ML19308E185

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Forwards Div of Reactor Licensing Preliminary Review Plan. Areas Involving Assistance from Ofcs Other than Reactor Projects Branch Identified in Plan
ML19308E185
Person / Time
Site: Crystal River, 05000303  Duke Energy icon.png
Issue date: 09/15/1967
From: Long C
US ATOMIC ENERGY COMMISSION (AEC)
To: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8003240723
Download: ML19308E185 (7)


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Peter A.. Morris, Director, D2L September 15, 1967 THRU Roger S. Boyd, Asat Director, Reactor Projects, DRL p".. I Sir:M h CUJ Charles G. Long, chief, n:':: 13, DRL Chuhs G uwg LRL PLAN AND SCHEDULE F02 REVIL'W OF FLORIDA POWER CORPORATION'S CITSTAL RIVER UNITS 3 AND 4. DOCKET NOS. 50-302 AND 303 A preliminary plan for the review of Crystal River Units 3 and 4 has been formuisted (Attachment I).

Areas involving assistance from other than RP have been identified, cc:

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Primary Coo'1cnt.Systen 2.

Control and-instrumentatien 3.

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SYSTEMS DESICNS, SAFETY Mr""ERS THAT *!ILL 'I'VE REVIE*J IN DEPTH 1.

Site and Environment 2.

Pressure Vessel.

- 3.

En ;ineered Safety Featurer 4

21ectrical Power Syste~s (E=crge ncy) 5.

Shared yestures 6.

Accid.cnt Analysi:

7.

Technical Competency Specifically, the following arc are..; identified as subjecc to detailed revieu.

Ascintc,c: in requestad as noted.

1.

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Outside Cenaul:2nre 1.

Cai;=cicsy

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Meteoroicsy EJ _. -

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dcolo3; di

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Mc -ine Ecology s p.- t F- -bcries and Wildlife e.

Hurricanc, " ave Runu; C2.ctal In;incering Rececrch Center f.

Seic=clogical 2cspeasu Nc acr;<. and Hall 3.

Internal Study (RT) 1 c.

Ociculate 2-hour, 30-day thyroid deses for TID-type relcace.

b.

Review raincut-inte-Gulf anclysi: (the source term for effects on marinc ecolo3y) c.

Review diffusion calculations; ccm ent on effect of buildings in the X/Q determination.

d.

Review environmental nenitcring plans--both pre-cnd post-operational.

a.

Review c. omulaticn d ia: :ribut 7.-) #cr2 casts.

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The rer.ponse of:the 'presnure vesnel'and internals to the thermal shock of.the V ECCS uill..be reviewed.= The review should.be bised principally on the questionn and dnserers formulated during the cource of the ? tot.Ed review. Thia lirt will.

nst he 'rc,icated here.. Other pressure-vessci related; review--arcas are:

AT a.

.kview the. analysis; and/oricomment en ' the deleterious ef fect o f

. core bypass flow throudh the~ core barrel check valves for a cold-leg brenk.

Alt.o conment on the valve structural adequacy follow-ing the same cold-leg break.

RT

-b.

C.went on adequacy of prennure vessel and related items relative:

r to the Tentative Supplementary Criteria (dated. 23 August) for 1:ucicar Pressurc Vessels.

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3.

T.naincercd STfety Teaturen i

T dtnc Scavend n3 5"-rcn "T

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Review arca:: include nature of ciccted chemical, rcsponce co cad i.tt bv' ** Lenparaturc; tendency teuarde platecut, corrastvity, and eff rhorne radioindine.

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3.

. u-- ' en e n t a - C r_i t o r i e

' he adequacy of the plant in view of the Su>picaentary Criteria (not y:t issacd) will be reviewesi. The extant to which applicant ts to bc a f fected cannot bc stated at the prenant time, aT C.

rr Trar.3fcr j

s quescion t: ncw out to Ut t-Ed on evaluatin:; the transient h. a t scansTer cae Licient during core recevtry.

An added review question involves the change in predicted hot-spot clad tempe r.tures, neral-water reac tions, number of. failed clements,

following the cold-leg rupture.

4.

5.1cetr ical ?nuer Sys tem t

17 Th c<o Crys tal : liver unit : sharc encr;cn:y pouer supplies, dienni and b e try.

Thc compatibiiity will be revis ie d.

5.

Ther~' 7en tures l

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J.il f:atures shared by the ruo plants, including manning, chemical nakeup,

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wate collection, spent fuct tora;c, uill Se reviewed for potential j

l adverse. interactions.

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TransIcut - flow and hot-spot clad tcuperature for flow losa associated with one prin try rump sheared sh-1f t.

(This plant does.

not have prInary flow sensing devicen.)

TT n.

Ade';uacy of turbino itop val.ve an a etcan line'icolation valve;-

renconse to continued blowdown thronr,h ruptured necan line;- problems cors,on to P'.IRn having narety valve Icakage and/or atnospheric dump valve-operation.

AP C.

runnary review of operator actionn in first 60 minutes following a 1.0C4.

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desponse of eco* ing systen tn various steam-line breaks (thereiarc no isolation valves).

7.

Technical Competency 30 Florida Nuor Corporation propose; to act an. owner, operater, ar.d co.. tractor.

Assi tance In evaluatinp, their technical competency 10 requested.

(': t i; c..uned that the ccapetency of Gilbert acucciates in designing prestrea.,ed contairacnt is new being reviewed for Itet-Ed.)

8.

p ee i.cy 'lan 30 The energency plan for the tuo unita ri'll be reviewed.

ATilE1 rtr.Z The following arcas will be rr; viewed, a~ hough not in depth.

1.

Ine:.rmen. :t ion and contrni

.1T The. degree of protection (if nny) for the sheared-pump-slaft accident; response of summed-ncutran-pouce devices to various open.s and shorts ;

adec uacy of sensing devices for initiation of engineerin safety featurc signals; and adequacy of final-actuating-device bypassee to deny ECCS i

action durfng normal shutdown.

1 2.

o,ctnr re uel and Containnent IMilding

.1T ae;ponse of various components and strucuarcs to combined loadin;;3 (live, dead, environnental, accident) will be reviewed.- Included is the horated L

water storado tank, caternal to the containment.

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- Other arcan to be investir,ated by itP include (but are not linited to):

A.

. jicsuaev of Plant Deninn itelative to 70 GDC D.

gylication of ACE Comment t on ' Duke _

(a) inspectability.of prinary system (b) quality assurance.

(c). posiLive' moderator coefficlent '

(d) fuct rod' rcsponse to expected transients (c) xenon oscillation

( f) containment lince inspectability C.

?!f acellaricous (a)

Detalla of condenscr cury inlet ntructure (for Coastal Enginee ring)

(b)

Possibility of clininstion of mandatory operator action for first 60 minuten a f ter ifCA (c)

Adequac'/ of fire protection and control (d)

R & D areas (c) Cor.tractual statue of Unit 4 (i) iiow to shut Own syste, from without control room (GDC Jil)

(;;) Tornado reciutance o f bordred unter storage tank (h)

C'ngic-failure criteria as applied to L pressuri::ation systcmc (for core Clonding tanks and sodium thiocul fate tanka)=

(i)

Radiation ef fcet s on primary pump oil, windings, etc.

(j)

Reculss of 37-tube model cecan generator blowdown. (for tube failure analysis).

(h)

Response of Unita 1, 2, 3, 4 to various water icvels _(up to thosc for Maximum Probahic liurricanc)

(1)

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1 provision, requiremcata for decay heat pumps

' (n)..Modci tests for hurricanc analysin

'(n) Ground secticment measurements related to Unit t;o. 2' Dllm DJ JL 1 Jd. JD

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Inspection criteria for steam generator tubes. Mode'of repair, plug, or replace (p)

Standby chemicals (borating, iodine scavenging)

(ri) Tabic of lottds for emer6cncy diescis (r) Manual control capability for emergency feedwater pump A proposed review schedule is attached.

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- 302, 303 CRYSTAL RIVER Uti1TS 3 AND 4 FIORIDA POWER CORPORATION

-A..

'AppilcationLFiled 10; August 1967

- 14.-

liec:ings 26 September 1967 1.

General 31-Octo14ce 1967 2.

. Technical C.

<.u e r. t ions 14 ti,vember 1967 D.

Answers 21 i)ecember 1967 E.

Consultant's Report 1 Iinvember 1967 l*<*e t ing 4 January 1963-G.

J.C.3 Jile Visit January l?63 19 February l'168 11.

AC3G Report I.

  • Ca3 Subccomittee 6 Itarch 1963 J.

ACM 'tecting 7, 8 March 1968 K.

.1ticty Evaluation 5 April 1968 Schedule based upon:

1.

Updating of application to incorporate appropriate safety recommendations fron Duke, liet-Ed reviews.

2.

Conducting ieview as another of the same generation as Duke, Itet-Ed.

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