Text

Summary of 830208 Meeting W/Util,Ge,Epri & Anl in Bethesda, MD Re Issues Relating to 1-inch Crack Discovered by NDT in 28-inch B Recirculation Suction Line safe-end to Elbow Piping.Viewgraphs Encl
	ML17194B472
Person / Time
Site:	Dresden
Issue date:	03/02/1983
From:	Gilbert R; Office of Nuclear Reactor Regulation
To:	; Office of Nuclear Reactor Regulation
References
	LSO5-83-03-002, LSO5-83-3-2, NUDOCS 8303070149
	Download: ML17194B472 (32)
	v • d • e

Docket No. 50-237 LSOS-83-03-002 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March2, 1983 LICENSEE:

COMMONWEALTH EDISON COMPANY (CECo}

FACILITY:

Dresden Nuclea~Power Station, Unit No. 2

SUBJECT:

SUMMARY

OF MEETING HELD ON FEBRUARY 8, 1983 The NRC staff held a meeting in Bethesda, Maryland with representatives of CECo and General Electric (GE} to discuss issues relating to the 1 11 crack, discovered by non-destructive testing, in tbe 28" 11 B 11 recircu-lation suction line safe end-to-elbow piping at Dresden Unit 2. A list of attendees is provided in Enclosure 1 and an agenda of the items discussed and the conclusions presented by the licensee's representatives are provided in Enclosure 2.

Licensee representatives presented the procedures used and the data obtained which allowed them to characterize the extent of the crack and also a fracture mechanics evaluation of the safe end cracking. Based on the fesults of a previous one month hydrogen addition test at Dresden 2 and additional GE laboratory hydrogen addition tests, they proposed that the present crack was not a safety problem and that the hydrogen addition procedure, if permanently implemented at Dresden 2, could arrest further crack growth from IGSCC.

They then requested staff approval of this procedure.

The staff stated, after discussing the issue, that, because there was insufficient quantitative data to support crack arrest with hydrogen addition, credit could not be given by the staff for this procedure.

to arrest IGSCC at Dresden 2.

However. the staff. concluded that hydrogen posed no adverse affects and could be beneficial~ Thus, agreed to evaluate the procedures with the intent of allowing its use in Cycle 91.

The staff also had some concerns relating to the NOE procedure and the data obtained by NOE.for this crack. It was agreed that further

. discussions would be held with the cognizant staff members to resolve these concerns.

Based on the above, the staff stated that, if the concerns were resolved, the licensee could use hydrogen addition lThe staff indicated that the licensee needs to address the potential affects of'the hydrogen system failures and effects.

.1 March. 2, 1983 during Cycle 9 and the affected area would probably not need to be removed or weld overlaid.

Further conditions relating to NOE examination(s) and leak detection procedures during Cycle 9 will also be required and the extent of th~ir implementation negotiated.

During the presentations,,viewgraphs \\'Jere used.

Copies were furnished to the staff for their use and files but portions were declared pro-prietary by GE.

The non-proprietary material is included as Enclosure 3.

The project*manager has a copy of the proprietary material in his files.

Enclosures:

1. List of Attendees

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Robert A. Gilbert, Project Manager Operating Reactors Branch #5 Division of Licensing

2.

Meeting agenda and licensee conclusions

3.

Non-proprietary viewgraph copies.

cc w/enclosu*res:

See next page

.I cc Isham, Linco1n & Beale Counselors at Law

One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr. Doug Scott

. Plant Superintendent Ru ra 1 Route #1 Morris, Illinois 60450 U. S. Nuclear Regulatory Corrrnission Resident Inspectors Office Dresden Station

_RR #1 Morris, Illinois 60450 Chairman

-'Board.of Supervisors of Grundy County Grundy Cou'nty" Courthouse Morris, Illinois 60450 Illinois Department of Nuclear Saf~ty 1035 Outer Park Drive, 5th Floor

Springfield, Illinois 62704

~U. S. Environmental Protection Agency

. f~deral Activities Branch Region V Office

. A.TTN:

Regional Radiation Representative 230 Scuth Dearborn Street Chicago, Illinois 60604 James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region Ill I

799 Roosevelt Road Glen Ellyn, Ililinois 60137 Mr. D. Farrar

Director of Nuclear Liceniing Commonwealth Edison Company Post Of~ice Box 767 Chicago, Illinois 60690 March 2, 1983

/

ENCLOSURE.1 LIST OF ATTENDEES Dresden Unit No. 2 Meeting of February 8, 1983 NAME AFFILIATION R. Galer

('

GE R. Law GE F. Leone GE J. Skarpelos GE J. Kass

- GE H. Mehta GE R. Rybak CE Co R. Ragan CE Co R. Tammenga CE Co J. Abel CE Co I

J. Thuot CE Co M. Strait CECo.

w.

\\~i tt CE Co T. Rausch CE Co M. Fox-EPRI R. Clark NRC

v. Benaroya NRC

w. Koo NRC

c. Cheng NRC R. Ranta la NRC R. Dudley NRC

\\

List of Attendees (Cont) NAME AFFILIATION

c. McCracken NRC F. Witt NRC P. Wu r'

NRC R. Serbu NRC D. Crutchfield NRC B. Li aw NRC H. Hazelton NRC

w. Collins NRC R. Gilbert NRC W. Key NRC - Region III L. Spessard NRC - Region II I D. Danielson NRC - Region II I

w. Shack ANL (NRC consultant)

/

A

MEETING AGENDA DRESDEN UNIT 2 RECIRCULATION SYSTEM SAFE END FEBRUARY 8, 1983 I.

INTRODUCTION - J.S. ABEL II.

FLAW CHARACTERIZATION -.W. WITT I I I. SECTION XI ADDENDA ANALYSIS - H. MEHTA IV.

HYDROGEN WATER CHEMISTRY BENEFITS - J; KASS V.* HYDROGEN ADDITION SYSTEM DESCRIPTION - J.R. THUOT VI.. CONCLUSION - J.S. ABEL ENCLOSURE 2

I CONCLUSIONS

- SAFETY LEAK BEFORE BREAK

-'CODE ANALYZED BY CODE METHODS.

- BENEFITS HYDROGEN PREVENTS OTHER IGSCC LONG TERM FIX MAJOR STEP IN IGSCC RESEARCH COST EFFECTIVE A

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SENSITllEC MICROSTRUC~.E FACTGa

PHASE 1 RECCX"'tJErmATIONS 0

Hi ROST FEASIBLE ADDITIVE 0

~Stt~ -r2 IS FIRST CHOICE FOR DEMONSTRATION PLAAT 0

02 GOAL SHOULD BE 50 PPB.

0 MATERlf.LS tf-ORK RUST BE DONE BEFORE MAJOR PLANT APPLICATION 0

TESTS A.t:tE r.EEDED TO Cot-ff l RM A)

H2 REQUIREf!ENT B)

N-16 DOSE INCREASE VS. o2 REDUCTION"

/

C)

Hi ADDITION SYSTEM R~LIABILITY AND EFFICIEf4CY D)

WAITR CHEMISTRY CHAHGES

/

OBJECTIVE -

ONE-MONTH DEMONSTRATION OF FEASIBILITY AND CONS~QUENCES OF OPERATION WITH HYDROGEN ADDITION FLOWSHEET DETERMINE..;.

0 CHANGE IN STEAMLINE ACTIVITY VS..H2 ADDITION RATE SCHEDULE -

0 FLOWSHEET ACCURACY (

0 ELECTROCHEMICAL POTENTIALS IN PRIMARY SYSTEM 0

OFFGAS SYSTEM PERFORMANCE

0 WATER CHEMISTRY CHAHGES 0

FEEDHATER 0

PRifiARY SYSTEM,

0 HYDROGEN ADDITION SYSTEM PERFORMANCE t]D H2 TO DRESDEN-2 IH MAY 1982

HIGH OFFGAS HYDROGEN LOW OFFGAs-oXYGEN REMOTE MANUAL SHUTDOWN ----

AREA GAS MONITORS ( 8)

HYDROGEN SUPPLY SECONDARY 40,000 SCF 175 pslg PRIMARY 120,000 SCF HYDROGEN CONTROL STATION FE EDWATER FLOW

'-Ill--- REACTOR SCRAM LOCAL SHUTDOWN LOW FEEDWATER FLOW

~

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CONDENSATE. BOOSTER PUMPS HYDROGEN INJECTION SYSTEM DRESDEN 2

RECOMBINER

, PREHEA TER STEAM JET AIR. EJECTOR AIR 65,000 SCF COOLER t

. WATER SEPARATOR.

HYDROGEN CONTROL OFFGAS SYSTEM

HYDROGE~ WATER D-!El"ilSTRY r'

- HYDROGEN ADDITI~ SYSTEM HO:iIT~Il:G SYSTE~

OFFGA.S SY STEM

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0 2 = ?4 (!'Pb t~AIH STE.AM FLOW TO TURBINE 02 c 2000 ppb H2 c 2.000 ppb H 2 c 19 6* pp b LJ)::===:=::==:;:::=== ~

o_Rl_Vl_H_G_FL_O_ll_~

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9.9 )\\106. lb/ hr t~AIN FEED FLOW FROM TURBINE EECIRCULATIOH PUUP 94.~ lb/hr 02 c 18 ppb H

c: tS6 ppb 2

FULL SUP?RESSlON fLOVI SHEET 02 = 20 ppb H2 = 1750 ppb.

100 c-k POWER

HYDROGEN ADDI TI ON SYSTEM

- SUPPLY AND STORAGE

- LINE BREAK PROTECT!~

- FLOW CONTROL AND MO:~IT~ING ISOLATION

/

HYDROGEN SUPPLY FARM TURBINE BUILDING FLOW CONTROL*

OF HYDROGEN LOCAL CONTROL *

(SECONDARY CONTROL)

CONTROL ROOM (PRIMARY CONTROL}

$)}%i@liigfilWJJ,MAIN STREAM* ~~~~~~E~ITI1 PUMP SUCTION HYDROGEN ADDIT.ION* SYSTEM

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OFFGAS SYSTEM

- AIR AND/OR OXYGEN ADDITION

- PROCESS CONTROL

- PROCESS MONITOR

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SYSTEM EFFECTS OF H2 ADDITION 0

STEAM ACTIVITY WILL HKREASE UP TO BX 0

OXYGEN GENtRATION WILL DECREASE *.* OFFGAS FLOW DECREASES FJID BECOMES HYDROGEN RICH (WITHOUT AIR ADDITIOO) 0 THE A.~ttT Of !i1YDROGEN. l ~ TKE STEAf1 REMA I NS CONSTANT OR OECREASES Sl!GH1lY

.0 CLEAN-UP SYSTEM ACTIVITY ~ILL DECREASE SLIGHTLY 0

OXYGEN LEVELS THROUGHOUT THE SYSTEM WILL DECREASE 0

ALL.CHANGES ARE RAPID

50,59 SAFETY REVIEW

e PERSONNEL EXPOSURE ROD DROP ACCIDENT G

FUEL

O MTERIALS e

EFFLUENTS.

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- ALARA ifl'DROGEN ADDITION SAFETY AND OPERATING CONCERNS

- FIRE PROTECTION

- PU!ti' CAVITATION

- TURSIJU:

- h!.TERIAl...S PRI fl.ARY SYSTEM FUEL SYSTEM

~ATER CHEMISTRY

- MAIN STEAH LINE RADIATION MONITOR

I

1

- OffGAS RELEASE r

r.-o CHANGE

- SITE DOSE TEST 19.4 TO 22.7 ~ 2.5 ON SITE (17i)

. 1981 9.8 TO 13.4 (36~)

1980 1~.4 TO 16.3 {56.7%)

IH PLANT ADDITICJUAl LHHTED ACCESS:

HIGH PRESSURE HEATER BAY LO'-d PRESSUP£ KEA TER SAY STEM ~"iEL,

MOISTURE SEPAAATOR ROOM TURBIH.£ SHIELD (INSIDE)

TURBINE WILDING ROOF TURBIHE BUILDING CRANE I

.et"

I' FIRE PROTECT ION

- DESIGN

- ISOLATION

- EXCESS FLOW ISOLATION

- BARRIERS

- PUMP TROUBLE

. - OFFGAS

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- I.LL hATERIALS TESTED IN LABORATORY SHOW SUBSTANTIAL IMPROVEMENT ELI~I~TES IGSCC IN 304 SS FUEL MTERIALS

- SIMILAR TESTING DATA INDICATES HO IHCREASEO CONCERN IS WARRANTED

- SIGNIFICANT*POST-IRRADIATION EXAMINATIONS PLANNED TO CONFIRM

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rm CHANGE

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t!AIH STEAM LINE ~DIATIO!f ri'DNITOR A.

BELO~ 2~ *PCM'ER - NO CHANGE B.

ABOVE 20% POWER

1.

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2.

OffGAS ~ITOR IS ENVIR~ME~TAL ISOLATION

ML17194B472

Contents

Text

SUBJECT:

SUMMARY

Enclosures:

Navigation menu

ML17194B472

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