ML20133H210
| ML20133H210 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/02/1984 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2228, NUDOCS 8508090235 | |
| Download: ML20133H210 (18) | |
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Q~ f y 9/2/84 da 9Mt1 Meeting Minutes ACRS Subcommittee Meeting on Class 9 Accidents July 23, 1984 - Washington, DC The ACRS Su'bcomittee on Class-9 Accidents held a meeting on July 23, 1984, in Room 1046, 1717 H Street, N.W., Washington, D.C.
The purpose of the meeting was to meet with New York Power Authority (NYPA) to discuss their recent source term analyses for the Indian Point (IP-3) nuclear power plant. Notice of this meeting was published in the Federal Register on Friday, July 6, 1984. There were no oral or written statements from members of the public at this meeting. A complete set of meeting handouts is available at the ACRS headquarters in the ACRS Files.
Included with these minutes are: Attachment A - Federal Register Notice; Attachment B - Meeting Schedule; Attachment C - Attendance List; and Attachment D - Reference List.
Meetino Highlights, Agreements, and Requests 1.
W. Kerr opened the meeting by stating he comended NYPA for the initiative and energy they have shown in addressing the source term issue. He stated he encourages the industry to take this type of initiatives and looked forward to reviewing NYPA calculations and results.
2.
H. Specter gave a brief introduction. He stated that the risk dominant sequence for latent fatalities is a slow overpressuri-zation accident and the risk dominant sequence for early fatalities was the Event Y scenario. NYPA did the source term analysis only for the overpressurization accident.
For the Event V scenario they looked for ways to decrease the probability of the event.
He noted that their sensitivity studies indicated that a factor of ten reduction in WASH-1400 type source terms with the current evacuation model led to a 400 factor reduction in early fatalities.
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Class 9 Meeting Minutes 2
July 23, 1984 If the factor were 15 with evacuation, there would be no early fatalities and if the, factor was 45, there would be no early fatalities assuming the worst weather conditions and no evacuation.
3.
H. Specter said they assumed that the containment failed at 141 psia.' For their source term calculations they assumed a.1% per day leakage before failure and that the containment failed at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the accident.
4.
C. Siess inquired if NYPA had considered other containment failure models such as a pressure-temperature time dependent leakage rate.
He noted some studies have indicated the level of leakage may be large enough to preclude the failure of the containment structure.
C. Siess stated NYPA should review the recent NRC investigation of containment failure modes. He thought it would be useful in their work.
5.
P. Davis stated that the NYPA report addresses only four of the fission products. He asked how did NYPA assure themselves that the other fission products were not of risk significance.
6.
W. Kerr asked if any of this source term analysis was available during the IP-3 hearings.
H. Specter stated almost all this analysis was performed after the hearing.
W. Kerr asked where does NYPA feel they are with respect to source term calculation for IP-3.
H. Specter stated NYPA beleives they have sufficient analyses to make a decision.
If they can demonstrate that the containment does not fail early, they will get very low release fractions.
7.
W. Kerr noted a good base case for their codes might be a TMI-2 like scenario.
H. Specter stated this might be interesting but NYPA has no plans to perform such a calculation.
Class S Meeting Minutes 3
July 23, 1984
- s, 8.
P. Bieniarz stated they have made the following code modifications:
Combining of MERGE, CORSOR, and TRAP-MELT into one code.
a.
b.
S,ynchronization of event timing in all codes.
Inclusion of model to account for heat losses from primary c.
system.
d.
Inclusion of a rigorous fission product haating model.
Implemented a resuspension model.
e.
4 1
f.
General coding modifications to improve running efficiency
)
(vectorization) and minimize manual input.
Their conclusions are as follows:
a.
The source terms they now calculate are a small fraction of the source term calculated in the previous studies (IFPSS and WASH-1400),
b.
The mode and exact time of late containment failure is not critical due to processes which remove fission products from the atmosphere within 6 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the accident.
I c.
The need for further research into primary system retention of fission products appears to be questionable.
d.
The fission products released from the primary system and from the melt by core-concrete interaction are readily removed by natural processes occuring in the containment. Condensation
Class 9 Meeting Minutes 4
July 23, 1984 of volatiles onto aerosols, agglomeration, and gravitational settling dominate the removal processes.
e.
Iodine and cesium are still the major contributors to early a,nd latent fatality risks. Environmental releases are not sensitive to primary system phenomena model (e.g., presence of insulation, fission product heating, log normal or " bin" aerosol model).
f.
Fission product heating of structural surfaces in the primary
~
plays an important role.
g.
This heating probably leads to system failure and subsequent primary system depressurization prior to lower reactor head failure.
P. Bieniarz said they do not want to duplicate NRC efforts. They expect to capitalize on the work being done elsewhere. They did not validate the codes.
M. Bender stated NYPA needed to study the phenomena more rather than depending on the NRC Staff to verify it.
9.
M. Bender, M. Corradini and W. Kerr stressed that NYPA needed to validate the models in the codes.
For instance, M. Corradini inquired if NYPA verified that the codes balance mass and energy.
W. Kerr asked what confidence NYPA had that the codes could predict core behavior. He is concerned about the industry's propensity to verify codes with another code. He agreed that it is important to know that codes predict the same results, however, he stressed codes can only be verified by studying the phenomena. He noted the logic of picking the " conservative" model is questionable. He.
stated that to be conservative one must know the answer, ignorance is not a synonym for conservatism.
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Class 9 Meeting Minutes 5
July 23, 1984 i,
10.
C. Siess asked could the code handle a pressure-tamperature time dependent leakage rate.
P. Bieniarz answered yes.
11.
W. Kerr asked whether NYPA has decided what is the correct source term to be used for decisions.
H. Specter stated for IP-3 the source term is relatively code independent. That is the magnitude of the source term that NYPA is calculating for early fatalities is low enough that they feel they can tolerate a fair amount of uncertainty and still be below an early fatality threshold.
P.
Bieniarz stated they will incorporate new data as it appears but they believe with calculated releases so low even an increase by a factor of 1000 in the source term would not increase consequences significantly.
12.
W. Kerr stated he was concerned that the conclusions reached today seem reasonable but the uncertainties are still large and we may have neglected something, as examples he mentioned:
10 to 15 years ago the assumption was that given the amount of a.
water available, given the fact that the iodine plates out, the likelihood of a large release out of containment is very low. Today we go through sophisticated codes, determine that iodine is readily dissolved in water, absorped on surfaces, and readily plates out however, the confidence in the calculated release fractions are no better thar, they were.
The uncertainties need to be addressed.
b.
The current concensus is that large dry containments don't leak much and not much is going to be released. About ten years ago the consensus was if you could resolve the large LOCA problem, reactors would be safe. Today no one is worried about large LOCA's but everybody is looking at small LOCA's.
Could we have missed something that 5 years from now is going to change our perspective of reactor safety.
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Class 9 Meeting Minutes 6
July 23, 1984 13.
R. Deem stated that NYPA did not do the source term analysis for the Event V scenario.. Rather they performed various analyses to determine what could be done to decrease the probability of the event. Based on their analyses, by strengthening the one overstressed support outside the containment building and given that their design allows time (hours) for operator actions, the Event V has negligible risk production potential at IP-3.
Meeting Adjournment.
NOTE:
ADDITIONAL MEETING DETAILS CAN BE OBTAINED FROM A TRANSCRIPT OF THIS MEETING AVAILABLE IN THE NRC PUBLIC DOCUMENT ROOM, 1717-H STREET, N.W., WASHINGTON, D.C., OR ONE CAN BE PURCHASED FROM FREE STATE REPORTING, 99 CATHEDRAL STREET, ANNAPOLIS, MD.
21404MDOFFICE(301)268-0232ORDC0FFICE(202)261-1902.
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Fedard Raistir / Vol. 49. No.131 / Friday. July 6.1984 / Mtic;s 2%62 __
- n..- f re.g orta%., of low.
knc. !e.fga f i,nd e nsJ.m permanently unless terminsted by either
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p.uty on thirty day s prior written notice.
cf this mponubii.t). the Commission packaging and transpocation Date th:s 7th do of June 1964 at Clen r;gub. :mLt.s si resiew of the regulations Sch functions as are El:yn. it g
tramp.: t.,,a pNsrams ofits licensees perforrned by the St4'e pursuant to g,,,, g g,pp,,'
includmg the licensees' procedures for hereto shall be perfonned without cost Regiono1Adminisrmror.
qu':hty assurance. packaging. marking.
or expense,to the Commission, except For the State ofIlhnois:
for situations where NRC finds it labeling and loading of vehicles This -
appropriate to proside training to the Dor. Etchison.
tansportation program review usually Dated this11th day oflune tes4 at State.
has bon found adequate to ensure 2.ne authority to inspect NRC Spring'ield. IL
- licerme compliance with the licensees pursuant to the preceding ini om. -i www Corn::. 'en's ten !ations regardinglow-paragraph is hmited to the licensee's a coo, 7,,
levelrd.xt.w 3aste packagirg and low. level waste pachging and transpcrut:cn uhout the need for transportation procedures.
Como uion inspection of each
- 3. In taking any alan authorited Advisory Committee on Reactor Indiw!: C W ent.
hereunder, the St 4!. shi,11 call undert.d e Safeguards, Subcommittees on Ctacs-Under Sm. : Sli. of the Atomic to amend or tes eke Ce~nission 9 Accidents andInd:2n Point;' Jesting Energy.irt Of..'4 as amndad. the hcer:ses. His Men r.aJam. hewes er. % ne ACRS Subcommittees on Class-9 Commm.cn in c.:ry mg oat its licensmg shall not be cons.ruca to preclude the Accidents and Indian Point will hold a and reg:.!. tory respunsibdit:es under tne State from emising any authonry cornbined meeting on July ?.3.1964. In Act is suthorized to enter mto M;moranda of Understandmg lawfully available to it under its own Room 1048. at 1717 H Street NW.
law s.
(:greements) with any State to perform
- 4. Efforts will be made by both parties Washington. DC.
Inspections os other functics on a to avoid duplicalise enforcement action he entire meeting will be open to cooperative basia as the Commission against an NRC licensee for the same public attendance.
dams appropriate While the violation. Tiowev er, this is not meant to The agenda for subject meeting shall Comm:ssion does not conduct on. site preclude appropriate complementar7 be as follows; inspecticas of every low.!: el wa ste actions foe the same violation. such as Monday. luly 23.1984-4.30 a.m. Until shipment of its licensees. it desires to termination of a user permit by the State the Conclusion of Business foster the goals ef the Waste Policy Act and NRC enforccment action.
cnd the State ofI"inois.
- 5. Nothing hercio shall be deemed to The Subcommittees will discuss New Accordingly. th:s Memorandam of authonze the State toinspect or York Power Authenty's deseloprnents in Understand:ng between the State of otherwise enter the pren ises of a v
.% 37.cce term naa r.d the I-dian
!!!m. y gthe NvC estabhsheseeab.e proced;res whereby licensee of the Comm:ss:on wh:cn is a Pu:nt PRA with rep d to the severe f
rnut...>
Federalinstromentaldy without m' Adent pche.
the S-9. Arm msycnon funen... f or end en bNr of tre pnor consent of heensee Oral sta:em'ents may be presented by 6 Nothing herem s'a'.! be der ad t members of th aubhc w.th cor.,.~nre Cm 9 e "g:n NPC rea:!ct a :3 precludeor affect m e.y mann :ne
,f 9, Subcommittee Chah c "en m-
- ccrv n fa:. tra uc i authonty of the Cor.:.mn 6,,a:orm statements wdl be accepted and inade r
e m es-i rads.- we e any or allof the funct.uns descr Sed available to the Committee. Recordm8a ha.6 cb> aped be%n le Commission and the State as follows:
herem.
"ill be permitted only dunng those
- 1. The Commission hereby authorizes
- 7. Nothing herein is intended to Portions of the meeting when a the State to perform. for and on behalf restrict or expand the statutory
'ranscript is being kept. and questions authonty of NRC or the State or to affect may be asked only by members of the of the commission. the fo!!owing functions with respect to low. level or vary the terms of any agreement in Subcommittees. their consultants, and radioactive waste as defined in Section effect under the authonty of Section Staff. Persons desiring to make oral 274b. of the Atomic Energy Act of1954.
statements should notify the ACRS staff 2(18} of the NuclearWaste Policy Act of
- as amended.
member named below as far in advance 1982. in the possession of Commission
- 8. Nothing herein shall be deemed to as practicable so that appropriate licensees located within the Stater permit the State to impose packagmg or arrangements can be made.
a (a} Inspections to determine compliance with the Commission's rules transport standards beyond those During the initial portion of the containedin Federal regulations.
meeting.the Subcommittees. along with and regulations regarding the packaging
- 9. De principal NRC contact under any of their consultants who may be cnd transportation of low-level w aste this Memorandum of Understanding Present, will exchange preliminary destined for disposal at a commercial shalf be the Emergency Preparedenss views regarding matters to be low-levelradioactive waste disposal and and Radioicgical Safety Branch considertd during the balance of the, Cte and Chief for reactor ficensees and the (b) Notification of Commission Materials and Safeguarde Branch Chief The Subcommittees will then hear meeting.
licensees and the Commmission in or materials licensees The principal presentations by and hold discussions writing of any violation of Commission State contact shall be the Manager.
with representatives of the NRC Staff.
regulations disclosed by such.
Office of Waste and Transportation their consultants. and other interested inspections. All enforcement action Management.
pursuant to this Subagreement resulting
- 10. This MOU shall b'ecome effectivepersons regarding this review.
Further information regardmg topics from such inspections will be upon sigrdng by the Director.
undertsken by the Commission.
Department of Nuclear Safety. State of to be discussed. whether the meeting ne Commission does not normally has been cancelled or rescheduled, the evaluate the State's ability to perform Illinois. and the Regional Administrator.
Chairman's ruling on requests for the.
such functions. however, the State Region III. Nuclear Regulatory opportunty to present oral statements Commission and shall remain in effect agrees to utilize personnel I.
9 Tcdcral R; gist;r / V21.,49. Nb.131 / Frid y. July 6,1984 / Notices 27863 l
cod the time allotted therefore c:n be issued at Bethe:de. M:r3 and, this 29th day and forms whkh sh1ll be followed by 1
ebtained by a peraid telqhone call to of June.19e4.,
necuhn agencies * * *.
tha cognitar.t ACRS staff raember. Mr.
Robert M.Laso.
The proposed policy ! citer:(a)
/
Alan B. Eng (tch phone 202/634-3267)
Act.ng ChiefAdministrative/udge. Atomic Designates the Federal Acquisition between 815 a m. and 5.00 p.m edt.
Safety andlicensieg Soonf Punel.
Regulations System as the single system I" Da **-1W**-**
8'8 8=1 or Government wide procurement Dated ju?y E 1964 regulations referred to in the OTPP Act:
N"'c C 05 "*
M mon w. LibarLN.
Assisica:Leem e Dimin or project (b) requires certain information flow in the FAR System: (c) requires that issues g,,j,,,d iw i.,.s.
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OFFICE OF MANAGEMENT AND on which DOD. GSA and NASA are BUDGET unable to agree be referred to the in om g,,, e,,, _,,
Administrator for resolution; and (d)
}.
Office of Federal Procurement Policy requires that decisions not to develop, -
FAR coverage on issues affecting IDock:t No. 43-2061-SC; ASLBP No.84*
Proposed Policy Letter on the Federal members of both the Defense Acquisition Regulations System Acquisition Regulatory Council and the 5c2-01 SC)
Civil Agency Acquisition Council Ke'rr-McGee Chemical Corp.:
actNev: Office of Management and (leaving such issues to be covered in.
E;tablishment of Atornic Safety and Budget.
agency supplementing regulations) shall Licensing Board act ow: Notice for comment.
be referred to the Administrator.
Public Meeting: A public meeting, for
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Pursuant to de!egaticn by the suuuany:The purpose of this notice is Commission dated Decernber 29.1972.
to solicit the views of Federal agencies the purpose of providing en opportunity published in the Federal Register. 37 FR and the private sector on a proposed for interested parties to present their views in person,is scheduled ta be held 28710 (1972). and il 2105. 2.700 2.702.
OFPP policy letter on the Federal In Room 2008. of the New Executive 2.714,2.714a. 2.717 and 2.721 of the Acquisition Regulations System.
ce Bu%ng. on August 2, M. at
' Commission's R. gulabons, all as cATE:Comrnents are due on or before 10.00 a.m. Any one interested in making emended.an Atornic Safety and A"USIII N '
a present.etion or in attending the Licensir.g Esard 4 b*.g ei abhshed in t
the following p-
/ g h..n::dct an3 FC"'"E mt"1" ^
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meetinp th~*d cc:...a Erp.:ct Davis decide an Avn" - dD-9d 'cr
%.c Office of Fece r.!
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3, Cc:wr. Aprm and 1-tcrested West' rut Any overv Artotr.The parties a in.ted to comment on this Kart McGee Cr.;r.c.l Co pvattun g. d Fed d L e
-d P 4 promd Wm le" *. Comments 11 est CiG cr ke Ect!! e T.....
Art th.b. L ob;" < enended by Pub.
phr.utd b fer. var:'
ta Wilhm Source Marctic! L. een.'s v. ST.4 x, L M and T b. L W191)prosides,in Mcst CLu ofi 6 cr ipr curement (Kress CreeA Deconicmirefienj part. the ic!!owing:
Policy. OMD. 726 ].ckson Placc. NW.,
Sun n 3A the tens smgle system of WasWom E m on deh This Board is being established Gose. rent. wide procure:nent terutat ons-August 17.1984. Mr. Mara,st may be i
meansiA)a s a u men wide.
c ntacted by phone on (202) 395-3300.
fun 2 281984 i Ean rd r o procurement reFulation issued and Dated June:5. M64 Sh ;w Cause. enasseed on March 2.1964. by mainteired jomtly by the General Sersices
- I I "'"8 h
th2 Director of the OfBce of Nuclear Admm:stranon. the Department of Defense.
AssociateAdminnimrw/wMicy Msterial Safety and SafeFuards which and the Natanal Aeronsubcs and Space D'reloPment ordered the Kerr McGee Chemical Admmistranon * *
- and (B1 agency Corporation t'o show cause why it acquisiter repletions implementma and OFPP Policy Letter 84 should not be repred to take 'certain sur7'ewnuns the coseminent. wide To the liends of Esecutive Departments FM ;*'~4 "* "i"I* h " * * **
and Estchhshments cetions with resped tu the c!eanup of r.tdiologica!!) contaminated areas in
')r*au'e^t o $$"*' j em
Subject:
Federal Acquisition Regulations l
d p.
pc T
e d leadership in the dne!opr ent of System cnd along Kress C rck and the D.: Pacs-e
' : rent systems of the esecuthe 1.Parpmer'lle pu pere of ttis Policy River. % est Crnrage. !!hnois. 49 l'P 929 Letter is to impicment ccrtain (March 12.1scA).
rs,,s.
The Board is con 7tised of the
'. : San e(dl ne functions of the requirements of the O*~ ice of Federal fillcwing administratis e judges:
trator shall include-(11 providmg Procurement Pohey Act (Pub. L 93-400 hahbshm nt.
as amended by Pub. L 90-83 and Pub. L bhn H. Frye. III. Chairman. Atomic
((e. sgenci 96-191) concerning the establishment.
Safety and Licensing Board Panel.
deu!.; ment and maintenance of the single.
development and mein'encnce of the U.S Nuclear Regulatory Commission' sp. cf simphfied Govemment. wide single system of simpl.hd Cosernment-pror.s ment regulations and resolving Washington, D C. 20555 dJr,*ences among the executive agencies in wide procurement regulations. It also l
Dr. Peter A. Morris. Atomic Safety and the de ulopment of simphf;ed Gosemment-rescinds and replaces Policy Letter 30-5 Licensing Board Panel. U.S. Nucleat wide procurecient regulations. procedures dated July 10.1980.
and forms.
- 2. Authorityr This Policy Letteris Regulatory Commission. Washington.
Se: tion 6(bl.In any instance in which the issued pursuant to Secuan 6 of the ~
(,
D.C.205T.5 Adm;natrator determines that the DOD.
Office of Federal Procurement Policy li -
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Act' Act)-
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ACRS CLASS-9 ACCIDENTS SUBCOMMITTEE MEETING JULY 23, 1984 - WASHINGTON, D.C.
- TENTATIVE SCHEDULE ***
PRESEl'TATION ACTUAL TIME TIME SPEAKER W. Kerr 10 Min.
8:30 am 1.
Chairman's Opening Statement H. Specter 20 Min.
8:40 am 2.
Intreduction NYPA historical Background a.
b.
Ider.tification of Risk Lcminant Sequences Earlier Source Term c.
Efforts d.
Other Organization's involvements 135 Min.
9:00 am 3.
Presert NYPA's Source Term Efforts Identification of Codes a.
Used b.
Improvements Made to Codes c.
Ar.alysis of TMLB Sequence d.
Analysis of Pump Seal Sequence 15 Min.
10:30 am
........** BREAK **********
10:45 am 3.
Continue 15 Min.
11:30 am 4.
Health and Economic Consequences 45 Min.
11:45 am 5.
Interfacing Systems LOCA 30 Min.
12:30 pm 6.
Conc 1usion 60 Min.
1:00 pm
- LUNCH ****+*****
F. Rowsome 180 Min.
2:00 pm 7.
Discussions with the NPC Staff on Indian Point PRA Review.
15 Min.
3:30 pm
- * * * * * * * *
- BRE A K * * * * * * * * *
- 3:45 pm 7.
Continue 5:00 pm
- ADJOURNMENT *****
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1 ATTACHMEtlT D I
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4 Reference List:
1.
Memorandum from A. Wang to W. Kerr, " Project Status Report for the ACRS Class-9 Accidents Subcommittee Meeting, July 23, 1984 Washington, D.C.."
dated July 13, 1984.
2.
" Source Term Safety Assessment," New York Power Authority and Risk Management Associates, dated July 1983.
3.
Memorandum from M. Bender to W. Kerr, " Commentary on IP-3 " Source Term Safety Assessment"," dated July 27, 1984.
4.
Memorandum from M. Corradini to W. Kerr, " Comments on the ACRS Class-9 Committee Meeting - July 23rd", dated July 31, 1984.
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