ML20212E597

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Summary of 861201 Meeting W/Util,Ge & AIF in Bethesda,Md Re Corrosion of Outer Surface of Drywell Shell.Licensee Provided Description of Drywell Re Matls of Const,Const Sequence & cross-section of Sand Cavity.Addl Info Encl
ML20212E597
Person / Time
Site: Oyster Creek
Issue date: 12/12/1986
From: Donohew J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8701050370
Download: ML20212E597 (37)
v • d • e


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  1. puso 'c, UNITED STATES

!' ., j NUCLEAR REGULATORY COMMISSION g a WASHINGTON, D. C. 20665 December 12, 1986 I;ocket No. 50-219 i

LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Statior SUEJECT: DECEMBER 1, 1986, MEETING WITH GPU NUCLEAR CORPORATION (GPUN)

TO DISCUSS CORROSION OF THE OUTER SURFACE 0F THE DRYWELL SHELL On Monday, December 1, 1986, a meeting was held at NRC, Bethesda, Maryland with GPUN, the licensee, on the potentially severe corrosion of th'e outer drywell shell, at an elevation , lust below the downcomers. This meetinc followed the information given by the licensee to the NRC Oyster Creek resident inspectors that evidence existed of significant wastage of the outer drywell shell. Figures 1 and 2 in Attachment 2 show a vertical cross section of the entire drywell shell and of the region just below the down-comers, including a drainage channel and the send filled cavity, respectively.

The corrosion was measured in the outer shell exposed to this sand filled cavity.

Attachment 1 is the list of the participants that. attended the meeting. ,

Attachment 2 contains two figures of the Oyster Creek.drywell and the meeting

,n notices issued for this meeting. Attachment 3 contains the handout from the licensee for its presentation. The following is a' summary of the significant items discussed and the actions, if any, taken or proposed.

This meeting was originally arranged to discuss the licensee's justification to restart Oyster Creek from the current Cycle 11 Refueling (Cycle 11R)

L i outage with the then measured shell wastage. The meeting was requested by

j. the staff ir. the November 24, 1986, telephone discussion with the licensee on the measured shell thickness data. The intent of this meeting was changed

, to that of an information exchange after additional measurements by the licensee, later that week, showed potential wastage down to 0.383 inch.

The ifcensee in its handout provided a description of the drywell ' including the materials of construction, construction sequence, partial cross section of the sand cavity and sources of water for leakage outside the drywell shell.

The licensee investigated the thickness of the dr

measured leakage rates (drops / minute up to from 2 gpm)ywell 2 drywellshell after having penetration i

drains and 3 of the drainage channels from the sand cavity. The sand cavity extends around the circumference of the drywell shell at an elevation of the drywell just below the downcomers. The sand in the cavity provides a transition region between the lower, fixed or pinned base of the I

B701050370 861212 PDR ADOCK 05000219 P PDR

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, shell which is in concrete and the upper, unrestrained shell. .The upper shell above the floor is not attached to the outer biolooical concrete shield. The l drywell shell is a free standing, unrestrained, except for the base, steel i pressure vessel. The sand reduces the stresses in the shell in the transition

! region.

-l There is a gap between the shell and'its attached insulation and the outer biologically concrete shield. The insulation is described in the enclosed handout. This gap extends down, from the top of the she11, past the dowr-comers, to the sand cavity and its drainage channels. There are 5 channels,

spaced at every other downcomer location. There are 10 downcomers. These channels allow drainage of water from behind the drywell shell through the 1i sand cavity to the torus room. This drainage allows the sand in the cavity to '

l be kept damp from such water and from the natural circulation of air into the Reacter Puilding. This air, which reaches temperatures in excess of 140*F j around the shell durino power operation, could be the phenomena which draws

cooler anc damoer air from the torus room in the bottom of the Reactor Puilding.

The damo sand in contact with the shell in the sand cavity would then provide water for corrosion of the shell.

The measured non-destructive examination (NDE) data is given in Attachment

, 3. This was taken by the licensee using an ultrasonic testing (UT1 device i which n.easures the shell thickness by sound waves being passed through the J

shell and reflected back from the outer shell surface.

The section on NDE results in Attachment 3 shows the plan view of the floor '

of the drywell. This shows the 10 downcomers and the 20 " Pays" or plates j around the circunference of the drywell at the elevation of the downcomers.

The NDE data is related to the 10 bays in front of the downcomers. A figure

of the entire drywell also shows the thickness of the shell at different elevations. The shell plates in the area of the sand cavity are nominally-
  • i 1.154 inches thick. The NDE measured thicknesses of the shell are shown as t function of the circumference around the base of the shell for the 10 bays

[, '

in front of the downcomers. The measurements in the figure are only for the shell between the floor elevation and the downcomer elevation. The lines

)

4 connecting the dotes or data points, representing different individual HDE

measurements, have no physical meaning. i t? -

The licensee discussed its isleas for the apparent corrosion of the outer surface of the shell. The licensee provided in its handout the outer shell environmental conditions including corrosion protection, its corrosion evalua-

tion of these conditions and its corrosion rate estimates. The estimated shell corrosion rates for 17 years since the operating license for Oyster , . .

Creek are shown to be typical of corrosion rates for aqueous environments

at neutral pH, '

t ,

The licensee ended it presentation with its current plan to develop a repair '

l program for the drywell shell. In the rest of this week of December 1, 1986,

it plans to take additional NDE measurements of and to remove a number of l t plugs from the drywell shell over the sand cavity. This vill include plugs  !

[ from the bays with the deepest indicated wastage. Sand will be removed from 1 the plugs for chemical analysis, the outer shell will be examined through i the plug and ground potential measurements for possible cathodic corrosion -

will be made.

1

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The licensee will submit to the staff the _results of its investigation of the drywell shell, its repair program for the shell including repair of the plugs removed from the shell and its justification for the restart of Oyster Creek from the current cycle 11R outage. The date for this submittal will be determined after the additional measurements are completed and analyzed.

The licensee stated that as soon as it completes its investigation and its repair and restart program it will have another meeting with the staff.

This would be arranged with the staff through the NRC Project Manager for Oyster Creek. *

\

Jack N. Donohe , Jr., Project Manager

< BWR Project Directorate #1 Division of BWR Licensing Attachments:

1. List of Attendees
2. Drywell Figures and Meeting Notices
3. Licensee's Handout for Meeting DISTRIBUTION:

Docket File NRC PDP Local '

See Attached List

  • The second meeting on this subject was held on Thursday, December 11, 1986.

DBL:BWD1 DBL DBL:BWD1 CJamerso b ' : ac 'JZwolinski 12/II/86 JDj/ 12/11,/86 Iq 86

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Oyster Creek Nuclear Genera +.ing Statior, rC:

Fr. Ernest L. R1ake,.1r. Desident Inspector Shaw, Pittman, Potts and Trowbridge c/o 11.5. P'DC 2300 N Street, NY Post Offica Box 445 Washington, D.C. ?0037 Forked D.iver, New .lersey 08731 J.P. Libeman, Escuire Comissioner Bishop, Liberman, Cook, et al. New Jersov nepar +nent of Eneray 1155 Avenue of the Americes 101 Conrerce Stree+

Few York, New York 10036 Newark, New Jersey 0710?

Pr. David P. Scott, Actina Chie' Recional Administrator, Pegion i Bureau of Nuclear Engineerino U.S. Nuclear Regulatory Cortnission Department of Environmental Prctectior 631 Park Avenue CN 411 Ving of Prussia, Pennsylvania 19406 Trenton, New Jersey 08675 BWP Licensing Manager Mr. P. P. Fiedler GPl! Nuclear Corporation Vice President & Director 1 Upper Pond Road Oyster Creek Nuclear Generating Parsippany, New Jersey 07054 Station P. O. Box 388 Deputy Attorney General Forked River, New Jersey 08731

, State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, l'ew .lersey 08625 ,

i Hryor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager  ;

Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.

P. O. Box 388 Forked River, New Jersey 08731 s

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ATTACWENT 1 MEETING l!!TH GPU NUCLEAR CORPOPATION (GPUN) ,

TO DISCUSS ,

DRYWELL SHELL CORROSION  ;

DECEMBER 1, 1086 NAME ORGANIZATION J. Dorohew NRC/NRR/ DBL /Bl!PI J. A. Zwolinski NRC/NRR/ DBL /BWD1 S. Giacabbe GPUN G. Capodanno GPUN D. K. Croneberger GPUN R. F. llilson GPUN A. H. Rone GPUN P. F. Czaya GPUN i

M. W. Laggart GPUN F. B. Litton BWR, EB R. Greiner GE L. S. Gifford GE -

W. S. Hazelton NRC/NRR/ DBL /BWEB W. J. Collins IE/NPC '

R. Huston AIF '

J. F. Costello NRC ,

, B. Turovlin NRC/EB/BWR F. Vitt NRC/NRR/ DBL /PSB R. A. Gilbert NRC/NRP/BWD#2/ DBL l D. Wagner NRC  :

P. Cortland NRC/01E T. S. Rotella NRC/NRR/ DBL /BWDfl ,

J. Stang NRC/NRR/ DBL /BWDf1 R. Hermann NRC/NRR/ DBL /EB I C. P. Tan NRC/NRR/ DBL /EB A. R. Blough NRC/RI/DRP/PB#1

V. Manaly NRC/RI/DRS/EB H. F. Conrad NRC/NRR/EP G. G. Gears NRC/NRR/ DBL G. Lainas ' NRC/NRR/ DBL /AD B. D. Liaw NRC/NRR/ DBL /EB R. Starostecki NRC R. Bernero NRC/NRR/ DBL D. L. Hill NMPC Licensing ,

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i ATTACHMENT 2 Two drywell figures Two meeting notices i

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I. IhTRODUCTION t

II. DRWELLDESCRIPIION III. NDERESULIS IV. POIENIIALCORR0SIONMECHANISMS V. CURREhTACIIONPIM VI. CONCLUSION r

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DRYWELL MIERIALS t ANLARSPACE SAND ELEVAIION: 8'11" - 12'3" FIBERGLASS ELEVATION: 12'3-23'-6" FIREBAR-D ELEVATION: 23'6"-94' MIERIALCRITERIA(PARIIALLISI)

' WOULD ADHERE IIGHILY 10 A CURVED, PAINTED SIEEL SURFACE IN FLA VERIICLEANDOVERHEADPOSITIONS ,

' WOULD REM IN DIMENTIONALLY SIABLE WITHOUT SIGNIFICANI FLA POWDERING

' WOULD BE UNAFFECTED BY LONG IERM EXPOSRE 10 RADIAIION AN a

~

DRWELL MATERIALS (CONT'D)

FIRERBAR-D: F0AMEDASBESTOSFIBERMAGNESITECEY.NI MANUFACHRER: ALLPURPOSEFIREPR0OFINGCORPORAIION ye^M M0DIFIED BY CERIIFIED INDUS H IAL PRODUCIS INO 00MPOSIIION: ASBESIOSFIBERS (75%)

MAGNESITE (Mg0)

MAGNESIUMSULFAIE AEROSOLPK APPLICATION: SPRAYAPPLIED @

1st00AT-1/2"(SIANDARDDENSITY) g .

2nd00AT-1"(REDUCEDDENSI 3rd00AT-1"(REDUCEDDENSITY)

BONDBREAKER: GRIFF0 LYN 4MILCLEARPOLYEIHYLENESBEET REINFORCEDWITHGIASSFIBERS-SEAMS SEALEDWITHFABRIOTAPE 5

I

e DRWELLSIEEL SPECIFICATION: ASIM:A-212-61TGrB FIREB0XFINEGPAIN-NORMALIZED CHEMISTRY: 0 .23 (IYPICAL) Mn-1.06 P .010 S .023 i Si .21 SIRENGTH: IENSILE-75,000 PSI (IYPICAL) YIELD -50,000 PSI ELONG -35%

NOTE: MATERIAL h'AS IMPACI TESIED e

1 9

f 4

- . . ----.--.,-,,------------------------------------...-------.n--.-----.r

~

DRMLLMAIERIALS(CONI'D)

SAND: CONCREIEAGGREGAIEPERASIM:033 COMPOSIIION: FIE AGGREGATE CONSISTING 0F NATURAL SAND, KMFACTUR SAND OR A COMBINATION HERE0F.

FIBERGLASS: FIBERGLASSSFVAPORSEALDUCIINSULATION MNFACERER: 0 WENS-CORNING i COMPOSIIION: FIBERGLASS SIRANDS EMBEDDED IN PHEN 0L FORMALDEHEE

. RESIN. BOARDS ARE C0VERED WIH A FACIORY APPLIED IMINATED ASPHALI KRAFI PAPER EXIERIOR FACE APPLICAIION: FIBERGLASS BOARDS WERE ATIACHED 10 HE VESSEL WIIH MASII0 AND INSULATION PINS. JOINTS WERE SEALED WITH GLASS FABRIO REINFORCED MASTIC t y

9

.i

4 e ** 0 NDERESULTS a

9 e

b a

E

'8 4

5 e

5 i

[

. *e .

N i g o.

l t

10 ll 12 II

(

9 - e BAY BA'T ll BAY 1 x 9 13 15 BAY BAY '

90 6  ;

1 l6 270' p

5 i[

^

BAY BAY 17 3 89 BAT 4 ' i- 18 k

3 ,a  ;

e f a zo

~

/

PLAM VIEW torus & DRTWELL '

l 1

0YSTER CREEIC DRWEll UI EXAMINATION ELEVATION BAY RESULTS 51' 17 & 19 N0AN0MALOUSREADINGS 51' 13 N0 ANA M. 0US READINGS 51' 7 N0 ANA E, 00S READINGS 11'-3"! ALLBAYS ANA M. OUS READINGS I

  • e t

I 4

4 l

_e w h h 9 l

.s? ,

j E

$c 4 og i

.L -

e- a, 14 Cc e

, e 5i

$" h

~

il -

u!a o jj 4 y]. a 9,43 m

L .@

\ "

F .

H I 1 f~ (l '

w II

% g/B <

Q B ri.l< @wfe 4 @ -

l N O; . 's ,' +_ . ' (-- ) -

(  ;

L:

i s= :- *l g

,_ ~

-g2%

.9 g

EN r

= = $ * # a 4-(+-

r l U ,*

x Jfh C - -

c ld hj e o, -

e 3 22 n j{-

ttf['

. s W.'N

,E 3 y l

\

% 5d g(k -

~

/ p*

cp kg i

n .s j,p. ./ g,~

(1 y4 U :o = h!; .__f, k

]\

[

'a p  ;

---___ _ _ ~ ~ ~

1 i -

1 1

0.C. DRYWELL UALL THICKNESS BY U.T.

2.0 _l l l l l l l l l l l l l l l l l l l l l_ 1 1*9 -

1.8

+++ = THICKNESS AT EL. 11 FT.-3 IN.2 -

U -

A 1.7 -

t .6 -

i 1, 1.

1.5 -

y -

l 1.4 -

H -

I 1.3 -

K 1.2 __ __ p

_ . . . . g. .

. 1.154 Z N 1.1 -

E ..

t.0 I, .

S i.

,I 7 S 0.9 -

0.8 -

I 0.7 N -

C 0.6

,._ H 0.5 -

- o E -

s 0 .4

0.3 -1~

3 5 7 9 11 13 15 17 19 -

^ ^ ^ ^ ^ ^ ^ ~

^ ^ ^

0.2 -

BAY N0. -

0.1 -

1 I I I I I I I I I I I I I I I I I I I l-0.0 0.0 353.3 706.6 1060.0 1413.3 1766.6 POSITION FROM LEFT EDGE OF BAY N0 1 , INCHES

~

ENVIR0h M AL CONDITIONS

1. ANLARSPACE: ' RED LEAD PAINI ON SIEEL PROVIDES SOE PROIECTION

' FIREBAR D MAY ABS 0RB SOME WATER BUTSHOULDDRYDURINGOPERATION TEMPERATURES x 140'F

.

  • FIBERGLASS BOARDS - PHEN 0L F0LEDABYDE GENERALLY RESISI N 10 WATER ABS 0RBIION SHOULD DRY OUT DURING OPERATION IF EITED 4

~

. . . . l EhTIR0hBTALCONDITIONS II. SANDBED: ' COULD BEC0E SATURATED DURING REFUELING.

WAIER LINE N EXISI IF DRAINAGE IS SLOW

'CANREMAINM0lSIDURINGOPERATION DUE10COOLERIEMPERATUREOFBEDAND HIGHHUMIDITYINIORUSR00M.

M IDITY IN A M LAR SPACE N CONDENSE ONCONCREIEANDFLOWINIOSANDBED.

' COULD NE BEEN EIIED DURING CONSTRUCIIONANDCONIAMINAIEDWITH MAGNESITEANDMAGNESIUMSULFATE

' E ER ANALYZED FROM SAND BED DRAINS.IN 1983 ONLY. CONFI E D PRESENCE OF CESIUM-NOCONIAMINANIANALYSIS

! PERF0MD.

f I

li

1 CORR 0SIONEVALUATION CORR 0SION: A. GENERAL CORR 0SION - POSSIBLE

' RUSTING - WATER /0HGEN

'LOWpH-WATER /0HGEN/00HAMINANI B. PIIIING - POSSIBLE

'DIFFERENIIALAERATION

'01,S-00NIAMINATION

0. SIRESS CORROSION - NOT PROBABLE

'LOWYIELDSIRENGIHMAIERIAL

'LOWIEMPERATURES

  • LOWSTRESS

'PROBABILI170FSCOFMIRONET-LOW ,

! ' PROBABILI1T FOR HYDR 0 GEN FMRIITLEMENI-LOW e

3 j

,i

~

i CORR 0SIONEVALUATION D. GALVANIC CORR 0SION SIRAYCURRENIS-N0BURIEDDCLINES SMALLAN0DE-LARGECATHODE 0XYGENDEPLETION .

SAND 00NIACIAREAVARIAIIONS E. MICR0 BIAL INDUCED CORROSION STAGNANTM0lSIAREA i NUIRIENTSPRESENT  !

ORIGINALSANDPOSSIBLYCONIAMINATED .

a e

e d

. --. + . - , . - _

I

I t

CORR 0SIONRAIEESTIMATION~

I. GENERAL 00Rit0SIONRATESFORCARBONSIEEL TYPICb AQUE0US ENVIROM AT NEUIRAL OFTEMPERATURE 12mpyAI70' 22mpyAI100'F 28 py AI 140'F -

TYPICAL AQUE0US ENVIR0M AI 100'F AS A FUNCTION OF pH 22 inpy AI pH 4-9 i

>50mpyAIpH<4 i

< < 22 mpy AI pH 9-13 l

L. II. CORR 0SION RATES BASED ON THICKNESS MEASUREMENIS IN 1986 ORIGINAL' THICKNESS 1.154"+.060

.010 1

BAY IHICfNESS(AVE)0.R.(6 YRS) 0.R.(17 YRS)

MAX / MIN MAX / MIN j 11 53/41 mpy 19/15 mpy

{97 MILS 19 873 MILS 57/45 mpy 20/16 mpy p .

SAMPLEANALYSIS l

I. DRAIN LIE SAMPLE A. SECTION OF DRAIN PIPE 10 BE REMOVED

'ANALY2ESAND

' B'ALY2E CORROSION PRODUCIS

~

'IRY10INSERIBOR0S00PEFORVISUALEXAMINATION II. WIPE SAMPLE A. IAKE WIPE FROM SIAINS BELOW VENT LIE

'ANALY2EFOR01,Mg,S,Si,B,pH 4

f

i s.o e e

SAVlEAMYSIS III. CORE SAVlES A. REMOVE SECIIONS Of DR M ll SIEEl

. VERIFYUIREADINGS CHARACTERIZE PIATE EIAllURGY EVALUAIECORROSIONPR0DUCIS IV. SAND SA9 tES A. REMOVE SAND FROM CORE SATLE H0LE

. LEYZE FOR ETALS, FA10 GENS, SULFUR AMYZEFORBA0TERIA -

MEASUREpH

.. EASRE RESISIIVITY EASURE h'AIER REIENIION

, g,

, _ _ , __.wr-- - --- - g- ' -"~'- '-'-"^ ~

I e

V. CURRENTACIIONPIE A. CORE PLAIE - MULTIPLE LOCATIONS

1. EVALUAIE0.D.PLAIESt1 FACE
2. SAMPLESANDANDOTHERMATERIALS
3. PERFORMVISUALEXAMINAIIONTHROUGHH0LE B. EXAMINE PLATE AI BOITOM 0F SAND CUSHION - WITH U.T.

C. GROUND POIENIIAL MEAS 3EMENIS D. VISUALLY EXAMINE VESSEL 0.D. VIA D0WNCOMER - IF POSSIBLE E.SAMPLEINSULAIION(FIREBARD),DRAINLINE F. DEVELOP REPAIR PROGRAM O

1 1

(

b, , NOTE: CORRECTION TO TIME, PLACE ,

AND SUBJECT OF MEETING

/[

/ \ unite]sTATss NUCLEAR REGULATORY COMMISSION s >

mannsmerom.a.c.ssues -

1 L, i b .ca

.e. 's O.-4996 - November 28, 1986

..~

%seD 'oc%et No. 50-219 .

MEMORANDUM FOR: H. Denton R. W. Houston F. Schroeder -

R. Vollmer D. Crutchfiele W. Butler -

J. Lyons E. Rossi D. Muller H. Thompson G. Lainas G. Hulman F. Miraglia T. Speis D. Vassallo R. Bernero W. Russell E. Adensam G. Holahan V. Benaro B. D. Liaw i T. Novak W. Regan.ya W. Hodges THRU: .fohnA.Zwo11nski,Directo f.

BWR Project Directorate i t Division of BWR Licensingb i, . . , .

FROM: Jack N. Donohew, Jr., Project Manager BWR Project Directorate #1 Division of BWR Licensing

SUBJECT:

DAlt.Y HIGHLIGHT - hEETING WITH GPil NUCLEAR CORPORATION DN THE OYSTER CREEK STATION DRYWELL SHELL CORROSION . .

.DATE & TIME: Monday, December 1, 1986

-10:.00 v.w.-------------------1 : 00 to 5 :00 pm l

~ ~ LOCATION: -tutit,-7;i;;;;v. L;;J;.,y ----P-118. Phillips Butiding 7920 Norfolk Avenue .

l Bethesda, Maryland

. PUDOSE: To discuss the corrosion of the drywell shall which has significantly reduced the thickness in two areas.

  • *11 i; PARTICIPANTS *: g Licensee

~

R. Vollmer R. Wilson R. Bernero D. Croneburger J. Zwo11nski J. Thorp J. Donohew .

M. Laggart B. D. Liaw . ,,

R. Hemann -

9 i - - ' ,- W --

3 -

..' O _

Q, Jack N. Do chew, Jr., Project Manager *

, BWR Project Directorate #1 F Division of BWR Licensing l

(0 c: See next page l.' ("'."Niegs between NRC technical staff and applicants for licenses are open for l interested members of the public, petitioners, intervenors, or other parties to ll- attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy",

j -

43 Federal Register-.28058,6/28/78.

,.-.w m m -- e , ,.~ = ==

=. wy , y - ,

~ ~- ~ =-

. p + .. = ~, s, . . . . ., .

,_N*~'**~*2****-_=_________________=%c

~~ 9_~ 2- < -c' ~~ -

e .

  1. 'o,, UNITED STATES

! a NUCLEAR REGULATORY COMMISSION 1 3 I wAsHmGTON, D. C. 20666

-% * * * * * ** November 25, 1986 Docket No. 50-219 MEMORANDUM FOR: H. Denton R. W. Houston F. Schroeder R. Vollmer D. Crutchfield W. Butler J. Lyons E. Rossi D. Muller  ;

H. Thompson G. Lainas G. Hulman F. Miraglia T. Speis D. Vassallo l R. Bernero W. Russell E. Adensam G. Holahan V. Benaroya B. D. Liaw T. Novak W. Regan W. Hodges THRU:

ohn A. Zwolinski, Directof

[

WR Project Directorate il ,

t Division of BWR Licensingu FROM: Jack N. Donohew, Jr., Project Manager BWR Project Directorate #1 Division of BWR Licensing .

SUBJECT:

DAILY HIGHLIGHT - MEETING WITH GPil NUCLEAR CORPORATION t

ON THE OYSTER CREEK STATION DRYWELL SHELL CORROSION DATE & TIME: Monday, December 1,1986

-> 10:00 a.m.

LOCATION:. P-422, Phillips Building 7920 Norfolk Avenue Bethesda, Maryland -

PURPOSE: To discuss the corrosion of the drywell shell which has significantly reduced the thickness in two areas. GPU <

Nuclear (the licensee) is preparing a safety analysis to justify operation from the current Cycle 11 Refuelina outage

' until the Cycle 12 Refueling outage.

PARTICIPANTS *: g Licensee R. Vollmer R. Wilson D. Croneburger

^

R. Bernero i

J. Zwolinski J. Thorp '

J. Donohew M. Laggart B. D. Liaw R. Hermann

@ y &, Jack N. Do ohew, Jr., Project Manager l ,

- BWR Project Directorate #1 Division of BWR Licensing

(. cc: See next page I

  • Meetings between NRC technical staff and applicants for licenses are open for
interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy",

j 43 Federal Reaister 28058,6/28/78.

. ~ - -. - _ . . _ _

- _ . _ - _ __ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _

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