ML17309A361

Forwards Safety Evaluation Re Util Responses to Exxon TOODEE2 Code Error.Code Utilized as Part of ECCS Evaluation Model.Current Version of Exxon Model Not Fully Acceptable Per 10CFR50.46

ML17309A361
Person / Time
Site:	Ginna
Issue date:	04/05/1985
From:	Thompson H Office of Nuclear Reactor Regulation
To:	Kober R ROCHESTER GAS & ELECTRIC CORP.
Shared Package
ML17309A362	List: ML17309A361 ML17309A363
References
LSO5-85-04-004, LSO5-85-4-4, NUDOCS 8504090151
Download: ML17309A361 (9)

Text

Apri 1 5, 1985 Docket No. 50-244 LS05-85-04-004 Mr. Roger W. Kober, Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 DISTRIBUTION Docket File NRC PDR Local PDR ORB ¹5 Reading HThompson ORAB CJamerson RVollmer CMil1 er JZwolinski OELD EJordan BGrimes JPartlow TBarnhart (4)

HDenton ACRS (10)

CMiles, OPA SECY RDiggs JScinto DCrutchfield RBernero Dear Mr. Kober;

SUBJECT:

EXXON CODE ERROR Re:

R.

E. Ginna Nuclear Power Plant On March 15, 1985 Exxon Nuclear Corporation (ENC) informed us that they had discoverd a coding error in the TOODEE2 code.

This code is utilized as part of the Exxon ECCS Evaluation Model.

In order to assure resolutinn of the code error, as, well as resolution of other concerns which have been raised as part'of our review of Exxon LOCA analyses for other licensees, the staff contacted all PWR licensees with Exxon fuel and requested that th'ey evaluate these concerns with respect to their plant.

10 CFR 50.46 requires that an acceptable evaluation model be used for analysis of ECCS cooling performance.'s indicated in the attached SER, the current version of the Exxon'odel is not fully,acceptable as required by 10 CFR 50.46.

However, ther'is reasonable

'assu'rance that Ginna will operate in conformance with the "acceptance criteria of 10 CFR 50.46 since a significant safety margin exists reqar'ding peak fuel'lad temperature,and the 2200'F limit, and that in the event. of a design basis'LOCA the maxittium fuel element cladding temperature will not exceed 2200'F,.

J n

Accordingly the public health and safety does not require, at this time, operating restrictions in accordance with 10 CFR 50.46(a).

Nevertheless, you are required pursuant to 10 CFR 50.54(f) to provide as soon as practicable on a schedule to be negotiated with your project manager a reevaluation based nn an acceptable model.

In no event shall the reevaluation to bring your facility into conformance with the regulations be submitted later than nine months from the date of this letter.

Sincerely, 8504090iSi 850405 PDR ADOCK 05000244 P

PDR Prggaae ggmi @

Hugh L. Thompson, Jr., Director Division of Licensing DC+

• SEE PREVIOUS PAGE FOR CONCURRENCE

~ Siin 't i'nclosure:

DL:DIR ONRR:KIR*

OELD pi~/~ vP Safety Evaluation Report HThn~pson HDenton JLibermkn 4/5 /85 4/05/85 4/0/85 DL:ORB¹5*

DL:ORB¹5*

DL:ORB¹5*

OELD*

DL:AD/SA*

DSI:DIR*

OIE:D*

CJamerson:jb CMiller JZwolinski JScinto DCrutchfield RBernero RVollmer 4/05/85 4/05/85 4/05/8S 4/OS/85 4/05/85 4/05/85 4/05/85 ~

ggy(

E~: oq

II (I

~

ll n

hl I l I ~

I 'llh(~ ~

~

'l F

1 FF'r(

"'r~

it I r I

'I

~

I I

h lhlh(

a v

• h" h

'I 'hv I r F h 41Pf rh

, P li I

E h

~ r

~ I, hhl r

EV r

'Il 1

F

.h)li Im I 'hr I, li

-r, I)-

F QI I P

PP(h i(

11 I

~'( hgr

Ivy

+g) l"%'g',

~ 'I v'

>> f ~ IF r

+Ill~(y I I

fvl r

~

n

=rr lh

~F

~ (i P

- ~

",l P

' I O'I (F '1 I I" 4 rI l I' r vr 1

I

, I I

~ I

(

~

r I g hrrw I

• E 4

'i IIIEh yl ~ Eh 1

l',,v I

h I

hv (FFPI

~

ll II ~

I

~

II rh, I

P IF h'I I

• P

~

I r

~ '

f hl

'1 ll(P+

I' lip

(

P II 1

~ rl Il

'j I'

V I

~

1 I ~

1 r h

~.'

r

'I I

1 I h

P,

'I 1

, r+FPO

~

h ~ V

Docket No. 50-244 Mr. Roger W. Kober, Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

EXXON CODE ERROR Re:

R.

E. Ginna Nuclear Power Plant On March 15, 1985 Exxon Nuclear Corporation (ENC) informed us that they had discoverd a coding error in the TOODEE2 code.

This code is utilized as part of the Exxon ECCS Evaluation Model.

In order to assure resolution of the code error, as well as resolution of other concerns which have been raised as part of our review of Exxon LOCA analyses for other licensees, the staff contacted all Pt/R licensees with Exxon fuel and requested that they evaluate these concerns with respect to their plant.

10 CFR 50.46 requires that an acceptable evaluation model be used for analysis of ECCS cooling performance.

As indicated in the attached SER, the current version of the Exxon model is not fully acceptable as required by 10 CFR 50.46.

However, there is reasonable assurance that Ginna will operate in conformance with the acceptance criteria of 10 CFR 50.46 since a significant safety margin exists regarding peak fuel clad temperature and the 2200'F limit, and that in the event of a design basis LOCA the maximum fuel element cladding temperature will not exceed 2200'F.

Accordingly the public health and safety does not require, at this time, operating restrictions in accordance with 10 CFR 50.46(a).

Nevertheless, you are required pursuant to 10 CFR 50.54(f) to provide a reevaluation based on an acceptable model on a schedule negotiated with your project manager.

Sincerely, Hugh L. Thompson, Jr.,

D rector Division of Licensing

• SEE PREVIOUS PA(xE FOR CONCURRENCF.

Enclosure:

DL:DIR IR Safety Evaluation Report HThompson D

4/

/85 4/v /85 DL:ORB¹5*,',, DL:ORB¹5,",, DL:ORB¹5*

OELD*

DL:AD/SA*

DSI:D OIE:

CJamerson: jb CMil1er,, JZwolinski JScinto DCrutchfield RBernero RVol 1m'/05/85

,'/05/85

"<. '/05/85 4/05/85 4/05/85 4/g/85 4/ $ /85 L.

V

1

~"

tt) 16

'I P

~

ht l' 4

h'l

'g 4

I P

4' 1tt

,1)

~ 4- '\\,

1 tt ~ 4 I h ~

II 'I )I fl htht 4,

I

'I I'l4 ft ~ -'I

>>414 V

hh',',

h 1

$ 1hh/

4 1

I II f 4 1

~ >>

~

III

'tl

~ ~

'I

~

I

)4,th I I,')

I Q Pl,,

~

~

4 "I

I" 'h

~

hl

" -" rf ha'S 4 ~ <<<

4

~ 1 I

"11

~

h 4

1, h

IIV*

4$

h 444

'"Pff I I

~

I h

4 I th IP g

I- ~,Ih Ph,

)lh 1 t t

O'I I

4

--Pn 4

I I

+P)t 4

I hP Ph I

IQP) 4 I

II 4

th

'lt

) 4 f)>>ht)t l

P

~

~

t=

h= 41, R

1 ~

II, ll'I ih

~

I

~1$

I

<> I ',1

~ t '141

~

II I' yt PV 4

h

~'

~

h I

I th lff I P)

<<'l'>

'4 <<tf 4)yth $ f W 4)

P ILI

$ "f'1 ~

sf

P ) hh )4

~ P)g

)R

~ ~ 4 I ~

41

Docket No. 50-244 Mr.

Roger W. Kober, Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 De'ar Mr. Kober:

SUBJECT:

EXXON CODE ERROR Re:.

R.

E.

Ginna Nuclear Power Plant On March 15, 1985 Exxon Nuclear Corporation (ENC) informed us that they had discoverd a coding error in the TOODEE2 code.

This code is utilized as part of the Exxon ECCS Evaluation Model.

In order to assure resolution of the code error, as well as resolution of other concerns which have been raised as part of our review of Exxon LOCA analyses for other licensees, the staff contacted 'all PWR licensees with Exxon fuel and'equested that they evaluate these concerns with respect to their plant.

10 CFR 50.46 requires that an acceptable evaluation model be used for analysis of ECCS cooling performance.

As indicated in the attached SER, the current version of the Exxon model is not fully acceptable as required by 10 CFR 50.46.

However, there is reasonable assurance that Ginna will operate in conformance with the acceptance criteria of 10 CFR 50.46 since a significant safety margin exists regarding peak fuel clad temperature and the,2200'F limit, and that in the event of a design basis LOCA the maximum fuel element cladding temperature will not exceed 2200 F.

Accordingly the public health and safety does not require, at this time, operating restrictions in accordance with 10 CFR 50.46(a).

Nevertheless, you are required pursuant to 10 CFR 50.54(f) to provide a reevaluation based on an acceptable model on -a schedule negotiated with your project manager.

We have not yet reached a decision as to what enforcement action, if any, is appropriate for not having the required model.

Sincerely,

Enclosure:

Safety Evaluation Report DL: ORB¹5 DL: ORB¹5 CJamerson: jb

.CMiller 4/4'/85 4/~-/85 Hugh L. Thompson, Jr., Director Division of Licensing DL ONRR: DIR HThorppson HDenton 4/

J /85 4/

/85 DL:ORB¹5 OELD DL:AD/SA DSI: DIR OIE: D JZwol inski JScinto DCr utchfield RBerner o RVol lmer 4/ P'85 4/~/85 4/ ~ /85 4/

/85 4/

/85 ye~

Lqo g P

Pg P'~-p~

(

(

1

Docket No. 50-244 Mr. Roger W. Kober, Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649

Dear Mr. Kober:

SUBJECT:

EXXON CODE ERROR DISTRIBUTION NRC PDR ORB 85 Reading RJones HTHompson OELD Local PDR BGrimes JPartlow CJamerson ACRS (10)

EJordan JZwolinski CMiller Re:

R.

E. Ginna Nuclear Power Plant On March 15, 1985 Exxon Nuclear Corporation (ENC) informed us that they had discoverd a coding error in the TOODEE2 code.

This code is utilized as part of the Exxon ECCS Evaluation Model.

In order to assure resolution of the code error, as well as resolution of other concerns which have been raised as part of our review of Exxon LOCA analyses for other licensees, the staff contacted all PWR licensees with Exxon fuel and requested that they evaluate these concerns with respect to their plant.

10 CFR 50.46 requires that an acceptable evaluation model be used for analysis of ECCS cooling performance.

As indicated in the attached SER, the current version of the Exxon model is not fully acceptable as required by 10 CFR 50.46.

However, there is reasonable assurance that Ginna will operate in conformance with the acceptance criteria of 10 CFR 50.46 since a significant safety margin exists regarding peak fuel clad temperature and the 2200'F limit, and that in the event of-a design basis LOCA the maximum fuel element cladding temperature will not exceed 2200'F.

Accordingly the public health and safety does not require, at this time, operating restrictions in accordance with 10 CFR 50.46(a).

Nevertheless, you are required'pursuant to 10 CFR 50.54(f) to provide within 6 months of the date of this letter, a reevaluation'ased on an acceptable model.

The failure to provide this model within 6-months, unless otherwise extended, may result in modification, revocation, or suspension of your license.

We have not yet reached"a,decision, as to what enforcement action, if any, is appropriate for no't,havingithe,required model; Sincerely,

Enclosure:

Safety Evaluation, Report Hugh L. Thompson, Jr., Director Division of Licensing DL:DIR ONRR:DIR HThom HDenton 85

/

/85 DL:ORBB5 DL;QP5 DL:ORB55 CJamers: jb Ct@LI)r JZwoli ski A/c /85 g/g /85 g/g /8 D:

D field

'Q/85

/ )785 DSI:DIR RBernero

/

/85 OIE: DD RVollmer

/

/85

'w PI ~

? $ I C ) P ji ItCh n >'

'ych 5

j) ts II ~'c'

~ I -ch 1 tht "~ I 1

f Crt fh j) rsl"

~ tt ft 4

Ii r

hn f

w

~

I I

'I E

r I'

'1 If

'h ti I

\\ts c t) 1

>>Sht ts 1

~ t hsg <>

Sr ~,1 l

wcf I

)

I I ~

F-1

"'F I

'sj I

r

~ 1 F

~

P wtlht I

sc FI'it I

C11 tjlt)A I r E

lj s

I C

1 1

l I

<>

j"}Fy Q A

~

r c" 0 A*

l

<1 Ii) Cgh<<C ur

1) A'lF 1

nt IFF sf' cfrc I,,: tf ij.

tg 1

j}

I'<<"

I~A

'I

)I Frh'1, 1:,,ih,,h,, jg.}1 ',)

y ))".

1

"'cf"'"

~

~'h

" rjh.

tl I

I I

I

- fl 1

I

}~ ji r ttt,},

I I SSC,rt,, ~

• V P-">> f

~

Ir I t I '1 1

't I '

f ch rwgcc

}I

F '4++

)f }fg) / Q*

1 Ct,'I 1f+

tts}t>>

)f I

)

}),EIF t 1}, }f)l~ 1

• )

w ', hhnj, PAF 1

I ll },hqlr f

r,;I ) rg,f

>>r1

'cgffh 1

ll

'I

~

IIflrh IF)

Fr

+

nf~h

~

I Et

~

F hf ~

s I c,)l E)<<srt tg' h>>

<<'1 flan

)

~

lf1 t)t ",, I"

~ I 1

I

Mr. Roger W. Kober April 5, 1985 CC Harry H. Yoigt, Esquire

LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire

Avenue, N.W.

Suite 1100 Washington, D.C.

20036 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.E. Ginna Plant c/o U.S.

NRC 1503 Lake Road

Ontario, New York 14519 Stanley B. Klimberg, Esquire General, Counsel New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Dr. Thomas E. Murley Regional Administrator Nuclear Regulatory Commission Region I Office 631 Park Avenue King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road

Ontario, New York 14519 Jay Dunkleberger Division of Policy Analysis 8 Planning New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 U. S. Environmental Protection Agency Region II Office ATTN:

Regional Radiation Representative 26 Federal Plaza New York, New York 10007