ML18094A074

Summary of 830809 Meeting W/Util,Nutech & GE Re Insp of Large Diameter BWR Pipe Welds.Util Will Submit Addl Info within Next Several Days.Agenda & Viewgraphs Encl

ML18094A074
Person / Time
Site:	Browns Ferry
Issue date:	08/10/1983
From:	Dunesia Clark Office of Nuclear Reactor Regulation
To:	Vassallo D Office of Nuclear Reactor Regulation
References
IEB-83-02, IEB-83-2, NUDOCS 8308190055
Download: ML18094A074 (50)

Text

August 10, 1983 Docket No.

50-296'ROM:

MEMORANDUM FOR:

Domenfc B. Vassallo, Chief Operatfng Reactors Branch 82 Division of Licensing Dick Clark, Prospect Manager Operating Reactors Branch P2 Division of Licensing

SUBJECT:

Re:

SUMMARY

OF AUGUST 9s 1983 MEETING WITH TENNESSEE VALLEY AUTHORITY (TVA) REGARDING INSPECTION OF LARGE DIAMETER BMR PIPE MELDS Browns Ferry Unit No. 3 OFFICE)

SURNAME)

OATEN A meetfng was held on August 9, 1983 between representatives of the NRC and TVA to discuss the proposed acceleration of inspections of welds in large diameter piping at. Browns Ferry Unft 3 fn view of the cracking recently identified at several BNR facilities.

Enclosure 1 fs a list of meeting attendees.

Enclosure 2 is a copy of the-mater'ial presented by the licensee.

Darrell Efsenhut (NRC) opened the meeting by stating that this was an fnformatfon gathering meeting and that the NRC position would not be established until after available fnformatfon had been received and r evfewed.

Browns Ferry Unit 3 (BF-3) fs scheduled to shutdown on November 11, 1983 for refueling and various NRC requfred modifications {e.g., completion of the Nark I torus modifications).

During the outage, the recfrculatfon and RHR system piping wfll be fpspected fn accordance with IE Bulletin 83-02.

Similar inspections have been performed on Units 1 and 2.

TVA presented fts gustfffcatfon for continued operation of BF-3 for the next 3 months until the scheduled refueling outage fn November, based pri-marily on the following:

o Leak-Before-Break fs a valid crfterfa; o

Cfrcumferentfal flaw instability fs impossible:

o Crack propagation rates fn large diameter piping fs very slow once a

crack r eaches approxfmately 30% throughwall, since the metal is fn compression; 8308i90055 830810 PDR ADQCK 05000296 8

PDR NRC FORM 3I8 110/80) NRCM 0240 OFFICIAL RECORD COPY

• U.S. GPO 1983~00.247

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3 visual inspections of the piping between now and the schedu1ed November 11, 1983 outage, and (3) the desirabi1ity of providing specia1 operator training to increase awareness of and prompt response if there is an indication of 1eakage.

Enc1osures:

As stated cc w/enclosures:

See next page Original signed by:

Richard J. Clark, Prospect I/tanager Operating Reactors Branch 82 Division of Licensing DISTRIBUTION:

Docket File NRC PDR Local PDR ORB82 R/F 8 Ntng Smry File J. Heltemes B. Grimes OELD E. L. Jordan J.

H. Taylor ACRS (10)

NSIC NRC Participants D. Vassallo D. Clark OFFICE I SURNAME)

OATEP ORBIT2:

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8///a /83 NRC FORM 318 RO/801NRCM 0240 OFFICIAL RECORD COPY J

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Mr. Hugh G. Parris Tennessee Valley Authority Browns Ferry Nuclear Plant, Units 1, 2

& 3 CC:

H. S.

Sanger, Jr.', Esquire General Counsel Tennessee Valley Authority 400 Commerce Avenue E

11B 33C

,':noxville, Tennessee 37902 Mr. Ron Rogers Tennessee Valley Authority 400 Chestnut Street, Tower II Chattanooga, Tennessee 37401 Mr. Charles R. Christopher

Chairman, Limestone County Commission P.

0.

Box 188

Athens, Alabama 35611 U. S. Environmental Protection Agency Region. IV Office Regional Radiation Representative 345 Courtland Street Atlar:ta, Georgia 30308 Resident Inspector U. S. Nuclear Regulatory Commission Route 2, Box 311

Athens, Alabama 35611 Mr. Donald L. Williams, Jr.

Tennessee Valley Authority 400 West Summit Hill Dr., W10B85 Knoxville, Tennessee 37902 Ira L. Myers, M.D.

State Health Officer S.ate Department of Public Health State Office Building Montgomery,. Alabama 36130 Yr. H.

N. Culver 249A:-:BD 400 Cc~ierce Avenue Tennessee Valley Authority Knoxville, Tennessee 37902 George Jones Tennessee Valley Authority P. 0.

Box-2000

Decatur, Alabama 35602 Mr. Oliver Havens U.S. Nuclear Regulatory Commission Reactor Traininq Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411 James P. O'Reilly Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

ENCLOSURE 1

ATTENDANCE LIST MEETING WITH TVA

~A Name Dick Clark Larry Hills Dick Parker J.

D. Wolcott Jim Domer Michael P. Ferrante Jim Charnley Wm. J'. Collins J. Dietrich T. Alexion S.

Ranganath John A. Zwolinski John W. Pendlebury J. B. Henderson J. J. Blake F. S. Cantrell B. 0. Liaw R. H. Vollmer

0. Eisenhut Or anization NRR/DL TVA TVA TVA TVA Am. Nuclear Ins.

NUTECH NRC/IE CP8L NRC/DL GE NRR/DL GE NRC/IE NRC/R-I NRC/R-II NRC/DL NRC/DE NRC/DL Name Jim Green Tom Ziegler Joe.

D. Ferguson Gary Pitzl T. Tesch Joseph C.

Danko Paul Goldberg Vince Derr Ambjorn Lindsuog D. L. Radius R.

Gamble J.

E.

McEwen, Jr Victor Benaroya Robert Baer

-James L. Coley D. B. Bassallo G. C. Lainas J. A. Olshinski E.

Case Or anization TVA TVA TVA TVA ANI EPRI NRC/OPE NUTECH RKS CBI Imoel 1 TSI NRR/CMEB NRC/IE NRC/R-II NRR/DL NRC/DL NRC/R-II NRC/NRR

Pl A6EHM AIJGlJST 9, 198>

I JUSTIFICATION FOR CONTI NUED OPERATION A.

LEAK-HEFORE-EREAX Ha CRACK-GRO'i'(TH PiQDELS ilALI D C

s STRUCTURAL INTEGRITY 0

s EXTENS I VE CRACK I NG EXPECTED Es LESS OPERATING T li~)E t I i SUMi~lARY OF PREVIOUS I NSPECTI OiNS 1 I t s

OESCR IPT ION OF PR INARY SYSTEiI I FAK BETECTI ON I V i t ~lPACT OF UN I T 1

I NSP CT I ON AND REPA I R iCT I V I T ~ ES A,

t:ONPLETED INSPECTIONS

~ ARGE DIAMETER PIPING Hi REPAIR PHilOSOPHY C

s CURRENT INSPECT I ONS

. Si~)ALL OI A51ETER P I P I NG li4lPACT ON OTHER SAF ETY-'RELATED AC'T I VITI ES VI, AVAILABILI TY OF EQUAL IF I ED INSPECTION PERSOiINEL YI I s

IMPACT OF ROUND ROBIN RESULTS

I )

JUST I F I CAT I OH FOR COiHT I HUED OPERAT I ON UNIT Ai LEAK 8EFORE HREAK CRITERIA STIL~

VALID STAINLESS STEEL HAS HI GH TEARiNG NODULUS CIRCUiilFERE'lTIAL FLAM Ii'lSTABIL!TY Ii(POSSIBLE

(

PRI REPORT HP-25".7, 4P-2508-LD, AtlD.~lP-22" 1)

ASYNtlETRY OF

'AELD SENSITI'ZATION AHD BEiHDING LOADS VERIFIED BY

,I EXTENSIVE F I E'. 0 EXPERIENCE 5

GPtl LEAK RATE BEFORE PLASTIC COLLAPSE (EPIRt AHD GE TECHNICAL SUNMARY, AUGUST 0, l983)

8c CRAC(

6RO".JTH

'HODEL,S YALI D INITIATION TO DETECTABLE SIZE SLO')J Si41ALl DIAMETER PIPING -

CRACK PROPAGATION RAP I Dp SMALL. THROUGH JALL LEAKS

~ I LARGE DIAMETER PIP! NG CRACK t'ROPAGATION FAIRLY RAPID T0 APPROXIMATELY 20-PERCENT THROUGHNALL; VERY Sl 0'(J BEYOND APPROX IMATEL

, 50-PERCENT THROUGH'<JALL CRACKING FOUND TO DATE FA~ LS HITHIN THESE MODELS

C s

ANALYSI S FOR STRUCTURAL INTEGR I TY-'ADEQUATE.'"MARGIN OF SAF ETY ST ILL EXISTS CRACK MUST BE 3600 AROUND THE PIPEi 53-PERCENT THROUGH'lALL BEFORE CODE SAFETY MARGINS INFRINGED SIzING UNcERTAINTY FRoN RouND RQBIN DQEs NQT INFRINcE QN sTRUcTURAL MARGIN DIAGRAM ( PRI, 6E PREsENTATIoN AUGUST I,

1983)

STRESS RATIOS

~ ESS THAN O,S SIzING BAsED oN cRAcK DEPTH sHomlN To BE vERY coNSERvATIvE (EPR1>

6 PREsENTATION AUGUST 4, 1983)

f'RACKING IS HOT SURPRISING tGSCC TAKES A

I ONG Tlt/E TO INITIATE TO DETECTABL" LEVELS HUHBER OF NELDS IN PAST INSPECTIONS VERY SHALL IEH EXAiRINATIOtl TECHi~lIQUES NORE SENSITIVE TO t6SCC NUMBER OF MELDS EXAtlINFD HAS GREATLY INCREASED

I)NIT 3 HAS t ESS OPERATING TIi~)E THAN ~JNIT l EFPO AT uisti' suuTooMM - ~lovsyssz ll, 1983 175 1759 X2'r EFPO AT UNIT 1

SHUTDOllN APRIL 15, l'383 1877 HAJOR PARA iETERS IDENTICAL FOR ALL 3 UNITS.

SAi't E P I PE F ABR I CATORS AND F ABR I CAT I ON PROCEDURES SANE INSTAi LATION PROCEDURES Sli~lILAR OPERATING PARAMETERS.

CRACKIIG IN UNIT 5 NOT'EXPFCTED TO BE AS SEVERE AS IN UNIT

11, Suui<ARY OF PREVIOUS NEi D Ii>>SPECTIONS CO~iPi ETED ON JNIT 3

A, 11 MEI DS INSPECTED libel NOVEMBER 1981 8

HO CRAC(ING OBSERVED C

g TECHNI QUE USED NOT AS SENS I T I VE To I GSCC AS I EB TECHNI QUES Sli>>GLE ELEi~lEiNT TRAi'lSDUCER USED PULSE-ECHO TECHNIQUE USED A(50 SHEAR NAVE I ARGER CRYSTAL USED FVALUATION AT NODE-AND-A-HALF klo TRANSFER TECHNIQUE USED

IfJ I E4KPf~; 0HFcTl0ii REQU IREi4lENTS IN PERDITION TO CURRENT TECHNICAL SPEC IF ICATIONS TECHNICAL SPEC IF ICATIONS SUBMITTED lARCH 25, 1983 FOR 2 6P l

INCREASE LIMITATIONS, i)ARCH Z)TH TECHt'I'ICAL SPECIFICATIOiNS ADMINISTRATIVELYENFORC D

JULY 1, l'383, CURRENT ADMINISTRATIYE REQUIREMENTS COLD SHUTDO>tN REQUIRED IF UNIDENTIFIED LEAKAGE INCREASES BY 2 GPH AVERAGED OVFR 20

HOURS, 2)

APPLIES ONLY AFTER REACTOR HAS BEEN IN RUN MODE FOR 2".

HOURS AFTER STARTUP, 3,

SURVEILLANCE INTERVAl IS ONCE/8 HOURS,

METHOD OF LEAKAGE i~1EASUREHENT OISCHARGE FLO'< FRON FLOOR MAIN SUi~1P INTEGRATED, INTEGRATION READING COMPARED TO READING TAKEN 24 HOURS EARLIER

UlllT 1

INSPcgTICN A~!~D REPA1R ACTI~/ITIES

lI B 83-02 f.'ISPECT[0 I

sU'4R'( ~"0 "CTi~~'~ (iO Jut Y

"=,

1983 I,

SUi1HARY OF 1'(E D EXAHINAT!ONS A.

'~JEi DS EXA1INED 1,

RECIRc RISERS SMEEPOLETS LARGE OIAt1ETER 90 8

Qg 91 2,

0,"R.

SUPPLY (20")

RETUP

< (2>")

7 2'5 32 TOTAL 123 8e RESULTS QF FXAiNINATIONS (SE "IGURES l i 2

p Ah!D 3) 1 o

MELDS HAYING.t RACKING RISERS

5 S>lEEPOLETS LARGE DIAMETER 23 33 SUPPL Y R

R E TURN

1 I TOTAL 2e FIELDS TO BE REPAIRED - 30

ARGE 9 AMMETER REC RCUI AT[0i~l P P

HG MELOS

~IIE D No, KR-1-2<

KR-1-58 fR-1-56 6R-1-65 KR-1-47 6R-1-27 6R-1-57 KR-1-45 6R-1-61 KR-1-52 INITIAL CRACK SI ZE 25%

3 INs 28%'-

360o 29%

17,5 IN.

33%

350o 23%

21 IN, 36% -

19 IN, 32%

360o 23%

360o

.30%

25 IN, 27% - 360o

'LLONEO INITIAL CRACiK SIZE FOR OHE CYCLE 71 50 63 51 66 51 66 50 PERCENT FRROR I'1ARGIN FOR SAFE OPERATION 117 55 170 78 120 JEN:MPA 81217A,MA

<so x

+6O Zl,

~ 40 o<0 20 0

7g%

MARGl w LiNF l oo%%u~

MARGiN EDMp~

>c xx Figure 10 2O 40 60 80

'f00 DY,'/o YFIIP.GUSH WAILL

\\

B~s

TABLE 1

OVERLAY DES lGiMS Pipe Neld No.

Diameter Crack Denth Ove r 1 ay Th ickness Overl ay

~enceth Steady State Stress Cateaor KR-1-37 KR-1-15 KR-1-3 GR-1-3 GR-1-58 GR-1-54 GR-1-60 KR-1-18 KR-1-21 KR-1-2 2 KR-1-16 GR-1-4 1

-.. GR-1-46 I

~'D-RHR-1-17 D-RHR-1-18 D-RHR-1-15 DS-RH R 9 DS-RHR-1-8B

.DS-RH R-1-1 1 DS-RHR-1-10 DS-RH R-1-5 D-RHR-1-5 DS-RH R-1-4 D-RHR-1-20 D-RHR-1-8 DS-RHR1-4A 221n

~

22 28 28 28 28 28 12 12 12 12 24 20 24 20 20 24 24 24 20 24'4 354 27 43 35 45 36 35 35 35 35 20 31 20 30 29 24 30 31 36 30 43 25 44

. 200in.

. 200

.35

.25

. 35

.35

.25

. 125

.125

. 125

.125

. 200

.125

. 200

. 200

. 200

.200

. 200

. 200

.200

. 200

.25

. 200

.200

. 200

.25

4. 5in.

4.5 7.0 7.0 7.0 7.0 7.0 2.5 2.5 2.5 2 ~ 5 4.5 2.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 7.0 4.5 4.5 4.5 7.0 8,384 7I/23 15,110 12, 461, 11,754 13, 283'5,244 12,593 13, 224 15,058 9,461 13, 829 13,427 12,633 12,057 11,879

'11,599 14,071 12,450 11,396 13,617 6

1 6,099*psi 6,099" 8,411 8,145 3

7,845 2

Pressure stress only assumed equal to that for weld number KR-1-34

1'ABLE 2

OVERLAY CATEGORIZATION Cate or Sou rce of Weld Residual Stress Applied Stress Initial Crack Size*

Pipe Defame ter Pipe Thickness Overlay Thickness Overlay

~Len th Reference 3

Compu te r Ru n Compu ter Ru n Re ference 4

Reference 5

Compu ter Run Compu ter Ru n

.6,099psi 8,411 8,145 15,110 35,344**

1 5 Q58***

13,617 70%

90 72 70 86 22"

28. 51

28. 15 12.75

" 12. 75 20.

20.

1.03 1.322 1.138 e789

. 57.9 1.031 1.031 2 II

.35

.25

.125

.20

.20

.25 5 II 7.0 7.0 2.5 4.5 4

~ 5 7.0 The measured U.T. depth was multiplied by 2.0 for use in the crack growth analysis.

The tabulated crack sizes are in percent of unrepaired pipe thickness.

Crack growth evaluation performed using 26,270 psi

= 35,344 1.031 Crack growth evaluation performed using 12,612 psi

= 15,058 1

Q31

+

2QQ TVA-01-031

100 80

~Iz hCO I-Cl 60 0

D 40 I

a hCo 20 75 ALLOWA8LE DEPTH 89 NO CRACK GROWTH AS K IS NEGATIVE 0

0 20 40

.TIME (MQNTHSj Figure 2 CRACK GROWTH FOR CATEGORY 1

100 80 z

hCO O

60 0

0 cR

~.. 40 Ci C3 0

20 72 ALLOWA8LE DEPTH 7I NO CRACK GROWTH AS K IS APPROXIMATELY P.P 0

4p 60 TIME (MONTHS)

Figure 4 CRACK GROWTH FOR CATEGORY 2

$ 00 M

CO Z

hCo Q

Lll 0

0'g 40 Cl hCo o

.20 74 ALLOWABLE DEPTH 59 NO CRACK GROWTH AS K IS NEGATIVE

~

40 TIME (MONTHS)

Figure 6

CRACK GROwfTH FOR CATEGORY 3

.100 80 R

hC I

L5 60

)0 0

40 0

hC

,CC 20 75 ALLOWABLE DE~TH NO CRACK GROWTH PS K IS APPROXIMATELY 0.0 0

20 40 I

60 TIME (MONTHS)

Figure 8

CRACK GROItTH FOR CATEGORY 4

80 z

bCO O

60 0

0 40 I

Cl hCO 20 62 ALLO'sVABLE DEPTH 18 4.116 X 10 K

CJC I

20 40 TlME (MONTHS)

Figura 10 CRACK GROWTH FOR CATEGORY 5

100 83 z

C3 I-O 50 0

O g

x 40 O

O O

ALLOWABLE 0 EPTH 75 72 NO CRACK GROWTH AS K IS NEGATIVE 0

0 20 40 TIME (MONTHS)

CTVA83.01 12 Figure 12 CRACK GROWTH FOR CATEGORY 6

V)

LIJ CD I-O UJ 0

80 60 75 ALLOWASLF DFPTH 71 NO CRACK GROVEL'H AS K IS APPROXIMATFLY 0.0 40 a

hC CD CD 20.

TIME (MONTHS)

Figure 14 CRACK GROWTH FOR CATEGORY 7

I.i EXPANSION OF t6SCC t NSPECTi ON HRQHNS ERRY UNI T 1

CORE SPRAY (ALL STAINLESS "lELDS) 27 REACTOR MATER Cl EANUP (ALL NELDS I ifS I DE F I RST ISOLATION VALVE)

HEAD SPRAY (ALL FIELDS INSIDE THE FIRST ISOLATION VALVE) 21 TOTAL 52

-V, 1.',PACT ON nTHFR SAFETY eFl ATED ACTIVITIFS

PLIRPGSE:

TO. PRESENT IHE SCHKULES QLj IYPACTS CN SAFEtY-RElATED ACTIVITIES OF AN INSFECTIBl OUTAGE GN BRONS FERRY UNIT 3 STARTIYG ON THE FGLLOAIi~G DATES:

SEPTPEER 15, 1983 KTGBER 15, 1%3 NOVPBER 15, 1%5

CCirerrS OF UNIT1 CYCLE 5 OUTRE PuJOED DURATION - 170 DAYS 1,

TORUS INE~RI7( PRCGBN A,

INTERi'll t'GDIFICATICt'6 8,

EXTERNAL tQDIFICATIC%

TIEI,'0PiiS SNUHHERS TORUS-ATTACHED PIPING (kNS CRITICAL PAtH) 2,79-018 RELATED i tODIFICATICt'5

. 3, Tf'lI KjDIFICATIQ6 REFUELIiKi (FULL CORE UNLM/RELOAO) 5, RK3ELIi'6 YAINTQJltNCE 6,

IKCC NELtj REPAIRS 36 (TO DATE) 7 CONTINUATICN OF I%PECTICi'I NORK Cil 52 ADDITI

CCKCERi6

. A.

TIf'KFRPYE FOR OUTAGE PREPNNING j,.

FOPi%L PLAi'5?i/G 2,

JCB AREA PlANt')ING Ai'8 LAYOUT TCOLS ND ECUIPi'Ei'K N/FGJER 5,

CQHRACTS 6,

PREFABRICATID'6, >iCRKPLANS, Df%lINCC SUPPORTING INIT 3

ccxcem (CCln'D)

B.

INCHED i%9FQilER LEVELS

~ I C,

SHORTAGE OF B<GINEERING ND QM I71'SSURNCE PERSCBEL 1,

WORK COVH%E 2,

PROBlB1 RESOLUTIQH 3.. NORKPLN CLOSURE

~.D, PARALLEL REFUEL FLCOR ACTIVITIE i~PfKEABILI71',

PARALLEL OPERATIC'5 NS SURVEILLA'FACE ACTIVITIES PJ'K) SUPPORT FOR PARALLEL OUTAGES

CNCERNS (GK'0)

F PRCBSILI7( GF f'KTIi~lG SEPTEJ'BER DH'"PM3 IS 86i.

G, ALA% CCNCERi'6 SEPTBPER IS END GF 3RD QUARTER H,

SPFEiY CGNCEB6 1,

YWGESILIlY 2,

PEPSNhiEL SA'ETY PN:lT SPFHY

SCHEDULE SLiYNRY BPSED ON THE FOLLG'/If'ATAA NOVEMBER 11, 1%3 SHUtK']li'<

DATE FOr" BRG'J!H FERRY UNIT 3 VJ'I BE SUPFORTE, TECHNICAL JUSTIFICATIC%

ttj-"ti'eGaeILITY

< VaZR AVAIueILITY THE ELIMINATICtlOF THOSE CONCERNS'SSCCIATED klITH PARALLEL OUTAGES (I,EUNIT 1 RETUWH TO SERVICB

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EXISrtNC BFN l&tT I UNIT 2 UNtT 3 1983 J

I=

H A 8 J

J A

S 0

N 0 CYCLE 6 I 74 CYCLE <

CYCLE 5 1Q84 A

N J J

A S

0 N 0 CYCLE 5 l52 DIVIStoll CF l4KLEAR ~R MKLEAA PROGUCT ICH oatti

mtT 1

PAOJECTEO EKH CYCLE 4 UNIT 2 CYCLE 5 l 71 CYCLE 5 I 59 m!T 3 CYCLE 5

TVA NDE INSPECTION PERSOHHEL 2 LEVEL IIX'S (IGSCC CERTXr"IED) 0 LEVEL II'S (IGSCC C"RTir"XED) 2 LEVEL Iii'S (NOT IGSCC CERTIFIED)

AUGUST 8 EPRX IGSCC TRAINING CURRENTLY UNABLE TO SCHEDULE FOR NRC IGSCC CERTIFICATION 3 LEVEL II'S (NOT IGSCC CERTIFiED)

SEPTEMBER 12-16 EPRX IGSCC TRAINING CURRENTLY UNABLE TO SCHEDULE FOR NRC IGSCC CERTXFICATIOit

BRO'rlNS FERRY Vi. INSPECTION SITUATION I.

EXPANSION OF IGSCC INSPECTION CORE SPRAY (ALL STAINLESS NELDS)

- REACTOR MATER CLEANUP (ALL 'rlELDS INSIDE FIRST ISOLATION VALVE)

HEAD SPRAY (ALL MELDS I'lSIDE THE FIRST ISOLATION VALVE) 27 TOTAL 52 gl II.

IllSPECTION OF BROHNS FFRRY UiNIT g~ REPAIR VrELDS (36-PLUS REPAIR MELDS) if UT OVERLAY FOR BOilDiiNG AHD DEFECTS UT OVERLAY FOR "UNDERCLAD CRACKING" UT TO ESTABLISH iver".'rl IGSCC BASELINE AUGUST 18 - CALIBRATION BLOCK FABRICATED AUGUST 22 INSPECTION PROCEDURES APPROVED MATTS BAR INSPECTION SITUATION MORK'ING TO COMPLETE PRESERVICE PRIOR TO JANUARY 1984 FUEL. LOADXiiG CURRENTLY BEHIND SCHEDULE DUE TO DRAIN OH PERSONNEL TO SJPPORT BROrlHS FERRY UNIT 1

IGSCC INSPECTIOi'l SEQUOYAH INSPECTION SITUATION

!- SEQUOYAH UNXT 2 CURRENTLY DO>lN FOR REFUELING OUTAGE AND ROUTINE XN-SERVICE INSPECTXON IN PROGRESS EXPECTED RETURN TO SERVICE SEPTEMBER 30, 1983 h

YI I i li~fPACT OF ROUND ROBIN RESULTS A.

TVA WAS TEAS 5

8i RESULTS SHO'tl VERY GOOD STANDARD DEVIATION Ci SAiRE PERSONNEL>

EQUIPi'1EHT TECHNIQUE AS USED Oi'l HROMHS FERRY UHI T D,

RESULTS LEAD TO ADDITIOl'lAL CONSERVATISN ON BROMNS ERRY Ui~lI T F

s GENERAL CONF I DENCE IN TVA' S I Z I HG CAPAB IL I TY SUPPORT 0

BY,>OUHD ROBIN RESULTS

'V II E