." Oper review arees were idertified in tillEG-0?l4 Ir slune ic70, the FSAF. was updeted end the review resterted. The revier procressed to the point where pcsitions were issued ty March 1070 It that tire, the plent corpletion and review was eprin deferred because of Tf!! ratters. The open review arees at the tire the review was stopped in tierch 1979 are in Enciesure 1, tueether with new Trl reevirerents identified in l'LfREG-0737. Applicent has responded to rost non-Ti'I areas so review can begin irrediately in these areas.

The respense to !!LiREG-07?7 reouirerents is expected Parch 15.

The scope of the review sheuld include resolution of open creas identified in the Interir SEP (included ir Frclosure ?) and any ner issues that beve arisen since its completier. Fcr all tiranches except Peactor Systers French, SE input should include epplicable sections of the Interim SER, which should be updated if necessary.

SE 1rrut for Reactor Systers Eranch will be completely new and include an ,

evaluetion of responses to cuestions fror steff and Savanneh River Laboratory personnel. A complete SEP will be issued - not just a supplerent to the Inter 1r SER.

1 You are reovested to assign reviewers in applicable review branches and send I this inforration to the licensino project ranaper. In addition provide schedule cm:qi l l l  !

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and assignrnent inforration for special team reviews (such as fire protection, i control room design, etc.) that will be consistent with completing all SE inputs by June 10, 1981.

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Robert L. Tedesco, Assistant Director for Licensino Division of Licensino cc: D. Eisenhut Directors BC's S. Treby

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l'ultiple Addressees -?-

FEB 2 4 tggy and assignment inforration for special team reviews (such as fire protection, control roor design, etc.) that will be consistent with completing ell SE inputs by June 10, 1981.

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Robert L. Tedesco, Assistert Director for Licensina Division of Licensinc cc: D. Eisenhut Directors BC's S. Treby DISTRIBUTION:

Docket File 50-341 RTedesco ASchwencer LKintner MService 1

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ENCLOSURE 1

- FERMI 2 OL REVIEW SCHEDULE -

Environmental Review Complete Review of Draft DES March 20,1981

(EEB, SAB, UFB, ETSB, RAB, '

AEB,HGEB)

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Send Draft DES to EPA . April 15,1981-

- Issue DES May 1,- 1981 Issue FES September 1,1981 Safety Review Review ncn-TMI,SE Input and Identify April l1,1981 Open Issues ( All Branches Except RSB and CPB)

RSB & CPB Prepare Draf t SE Input and April ' 15,1981

, Identify Open Issues Prepare TMI Draft SE Input and Identify May 1, 1981 4' i Issues Resolve Open Issues May 1-31,1981 Complete Final SE Input June 10,1981 1

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Plant Name: Fermi 2 ENCLOSURE 2

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i Division Branen Reviewer Open Items

• DOE MEB Asymmetrical loads due to LOCA combined with seismic loads - '

effect on reacotr internals and reactor support. Evaluation to assure operability ECCS valves and pumps subjet: to hydrodynamic loads -

from suppression pool j

Inspection programs .for operability -

of ASME Class 1, 2 & 3 pumps of valves Confirmatory Piping Analysis II.D.1 Relief a safety-valve test requirements SES Structural evaluation of Mark I Containment modification to account for hydrodynamic loads in suppress-ion pool Structural evaluation of sacrifi:31 snield Fuel Fool Structural Acecuacy GE for High Density Fuel Storage

• • Revised response spectra HGE5 Quality Assurance & Inservice MTEE Survey of Breakwater (snore carrier)

Exemptions from 1C CFR EO Apcendix G and Appendix H Inscettien programs for material '

integrity of ASME Class 1, 2, & 3 components ECB Review by SORT of NSSS and 30P equipment, including effect of hydrocynamic loads from suppression pool '

Environmental cualification of electrical E;uipment conformance to NUREG-0528, CEB Steps to minimi:e stress corrosion in SS components (recirculation no::les, CR0 mecnanism, RHR lines i Fire protection; capability for

~ remote shutdown; !EEE-133 recuire-

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ments, separation of redundant systems

- Spent fuel pool filtratien

• • • Questions not completed - could recuire long review thre.

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1 Di vi sion Branch Open Items

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DSI High energy.line break protection for control rod drice hydraulic system Hign density fuel storage racks ICSB II.D.3 Valve cosition indication Instrumen; se: points Startuo -

monitoring and recording systems PSE Offsite emergency power -

protection for cegraced grid voltage; bypass for load shedding feature wnen on diesel generators RSS Potential for missile damage from high pressure gas storage bottles Potential for missle damage fror recirculation cumo overspeed Effec: of mocifications to controi rod drive return line on water make-up capacility-Overpressurization protection for reac:or coolan: system anc connecte:

low pressure systems (RHR, HPCI, RCIC, Core Soray; Leak cetection systems to mee:

Regulatory Guice 1.d5 Componen- design - switchover cf RCIC scetion line to torus; loss of recirculation pumo seal water; '

capability of relief valves for RHR Steam Concensing Mode (50.55e Report)

Water hammer poter.tial damage for owo in steam enadaasiaa Pade; dyra--

loads on RHR relief valve disenarge pipes ECCS analysis per 10 CFR 50.a5 Appendix K and cuestions on FSAR Section 5.3 Main steam bypass system and renea:e s methoc of analysis for credit during turoine trip: failure taode and effee analysis Reactor transient analysis '

r** Reactor Systems Branch Evaluatien 1.C.1 Short-term accicent & proce-dure review 1.G.1 Training during low-power testing E not coepietcc - ta) result in several issues. ,"

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Di vi sio n B ranch Reviewer Ooen Items

• 051 (Cont'd) RSS II.B.1 Reactor-coolant-system vents i II.K.L IE Bulletins Review ESP' Valves Operability status Aux. Heat Rem. System, procedures

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II.K.3 Final recommendations, B&O _

f' . task force Reporting SV & RV failures & challenos HPCI & RCIC unit levels a) Analysis

,l b) Modify 1 solation of HPCI and RCIC Challenges to & failure of relief vals a) Study b) Modi fy ECCS outaces ADS actuatien a) Stucy c) Drocosed mocs c ) Modi fy Res: art of LPCS & LCP:

a) Desfgn  :

b) Mocification RCIC suc-ion a) Procedures b) Modification -

Space cooline for HPCI/RCIC modifi-cations Power on pum; seals a) Propose mocs b) Modifications Common reference level Qual . o f ACS accumlators SS LCCA methocs a) Senedule outline b) Model c) New analyses <

Plant-spe;ific analysis

, Evaluate trar.sients witn single failur Manual depressuri:ation Michelson concerns AEB - Exclusion aria and population center distance i

Potential for aircraft crash damage from new airport Tornado missile protection for RHR cooling tower fans Main steam isolation valve leakage control system - frequency of in-service leakage tests .

Design of ventilation systems to mitigate fuel handling accident.

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Division Branen Reviewer ~ Ooen Items *

, OSI (Cont'd) AEB (Cont'd) III .D 3.4 Control-room haoitability ,

ETSB II.B.3 Postaccident sampline II.F.1 Accident-monitoring instru-

,- men ta tion III.D.1.1 Primary coolant oraide con ta inment RAS II.B.2 Plant shielding -

111.D.3.3 Inplant I," radiation mo ni to ring CSB Suppression pool temperature limit I

Pressure distribution within sacrifici shield for reactor vessel nozzle bre Secondary containment pressure transie following LOCA Containment isolation valve type C leakage test exemptions Evaluation of. combustible gas con:rci witn air (not ti,) in containment during opera tier.

II.E.a.1 Dedicated hycrogen penetratic II.E a.2 Containment isolation deoendability C?B Asymmetrical loats due to LOCA combint aith seismic itacs - effect on fuel assemblies Methods of analysis of core performar.c thermal-hydraulic stacility uncertat in MPCR; flow distribution through core Loose Parts Monitor t

II.F.2 Instrumentation for detection c inadequate core-cooling CHF5 OLS I . A.2.1 Immedia te upgraot of RO & SRC training and qualifications I. A.2.3 Acministration of training pro grams I.A.3.1 Revise scope & criteria for

, licensing exams HFE5 I.D.1 Control-room design reviews

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I .D.2 Plant-sa fety-parameter display consol e 3

LOS I. A.l .1 Shift technical addsor I.A.l .2 Shift Supervisor responsibilit I . A.I .2 Shi ft manni ng I.B.I.2 Evaluation of organization &

management l

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. 5-Division B ra ne n Reviewer Ooen items

• DHFS (Cont'd) ' LGB (Cont'd) 1.C.2 Shift & relie f turnover procedur I.C.3 Shift supervisor responsibility I.C.4 Control-room eccess I.C.5 Feedback o f operating experience II.B.4 Training for mitigating core damage DTRB Test progr?.m - develop procedure for water hame:r detection and correctic~ i in HpCl-& RCIC Preocerational tests test main stear - 3 isolation valve leakage control system under service conditions, t Startup tests; response time of RPS;-

DC (battery); response time of.valvt j in main steem & bypass steam system:

test procedure modifications; identi non-essential tests; justify CRD ser times for pressure less tnan ' 950 ost I.C.5 Verify correct performance of-ocerating activities I.C.* Pilot mon of selected emergency proc for NTOLs IE Resicent  !.C.7 NSSS vencer rev of proc Insoector (

IE EPPO II! . A.I .1 Emergency prepa recness.

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!II.A.I.2 Vograde amergency support facilities III.A.2 Emergency preparedness I ems i1stea reflect of review terminated by TMI in Marcn of 79, and may not necessarily be open items. Revi, ewers have not been assigned to restart Fermi 2 review at this poln' .

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