ML20136E220

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Summary of ACRS Subcommittee on Metal Components 850904-05 Meeting in Washington,Dc Re Pressure Boundary Integrity & Proposed Rev 2 to Reg Guide 1.99, Radiation Damage to Reactor Vessel Matls. Fr Notice & Discussion Schedule Encl
ML20136E220
Person / Time
Issue date: 12/10/1985
From:
Advisory Committee on Reactor Safeguards
To:
Advisory Committee on Reactor Safeguards
References
RTR-REGGD-01.099, RTR-REGGD-1.099 ACRS-2349, NUDOCS 8601060469
Download: ML20136E220 (14)


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CERTIFIED COPY DATE ISSUED:12/10/85 MINUTES OF THE MEETING 0F THE ACRS SUBCOMMITTEE ON METAL COMP 0NENTS SEPTEMBER 4-5, 1985 WASHINGTON, D. C.

The ACRS Subcommittee on Metal Components met in Washington, D. C. on September 4-5, 1985.

The meeting dealt primarily with pressure boundary integrity, among other things it covered:

Proposed Rev. 2 to Reg. Guide 1.99 " Radiation Damage to t

Reactor Vessel Materials" Steam generators shell transition joint weld cracking Irradiation Assisted Stress Corrosion Cracking (IASCC)

Materials Research Program (NDE, RPV integrity and piping degradation)

Notice of the meeting was published in the Federal Register on August 19, 1985.

(AttachmentA) 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 included in Attachment C.

The meeting was entirely open to

~

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

E. Igne was the cognizant ACRS Staff member for the meeting.

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' MIN. METAL COMP 0NE"TS 2

Sept. 4-5, 1985 Mtg.

Principal Attendees ACR5 NRC G. Shewmon, Chairman C Serpan W. Hazelton D. Ward, Member M. Vagins N. Randall R. Odette, Consultant A. Taboada R. Dillon, Consultant M..Mayfield B. Thompson, Consultant J. Mucara W. Johnston Other B. D. Liaw L. Willertz, PA. Power &

D. E. Smith Light Co.

Johnston, Liaw and Hazelton, NRR, briefed the subcommittee on steam generator shell transition joint-weld cracking.

In 1982 Indian Point, Unit 3, found leaks in the transition joint-weld examination and showed that the leaks resulted from extensive cracking in this joint. The problem stemed from a poorly understood interaction of corrosion and fatigue.

I&E sent out an information bulletin suggesting that other utilities with PWR's shell transition joint-weld should look for cracks in such joints at their next major' outage. Surry, Unit 2, among others did such an inspection and found that they had similar cracks. These cracks were subsequently ground out and repaired during a subsequent outage. The Materials Engineering Branch of NRR have suggested that each licensee of a Westinghouse or CE PWR steam generator with similar shell transition joint-weld be required to do an inspection and report back on what they find. A counter proposal by the Division of Licens-ing, NRR, is that since,1) any such cracks would probably leak before the upper shell portion of the steam generator fails catastrophically,

2) even a major rupture is within the design basis accident (main steam line break) and 3) a PRA study indicates that the increase in the probability of core melt is insignificant for this scenario, such an order is unnecessary. Mr. Denton's office will decide.

n,

MIN. METAL COMPONENTS 3

Sept. 4-5, 1985 Mtg.

L. Willertz, Penn. Power & Light presented a careful detailed report on the current knowledge on IASCC. The cracking appears in stainless steel 2

exposed to over 1E20 nyt/cm. Components that reach this exposure are top guides, orf tubes and maybe control blades and shroud. They have reviewed the fracture of each of these components, but cannot find how pieces of any of them would cause a safety problem. General Electric's current belief is that hydrogen water treatment will push the threshold for the appearance of IASCC to significantly higher fluence.

N. Randall, RES, discussed the proposed Rev. 2 to Regulatory Guide 1.99

" Radiation Damage to Reactor Vessel Materials." The main concern about reactor vessel integrity centers around the possible brittle behavior of the vessel at low temperatures.

Reg. Guide 1.99 defines a conservative bound for the shift in Reference Nil Ductility Temperature (defined as the mean plus 2 sigma) to be expected from exposure to fast neutrons.

This is used to define the maximum pressure to which a vessel can be pressurized on heatup and in set'.ing limits for the PTS rule.

Revision 2 incorporates the results of a good deal of research..The main changes of Rev. 2 are as follows:

It has now beeN found that' nickel has a substantial effect on the NDT, and this effect is reflected in the revised guide.

(Nickel content is added as variable and phosphorus removed).

There is a considerable range of nickel contents in the field, especially because the welds in most of the newer vessels have high nickel (up to 1%) which was added to improve strength and initial toughness, t

MIN. METAL COMPONENTS 4

Sept. 4-5, 1985 Mtg.

At high fluence the rate of shift of NDT with fluence de-creases relative to Rev. 2.

This helps some of the older high Cu, low Ni vessels.

A different curve is defined for welds which has a somewhat higher rate of rise in NDT with fluence than that of.the base metal.

Guidance is given for calculating attenuation of damage through the vessel wall.

The proposed Rev. 2 of Reg. Guide 1.99 has been carefully considered and is a significant change from Rev. 1.

The subcommittee recommends that it be allowed to go out for public comments.

J. Muscara, RES, briefed the subcommittee on the status of the NDE program. The acoustic emission / flaw relationship program is presently winding down to a 1987 completion. This system has been installed at Watts Bar for on-line acoustic emission (AE) monitoring of the primary pressure boundary.

It is the intent at the conclusion of this program to establish an approved ASTM standard and gain ASME Code acceptance.

Field tests during startup and early operation at Watts Bar are planned.

SAFT-UT laboratory studies are being performed for system optimization.

Field validation tests have been preliminarily run with satisfactory results. Cooperative effort with industrial organizations for technolo-gy transfer is in progress. Code case acceptance efforts have been initiated.

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s MIN. METAL. COMPONENTS 5

Sept. 4-5, 1985 Mtg.

Inspection of weld overlays is still a problem in that detection and sizing of IGSCC less than 50% of the original wall thickness is unreli-able, although if the overlay surface is machined, improved detection is possible. Tandem wave probes can determine the remaining ligament associated with deep IGSCC cracks with some degree of accuracy.

It was stated that qualification of sufficient numbers of ultrasonic inservice inspection personnel remains a serious problem. More work in this area is necessary.

Mr. Vagins, RES, provided highlights of the pressure vessel integrity program. The program continues to evaluate the effects of flaws,.

variations in material properties (including environmental effet.ts) stress risers and residual stress on the integrity of reactor pressure vessels under normal and upset conditions. The program results are being utilized to improve ASME codes, ASTM standards, regulatory guides, Federal regulations, and the supports of the NRC staff in its licensing and safety evaluation process.

It was pointed out that integrity of the secondary systems is not being addressed by this program because of lack of resources. The following are some significant items that have been confirmed by experiments performed under this program:

The effectiveness of warm prestressing which significantly increases the pressure vessel toughness under PTS environ-ments.

The applicability of linear elastic fracture mechanics in predicting the behavior of the pressure vessel under combined pressure and thermal shock environment.

l

MIN. METAL COMPONENTS 6

Sept. 4-5, 1985 Mtg.

Demonstrated that ASME Section III and Section XI flaw eval-uations are conservative.

In reply to H. Etherington's concern, M. Vagins stated that it is a legitimate concern, the NRC Staff is aware of. it and it does not affect normal plant operation.

It may affect some of the conservatism we have built into the PTS screening criteria for low upper shelf materials and that this matter would be determined fron tests.

M. Mayfield, RES, presented a brief di.scusrion on the piping degradation program. This program covers piping fracture, IWB-3640 and leak-before-break. This program through analyses and experiments will determine the toughness of piping systems and validate the leak-before-break concept. This program has been in effect for about a year and much work still needs to be performed.

The subcommittee at the conclusion of the meeting decided to present the matter of the proposed Rev. 2 to Reg. Guide 1.99 to the full ACRS at the 305th Meeting, and reconsnended that it be released for public comment.

NOTE:

A complete transcript of the meeting is on file at the NRC Public Document Room at 1717 H Street, NW., Washington, D. C.

or can be obtained at cost from Ann Riley & Associates, Court Reporters, 1625 I St., NW., Suite 921, Washington, D. C. 20006 (202)293-3950.

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1611,161o. and 182 of the Atomic Energy 1me enomen e.i ohd d b, _ _ __,m -

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  • 7ui Act of1964, as amended, and the Commission's regulations in to CFR g- -

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Director. Division of Licensing. NRR. for g

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20 days of the date of publication of this W W~

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Order in the Federal Reghter. Any P===en.

emme.e. e se its consultants, and other interested ~

request for a hearing should be

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persons regardmg this review.

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Furtherinformaton regarding @

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Ar!ministre tor. Reg!on IV. U.S. Nuclear

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76011. A copy should also be sent to the skQ ".

Chairman's ruling on sequests for the opportunity to wel statensets Executive legal Director. U.S. Nuclear j j, 4 'se en s e,

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DC 20555. A request for hearing shall the cognizant ACRS staff member Mr.

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planning to attend this meeting ase 3 ;

Commission willissue an Order

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arged to contact the above====<4 designating the time and place of any

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scheduled meeting to be advised of any -

If a bearing is held concerning this t

Order, the issue to be considered at the / visory Committee on Reactor' changes in schedule.e'c,which many Ad hearing shaU be whether the licensee safeguards Subcommittee on Metal ~ have occuned..~

o should comply with the requirements set Componenta; Meeting Datd August 13 sess. ~#*MT L'.~...

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f, forth in Section IV of this Order.

De ACRS Subcommitteeb Metal Assisfarit Ersarcim gkruceerJhr Aufset i

his Order is effective upon issuance.

Components wiU hold a meeting on -.. Aeriew.

Dated at bethesda. Maryland this 2nd day September 4 and 5.1965. Room 1046

{FR Doc.as.1eam Fund HHe; eses am),

l Ef August.1985.

1717 H Street NW., Washington. DC.

- antaus cosa noses * "'* ' e" For the Nuclear Regulatory Commission.

To the extent practical the meeting Hush I.W le, will be open to public attendance. s -

However, portions of the meeting may.

Advloory Committee en Reactor T-I Director. Division ofLicensing Office of e

NuclearReactorRegulation, be closed to discuss GeneralElectnc '

safeguertes Sutnoommfttee en Remotor prcpr'stary information.

Operatione; bleeting s*!

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%e ACRS Soboommittee on Raeetoe I

Wednesday. September 4.1965-8:30 Operations will hold a meeting en to NtJREG-0737 am am until the conclusion of businesa September 9.1965. Room 1046.1717 H.

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% ursd. September 5.1965-8.30 a.m.

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ne Subcommittee willreview t meer.=

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%e agenda foe b subject messing i,a c iii Reguls tory Guide 1.s9. Revision 2. and shaU be as foUows-

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other related concerns and discuss the

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status of the NITT of piping program and Monday. September A 2sas-2.10ti m.

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ATTACHMENT B A-TENTATIVE SCHEDULE REVISION 2 ACRS METAL COMPONENTS SUBCOMMITTEE MEETING SEPTEMBER 4-5, 1985 WASHINGTON, D. C.

September 4,-1985 I.' Clairman's Opening Statement and Coments P. Shewmon (15 min) 8:30-8:45 II. Steam Generator

  • Shell girth weld cracks Surry

- Indian Point

- Others Safety Issues Causes, fixes, and generic implications Liaw (120 min)8:45-11:00

[with15-min.breakatabout10:00]

III. Irradiation Assisted Stress Corrosion Cracking (IASCC)

  • M
  • Discussion of Internal Report on 1

i IASCC, summer 1984, by L. E. Willertz, Pa. Power & Light Co.

(Susquehanna)

(90 min)11:00-12:30

+++

LUNCH

+++

(60 min)12:30-1:30 IV. Irradiation Effects on Pressure Vessel Materials; Regulatory Guide 1.99, Rev. 2**

  • Technical Basis, including differences with respect to Pressurized Thermal Shock RT I

N. Randall NDT (60 min) 1:30-2:30

  • Implementation N. Randall (30 min) 2:30-3:00 V. Materials Research Programs A. Introduction and Foreign Interactions C. Serpan (30 min) 3:00-3:30 i

i

+++

BREAK

+++

(15 min) 3:30-3:45 l

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B. NDE Acoustic Emission i

i SAFT-UT l

Eddy current, stm gen.

f Round~ robin Qualification J. Muscara (60 min) 3:45-4:45

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i VI. Subcomittee Discussions and (15 min) 4:45-5':00 Recess 5:00 ATTACHMENT I l

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2 September 5 1985 VII. ~~ Chairman's Remarks P. G. Shewmon (15 min) 8:30-8:45 VIII. Materials Research Program (Con't.)

C. HSST PTS results PTS future plans Wide plate crack arrest and crack growth rate I

Effects of cladding K

verification yc Irradiated crack arrest H. Etherington concerns on low upper shelf energy M. Vagins (120 min)8:45-11:00

[with15-min,breakabout10:00]

D. Piping Degradation Fracture IWB 3640 Leak Before Break Mike Mayfield (60 min) 11:00-12:00 a

IX. Subcommittee Discussions and (30 min) 12:00-12:30 Adjournment 12:30 e

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ATTACHMENT C

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HAND 0UTS FOR METAL COMPONENTS SUBCOMMITTEE MEETING SEPTEMBER 4-5, 1985 1.

Steam Generator Shell Cracking - W. Hazelton 2.

Memo to J. P. Knight from H. L. Thompson, NRR

Subject:

Steam Generator Shell Transition Joint Cracking 2.a Regulatory Responses 3.

IASCC, PA Power & Light Co. - L. Willertz 4.

Draft Regulatory Guide 1.99, Revision 2 Radiation Damage to Reactor Vessel Materials 5.

Review of Materials Engineering Branch Budget and Research Program

- Foreign Interactions 6.

Overview of NRC Research Programs in NDE - Joseph Muscara 7.

A Review of Program Elements of the MEBR Pressure Vessel Research Program by Milton Vagins 8.

Piping Degradation by M. E. Mayfield l

' ~ ~. ~

+ ;_

E. IGNE ATTACHMENT D 9.

ACRS SUBCOMMITTEE MEETING ON METAL COMPONENTS LOCATION 1717 H St. NW., Washington, D.C. Room 1846 DATE SEPTEMBER 4-5, 1985 ATTENDANCE LIST PLEASE PRINT:NAME AFFILI ATIf1N P. % um< m Acts A R. ijJosul R.Od_tb A a s.

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LOCATION 1717 H St. NW., Washington, D.C. Room 1446 DATE SEPTEMBER 4-5, 1985 ATTENDANCE LIST PLEASE PRINT:NAME AFFILI ATION

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