ML20214S000

Summary of 861016-17 Meetings W/Util,Bnl,Pickard,Lowe & Garrick,Inc,Westinghouse & Fauske & Assoc in Brookhaven,Ny Re Emergency Planning Sensitivity Study.List of Attendees & Viewgraphs Encl

ML20214S000
Person / Time
Site:	Seabrook
Issue date:	11/26/1986
From:	Long S Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8612080161
Download: ML20214S000 (41)

Text

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',' Wh 3# %,#'o, UNITED STATES I

[; , 'j NUCLEAR REGULATORY COMMISSION wassincrou. o. c. 20sss s, .-

NOV 2 61966 Docket No. 50-443 APPI.ICANT: Pub'lic Service Company of New Hampshire FACII.ITY: Seabrook Station, Unit 1

SUMMARY

OF MEETINGS HEl.D ON OCTOBER 16 and 17, 1986 TO DISCUSS SEABROOK EMERGENCY Pl.ANNING SENSITIVITY STUDY

REFERENCE:

Seabrook Station Risk Management and Emeroency Planning Studv and Seabrook Station Emergency Planning Sensitivity Study.

Submitted by letter from John DeVincentis to Vincent Noonan, dated July 21, 1986.

Publicly noticed meetings were held on October 16-17, 1986, at Brookhaven National 1.aboratory in New York. The NRC staff was represented by members of the Division of PWR l.icensing-A and Brookhaven National I.aboratory (BNI.). The Applicant was represented by members of the Public Service Company of New Hampshire, Pickard,l. owe and Garrick, Inc., Structural Mechanics Associates, Fauske & Associates, and Westinghouse Electric Corporation.

The purpose of these meetings was to facilitate the NRC's ongoing review of the information in the referenced documents. There were two distinct sub.jects covered by two separate working groups. A group which focused on details of containment strength calculations met both days. A second group met only on October 17 to discuss convective transport of heat from the melting core to other parts of the reactor coolant system (RCS), l.ists of attendees are included as Enclosures 1 and 2.

The group dealing with containment strenath issues discussed in detail the containment strength calculation report prepared by Structural Mechanics Associates (SMA) for Pickard,l. owe and Garrick, Inc. (Pl.G). The SMA report was incorporated into the probablistic safety analysis study performed by Pl.G . The entire meeting was devoted to the discussion of the SMA report by M

. P-O

e 4

.?-

oxamining the methods used, the underlyina assumptions regarding the variability estimates and results obtained. A number of items of clarification needed by the BNL staff were discussed, and these action items were later forwarded to the licensee in a letter from Steven M. Long to Robert J. Harrison dated October 23, 1986.

The group dealing with convective transport of high temperatures inside the RCS during core melt heard presentations by Westinghouse and Fauske personnel.

Physical model exoeriments at Westinghouse facilities in Pittsburgh were described, and computer modeling of the convective flow phenomena for hiah pressure core melt sequences at Seabrook was presented. The applicant concluded that the heat transport phenomena would not raise the steam cenerator tubes to a temperature sufficiently hiah to cause creep failure.

An important element of the applicant's model is the interruption and the convective transport mechanisms by the disruption of core aeometry during melt. Discussions focused on the nature of the model and the sensitivity of

• its results to its underlying assumotions. Materials from the applicants' presentation are included as Enclosure 3.

Questions arisina in both meetings were formallv submitted to the applicant by letter dated October 23, 1986, from Steven M. Long to Robert J. Harrison.

Durina a combined meeting of the working groups at the end of the second dav, it was decided to publicly announce three additional meetina dates so that additional discussions could be held, if necessarv, durina the period wnen the NRC's review is nearing completion. The dates chosen were November 6, 12 and 19, 1986.

,i -

Steven M. l.ong, Project Manaaer PWR Project Directorate No. 5 Division of PWR licensing-A

/ o Mr. Robert J. Harrison Public Service Company of New Hampshire Seabrook Nuclear Power Station cc:

Thomas Dignan, Esq. E. Tupper Kinder, Esq.

John A. Ritscher, Esq. G. Dana Bisbee, Esc.

Ropes and Gray Assistant Attorney General 225 Franklin Street Office of Attorney General Boston, Massachusetts 02110 208 State Posue Annex

, Concord, New Pampshire 03301 Mr. Bruce B. Beckley, Project Manager Public Service Company of New Hampshire Resident Inspector Post Office Box 330 Seabrook Nuclear Power Station Manchester, New Hampshire 03105 c/o US Nuclear Regulatory Commission Post Office Box 700 Dr. Mauray Tye, President Seabrook, New Hampshire 03874 Sun Valley Association 209 Summer Street Mr. John DeVincentis, Director Paverhill, Massachusetts 01839 Engineeri,ng and I.icensing Yankee Atomic Electric Company Robert A. Backus, Esq. 1671 Worchester Road O'Neil, Backus and Spielman Framingham, Massachusetts 01701 116 lowell Street Manchester, New Fampshire 03105 Mr. A. M. Ebner, Project Manager i United Engineers & Constructors William S. Jordan, III 30 South 17th Street Diane Curran Post Office Rox 8223 Parmon, Weiss & Jordan Philadelphia, Pennsylvania 19101 20001 S Street, NW Suite 430 t

Washington, D.C. 20009 Mr. Philip Ahrens, Esq.

Assistant Attorney General State House, Station #6 Augusta, Maine 04333 Carol S. Speider, Esq.

Office of the Assistant Attorney General Environmental Protection Division Mr. Warren Fall One Ashburton Place Public Service Company of Boston, Massachusetts 02108 New Hampshire Post Office Box 330 0. Pierre G. Cameron, Jr., Esq.

Seabrook, New Hampshire 03874 General Counsel Public Service Company of New Hampshire Seacoast Anti Pollution league Post Office Box 330 Ms. Jane Doughty Manchester, New Hampshire 03105 5 Market Street Portsmouth, New Hampshire 03801 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Diana P. Randall 631 Park Avenue 70 Coll' ins Street King of Prussia, Pennsylvania 19406 Seabrook, New Hampshire 03874 Richard Hampe, Esq.

New Hampshire Civil Defense Agency 107 Pleasant Street Concord, New Hampshire 03301 '

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Public Service Company of Seabrook Nuclear Power Station New Hampshire cc:

Mr. Calvin A. Canney, City Manager Mr. Alfred V. Sargent, City Hall Chairman 126 Daniel Street Board of Selectmen Portsmouth, New Hampshire 03801 Town of Salisbury, MA 01950 Ms. Letty Hett Senator Gordon J. Humphrey Town of Brentwood ATTN: Tom Burack RFD Dalton Road U.S. Senate Brentwood, New Fampshire 03833 Washington, D.C. 20510 Ms. Roberta C. Pevear Mr. Owen 8. Durgin, Chairman Town of Hampton Falls, New Hampshire Durham Board of Selectmen Drinkwater Road Town of Durham Hampton Falls, New Hampshire 03844 Durham, New Hampshire 03824 Ms. Sandra Gavutis Charles Cross, Esq.

Town of Kensington, New Hampshire Shaines, Mardrigan and RDF 1 McEaschern East Kingston, New Hampshire 03827 25 Maplewood Avenue Post Office Box 366 Portsmouth, New Hampshire 03801 Chairman, Board of Selectmen RFD 2 South.Hampton, New Hampshire 03827 Mr. Guy Chichester, Chaiman Rye Nuclear Intervention Mr. Angie Machiros, Chairman Committee Board of Selectmen c/o Rye Town Hall for the Town of Newbury 10 Central Road Newbury, Massachusetts 01950 Rye, New Hampshire 03870 Ms. Cashman, Chairman Jane Spector Board of Selectmen Federal Energy Regulatory Town of Amesbury Commission Town Hall 825 North Capital Street, NE Amesbury, Massachusetts 01913 Room 8105 Washington, D. C. 20426 Honorable Peter J. Matthews Mayor, City of Newburyport Mr. R. Sweeney i Office of the Mayor New Hampshire Yankee Division  !

City Hall Public Service of New Hampshire '

Newburyport, Massachusetts 01950 Company i

7910 Woodmont Avenue l Mr. Donald E. Chick, Town Manager Bethesda, Maryland 20814 Town of Exeter 10 Front Street Mr. William B. Derrickson Exeter, New Hampshire 03823 Senior Vice President Public Service Company of i Mr. Richard Strome. Director New Hampshire l State Civil Defense Agency Post Office Box 700, Route 1 State Office Park Scuth Seabrook, New Hampshire 03874 107 Pleasant Street Concord, New Hampshire 03301 l

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ENCL.0SURE 1 ATTENDANCE SEAPR00K CONTAINMENT STRENGTF' OCTOBER 16-17,1986 NAME AFFil_ T ATION Goutam Racchi NRC/NRR/PWR-A Kamal Bandy 00adhvay BNI.

Charles Hofmayer B NI.

Howard Hwang B NI.

Paul Rezler B NI.

i Gordon Thompson Mass. Attorney Genl.

Fred Torri Pl.G Robert White New Hampshire Yankee Frank Bellini Yankee Atomic Elec Ralf Peek Univ. Cal., Berkley-Don Wesl'ey NTS i

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f ENCL.0SURE 9-ATTENDANCE S/G TUBE Fall.URE DURING CORE MEl.T OCTOBER 17, 1986 Steve f.ong NRC/NRR/DPl.A Steve.Follen Yankee Atomic Jim Moody NNY Bob Youngblood Brookhaven National I.ab '

Pete Davis PRD Consulting i David A Maidnand Asst. Prof. Mgr. YNSD Bill Cloutier f.ead Systems Eng YNSO Martin Plys Fauske & Associates i

Robert Henry Fauske & Associates Marc Kenton Fauske & Associates Bob I.utz Westinghouse Electric Mohsen Khatib-Rahbar B NI.

Trevor Pratt B NI.

Hossein Nourbakhsh B NI.

Nam Cho B N!.

Tsong-l.un Chu 8 NI.

Warren C. l. yon NRC/NRR/DPl.A/RSB.

George Bozoki B NI. f Joanne Heinz R NI.

].

4 Jae Jo B NI.

! Ken Perkins R NI.

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ENCLOSURE 3 r .

SEABROOK STEAM GENERATOR INTEGRITY ANALYSIS-Martin G. Plys Marc A. Kenton Robert E. Henry Fauske & Associates, Inc.

Burr Ridge, Illinois Peter Kirby l Westinghouse Electric Corporation

, Pittsburgh, Pennsylvania .  !

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Presented at l

Brookhaven National Laboratory Upton, New York October 17, 1986 '

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ANALYTICAL APPROACH -_

J Objective Determine the thermal resnonse of steam cenerator tubes under severe accident conditions. .

Secuences Considered Since steam cenerators must be dry to experience any slanificant thermal transients, station black-out conditions were used in the analysis.

Kev System and/or'00erator Responses Analvzed

, , ., a. Station blackout without operator actions or oump seal LOCA,

b. Station blackout with the oumo seal LOCA and no )

ooerator actions, 1

c. Station blackout with nossible onerator I actions.

d. The influence of key uncertainties.

E

t s DOSSIBLE OPERATOR ACTIONS FOR STATION BLACK 0UT CONDITIONS e Initiate steam turbine-driven cuxiliary feedwater i flow. i

. 1 e Restore emeraency AC cower, i l

e Shed all no~n-essential loads. 1

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e -- -

e Ooen the Power Ooerated Relief Valves (PORVs) when core temoeratures exceed 1200 F.

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IMPORTANT RESPONSES BROUGHT ABOUT BY OPENING PORVs AT 1200 F CORE TEMPERATURE e Deoressurize the crimary system such that accumu-lators inject water and help maintain core coolino.

. I e Deoressurize the crimary system such that stresses ~

on all primary system comconent's are substantially reduced. .

e Flow out of the PORV overrides circulation such

'T,. that high cas temperatures are not imnosed on the

,_ steam aenerators, includino the tubes.

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STEAM GENERATOR TUBE INTEGRITY CONCERNS DURING STATION BLACK 0UTS s During unmitigated station blackout secuences, the presence of high pressures and no makeup lead to strong natural circulation flows between the core and the upper plenum of the reactor vessel, e Since a loop seal exists in the pump bowls so that no flow can pass there, high temperatures in the

., upper plenum will initiate counter-current natural circulation between the steam generator inlet plena _

and the RV upper plenum, e The resulting increased temperature in an inlet pl'enum leads to natural flows out to the outlet

> 5, , plenum through some tubes and a return flow to the inlet plenum through other tubes.

e High temperatures in the inlet plenum or tubes raise concerns that steam generator tube failures could result.

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OVERVIEW 0F MAAP NATURAL CIRCULATION MODELLING e Gas and wall temperatures in primary system control volumes computed by conventional lumped parameter models: 15 gas control volumes, 17 heat sinks (two dimensional).

-- e Natural circulation flows computed by quasi-steady momentum balances and continuity equations. -

e Steam generator inlet plenum temperature computed

,.._ quasi-statically in the hot leg natural circulation

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COMPARISON OF H0T LEG-STEAM GENERATOR NATURAL CIRCULATION MODEL TO EXPERIMENTAL DATA Experimental Model Prediction Quantity Measurement. n g = 6' ng = 12 ng = 24 0 (kw) 2,43 2.0 2,6 2,9

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1, No Operator Action a, Base Case,

b. Seal LOCAs,

2. Operator Action

a. With turbine-driven AFW (nat shown-sequence

-- does not progress),

b. With failure of AFW and manual depressuri-zation of primary system when core tempera-tures reach 1200 F,

3. Uncertainty Analyses .

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_ _ _ a. Depressurization case with high core melting temperature (3000 K),

b, Base case except high core-upper plenum flow (low friction factors),

c. Base case except low steam generator flow (low fraction of tubes carrying flow away from inlet plenum).

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SUMMARY

OF RESULTS  !

l i 1. In the base case, peak steam generator temperatures l prior to vessel failure occur in the inlet plenum i and are s 850 K.

2. Seal LOCA case very similar to base case,

3. When the operator opens the pressurizer PORVs, depressurization occurs very rapidly due to the small water inventory. Accumulator discharge

-_ occurs approximately 1400 seconds later. Steam generator temperatures are low (4 700*K) prior to ~

depressurization below 7 MPa. Temperatures in-crease ofter complete depressurization but remain generally lower than the base case,

' S . ,. 4. Steam generator temperatures in the uncertainty

,__ caser. are significantly higher only in the low steam generator flow case where peak temperatures are approximately 150 K higher, E

( .

J

NOV 2 61986 examining the methods used, the underlying assumptions regarding the variability estimates and results obtained. A number of items of clarification needed by the BNL staff were discussed, and these action items were later forwarded to the I.icensee in a letter from Steven M. Long to Robert J. Harrison dated October 23, 1986.

The group dealing with convective transport of high temperatures inside the RCS during core melt heard presentations by Westinghouse and Fauske personnel.

Physical model experiments at Westinghouse facilities in Pittsburgh were described, and computer modeling of the convective flow phenomena for high pressure core melt sequences at Seabrook was presented. The applicant concluded that the heat transport phenomena would not raise the steam generator tubes to a temperature sufficiently high to cause creep failure.

An important element of the applicant's model is the interruption and the convective transport mechanisms by the disruption of core geometry during melt. Discussions focused on the nature of the model and the sensitivity of its results to its underlying assumptions. Materials from the applicants' presentation are included as Enclosure 3.

Questions arising in both meetings were formally submitted to the applicant by letter dated October 23, 1986, from Steven M. Long to Robert J. Parrison.

1 During a combined meeting of the working groups at the end of the second day, it was decided to publicly announce three additional meeting dates so that additional discussinns could be held, if necessary, during the period when the NRC's review is nearing completion. The dates chosen were November 6, 12 and 19, 1986.

Steven M. I.ong, Project Manager PWR Project Directorate No. 5 Division of PWR licensing-A PD#5 ~

St.ong:es l ft/n/86 L

g -

1 Meetino Summarv Distribution 4

ME%MCentral File NRC' Participants NRC POR

! I.ocal PDR G. Bagchi j- PD#5' Reading File S. l.ong J.-Partlow V. Nooran E. Doolittle.

0GC-Rethesda E. Jordan B. Grimes

. ACRS (10) i M. Rushbrook i

l i s.

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cc:- I.icensee and Plant Service

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