ML20151D323
| ML20151D323 | |
| Person / Time | |
|---|---|
| Issue date: | 03/17/1988 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 ACRS-2557, NUDOCS 8804140138 | |
| Download: ML20151D323 (18) | |
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SUMMARY
/ MINUTES OF THE ACRS SUBCOMMITTEE MEEf!NG ON METAL COMPONENTS FEBRUARY 18, 1988 WASHINGTON, D.C.
The ACRS Subcommittee on Metal Components met on February 18, 1988 in Washington D.C. reviewed Regulatory Guide 1.99, "Radiation Embrittlement of Peactor Vessel Materials" and was briefed on low flux embrittlement of reactor support structures.
Notice of the treeting was published in the Federal Register en February 2,1988(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.
There were no written or oral statements received or presented from members of the public at the meeting.
E. G. Igne was Cognizant ACRS Staff Member for the meeting.
Principal Attendees ACRS NRC Staff G. Shewmon, Chairman C. Serpan D. Ward, Member K. Wichman C. Michelson, Member R. Boshak H. Lewis, Member B. Elliot R. Odette ACRS Consultant G. Arlotto L. Shao Others C. Cheng ETrTesbach, EPRI J. O'Brien W. Server, RLC & Asso.
N. Randall R. Gamble, Novetech Corp.
R. Woolley, GA International Ser.
C. B rgeron, Grove Eng.
G. Honan, LLNL L. Nielsen, ANF D. Fitzgerald, U.S. GA0 J. Scarborough..QCM h'Y@U %,
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Minutes / Metal Componen%s Mtg.
2 February 18, 1988 R. Carter, Yankee Atonic T. Mager, Westinghouse A. Lowe, Jr. B&W NPD W. Corwin, ORNL L
E. Chevertnn, ORNL A. Banerjee, Stone & Webster W. Shack, ANL 5
Hichlights:
1.
N. Randall, RES, discussed Rev. 2, of Regulatory Guide 1.99, l
"Radiation Edrittlement of Peactor Vessel Materials." He stated that there are four types of analyses of reactor vessel integrity that depend on the fracture toughness of beltline inaterial. They are1) pressure-temperaturelimits,2)evaluationofflaws,3) post-accident evaluation of damage, and 4) screening criteria for pressurized thermal shock. Data base for Revision 2, is primarily due to reports by Odette (EPRI NP-3319, dated January 1984) and by r
Guthrie (NUREG/CP.-3391. Vol. 2 or HEDL-TME 83-22, Quarterly 1
^
April-Jure 1983.) Note that these reports are about 5 years old and that Revision 3 of Reg. Guide 1.99 is being planned to incorporate the latest data.
l Comparison of Revision 2 of the regulatory guide to Revision 1 are as J
follows:
3 o
Updates Revision 1 after 10 years of use o
Data is based on regression analysis by Guthrie and Odette of power reactor surveillance test results o
Provide the mean values of ART and states margin separately l
NDT o
Uses different chemistry factors for welds and base metal
Minutes / Metal Components Mtgo 3
February 18, 1988 o
Copper and nickel is accounted for in chemistry factor o
The fluence exponent changed from 0.50 to 0.28 minus 0.1 Log F.
o Provides formula for through-wall attenuation based on DPA.
o Tightens requirements for use of plant specific data.
The promulgation of Reg. Guide 1.99, Rev. 2, impacts on both PWR's and BWR's. The impact on PWR's is with regards to low temperature over-pressure (LTOP) concerns.
N. Randall stated that in all but 12 PWR plants, the present LTOP set point is more than 75 psi below the Appen dix G pressure at T,=
120 F., calculated using Rev. 2.
Of these, 7 plants are already at or below 450 psi.
Remedies for these restricted operating windows were elaborated as follows:
o The definition of "at low temperature" in SRP5.2.2 and Branch Position 5-2, provides about 60 relief on the temperature
- windew, o
Adjustable setpoint PORVs provide additional relief on temper-ature window o
Better pressure instrumentation provides leeway on the pres-sure window o
If setpoint is above the P-T limits the utility must demon-strate that LTOP frequency is well below one per reactor lifetime.
It will also require a bubble be forined in the pressurizer at startup. Note: B&W plants already start up with bubble in the pressurizer.
I
~
' Minutes / Metal Components Mtgo 4
-February 18, 1988 j
]
o In any case, resolution of the LTOP concern has to be on a 4
1 case by case basis.
i i
Impact on the BWR's involves code pressure tests. Higher required j
temperatures are needed and it requires increase heatup time with i
0 j
present pump heat.
In addition, temperatures'over 200 F. require that the containment be closed, which makes it more difficult to inspect for leaks. Remedies stated by N. Randall includes a "two-step hydro", which L
requires a code change and the use of an auxiliary boiler. The time
{
saved by using an auxiliary boiler should be sufficient to pay for the.
auxiliery boiler and piping changes.
I With respect to Rev. 2 impact on the PTS scree.ning criteria, N. Randall
-l l
stated that its impact could be favorable (screening criteria reached later in plant life i.e., Zion 1, 2011 instead in year 2005) or unfaver-l j
able (screening criteria reached sooner in plant life ie..e. Palisades 1988-1992 insteadof2007usingRev.1).
Potential remedies include 1) more flux reduction, 2) recheck material properties, and 3) anneal the pressure vessel.
If the utility desires to operate beyond the screening l
criteria, the following items need to be addressed:
l I
o System changes could be made to mitigate severity of tran-4 sients, and o
Plant-specific probabilistic analysis per Reg. Guide 1.154 can be performed using better fracture mechanics and system analysis and using updated irradiation data.
I.
i Minutes / Metal Components Mtg.
5 February 18, 1088 l
l l
Implementation of Rev. 2 will be by generic letter. After publication of the guide, utility will have about 3 years or 2 plant outages to be in templiance, j
i 2.
C. Serpan, RES, lead the presentation on the status of the low flux l
embrittlement issue. He stated that the embrittlement issue may be a current or future threat to the safety of nuclear power plants due to a nore rapid than expected embrittlement of reactor pressure I
vessel supports as a result of Icw temperature irradiation at a low l
fluy level. He stated that this problem was identified by Stone &
Webster about mid 1978. The NRC in late 1979 agreed with the Naval Research Laboratory prediction of excessive NDT shift for North Anna shield tank materials. At about the end of 1983, the NRC stated that proposed safety issue 15, Radiatien Effects on Reactor t
vessel Support Structures, he classified as a low priority item.
l At about the end of the year,1986, HFIR was shutdown for vessel l
embrittlemer,t analysis, i
l l
l C. Serpan provided a brief outline in an approach to resolve the l
l reactor support structure embrittlement issues, as follows:
l 0
Identify suprort structure types for all U.S. LWRs and identi-fy 1 or 2 plants most susceptible to brittle fracture and 1
I failure l
1 l
i
Minutes / Metal Components Mtg.
6 February 18, 1988 o
Strengthen the basis for low temperature, low flux, soft spectrum embrittlement trend curves by evaluating supports in decomissioned LWRs i.e., Shippingport and Belgian BR-3.
4 o
Define appropriate action 3.
C. Y. Cheng, NRR, stated that its current assessment of this issue is that insufficient data and analyses exist in order to determine l
whether the NDT temperature for any plant exceeds its operating temperature.
He stated that the existing RES program to resolve this issue is adeque.te.
4.
J. O'Brien, RES, discussed the 1) structural margins in existing PWR rcactor pressure vessel supports and 2) ability to support the i
reactor pressure vessels during earthquakes by the attached coolant piping alone.
He stated that large safety factors exist in
{
Westingbouse, B&W and CE plants, and even if the reactor pressure supports should fail the reactor coolant piping should support l
(defense-in-depth) the pressure vessel under the worst set of loading conditions including a large earthquake i.e., Diablo Canyon (SSE=0.75G).
5.
R. Cheverton, ORNL, stated that reevaluation of some LWR vessel
~
supports is underway to assess impact of recent radiation embrittlement data from HFIR, ORR, Hawthorne / Steel and the V. S.
Army. Preliminary estinate of end-of-life (32 EFPY) MDT for sahe i
I
Pinutes/ Metal Components Mtg.
7 l
February 18, 1988 7
supports at greater than its operating temperature were perfonned in the ORNL study and are listed as follows:
l l
Vendor 4NDT (O )
F Nominal Maximum l
B&W(ANO-1) 144 185 l
CE(ANO-2) 360 423 W (McGuire-1) 35' 414 GE O
16 [shownforcomparisononly]
The above data shows increasing material damage due to the following parameters:
o lower fluence rate, and o
lower radiation temperature With the above degradation information ORNL will study the structural integrity of all types of LWR vessel supports, i.e., skirt, long column, shield tank, short column and suspension.
This study will be completed before the end of the year 1988.
6.
T. Griesbach, EPRI working with similar data, except data from the U. S. Army, estimated that the maximum end-of-life NDT shift to be 0
about 200 F.
He stated that few structures are expected to have NDT greater than 200 F. at its end-of-life. He stressed that
Minutes / Metal Components Mtg.
8 February 18, 1988 e
i rore data is needed to verify embrittlement prediction methods.
With regard to reactor support structure, he stated that support i
stresses are low and mostly in compression and that no known 4
failure mechanism exists.
i 7.
W. Snack, AWL, discussad the joint NRC-DOE sponsored effort to obtain er.d test samples from the neutrcn shield tank of the Shippingport reactor.
Schedule for the effort must be coordinated with the ongoing decomissioning of the Shippingport reactor.
Samples shculd be available for testing and analysis by the sumer ot~ 1988.
P.
A. Banerjee, Stone ard Webster, presented their involvement in the I
neutron shield tank (reactor vessel support) analysis accounting
]
for lcw flux embrittlement during the mid-seventies. During that j
period, the effect of low energy neutron (less than 1 NEV) became an issue and S&W evaluated the neutron shield tank designs for this effect.
S&W study indicated that low flux erbrittlement will not effect plant safety within its design life.
S&W performed Surry life extension studies in 1985. The neutron support tank was reviewedforneutronembrittlementconcerns(highandlowenergy).
The design was found acceptable for its design life but recomended that further research to evaluated effects of low energy neutrons on carbon steel at low temperatures be perfoormed. Calculation of stresses in Surry neutron shield tank without primary loop break loading show that the support to be essentially in compression with i
Minutes / Metal Cornponents Mtg.
9 February 18, 1988 no stress exceeding 6ksi. He stated that brittle failure is unlikely at this low stress level.
Subcomittee Action The matter of Reg. Guide 1.99, Rev. 2, and the low flux ernbrittlement will be reported to tbt /CRS at the March meetinn.
NOTE:
A transcript of the teeting is available at the hRC Public Document Rone, 1717 H Street, NW., Washington, D.C., or can be,
purchased from Heritage Reporting Corporation, 1220 L Street, NW., Washington, D.C. 20005. Telephone (202) 528-48E8. All documents listed in Attachment C are available in the ACRS fi'es.
l l
ATTACHMENT A Federal Redster / Vol. 53, No. 21/ Tuesday, February 2,1988 / Noticca 2aN Asylum and Parole in the intnhtration Management Offleet, National urged to contact the above named Service, notified field offices of the new Endowment for the Arts, Washington, individual one or two days before the pro lms %is was dme by cable on DC 20506, or esil 2M/682-M33 scheduled meeting tobe addsed of any changes in schedule, ett'., which may October 30.196", as Mr. Walkinson had Marthe Jones, adnsed that the new splem of Counci/ Coordinctor. Courn7 and I'ao,]
have occurred.
rispondmg would besta Novernber &
operations. Nationof Endo wment for the Arts-Dated: January 28.1958.
W47. This new pocedun raoddies (m Doc. so-:o:s Ed 2-1-ta a 45 aml Morton W, taaMe, Opnating lestraction sa.a(e).
,u,,,,ac,.m 'bei Assistant riccutii e cirectorfa hutcat Deted: December 9,19er.
g,n, w.
Ronald A.Brooka.
[FR Doc. 86-2115 Fded 2-1-4EL 8 45 am)
NU LEAR REGULATORY Acru s Asvociate Cams.sloner.
MON En om:notiors. le'miticHon and Natu:uhection Semw, A
[FR Doc. 88-2Ws Filed 2-1-eA 4 45 aml Advisory Comtr*"ee on Reactof Safeguerds, Jt es out> committees on suaso coce mms Co W ; M M Secam Systems Rettabthty and Core ne ACRS Subcommittee on Metal Performance; Meeting NATION AL FOUNDATION 061 THE Components will hold a meeting on The ACRS Subcommittees on Scram ARTS AND THE HUMAMTfES February 1& 19aa, Room 1M8,1717 f f Systems Reliability and Core Street. NW, Washington. DC.
Performance will hold a jolnt meet:ng on Dance Adyteory Panel (Dance / Fem /
The entire meeting will be open to February 19.1988, Room 1No.171711 Video Section); Meeting public atlandaxa.
Street, NW. Washington. DC.
Pursiant to section 10(a)(2) of the The agenda for sub}ect toceting shall The entire meeting will be open to be as followa:
Federal Advisory Committee Act (Pub.
pubuc attendance.
The agtsda for subject meeting ahall Thursdad,he conclusion of businessFebruary 1& 1988-6JO an.
L 92-463), as amendd notice is hereby unt t given that a meeting of the Dance be as f#ows:
Advisory Panel (Dance /Fibn/ Video The Scbcommittee w til review Section) to the National Council on the Regulatory Guide 1S0 Revision L Friday, febtvery 19. WMM am t.mid Arts w di be held on Febnary 17 and 18 "Radiation Embntilement of Reactor the conclusnan of business 198& from Mn a.rn. 7.C0 p.m; and on Vessel Material." and other matters.
The Subcommitices will redew the February 19,1988. from 9TO am 5SO Oral statements may be presented by current status of LWR plant e erstions p m. in roo:n 716 of the Nancy llanka members of the public with the (core reload designs, etc.) as t ey impact Center,1100 Pennsylania Avenue NW.,
concurrence of the Subcomtnittee on core reactivity control eperanonal Chairman; written statements will be limits (e g ' moderator temperature Wa shington, DC. 7.20fL if time permita, a portion of this accepted and made available to the coefficients]in general, and ATWS meeting wdl be open to the pubuc on Committee. Recordings will be permitted anal) ses in particular' those portions of the O
only durinfen a transcript is being kept, f$e ub ic h on ence February 19,1938. from s.00 pm.sa0 pm for a pobcy dacession.
meeting w
,,r er
'Its remstrung sessions of this and uestione may be asked only by f the Su> committee Chairtnan: wntten meeting on Febn.ary 17 and 1& from 9D0 mem$ers of the Subcommittee,ita statements will be accepted and made a m,7.00 p m. and on February 19,1968, consultants, and Staff. Persons destrhig suitable to the Committee. Recordmss to make oral statements should notif from 9.00 am.3 00 p.ro. are for the the ACRS staff member identified befow will be permitted only during those purpose of panel redew, dacussion, p rtion: of the meeting when a evaluation and recommendation on as far in advance as practicable so that transcnpt is being kept, and questions applications fx financial auistante apbrepriate arrangements can be maA may be asked only by members of the under the National Foundatha en the uring the initial portion of the Subcommittee,its consultants, and Staff, Arts and the !!urnaniuea Act of 19G5, aa meeting. the Subcommittee, alorg with Pusons desiring to make oral amended. including information gis en in arry ofits consultants who may be statements should nottfy the ACRS staff confidence to the agency by grant present, may exchange preliminary member named below as far in advance applicanta. In accordance with the views regarding matters to be as practicable so that appropriate determination of the Chairman considered dartng the balance of th, arrangements can be made.
published in the Federal Registar of meeting.
During the Mitial portion of the i
February 13,19Nk these sessiana will be The Subcommittee will then hear closed to the pubbe pursuant to presentations by and hold discussions meeting, the Subcommittee, along with subsection (c)(41. (6) and (ellb) of with representatives of the NRC Staff, any of its consultants who may be section 552b of Title 5 United States its consultants, and other interested present, may exchange preliminary view s regarding matters to be t
Code.
persons regardig this review.
considered durma the balance of the if you need special accommndatPma Further information regarding topics due to a disability, please cantact the to be discussed, whether the meeting meeting.
Office for Special Constituencies, has been cantalled or restheduled, the The Subcommittee will then hear National Eadowmant for the //s,11CD Chairman's ruhng on requests for the presentations by and hold discussions Pennsylvania Aven'ur NW., hhh4 tan opportunity to prennt cral statements with representatives of the NRC Staff, DC 20508. 202/es:-5M iTY 202/682-and the titne allotted therefor can be its consultants, and other interested 5496 at least seven (7) dag prior to the obtalced by a peeld telephou call ta persona regarding thJs review.
meeting.
the cognizant ACRS staff member,Mr.
Further information regarding tepica Ej idio Igne (telephone 202/63k1414) to be discussed whether the meetmg Further infonwatbn with reference to p
this meeting can be obtained fmm Ms.
between e15 a m. and 5 00 pm Persons has been cancelled or reacheduled, the Yvonne M. Sabine, Adeitory Committee planntng to attend th!s meeting are Chairman's ruling on requests for the I
m
ATTACHMENT B REVISION 2 Feb.17,1988 TENTATIVE AGENDA ACRS SUBC0FMITTEE ON METAL COMPONENTS MEETINC WASHINGTON, D.C., FEBRUARY 18, 1988
?5
/8:30 - 8:45 a.m.
1.
Opening Statenents P. Shewmon, Chairman sn 8:45 - 12:00 Noon 2.
NRC Presentation of Reg. Guide 1.99, (15 Min. Break at Rev. 2, N. Randall 10:00 a.m.)
Regulatory Context & Safety Significance Tech. Basis for Rev. 2 - Comparison with Rev. I and the PTS Rule Response to Public Coments Impact of Changing from Rev. I te Rev. 2 as the Besis for P-T Limits Impact of Amending the PTS Rule to be Consistent with Rev. 2 UIh'CH 12:00 - 1:00 p.m.
wm y
3.
NRC Presentation en Status of Low Flux Embrittlement
\\ 0 ', a i 400 - 1:10 p.m.
Overview Chuck Serpen 1:10 - iMO p.m.
Technical Problem Dick Cheverton R ).
2:10 - h40 p.m.
NRP. Views C. Y. Cheng l
\\7L 4:40 - 3:00 p.m.
Structural & Fracture John O'Brien, t'6
\\;iT
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BREAK l
3:00 - 3:15 p.m.
3:15 - 3:20 p.m.
Pesearch Chuck Serpan
<nc 3:20 - 3:35 p.m.
Shippi'ioport Program BillShack4 i
' 3:35 - 3:55 p.m.
ORNL Work Dick Cheverton U s!
t ri i
INDUSTRY INPUT i
3:55 - 4:25 p.m.
Stone A Websters Brad Dodson/Banerjee j
Involvement no
-4r25 - 4:45 p.m.
EPRI Involvement Tim Griesbach 4:55 - 5:00 p.m.
P.0MMENTS & ADJOURN ATTACHMENT I l
l l
ATTACHMENT C o
t e
LIST OF DOCUMENTS FEBRUARY 18, 1988 METAL COMP 0NENTS SUBCOMMITTEE MEETING 1.
Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Recctor Vessel Materials presented by P. N. Randall 2.
Ltr. to P. Shewmon, ACRS Member from A. L. Lowe, B&W,
Subject:
Reg. Guide 1.99, Rev. 2, dated Feb. 16, 1988 3.
Low Temperature Low Flux Embrittlement of Reactor Support Struc-tures presented by C. Z. Serpan, Jr., NRC, RES
]
4.
Radiation Embrittlement Rate Effect Deduced from HFIR Surveillance Prc3 cam and Application to Evaluatiun of LWR Vessel Supports presented by R. D. Cheverton 5.
Neutron Shield Tank Sampling Program - W. J. Shack, Argonne Nation-j al Lab., R. Allen, Pacific NW Lab., D. Carlson, Sandia Lab.
6.
Radiation Effects en Reactor Vessel Support Structures presented by T. J. Griesback, Electric Power Research Institute 7.
Reactor Vessel Supports presented by Stone & Webster, Banerjee 1
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