ML20203N047

Summary of ACRS Subcommittee on Metal Components 860701-02 Meetings in Columbus,Oh to Review Degraded Piping Program Being Performed at Bmi,Anl & Matls Engineering Assoc

ML20203N047
Person / Time
Issue date:	09/16/1986
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-2438, NUDOCS 8609230103
Download: ML20203N047 (16)

Text

hbf$~ kYS L

PDR 9-/fdh l

~

'/

r CERTIFIED COPY ISSUED: Sept.16,1986

SUMMARY

/ MINUTES OF THE ACRS SUBCOMMITTEE ON METAL COMP 0NENTS JULY 1-2, 1986 COLUMBUS, OHIO The ACRS Subcommittee on Metal Components met at Battelle Columbus Laboratories (BCL) in Columbus, Ohio on July 1-2, 1986 to review the degraded piping program being performed at BCL, Argonne National Laboratory (ANL), Materials Engineering Associates (MEA), David Taylor Naval Ship Research and Development Center (DTNSRDC) and others under the sponsorship of RES.

Notice of the meeting was published in the Federal Register _ on June 24, 1986 (Attachment A). The schedule of items covered in the meeting is in Attachment B.

A list of handouts kept with the office copy of the minutes is in Attachment C.

There were no written or oral statements received or presented from members of the public at the meeting.

E.

Igne was the cognizant ACRS staff member for the meeting.

Principal Attendees NRC ACRS P. Shewmon, Chairman M. Mayfield H. Etherington, Member G. Arlotto W. Kerr, Member M. Bender, Consultant E. Rodabaugh, Consultant J. Hutchinson, Consultant E. Igne, Staff Battelle Columbus Laboratories G. Wilkowski G. Kulhowvick B. Saffell G. Ahmad R. Schmidt P. Scott C. Jaske G. Kramer V. Papaspyropoulos J. Kiefner R. Eiber F. Brust M. Landau Others W. Shack, Argonne National Laboratory D. Kupperman, Argonne National Laboratory O. Chopra, Argonne National Laboratory 860923o103 e60916 0

PDR Certi f! ed By ___

a

i W

b y

METAL COMPONENTS 2

July 1-2, 1986 Meeting W. Cullen, Materials Engineering Asso.

R. Hays, David Taylor Naval Ship Research & Development Center G. Wilkowski, BCL, is the Program Manager for the NRC Degraded Piping Prograrii, Phase II. The program objectives are to verify, improve and develop flaw assessment analysis for leak-before-break methodology. The scope of this program involves the analysis and experiments relating to circumferential cracked pipes (simple through-wall cracks, internal surface crack and their combination) with various materials (austenitic steels and welds, carbon steels and weld, and centrifugally cast stainless steels), and loading combinations (bending, axial and its combination). Pipe sizes vary from 4 to 40 inches in diameter, and test temperatures at room, 300*F and 550 F.

This program interacts with regulatory, industry, other NRC contractors, and foreign governments.

A summary / status report of this program after three years of work is as follows:

Limitations on the net-section-col' lapse (load-limit) method of analysis have been determined.' Surface crack data show that the pipe radius to thickness ratio is an important parameter.

Additional data is needed for different crack size.

A screening criteria has been developed to determine when the net-section-collapse method is valid. Generally, it is not valid for large-diameter pipes due to pipe becoming out of round at large loads.

l Weld overlay repair (W 3) of cracked pipe has been initiated.

Preliminary results indicate WOR pipe failed below the j

net-section-collapse loads. This is probably due to residual l

stresses and plasticity factors. Additional tests are being planned to assess plastic-zone screening criterion and IWB-3640 l

analysis.

~

b' N

July 1-2, 1986 Meeting 3

I,j *,, METAL COMPONENTS Cast stainless steel pipe specimens are being aged and will be tested in 1987.

Data on torsional load interactions are needed.

Test results on piping material indicate that dynamic strain-aging (property changes occur during plastic deformation) has been This leads to an increase in strength 0

encountered at 550 F, (ultimate and yield) and a decrease in total elongation and The effect of dynamic strain-aging on fracture fracture toughness.

resistance is not yet well estalished, especially with varying loading rates.

Various elastic-plastic fracture mechanics methods to predict GE/EPRI through-wall-crack failure loads have been evaluated.

The. Paris method is not, general enough analysis is conservative.

The NRC/LBB method is the because the hardening tem is neglected.

most accurate.

In evaluation of a complex-cracked (internal surface crack with a portion of it through-wall, Duane Arnold type crack)) pipe, the J-estimation schemes do not account for the radial crack driving An empirical correction was developed to make realistic force.

Likewise, the J-estimation schemes predict load predictions.

displacement well up to maximum load, but overestimate loads past Improvements to J-estimation scheme predictions are maximum load.

under way.

i l

l

)

k k

METAL COMPONENTS 4

July 1-2, 1986 Meeting Finite element stress analyses have been performed to assess the accuracy of the estimation schemes and the applicability of small-specimen J-R curves to large-crack-growth analysis.

A. Hiser, MEA, briefly discussed the piping fracture mechanics data base (PIFRAC) program. This werk will develop a comprehensive, computerized data base for use in postulated accident analysis. Data base information will include material chemistry, tensile properties, Charpy energy values and J-R curves. Test parameters will include material type / size, temperature and grain orientation. Query software for this program is nearly complete.

B. Saffell, BCL, discussed the developing international piping integrity researchgroupprogram(IPIRG). This program is to be managed by the NRC for the performance of complex piping experiments.

It will provide

~

a forum for reaching international consensus on new pipe break rules and a replacement for the double-ended break criterion. This program will be performed by BCL.

The objective of the program will be to develop, improve and verify engineering methods for evaluating the structural integrity and performance of nuclear power plant piping containing defects.

Specifically, the IPIRG program will develop an understanding of the response of high-energy, flawed piping systems to dynamic loading, establish pipe fracture and expand material property data base, verify leak-rate estimation models, and coordinate program results and regulatory issues through information exchange seminars.

The following countries are expected to join IPIRG:

• United Kingdom

• France

• Japan

~~

i 2

METAL COMPONENTS 5

July 1-2, 1986 Meeting

• Canada

• Sweden

• -Switzerland

• Taiwan EPRI Other countries, i.e., FRG, Italy, Spain, Argentina and Korea, are considering becoming members, and Finland and Belgium have declined.

D. Kupperman, ANL, briefly discussed the assessment of leak detection for nuclear reactors. Current practice for leak detection is given in Regulatory Guide 1.45.

It recommends three methods be employed for leak detection as follows:

sump flow airbone - particulate radioactivity and condensate flow rate or airborne gasebus radloactivity The regulatory guide also recommends that identified and unidentified sources be rr.onitored separately to an accuracy of I gal / min for PWRs and l

5 gal / min for BWRs.

i I

Laboratory studies at Argonne have been established to assess adequacy of acoustic methods to detect, locate and size leaks.

In addition,

. :-.m Argonne will also evaluate the moisture sensitive tape system. Studies will be carried out with field-induced cracks with acoustic background data acquired from existing reactors.

D. Kupperman stated that, depending on the background noise level, about 20-40 acoustic sensors will be needed for a leak detection system at a plant. Leak rates in

.the range of 0.01 to 1.0 gal / min should be measured with some accuracy.

j Using cross-correlation techniques the leak location capability has been significantly improved. The computer-based system has been tested under field conditions at Braidwood, and plans to monitor the Watts Bar plant with ANL/ GARD two-channel acoustic monitors are under way.

l l

l-METAL COMPONENTS 6

July 1-2, 1986 Meeting

0. Chopra, ANL, discussed the mechanisms of thermal aging of cast stainless steel (CSS). The current NRC research program essentially seeks to correlate the microstructural changes in aged CSS with the loss in. toughness and to identify the mechanism of embrittlement.

Preliminary test results indicate that the mechanism of low-temperature embrittlement are as follows:

Primarily caused by N precipitation The o(' phase forms by spinodal decomposition Role of G and Type X phases is still unclear Carbide precipitation at Tt boundaries influences the toughness of high-carbon grades aged at temperatures greater than or equal to 400*C Preliminary results indicate that toughness of the low-temperature aged material may be recovered by annealing at 555*C for 30 minutes.

W. Shack, ANL, discussed environmentally assisted cracking of stainless steels in BWR environments.

W. Shack briefly reviewed the status of studies on intergranular stress corrosion cracking (IGSCC).

For sensitized stainless steels in the recirulation piping systems, three remedies are proposed as follows:

alternatiave materials (316NG, TP347),

hydrogen water chemistry with impurity control, and residual tensile stress modification by either IHSI or mechanical stress improvement process (MSIP).

For nonsensitized stainless steels in high-radiation area materials become susceptible to stress corrosion cracking at high-fluence levels (currentGEestimate s

20 2

5 x 10 n/cm, E >1MeV). Currently, studies of interaction between irradiation, environment and stress are unclear. Proposed remedies in

I 1..

METAL COMPONENTS 7

July 1-2, 1986 Meeting L

this instance are impurity control in the stainless steel, and hydrogen water chemistry with in. purity control.

Transgranular stress corrosion cracking (TGSCC) based on laboratory testing results in a potential problem for 316NG and probably TP347 materials. Preliminary results show that this concern may be mitigated by tight controls of impurities in reactor coolant, residual stress improvement and could probably be elimincted by the use of hydrogen water chemistry.

In addition, ongoing ANL crack propagation rates in 316NG are greater than in sensitized 304SS even in high purity water.

ANL has notified General Electric Co. of this disconcerting problem.

ANL has evaluated the mechanical stress improvement process (MSIP) developed by O'Donnell and Associates. This process uses a split-ring tool somewhat similar to the pipelock configuration. The split ring is installed, shimmed, and tightened to plastically deform the pipe to a range of 1-2%.

This process permits a one-sided application which permits its use on more complex piping system geometries.

Unlike the IHSI process the inner pipe surface does not need to be cooled, which simplifies scheduling, and is generally claimed to be cheaper and faster than IHSI. Monotonic plastic flow with no large tensile loads on the inner surface exists in the MSIP, unlike the reverse of plastic flow associated with IHSI.

W. Shack stated that utilities would like to use the MSIP on some piping system but NRC is hesitant, until further data is developed. Utilities may use it, according to W. Shack, but no credit will be given for its use by NRC. s W. Cullen, MEA, discussed applications-oriented fatigue and fatigue crack grwoth studies in LWR materials. Historically, environmentally-assisted cracking research in LWR materials started about 20 years ago when the AEC awarded a contract to Westinghouse in the mid-1960s.

It was noted that all this work is oriented toward PWR environment.

W. Cullen discussed details of the following programs:

j l

L~

I

(

. METAL COMPONENTS 8

July 1-2, 1986 Meeting Part-through crack growth studies of panel specimens (piping and RPYsteels)

Variable amplitude loading studies Stress-life testing of piping steels Fatiguecrackgrowthofpipingsteels(carbonandcaststainless steel).

The tests above will be run in a cyclic pressurization test facility that still needs to be constructed in order to grow realistic (3-D) cracks in 12-inch-diameter pipe sections in air and PWR environments (2500 pss, 650'F).

It is planned to have visiting scientists (initially from Italy and Finland) to help in determining the models that can be used to predict the environmentally-assisted crack growth in plants.

Future Meetings No future subcommittee meetings were pl'anned.

NOTE: A transcript of the meeting is available in the NRC Public Document Room, 1717 H St., N.W., Washington, D.C., or can be purchased from ACE-Federal Reports, 444 North Capitol St.,

Washington, DC 20001[(202)347-3700]

1 Feder'.1 Register / Vcl. 51, No.-121 / Tu;sd2y, Jun1r 24,1986 / Notte:s

) 23014 f=

Dated: june 19,1986.

Dated; june 19,1986.

. visory Comr'nittee on Reactor Morton W. LlbarUn, Maeton W. IJbaddn,

!guafda, Subcommittee on Metal mponents; Meetin9 Assistont Executive DirectorforProject Assistont Executive DirectorforPwject Review.

Review.

Th2 ACRS Subcommittee on Metal

[FR Doc. BM4232 n!ed 6-23-86. s.45 aml(FR Doc. 86-14233 Filed 6-23-86: 8.45 am)

Components will hold a meeting on July a,,,,,,m 1 and 2,1986, at Battelle Columbus Laboratory, Conference Room G 505 Advisory Committee on Reactor IDocket No. 4Ho271 King Avenue, Columbus,011. -

Safeguards, Subcommittee on Plant NRC Meetings Regarding Resumption The entire meeting willbe open to Operating Procedures, Meeting of Operation for Sequoyah Fuels public attendance.

% ACRS Subcommittee on Plant Corporation, Gore,OK He agenda for subject moetmg shall Operstmg Procedures will hold a be es follows: Tuesday, July 1.19EA~

meeting on July 1,1986. Room 1046,1717 AcENcr. Nuclear Regulatory 8:30 A.M. until the conclusion of H Street. NW., Washington, DC Commission.

business Wednesday, July 2,1986-8:30 The entire meeting will be open to ACTICN: Notice of meeting.

A.M. until the conclusion of business.

public attendance.

suMMARr. Meetings will be held by the The Subcommittee will review the ne agenda for the subject merJing RES degraded piping program being shall be as follows: Tuesday, July ;,

Nuclear Regulatory Ccmmission [NRC) 1966-1 M AM. untiliDO RM.

to solicit information from members of performed at the Battelle Columbus ne Subcommittee will review a the public about issues which they Laboratories.

would like to have the NRC consider

" Proposed Commission Paper on Oral statement may be presented by Technical Specificatiens."

duringits review of the proposal from members of the public with concurrence Oral statements may be presented by Sequoyah Fuels Corporation to restart e,f the Subcommittee Chairman; written members of the public with the UF. production at the Sequoyah Fuels statements will be accepted and made concurrence of the Subcommittee Facility in Core, Oklahoma, Since an tv llable to the Committee. Recordings Chairman; written statements will be accident which occurred at the facility willbe permitted only during those accepted and made available to the on January 4,1986, involving rupture of a portions of the meeting when a Committee. Recordings willbe permitted UF. cylinder, operation of the facility transcript is being kept, and questions nly during those portions of the has been suspended.

m:y be asked only by members of the me ng hen an cripti ng kept, July 8,1988,7 p.m. to 10 p.m. and oATEs:

ubcommittee,its consultants, and Staff.

July 9,198%10 a.m. to 12 noon.

ne desiring to make oral members of the Subcommittee,its tements should notify the ACRS staff consultr_nts, and Staff. Persons desiring AoonEss: Brooks-Cawhorne Imbers as far in advance as to make oral statements should notify Gymnasium, Core Oklahoma.

practicable so that appropriate the ACRS staff member named below as " " * " " '"'" * "" * " *4309.

j crrangements can be made.

far in advance as is practicab!- so that William T. Crow,(301) 427-l During the initial portion of the appropriate arrangements can be made.

suPP1.EMENTARY INFORM ATION:De During the initial portion of the scope of the meeting includes matters meeting. the Subcommittee, along with meeting, the Subcommittee, along with such as emergency response, effluents.

cny of its consultants who may be any of the consultants who may be and any other issues related to the present, may exchange preliminary I

viiws regarding matters to be present, may exchange preliminary resumption of operation of the UF.

considered during the balance of the views regarding matters to be facility. Statements by the public are considered during the balance of the being limited to 3 minutes per individual I

meeting.

meeting.

and 6 minutes per group.The pubhc ne Subcommittee will then hear The Subcommittee will then hear meeting does not include issues presentations by and hold discussions presentations by and hold discussions associated with the two hearings with representatives of the NRC Staff, with representatives of the NRC staff,its

'Its consultants, and other interested consultants, and other interested pending before the Nuclear Regulatory Commission's Atomic Safety and persons regarding th.is review.

persons regarding this review.

Licensing Board (ASLB). namely, the Further information regarding topics Further information regarding topics applications relating to the proposed t)be discussed, whether the meeting to be discussed, whether the meeting UF. to UF. production and solid waste his been cancelled or rescheduled, the has been cancelled or rescheduled, the disposal. Both of these matters will be Chairman's ruling on requests for the Chairman's ruling on requests for the dealt with in separate public hearings epportunity to present oral statements opportunity to present oral statements conducted by the ASLB.

cnd the time alloted therefor can be and the time allotted therefor can be.

cbtained by a prepaid telephone call to obtained by a prepaid telephone call to Dated at Silver Spring. Maryland. this 17th the cognizant ACRS staff member, Mr.

the cognizant ACRS staff member, Mr.

day of June.1986.

Elpidio Igne (telephone 202/634-1414)

John O. Schiffgens (telephone 202/634-Fdmebr Ruulcory Gmmwiom between 8:15 A.M. and 5:00 P.M. Persons 1413) between 8:15 A.M. and 5.00 P.ht M* N """4**

Persons planning to attend this meeting Director. Division of fuel Cycle andMoterial planning to attend this meeting are are urged to contact one of the above Sofety. Office of Nuclear Moterialsofery and urged to contact the above named named individual one or two days Sofeguards.

individual one or two days before the before the scheduled meeting to be

[FR Doc. 86-14226 Filed 6-2Fe6; 8.45 am]

cheduled meeting to be advised of any advised of any changes in schedule, etc.

anges in schedule, etc., which may which may have occurred.

swwo coce rsso-s -u ve occurred.

ATTAcymdT

.w _

A REVISION 1 6/27/86 PROPOSED SCHEDULE FOR THE ACRS METAL COMPONENTS SUBCOMMITTEE MEETING HELD AT BATTELLE, COLUMBUS, OHIO ON JULY 1 AND 2, 1986 Tuesday, July 1, 1986

/:30-8:46a.m.

Opening Remarks P. Shewmon T2.

8 32 v'8:45 - 9:30 a.m.

Degraded Piping Program G. Wilkowski

- Overview A:36 - 12:00 N00N Degraded Piping Program BC)fStaff

- Presentation of Technical Results and Plans 15 Minutes BREAK during this session 12:00 - 1:00 p.m.

LUNCH Le49 - 2:00 p.m.

Evaluation of the Ductile R. Hays, DTNSRDC Ojo Mo-Fracture of Carbon and Stainless Steel Welds

- 2:30 p.m.

Piping Fracture Mechanics A. Hiser, MEA

') ' 0 Data Base s

- M 0 p.m.

BREAK 2..' &3 esde p.m. END OF DAY Informal Tour of BCL's West Jefferson Facility for ACRS only Wednesday, July 2, 1986 8:30 - 9:30 a.m.

International Piping G. Wilkowski, BCD OY;L Integrity Research Group (htww OtLTEER )

eg

- % M'dle HW g - 10:15 a.m.

Assessment of Leak D. Kupperman, ANL Detection Capabilities f

~- 10:30 a.m.

BREAK jfbHT - 11:30 a.m.

Investigation of the

0. Chopra, ANL Mechanisms of Thermal Aging (O'di of Cast Stainless Steels h&lkHIO/T

. [-

METAL COMPONENTS JULY 1&2 MTG.

2 d

i SI@

-]

g0-12:30p.m.

Environmentally Assisted W. Shack, ANL Cracking of Stainless Steels in BWR Environments J k30 - 1:30 p.m.

LUNCH p 30 - 3:00 p.m.

Environmentally Assisted j',g Cracking of Stainless Steels in BWR Environments (Cont.)

3.00 3:15 p..

BREAK

~

SS

- 4:30 p.m.

W. Cullen, MEA 2:3D Applications Oriented Fatigue Crack Growth Rate Studies in PWR Materials &

f 4',g )

Environment

- 5:00 p.m.

Closing Remarks and Adjournment e

I 9

I h

=

E

)

/

l g.

o.

ATTACHMENT C LIST OF HANDOUTS JULY 1-2, 1986 MEETING OF THE ACRS SUBCOMMITTEE ON METAL COMPONENTS, COLUMBUS, OHIO 1.

Battelle Columbus Labs: NRC Degraded Piping Program, Phase II Presentations, G. Wilkowski, Program Manager 2.

Fracture Mechanics Evaluation of LWR Alloys, R. A. Hays, David Taylor Naval Ship Research and Development Center 3.

-Piping Fracture Mechanics Data Base-(PIFRAC), A. L. Hiser, Materials Engineering Associates, Inc.

4.

Assessment of Leak Detection for Nuclear Reactors, David Kupperman, Materials and Components Technology Div., Argonne National Lab.

5.

Investigations of the Mechanisms of Thermal Aging of Cast Stainless Steels, O. K. Chopra, Materials and Components Technology Div., Argonne National Lab.

6.

Environmentally Assisted Cracking of Stainless Steels in BWR Environments, W. J. Shack, Argonne National Lab.

7.

Applications-Oriented Fatigue and Fatigue Crack Growth Studies in LWR Materials, William H. Cullen,-Materials Engineering Associates, Inc.

8.

International Piping Integrity Research Group Program, B. F.

Saffell, Battelle 4

l-6 i

ATTACHMENT C l~

E. IGNE

)d' -

ACRS SUBCOMMITTEE MEETING ON NNN LOCATION BATTELLE COUNBUS IAB.. COIRBUS, OHIO DATE JUlXbnd2.1986 v

ATTENDANCE LIST PLEASE ~ PRINT: NAME AFFILI ATION S,L to wM bC2. 5 1 Rilmb d

W (h

o W

\\h dw Actz s co*\\bJ

e. TLerKML

!- +1u&asb E. J gou kE9 Cos be, -

a e

b hC I

01 ll'lA v fi s i D asNec G o A.

b toTTc u.s o <t. t.

E A & ( & //

Esthe a.a su m,or ssrrrae c&

E, dece-BaYfeYo N. ems.u oemes smne E, 46 ipa E(?_.

M TTt3LLI l

3ttu Etwac Afees-th L C de~

7AA-f%s. b.

uv i

E. IGNE MAL COMPONINTS ACRS SUBCOMMITTEE MEETING ON

.)

LOCATION BATTELLE COLIABUS IAB.. COIBBUS, OHIO DATE JUL nd 2. 1986 v

ATTENDANCE LIST PLEASE PRINT:NAME AFFILIATM GrRaco Evtuuwerc (

SnfrELLE

.IAtees Amm BWTTEtt F 7a Sw h ike sua nuac mnaat UOHA) }(iEforte BATTELLE Fre) S co sf.

RAT 71:LLF

$wW la ado w f n$ lle l

f.

t I

l 1

E. IGNE

~

MAL MM

, ACRS SUBCOMMITTEE MEETING ON g

LOCATION BATTELLE C01B EUS LAB.. COLUMBUS, CHIO DATE JULY 1 an 1986 v

ATTENDANCE LIST PLEASE PRINT:NAME AFFILIATION

h. Sblo utM

.A.C.Q_.5 Lkt% to k

• b't M

M q;

teruv '

o viA b a u J hs

cows, ri.- ErhtQ u

J. euwde o

E LsNE ices M-G. N. W.iLtk' Ede.1Ae CWkb M oa.'~

s.r. uLlt A4. ka4 E.'oM t>5/v R C Gow A. A R LoTt o LA. S. N. R.. C.

I.

S S-([effg 10 l

bfAstLO bwLHowsok bded l<,,

Ow dashe 5 ff eIle > Ce[%/.u.s Dinhb4 Allen Acc-f1a+e Ads Eng',weecimy Asmade

~

f g.

E. IGNE METAL COMPONENTS ACRS SUBCOMMITTEE MEETING ON 1

LOCATION BATTELLE COLUMBUS LAB. COLUMBUS, OHIO DATE JULY 1 an b l986 v

ATTENDANCE LIST PLEASE PRINT:NAME AFFILI ATION Mill bnc4 kR60NMs N4d. E bye Kurrernuv)

Arnoorte A1,4ss Lab OMESH D'CHOPR A A veo n w e % [7 m d L d

@smu

%1 htLo - Ldu,,%s biviam,,

7 A ber

%i.J4 - coloan h4.J GzcG dean n 3didh - Caph%d B,ll C A (Nk. E%

Asm.

dnaHmvwaa Hwva C 'AcRs w s.

/

bnaZ?" I?, d sbo o.l.

Ecl7adsbus.5" Arie e,il,s T., c.

fej k $tuferL A)/Oted / /trals r

$J,kGcm bedhk - A-[b[

l

[

, -.. _ _