ML20213D439

Requests Review of Licensee 800819 Submittal Re Engineering Evaluation of Mods to Sacrificial Shield Wall,Including Section on Rationale for Leaving Existing Known Defects in Wall

ML20213D439
Person / Time
Site:	Columbia
Issue date:	11/20/1980
From:	Youngblood B Office of Nuclear Reactor Regulation
To:	Schauer F Office of Nuclear Reactor Regulation
References
CON-WNP-0318, CON-WNP-318, CON-WPN-318 NUDOCS 8101060901
Download: ML20213D439 (5)

Text

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MEMORANDUM FOR: Franz P. Schauer, Chief. Structural Engineering Branch, DE Stefan S. Pawlicki Chief, Materials Engineering Branch, DE FROM: B. J. Youngblood, Chief, Licensing Branch No. 1 DL

SUBJECT:

REVIEW 0F WNP-2 SACRIFICIAL SHIELD WALL By letter dated August 19,1980, WNP-2 submitted an engineering evaluation of the modifications to the sacrificial shie.1d wall. T11s submittal included a section discuss'ing the rationale for leaving existing known defects in the sacrificial shield wall. Please review this section (Enclosure 1) and provide your analysis to M. D. Lynch by November 26, 1980.

B. J. Youngblood, Chidf Licensing Branch No. 1 Division of Licensing cc: J. Knight R. Vollmer R. Tedesco DISTRIBUTION: -

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N%C FORM 310 (9 76) NRCM 0240 D U.S. GOVERNMENT PRINTING OF FICE: 1979 289 369

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ENCLOSURE R0. 1 RA:10NALEFORLEAVfNGEXISTlNGDEFtuTS\

lli THE SACRIFICIAL SHIELD WALL (SSW) 4 I. Introduction .

A reviewof the as-built quality of the SSW revealed the presence of a number of weld defects per AWS DI.1.,

Some of the defects were detected after completion of the structure by visual inspection, the method of examination originally specified. l These defects do not meet the original design, weld quality criteria.

Other defects were detected by ultrasonic testing (UT), an exami-nation method more sensitive and stringent than the original inspection criteria. These defects do not meet AWS DI.1 criteria for volumetric inspection. However it should be noted that these defects would not ha~ve been found by the contract inspecticn methods, and structures built using only visual inspection for welds during fabrication would be expected to contain subsurface defects.

An assessment of the structural integrity of the SSW in the as-built condition concluded that all known defects will not prevent the structure from performing its design functions, and therefore do not require repair.

In general, further repair activities beyond those identified as necessary in the original report are considered to present more potential for detrimental effects on the SSW than for benefits to be gained.

The completed SSW represents a highly restrained structure with the fabrication sequence completed. To perturbate this structure with additional welding and localized preheats where repair is not required for design function should be avoided. Specifically, repair of structurally non-significant defects under these conditions has the potential for creating additional defects, such as cracks, which are more harmful than the defects under consideration. Elaborate precautions have been specified for the required weld repair at elevation 541'-5" to minimize such concerns.

Some defects are inaccessible and/or extensive disassembly, welding ,

out of sequence and rework would be required for repair.

Additionally, access to many areas of the SSW is limited by subse-quent attachment,s that restrict the working conditions for normal

, repair activities.

However, in consideration that some undersized fillet welds have a significant reduction in their load bearing capacity, the Supply System has elected to repair some defects of this type. ..

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. Specific defect considerations are discussed below.

II. Defects Not Being Repaired A. Electroslag Weld Indication -

Of the 73 electroslag welds examined by UT under Task Force direction, one contained an unacceptable indication. The rejectable indication was a large reflector located in a permanent steel backing shoe.

The defect is difficult to repair because of installed piping interference.

The defect is not conaldered structurally significant for the following reasons:

o The structural assessment provided in the original repo,rt, o It is located in the backing shoe, and o The weld function is redundant in that other weld joints in that vicinity have the capability and responsibility of transmitting the relevant loads.

B. Incomplete Penetration in Shielded Metal Arc Welds (SMAW)

These defects were found by UT, directed by the Task Force.

Of six welds examined, one was rejected for incomplete penetration in the weld root of a single bevel weld.

The defect has been assessed to be structurally acceptable using the conservative static analysis discussed in the original report.

Repair would require extensive excavation, preheating and rewelding with the potential for creating additional and more serious defects. ,,

C. Incomplete Penetration in Flux Cored Arc Welds (FCAW)

Seven double bevel T-welds were examined by UT. Six were found to have incomplete penetration in the root.

'Two single bevel welds were also found to have incoinplete penetration in the root by UT examination.

These defects have been found to be structurally acceptable

u. sing the conservative static analysis discussed in the original report.

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The double. bevel T-welds are located inside the SSW.

Their repair would require removal of external plates, redesign of the joint configuration, preheating and rewelding.

The single bevel joints are accessible, but extensive excavation, preheating and rewelding would be requireli.

In both cases, a potential for creating additional defects by the repair exists. '

D. Workmanship Defects Identified by Visual Inspection The following defect categories were identified by visual inspection of the outside.of the SSW:

o Porosity o ' Crater Fill

' o Undercut o 5xcess Reinforcement o Arc Strikes o Localized Lack of Fusion o Overlap o Convex Fillet.

As discussed in the original report, none of these defects are structurally significant.

Repair would require grinding or are air gouging, preheating and rewelding. In the case of overlap and arc strikes, rewelding would be necessary if the material' thickness were reduced below the design thickness.

Similarly, there is a potential for creating additional defects during repair as discussed before.

III. Repair of Structurally Significant Defects The following defect categories were identified by visual inspection:

o Undersize fillet welds o Underfill on a butt weld.

The undersized fillet welds were assessed in the original report '

for their collapse. potential for causing It was concluded thatfailure of by failure theplastic SSW by plastic collapse will not occur.

Some of the undersized fillets have an effective loss of load bearing cross section on the order of 50% or more. Because of the 3

,) c) large reduction in cross-sectional area of some of these welds, the Supply System will re-inspect the undersized fillet welds, care-fully determine the amount by which they are undersized, and repair those welds which have a reduction of load bearing cross section in excess of 25%, provided that the repair has a minimum potential for creating additional defects.

The underfill on the butt weld was not significant and will not be repaired for similar reasons discussed above.

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.f fiEMORAflDUM FOR: Robert E. Jackson, Chief  !

Geosciences Branch, DE .

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THRU: Richard B. McMullen, Acting Leader r.

Geology Section, GSB, DE _

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FROM: Philip 5. Justus, Geologist a . . ,

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D4 j Geology Section, GSB, DE '

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SUBJECT:

• ha i REPORT OF MY BISIT TO GABLE l'00NTAIN TRENCH EXPOSURES. HANFORD, WASHINGTON AtiD TO OTHER **

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GEOLOGICAL FEATURES OCTOBER 16 Af;D 17, 1980 C0tiCERfING UPPSS-2 OPERATIt!G LICENSE REVIEW - I Backaround -

On August 19 via conference call involving WPPSS, USGS, Golder Associates, '

I:ESCO (Puget SoundPPower) and fiRC (PM and GSB) it was decided that a joint liRC-USGS inspection of newly discovered possible capable faults at Gable  ;

fiountain, Hanford would be conducted in October.

References:

nenos-Jackson '

to V, night, 21 Aug. 80; Renberoer to Youngblood, 2 Sep. 80; Vollner to Pressesky, 2 Sept. 80.

Purnoses of Trip to Hanford

1. To gain knowledge of the reported possible capabic fault on Ga51e f40untain by direct field observation and discussion with discoverers.

2. To hear presentation of aeromagnetic anomaly interpretation of Rattlesnake Ilills area by llPPSS consultants. Weston Geophysical. .

3. To hear presentation of synthesis of tectonics of Columbia Plateau by UPPSS consultant, Prof. G. Davis. .

4. To hear presentation of t.lternative expla:.ations of the Toppenish Ridge ',

young faults by Prof. Davis. l

}

5. To visit exposures of faults alors '.he Rattlesnake Hills-Vallula lineament by WPPSS consultants tnd to be discussed with Prof Davis on site.

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f 10/16/80 ATTENDANCE LIST NAME AFFILIATION John Doherty Weston Geophysical i

David Tillson WPPSS Jim Mecca NESCO Lic.

Gary Anttone Golder Associates Donald M. Caldwell Golder Associates Howard A. Coombs Consultant - NESCO i Jay L. Smith Consultant - Golder Associates ,

l Donald M. Hitchcock Woodward-Clyde Consultants Philip S. Justus US NRC i

Robert H. Morris USGS M. H. Hai t, Jr. USGS 4

W. H. Hays USGS

Oreg Davis WPPSS Consultant John Imse Weston Geophysical Carl Stepp ERTC(ONWI)

Joe Caggiano Rockwell Geosciences J

Karl Fecht Rockwell Dave Squires US DOE - RL Ron Chitwood WPPSS 3

Jerry Sorensen WPPSS

{

j L. J. West Golder Associates *

{ Scott S. Smith Battelle/0NWI f Albert M. LaSala, Jr. USGS/ Columbus, Ohio

{ Michael V. Stimac Puget Power  !

j Steven W. Martsolf Puget Power l Paul W. Gottschalk ANCO Engrs.

l Vincent Murphy Weston Geophysical l

Don Bouchey WPPSS j Booker Hall WPPSS Larry Peralta WPPSS i

Stephen Reidel RHO j Ed Price RHO

.)

W. G. Keltner WPPSS i

Itinerary WPPSS 2. Site Visit to Hanford Region Thursday - October 16, 1980 Aporoximate Subject, Speaker, Affiliation

1. 8:00 - 12:30 Presentations in Board Room, WPPSS Central Office 3000 George Washington Way, Richland, WA 8:00-8:30 Introductions David Tillson, WPPSS 8:30-9:30 Aeromagnetic linears near Rattlesnake-Wallula structure John Doherty, John Imse, Weston Geophys.

9:30-10:45 Tectonic interpretation.of Rattlesnake-Wallula structure Gregory Davis, Univ. So. Calif.

10:45-11:00 Break 11:00-12:00 Gable Mountain Geology and History of Trenching Don Caldwell, Garry Antonen, Golder Assoc.

12:00-12:30 Slide review of Toppenish Ridge surface offsets. Gregory Davis, Univ. So, Calif; lunch

2. 12:30-6:30 Field Trip 12:30-4:00 Gable Mtn trenches Garry Antonen, Don Caldwell, Golder Assoc.

4:00-5:00 Umtanum Ridge at Priest Rapids Dam Ed Price, RH) 5:00-5:30 Break 5:30-6:30 Saddle Mountains at Sentinel Gap Steve Riedel, RHO Friday, October 17, 1980

1. 6:30-3:00 Field Trip 6:30-7:45 Badger Mountain overlook, G. Davis 7:45-8:45 N-Hill Quarry, G. Davis

8:45-9:45 K-Hill Quarry, G. Davis 9:45-11:00 Finley Quarry, G. Davis 11:00-11:30 Break 11:30-12:15 Wallula Gap, G. Davis 12:15-1:15 Burlingawe Ditch, D. Tillson 1:15-2:00 Faulted Touchet, Umapine, OR, D. Tillson 2:00-2:15 Discussion, P. Justus 2:15-3:00 To Pendleton Airport l d

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./

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l

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\,. .- .

[s .

I j;1 = / / ... }

l5 $g f,.:

h . $,s**' i .G . ? ,?

. l E i () l' ' .3

'^

K_ ... '.

'y* ,,R. *_lc ,3 5 lD x. . ...n . /,' $.

~.

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/- .. . - c l's. A . /6 1: 4' '/,/.- . . . . -

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,-.. f .h .bU b U

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j -,-l-s f y - - .- e4 g_ m '. .

s'a .' . ',Ry'

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a I

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W SM SE .

h;; ..;;.S-2'[

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Feer l: #e.e.-

' ~ N 840* W j ;,[, ', - f - k 8\j .

Q^i f('-

I.':'- Ci B

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nw '

,. W ~ 's *C 'T I R-2

. . . GQ.~C5f?

~ T f ~ ~~

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p:o -... =. x f <

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...o

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f, m;fe_/ ~

., y ', .,

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, 'o .o : B g3_3 -

c . .' , ,- ;r j l .j .>

W:

l .

o 3.= Q-3. l' ' _ . ,~- **'

^

, * :. . * ; l n g"

. R -20

t-z ___ 2 =S-3'~..J'.."'e# ,, % , ((*' D ,.B7,; . , , : ' - 2 d

-3 y I- .', . ! [o' - ,

O ; J S-2.p., (,.g. . : R'l '

~

( .,":,'. ' N / $. .,.

' " Q .. . '

.s R2 - ' lIl N ,f l;- . p.g

- I;~'..,.M . jl., ?;.o .Ei'.$, %[?A G'E* j .-: .-, -

%.> 4

i. '.,$,a

+ . .,

., ' . o,N ';. ' ' AD. . . . ' .

,.. . ' j

- s . y..:

, . I

=J* .i . ,,;p..y f l,6 f.e ,;.. , ,f. : ,m. n " -

2

, . :7 .c.Y

' . 3 rp,;, .h f

. .. . 1 ' ' . .h 7

.-(j 3...

~

. -Ra .g. .

l u

c.v.q

%.. ,g

+ ,s,qysyigj,L',i "q.;  ;, 2 %yy, l-l .; g-( : w, e:#;

t. ', t, ". ,

g, f .s .,g,,,j g :,, g, g f, ,7,j,g';, ,, j in

.t , , ;

NN$hh NShik;N[I)N,N}h_Ck__.$.0 , d 1',, a

_ a. '.~lw..

_S I --

TRENCH G-3 S-2 Glacial ficod dc}xats, sarkj aruj graw-t DETAILED LOG NE WALL

[]S-3 Glacu thj 2repositi,, piit at21 sarts, some gravel O S-2a,S-3a Clastic x,like ' ',

R-l FcutWall basait-R-2 Tuff accous, gilty sandstone (Pattiesnake Kici.pintertrzj)

R-2a erecciated tuf faceous, siity sarvistone (Katlicenake Ric1ge Intert;ed)

F-l Fault gouge. -

S Shear-B ENwatt clast-f Fracture

• N GO W NW St.

O S-3 c,lacial flood deposiis, silt and Tggyv m sand, some gravel lg_3 7  % g' __ .y. .

R O S-3a clastic dike .

(S-3c>' ,

r ge S-3c- ..s, S-3b

. ]

O S-3b C.rossbedded silt- l --

- 7 . . -l - B -\ ' i ' I O S-3c crossbeooca basaitic sand i l S ab l 9:--

'" e? -

~5 +' .

0 S-3dsilty, sandy gravel gqq s '(B:'

-(l s s. t F p ,. 1@

R-l Fcorwatt basalt' '. ~ ..

A..

y

., 31 l. _J'y' S-$d'

_ _#_ - G L(NlyB

%l.

1. p i-S- s'c f 9 R-2 Tuffaceous. s)lry sandstone ol -

' .l ..

y l.,'A

[l (Pattlesnake Ridge Interbed) '

'[!ag.pp'g i

'b S-3b

'j,' . d"'-Q N

- i

, yr d R-3 Hanging Wall basalt- l- g 7- .7 ' j,,,.[)' , ..

3,{,, ,

F-l Fault gouge l sg'3 ~~g Sc 5 -- m- .

,q-  ;. . c ' . . '. .' . l S Shear l ,

'S~

' ' l

[ S-3b.' /

"7'.'-

%.  :.!L. " . . . . *B '.' 'd B basalY clast- L M~ ~~... "

,,L:'C.-mAfthAoppe[?+"~

s 1 V?'!%'..! A ;,

;..'* , t f Fractur'e .

l .

.g..e . .

, gif-.. @ c L

J W ' d. ]!gj . ' 0, f<

' )l .<,. 3 lr :. ..S.- 3c . n . , . ..

o .. 3:: ;,-

-B . .t .t, . 4 e . ...

.o . s - , .

.... 't.

_g ,', "iI

". _f

, 3, . ,

.s

.v . ; g. ,g3- f.,, '. O * ,

...r- -

. r ,. ;., . 7 .. s ;q. .. .;. f . ' -

, ('* h . * ' a J ,

~' '

l. _

l-l.\. .

.o. .vA w' ...L. ij1.l . s .

I l 1 l  :: .

'R-l

'l:

o .

n y '

. + ' ' / . ,. -

,,y c)

I

• l TRENCH G-4 l DETAILED LOG NE WALL r

St=. N Go" w w NW OS-3 eiaciai riood aeposits, siit ana ~

sand, some gravel T(la

~-

B SN30 ,:..:.

-37l B 3_3 ... .

, S-3b /

Clast'ic dike OS-3a OS-3b crossbedded silt- I '

, : r-

' }"' , S-3c-

'c---

A S-3b * ' ' ' ~

1. '2" ' " #'

'I OS-3c crossbedded basaltic sand l'"'- 't. N CS-3d s'ilty, Sandy gravel '

f :': C

.',r WB Rx S-3b Ql OR-l

.R-2 Footwall basalt-Tuffaceous, silty sandstone nl :; .. .1 ,,

.. (,.. $

S-3

~

l. q

4'm' -

3 y rlf (Ratilesnake R1dge Interbed) <l' /,.;;< D 7,,,

, y . ~' {l ,

S-3cks NR-3

1. - 'D Hanging Wall basalt- M" ' - R 2'... .

\ (B Bj ~

=.__ k F_l Fault cjotx3e. y

. q, m .p l lll S Shear .c

. ' u %.

.: ' i m: . s.

. . : 'c.

s.~._x:a W:-- - -l g]

-l l~ ' . \

"X('.e p- ' ^ %. '.

B Basalt clast- -

~

N : r. .... , - . . ..

" :I..

f Fracture

.'~.;.*l

.S

. ' ..3

...\

t

. .-  ;.'.,'Ir'

..~ . -

h 1, ,

. h, d.I,.[5l CB3 S - 3 c ' ' . q , ' < , .

,, \h.\:, . ' p87 S - .. ~b[, l x- y ,\ .

.. '. F '#,'

c O.

i I

b) - -

, ' lpgut 7

{ c . *, iR-

~

- ~. '

• *Q. --

Q. :,_ . -

i lb..i , .. .

,:f .

.,(

...S-3c

.,. l 1 .; . ,. .

...l, - '

l. .

. , .!' ' , . f.?Q l po .

. :l

,t ,

, , . . ., n

_ j TRENCH G-4 DFTAll FD I OG SW W Al I

SE:.

t 4 25* W l

Top cf Trench Excavallori -

t JW S-1 S-l 03 s J

gl g_; \

g lb b @ '

F I S-3 ,Oo.h , <8 rr n) d[' 'b N "o.

, - Ico ,h.op-

.i '

..[f) I'))

~

F uL7 W'Dottom of Trench \ f ' '

s, Os-i tcess .. '

-I rect

• S-3 Glacial flood deposito, siIt' and sand, scxne grael I R-l Footwall basalt-R-lo E3recciated Icutwall basalt-R-2 Tuffaceous salty sandstcvle (futticsna e Ridge Interred)

ER-3 Hanging Wall basalt-F-l Fault gouge, S snear- TRENCH G-8 .

B [5asait clasts SW WALL

e' ld -----

(m o pua W . ^ .-, -

,I .

g: a g.

,*^Q-

.e. I <

' .' l f6 05 42 . , ,

P tE

. :y , . . -

.: ,'.I 1 ~,.&. o

. . .. g. . . ..: ..

. 1m g ,-

Z

. . ' . ' .,: {. . -

.:..] O(. W m

i

..._e .- . ...

..i .

.0 CC c,-

/ '

_... .g . -

..s..

. ,\ . a p. .. . d. .a.

p

-.m ...:.. . .p .

s..

.tu e .o.-. f.

i - .

. .I c. o c-m ' :, ..'

. I QB .

< ..'^ .

, . 9 9. . .

c

/ ,

./.

g.

1;.fp

, n. .:-

Q ,  % v' .

In- .c. ,C g A c

.Q , 195 g ,

g -

.c .

.. .. . jas ., s v --

y a . v. e E -

a.

.? ;I'm a

.Q.., oo: la W g

. . . . . j t . G Rc

. ..g..p.

,9.,ea. .

e g -

~ .

..y a 7

y -

m.

I . h.  :. s p

a 9 ,.

.r ,

e -

zc 2 c. q-

a. -

. -.

• I; m

P ': . .0 ..' -

F N *

• 2

_ . . / ,.. ?

.:.y$.g-.

\

' ,. , ; i ..

p' 7

ci i

' '.Y \. ,

.h y D

y -h r0 t

M a .-

., = :n

.O 0 &

oi ,

P cu a i

.T/e f..%

v t

E o

ea.

o m 76 j =,

a t.

m e

t g

. .t. .3 G tE e Fn 3

- . .m Q '~ _m_

~4. /

aaeiem g L _ __ -- -

'W D 00 Z DCT -P Pug

Se t t ns* w -~

'f_

1 Top cf Trench Log NW S-2 i

gQ,QP Ocb 'b o ggggg oq:4p 6 PSB@31N m wo f c

i T. M{

s c

,~....w.

Y f"'f " "'""'"s.T

,.c_

.'"',,_,._ . o {R 3 i ; h, --

o o ._

F

d. , [,'.

8B M a, ma. '

.y . . f. y f,e , - - 7 7.Q . i e

<, r2. . . { ,: .[i ' wis Trencn

f. d~MJLT

• 4

. . I.

fect a

~ '* ,

Os-2 emanima aeers.Saw and era *' """* S"

on_i roamn tes "~

OR-lo secciated fmman bsaH- TRENCH G-10 BR-3 HangingWall tasait- SW WALL OF-l moirgouge.

OF-2 Decciated 11.orraccous sg) saestone ')

St.iesnaxe a+ inter 1

t se nu.u-- ~

nu V'

l;nmewa-aav:r. 9 acq 0>.wt o o Bg , j> : a c. .

n

a i~l

.l l

l.

s-2.ggayj?l;Le3o. t ~l

.c .e . .

.:. ..,.. &p.  : * *: v E, l_ .. ... . . ...

-(j)

C>[_ g . -

b h .g.?d.. 0., - o/ ,.

y c

~ . -

f.3 lf s

al

• l '

9,.s l .

. R to g_

.. 7 l

[j- s.

. : l

3. q " '

' ' - ~

l 4

. .' (: ;3

.' , .. . g r ' '. ';

~.

. N .\ .. .,, l 4/,l'.

' p.-)f@. r-

'I '.. .il*6$.'!.W.i.;

i. \' b.1f il TRENCH G-10 1

.l- ', g,

?. Q'. -

.1  :

, - ' : ' ' ! '...1.:i (-l . ..pld .'

\

i

.l DETAILED LOG SW WALL

3. "J.*.M .; :,.. * ,' y . (,. J ' . 1.' . i.: . ' . V . J ~. ,c

' ~

. p j i

S-2 Glacial flood depoe;its, sand and cyavel sone sit-R-I Fcutwall basalt-O R-ia ereccnatea footwail basair

. R-3 Ilanging Wall basalt- -h O F-l Fault gouge.

F-2 b ecciated, t uffaccous, soty sandstone '(2 8, (Kattlesnake. Ridge Interbed) rect-B Basalt clast-F Frac turc

N

= - N :S

• W 1

I Top of Trench E>ccavahon I /

~

I i s I

I I

I I I I S-2 1 g .

3:I .

S-2

'bl x

' Ii [rs f

n':: . -

t c... _..

i i:S .2:. =;

lill2 , .

iB if t

~ ; m s , q.e.._,m =. . ,,,-,_,_,;,, .

.;; . . .._=:S-2  :;

. ;~ cr.. ymyn g

Q. . ., . . .; r r :..S u . '

i > .

- R-l gx . , .,.. . ,

S-2 .. .

8.3 I g_, . c. ... . . . . . . .

, . ~, / . . . :*/g.gr% Qk Rc Neonorn r' d.

of Trencr/M s; S 'sS

%, , . .> F- I '

~

f

. s <

\ ,,ut7 S-2a \

t .

c,iaciai fiwa' erosits. eena S-2 TRENCH G-11 OS-2a clastic dike EAST WALL l R-l Footwall basalt-BR-2 Hanging Wall basalt- I-F-l ISasalt breccla w 0 l S Shear Feer -

B Basalt clast-

N = -N:5 W 1

I Top of Trendl L=xcavation I /

I l

1 S

i i

l I I I S-2 '

I -

I u s

.I

.','lp g .,

S.- 2 ,

.~ I

~'

'O '. . h C'.. ~

~~

i til ':::S .2 tB

..~~' ' '

,' .$ - 2 ll

, 'C-u:.L; :  :.'. ' ..+m'-t.'.~-~.=r; -=.~r.~. =~. -- .~~ = -

.g.3,~.=yq:@. .s' f;: .g_y;5. ' . . .- ;....:...

. y-I i '.s s'

' ' . .. . . . , . , , [ e. * :. S....- 2

w. S -2 .. 6. .; .i R-l. sb ,'

' '^ '

. ':J' . 9:. . . .m ' ,ji N .

P,

~

R .I . .

.D'

, N ?y.m\ .

yS'sS

~

?' E' :'

eortom of TrencdDs . '.

% \ F- l

s s,

_. 3 . . l *

'S-2a

.. s FAULT

\. ,

S-2 m aciai n aca a' eposus * "a TRENCH G-11 OS-2a clastic dike EAST WALL R-l Foohvall basalt-R]R-2 Hanging Wall basalt-1-

F-l Basali- brecc'ia .

o i

! S Shear Feer

B Basalt clast-i

N N3"W

.. ,i

.; , I Top of Trench E.xcavation s

d

.-l S-2 '- .'. ; . . .

.l  ;

f. ..

.i

_ ,.....;,..j_

~' '

' '. - .':c'.. .

i. . .'. s-2 '. -

. ,: .'l:i:.* . ;W .hk. .q.qlM.Mi~

c\$%fiEfJ.Qb{

' m.. . ' ..  %

's

.= :. . . . ...:. . ,. . ._ . .[. _ . . ,:: . ,. . . . .

n llk w..ar.1) 7 . , ,

..  ; s .: .- ._.;...- .

dj$

] .- . '

< .- . .p . c y .

4 g &ilh k.?.,AT i.

,3. P,..'~ _ ' " . . ' i>  ; 2 .I

,;.I y}8,.>:.3. ,:... S '[.R[s.lM...f.r...%_ '

i 2 ....  ;,

\ \

,:r .

- ~

.g l ,_

F iU r ,

r

/

, hDS.9 '. ,

,..1 Q,,"y.. .;,.

, C ', '. ,I jo: ' ,, . :. ., ;i .lR-l . " I

. . . . < . e,

. U . .,..:

' ,.R . .t, '~. -,.

J j .

, ". . y> .

, ' .4

...a... .< /

-)-

.1 ,

1

. 6, . , ,,. -

l

.C'., .

Neottom cf Rench

_ a ._-

rL I ..

. A, l

i S-2 Glacial flocd dep-st's, sand TRENCH G-12 l

R-l Footwall basalt- WEST WALL 0 R-lo weathered fcotwall basalt-lH R-2 Hanging Wall basalt-F-l Fault- breccia S Shear _i B E5asalt clast- I f Fracture Feet-

l l

l GENERAL OBSERVATIONS '

NORTH FAULT e Single fault striking general N40E to N60E and dipping 30 S.

No major branch to NE (Trenches G-6 and G-7).

, '\

o Hanging yall di,splSced to NW with thrust sense of movement.

. ' . . ,~,.., , Q) e Displacements i,rb'edrock units die out to the NE along fault strike.

,e:/ ,,'

\~ . ./ _

e Displacements of flood deposits over the bedrock fault are small and thrust in nature (D.'2' foot or less) .

s

. </ /

- .c

. rl ..! s e Associated,.,e.. mi,nor normal rdisplacements of flood deposits in hanging wall are obse'rved-in,. some trenche,s.X

~,.-

..* ,e' t .

e Displacements appear to b'e refracted and absorbed by ' flood deposits.

(? ,.

k,~

,/

e Apparent maximum lerigth of displacements in' flood deposits -

is 1100 feet.

.? -

' /V .

, . . - y y, ,.e y e

Clastic dikes show evidence o,f.m6vement in two loc,ations t, (Trenches CD-5 and G-3)'. .- ,

/ ,r.

/

/

O b

SUMMARY

OF OBSERVATIONS NORTH FAULT TRENCH CD-5 e Oriented.. slickensides in clastic dikes parallel to slickefi,si' des in gouge on fault Breccia (Trench CD-5).

, .' s '

)

-e Rol$s,hed,slickensides on fault plane only -- not on

',r,.-

. . verticai dikes above fault (Trench CD-5) .

\ ,

_/

'e Wherever firie-gtained material is present along fault

,e J q plane, s'lickensides are present. '

i / *

./

e No, displacements were measured by Golder Associates wh'ere. dike crosses fault NIane.

,. ,o ,..

.-' . i' .

.. / Q ' _. '

TRENCHES CD-8 AND G-1 ". '

e No apparentIispla' cement of coarsfyrained flood deposits across fault (CD-8 aiTd G.71)'.' -

,/ s.j-

/, , ,

o Clastic dike present' alo,ng ' fault

• plane (CD-8) .

'y*"

e'

,/' .

,' .- 1

/

l ',/

/ s' 9

b

SUMMARY

OF OBSERVATIONS (cont.)

NORTH FAULT TRENCHES G-T, G-3, AND G-4 e Base of flood deposits disrupted along fractures par.ille,l,tc fa' ult plane (all 3 trenches).

. ./ \

\

,-a. ~Q!spla. hemebts in flood deposits 0.2 foot or less

, and thrust in nature parallnl to the fault (all 3 trenches).

.. / '

\

_f

^

\ '* e,. Base of flood,d& posits displaced normally 0.3 foot in hanging will (Trench G-3).

/ // ,-';

e C1'ay, gouge extehds into flood deposits 0.2 foot

('all. 3 trenches).- . .

.es

%. . - , _. /

_s . ,

o Clastic dikes associatedwith' fault (Trenches G-2 and C-3) ./

.-f' ,<'.

< _,s - l o Clastic dike' displaced normally C'.'3 foo,t (Trench G-3).

p f /\j.3

,/ . y, TRENCtlES G-9 AND G-10 v.

s ..

/ ,,

e No apparent displacdments in flood deposits SW in .

Trenches C-9 and C-10. ,,/' ,

j.,

./,, /  :

i

( ,

e i

e

f

SUMMARY

OF OBSERVATIONS { cont.)

NORTH FA' ULT TRENCHES G-2, G-3, AND G-4 l l

4 e Base of flood deposits disrupted along fractures l parallel..to fault plane (all 3 trenches).

\

e. 'Displaceme' n ts in flood deposits 0.2 foot or less

- - ,.^' and

_- thrust ..- in nature parallel to the fault (all 3 trentnes).

\ e,Aase of flood dep'osits displaced normally 0.3 foot in Trench G-3) .

hanging / wall / (/ ,!

~~

,e _.

e Efay,go0ge exteibs into flood deposits 0.2 foot (al} 3 trenches) .

, ,,s s

e,.. s e Clastic dikes .- associated'with fault (Trenches G-2 and G-3) ./ .7

/.

. e , ,

. ,/ ,

.e s e Clastic dike' displaced normally W.3 foot (Trench G-3).

.- u -

,/s.,:>

[ 'g TRENCHE5 C 9 AND G-10 ':

s e No apparent displacdments in flood deposits SW in

./ .

Trenches G-9 and G-10. ,

> /

/ y.- 1

(

g O

e

- + - - . * . - , - , - -

GENERAL OBSERVATIONS SOUTH FAULT e Continues to the east for 300 feet from Trench CD-6 to C-12 with nearly E-W strike and 30 to 40 S dip.

,~.\,

e Does not-di plad flo,od deposits in Trenches G-11 and C-12.

, .e ,, /

. /

e Claspq dikes .al ..-ong fault plane in Trench CD-6 have stickensided

' ~

st)r, faces.with striae parallel to the dip of the fault.

. /

!~ ..

_.- .e ,

e Shears, possibip s asso6iated ,with the thrust fault, appear to cross and..slightly,'.-displace' clastic dikes in the footwall in an area of Trenfi1ID;6.'

/s 4 -

.s.  ?,

, ,o y*

,e * '

m

,S

• gO, f  %

./p '

/* ,s- .

i

/ W

/*,/ -'

.. s

-f

%,." g

, [ ,

d' #

~

, , /

/

\,./-

l I

e

h FINDINGS CLASTIC DIKE AND SURFICIAL DEPOSITS STUDIES

e. Two distinct cycles of deposition are present on the north side of Gable Mountain; possibly three on the south side.

e

/\

Clastic dikes' associated,,-

with each overlying cycle are found in Trenches'CD-ff G-2, and G-3.

.? . .? ./

,,(s -* .. ~

e "C, astic ' dikes-In Trenches.CD-5 and G-3 are displaced by shearing onNthe fa' ult plane (CDd) and in the hanging wall (G-3) .

e _.

l fj' ,'?

e in Trench G.--3 displacemen.ts in the flood deposits appear to s y; '

post datefthe younges.t d!astic dike.

% ,. ?',- '

/, A

'o The youngest. clastic dikes origi,nate (f.om the base of the coarse upper unit of flood deposits,whidh,is' bounded at the top by St. Helens S ash as'found N 7,renches CD-4 and G-1.

o Clastic dikes on Gable Mountain are sinlilir in'ljthology and fabric .

, s .

to those found elsewhere in the Pasc'o Basfil.'-/

/ .. -.

. r' e Flood deposits on Gable Mou,. . -n,tain', bear a close resemblance to s- .

typical Missoula flood deposits. '. ,

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ASSESSMENT e The north fault displaces materials apparently correlative with late Pleistocene Missoula flood deposits, e Displacements..in recent sediments are compatible with older movements on the underlying bedrock fault.

.,,, ~ > ,,s.. / _

e .Displac.e,ments..are small (0.2 foot or less) and limited in length (maxi' mum. distance over, which displacement in young materials

~

can be traced is approxim,ately 1100 feet) .

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e To date, noviden.j:e -

E,/ h.as been found in trenches to disprove tectonic activity'as the origin of displacements in the flood deposits. . '. ' ~' f ^t s, e' +

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fa areg[%, UNITED STATES

[% g NUCLEAR REGULATORY COMMISSION s- l wAswmcTon, o. c. rosss

..... DEC 5M Docket Nos.: 50-3584 M' 50-322, 50-341 g *,cp 50-373, 50-387 F APPLICANTS: Cincinnati Gas and Electric Company Long Island Lighting Company Comonwealth Edison Company Detroit Edison Company  :

Pennsylvania Power and Light Company Washington Public Power Supply System FACILITIES: Zimer 1, Shoreham 1, LaSalle 1, Fermi 2, Susquehanna 1 WNP-2 .

SUMMARY

OF MEETING HELD ON DECEMBER 2, 1980 A meeting was held in Bethesda, Maryland with the above named members of the Boiling Water Reactor-Licensing Review Group (BWR-LRG). The purpose of the meeting was to discuss the current status of the LRG issues. The list of attendees for this meeting is provided in Enclosure 1.

I began the meeting by distributing a list of the LRG is' sues which indicated the current status (refer to Enclosure 2). Each of these issues were discussed with the LRG members. During the discussion of PSB issues, Fire Protection concerns were also discussed. A status report of the LaSalle specific issues was also presented at the meeting. This report is attached as Enclosure 3.

At the conclusion of the meeting, the LRG presented their consensus positions on recently)

Enclosure 4 . issued The nextconcerns fromthe meetire. with theBWR-LRG Core Performance Branch was tentatively (provided as scheduled for February 1981.

i

• J .

, ry N. Wilson RC Manager for BWR-LRG

Enclosures:

As stated cc w/encls.: See next page l

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00) 2! ?c 2.?j

Mr. M. S. Pollock Vice President- Nuclear Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801 ces:

Howard L. Blau, Esq. Honorable Peter Cohalan Blau and Cohn, P.C. Suffolk County Executive 217 Newbridge Road County Executive / Legislative Building Hicksville, New York 11801 Veteran's Memorial Highway Hauppauge, New York 11788 Jeffrey Cohen, Esq.

Deputy Commissioner and Counsel David Gilmartin, Esq.

hew York State Energy Office Suffolk County Attorney Agency Building 2 County Executive / Legislative Building Empire State Plaza Veteran's Memorial Highway Albany, New York 12223 Hauppauge, New York 11788 Energy Research Group, Inc. MHB Technical Associates s

400-1 Totten Pond Road 1723 Hamilton Avenue - Suite K Waltham, Massachusetts 02154 ,

San Jose, California 95125 Irving Like, Esq. Stephen Latham, Esq.

Reilly, Like and Schnieder Twomey, Latham & Schmitt 200 West Main Street P. O. Box 398 Babylon, New York 11702 33 West Second Street Riverhead, New York 11901 J. P. Novarro Project Manager Joel Blau, Esquire Shoreham Nuclear Power Station New York Public Service Commission P. O. Box 618 The Governor Nelson A. Rockefeller Bldg.

Wading River, New York 11792 Empire State Plaza Albany, New York 12223 W. Taylor Reveley, III, Esq.

Hunton & Williams Ezra I. Bialik P. O. Box 1535 Assistant Attorney General Richmond, Virginia 23212 Environmental Protection Bureau New York State Department of Law Ralph Shapiro, Esq. 2 World Trade Center Camer & Shapiro New York, New York 10047 9 East 40th Street New York, New York 10016 Edward J. Walsh, Esq.

General Attorney Long Island Lighting Company 250 Old Country Road Mineolg, New York 11501 Resident Inspector /3horeham NPS j

c/o U.S. Nuclear Ec3ulatory Comission P. 0. Box B Rocky Point, New York 11778 l

yn Mr. J. S. Abel l Director of Nuclear Licensing Commonwealth Edison Comoany Post Office Box 767 Chicago, Illinois 60690 cc: Richard E. Powell, Esq.

Isham, Lincoln & Beale One First National Plaza 2400 Chicago, Illinois 60670 Dean Hansell, Esquire Assistant Attorney General 188 West Randolph Street Suite 2315 Chicago, Illinois 60601 Mr. Roger Walker, Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 737 Streator, Illinois 61364 O

I e

.. 1

,- J Mr. Noman W. Curtis l Vice President - Engineering '

i and Construction -

Pennsylvania Puer and Light Ccmany 2 North Ninth Street Allentown, Pennsylvania 18101  ;

cc: Mr. Earle M. Mead Mr. E.B. Poser Project Engineerirg Manager Project Engineer Pennsylvania Power & Light Company Bechtel Power Corporation 2 North Ninth Street P. O. Box 3965 Allentown, Pennsylvania 18101 San Francisco, California 94119 Jay Silberg, Esq. Matias F. Travieso-Diaz, Esq.

Shaw, Pittman, Potts & Shaw, Pittman, Potts &

Trowbridge Trowbridge

. 1800 M Street, N. W. 1800 M Street, N. W.

Washington, D. C. 20036 Washington, D. C. 20036 Mr. William E. Barberich, Dr. Judith H. Johnsrud Nuclear Licensing Group Supervisor Co-Di rector .

Pennsylvania Power & Light Company Envirunmental Coalition on 2 North Ninth Street Nuclear Power Allentown, Pennsylvania 18101 433 Orlando Avenue State College, Pa 16801 Edward M. Nagel, Esquire General Counsel and Secretary Mr. Thomas M. Gerusky, Director Pennsylvania Power & Light CoIpany Bureau of Radiation Protection 2 North Ninth Street Department of Environmental Allentown, Pennsylvania 18101 Resources Commonwealth of Pennsylvania Bryan Snapp, Esq. P. O. Box 2063 Pennsylvania Power & Light Company liarrisburg, Pa 17120 2 North Ninth Street Allentown, Pennsylvania 18101 Ms. Colleen Marsh Box 538A, RO#4 Robert M. Gallo Mountain Top, PA 18707 Resident Inspector P. O. Box *52 Mrs. Irene temanowicz, Chairperson Shickshinny, Pennsylvania 18655 The Citizens Against Nuclear Danagers John L. Anderson P. O. Box 377 Dak Ridge National Laboratory RD#1 Union Carbide Corporation Berwick, PA 18503 Bldg. 3500, P. O. Box X Oak Ridge, Tennessee 37830 Mr. J.W. Millard Project Manager Gerald R. Schultz, Esq. Mail Code 394 Susquehanna Environmental Advocates General Electric Company P. O. Box 1560 175 Curtner Avenue Wikes-Barre, Pennsylvania 18703 San Jose, California 95125

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Mr. R. L. Ferguson Managing Director Washington Public Power Supply System P. O. Box 968 3000 George Washington Way Richland, Washington 99352 ces:

Joseph B. Knotts, Jr., Esq.

Debevoise & Liberman 1200 Seventeenth Street, N. W.

Washington, D. C. 20036 Richard Q. Quigley, Esq.

Washington Public Power Supply System P. O. Box 968 Richland, Washington 99352 -

Nicholas Lewis, Chainnan Energy Facility Site Evaluation Council 820 East Fifth Avenue Olympia, Washington 98504 Mr. O. K. Earle Licensing Engineer P. O. Box 968 Richland, Washington 99352 Mr. Albert D. Toth Resident Inspector /WPPSS-2 NPS c/o U. S. Nuclear Regulatory Commission P. O. Box 69 Richland, Washington 99352

[

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Mr. Earl A. Borgmann Vice President - Engineering Cincinnati Gas & Electric Company P. O. Box 960 Cincinnati, Ohio 45201 cc: Troy B. Conner, Jr., Esq. Leah S. Kosik Esq.

Conner, Moore & Corber 3454 Cornell Place 1747 Pennsylvania Avenue, N.W. Cincinnati, Ohio 45220

} Washington, D.C. 20006 W. Peter Heile, Esq.

I Mr. William J. Moran Assistant City Solicitor General Counsel Room 214 City Hall Cincinnati Gas & Electric Company Cincinnati, Ohio 45220 P. O. Box 960 Cincinnati, Ohio 45201 John D. Woliver, 8sq. ~

Clermont County Comunity Council Mr. William G. Porter, Jr. Box 181 -

E Porter, Stanley, Arthur Batavia, Ohio 45103 and'Platt 37 West Broad Street Mrs. Mary Reder Columbus, Ohio 43215 Box 270, Rt. 2 Mr. James D. Flynn, Manager Licensing Environmental Affairs Andrew B. Dennison, Esq.

3 Cincinnati Gas & Electric Company 200 Main Street B P. O. Box 960 Batavia, Ohio 45103 Cincinnati, Ohio 45201 Robert A. Jones, Esq.

David Martin, Esq. Prosecuting Attorney of Clemont Office of the Attorney General County, Ohio 209 St. Clair Street 154 Main Street First Floor Batavia, Ohio 45103 Frankfort, Kentucky 40601 Resident Inspector /Zinner Dr. Frank F. Hooper RFD 1 P. O. Box 2021 School of Natural Resources U. S. Route 52 University of Michigan Moscow, Ohio 45153 Ann Arbor, Michigan 48109 Charles.Bechhoefer, Esq., Chairman Atomic Safety & Licensing Board Panel ,

U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Mr. Glenn O. Bright Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Comission Washington, D.C. 20555

F.

Dr. Wayne H. Jens .

Assistant Vice President Engineering & Construction Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 cc: Eugene B. Thomas -Jr., Esq. David E. Howell, Esq.

LeBoeuf. Lamb, Leiby & MacRae 21916 John R 1333 New Hampshire Avenue, N. W. Hazel Park, Michigan 48030 Washington, D. C. 20036 Peter A. Marquardt, Esq.

Co-Counsel The Detroit Edison Company 2000 Second Avenue . .

Detroit, Michigan 48226 -

Mr. William J. Fahrner Project Manager - Fermi 2 The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 40226 Mr. Larry E. Schuerman Licensing Engineer - Fermi 2 Detroit Edison Company 2000 Second Avenue

. Detroit, Michigan 48226 .

Charles Bechhoefer, Esq. , Chairman Atomic Safety & Licensing Board Panel U. S. Nuclear Regulatory Commission

• Washington, D. C. 205S5 Dr. David R. Schink Department of Oceanography Texas A & M University College S.tation, Texas 77840 Mr. Frederick J. Shon ~

Atomic Safety & Licensing Board -

Panel U. 5. Nuclear Regulatory Commission Washington, D. C. 20555 i

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-~ "

ENCLOSURE 1

^

List of Attendees NRC Staff Cincinnati Gas & Electric Comoany

~

Jerry Wilson J. D. Flynn Anthony Bournia F. J. Svetkovich Bob Bosnak Farouk Eltawila General Electric Wayne Hodges Jerry Mazetis D. J. Robare Robert L. Tedesco Tom Wortham Bill Morris J. L. Mauck G. G. Rhoads Commonwealth Edison Comoany Richard Stark L. L. Kintner L. O. DeMeorge I. A. Peltier G. Thomas J. Knox Detroit Edison Comoany Tim Collins Larry E. Schuerman Wm. F. Colbert Stone & Webster (Shoreham)

John Murphy Pennsylvania Power & Liant Comoany 4

C. T..Coddinaton Long Island Lichtina Comoany Phil Henrickson John P. Morin Bechtel Washinaton Public Power Sucoly System E. Connell, III John A. Ellwanger

. Pat Powell

~.

W me b

ENCLOSURE 2 LASALLE ISSUE RESPONSIBLE A/D LRG STATUS STATUS ACTION RSB-1 Plant Systems Unique Ooen C RSB-2 Closed Open C RSB-3 Doen Open C RSB-4 Closed Closed -

RSB-5 Doen Onen C RSB-6 Closed Open C RSB-7 Closed Closed -

RSB-8 Open Onen C RSB-9/13 " (new MEB concern) Open Open N RSB-10 Unioue Closed -

RSB-11 Unique Open C RSB-12 Closed Closed -

RSB-14 Closed Lic. Cond. -

RSB-15 Open Closed -

RSB-16 Closed Closed -

RSB-17 Closed Closed -

RSB- 18 " (plant specific analysis) 0 pen Closed -

RSB- 19 Closed Closed -

RSB-20 Closed Doen N RSB-21 Open Open C RSB-22 Open Ooen C RSB-23 Doen Open C RSB-24 Open Open C RSS-25 Closed Closed -

RSB-2E Closed Lic. Cond. -

ICSB-1 Unique Open N ICSB-2 Unique Open C ICSB-3 N/A N/A -

ICSB-4 Unique Open C ICSB-5 Unique Open N j

ICSB-6 Unioue Ooen C ICSB-7 Closed Doen C ICSB-9 Open Open N ICSB-10 Open Ooen N' l ICSB-11 Closed Closed -

CaCommonwealth Edison NsNRC l

f '

ISSUE RESPONSIBLE A/D LRG' STATUS LASALLE ACTI0':

STATUS PSB-1 Plant Systems Open Open C PSB-2 Unique Doen N PSB-3 Onen Onen C PSB-4 Open Open C PSB-5 Closed Open C PSB-6 Unique Closed -

PSB-7 Open Open C PSB-B Closed Closed -

CSB-1 Core & Containment Systems Open Open C CSB-2 Closed Open C CSB-3 Unioue Closed -

CSB-4 Doen Open N CSB-5 Open Ooen C MEB-1 Components & Structures Closed Closed -

MEB-2 Closed Closed -

MEB- 3 Closed Closed -

MEB-4 Closed Closed -

MEB-5 N/A N / 4. -

MEB-6 Closed Closed -

MEB-7 Closed Closed -

MEB-8 Unique Ooen C MEB-9 N/A S /;- -

MEB-10 Doen Ocen  :

MEB-11 N/A N/A -

MEB-12 Unique noen i:

MTEB-1 Materials & Oualifications Unique Ooen C MTEB-2 Uniaue 0?en C MTEB-3 Unique Ooen C MTEB-4 Closed Onen C C= Commonwealth Edison N=NRO

c jf; CLOSURE 3 STATUS OF LASALLE ISSUES 2 1.

Flood Potential - (2.4.2, 2.4.5)

The is acceptable.revised gradation for the riprap submitted in Amendment 41 to the F However, the as-built spillway riprap does not conform to either theThe practices. stated design in the FSAR or to good riprap erosion protection applicant is taking remedial action.

completed, we will inspect the as-built riprap. When this action is '

2.

Low Shear Modulus - (2.6.1, .2.6.6) '

The shear applicantmodulus at low hasstrain connitted levels. to provide field testing ng data the for verifyi 3.

Internally Generated Missiles - (3.5.1) damage to structure, systems and components are orotected against missiles inside containment.

ant" ese SSC (SSC) a 4

Mark II Containment (a)

Dynamic System Analysis Under Faulted Conditions . .

- (3 9 2

,3.9.5)

We require documentation of the applicant's reevaluation e reactor of th loss-of-goolant accident and safety shutdown the annulus pressurization effects. , including earthquak (b)

_Loadino Combinations, Desion Transients and Stress Limits - (3.9 We require documentation of the applicant's reevaluation of the safety-related systems and components based upon the load combinatio response us. combination methodology, and acceptance criteria y required b (c)

Pool Dynamic LOCA and SRV Loads - (6.2.1.1)

We need areas: additional information to complete our review owing in the foll a.

T-quencher air clearing load specification, and b.

5.

Pool temperature responses to safety relief valve transients .

Component Supports - (3.9.3)

The applicant has not submitted its resolution ofofobserved pump holddown beams.

the jet cracking 6.

.preservice and Inservice Testing of Pumos and Valves - 3.9.6)

The inservice applicanttesting of pumps has not andsubmitted valves. its proposed program eservice and for the pr

? '

7.

Seismic Qualification (a)

The applicant has not submitted the information describing the ' '

methods and criteria used to address the vibration fatigue cycle effects on the affected equipment due to the required loading conditions, has not submitted the results of the in-situ impedance tests and has not completed the qualification program (b)

~

We have not completed our seismic qualification review ew.

team rev 8.

~

_ Environmental Qualification - (3.11)

We are currently reviewing the applicant's NUREG-0588 na environm submittal, and we anticipate a site audit in December 1980.

9.

Balloonino and Ruoture - (4.2.3)

We have criteria not completed for cladding models. our generic review and implemented p ance new in the FSAR be supplemented and be perfomed of NUREG-0630. s with the m 10.

Combined Seismic and LOCA Loads on Fuel Assembly - (4.2.3) as reported acceptance criteria. in GE Report NEDE-21175-P os to sho 11.

Channel Box Deflection - (4.2.3)

The applicant has not referenced NE00-21354 perfoming these tests. committed to perfom the recommended tests or 12.

_MCPR - (4.4.1, 4.4.2,15.1)

The applicant must modify the operating limit MCPR based on the generator safety limit load rejection without bypass event satisfying the MCPR of 1.06.

13. ODYN Reanalysis The applicant rejection withoutmust analyze the following transients:

bypass (a)generatorload isolation valve closure,,an(b) turbine trip without bypass and main steam d c) for ASME Over steam isolation valve closure (with flux scram. pressure Protection - main 14 Control Rod System Modification - (4.6.2)

The applicant must show operability of the controlm rod in drive syste 15.

order to justify elimination of the return line to the reactor .

vessel Scram Discharoe Volume - (4.6.2) generic study on scram discharge volume rom thedesign.We

~3 -

16.

Safety / Relief Valves - (5.2.2, 6.3.2)

We require that the applicant perform tests to sho the safety relief valves is adequate to provide thw that flow through -

relief for alternate shutdown cooling. e necessary fluid must submit drawing's indicating modification ytovalves the CrosbIn addition and of thesethe results valves. of review performed by theonBWR tests Owner's G 17 M - (5.2.2, 7.2.3, 15.2.1) -

(a)

We require that the applicant agrees to implement pl ant modifications on a schedular basis in conformance resolution of ATWS. with the Co before necessary plant modifications are implementedIn

, we require further, the risk from ATWS events.some interim actions b to: ,

The applicant will be required (i)

Develop emergency procedures to train operators to recognize an ATWS event, including consideration of scram indicators, rod position indicators, flux monitors, vessel level and pressure indicators, relief valve and isolation valve i containment temperature, pressure,ndicators, and indica tors . and radiation (ii)

Train operators to take actions in the e e reactor by using the manual scram buttons followed by changing the rod scram feeder breakers switches on the reactor to the scram protection syst position, s em power distribution buses, opening the scram discharge vol ume drain valve, prompt actuation of the standby liquid control sy and prompt placement of the RHR in thespool em, cooling mo 18.

reduce the severity of the containment conditions .

Preservice and Inservice Insoection Procram - (5 2 4 ..

The applicant inservice ins has not submitted its revised program to 50.55 a(g)pection of Class 1, 2, and 3 components in accordanceof p 19.

Detection of Intersystem Leakace - (5.2.5)

The applicant must address leakage crite RCS/RHR, RCS/LPCS, RCS/LPCI interfaces a.ria for check valves at the RC and LPCI system is detected. nd show how leakage into the LPCS ,

20.

1 C_omoliance with Accendices G & H . . -, 5.3.3)

(5.3.1, 5 3 2

! ror Unit 1, additional information for exemption f 1

or paragraphs For Unit 2 insufficient information complete our review. are presented fIV e applicant.

or use to

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21. Flow Caoacity of Safety / Relief Valves in RHR (5.4.2) -

See item 16 above. .

22. Classification of RHR Isolation Valves - (5.4.2)

We require that the valves which serve to isolate the residual heat removal system from the reactor coolant system be classified category A/C in accordance with the provisions of Section XI of the ASME code, a

23. Steam Bypass of the Suooression Pool - (6.2.1.1)

The applicant approach to suppression pool bypass is not consistent with Branch Technical Position CSB 6-5. The applicant must conrnit to perfom a low power surveillance leakage test of, the containment at each refueling outage. Applicant plans to appeal the staff's position.

24 Containment Leakage Testing - (6.2.6)

With respect to' applying with Appendix J, the following commitment and additional information is required:

(a) Leak test of RHR shutdown return 1:olation valve be perfomed as Type C test utilizing air.

(b) Additional information is required for isolation valves in lines for LPCS injection HPCS injection, RHR/LPCI injection, and the RHR shutdown cooling return and the arrangements of the '

vacuum breaker valves.

ha

25. Assurance of Filled ECCS Line - (6.3.2)

The applicant must specify the test interval for the periodic venting of the ECCS injection lines to reduce the likelihood of air pocket presence.

26. Perodic Testing of Valves Used to Isolate Reactor Coolant System - (6.3.2)

See ite 14 above.

! 27. Post-LOCA ECCS Leakage - (6.3.4)

~~

We require the applicant to address the consequences and means of containing leakage from the first isolation valve outside the suppression pool.

28. Physical Separation and Electrical Isolation - (7.1.4, 7.2.3, 7.3.3, 7.6.3)

Based on information supplied by the applicant, there is still concern regarding

' c%11e's definition and/or treatment of associated circuits. We are reviewing the adequacy of the present design. For the instrument cabinets where non-Class i

IE wiring is bundled with Class IE wiring, we require that the applicant demonstrate (by test or analysis) that the Class IE circuits and equipment i are not degraded below an acceptance level by challenges by non-Class IE circuits.

[,

- _3_

e

29. Test Technioues - (7.1.4)

In order to perfom some surveillance testing, it in necessary for the -

applicant to pull fuses. We consider that this design does not satisfy the requirements of IEEE Std 279-1971 Paragraphs 4.11 and 4.20. We consider this item closed. The applicant will only utilize this method at refueling. The applicant must document its comitment.

30. Safety System Setooints - (7.1.4)

We have not completed our review of the Technical Specifications. We intend to review the infomation on setpoints in the Technical Specifications. If any concerns are noted, we will require some clarification.

31. Drawings - (7.1.4, 7.3.3, 7.6.3)

Based on our audit of certain drawings during our site visit, we consider this item closed except for confirming documentation (drawings) to be supplied on the low-low set relief logic and documentation of the function of this system.

32. RCICClassification-(7.4.3)

The acclicant has provided the infomation on their proposed design change for switchover. We consider this item closed except for their submittal of the final design.

33. Safety - Related Disolay - (7.5)

We are reviewing this item as a result of the applicant's inout.

34 Rod Block Monitor - (7.6.3)

We are reviewing this item. The apolicant has documented that the rod block monitor is not required for any of the analyses in Chapter 15.

35, t.ow or Degraded Grid Voltage - (8.2.2)

The applicant committed to implement the second level undervoltage protection.

We require the design implementation information prior to our aoproval. This information has not been provided.

35.

Shared Diesel - Generator (8.3.2) i (a) The applicant has infomally comitted to transferring automatically a number of vital support system loads for the shared diesel genera-tor. This has been found acceptable pending verification of the design implementation. Drawing showing the implementation have not bee provided.

(b) The applicant did not comit to transferrinc automatically the AC source of power to the 250 DC and 125 DC battery chargers. The applicant indicated that the battery had sufficient capacity for the time required to manually reconnect the AC power. We require manual procedures be provided for our review.

w.:---- - - , -,-- - - - ,---------e m e- -

37. Reactor Containment Electrical Penetrations - (8.4.1)

The reactor containment electrical penetrations do not conform to Regulatory Guide 1.63. The applicant has informed that we will not accept self-fusing characteristics of cable to provide protection against rupture of primary containment. Applicant plans to appeal the staff's position.

38. Adequacy of the 120-Volt Alternatino Current Reactor Protection System Power Supply - (8.4.7)

The applicant has committed to comply with the generic resolution. This was found acceptable pending verification of the design implementation.

Drawings showing design implementation have not been provided.

39. Thernal Overload Protection Bypass - (8.4.9)

The applicant has indicated that provisions for bypassing thermal overload protection would meet position C1 of Regulatory Guide 1.106. This was found acceptable pending documenting. The documentation has not been provided.

40. Physical Separation Between Class IE and Non-Class IE Cables A site visit by the staff (I&E and ICSB) identified a number of locations where inadequate separation exists between Class IE and non-Class IE cables.

Separation criteria in the FSAR specifies that non-Class IE cables are separated by an acceptable distance or barriers from Class IE cables.

41. Fire Protection - (9.5)

With respect to fire protection, the following additional information is required:

(a) For the alternate shutdown panel, it was determined that simultaneous loss of several circuits and/or cabinets would jeopardize safe plant shutdown. The applicant has not provided details of the design to alleviate this condition.

(b) The applicant agreed to evaluate the physical separation between cables for the control room redundant HVAC systems and identify areas where separation does not meet fire protection guidelines.

The results of this evaluation has not been provided.

(c) The applicant has not documented that all primary shutdown cables are not located in the same room with the alternate shutdown panel.

(d) Control cables for two series RHR valves are not separated by the i required distance at two locations. The applicant has stated though that these RHR valves are the only primary reactor boundary interface protected by two series motor operated valves. This needs to be docunented to resolve this issue.

(e) Separation of associated cables is a requirement resulting from Appendix R. Additional questions are being prepared to address

this item.

(f) Violation of containment isolation due t.u a design basis fire is a requirement resulting from Appendix R. Additional questions are being prepared to address this item.

42. Radiation Protection Manaoement (12.5)

(a) The Radiation Protection Manager should have a clear line of authority to the Plant Manager as indicated in NUREG-0731 and Regulatory Guide 8.8. Figure 1.7 of the Topical Report CE-1A, Rev.14. does not delineate this line of authority between the Rad / Chem Supervisor and the Plant Superintendent.

(b) It is our position that the Rad / Chem Supervisor meet the minimum requirement of Regulatory Guide 1.8 which references ANS/18.1.

Your Rad / Chem Supervisor resume indicates that he has a majority of his training and experience as a chemist and does not meet tne requirements of Regulatory Guide 1.8.

43. Industrial Security (13.4)

As a result of our site visit and our review, there are 32 items of concern.

44 Use of Nonreliable Ecuipment in Anticioated Ooerational Transients - (15.1)

(a) The applicant must analyze the generator load rejection without bypass

• and turbine trip without bypass transients without relying upon the use of the level 8 trip.

(b) In analyzing anticipated operational transients, the applicant took credit for equipment which has not been shown to be reliable. Our position is that this equipment be identified in the technical specifications with regard to availability, setpoints and surveillance testing. The applicant must submit its plan for implementing this requirement along with any system modification that may be required to fulfill the requirement.

45. Use of Non-Safety Grade Equioment in Shaft Seizure - Accident - (15.2)

The applicant included the use of non-safety grade equipment in his analyses for shaft seizure and shaft break accidents. We require that these accidents be reanalyzed without allowance for the use of non-safety grade equipment.

46. Technical Soecifications - (16)

We have not completed our review of Technical Specifications.

47. _uality Q Assurance - (17.0)

The applicant must address deficiencies of those systems, structures and components which should be under the control of the operational quality assurance program (Q-list).

48. Financial Qualifications - (20)

We have not completed our financial qualifications review.

. . . \

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ENCLOSURE 4 .

l

' LRG WORKING PAPER 12/2/80 Issue CPB-1 Loads Assessment of Fuel Assembly Components The proposed addition of Appendix A to SP.P 4.2 provides guidance for the analysis of Fuel Assembly Components and Acceptance Criteria for Fuel Assembly Response to externally applied forces. The applicants fuel assembly capability should be assessed accordingly. "

, Position Common

• General Electric has completed development of fuel assembly loads modeling and results acceptance criteria both deemed to be in accordance with the requirements of Appandix A to SRP 4.2. The LRG 1ead plant (LaSalle) has been evaluated accordingly with acceptable results. LRG plants will be evaluated on an appropriate schedule basis.

GE will issue a Licensing Topical Report revision early in 1991 to document the methodology and acceptance criteria utilized.

Reference LCSC ZPS SNPS EF-2 WNP-2 SSES Open - -

N/A - -

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8 Se

, A.

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LRG ORKING' PAPER -

12/2/80 Issue CPB-2 Fuel Claddino, Swellino & Ruoture Models The applicant has not provided info $ nation to assure that for the fuel cladding in .a 1.0CA "the degree of swelling and incidence of rupture are not underestimated" as required by Appendir. K of 10CFR50.45. The procedures proposed in NUREG-0530 introduce additional conservatism and should be utilized to perform supplemental calculations to the current ECCS analyses.

Position (Common)

The current analyses is FSAR Section 6.3.3 conservatively bounds the clad swelling and rupture model concerns of NUREG-0630. Additional analyses would be of little value to the ECCS performance evaluation -

review. In any case, since General Electric has not begun to develop .

model changes suggested by NUREG-0530 it would not be possible to perform such an analysis in the near future.

This position is supported by three General Electric letters discussing existing model suitability; a GE letter providing ccmments to NUREG-0630 and a letter from ACRS to the NRC of September 9,1980 stating "The ACRS recommends that implementation of the NUREG-0630 models and other significant changes in the evaluation models be held in abeyance until a thorough revision of the Appendix K reouirements can br; undertaken by

• the NRC staff." These references are listed below.

Reference LCSC 2PS SNPS EF-2 ^

WNP-2 SSES Open - - -

Open 10/8/80 231.5 letter

• Tedesco to Borgmann -

1) GE letter MFN-258-79 of November 2,1979 from R. H. Buchholz to -

Darrel G. Eisenhut, "0RNL Cladding, Swell and Rupture Data - BWR Evaluation."

2) GE letter MFN-278-79 of November ifi,19791 rom R. H. Buchhofz to Darrel G. Eisenhut, "GE Ciadding Hoop Stress at Perforation."

3) GE letter MFN-055-80 of Harch 24,,,1980 from G. G. Sherwood to Richard P. Denise.

4) GE letter MFN-294-79 of December 7,1979 from R. H. Buchholz to' Richard P. Denise, " Comments on thg, draft report ' Cladding, SwellinD and Rupture Models for LOCA Analyses,' HUREG-0530 dated November e, 1979."

5)

ACRS letter of September 9,1980 from Milton S. Plesset to William J.

Dircks, " Cladding, Swelling and Rupture Models for LOCA Analysis -

NUREG-0630."

LRG WORVdNG PAPER 12/2/80 .

Issue CPB-3 Channel Box Design -

~

'The applicant has not referenced General Electric Licensing Topical Report NEDE-21354-P which describes the fuel channel design. Of specific

- concern, is the commitment to control rod drivaline friction testing recommended,in Section 4.4.2 of HEDE-21354-P.

• s ,

~

[ Position (Common) .

The LRG inembers agreed to reference NEDE-21354-P in an appropriate FSAR section. This Licensing Topical Report is applicable to the fuel channel design being supplied to all LRG, plants.

All LGR plants are now designed in accordance with iiE0E-21354-P.

Operating plant experience ar.d inspection has verified the adequacy of this design. Therefore, the control rod driveline friction screening-type testing suggested in Section 4.4.2 is not deemed necessary as a routine test for detecting the onset of control rod interference. -

The periodic technical specification requirements for scram time testing and rod notch testing would provide an indication of a pending drive line friction concern. Should either of these tests .

suggest a drive friction problem, the pressure test described in !!EDE-21354-P (4.4.2) can be used as an aid in isolating the cause of the drive malfunction.

Reference

• LCSC ZPS SNPS EF-2 WilP-2 _SSES . I.

Open - - - Open -

0211.137 ,

.. g g$

j 1

LRG HORKING PAPER

~-

12/2/80 I

,' :n ,

Issue CPB-4 Water Side Corrosion .

The applicant has not addressed the potential for fuel corrosion failure s'imilar to that which occurred at the Vermont Yankee Plant.

Position Unique As indicated in the General Electric presentation given to the NRC in December 1979, the failures appeared to be associated with a metallic incursion in the feedwater. This event has occurred only once in the BWR operating history and is unlikely to occur.

1. Plants with non-copper bearing main condensor tubes are not expected to experience the clad perfarations of this concern. La Salle, Shoreham

... and Susquehanna do not have copper bearing condensors.

2. Plants with adequately designed filters demineralizers are not expectId to experience the clad perforations of this concern even with copper bearing condensor. tubes. Zimner, Fermi 2 and .flanford 2 are designed accordingly.

Reference ,

LCSC 2PS SNPS EF-2 WNP-2 SSES Open - - - - -

6 9

9 9

t 9

1

_..-n___,.,we. - , . . - . _ . - , . _ - _ _

cp...

- .. n - n.,- ..

g f y

& . .. .- . . ~ ;uq DEC 5 1980 MEETING

SUMMARY

DIST_RIBUTION M G. Lear NRC POR V. Noonan Local PDR S. Pawlicki l TIC /NSIC/ Tera V. Benaroya NRR Reading 2. Rosztoczy LB#1 Reading W. Haass H. Denton D. Muller E. Case R. Ballard D. Eisenhut ei . Regan R. Purple D. Ross B. J. Youngblood P. Check A. Schwencer R. Satterfield F. Miraglia 0. Parr J. Miller F. Rosa G. Lainas W. Butler R. Vollmer W. Kreger J. P. Knight R. Houston R. Bosnak T. Murphy F. Schauer L. Rubenstein R. E. Jackson T. Speis Project Manager J. N. Wilson W. Johnston Attorney, OELD J. Stolz M. Rushbrook S. Hanauer OIE (3) W. Gammill ACRS (16) T Murley R. Tedesco F. Schroeder N. Hughes D. Skovholt M. Ernst NRC Particioants: R. Baer J. Wilson, A. Bournia, B. Bosnak, C. Berlinger F. Eltawila, W. Hodges, J. Mazetis, K. Kniel R. Tedesco, B. Morris, J. Mauck, G. Knighton G. G. Rhoads R. Stark, L. Kintner, A. Thadani I . Pel tier, G. Thomas, J. Knox, D. Tondi T. Collins J, Kramer D, Vassallo P. Collins D. Ziemann bec: Applicant & Service List l

- c

• [yte R80 .',o UNITED STATES g

g NUCLEAR REGULATORY COMMISSION

[

j WASHINGTON D. C. 20555

%*****/ -

DEC 5 1980 DOCKET NOS. 50-358 50-322 C50%

50-341 50-373 50-387 APPLICANTS: Cincinnati Gas & Electric Company Long Island Lighting Company Commonwealth Edison Company Detroit Edison Company Pennsylvania Power & Light Company Washington Public Power Supply System FACILITIES: Zimmer 1, Shoreham 1, LaSalle 1, Fermi 2, Susquehanna 1, WNP-2

SUMMARY

OF MEETINGS HELD WITH BWR-LRG SEE Tb: 30 -S5 'if ,b wrt '

A series of meetings were held in Bethesda, Maryland with the above named members of the Boiling Water Reactor-Licensing Review Group (BWR-LRG). The BWR-LRG was formed on May 1, 1980 by a group of utilities with BWR's that are nearing completion of their review for an operating license. The goal of the group is to identify open issues from their licensing reviews that are generic to the group, form a consensus position on the issues, resolve the issue with the NRC, and apply that resolution to all 6 plants. This will expedite the licensing reviews for these plants and minimize the use of staff resources.

The BWR-LRG has designated LaSalle as the lead plant. A list of the meetings held with the BWR-LRG is presented in Enclosure 1.

The BWR-LRG met with the staff of the Office of Nuclear Reactor Regulation (NRR) on May 14, 1980 to discuss the organization, their goals, and how the group will function. The summary of this meeting was issued on June 17, 1980.

The BWR-LRG met internally on a number of occasions to develop consensus posi-tions for the issues which were open on the LaSalle docket. These positions were presented to the responsible technical review branches (identified in Enclosure 1) on June 13, 1980 and July 24, 1980. The consensus positions for MEB and MTEB issues were delivered.to the staff on August 19, 1980. The consensus positions are provided in Enclosure 2.

The other meetings identified in Enclosure 1 were held to discuss the consen-sus positions with the responsible technical branch. The primary goal of these meetings was to determine if the consensus positions developed by the LRG are acceptable for resolution of the open issues on the LaSalle docket.

There was limited discussion of these issues relative to the other five BWR plants. If an issue was resolvad, then that position is documented in this meeting summary (refer to the resolutions provided in Enclosure 3). In addi-tion, the position may also be discussed in the Safety Evaluation Report fo'r i LaSalle. The LaSalle Final Safety Analysis Report (FSAR) will be revised to incorporate the resolved positions. If any of the other BWR plants choose to i

{C ! $,5b lN

r .

2 DEC 5 1980 adopt that position to resolve'their open issues, then they must document that position in their FSAR. Before the NRR staff accepts the LaSalle resolution on the other BWR plants, the staff will perform an additional review to deter-mine if the position is applicable and/or properly irr.plemented on that particular BWR plant. This may involve additional questions for the other BWR plants.

On July 22, 1980, NRR Hanagement held a meeting with the BWR-LRG to discuss the new licensing requirements that were developed as a result of the accidernt at Three Mile Island, Unit 2. The requirements in NUREG-0694 were discussed and the LRG was told that a report was being prepared to clarify these require-ments. During the meeting, NRR Management agreed that blanket questions would not be issued to insure that all the BWR plants participating in the LRG received the same questions. However, questions on significant issues will be asked on a case-by-case basis.

e x 4 ,

Je y N. Wilson C Manager for BWR-LRG

r Mr. M. S. Pollock Vice President- Nuclear Long Island Lighting Ccmpany 175 East Old Country Road Hicksville, New York 11801 ces:

Howard L. Blau, Esq. Honorable Peter Cohalan Blau and Cohn, P.C. Suffolk County Executive 217 Newbridge Read County Executive / Legislative Building Hicksville, New York 11801 Veteran's Memorial Highway Hauppauge, New York 11788 Jeffrey Cohen, Esq.

Deputy Commissioner and Counsel David Gilmartin, Esq.

New York State Energy Office Suffolk County Attorney Agency Building 2 County Executive / Legislative Building Empire State Plaza Veteran's Memorial Highway Albany, New York 12223 Hauppauge. New York 11788 Energy Research Group, Inc. MHB Technical Associates 400-1 Totten Pond Road 1723 Hamilton Avenue - Suite K Waltham, Massachusetts 02154 ,

San Jose, California 95125 Irving Like, Esq. Stephen Latham, Esq.

Reilly, Like and Schnieder Twomey, Latham & Schmitt 200 West Main Street P. O. Box 398 Babylon, New York 11702 33 West Second Street Riverhead, New York 11901 J. P. Novarro Project Manager Joel Blau, Esquire Shoreham Nuclear Power Station New York Public Service Commission -

P. O. Box 618 The Governor Nelson A. Rockefeller Bldg.

Wading River, New York 11792 Empire State Plaza Albany, New York 12223 W. Taylor Reveley, III, Esq.

Hunton & Williams Ezra I. Bialik P. O. Box 1535 Assistant Attorney General Richmond, Virginia 23212 Environmental Protection Bureau New York State Department of Law Ralph Shapiro, Esq. 2 World Trade Center Camer & Shapiro New York, New York 10047

• 9 East 40th Street .

New York, New York 10016 Edward J. Walsh, Esq.

General Attorney Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 Resident Inspector /Shoreham NPS c/o U.S. Nuclear Regulatory Commission P. O. Box B Rocky Point, New York 11778 l

I l

r Mr. J. S. Abel Director of Nuclear Licensing Commonwealth Edison Company .s Post Office Box 767 Chicago, Illinois 60690 cc: Richard E. Powell, Esq.

Isham, Lincoln & Beale One First National Plaza 2400 Chicago, Illinois 60670 Dean Hansell, Esquire Assistant Attorney General 188 West Randolph Street Suite 231S Chicago, Illinois 60601 Mr. Roger Walker, Resident Inspector U. S. Nuclear Regulatory Conmission Post Office Box 737 Streator, Illinois 61364 e

i 9

i

(

Mr. Norman W. Curtis  ?

Vice President - Engineering and Construction Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 cc: Mr. Earle M. Mead Mr. E.B. Poser Project Engineering Manager Project Engineer Pennsylvania Power & Light Company Bechtel Power Corporation 2 North Ninth Street P. O. Box 3965 Allentown, Pennsylvania 18101 San Francisco, California 94119 Jay Silberg, Esq. Matias F. Travieso-Diaz, Esq.

Shaw, Pittman, Potts & Shaw, Pittman, Potts &

Trowbridge Trowbridge 1800 M Street, N. W. 1800 M Street, N. W.

Washington, D. C. 20036 Washington, D. C. 20036 Mr. William E. Barberich, Dr. Judith H. Johnsrud ,

Nuclear Licensing Group Supervisor Co-Di rector Pennsylvania Power & Light Company Environmental Coalition on 2 North Ninth Street Nuclear Power Allentown, Pennsylvania 18101 433 Orlando Avenue State College, Pa 16801 Edward M. Nagel, Esquire General Counsel and Secretary Mr. Thomas M. Gerusky, Director Pennsylvania Power & Light Company Bureau of Radiation Protection 2 North Ninth Street Department of Environmental Allentown, Pennsylvania 18101 Resources Comonwealth of Pennsylvania Bryan Snapp, Esq. P. O. Box 2063 Pennsylvania Power & Light Company Harrisburg, Pa 17120 2 North Ninth Street Allentown, Pennsylvania 18101 Ms. Colleen Marsh Box 538A, RD#4 Robert M. Gallo Mountain Top, PA 18707 Resident Inspector P. O. Box 52 Mrs. Irene Lemanowicz, Chairperson Shickshinny, Pennsylvania 18655 The Citizens Against Nuclear Danagers John L.. Anderson P. O. Box 377 Oak Ridge National Laboratory RD#1 Union Carbide Corporation Berwick, PA 18503 Bldg. 3500, P. O. Box X Oak Ridge, Tennessee 37830 Mr. J.W. Millard ProjectMAnager Gerald R. Schultz, Esq. Mail Code 394 Susquehanna Environmental Advocates General Electric Company P. O. Box 1560 175 Curtner Avenue Wikes-Barre, Pennsylvania 18703 San Jose, California 95125

[5 Mr. R. L. Ferguson Managing Director Washington Public Power Supply System

• P. O, Box 968 3000 Ceorge Washington Way Richland,Washirgton 99352 ces:

Joseph B. Knotts, Jr., Esq.

Debevoise & Libernan 1200 Seventeenth Street, N. W.

Washington, D. C. 20336 Richard Q. Quigley, Esq.

Washington Public Power Supply System P. O. Box 968 Richland, Washington 99352 Nicholas Lewis, Chairman Energy Facility Site Evaluation Council 820 East Fifth Avenue Olympia, Washington 98504 Mr. O. K. Earle Licensing Engineer P. O. Box 968 Richland, Washington 99352 Mr. Albert D. Toth Resident Inspector /WPPSS-2 NPS c/o U. S. Nuclear Regulatory Commission P. O. Box 69 Richland, Washington 99352 6

l

[

e

Mr. Earl A. Borgmann Vice President - Engirieering Cincinnati Gas & Electric Company P'. O. Box 960 Cincinnati, Ohio 45201 cc: Troy B. Conner, Jr., Esq. Leah S. Kosik, Esq.

Conner, Moore & Corber 3454 Cornell Place 1747 Pennsylvania Avenue, N.W. Cincinnati, Ohio 45220 Washington, D.C. 20006 W. Peter heile Eso.

Mr. William J. Moran Assistant City Colicitor General Counsel Room 214 City Hall Cincinnati Gas & Electric Company Cincinnati, Ohio 15220 P. O. Box 960 Cincinnati, Ohio 45201 John D. Wo11ver, Esq.

Clermont County Comunity Council Mr. William G. Porter, Jr. Box 181 Porter, Stanley, Arthur Batavia, Ohio 45103 and Platt 37 West Broad Street Mrs. Mary Reder Columbus, Ohio 43215 Box 270, Rt. 2 Mr. James D. Flynn, Manager Licensing Environmental Affairs Andrew B. Dennison, Esq.

Cincinnati Gas & Electric Company 200 Main Street P. O. Box 960 Batavia. Ohio 45103 Cincinnati, Ohio 45201 ,

Robert A. Jones, Esq.

David Martin, Esq. Prosecuting Attorney of Clemont Office of the Attorney General County, Ohio 209 St. Clair Street 154 Main Street First Floor Batavia Ohio 45103 ,

Frankfort, Kentucky 40601 Resident Inspector /Zimmer Dr. Frank F. Hooper RFD 1. P. O. Box 2021 School of Natural Resources U. S. Route $2 University of Michigan Moscow Ohio 45153 Ann Arbor, Michigan 4B109 Charles Bechhoefer, Esq., Chaiman Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Mr. Glenn 0. Bright Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Comission Washington, D.C. 20555

Dr. Wayne H. Jens -

Assistant Vice President Engineering & Construction Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 cc: Eugene B. Thomas, Jr., Esq. David E. Howell, Esq.

LeBoeuf, Lamb, Leiby & MacRae 21916 John R 1333 New Hampshire Avenue, N. W. Hazel Park, Michigan 48030 Washington, D. C. 20036 Peter A. Marquardt, Esq.

Co-Counsel The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Mr. William J. Fahrner Project Manager - Fermi 2 The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Mr. Larry E. Schuerman Licensing Engineer - Fermi 2 Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Charles Bechhoefer, Esq., Chairman Atomic Cafety & Licensing Board Panel U. $, Nuclear Regulatory Commission

• Washington, D. C. 20555 Dr. David R. Schink Dep.artment of Oceanography Texas A & M University College Station. Texas 77840 Mr. Frederick J. Shon Atomic Safety & Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i

i e

t ENCLOSURE 1 ORGANIZATION DATE ATTENDEES -PURPOSE NRR 5-14-80 9 am 6-17-80 Summary Introduction to BWR-LRG RSB/ICSB 6-13-80 6-19-80 Summary To present consensus positions RSB 7-2-80 9 am Enclosure 4 To dicusss consensus positions RSB 7-9-80 10 am Enclosure 5 To discuss consensus positions NRR 7-22-80 9 am Enclosure 6 To discuss TMI issues PSB/CSB/EQB 7-24-80 1 pm Enclosure 7 To present consensus positions ICSB 8-19-80 9 am Enclosure 8 To discuss consensus positions PSB 8-21-80 8:30 am Enclosure 9 To discuss consensus positions CSE 8-21-80 1:30 pm Enclosure 10 To discuss consensus positions MEB 8-28-80 9 am Enclosure 11 To discuss consensus positions MTEB 8-28-80 1 pm Enclosure 12 To discuss consensus positions

DEC 5 1980 MEETING

SUMMARY

DISTRIBUTION M G. Lear NRC PDR V. Noonan Local POR S. Pawlicki TIC /NSIC/ Tera V. Benaroya NRR Reading Z. Rosztoczy LB#1 Reading W. Haass H. Denton D. Muller E. Case R. Ballard D. Eisenhut W. Regan R. Purple D. Ross B. J. Youngblood P. Check A. Schwencer R. Satterfield F. Miraglia 0. Parr J. Miller F. Rosa G. Lainas W. Butler R. Vollmer W. Kreger J. P. Knight R. Houston R. Bosnak T. Murphy F. Schauer L. Rubenstein R. E. Jackson T. Speis Project Manager J. N. Wilson W. Johnston Attorney, OELD J. Stolz M. Rushbrook S. Hanauer OIE (3) W. Gammill ACRS (16) T, Murley R. Tedesco F. Schroeder N. Hughes D. Skovholt M. Ernst R. Baer C. Berlinger K. Kniel G. Knighton A. Thadani D. Tondi J, Kramer D, Vassallo P, Collins D, Ziemann bec: Applicant & Service List e