ML19317G517

Summary of 710921 Meeting W/Util in Bethesda,Md Re Introductory Matters Concerning OL Review.Water Level Associated W/Pmh Predicted by AEC Consultant to Be Ten Ft Higher than Reported in FSAR

ML19317G517
Person / Time
Site:	Crystal River
Issue date:	09/28/1971
From:	Faulkner H US ATOMIC ENERGY COMMISSION (AEC)
To:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8003180809
Download: ML19317G517 (5)

Text

e 1-2 it -

.n i{

j

.Y. @

^

/

UNITED'. STATES ATOMIC ENERGY COMMISSION

!.qQQ

j. l

/

p WASHINGTON. D.C. 20545-SEP 2 8 1971 R. ! C. De' oung,2 Assistant Director for PWRs,

Pl.

THRUL. A. Schwencer,: Chief, PWR-4, DRL MEETING WITH FLORIDA POUER CORPORATION CONCERNING' OPERATING LlCENSE REVIEW

'FOR' CRYSTAL RIVER' UNIT 3 - DOCKET NO.

50-302 ower Corporation (FPC) was held in Bethesda on A meeting with Florida o September 21, 1971,-to discuss introductory matters concerning the opera-ting license review for. Crystal-River Unit 3.-

An attendance list is attached.

The most significant item _of the meeting was the predicted water level associated with the maxi =ua probable hurricane,' item 4.

A preliminary calculation _by the staff consultant resulted in a water level'approximately-

10. feet higher than that reported in the:FSAR. A water level of_this mag-nitude introduces the' possibility of design changes to the plant because

'of flood considerations.:

The individual items discussed at the meeting are summarized below.

1.

General Topics Florida Power Corporation has reorganized recentiv. All nuclear effort has been centralized under the nuclear project ~ manager including his elevation to vice presidential level.

Licensing and environmental affairs'are administered in a single department with the manager report-

-ing.directly to.the vice president.

Details of the new organization will be forwarded in a supplement to the FSAR.

FPC has contracted-to construct and. operate an additional nuclear unit

at this site, Crystal River Unit 4.

The PSAR for this plant.is scheduled to be submitted to AEC between March 1 and June 1, 1972.

t

2. " Review Schedule We' discussed the schedule for our safety review culminating in the presentation to ACRS-in September 1972 and publication of the Safety 1 Evaluation in' October 1972.

FPC indicated this schedule was compati--

ble with their projected fuel loading date of July 1973.

There was

~

-some doubt abouc whether.the detailed environmental statement being -

prepared by the Division of Radiation and Environmental Protection-(REP) would..be ready' consistent with this schedule.

This is discussed further in ~itsm 6 :belev.

8003180 g

~.

u

%b:' (o.%y ~ %m +fL N'y nr ^

w

~

w

-a

m2 ~-

--x,

. w m; wc

. q& Mq~y j

S rp g ',%

K,y

~,

~

pp 7 4 ' ; <'; ;..

t g.

E ~

~

- -:2

~

mm,.;; _

n-,. =,

~

e f$l QQ

._,4 sh.

m

..,L

. 2

,234>MeteorolayL -

s.

I r

~

~

,'Informationiin the1FSAR indicates only-a 58% recovery of ' data from s

~

~

125'.-: months :of Tdatartaki~ng.; 1The c iscaffsstated that this was unsatis-

,tfactoryJand;that data for-a 12l consecutive month period vith'90%

k

_ k.

trecoveryi.is~requiredf-!If.suchidataEis notrava11able from existing.

~

' Ws 3.nformation,(additional: measurements'willbe'raquired.

k t' Alt u ugktemperature data willj not be: required-for -accident analyses,

itivaa:sug'ested thatisuchidata would be' helpful in estimating annual g

v L' radioactive 7 releases las. required by.the proposed Appendix I to 10 CFR 50 :

E4r Maximum Water leveli 1

For;thei:dax1=um' probable hurricane,- a' preliminary calculation by our '

Econ'sultant,7 the Coastal 1 Engineering Research Center (CERC) indicates

'a maxim = water lavel which is about.10 feet higher chait that reported

~

'inithe FSAR. 'This' water' level is of such magnitude as-to cause' con -

cernfabout.the7safetyJof the, plant under hurricane conditions.

a

-TheYealsulated water-levels are different because of differences in

?cothithe calculational technique and-the use of critical parameters.

Me suggest'ed that FPC recalculate their water level according to the.

o.'

-following prescription.

4 I i

a. : Use probSEla maxim.:= hurricane critical' parameters as published in U. S. Weather.3ur*au EUR 7-97.

S I.Ddter=inecthelsurge accordin, to the bathystrophic stor= tide-l >

theory.

~

c'. ~ Cal'eulate wave height and runup both statically and dynamically according t'o CERC, Technical Report No. 4' c

p

-a..

TIf?these sub' sequent, cal'ediations confirm the large increase in water-p' jlsvel,jdesignichanges to the.. plant may be necessary because;of flooding i

a, l c,onsiderations.

4 s =

.. 5.J Site 7 Consider 2 tion's :

J0uriconcerncforithefpossibilityrand consequences of marine accidents W

a-fvas. expressed.$ Weiindicated:that the. proposed waste disposal sys~em

willireceiveTa close ~1ook because of' the 'f ailure of current ccmponent:

7.

E" derfor=ance $o'meetimanufacturers claims. LWe will:als.o' require iestimates of j the maximum annualidischargeiof :alliisotiopes from all

' O' ~

Tscurces including Neactor? building. ventilation operatiens.

4

-w

b. (

s N,

[- ~>

m.

- e m

~.

• i Y

F

. j y

. V.6

~, ~ s.

- T r

< >.s "k

-?.W Y &

A y?N,

, f.)

t'j'-

3' e

F -

<r

,.sp

n..,

h~

a

< *~

y 1+-

_ :Uk

~9 m-

-=

+-

- n=

~~

- - 4 g;q - ww

" my

[,f y

y, m

Di w

3-

~

_ ;A' preliminary: calculation of the two-hour dose at the site boundary for the design basis accident has been performed'by.the staff. The cal-

- culation:u' sed the' design leak rate of 0.'25.v/o, a wind speed-and stability class 1which 'may be - conservative, andino benefit for the chemical espray: additive. The resulting dose was 655 rad. We informed the appli -

ennt'of our target dose of 150 rem and the manner in which ' leak rate,

-meteorology:and spray reduction factors interact to affect the final

predicted. dose.

16.

Isplementation-of NEPA

-FPC, stated that they. intend to submit an-entirely new environmental report-

-covering Crystal River Nuclear Units 3 and 4.

This report is scheduled

.for: submission ~by:the'end cf_the year.and.it will replace entirely the~ environmental report which had been ' submitted previously for Crystal River Unit 3. Tr.-R. 3allard of REP discussed ~the administration of implementing (the requirements of revised Appendix D.

For.each reactor project a. group leader from REP will be assigned to coordinate the ireview of the environmental report with the assigned national laber-a tor /.. He vill also coordinate the effort in producing the draf:

and detailed environmental ~ statements.

.Present1'/.there-are no d' tailed guidelines available addressing the e

preparatien of the environmental report.. Requirements for these reports-will evolve as projects are reviewed. A few "new lock"

( envircnmental statements are. targeted for publication during October.

These = statements will provide some assistance ' for the preparation of

future! reports., Even without detailed gudelines, two requirements were stated: (a) alternatives must be' considered quantitatively and (b)fthe cost-benefit, considerations sh'ould be treated in depth.'

~

REP stated'that if'the environmental report is received about the end of the year, the projected time table to publish.a detailed statement by:.-late 1972 or~early.1973 would be tight. REP agreed to keep the DRL project leader!1nformed of progress through the' environmental review land:of any_significant items which might affect the proposed.licen-

' sing schedule..

s o

~7.: : Proposed Regulations ;

iWe briefly revieweid proposed regulations,, Appendixes G through J,-to 10; CFR L50.~.

Appendix,G;-LFracture Toughness Requirements--

-Appendix lH - Reactor Vessel Surveillance. Program JAppendix I - Numerical Guides to Meet As Low As Practicable'

! Appendix;J~. eReactorJContainment leakage Testing l,

d

, w.

l

,W r,&

4-

It was noted that'the G2neral Design Criteria which were adopted-as regu-lation are somewhat different.than the proposed criteria of July 1967.

The applicable. criteria are those as published in the Federal Register

~on July 7, 1971.

8.{Safetv Guides

-We' informed the-applicant that 13 Safety Guides from DRS had been published and were available.- We also indicated the publication and availability of the Guides for Planning of Preoperational Testing and

. Initial Startup Programs.

9.' Technical Specifications FPC stated.that the Technical Specifications for the operation of Crystal River Unit 3 will be submitted in October.

10. ECCS Highlights of the Interim Policy Statement of ICCS vere reviewed with

-i.ne applicant. - FFC was informed that 3abcock & Wilcox (B&W) currently does not:have an acceptable ECCS evaluation model; however, approval of a model is anticipated.within the next few months.

11. Hvdroaen Control The. regulatory position as. described in Safety Guide 7 was enumerated.

For Crystal River Unit 3.the applicant should furnish information rescrd-

ing the calcul'ated dose form purging using the assumptions in the Safety Guide.. The need for backfitting. hydrogen' control equipment will be evaluated considering the dose'from purging.

.12. Wall Thickness of Cast Components (The applicant was. informed that recent experience indicates that the wall' thickness 'of cast components, especially-. valve bodies, were.some-

-times less than the minimum design requirement. We informed him that-

- we would'requi.e a. description of the quality c trol procedures to verify that actual; wall mesurements me t des

• requ ements.

E

~g!

< 4-

~

- H. J.' Faulkner PWR raach 4 Divisio1. of Reactor. Licensing k

)

~.:

._3.

A

( v: - ~..wayg;.;;;www. m..:a:. -

a, -

i

.,(..

- ~.

!si :

=.

4

+-

41:

,7

g. m

.e Gf

.5.,.-,

4 m

-7x Attendees Florida' Power' Corporation J.. HancocA

-:AEC-DRL

.,H.~ Faulkner

.C.-Ferrell E..Markee A.GSchwencer.

AEC-DRS.-

D. Nunn.

L. Hulman

'AEC-PSP.

R.'Ballard' DISTRIBUTION Attendees'

~ Docket,'

m"

.RL: Reading.

,u c ?D.!J.-Skovholt; F.-Schroeder T..R..Wilsoni

.R.

C.'.DeYoung~

.Branchichiefs.DRL/PWR CO.:(2))

1

-PWR-4 Reading 0

' ~ G.1Blane i-; ^

c H. Faulkner

.F

,R.yS.7 oyd.

3

H.-~ Denton "

,:j i:F.(Karas '

s 2'

_,P;/A.S Morris-

~

R;)iinogue "

)

-,g [.

u.

d' I

t 1

i

.qy _}

,I '.

A y.

,_.m:.

,v-_

r w._, ' * ;

.. [ald,,-;+ : --

d &'e L c T

o:

e.,

m i.._;.-

..~., T,:4 - i g'. n ;

m

,., :.

-f.

.,,.o

,._.x

m. ;. ;p. ~.

1

= '.

~

? - = '

y.

-