ML20206J291
| ML20206J291 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 01/31/1985 |
| From: | Khatibrahbar BROOKHAVEN NATIONAL LABORATORY |
| To: | Lyon W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20205K769 | List: |
| References | |
| CON-FIN-A-3778, FOIA-87-7, RTR-NUREG-CR-4540 NUDOCS 8704160064 | |
| Download: ML20206J291 (137) | |
Text
{{#Wiki_filter:_ h BROOKH, WEN NATIONAL LABORATORY { { {. { ASSOCIATED UNIVERSITIES, INC. Upton, Long Island. New York 11973 Departmentof NuclearEnergy (516) 282x 2626 FTS 666' January 31, 1985 Mr. Warren Lyon ' Reactor Systems Branch Division of Systems Integration U.S. Nuclear Regulatory Commission Mail Stop P-1132 7920 Norfolk Ave. Bethesda, Maryland 20814
Dear Warren,
Enclosed please find a copy of a BNL technical report entitled, "Prelimi-nary Review and Evaluation of the Seabrook Probabilistic Safety Study," by M. Khatib-Rahbar, A. K. Agrawal, H. Ludewig, and W. T. Pratt. This draft report satisfies the Level 1 review milestone as defined under Subtasks I.3 and 1.4 in the 189, Review of the Probabilistic Risk Assessment for the Seabrook Nu-clear Power Plant (FIN A-3778). If you have any questions on the report, please don't hesitate to call me or any of the other authors. Very truly yours, Y Mohsen Khatib-Rahbar Engineering & Risk Assessment Division MKR:tr Encl. cc: W. Y. Kato (w/ enclosure) R. A. Bari " " W. T. Pratt " J. Rosenthal B. Sheron j'c.ZR -E7- 7 8704160064 870409 PDR FOIA E/ / PDR SHOLLYB7-7
STATE CF NEW HAMPSHIRE EXECUTIVE CEPARTCENT how Haanpshire Cml Defense Agergy State Office Park Soiath SZ ICT Pleasant Sueet Corn ced. he Harnpshire 0330t 603#271 2231 1400452 3792 '
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JOHN H. SUNUNU Governor " JMES A.SAGQlOTES Deputy Detector April 4, 1986 Mr. Henry G. Vickers, Regional Director Federal Emergency Management Agency Region 1 J.W. McCormack Post Office & Courthouse Boston, Massachusetts 02109 *
Dear Mr. Vickers:
Enclosed please find a copy of the sixth and final Progress Report of the i Evacuation Time Estimate prepared by KLD Associates, Inc. I am informed by Mr. Lieberman that these Progress Reports, in fact, will constitute chapters in the final report and that the final conclusions will not vary from the previously submitted materials. Accordingly, I am informing you at this time that the Evacuation Time Estimate prepared by KLD Associates, Inc. is submitted formally as part of the New Hampshire Radiological Emergency Response Plan (RERP). As you are aware, we have already begun incorporating the results of the KLD study into the REHP and we will continue to review our planning efforts to determine if any additional modifications are.necessary. Given the duplicate nature of the Progress Reports submitted and the final report, we suggest, that for review purposes, FEMA refer to those Progress Reports Nos.1-6
- already submitted.
1 Thank you for your assistance. Sincerely, \ - Richard H. Strome Director RHS/sjc cc: Dana Bisbee jj _ g _ 7 f/f f renerewncv Mananonwnf for No'w Harornhire
i STATE OF NEW HAMPSHIRE EXECUTIVE DEPARTMENT New Hampshire Civil Defense A0ency siete omee para soum ior pies.ent sir.e ;. Concord New Hampshire 03301 j 803 271 2231 14008524792 JOH06H.SUNUNU RICHAAD H. STROME m, Duector JAABES A.SAGGIOTES Deputy Director April 16, 1986 Mr. Henry G. Vickers, Regional Director Federal Emergency Management Agency Region I - J. W. McCormack Post Office & Court House Boston, Massachusetts 02109
Dear Mr. Vickers:
Enclosed please find copies of tne following information to be incorporated in,to New Hampsnire's Submission of the Radiological Emergency Response Plans for the Seabrook Station Emergency Planning Zone:
- 1) KLD Progress Report C
- 2) A Revision to DPHS Procedures
- 3) Rockingham County Complex Procedures These documents constitute tpdated and revised material tnat already is contained in the RERP.
Sincerely, A/- ,.% _
, /f f L Richard H. Strome Director RHSMWelm Enclosure cc: D. Bisbee, Asst. A.G. .
32128 pxH 7 5/M Emergency Management for New Hampshire
{ .
?- .E **g,E,"g THE STATE OF NEW HAMPSHIRE 8EN3,7 " ^55 87g,7 Al m CENER R DEPLTY ATTORNEY CENERAL ASSISTANT ATTORNEYS GENERAL BRUCE L kBOHL LESLIEJ LUDTKE CEORGE DANA 31$8EE j ASSOCIATE ATTORNEYSCENERAL BRIAN T TOCXER J t FK EN!K JErrREY R 500% ARD INVESTIGA1DR -
CHRISTOPHER T. DOM 1AN PARALEGAL TARA BICKFORD BAILEY THE ATTORNEY GENERAL ENVIRONMENTAL PROTECTION BUREAU STATE HOUSE ANNEX 26CAPntEIHREET CONCORD, NEW HAMPSHIRE 033014397 1403:271 4878 April 18, 1986
- Mr. Jonn DeVincentis, Director Engineering and Licensing Yankee Atomic Electric Company 1b71 Worchester Road Framingham, Massachusetts 01701 RE: PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE, ET ALS.
(SEABROOK STATION, UNITS 1 AND 2) NOS. 50-443-OL AND 50-444-OL: NEW HAMPSHIRE RADIOLOGICAL EMERGENCY RESPONSE PLAN SUBMISSION
Dear Mr. DeVincentis:
I have enclosed a copy of the following materials which were suomitted by Richard d. Strome to tne Federal Emergency Management Agency Region I on April 16, 1986, and which, as he indicated, are to be included in the New Hampshire Radiological Emergency Response Plan for Seabrook Station:
- 1. KLD Progress Report No. 7.
- 2. A revision to DPHS Procedures, including replacement and new appenaixes to the DPHS Procedures. The revisions to the DPHS procedures relate primarily to a modification of the responsibilities for coordinating tne decontamination center supervisors. " Housekeeping" changes have also been made to these procedures. The revised appendixes to the DPHS procedures have resulted from an update of those appendixes. Three new append 1xes have been added. An instruction sheet on how these DPHS materials are to be inserted in Volume 4 of the State RERP is provided.
pew 2P7 _ E/2e
s - v Hr. Jonn DeVincentis, Director April 18, 1986 Page Two.
- 3. Rockingham County Complex Procedures, including those for the Rockingham County Nursing Home, the Rockingham County Jail Facility and the Rockingham County Dispatch Center.
In addition, I am enclosing the procedures for the decontamination personnel at the Manchester Decontamination Center, along with Appendix F to those procedures, which materials were included in the April 16, 1986 submittal by the New Hampshire Civil Defense Agency to FEMA. Finally, I am sending to you under cover of this letter . pages 9 and lu to Appendix C of the DPHS Procedures, and pages 2 and 3 of Appendix D to the DPHS Procedures. These pages have previously been sent to FEMA, but they were inadvertently ouitted in the copies of the plans distributed to the parties. As all of these materials are now incorporated in the New Hampshire Radiological Emergency Response Plan, they may be appropriately transmitted to the Licensing Board and the parties to the licensing proceeding. Yours truly, , George Dana Bi eb Assistant Attorney General Environmental Protection Bureau 271-3678/3679 GDB/ sed Enclosures cc: All Parties to the Licensing Proceeding Richard h. Strome t l l l
w
*
- STATE OF N HAMPSHIRE
'9
- EXECUTIVE ugPARTMENT New Hampshwe C#se Defense Agency j sisteow==Pertsoum 107 Pteenere Street coneoro,NewHampshre 03301 - "
403G714231 14004524792 JOHN H. SuNuNu RICHARD H. 8TROME Govemor Drector May 14, 1986 saaess a.saoosoras ooputy crector Mr. Henry G. Vickers, Regional Director Federal Emergency Management Agency Region 1 J.W. McCormack Post Office & Courthouse Boston, Massachusetts 02109
Dear Mr. Vickers:
Enclosed please find copies of those pages that were missing from our earlier supplemental submission. Included are: Appendix G Appendix U Figures IA Figures 1B Figures 2-4 Attachments A and C Also enclosed ere higher quality copies to replace existing pages which might not be entirely legible. Note that the enclosed copies of Tables 35-38 of KLD Progress Report No. 7 have been renumbered to Tables 11-1 through 11-4. i If you have any questions, please do not hesitate j to contact me. Sincerely, y-Richard H. Strome Director RHS/sJc Enc. '**""'"'"*'""*'"*"H***** I i l Fezn 7 l E/il w , - ---- - . y. . . - -. . . - _ .~ , ,,,-- -- .. - - -
6- . APPENDIX G OFF-SITE MONITORING TEAM KIT - INVENTORY >
- 1. 12 Pens
- 2. 12 Pencils
- 3. 6 Magic Markers
- 4. .
25 Blank Survey Forms
- 5. 23 Pads Community Survey Naps
- 6. 1 Box D-Cell Batteries
- 7. 1 NA State Map
- 8. 1 NH State Map
- 9. 1 Box Spare Fuses
- 10. 1 Box Examination Gloves
- 11. 100 Foot of Radiation Rope *
- 12. 2 Rolls of Masking Tape .
- 13. 2 Rolls of Duct Tape
- 14. 1 Eberline E-140 Portable Count Rate Meter .
- 15. 2 Eberline HP-210L Shielded Probes and Holder ,
- 16. 2 BNC Cables (Spares)
- 17. 2 Boxes of Particulate Filters
- 18. 1 DC Cable Air Samplers .
- 19. 25 Silver Zielite Cartridges
- 20. 3 Spare Air Samp1*ing He~ ads '
- 21. 25 Sample Zip Lock Bass
,' 22. 25 Glassine Envelopes
- 23. 1 Box of Smears 24 10 Sample Loss
- 25. 1 Eberline R02-A Ion-chamber
- 26. 2 Check Sources (CS-137 - CL-36)
- 27. 1 Stop Watch
- 28. 1 Tape Messure
- 29. 1 Tweezers 30, 1 Dosimeter Charger 31'. 1 Copy of ER-5.2
- 32. 1 7HF Portable Radio
, ADDITIONAL EQUIPMENT: (available as needed) 1, 3 Full Face Respirators
- 2. 3 Iodine Canisters
- 3. 6 Sets of Protective Clothing (Paper)
- 4. 25 Pairs of Plastic Shoe Covers
- 5. 3 Pairs of Boots
- 6. Dosimetry 1019o 11/15/85
i
- i
. \' '. . - ,
, FIG"RE 1A
' s .
/
P:ccec:1ve Action Recommendacion Workshes: for Ca eral Popula: ion 1. Ti=e of calcula: ion (use 2a hour clock) hours
- 2. Ti== of release s:ar: hours
- 3. Ralease dura: ion e hours
- 4. a. Wind speed sph
- b. Wind direc: ion from degrees
- 5. Dis:ance to reference loca: ion =iles
- 6. Affec:ed subareas (use I:e s 43 and 5 and Tigure 1) .
7. Ple=a ::avel ci=a (I:e= 5/::e: aa ) hours S. i=e un:il exposure (choose a or b)
- a. If relesse has berun:
(1).D.if.feren.ce (I:e= 1 - I:e= ) . hours (2) Ti=e (I:e= 7 - I:e= Sa(1)] hours
. . . b. If release vill berin la:er:
(1) Difference (I:e= 2 - I:e= 1) hours (2) "i=e (I:e= 7 - I:e ib(1)) hours
- 9. Evaeus: ion condi:1ons
- a. Season (circle one)
(1) Su==ar: May 15 - Se;: 15 (ses ?:ocac:ive A :1: s f:: Seasenti ?:pula:icns) (2) Wis:ar: Sep: 15 - May 15
- b. Wea:her (circle one) ..
(1) Nor=al seasonal wea:her (=ild, ligh: rain, ligh: sncv) (2) Adverse ~ (Su==ar: heavy rain /f:g 'Jin:er: heaty sn:v/ ice)
- 10. Ivacua:icn Ti=e N -
. h:urs .
(Use ::e:s 6 and C and Tigure * , Evacua:1:n Ti=e Is:i=a:es :: de:er-eine evacua:1:n :1=e.) on- -, ,- - - . . . - - -, -e,. , - , . . + - - - - , . - - - - . . . - - - - - - - - - . . - - - . - . - - . . , - . - , , - - , - - - ., - - - , . -
- 11. Exposure Ti e hcur.
/ (I:e= 10 - I:e= Sa(2) or 8b(2)]
- 12. Evacuatien Egosce Peried hc=:
(s= aller of Ice: 3 cr Ita= 11)
- 13. Projec:ed khole Ecdy Dose
_ R
- 14. Monitoring Tea: khole Bcdy Dose Rate R/hr
- 15. Monitoring Tas:n khole Body Dose R
- 16. Mos: Reliable khole Ecdy Dese R
(1:e= 13 cr Ita= 15) .
- 17. - Mcci: ring Tea: Tay::id Dese Ka:e E/br
- 18. Menit: ring Tea: T.yrcid Ecse
_. R (1:e= 17 x Ice: 3)
. . 19. khcle Ecdv.Evae;.:sti:n Dese R
(" , (Ice: 12 x I:e= 16/I:e= 3)
- 20. Tayroid Evae.:stien Cese
},
(Ice = 12 x I:e= 16/I:e= 3)
- 21. khole Ecdy Shel:er Ecse .
(1:e.= 16 x 0.9)
- 22. Thyrcid Shel:er Dose (c'.cese a cr b) a.
Fcr release dra:icn if less t'.a= 1 hc = R (I:e= 18 x 0.5) b. For release d=a:ict cf grea:er than 1 F.cc R (I:em 18 x (1 _ 0.5 ] _ u t._. a 23. khole Bcdy Indicated Ac:ica - refer to Figre 4 (indicate no actien, shelter, cr evae:aticc) 26 Thyroid indicatec ac: ice - refer :: Figre 1
.\
(inuica:e ne ac:i:n, shel:e:., er evae.:acic )
- 25. Rec ccended P ::ac:ive Ac:i:n (Reccrd cre severe ac:ic:* c--
v - 2J Cr .a:g: g/
. - _ - - - - _ - - ~ ~ - - - - - _ _ -en pip,.;.e 2). _ _ - - - _ - .
.s- -
FIGURE 13 Special Fa' cili:7 Protec:1ve Ac: Lou Workshee:
- 1. Affe :ed Towns 3x4 Facili:v l - k'nole Desa Body l Shelter Tae:or l Shel e l ?;ote :ive Ac:Lon Dose 4
4
'=
(- 1
! I i
Sceps
- 1. Ob:ain affe::ed :: tens f:ce Figure 2.
- 2. De:ersist facili:ies in affe :ed costs f:sc Figure 5.
3. Obtain whole body dese froc I:e= 16 Figure 1A. 4 Ob:ain Shel:e: fac::: f::= Figure 5. 5. t P.ul:iply wholehedy dose (3) ti=es shel:e: fa:::: (').
- 6. Determine prote :ive ac:Lon froc Figure 4 s
.. yIggII 2 PROTICIVE ACION RICOMfI'.'DN" IONS 3Y TOW
'/
DISTANCE W!'O DIRICION TOWS . SEI*TIR E*iACA~I (IROM) 0-2 Miles All SIA3 ROOK, NE .. E.W.PTON, NE () () EAMP!ON FALLS 2-5 Miles INI,I,ISI,SI KINSINcTON, NE () () .
. SOU E F.CC3 TON, NE SSI,$,SSW,SW NOI~E til'!PTON, NE
() () INI,I,ISI, 3EI:C~000, NE SI SSI () () IAST KINGSTON, NE 5 .' O v.' ' e s e.v.e
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a . c'ie l. l l .; ,9 cc' ~m:ww. e,e e e so -e. e = re - . c., mt We4eIe . , - - e i s :-. c. N N m n.-
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a FIGJRE 4 PROIECTIVE ACTION RECCWDiDC_0N GL*DMCE CJECS FT T BC0Y GL'IDECE CJR.'" l IF I I-Zi l l Projected dose (Icem 16) is l No ac: ice less than 1 rem l. I Shelter dose (Ices 21) is l Shelter I { 1ess than 5 re= I l Shelter dese (I e= 21) is Shelter ecual to or greater &m 5 l l* lre=andevacuaticadose l (Ice: 19) is ecual :o c: l Leester than shel:er cosa l l l Shelter dese (Ice: 21) is l Evacuate egal to cr greater 6.an 5 l lre:andevacua:icncese l (I:e 19) is less em l 3
, Lshel:er dose
- I .. . .
I
/'
(_. _T_. MOD G.rCCE CJT_ ' I I Ecse (I:e= 18) is less 2.En 50 ac:icn i L 5 re i i l Shel:er dese (Ita= 22) is l Shel:er _ less 6.r. 25 re: l Shel:er cese (Ice: 22) is Shelter l egal to er grea:er than 25 l re: and evacuatien ecse l 1 l- (I:en 20) is eq:al to er l _ erea:ar & m shelter dese l l l Shelter ccse (Ita= 22) is Ivaca:e I l egal to er greater em 25 l re: anc evacatica cese l l " _s(helterIces dose 20) is less than l l i Shel:er turning cid is air c: cendi:i be wi:h neven:ila:i:n s er fr.s, clesi :ntr:1.
.g d:crsVen:i'a:i:n a .d c:n:::" :er.s
;:reven:ing ac:ess cf cucsida air.
in::ws , 6.us Pr:ceed c: a baseman: if avai:.si.e. l
- _ . , _ _ - . . . _ ~ . -
i i . l __ . _ SPIIIAI. FAC11EIY Sil0.TI-RING FM*l1RS 3 Illa.nnce train beside Projected Seabrook Sheltering Wiole Isody Dose To Facility ,, Station Cruistniction Cluirecteristics Factor (SF) Warrant Evacuston Brentwod RockQlume unwity - Mart:ing Ilouc . 4 l 0 claisdell itidg. 12-13 mL lirick Faced, Cnnerete Franc L Itoof .3 16 rese
! O Fenumal nhlg. 12-13 mL lirick Faced, Concrete Frame L Hoof .3 16 ran . O Hitclusil itidg. 12-13 mL lirick Facal, Concrete Frasme L Wood Hoof .4 12 ran O LhulertiLI1 Isidg. 12-13 mL ltrick Faced, umod Fnsums b Hoof .5 10 rem Rockingham County Jail 12-13 mL ;l 50 rein Exeter -
4 Exeter llospital East Wing 6-7 mi lirick Faced, Concrete Friva .3 16 rem - , Mot Wing 6-7 mL lirick Facal, Poured Concrete - 12" .1 50 rem j Exeter llcaltIn Care 6-7 mi lirick Faced, Wood Fnwe .5 10 rem Eventide of Exeter 6-7 mi . firick Faced Steel Frame .4 12 res
- Coodwins of Exeter 6-7 mi . lirick Faced Wood Frame .5 10 res
! Portamermath Portmenouth llompital
; O Adulnistration itidg. 11-12 mi lirick Faced, Steel Frame, Misonry Mills .3 16 rein uxmlRoof -
O Seybolt itidg. 11-12 int lirick Facal Steel Frame, Hnsonry Walls .3 16 rem , Wood Hoof i O Hain itidg. 11-12 mi lirick Faced, concrete Franc L 1 oof .2 25 renn Edgeuxx1 tkstor 11-12 mi lirick Faced, wood Frame .5 10 rem M:ntworth lione 11-12 mL lirick Faced Wood Frame .5 lu rem Cligycr lione 11-12 mL lirick Faced, Partial Concrete Frame, .4 12 ress Partial wood Fraue lloine for Ageel Women 11-12 mL lirick Faced, Poured Concrete . .1 50 ran 1 t 4
ATTACF.XINI A
. PLANT SYSTIM CONSIDERACCNS TOR EARLY PROTICTIVE ACTION DECISIONMAKIN k* hen considering early protec:1ve ac:Lons, par:icularly for seasonal popula: ions , pri=ary concer:s are plan: condi:Lons ,a=d prognesis ra: hor :han projec:ed or =easured radialegical consequences. Par:1cular attention on :he par:
tisen:ofplant the decision sys:e:s and =akers condi:Lons: should, therefore, be direc:ed to the following per-A. Reactor Coolanc .5ys:e=
- 1. What is reactor vessel level? Is reac:or cooling adequata?
- 2. What is reac:or core ext: cooling ta=perature.
cooling eff ec:ive? Is reac:or
- 3. Whs: is reac:or coolan: pressure? Ara pressures incre'asing .
~
or decreasing beyond nor:al cpera:ional pressuras? 4 Confir: whe:her rese:or has been shu: dow:. .
- 3. Turbine Canera::: Sys:e=
- 1. Wha: are S:aa: Lina M:ni:or readings?
. . .. . 2.
Do readidgs indica:e pri:ary syste: :ssacecharysys:e: leakage' vi h radioac:ivi:y! k ,, C. Elec::ic Power Sys:eas
- 1. Are a:argency buses - buses I-3 and E-S powered?
2. Are the buses powered by off-si:e power sour:e or by en-st:e diesel genera:or source? D. Radia:icn Da:a =anagenen: Sys:e=
- 1. Wha:
Ven are readings S:ack tha: on Wida ?.ange Gas Moni: ors on the ? izary 4 veuld indica:e re'assa ra:es froc c:n:sincent?
- 2. Wha:
are : adings en Main S:aa: lina M::.1: ors tha: v:uld indi-ca e significant levels of a::1vi:7 in :he secondary sys:e=?
- 3. What are In-Contain=en: post-10CA Moni:c readings :ha: vould indicate increase of ac:ivi:7 inside :he con:ain=en: s::ue:ure?
s
E. Engin :: 52fety Tac:ures
- 1. Status of con:ain=es: 1::egri:y? Is con:ainment isolated?
, 2. Ac:1va: ion of Emergency Core Cooli:g Sys:e ?
injection? Is there safe:y
- 3. 5: acus of con:ain en: air press'ure? Is pressure inside con-tain=en: increasi:g, decreasing, or s:aady? .
- 4. If pressure 1: side con:ain=en: is a concers, wha: is sca:us of Containmen: Spray Sys:em? Is 1: available?
F. Maceorological" Measure =en:s Sys:en
- 1. Wind Speed?
- 2. Wind Direc: ion? -
- 3. Precipi:a: ion?
4 A:mospheric S:abili:y Class? Affec: :ha: s:abili:y class vould have on plu== dispersion? NOTI ON ATMOS?EI?.IC STA3ILITY CLAS5: The .=e:ee:clegical ,=easure en: sys:e: v11* provide a::cspherie da:a leading to classif t:a: ion of a::espheric c:ndi: ions ranging f::=
- rela:ive turbulance to rela:ive s:abili:y. A:mospheric S:abili:7 l
(. Classes are: l A - ex: e=ely uns:able 3 - :odera:ely uns:able C - slightly uns:able D - neu::a1 I - s11gh:1y uns:able T - :odera:ely scable C - very s:able
\
A m C'95.3T C e
. E ergency 0:ganima: ion Sca:us and Local Condi: ions
/
A. Resoonse 5:stus of the S:a:e and Town I=arrency 0:raniza:iots 1. The pro:ee:1ve ac: ice decision mus: take into consideia:1cn the sca:us of scate and coun e:ergency personnel and resources and the ti=1:g of the protec:1ve ac:ior. announce=en:s to the public. 2. Of par:icular impor:ance to precautionary actions for the beach areas is the scatus of the Sta:e Police and local police to implement traffic a:d access controls.
- 3. Status considera: ions include: .
- a. Availabili:7 of personnel
- b. Ti e required for mobili:a: ion
- c. Degree to which mobiliza:1on has progressed '
d. Ti:e required f:: 1:ple:en:a:Lon of e:ergency ac:icas J
- 1. local Condi: ions
. . 1. . Local condi: ions vi:hin a:
decisions and their 1 ple:en:a: ion.affec:ed area =ay c:cs::ais pr:tec:ive ac:1:n 2. Local condi: scr.nel ices:he through should
!?; a:he reper:ed :o decistor. akers by loca.* ICC ;er-Neving:::..
3. Per:inen: local c:cdi:icns include: a. Condi: ions cf ::ad and evacua:icn tsu:es considering: (1) Seasonal ::avel 1 pedices:s (2) S:a:us of : sad repal s (3) Surface condi:icas due :o vea:he (4) Na: ural c: =a:-=ade impedi en:s (5) Affec of traffic signals on traffic flov in dire::icn of evacuacion - r s i
- b. Populatica d3nsity and dis: ibutien
. c. Evacuacion routi capabilities d.
Incionen: heavy rains, weather etc.) condi: ions that would affec: travel (snow, fog, e. Local'evencs which cay presen: requirenen:s for special notifica-tion, traffic con:rol, transpor:ation assis:ance ,,
- f. Scacus of schools and other special facilicies O
e o j .
*
- 4 .' e e p.
' * *- e a e o e **. . .
[ Q 1 i a i e O*, I 9
. . . . . . . . . . . . . . ~. -- e 1
'. TABLE 11-1 hDNBER CF NON-RFTURNERS FOR HCUSEHCLDS WITH 1 CAR ANC 1 COPPUTER WHO DRIVES AMESBURY, FA 1 HOUSEHOLOS WITH ONE CAR 4 SIZE OF SUCH HOUSEHOLOS E 1 CCMMUTER WHO DRIVES i l i 1 2 3 4 5 6
--- 7 8 9 10
>=
UNKNCWN TOTAL 4
- p. - ---- -----
I l 68 4 NO. OF SUCH HOUSEHOLDS: 4 3 2 4 1 0 0 0 0 0 1 0 14 l NC. CF NCN RETURNERS : 1 1 0 0 0 0 0 0 0 f 0 0 2 NO. OF RETURNERS 1 2 i 2 4 0 0 0 0 ! 0 0 0 9 i l NO. OF UNSURE - 2 0 0 0 . 1 0 0 ] 0 0 0 0 3 NGH RETURNFRS PCT. : 50 0 33.3 1
- 0. O. O. O. O. O. O. D.
- O. 13 2 TAL NO. OF PERSONS REQUIRING TRANSIT
- 3
- TAL 3C. OF PERSONS AT HOME RECUIRING TRANSIT: 2 e
9 m e 1
. 1 .
TABLE 11-2: NUPBER OF A0k-RETURKERS FOR HCUSEHOLOS ! WITH 2 CARS AND AT LEAST 2 COMPUTERS WHO OR1VE i i - q AMESBURY, MA HOUSEHOLDS WITH 2 CARS SIZE OF SUCH HOUSEHOLOS I C AT LEAST 2 COMPUTERS i . { 1 2 3 4 5 .6 T 8 9 10 UNKNOWN TOTAL w , H I NO. OF SUCH HOUSEHOLOS : 0 15 13 10 4 1 0 0' 0 0 0 43 I
- l
! NO. OF NEITHER RETURNE0: 0 2 0 0 0 1 0 0 0 0 0 3 I ! NO. OF EITHER PETURNEO : 0 13 8 9 3 0 0 0 0 0 0 33 i
j NO. OF UNSURE : 0 0 4 1 1 0 0 0 0 0 0 6 .I NON RETURNERS PCT. : 0. 13.3 0. O. O. 100.0 0. O. O. O. O. 8.3 1
'AL NG. OF PERSONS REQUIRING TRANSIT : 9
!1 *AL NG. OF PERSONS AT HOME RECUIRING TRANSIT: 3 j
TA3LC 11-42 AUMBER OF N0h-RCTURNERS F9R HCUSEHOLOS i WITH 4 CARS AND AT LEAST 4 CCPPUTERS WHO DRIVE AMES80RY, MA i HOUSEHOLOS WITH 4 CARS SIZE OF SUCH HOUSEHOLDS ' ! ______________________ _______________________ e l AND AT LEAST 4 COMMUTERS 1 2 3 4 5 6 T 8s 9 10 UNKNCWN TOTAL
'N
, - + _ co ' T
. s NO. OF SUCH HOUSEHOLDS : C s9 J ,C 1 C 1 0 1 0 0, 0 3 e , w- x -
NO. OF NONE RETURNED : C 0 , 4. C 1 0 0 0 0 0 0 0 1 NC. OF AT LEAST 1 RTRNO: 0 0 0 0 C 1 0 1 0 0 0 2 NO. OF UNSURE : 0 0 0 0 0 0 0 0 0 0 0 0 . NON RETURNERS PCT. : D. C. O. 100.0 0. O. O. O. O. O. O. 33.3
- ~AL NO. OF PERSONS REQUIRING TRANSIT : 0 ?AL MO. OF PERSONS AT HOME REQUIRING TRANSIT: 0 4
9 6 4 #
l . . TA3LE 11-4: huMSER OF NOA-RETURNERS FOR HCUSEHOLOS ' WITH 4 CARS AND AT LEAST 4 CCPPUTERS WHO ORIVE AMES8ORY, MA HGUSEHOLOS WITH 4 CARS SIZE OF SUCH HOUSEHOLOS AND AT LEAST 4 COMMUTERS 1 2 3 4 5 6 7 8 9 10 UNKNCWN TOTAL w i
, T m
NO. OF SUCH HOUSEHOLDS : 0 0 C 1 0 1 0 1 0 0, 0 3
- 40. OF NONE RETURNED : C 0 0 1 0 0 0 0 0 0 0 1 NC. OF AT LEAST 1 RTRNO: 0 0 0 0 C 1 0 1 0 0 0 2 NO. OF UNSURE 0 0 0 0 0 0 0 0 0 0 0 0 NON RETURNERS PCT. : O. C. O. 100.0 0. O. O. O. O. O. O. 33.3 "AL NO. OF PERSONS REQUIRING TRANSIT 0 TAL .90. OF PERSONS AT HOME REQUIRING TRANSIT: 0 o
9
' . .. . -~, x a a accacsaneesnt s Page 1 SAFETY INFORMATIOfJ N) m o w s.w.u .
i Th. uen.o si.... no...,,,,eai t,n..im, ia,,,,1, ii, i ....i.i., eni,, omoi,.. - ' i t!Ona! Safety and Health Act of 1970 (OSHA), has established an electromaunctic energy safety standard which spplies to the use of this equipment. Proper use of OPERATING INSTRUCTIONS . this ri dio will result in exposure below the OSHA limit. FOR YOUR t "CONVERTA-COM i' DO NOT operate the transtmtter of a mobile radio when someone outside the vehicia ls within two feet (0.0 meter) of the antenna. DO HOT operate the transrnitter of any radio unless all RF connectors are secure and any open connectors are properly terminaicd. Mobile Radio Console , WIIII DO NOT hold the transtnit (PTT) switch on when not actually desiring to transmit. MX000 Series "Handie-Talltie" Radios ' 00 NOT allow ch,ildren to play with any radio equipment containing a transmitter. - DO NOT operate a transmitter near unshielded electrical blasting caps or in an explosive atmosphere unless it is a typo especially qualified for suels use, a . k I > ff 3 s Ip hGfa !
!'i=Q. r - -- r _ ----- -- i k.
(h Motorola, MX300, Converta-dom Hen' die. Talkie,'and Private Line are registered trademarks of Motorola, loc. *
' @ 1975 by Motorola, Inc.
s I Portable Products Division , 8000 W. Sunrise Etivd., Ft. L.auderda,c, F L 33322 - Printed in U.S.A. 3/31 -IH ,
,. CDP 01010CU0-0 O
. ~ . . .
Pzge 2 - Q.y ----
.e ?
e fdm we side on.netor tust e.nve. seen. twerte.leia sati,i g 8 1 save it for futurr esse. f iN*d ' 9 Placa the poalaisl2 eni%s in lin: ernsnt:Ioef;ct so the a:xl;te NOTE - 3 y A t.omt anion MX200 krins Henrjie. Talkie" portable radio must tw imtelled in rp:aktr sp ette f rrs th
/
8 g g ] 1.se tum at ilm sun eld. e f*usti sten rnina (nne the g:ndell until le toes h.s (top of slw. e.ulme ed. n* fliph whts II.e. ha .** Hi Ilip e nn ulel. stue consula for mohele two-wey rado operation. The following peorernases
" ~~s h e et,veihn typirnt uppedese Mll'a PMbeble IneNo tinnMWh*g all His tintulrn'd
[ l l (/l e luen the key olockwise t e le ck th v ri>Ns in the en+rs' it le .tnw hwludW **Prhl.ine" equed Disregard procedures refersisig to o The key may be renwswed froen the luct when in its locked controls not contained on your teilio. j or unlocked pnsition. > TURN ON, SET VOLUME, SETSQUELCH, AND MOMITOR
' Ilotate the portetsie radio volume control oewhelf turn clockwisit to tum on f .; - - - - -
the radio. This else turns on the night light ediich illuminates the radio con- "
'J 7...'. m j trols. The night light is also turned on when the ignition switch is turned on. --_)
b(f-[-f **(*"'a'*) l 4** e Place the PL switch in itt of f (o) position. ~ incq f p] g-f e c _ 4 QEp,, _ ; _ ,j O flotste the radio squelch control to the maximum counterclocirwise position
- h
- and set the volume control to a comfortatste listening level. If the op:ioeul ,
Set the frequency selector on 12-wett speaker is useil, the rad i_o volumit control : desatsled and the volume is yO N&MWM S - -- e now controlled by the console volume content. l , de i -g,.[Ny 'l When the channel is cleor. sinwly rotate the se He!cle conte 01 clockwise until the e noise stops (squelchesl. Pisce the PL switch in the on N ** " D* Iwr.ilion @ af ter enonitoring. ( l TRANSMIT AND RECEIVE WilEN Cli/tMMEL IS CLEAR
-- RELOCATE SPEAKER Wi!!LE OUTSIDE Tile VEHICLE-To transtnis place the ignitinn switch in les on taisition.
j f~' Hold the push-to-talk switch depressed (on the miemphonel end speak nnrmetly across the micanphnme with lips obnut , g 3 two inches from the grille. e it the console is ertulpped with either the %-wett or j J yy>, / g# NOTE
- 17-w.sti ustaker option loosen - da not reenove - the \
The red transmitter Indicatar lamp grows den the . ton wing s .cws horrfing the speakar in the inacket enri tronsmitter is on-the-eir. lif t the speaker frtwn she tirocket. '*'],e/ # * ( hi
.a -T--
to,,, the window shnhtly in the vehicte sad clip the sp.*aker twer Itw top of the wirwlow. This pesmits hearing 7.N s
* *I h
.g . -.
catis in the orna oroemd the vehicle.
' h. 4 d)
G "*it m receiving.* " " " " " " " ' ' ' " " ' ' ' ' ' ' " ' ' ' " * " " ' " ' ' " ~ ' ' ' ' ' * ' ' ' " ' s~ \ f. . N REMOVE RADIO WHEN LEAVING THE VEHICLE- = - - - KEEP THE DATTERY CHARGED IN THE RADIO - - Turn the key countercloci: wise to unlock the entie ant q'p..g r-- e..--- T -~ -- pi**cc.-- while still holding the key push the key lock buret. The trulio { ""**,} ' The b.ittery in th: r;dio is automatically rer.harged while 9' l end po@vt will spring forward for easy removal of the port.
,$ - '~ 5
instellati in the cor.mic witte the ijnition switch on. If the oble radio. Pull the radio cut of Turn the console end refer to 'the b % --o-
"c radio hae e simusmd charge hattery. the yeen charge temp porteAal) red 6o manuel for operation. off the lenition " :- 6. -
N ginws cll the einse ties rarlin is Iri the console pocket, if the swit ch for minirni en curreni drein. Fi prece side connectos dest cover back on portable radio. .hy*^ c-d *" h*5 * '"5'M ' ""* '**'Y ** 8a ch*'ge lamp glows
,{,g f, [.!3,,
3 ./" p
.{ until the Isottery is r.twafcf.
w' , 9 - _ m w
APPENDIX F4 - FORM 3 PROCEDURE AND DIRECTIONS IN DRIVING YOUR VEHICLE TO THE CAR WASM.. . This procedure is for externally contaminated vehicles only.
- 1. Notify the firefighter responsible for your vehicle that you are ready to go to the vehicle wash.
g not use your vehicle without first seeing the firefighter because you could get centaminated.
- 2. Follow the firefighter's instructions in getting into your vehicle.
- 3. Once in the vehicle, do not get out (unless an emergency) until the vehicle' has been washed.
- 4. Close all vents. Do not use the vehicle's heater or air conditioner and close all vents and windows and do not open them even if it is uncomfortable.
- 5. Do not, eat, drink or smoke in the vehicle.
' ~
- 6. For your"pfotectioti, 'af ter the vehicle has been* wsshe'd, c'ome back to the' Reception Center so your vehicle may be remonitored.
- 7. For you and your loved ones protection, follow the firefighter's instructions!
;S*
APPENDIX..O Dose Assessment and Atmospheric Dispersion Estimates "3AAADE" 3efine.! Procrams (i -'
. s Storage Resister Contents
?r.ce r *abel Rerister Centeh.t Units IL r.n :v: - P5C A
~
A A an exponent
- ?SC 3
- i S an exponent -
- PSC C D C Chi
~
- PSC 3 F curies / cubic mere
" , D dose rems PSC E
- PSC F G
H E factor for R.100 - Sigma (T) - PSC A 7 F factor for 1.100 -
~
PSC 3 X G factor for R.100 - PSC C H eff. stack height meters
~
?SC J "
C I Chi (iscplerh) curies / cubic . e e:
~ J Sigma (Y) meters, i
PSC E 3 K Sigma (7) PSC F '; meters L sn exponen: Input ADE parameters J M an exponent Ge=eral equation K Gr=und level ecuation Q emissien rare curies /sec L R dose rate Centerl'ine (GL) 'ecuation .!
' mR /hr T time hrs
. Greund level source eg. SPC U wind speed Dese estimate = meters /see WS a string variable -
X downwind distance Y kilometers Undefined Procrams (2) . crosswind distance me ers 2 vertical distance - meters Program Star: line Y-distance, center-line to isopleth 90 Values of E. T. and G Is:pleth concentra- uG P
==
l rien for given dose 100 i 1 E 1.0129 1.0105 Reserve Programs ( ) P~rceram Label G Ll.7652 14.335 rph to mps A sei to km S f: ic m 3 mps to mph 2 kr. to mi X
- c. to f: C .
(1) must be in DEF cde (2) must be in DEF cr RUN mode (3) must be in RUN mode O 11/18/85
I .' '
APPENDIX 0 Ex'moh.e Problem
.z. .
=D Z = 0 meters
,s = 3 mi H = 150 ft '
- r. = 100 Ci/sec Problem = radiciodine (P)
, U = 10 eph - T = 1 hr Y = 0 meters D (max. acc.) = 5 rems Kevstroke secuence Outout Value (RUN MODE) X = 3, SHFT S, ENTER X (km) U = 10, SHFT A, E.WER 4.828041264 U (mps) 4.469473496 H = 15D . SHFT D , EMER H (m) 45.72 (DEF .TDE) SHFT F, downwind distance (X) , ENTER Sigma (Y) (m) 277 SHFT V, downwind distance (X) , ENTER Sigma (Z) (m) 84 SHFT J. emission rate (100) , ENTER, wind speed (U) , ENTER, crossuind distance (0) , ENTER, vertical distance (0) , E.WER, sffective.. stack height (H) , ENT:..s r.0 ? .' -- IM - Chi (gnd lvl, ctrin) (Ci/m3) 2.62E-04 SHFT =. P, ENTER, C, ENTER, TIME (1) , ENTER child's thyroid dese (rems) 395 a.100, ENTER, dose (max acc.) (5), ENTER, time (T) , ENTER, factor (-1.69
- LNT + .975) , ENTER, factor =
(1.0105) , ENTER, factor (14.335) , ENTER dose (max. acc.) (rgms) 5 ENTER Chi (isepleth)(Ci/m3) 3.uE-06 R.00, ENTER, J. ENTER, C, ENTER, I, ENTER downwind distance (X) (km) 4 (truncated) ENIER crosswind distance
, (Y) (m) 815 (RUN MCOE) Y, SHFT C, / , 5280, ENTER 0.5064175217 crosswind distance (mi) e
( APPENDII. O. ( rblatica.cf.atc; pi:cric s:::bility class to %eather ccnditions?
. =
A - Extrernaly unstoble ccnditions D :- Neutral conditicas* B '-bdirately unst,able conditiens E.- Slightly stable conditiens C - Slichcly er. stable cc:xiitiens F - Moderately sthie conditier:s D.tytiMe c .:ditiens Senli!,ht in cns . cv k'iShtime condi_tiens _ !
- 'inin overcast -
cr >.r -.t a < .: Swnce Wind - c!cucT..0;ie . c2:tu'ir.3 :; ' NP-! r2Nd, M/Sec Strenc Mcdirati Siid,t
- - I
. . i
<3- <,.
n, . o
.3 -- 2 A-B B ' "
C E . F' ,
~ 6. 5
- 4 8 C-C D 0 E , ,
10 .. 6 C C-D D .
.c . 0 .
^
>6 C D
. i D D C
. j i
i
- c. Ifcable to heavy ev.wcast., dayornig$t 7.:.,..
g,. ,7e..-,,: c '. .~ ' i r.e s .' '. - de '. '. n. ' ~_ ". .. .... _ .- ' *.- ' - ' '. - - ~ = '...
.. . * ' s... ' --
c ' .. . c*'
.-... . 1 c._ . c c. .. . 3n .s p, . 4. ., . . . .. .. .. e.- ., .s. 4 -. v. ... ., ,p., uc.,., u. . . .e.
2
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APPDIDIX O 0-7 A. . 100 9c l
--l- - i.j . f fjil l 3 .
SCC P- l 3
. : . ,g g.g 700 F. -
600p-y-l 1 I I -j y , . . r ---l '. l l; I .
- j.
300 ago 1 'l d
"88 '"8 caa8*=
r
. a -4 1000.0 ,0 l
i
# i ?-['evemame eser vi.e some asemasem ame eine esseee nnemuse i!s,e e .
4conoco 8 ff 3co ' ese,=.re v=e n=e.estee v i e -. taan e 230 t J- i ei i a s'e tenseurienness am
.meessene rise ssamme. oneeu ves .e 200 k .. !
i
. l j .. !.. I._.! l : 1 2.00Q000 r
33 o .\ l l .e l ' .; '. '
\N.
! I dl . l
! l l
Il.Ii I.Ii'I -I !C-* -
.0C0000 50cc0c
'%8 '.xk-l.. --IO,I-p.. f.. , _;2 80 1 4 i 4- . . - --
'p k $;0$ $
r- ; 2 ,9 -f i i .' .- . '#c ---)r, , i . . . r- o - 6cacco .i! . 50 =- i
,iiii, .- ex i ....., .. ,., sco.cco Q 3 aci N pi li -_i .%p;fo* -
D t._ , I ! l ! I - *- ,j, 400 000 *g i s 30 \l l gS . '
.i.6 I **
,._ il!l Q 300.cco .:.
T 23 ' A Li ~
' ' ' e 's v i 2o I %I '
'.ill . eV_ l , I I iN.f8.4 F, 2 - l
~
2cccc0 $
,I 33
\! ! /o, ,.,
I I I l INl )2 $ t l i l i..c
.". \ ' :
e kg n x
~
x ;..
.[ l ! i .-it t0-8 i 1.00.C00 $
* .N . . .N -
r *-
' - - '. 90.CCO 2
.-e . x#,, e , x 5 Sa000 . i. .
7 . xi e .
- s. . .
g/9 .x. ,e- (; i 4 8 A. 8 X4 i asA i s iNe . . . N Fe - . 70.0C0 $ 60.000 :F, aE i i N I \; 881 \! i 3 a Na e a e .'t 4 30.000 e I I I l #' 'N l l tY
,Ni 4 l l :N iesF4- } 40.0C0 ,j
- j 3 N'
l i l lNi i !K
N
! IM' I i ! N I.2 - i 30.cco i 2.5 N' '
A* ' e l 2 i \' ! f l i ! \l I\ 'I \8 I f ' ts - i l! e><l li!! \ ! r$. i l I \ !!l i tn
!s; .
i I g/g i a
!.li.
- 810 " : ,
-} .
e .
*- 10.0C0 -is r x 4p g .x -** .
- x. .
. x4 x
x . 9.C00 4.0C0 *
- l 7 ( . .
N_ .
. . . .N e . . .N x 4-N.
2000 i g . e No . e e.: ,A e ee .N s .-e - 4.0C0 i j \i e iYJ(l i
- i i \a f l l I .\ ;. 75- 1000 j
,, I \i i ! N r8ii! i\1 l . I ! N ; i -- d.0c0 i l l ! M ll lNef R..8 lh , 1 o l' I e
3.Cc0 !
. i e i i i ..
i 3;. i e : . i t, i sr iii. . _ii. x- . . r2 - 2.000 I Ii! I l .Ndl . N.l ' iN: 1 . to lll ' ll4ll sito ' l.cc0 IS 22.33 4 3 o 78910 13 20 25 20 40 cc 40 :00 t i e,. ..,.a n, . e... 4 .; e... . o ,o 3 f . i
. ..i . o.m.e.ts.o....
. aos.es se.s.s. ..... s sv,ac.t.o o.e.c.a . ,
' I .. .* ...,6C
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. 8 S 1 W.w.fl .e w*n. @
.--. . - . ~ . - - *
,- ,,- , - , , - - - - , , _-,,-.-----n , - - - - - , - - , , , ,,,..- ,,-- ,- - - - - - - _ , - - - - _ . - - , . , , - - - - .--
V a O
\ *
{
#8M N. F:"X":IlFUT "X
/[2t[IL ="IX IF X(=.- 19:K=D(P (.4248'
*LN X+2.7449 44: IllPUT "CH<G)
TLET K=EXP ( ="I C , "T1 HE=" 1 "A". IHFUT "X .9759*Wi X+4 ):60TO 20 1T
.6126):GOTO 19:PR1HT USING
="lX:J=EXP ( .
20 '
"statst"l"S( 45:R=EXP (1.012
.8666*U1 X+5 ~. Y)=",J:STOP 9*U4 C+11.76
.3336):GOTO I@K=EXP (1.094 52) D=R*T/10
.." . 19 - 1*LH X+4.695. 20 PRINT USING -
-):GOTO 20 "ststS5"l"S( .'.00:3=IH1 (D+
' 2:"S":IfFUT "X Z)=",K:STOP .5) .
="lX:J=EXP ( 11:"C":!WUT "X 46 PRIHT US!HG
.9805+LH X+5 ="IX IF X<=. 21:"J" IHPUT "O
="10,"Un'fUs
.0268):GOTO 8LET K=EXP ( " ass"I"WB="s 3
"Y=" lye"Z="I D 19 .9145*U4 X+4 i Z,"H="lH 4T:EHD 3:"D":IIFUT "X 20
.109T):GOTO 22: A= dip ( .5*( 50:IHFUT "CH(P) i
=" l X: J=EXP ( ". Y/J)^2 3=E)? ="lC,"T1HE="
.8978*LH X+4 12 K=EXP (.9112 iT 1
.6341):GOTO *LH X+4.1203 ( .5s(Z-H)A(
19 ):GUTO 20 *(Z-H)/K):L* 51:R=EXP (1.010 i 13 "V":lHFUT "X EXP ( .5*(Z+ 5*U4 C+14.33 43 "F":lliFUT "X H)/K*(Z+H)/K 5) D=R*1*( .
.="lX J=EXP - ( ="lX:IF X<=1 ) -
1699LH T+.9T
.902T*UI X+4 .g LET K=EXP (.
.2036):GOTO .m.:/ 8264*LN X+3. 23:M=EXP (~.5*( 5):D=IH1 (D+
.5) 19
' .. 4T4):GOTO 20 H/K)^2):GOTO 29 52:PRIHT US1HG 53'"G":!HPUT "X 14a'K=EXP (.5833
~
*LN X+3.5186 248"K" C W (2*N "N433"I"CT="
="lM J=EXP (. :. D
.9046*Ut X+3 ' . .):GOTO 20 *J*4(*U)*A*(3 53tEHD
.9071):GOTO :153"B" IWUT "X +t.):GOTO 28 19 25 "L" C=0/(R*J 90 IHPUT "S(Y)=
="IX:IF X<a. *K*U)*Fe*H: *lJ,"CH1/C="
6:"H" INFUT "X 9LET K=EXP (
="IX J=EXP ( .T861*LH X+3 GOTO 28 1C " CHI /!="I 26 *M":C=Q/(R*J
. I '
.9181*LH X+3 ' .095):GOTO 2 *K*U)* mig 010 91:Y=Je(<UI (I/
.4T12):GOTO O.
19 16:K=EXP (.47CH 28 C)/~.5).Y= l *LH X+3.2106 2T:" *:C=Q/(R*tJ IHT (Y+.5)
?:"Z":IHFUT
="iX IF X<=."X ./ ' ):GOTO 20 *K*U):GOTO 2 92: PRINT USIHG 5LET K=EXP ( 17:"H":!HFUT "X 8 "Rtutst"I"X=
="lH IF X<=. 20:PRIHT US!HG ",X PRINT'"Y 1.2335+LH X+ =",Y 5.4242):GOTO 8LET K=EXP ( "st.12^"1"CH 93:EHD 20 '
.7993*LH X+2 =" e C: STOP
'3:K=EXP (2.103 . .6TT6):GOTO 2?:PRIHT "EQ?" 100:IHFt)T "D="I3
- 20 STCP ,"T="ITo"F="
5+LH X44.115 IF,"E=" lee"G 4):GOTO .t0 '. 41:"=" 1HFUT "G ="IG 4 ' OR P?"IW8 42:IF Nf="G" 101:!=EXP ((LN < GOTO 44 D/T/F)-G)/E) , 43:00T0 50 IO2: PRINT USING i
"RE88"I"D=",
.' D PRINT
\ USING "St.2* *
"I=I=",1 l'03:EllD
*u
~
'L eeg7eg" 4492 10:"L" CLEAR IlftlT "A="i A :
,"E='IEn"H="
1H 20:0=E-317):F=H
-39210:2=A-7 6
30:D=ATH ABS (F
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- . - = . - .nnsa
--.aaMu een- -
' . . .. .y..m. 3 ce gMD*?bW .
.2 . .
j$dh$; != .
% = A *
- SCs="E"OR =c
- 1220:JFc 7)=.JAND
- s="F"OR SC*= .T<s.3L'ET
) % -
F "G")LET DJ=- - EXP C .15287
.30454*LH CX *LN T .S8905., , 1410:NEXT N; ; -
L /1000)+.2826 ):GOTO 1330 1420:NEXT I i 3330:IF EH)=56.4 1280:IF T).5AND T 1430:END _ AND (SCs="Q" <=2LET D=EXP
. OR SCs="B"OR ( .27225*LN
[ SCs="C")LET T-1.08096); il
. 0l= .08247* GOTO 1310 i L
LN (X/3000)+ J290:IF T)2AND T< r .91002 =20LET D=EXP - r 1340:IF EH)=56.4 ( .5989*LN T AND SCs="D" _ .27323): LET D1= .097 GOTO 1310 S6*LN (X/100 1300:IF T)20AND T 0)+.93843 <=500LET D= $ E 1150: IF EH)=56. 4 AND (SCs="E" EXP ( .06565 LN T-3.07072 jl i OR SCs="F"OR ) . SCs="G")LET 1310:GD=CH*D: WB=G 5 D1 .07584* D*]/1000: 1 LN (X/1000)+ USING "###": 0 .96329 LPRINT N;: 's 1160:IF RP<=.02 USING "##.##
- LET D2=1 ^":LPRINT GD
- 1120:lF RP).02AND i RPC=.06LET D 1320:JF WB(ILET P 2= .12003*LN As="NONE" -
A DP+1.13375 1330: IF WB)=1 AND
-- 1280:IF RP).06AND WB<5LET pas =
!; (^g, .f RP<=.ILET D2 "SHEL": COLOR
= .22536*LN 2 DP+1.10094 1340:IF W8)=5LET
_ . ,W e -- l 'l 1190:IF RA).1AND pas ="EUAC". w. 4 RP<=.25LET D COLOR 3 [ 2= .23175ruN 1350: US]NG "##### $< f OP-1.02898
.t":LPRINT W 1200:IF RP).25LET B;" "; pas;
$ EY:US]NG "## g D2= 19554* LN DP+. 27143 t.##":LPRINT F . 't 1210:IF D2<0LET C ETA:GOTO 141 { 2=0 0 _ 1215:CH=CHXD1*D2: 1360:RC=CH*3.58E2 . GOTO 1360 :DC=RC*]/100 E 1220:IF LTs="l' O : i GOTO 1240 1365: US I NG # # # ' : P 1230: 1F LTs=' 3' LPRINT N;: [ GOTO 1280 US3NG "##.## _ 1240:IF T)=.14ND ^":LPR]NT RC E T<=2LET D= ; L EXP ( .07318 1320: ]F DC< 5LET P g *LN T-2.9054 As="NONE' 4): GOTO 1310 1380:1F DC)=5AND g 1252:IC T)2cN: < DC<25LET oAs
- 2_E :=Ev: = ' E HE_
" ( .2. 3 =_s 22.0 E - -2.E;E.E. .352:: C )=25 E-GOTO 13;2 Pos='EUAC'. L 1260:1F T)10ANO T COLOR 3 i <=200LET D= 1400: USING "##### , eXP ( .0432* .#':LPRINT D LN T-3.2383) - C:' : P A s
~'hy33 5 ("'~p /J W3 Jt . .Sese Eqicyr % = -
(-LN U+6.S0276
- b~- A .
720:"IF SC*="F"GOTO. 3 1 570:JF SCs="G"ANO ~
;- 2=6.'73*X^.305-U<= ISLET PR= ?30: IF SC*="G".SOTO I840 B4
'EXP < "33333* -
S80:GOTO 1980 LN U+4.34J64) 740:SY=.3658*Xa.30 : 580: IF RPs="S"OR R E . ^.90 750:IF X<=100LET S r 31 Ps="C"OR(RPs[-
"P"AND (J2.8/ 2=.192*X^.S36: , 2000:IF X<=100LET US* 447))<1.32 GOTO 780 g S2=. 053na. 8 .
)LET EH=0 260:IF X)100ANO X< g 14:GOTO 1030 585:IF RTs="G"LET =2000LET S2=.0 p 1010:IF X)200AND EH=0:GOTO 600 0066*X^1.S41.+9 j X<=1000LET S 590: IF RPs="P" ANO . :GOTO 780 g
- 2=.086 un.74 (12.8/(us*,447 770:IF X)1000LET S & .35:GOTO 10
))>=1.32LET EH 2=.00024*X^2.0 30
=56.4+PR*.3048 S4-S.6 = 1020 IF X)1000LET 600:IF RPs="S"LET 0:GOTO 1080 5 S2=18.05*X^.
~ Q=RS*FR*J:GOTO 790:SY=.2751*X^.90 E 18-48.6 , 645 31 = 1030:GOTO 1080 610:IF RPs="C"LET 800:IF X<=100LET S . In 1040:SY=.0481*X^. 2=.156*X^.922: E S031 Q=CR*FR*J:GOTO 645 GOTO 830 E 1050:IF X<=100LET 620:IF RPs="P"AND 8 0:IF X)100AND Xi 9 3 S2=.032*X^.8
=2000LET S2=.0 r 14: GOTO 1G80 EC<=1E-2LET O=
EC*4.32SE2*FR* 3OU^I I43+3 3 ( SO: F X)100AND J:GOTO 645 :GOTO 830 1 X<=1000LET S 630:IF RPs="P"AND : F X)1000LET S
= Z=.052*X^.24 F:
EC)1E-2AND EC< 2=.055*X^1.Os8
+2
[ g 80
.21:GOTO 10 Q(f.~ 4-
=1E2LET Q=EC*2 Q. - :
.84JE4*FR*J: 830:GOTO 1080 g 1070:IF X)2000LET W.
GOTO 645 840:SY=.2089*X^.30 m S2=10.83*X^. i$.:; i . -
*2 bh
~
640:IF RPs="o"AND p EC)1E2LET Q=EC 850:IF X<=100LET S 1080:EY=SY*(CLN . dj 2=.I16*X^.905: E 01/C .5))^.5
*1.19E2*FR*J 645: FOR I:1TD 8*. GOTO 880 )/1609 g
COLOR 0 860:1F X)100AND X< 1085:IF RPs="S"DR h,,, . 647:CS12E 1:LF 3: =1000LET S2=.1 RPs="C'LET E @k ". USING "ta": 13*X^.SJJ:GOTO T=DMS (DEG R S J; ! LPRINT TA8 12', 880 s T+N/LS) , g. g., I ; " HOUR C S)": 870:IF X)1000LET S . 1086:IF RPs="P' ; 2.% . LF j 2=.113*X^.911 LET ET=Dns c .: ? 648:LPRINT T A8 2' ,. 880:GOTO 1080 DEG RT+N/U3) 7 890 : Sy=.14 71 *X^. 90 1082:IF ET>24LET (f : X";TA8 2;"OR'. gc T A8 14 ; " DOSE " '.' 31 ET=ET-24 rghg TA8 21 ; " PAR' - 900:IF X<=100LET S 1090 : CH=O/ C JI* S y
- S %.} .,;
7A8 28;"WID".' 2=.02S*xe.881: 2*(U*.447)>x TA8 32;" ETA.' GOTO 930 EXP ( .5*cEH .-)q -h. ' 910:IF X)100ANO X< 649:LPRJNT TAB 2., '32)^2) MI"; TAB 5;"nR, HR";TA8 14;"RE
=1000LET S2=.2 22*X^.225-1.2:
1095:IF RTs="G" GOTO 1220 b-].Y M";TA8 28;"n], GOTO S30 1100:IF EH=0AND ( @((.e J. E50: COR N=1TO 10 920:IF X)1000LET S SCs="A"OR SC 3.7 660: x=N*1609 2=1.26*X^.516- $="8"OR SCs= - %M SS5: COLOR e 13 "C")LET DJ=- W: .. E72:1: 5:s= : :- - 930:GOTC 1082 .080171LN (X 7.W N 9'2 D=.5246* ".52 N2 /1000 b.2122 553:1: SCs= c- - 2' Q pSe ~2:1: xc=100LET S 1. 0:1: EH=2ct ! SSO:IF SCs='C'GOTO 2=.063*x^.821: Cs=' D LE 0; [p$ ? 840 GOTO 980 = .091*LN (X 720:IF SCs="0"GOTO c4A 960:IF X)100AND X< /1000)+.7568 ..[: E
=1000LET SZ=.2 .
[' .".
___,-A& 226:IF RTom"G" LPRINT "U80"' (lesIF RPC="S"ANO OAAAOE6V4 LPRINT "-- ": CNs="S"AND SP) GOTO 230 =1185ANO SP(12 ( 227:LPRINT "CTO": 03LET FR=2.543 LPRINT "-- " E6
'230:IF RPs="S"OR R 420:.IF RPs="S"ANO Ps="C"LET L=LO CNs="S"AND SP) !
100:"A": CLEAR :LF :LET U=LS:GOTO =1203AND PS(12 l 8:USING : 260 20LET FR=5.082 ! 240:IF RPs="P"ANO E6 LPRINT TIME l 105: COLOR 0: INPUT (12.8/(US*.442 430:IF RPs="S"AND
" LOWER DELTA T ))(1.32LET L=L CNs="S"AND SP) !
(OEG F) " ;LO: 0:LET U=US: =1220AND PS(12 INPUT " UPPER O GOTO 260 38LET FR=2.609 250:IF RPs="P"AND E6 ELTA TCOEG F) !
";UO (12.8/(US*.447 440:IF RPs="S"AND '
120: INPUT " LOWER W )))=1. 32LET L= CNs="S"AND SP)
< INO SPEEO(MPH) UO:LET U=US: =1238AND PS<I2
";LS:!NPUT "U GOTO 330 55LET FR=1,014 I 260: IF L<=-1.12LET E2 '
PPER WINO SPEE
- O(MPH) ";US SCs="A": GOTO 4 450:IF RPs="SPAND 130: INPUT " PPT RAT 00 CNs="S"AND SP)
E(IN/HR) "
;RP: 270:IF L)=-1.11ANO =1255LET FR=1.
INPUT " PPT DUR L<=-ILET SCs=" 266E7 i !
' ATION(MIN) ";O B":GOTO 400 460:IF RPs="C"LET P 280: IF L)= . 99AND FR=886*CP/52 140: INPUT "CONTAIN L<= .89LET SCs 470:IF RPs="P"LET MENT PRESS (PSI . .
="C": GOTO 400 FR=ER/EC G) ";CP: INPUT '290:IF L)= .88AND 480:IF RPs="S" -
(. t
" STEAM LINE PR L(= .3LET SCs= PRINT "USE SL ESS(PSIG) " ;SP "O":GOTO 400 J, LOCA ";LTs; ISO: INPUT "CONTAIN 300:IF L)= .23AND , T="; T: INPUT L(=.88LET SCs= "J= ";J:GOTO 5 ,
MENT OR(R/HR) 10
";CR: INPUT "ST "E":GOTO 400 EAM LINE ORCMR 310:IF L)=.89AND L 490:IF RPs="C"
/HR) ";RS <=2.34LET SCs= PRINT "USE CT 160: INPUT "WRGN EN "F":GOTO 400 J, T="; T: 1NPUT 320:IF L)=2.35LET "J= ";J:GOTO 5 RATECUCI/SEC) 10
";ER
- SCs="G":GOTO 4 120: INPUT "WRGM EN 00 500: IF RPs="P" CONC (UCI/CC) 330:IF L(=-I.74LET PRINT "USE STK i
";EC J, LOCA ";LTs '
SCs="A":GOTO 4 180: INPUT " TIME AF 00 ; ", T=";T: TER SHUTOOWNCH 340:IF L)=-1.23AND INPUT "J= ";J ! RS) "; T L<=-1.55LET SC 510:IF SCs="c"OR S 190:!NPUT "LOCA TY s="8":GOTO 400 Cs="8"OR SCs=~ PEC1 OR 3) " ; L 350:IF L)=-I.54AND C"OR SCs="0" s Ts - L<=-1.32LET SC LET PR=EXP (- 200: INPUT " CONT. A *="C":GOTO 400 LN U+6.90276) T NEG PRESS (Y/ 360:IF L)=-1.36ANO 520:IF SCs="E"AND N) "; cps L<= .46LET SCs U)15LET PR=EXP 210: INPUT "RLS PTH ="0":GOTO 400 (-LN U+6.90776 WY($,C,P) ";RP 370:IF L)= .45AND 3
$ L<=I.36LET SCs 530:IF SCs="E"QNO 222::NcUT rS/L PAT ="E":GOTO 400 U<=15LET PR=
( HCN, c. 5) *;CNS 380:IF L)=1.32AND EXP ( .32548x 225: INPUT "RLS TIN L<=3.64LET SCs LN J+5.1299: ~ ECHH. MMC 24HR)) =F":GOTO 400 540:*F 5:s=~r ONC ;
";RT: INPUT "R 390:IF L)=3.65LET J>18LET PR=Ex: ,
LS TYPE (G OR P SCs="G" (-LN U+6.90276
)
i ":ers . 400:IF RPs="S"AND CNs="A"LET FR= 550:IF SCs="F"AND i g7p u~- - U<=18LET PR= ~l_ -
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p e et II. Protective actions for the consumption of food shall be in accordance with { the following: A. RESPONSE LEVELS (1) Response level for preventive PAG Infant as critical segment of population. Response levn1s Far preventive PAC 131; (34Ce 137Ca 90S r 89sr Initial Activity Area Deposition (microc,uries/ square meter).. ........ O.13 2.0 3.0 0.5 8.0 Fcrage Concentration (microcuries/ kilogram).... .......................... 0.05 0.8 1.3 0.18 3 '. 0 Peak Milk Activity (microcuries/ kilogram) .............................. 0.015 0.15 0.24 0.009 0.14 TOTAL INTAKE (microcuries):..... 0.09 4.0 7.0 0.2 2.6 (2) Response level for emeroency PAC The response levels equivalent to the Emergency PAG are presented for both infants and adults to permit use of either level and thus assure a flexible approach to taking~ action ih cahses where exposure of the most critical portion of the population (infants and pregnant women) can be prevented: RESPONSE LEVELS for EMER. PAG / 131 / 134 / 137 / 90 / 89
/Inf Adit /Inf Adit /Inf Adit /l5F Adit / Inf Adit Initial Activity Arsa Deposition (microcuries/ square meter... 1.3 18 20 40 30 50 Forage Concentration 5 20 80 1600 (microcuries/ kilogram).... 0.5 7 17 Psck Milk Activity 8 13 19 1.8 8 30 700 (microcuries/ liter) ..... O.15 2 1.5 3 2.4 4 0.09 0.4 1.4 30 TOTAL INTAKE (microcuries). 0.9 10 40 70 70 80 2 7 26 400
- 8. IMP L EMEN T A TION When using the PAG's and associated response levels for response planning or protective actions. the following conditions '
should be followed: (1) Specific food items. lo obtain the response level (microcurie / kilogram) equivalent to the PAG for other specific foods. it is ne,cessary to weight the contribution of the individual food to.the total dietary intake; thus. Response Level - Total intake (microcuries) ( 1272o Consumption (kilograms) 02/86jc
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===== EMERGENCY PL ANNING ZON E (EPZ) BOUNDARY
.' r j -
ROCKINGHAM COUNTY NURSING HOME E.ACUATION ROUTE MAP
,,, BRENTWOOD l p-- Q y SEE Os7 AIL A Q
i l -a..
, MANCHESTER 3 m ~
sus osrait s . I L. _ _h ] oisranceg APPROXIMATE TRAVEL J
- _ _ as vitas 3~ 9 DETAIL A i las oi % TOWN OF BRENTWOOD I \
t i j l I i ROCKINGHAM COUNTY , 3 . 1 NURSING HOME i i i j h i 1 ! _a
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DETAll. 8 ' I5i RECEPTION CENTER LOCATION va coNeono
~
MANCHESTER, N.H. a MEMORIAL HIGH SCHOOL SouTM FonttR
'* l souTM k TrY 5 wgoam J EXIf No.1 3 gToM87aN l 70 storono N\ MALL OF N.H. 1 F.4-)
er
,.. '8 *" ENE"^'
STEPHEN E. MERRILL THE STATE OF NEW HAMPSHIRE SENIOR ASSISTANT AMRNEY GENERAL ROBERT P. CHENEY. Jr DEPL'TT ATTORNEY GENERAL BRUCE E 3s0HL ASSISTANT ATTORNEYS GENERAL LESLIE J. LUDTKE ASSOCIATE ATTORNEYS CENERAL CEORGE DANA BISBEE BRIAN T TUCKER PETER G. BEESON JEFFREY 3, BOWARD JEREMY F. KORZEN!K CHRISTOPHER T. DOM 1AN PARALEGAL TARA BICKFORD BAILEY THE ATIORNEY GENERAL ENVIRONMENTAL PROTECTION BUREAU STATE HOUSE ANNEX 25 CAPITUL STREET CONCORD, NEW HAMPSHIRE 033014397 (603i2714878 May 15 , 1986
.d.r. John DeVincentis, Director Engineering and Licensing Yankee Atomic Electric Company 1671 Worchester Road F ramingham, MA 01701 RE: PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE, ET ALS.
(SEABROOK STATION, UNITS 1 AND 2) NOS. 50-443-OL AND 50-444-OL: NEW HAMPSHIRE RADIOLOGICAL EMERGENCY RESPONSE PLAN SUBMISSION
Dear Mr. DeVincentis:
Enclosed you will find copies of the following documents which were sent by the Civil Defense Agency to FEMA under copy of a May 14, 1986 letter from Richard A. Strome to Henry G. Vickers (a copy of vnich is also enclosed):
- 1. Appendix G (a one-page document) and Figures lA, 1B, 2-4 and A-tachments A and C to Appendix U of the DPHS Procedures. These I.aterials were inadvertently omitted from the materials that I sent you on April 18, 1986.
- 2. Higher quality copies of miscellaneous pages sent you on April 18, 1986 to replace ones which may not be entirely legible.
Please note that the enclosed copies of Taoles 35-38 of the KLD Progress Report No. 7 have been numbered as Tables 11-1 througn 11-4. An accordance with the procedure we have followed since the March 25-26, 1986 pre-hearing conference, these materials should be served on the Board and the parties. Thank you for your consideration. Yours truly, , eorge Dana B bee enior Assistant Attorney General nvironmental Protection Bureau gg .g'/-/ b f ures gg' ,1 cc: Seabrook Service List
]
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CERTIFICATE OF SERVICE J, George Dana Bisbee, hereby certify that on the If day of W/ , 1986, I made service of the within documentsby mailing copies t'tereof, postage prepaid, to: Administrative Judge Helen Hoyt Administrative Judge Sheldon J. Chairperson Wolfe, Chairman Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Board Panel U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, DC 20555 Washington, DC 20555 Dr. Emmeth A. LueDKe Dr. Jerry Harbour Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Board Panel U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, DC 20555 Washington, DC 20555 Philip Ahrens, Esquire Thomas J. Dignan, Jr., Esquire Deputy Attorney General R. K. Gad, III, Esquire Department of the Attorney General Ropes & Gray State House Station 6 225 Franklin Street Augusta, ME 04333 Boston, MA 02110 Carol S. Sneider, Esquire Sherwin E. Turk, Esquire Assistant Attorney General Deputy Assistant Chief Department of the Attorney General Hearing Counsel One Ashourton Place, 19th Floor Office of the Executive Counsel Boston, MA 02108 Director Ms. Diana P. U.S. Nuclear Regulatory Commission Randall Washington, DC 20555 70 Collins Street Seabrook, NH 03874 Robert A. Backus, Esquire Backus, Meyer & Solomon Diane Curran, Esquire 116 Lowell Street Barmon & Weiss P. O. Box 516 20001 S Street, N.W. Manchester, NH 03105 Suite 430 Washington, DC 20009 Anne Verge, Chairperson Board of Selectmen Jane Doughty Apt. 2056 Old Englisn 5 Market Street Dover, NH 03820 Portsmouth, NH 03801 m-,y - -. .- _ _ _ _ ___ - _
a: 9.. ), Paul McEachern, Esquire Matthew T. Brock, Esquire J. P. Nadeau, Esquire Shaines & McEachern Selectmen's Office 25 Maplewood Avenue 10 Central Road i P. O. Box 360 Rye, NH 03870 Portsmouth, NH 03801 ; Mr. Calvin A. Canney Ms. Roberta C. Pevear City Manager The Town of Hampton Falls City Hall Drinkwater Road 125 Daniel Street Hampton Falls, NH .03844 Portsmouth, NH 03801 Mrs. Sandra Gavutis Mr. Angie Machiros
.The Town of Kensington Chairman of the RFD 1, Box 1154 (Route 107) Board of Selectmen Kensington, NH 03827 Town of Newbury Newbury, MA 01950 -
Senator Gordon J. Humphrey Mr. Richard E. Sullivan U.S. Senate Mayor Washington, DC 20510 City Hall (Attn: Tom Burack) Newburyport, MA 01950 Senator Gordon J. Humphrey William S. Lord 1 Pillsbury Street concord, NH 03301 Board of Selectmen Town Hall (Attn: Herb Boynton) Friend Street Amesbury, MA 01913 Mr. Thomas Powers Brentwood Board of Selectmen i Town Manager RFD Dalton Road Town of Exete'r Brentwood, NH 03833 10 Front Street Exeter, NH 03833 Gary W. Holmes, Esquire Holmes & Ells H. Joseph Flynn 47 Winnacunnet Road i- Assistant General Counsel Hampton, NH 03841 Office of General Counsel Federal Emergency Management Richard A. Hampe, Esquire Agency Hampe & McNicholas 500 C Street, S.W. 35 Pleasant Street Washington, DC 20472 Concord, NH 03301 Mr. Ed Thomas FEMA, Region I John W. McCormack Post Office and Court House Post Office Square Boston, MA 02109 f v b ' George Dana Bisbth ' i i.
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App 1373/ Ge ATTENTION: JIM MACDONALD 32- Define and docusient_the interaction between g6[4] tNr . porate EP staf f and the station staf f. 85- Assign the responsibility to performthe initial avne assessment on shift and revise Appendix A of Emergency Plan accordingly. (85-32-86): Provido additional qualified alternates for a h M key ERO positions to assure the ability to staff the g(pf augmented organization on a 24 hour basis. (85-32-97): Complete arrangements with offsite survey groups to ensure availability of of f site support during , emergencies. (85-32-09): Complete implementation of the respiratory protection program (training and air bottle refill capability). X (85-32-19): Complete installation of equipment in the First-Aid Facilit . 6f
-12/13):( % re that arrangements for transportation f .;i , contaminated /in.jured personnel are mad 6and described in plans and procedures.
~
(85-32-14a)': Paragraph 3.2 (et al) of EPIP ER-2.2 is not consistent with the requirements of 10 CFR 50.72, in that it does not require notification of the NRC immediately after the state (s) and within one hour. (85-32-14c): Form ER 2.2A, " Initial Notification Fact Sheet", does not contain provisions f or recording or (NUREG-0654 reporting whether a release is in progress l II.E.3). (85-32-14d): No on-shift dose assessment capability is . provided. i
>< (85-32-14h): Shift operating crews were not aware of containment design leak rate specifications.
(85-32-141): Shift operating crews were not aware of the g capabilities of the Post Accident Sampling System (PASS). (85-32-15b): Qualification criteria for assignment to positions in the Emergency Response Organization were not spectfied. (85-32-15d):...EP training instructors do not meet the . . . . _ _ . . . . . experience requirements of ANSI /ANS-3.1. ~~
,3-
, _, 5 ^ e t x;
(85-32-18): Complete procedures eshich describe the equipment and organization of the Media Center.
%32-19)Minalize the meteorological system design
-.. wns with FSAR commitments, and revise description in the Emergency Plan.
(85-32-29): Provide for backup meteorological measurements l representative of conditions in the vicinity of the site. (85-32-21): Provide a method for notification of impending severe eseather to the Control Room. (85-32-22): Implement surveillance program procedures for meteorological equipment. (85-32-23): reflect minimum Modify requiredcalibration accuracy procedure of delta-TIX-1654.418[toA W 3'3 instrumentation of B.1 degrees centigrade. (85-32-24): Provide for maintaining a historic record of basic data required for atmospheric dispersion calculations. B-9 b )meroency Plan. Chanter 5. Section 1 does not
.mny wnich responsibilities of ERO staff members may not <
be delegated.
^(86-18-82): The Security Officers
- Lesson Plan does mot - '
include discussion of the use of KI as a possible protective action. (86-18-93): Periodic radiological retraining of the hospital staff has not been developed or scheduled. (86-18-84): Mitigation of core damage training is not required for the Response Manager, EOF Coordinator, Short Term Emergency Diractor, Site Emergency Diroctor, or the Emergency Operations Manager. (86-lhj PEETPAC Operator and sample analysis personnel
._- described in the Emeroency Plan as augmentation
~
personnel. 86-18 k Procedure ER-1.4 does not pravide for (or
=11 " .f protective action recommendations (PAR) to be..
eade unless a General Emergency has been declared. [-[4
' ~
(86-19-97): The initial dose assessment ebdel as'ouses rN iodine in the release. . . . . (86-18-98): Complete operational. . testing. And turnsyver._spf_ . the Radiation Data Monitoring System. .-
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- p e . emme me.e .e** .e w p _ -m_ , o =
(86-18-89): Complete the revision to ER-4.4, "Onsite Medical Emergency". (86-18-18): Complete and implement the Estater Hospital Radiological Procedure Manual. (86-18-11): Installation of instrumentation in the TSC is not complete (MURES-9654 II.H.5). (86-18-12): Implement the station security program and demonstrate the ability to perform accountability of onsite i personnel during an emergency. i (86-18-13): Provide backup emans of communication with off-site radiological teams in event of loss of radio communications. . (86-18-14): Include specific instructions to Off-site Monitoring Coordinator regarding use of respiratory equipment and KI in procedures. (86-18-15): Draft appropriate procedures for the perf ormance of on-site (out-of ple.nt) radiological surveys. (86-18-16): Distribute interim public information brochures, providing basic information concerning what action to take on siren activation, where to receive additional information, etc. _ __ _ -
,y.
l (86-18-17): Distribute final detailed public inf ormation e c, brochures describing all necessary emergency planning . l inf ormation for the public, including evacuation routes. (86-18-18): Revise T.S. 6.4.2 and implement the GA audit b. program f or emergency proparedness. (86-18-19): Promulgate final version of emergency, alarm, and abnormal procedures. (86-18-28): Train operators in the final versions of emergency, abnormal, and alare procedures.
~
(86-18-21): Revise procedurie~ss ER 1.2-1.5 to reflect that the authority to authorize notif.ication cannot be delegated to the ECF Coordinator. (86-19-22): The Followup 'Neptification NorIns in procedures ER-1.2 through ER-1.5. do n.p). include _igigreetion regarding type of release, projected integrated does at the site boundary, and projected deep. rate _pr. integrated dose,at ten - oiles.
-,---w---.wevm.-----v------ - - - . - - _- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
(86-18-23): ER-1.3, Figure 1, does not identif y the on-shif t W technician as an alternate Advisor, to be consistent with ER-4.1. (86-19-24): Procedure ER-1.4 contains an error concerning the selection of evacuation alternatives as a function of wind direction...has evacuation to the dog track when wind is blowing toosard the track. (86-19-25): W 41 calculator cannot be used to calculate the doses at 2, 5, and is elles required by procedures ER-1.5 and 2.2. 1 Item E of Faarnancy Plan pas. A-1 and A-2
...vosa be identified as a non-delegable f unction.
- The listing of primary and alternate staf fing i,, ,pendix A of the Plan is not consistent with ER-2.1 (e.g. SED).
(86 Revise ER-1.1 and _FSAR to be consistent with of NUREG-8654. g (86-18-29): Ieplement site Security Plan. (86-18-38): Complete security training for station personnel.
- m 6- Verify that all letters-of-agreement are _
en =~ % . C- fk (86-18-32): Complete the orientation and of f-site training prograe for New Hampshire and Massachusetts state and local officials. DrG-ts- 3 4) c. .px e rc wsn,asrw ,ws regring oy pess (sms). l
. TG -l8-39) Com f>/ ETE IAs s rn tl +Ttop n a/b TEs r/A of Pas s .
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O KLD ASSOCIATES i INCORPORATED
- ggg 300 BMoADWAY le#8TINGTON STATION, NY11748 SIS) 54H003
- May 30, 1986 Mr. Michael J. Nawoj, Director -
Technological Hazards Division New Hampshire civil Defense Agency State Office Park South 107 Pleasant Street
- concord, NH 03301 RE: Telecon of 26 May, 1986
Dear Mike,
The purpose of this letter is to outline the differences between the draft Final Report entitled, l - Seabrook Stat' ion ' Evacuation Time Estimates and Traffic Management Plan Update which was published 1 May 1986 and the seven Progress Reports i which were published in sequenc,e from November 1985 through April 1986. As noted in the Preface of the draft Final Report, these differences reflect editorial changes and extensions. None of these changes, in our view, substantively impacts the contents of these Progress Reports. We indicate the relationship between the draft Final Report and the earlier Progress Reports in the following text. Section 1 Text was added to provide a more complete description of the ' EPZ -- see Section 1.2. The General Highway Map was extended to show the EPZ boundary and Figure 1-2 was added to provide an ' overview of the geographical region around Seabrook Station. Table 1-1, providing climatic information was also added. Section 1-3 presented an overview of the activities performed so as to orient the reader. Figure 1-3 is new and presents the evacuation network, showing the direction of evacuating traffic; I jh Z /) -U' 7' I N/ay ; I c-,,-.--, ,v,nn,-,-- n. --
Pag 3 2 C> 4 all origin centroids, links and nodes; all communities and their boundaries and all ERPA boundaries; as well as the 2, 5 and ! 10-mile circular areas centered at Seabrook Station. This map, in color, serves as a valuable reference for the reader. l
- Section 2 This section is a direct copy of Section 4 of Progress Report No. 1. The lone exception is the removal of the subsection on .
Nanufacturing and Industrial Employment which was obsoleted by i information received subsequently and documented in Progress Report No. 2. Section 3 No. 1. This section is a direct copy of Section 5 of Progress Report We added Table 3-1 in response to a request by FEMA. The
- ,sub-section on recommended highway improvements was added as.
i suggested in NUREG 0654. A sub-section on ocean fog was added. . Section 6 of Progress Report No. I was discarded as it was obsoleted by later studies. i - l Section 4 As No. 2. This section is a direct copy of Section 8 of Progress Report j Section 5 I' No. 2. This section is a direct copy of Section 9 of Progress Report Section 6 i No. 2. This section is a direct copy of Section 9 of Progre's s Report Section 7 This section is a direct copy of Section 11 of Progress Report No. 2. One paragraph was omitted and some text was changed to indicate that these controls were no longer
" preliminary".
(
h- P2g3 3 - Section 8 This section is a concatenation of Sections 16 and 17 of Progress Report No. 4, suitably updated to reflect comments by pol:.co chiefs of communities within the EP3. The discussion of evacuation route signing was extended to provide for an alternative to permanent installations. 5 Section 9 , This section is a direct copy of Section 21 of Progress Report No. 6. The ACP within Newington just south of Pease AFB was removed as it was considered to be unnecessary by N.H. State Police. Those TCP within the EPZ which would also serve as ACP under specific circumstances, were identified in a new Table 9-5. Section 10 T'his section synthesizes the contents'of Progress Repo'rts Nos. 3 and 5. The sensitivity studies in Section 14 of Progress Report No. 3 which dealt with Scenarios 11 were discarded. The results obtained for these scenarios indicted that the implementation of additional controls would not yield benefits in the form of significantly reduced ETE and would consume personnel resources which would likely be more effective elsewhere. The other sensitivity study results were retained. The bulk of this section is a direct copy of Section 19 of Progress Report No. 5. Additional sensitivity studies addressed the prospect of an "Immediate" General Emergency, as compared with the Planning Basis which asserts a time lag of 25 minutes between the sounding of the sirens and the order to Evacuate. The " roses" of Fipres 32 through 41 in Progress Re, port No. 5 were reviewed and refined. Any changes in the numerics were extremely small and not at all substantive, with one exception: on some roses, the demand associated with the Seabrook (greyhound) Park was inadvertantly omitted. Table 10-10 includes the ETE for the Special Population grouping and the Confirmation Time. Section 11 This section is a direct copy of Section 23 in Prgrass Report No. 7, with some editorial changes. Tables 32 in Section 23 were moved into Section 10 of the draft Final Report.
, . 4 ,'f '
Page 4 sections 12 and 13 These sections are direct copies of section 24 and 25, respectively, of Progress Report No. 7. 9.thSE Other changes are editorial in nature. Changes in text were designed to correct typo errors and to clarify communication with the reader. I trust the above summary is responsive to your request. If you have any questions, let me know.
, , .. Yours truly,
~
f,eL./'pf/~... Edward Lieberman, P.E. Vice President ), i EL:ab l \ \ l cc: T. Calandrello B. Hausner I l
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a
/ NUREG/CR-4540 BNL/NUREG-51961 A REVIEW OF THE SEABROOK STATION PROBABILISTIC SAFETY ASSESSMENT: CONTAINMENT FAILURE MODES AND RADIOLOGICAL SOURCE TERMS M. Khatib-Rahbar, A. K. Agrawal, H. Ludewig and W. T. Pratt February 1986 i
l l Department of Nuclear Energy l Brookhaven National Laboratory l Upton, New York 11973 l l t l for n 7 E//4 i
,. 3 -111-ABSTRACT SafetyAAssessment technical review andperformed. has been evaluation of the Seabrook Station Probabilistic It is determined that (1) containment response to severe core melt accidents is judged to be an important factor in mitigating the consequences, (2) failure during the first few hours after core melt is also unlikely and the timing of overpressure failure is very long compared to WASH-1400, (3) the point-estimate radiological releases are compa-rable in magnitude to those used in WASH-1400, and (4) the energy of release is somewhat higher than for the previously reviewed studies. 1
g
-iv- t' ACKNOWLEDGMENT The authors are grateful to R. A. Bari (BNL), W. Lyon, J. Rosenthal (USNRC), J. Moody (YAC), and A. Torri (PLG) for their review and many helpful remarks on this manuscript. The authors also wish to thank T. Skelaney for the excellent job in typing the many versions of the manuscript. The work reported herein was conducted under the auspices of the United States Nuclear Regulatory Commission (USNRC), Office of Nuclear Reactor Regulation.
h
se. ., -v-4 CONTENTS Page ABSTRACT................................................................ iii ACKNOWLEDGMENT.......................................................... iv LIST OF TABLES.......................................................... vi . LIST OF FIGURES......................................................... vii
- 1. INTR 00VCTION....................................................... 1 1.1 Background.................................................... 1 1.2 Obj e ct i v e a n d Sc ope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.3 Organization of the Report.................................... 1
- 2. PLANT DESIGN AND FEATURES IMPORTANT TO SEVERE ACCIDENT ANALYSIS.... 2 ,
2.1 As s e s sment of Pl a nt De s i g n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.2 Compa ri son wi th Other Pl ants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
- 3. ASSESSMENT OF CONTAINMENT PERFORMANCE.............................. 7 3.1 Containment Analysis Methods.................................. 7 3.2 Containment Failure........................................... 8 3.2.1 Background............................................. 8 3.2.2 De s i g n De s c r i p t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.2.3 Lea kage Rate Cal cul ati on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 3.2.4 Conta i nment Fa i l ure Model . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 4
3.2.4.1 Leak-Before-Failure........................... 22 3.2.4.2 Cl assi fi cation of Fail ure . . . . . . . . . . . . . . . . . . . . . 23 , 3.2.5 Containment Pressure Capacity.......................... 24 3.2.5.1 Concrete Containment.......................... 24 3.2.5.2 Liner......................................... 27 3.2.5.3 Penetrations.................................. 27 3.2.5.4 Containment Failure Probability............... 31 3.2.5.5 Contai nment Encl o su re . . . . . . . . . . . . . . . . . . . . . . . . . 31 3.3 Definition of Plant Damage States and Containment Response C1 asses.............................................. 31 3.4 Containment Event Tree and Accident Phenomenology............. 33 3.5 Containment Matrix (C-Matrix)................................. 38 3.6 Rel ea se Catego ry Frequenci es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44 i j 4 ACCIDENT SOURCE TERMS.............................................. 48 I 4.1 Ass es sment of Severe Accident Sou rce Te rms . . . . . . . . . . . . . . . . . . . . 48 4.2 Sou rce Te rm Uncerta i nty Analysi s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 4.3 Re c ommen d ed So u rce Te rms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56
- 5.
SUMMARY
AND CONCLUSIONS............................................ 60 ,
- 6. REFERENCES......................................................... 62 l
. , . -vi-LIST OF TABLES Table Title Page 2.1 Comparison of Selected Design Characteristics.................... 5 3.1 Containment Operating and Design Parameters...................... 10 3.2 ' Cont ai nment Li ner Penet rati ons . . . . . . . . . . . . . . . . . . . . . . . . . . . .'. . . . . . . 18 3.3 Leak Area Estimates fo Mechanical Penetrations................... 29 3.4 Frequencies of Occurrence of the Plant Damage Stata............. 35 3.5 Containment Response Cl ass De fi nitions . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 3.6 Contai nment Cl ass Mean Frequenci es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3T 3.7 Accident Phase and Top Events for tae Seabrook Containment Event Tree....................................................... 39 3.8 Release Categories Employed in the Seabrook Station Risk Model............................................................ 40 3.9 Si mpl i fi ed Contai nment Matri x f or Seab rook . . . . . . . . . . . . . . . . . . . . . . . 41 3.10 Frequency of Dominant Rel ease Categories (yr 1) ...... . .. . ... .. . . . 45 3.11 Contribution of Containment Response Classes to the Total Core Melt Frequency.............................................. 46 3.12 Release Category Frequency as a Fraction of Core Melt Frequency........................................................ 47 4.1 Seab rook Point-Estimate Rel ease Categories . . . . . . . . . . . . . . . . . . . . . . . 49 4.2 Late Overpressurization Failure Comparison....................... 51 4.3 Comparison of Releases for Failure to Isolate Containment a nd t he By- Pa s s Seq u e n c e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 4.4 Comparison of AB-c and TMLB'-c (BMI-2104) to T3Y and 37.......... 55 4.5 Comparison of 31fi (sum) to V-sequence (Surry).................... 57 4.6 BNL-Suggested Source Terms....................................... 58 4.7 BNL-Suggested Release Characteristics for Seabrook.... .. .. ... . . . . 59 1
j 5.1 Comparison of SSPSA and WASH-1400 Containment Failure i Frequencies...................................................... 61 l
- v. s -vii-LIST OF FIGURES Figure Title Page 3.1 A schematic representation of source term calculation............ 9 4
3.2 Equi pment hatch wi th personnel ai rl ock . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 3.3 Personnel airlock....................................'............ 14 1 3.4 Typi cal hi gh ene gy pi pi ng penetrati on. . . . . . . . . . . . . . . . . . . . . . . . . . . 15 3.5 Typical moderate energy pi pi ng penetrati on. . . . . . . . . . . . . . . . . . . . . . 16 3.6 Typi cal el ect ri c al penet rati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 3.7 Typi cal venti l ati on penet rati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20-3.8 A pictorial representation of leakage categories................. 25 3.9 Estimated radial displacement of containment wa11................ 26 l 3.10 Estimated containment failure fractions.......................... 32 3.11 Definitions of the plant damage states used in SPSS............... 34 5 l
, 1
- 1. INTRODUCTION
1.1 Background
Probabilistic Risk Assessment (PRA) studies have been undertaken by a number of utilities (as exemplified by Refs.1-4) and submitted to the Nuclear Regulatory Commission (NRC) in support of various regulatory actions. Brook-haven National Laboratory (BNL) under contract to the NRC, has been involved in reviewing the accident sequence evaluations, core melt phenomenology, con- \ tainment response and site consequence aspects of the PRAs. This report presents a review and evaluation of the centainment failure modes and the radiological release characteristics v the Seabrook Station Probabilistic Safety Assessment (SSPSA), which was compieted by Pickard, Lowe and Garrick, Inc. (PLG) for the Public Service Company of New Hampshire and ( Yankee Atomic Electric Company in December 1983.5 , 1.2 Objective and Scope The objective of this report is to provide a perspective on severe acci-dent propagation, containment response and failure modes together with radiol-ogical source term characteristics for the Seabrook Station. The determina-tion of accident initiation 6 and propagation into core damage and meltdown sequences was reviewed by the Lawrence Livermore National Laboratory (LLNL) under contract to the Reliability and Risk Assessment Branch of NRC. In the present report, principal containment design features are discuss-ed and compared with those of Zion, Indian Point and Millstone-3 designs. Those portions of the SSPSA related to severe accident phenomena, containment response and radiological source terms are described and evaluated. Numerical adjustments to the SSPSA estimates are documented and justified. 1.3 Organization of the Report At brief review of the Seabrook plant features important to severe acci-dent analysis is presented in Chapter 2 along with comparisons to Zion, Indian Point and Millstone-3 plant designs. Chapter 3 contains the assessment of containment performance. Specifically, the definition of containment response classes and plant damage states, analytical methods, containment failure mod-el, containment event tree and accident phenomenology and the containment ma-trix are reviewed. Chapter 4 addresses the accident source terms together with justifications for adjustment where necessary. The results of this re-view are summarized in Chapter 5.
e , _2
- 2. PLANT DESIGN AND FEATURES IMPORTANT TO SEVERE ACCIDENT ANALYSIS In this section, those plant design features that may be important to an assessment of degraded and core melt scenarios and containment analysis are reviewed. These important features are then compared with the Zion, Indian Point and Millstone-3 facilities to identify commonalities for benchmark comparisons.
2.1 Assessment of Plant Design 4 The Seabrook Station is comprised of two nuclear units each having an identical Nuclear Steam Supply System (NSSS) and turbine generator. The units are arranged using a " slide-along" concept which results in Unit 2 being ar-ranged similar to Unit 1 but moved some 500 feet west. Each unit is a 1150 MWe (3650 MWt), 4-loop, Westinghouse PWR plant. The turbine-generators are supplied by the General Electric Company and the balance of the plant is de-
- signed by United Engineers and Constructors.
Each containment completely encloses an NSSS, and is a seismic Category I reinforced concrete structure in the form of a right vertical cylinder with a hemispherical top dome and flat foundation mat built on bedrock. The inside face is lined with a welded carbon steel plate, providing a high degree of leak tightness. A protective 4 ft. thick concrete mat, which forms the floor i of the containment, protects the liner over the foundation mat. The contain-ment structure provides biological shielding for normal and accident condi-tions. The approximate dimensions of the containment are: Inside diameter 140 ft. Inside height 219 ft. Vertical wall thickness 4 ft. 6 in. and 4 ft. 71/2 in. Dome thickness 3 ft. 6 1/8 in. Foundation mat thickness 10 ft. < t Containment penetrations are provided in the lower portion of the structure, and consist of a personnel lock and an equipment hatch / personnel lock, a fuel transfer tube, electrical, instrumentation, and ventilation penetrations. Each containment enclosure (also known as secondary containment) sur-rounds a containment and is designed in a similar configuration as a vertical right cylindrical seismic Category I, reinforced concrete structure with dome and ring base. The approximate dimensions of the structure are: inside diam-eter,158 ft; vertical wall thickness, varies from 1 ft, 3 in. to 3 ft; and dome thickness, 1 ft, 3 in. l The containment enclosure and enclosure ventilation system is designed to collect leakage from the containment structure and to discharge the leakage to the filtration system of containment.* To accomplish this, the space between the containment enclosure and the containment structure, as well as the pene-tration and safeguards pump areas, are maintained at a negative pressure fol-lowing a design basis accident by fans which take suction from the containment !
- Leakage via connections which pass into the steam and feedline penetrations are expected to bypass this system.
enclosure and exhaust to atmosphere through charcoal filters. To ensure air tightness for the negative pressure, leakage through all joints and penetra-tions has been minimized. A containment spray system is utilized for post accident containment heat removal. The containment spray system is designed to spray water containing boron and sodium hydroxide into the containment atmosphere after a major acci-dent to cool it and remove iodine. The pumps initially take suction from the refueling water storage tank and deliver water to the containment atmosphere through the spray headers located in the containment dome. After a prescribed amount of water is removed from the tank, the pump suction is transferred to the containment sump, and cooling is continued by recirculating sump water through the spray heat exchangers and back through the spray headers. The spray is actuated by a containment spray actuation signal which is generated at a designated containment pressure. The system is completely re- - dundant and is designed to withstand any single failure. The containment isolation system establishes and/or maintains isolation of the containment from the outside environment in order to prevent the re-lease of fission products. Automatic trip isolation signals actuate the ap-propriate valves to a closed position whenever automatic safety injection oc-curs or high containment pressure is experienced. Low capacity thermal elec-tric hydrogen recombiners are provided. The emergency core cooling system (ECCS) injects borated water into the reactor coolant system following accidents to limit core damage, metal-water reactions and fission product release, and to assure adequate shutdown mar-gin. The ECCS also provides continuous long-term post-accident cooling of the core by recirculating borated water between the containment sump and the reac-tor Core. The ECCS consists of two centrifugal charging pumps, two high pressure safety injection pumps, two residual heat removal pumps and heat exchangers, and four safety injection accumulators. The system is completely redundant, and will assure flow to the core in the event of any single failure. The control building contains the building services necessary for contin-uous occupancy of the control room complex by operating personnel during all operating conditions. These building services include: HVAC services, air purification and iodine removal, fresh air intakes, fire protection, emergency breathing apparatus, communications and meteorological equipment, lighting, and housekeeping facilities. Engineered Safety Feature (ESF) filter systems required to perform a safety-related function following a design basis accident are discussed below:
- a. The containment enclosure exhaust filter system for each unit col-1ects, filters and discharges any containment leakage. The system is not normally in operation, but in the event of an accident, it is placed in operation and keeps the containment enclosure and the building volumes associated with the penetration tunnel and the ESF equipment cubicles under negative pressure to ensure all leakage from
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to the plant vent. o
- b. One of two redundant charcoal filter exhaust trains is placed in op-f eration in the fuel storage building whenever irradiated fuel not in -
> a cask is being handled. These filter units together with dampers e -
and controls will maintain the building at a negative pressure. u N The emergency feedwater system supplies demineralized water from the' con-densate water storage tank to the four steam generators upon loss of normal ,
' feedwater flow to remove heat from the reactor coolant system. Operation of.
the system will continue untti the reactor coolant system pressure is reduced 1 f to a value at which the .esidual heat removal system can be operated. The combination of one turbine driven and one motor-driven emergency feedwater- ! pump provides a diversity of power sources to assure delivery of conder. sate
, < under emergency conditions. ,
x The two units of the facility are interconnected to off-site power via three 345 kilovolt lines of the transmission system for the New England states. The normal preferred source of power for each unit is its own main turbine generator. The redundant safety feature buses of each unit are power- ! ed by two unit auxiliary transfomers. A highly reliable generator breaker is
,, provided to isolate the generator from the unit auxiliary transformers in the yf- event. of a generator trip, thereby obviating the need for a bus transfer upon '
j loss of turbine generator power. In the event that the unit auxiliary trans- ', formers are not available, the redundant safety feature buses of each unit are powered by two reserve auxiliary transformers. Upon loss of off-site' power, i each unit is supplied with adequate power by either of two fast-startin(; diesel-engine generators. Either diesel-engine generator and its associated safety feature bus is capable of providing adequate power for a safe shutdown i, under accident conditions with a concurrent loss of off-site power. A con-stant supply of power to vital instruments and controls of each unit is assur-i ed through the redundant 125 volt direct current buses and their associated
, ) battery banks, battery chargers and inverters.
\ 2.2 Comparison with Other Plants Table 2.1 sets forth the design characteristics of the Zion, Indian Point-2, and Millstone-3 facilities as they compare to the Seabrook station.
It is seen that the containment characteristics are quite similar with the i exception of the containment operating pressure for Millstone-3 (subatmos-pheric design), the use of fan coolers in Zion and Indian Point for post-acci- '
- dent containment cooling, lower reactor cavity configurations, and the chemi-1
, cal composition of thoconcrete mix. The primary system designs are nearly ,
identical between the four units. ' ~
< The Seabrook containment building basemat and the internal concrete f /g structures are composed of basaltic-based concrete. As concrete is heated,
< water vapor and other gases are released. The initial gas consists largely of carbon dioxide, the quantity of which depends on the amount of calcium carbon-ate in the concrete mix. 1.imestone concrete can contain up to 80% calcium carbonate by weight, which could yield up to 53 lb of carbon dioxide per cubic foot of concrete. However, basaltic-based concrete contains very little cal-cium carbonate (3.43 w% for Seabrook) and would not release a substantial
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. . Table 2.1 Comparison of Selected Design Characteristics Zion Design Parameters Unit 1 IndianPgint Unit 2 Mllistg Seabrook Unit 3 e Unit 1,2 Reector Power (Mw(til 3,250 3,030 3,411 3,650 Containment Bulld!ng Free Volume (ft ) 2.73 x 100 2.61 x 10 6
2.3 x 106 2.7 x 106 Design Pressure (psla) 62 62 59.7 67.7 Initial Pressure (psla) 15 14.7 12.7/9.1 '*.2 . Initial Tamperature (*F) 120 , 120 120/80 120 Primary Systan t
- Water Volume ( f t3.' 12,710 11.347 11,671 13,140 Steen volume (ft ) 720 720 7 2,012 Mass of UO2 In Core (ib) 216,600 216,600 222,739 222,739 Moss of Steel in Core (Ib) 21,000 20,407 7 19,000 Moss of Zr in Core (lb) 44,500 44,600 45,296 45,234 Moss of Bottom Head (lb) 87,000 78,130 87,000 87,000 Bottom Head Diameter (ft) 14.4 14.7 14.4 14.4 Bottom Head Thickness (ft) 0.45 0.44 0.45 0.45 Steam Generator System inventor'y per Generator (Ibe) 77,C00 - 82,000 113,600 112,000 Containment Building Coolers:
Sprays yes yes yes yes Fans (with safety function) yes yes no no Acetsuulator Tanks: Total Mass of water (Ib) 200,000 173,000 348,000 213,000 Initial Pressure (psla) 665 665 600 615 - Tenperature f'F) 150 150 80 100-150 Refuelino water Storace' Tank Total Mass of water (Ib) 2.89 x 10 2.89 x 106 Temperature 10 2.89 x 10 6 (
- F) 100 120 50 86 Reactor Cavity: ~
ConfIguratton wet Wet Dry Dry / wet Concrete Material Limestone Basaltic Basaltic Basaltle w
' Minimum (Meximise Opacity = 3.9 x 10 6 l b)
+ amount of carbon dioxide.s Thus, pressurization of the containment as a result of corium/ concrete interactions would be expected to take a very long time. In Table 2.1 the reactor cavity configuration is described as either wet or dry. Wet means that the reactor cavity configuration is such that for a wide range of accident sequences the cavity would be flooded. This means that if the reactor core melts down and f alls into the cavity it would contact significant quantities of water. This has important implications in terms of ultimately cooling the core debris and perhaps preventing core / concrete inter-actions. It is also important in terms of containment pressurization because boiling water by the core debris is a much more efficient way of building up pressure in containment than by core / concrete interactions. Dry in Table 2.1 implies that the reactor cavity configuration is such that for a wide range of accident sequences the cavity would not be flooded thus extensive core / con-crete interactions wauld be expected. e
- 3. ASSESSMENT OF CONTAINMENT PERFORMANCE In this chapter, the review of containment response to severe accidents is described. Analytical techniques used to analyze core meltdown phenomena and containment response are reviewed, the containment failure model is assessed, plant damage states and containment failure modes are evaluated.
Parallels between this study and other PRAs are made. Finally, the relevance and validity of the conclusions is addressed. 3.1 Containment Analysis Methods A brief description of the computer codes used to perform the transient degraded, core meltdown and containment response analyses is provided in this section. The MARCHs computer code is used to model the core and primary system transient behavior and to obtain mass and energy releases from the primary, system until reactor vessel failure. These mass and energy releases are then used as input to the other computer codes for analysis of containment re-sponse. For sequences in which the reactor coolant syst$m remains at an elevated pressure until the vessel failure (" time-phased dispersal"), the MODMESHS computer code is used. This code calculates the steam and hydrogen blowdown from the reactor vessel using an isothermal ideal gas model. The water level Loil-off from the reactor cavity floor is modeled using a saturated critical heat flux correlation. Additionally, the accumulator discharge following de-pressurization caused by the vessel failure is also considered. A modified version of the CORCON9 code is used to replace the INTER 8 sub-routine of the MARCH code. CORCON models the core-concrete interaction after the occurrence of dryout in the reactor cavity. The mass and energy releases from the core-concrete interaction are transferred to the MODMESH code for proper sequencing and integration into the overall mass and energy input to C0C0 CLASS 95 code. COC0 CLASS 9, a modified version of the Westinghouse COC0 computer code utilizes the mass and energy inputs to the containment as computed by MARCH to model the containment building pressurization and hydrogen combustion phenom-ena. This code replaces the MACE subroutine of the MARCH code. The code also models heat transfer to the containment structures and capability for contain-ment heat removal through containment sprays and sump recirculation. Fission product transport and consequence calculations are performed using the CORRAL-II and the PLG proprietary CRACIT S computer codes, respec-tively. The analytical methods used to carry out the core and containment thermal hydraulics, and fission product transport calculations are identical to those used for MPSS-3.7
8 . 4 3.2 Containment Failure j 3.2.1 Background In order to assess the risk of the Seabrook-1 plant, radiological source I terms have to be calculated. Many steps are involved in such calculations. These are schematically shown in Fig. 3.1. The mode and time of containment failure directly impact on the radioactivity release categories. These, when coupled with the status of reactor cavity and the spray system, determine the source terms. This section deals with the mode and time of containment fail-ure. 3.2.2 Design Description The primary containment of the Seabrook plant is a seismic Category I re-inforced concrete dry structure. It consists of an upright cylinder topped with a hemispherical dome. The inside diameter of the cylinder is 140 feet
- and the inside height from the top of the basemat to the apex of the dome is approximately 219 feet. The cylindrical wall is 4'6" thick above elevation 5' and 4'7-1/2 " thick below that evaluation. The dome is 3'6-1/8" thick and 69'11-7/8" in radius. The cylinder is thickened to provide room for addition-al reinforcing steel around the openings for the equipment hatch and the per-sonnel 6 3 airlock. The net free volume of the containment is approximately 2.7 x 10 ft .
The inside of the containment is lined with a welded steel liner. The liner plate in the cylinder is 3/8" thick in all areas except penetration and the junction of the basemat and cylinder where it is 3/4" thick. This liner serves as a leak-tight membrane. Welds that are embedded in the concrete and not readily accessible are covered by a leak chase system which permits leak testing of t'.cse r welds throughout the life of the plant. The dome liner is 1/2" thick and flush with the outside face of the cylindrical liner. The op-erating and the design parameters of containment are noted in Table 3.1 The containment building is surrounded by an enclosure. The containment enclosure is a reinforced concrete cylindrical structure with a hemispherical dome. The inside diameter of the cylinder is 158 feet. The vertical wall varies in thickness from 36 inches to 15 inches; the dome is 15 inches thick. The inside of the dome is 5'6" above the top of the containment dome. Located at the outside of the enclosure building is the plant vent stack, consisting of a light steel frame with steel plates varying in cross-section. The stack carries exhaust air from various buildings. The containment enclosure is designed to control any leakage from the containment structure. To accomplish this, the space between the containment and the enclosure building (approximately 4'6" wide) is maintained at a slight negative pressure (-0.25" water gauge) during accident conditions by fans which take suction from the containment enclosure and exhaust to atmosphere through charcoal filters. There are a number of containm?nt penetrations which are steel components that resist pressure. These penetrations are not backed by structural con-crete and include the following:
c . '. 9 CONTAINMENT TIME OF FAILURE FAILURE MODE WET OR ORY RELEASE SPRAY REACTOR CAVITY CATEGORY SYSTEM o SOURCE TERM i Figure 3.1 A schematic representation of source term calculation. I 1 l
Table 3.1 Containment Operating and Design Parameters Parameter Value Normal Operation Pressure , psig 0.5 Inside Temperature , F 120 Outside Temperature , F 90 Relative Humidity , % 45 Service Water Temperature , F 80
- Refueling Water Temperature , F 86 Spray Water Temperature , F 88 Containment Enclosure Pressure , inches .*.g, -0.25 Design Conditions Pressure , psig 52.0 Temperature , F 296 Free Volume , ft 3 2.7x106 Leak Rate , % mass / day 0.2 Containment Enclosure Pressure , psig -3.5
. . 1. Equipment hatch,
- 2. Personnel air lock,
- 3. Piping penetrations, 4 Electrical penetrations,
- 5. Fuel transfer tube assembly,
- 6. Instrumentation penetrations, and
- 7. Ventilation penetrations.
These components penetrate the containment and containment enclosure shells to provide access, anchor piping, or furnish some other operational requirement. All penetrations are anchored to sleeves (or to barrels) which are embedded in the concrete containment wall. Equipment Hatch The equipment hatch (Fig. 3.2) consists of the barrel, the spherical dished cover plate with flange, and the air lock mounting sleeve. The center-line of the hatch is located at elevation 37'1/2" and an azimuth of 150*. The' hatch opening has an inside diameter of 27'5". A sleeve for a personnel air lock, the inside diameter of which is 9'10", is provided at centerline eleva-tion 30'6". Thicknesses of the primary components are as follows: Component Thickness (inches) Barrel 3 1/2 Spherical 1 3/8 Fl ange 5 3/8 Air lock mounting 1 1/2 sleeve The equipment hatch cover is fitted with two seals that enclose a space which can be pressurized to 52.0 psig. The flange of the cover plate is at-tached to the hatch barrel with 32 swing bolts,1-3/8 inch in diameter. The barrel, which is also the sleeve for the equipment hatch, is embedded in the shell of the concrete containment. The equipment hatch cover can be lifted to clear the opening. Inserted into the mounting sleeve through the equipment hatch cover is a personnel air lock consisting of two air lock doors, two air lock bulkheads, and the air lock barrel. Significant dimensions of the air lock are as follows: - Parameter Dimension Inside Diameter of Barrel 9'6" Barrel Thickness 1/2" - Door Opening 6'8" x 3'6" Door Thickness 3/4" Bulkhead Thickness 1-1/8" Each door is locked by a set of six latch pin assemblies, and is designed to withstand the design pressure from inside the containment. To resist the test pressure, each door is fitted with a set of cast clamps. The doors are hinged and both swing into the containment. Each door is fitted with two seals that l . i ^
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are located such that the area between doors can be pressurized to 52.0 psig. The doors are mechanistically interlocked so that only one door can be opened at a time. The capability exists for bypassing this interlock to equalize the pressure by use of special tools. The doors may be operated mechanically. Personnel Air Lock The personnel air lock (Fig. 3.3) consists of the air lock doors (2) and the lock barrel. The barrel, which is also the sleeve for the personnel air lock, is imbedded in the shell of tne concrete containment. The centerline of the barrel is located at elevation 29'6" and an azimuth of 315*. Significant dimensions are as follows: Parameter Dimensions Clear Opening 7'0" 0.D. of Flange on Door 7' 9 1/8" , Barrel Thickness 5/8" Cover Thickness 5/8" The air lock barrel has a door on each end, each of which is designed to withstand the design pressure from inside the containment. The doors are hinged and swing away from the air lock barrel. Each door is fitted with two seals that are located such that the area between doors can be pressurized to 52.0 psig. The locking device for the doors is a rotating, third ring, breach-type mechanism. These doors are also mechanically interlocked so that only one door can be opened at a time. The capability exists for bypassing this interlock and relieving the internal pressure by use of special tools. The doors may be operated mechanically. Piping Penetrations There are two types of piping penetrations: moderate energy and high energy. Moderate energy piping penetrations are used for process pipes in which both the pressure is less than or equal to 275 psi, and the temperature of the process fluid is less than or equal to 200*F. High energy piping pene-trations are used for that piping in which the pressure or temperature exceeds these values. High energy piping penetrations (Fig. 3.4) consist of a section of pro-cess pipe with an integrally-forged fluid head, a containment penetration sleeve and, where a pipe whip restraint is not provided, a penetration sliding support inside the containment. The sliding support provides shear restraint while permitting relative motion between the pipe and the support. The annu-lar space between the process pipe and the sleeve is completely filled with fiberglass thermal insulation. The pipe and the fluid head, are classified as ASME III Safety Class 2 (NC), whereas the sleeve is classified as part of the concrete containment, ASME III (CC). The sliding support inside the contain-ment is classified as an ASME Safety Class 2 component support (NF). Moderate energy piping penetrations (Fig. 3.5) consist of one or more process pipes, the containment penetration sleeve, and a flat circular end-pl ate . The pipe is classified as ASME III Safety Class 2 (NC). The sleeve is classified as ASME III Div. 2 (CC). The end-plate is classified as Class MC.
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- l Table 3.2 gives a list of the containment piping penetrations. Included in this table is the penetration size. All of these piping penetrations are in the lower portion of the structure.
Electrical and Instrumentation Penetrations Electrical penetrations (Fig. 3.6) consist of a stainless steel header plate with an attached terminal box, electrical modules which are clamped to the header plate, and a carbon steel weld ring which is welded to the header plate and to the sleeve. The metallic pressure resisting parts, the sleeve, stainless steel header plate and carbon steel weld ring were designed as ASME III Safety Class MC components (NE); that portion of the sleeve which is backed by concrete was designed as part of the concrete containment, ASME III (CC). Double silicone and Hypalon 0-rings provide a seal with a cavity for leakage monitoring between the header plate and the modules. The header plate is provided with a hole on the outside of the containment to allow for ' pressurization of the penetration assembly for leakage monitoring. There are a total of 64 electrical penetrations out of which 14 are spare and 8 are unused. All of these electrical penetrations are below the grade. Instrumentation penetrations are of two types -- electrical and fluid.
- The electrical type is similar in construction to the other electrical pene-
, trations. The fluid penetrations are si v in construction to the moderate ! energy piping penetrations. Fuel Transfer Tube Assembly The fuel transfer tube assembly consists of the fuel transfer tube, the penetration sleeve, the fixed saddle on the reactor side, and the sliding sad-die in the fuel storage building. The fuel transfer tube centerline is at elevation (-)9'4-1/4" and it has approximately 20" inner diameter. The fuel transfer tube wall penetration sleeve, which is embedded in the concrete, has an inside diameter of about 25". Ventilation Penetrations . There are two types of ventilation penetrations -- the containment air purge penetrations (HVAC-1 and HVAC-2) and the containment on-line penetras tions (X-16 and X-18). The containment air purge penetrations (Fig. 3.7) each consist of a pipe sleeve (a rolled and welded pipe section, 36" outer diameter by 1/2" wall thickness) which is flanged at each end with 36"' weld neck flanges and, attached to these flanges, the inner and outer isolation valves. Together with the pipe, these valves form a part of the containment pressure " boundary. The valves are 36" diameter butterfly valves with fail-safe pneu-matic operators. The weld between the pipe and the containment liner is equipped with a leak chase for pressure testing. The containment on-line purge penetrations each consist of a pipe sleeve (a rolled and welded pipe section, 8" o.d. by 1/2" wall thickness). A short section of pipe with a nipple is welded to the sleeve on the outside of the containment, and a 3/4" valve and test connection is attached to it. The
Table 3.2 Containment Liner Penetrations Penetration Penetration Numbers Service Size X-1 to X-4 Main steam line 30" X-5 to X-8 Main feedwater 18" X-9, X-10 RHR pump suction 12" X-11 to X-13 RHR to safety injection 8" X-14 to X-15 Containment building spray 8" X-16, X-18 Containment on-line purge 8" X-17 Hydrogenated vent header ' 2" X-20 to X-23 CCW supply and return 12" X-24 to X-27 Safety injection 4" X-28 to X-31 CVCS to pump seal injection 2" X-32, X-34 Drain line 3",2" X-33, X-37 CVCS 3" X-35, X-36, X-40 RCS test / sample control X-52, X-71, X-72 1" or smaller X-38 Combustible gas control 10" X-39 Spent fuel pool cooling 2" X-43, X-47, X-50 Instrumentation lines <1" X-57 X-60, X-61 From containment recirculation sump 16" X-62 Fuel transfer tube 20" X-63 to X-66 Steam generator blowdown 3" X-67 Service air 2" HVAC-1,2 Containment purge supply / exhaust lines 36" X-19, X-41, X-42 X-44 to X-46, X-48 Spare ? X-49, X-51, X-58 X-59, X-68 to X-70
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CARBON STEEL WELD RING / ' FIELD WELD SLEEVE JUNCTION (TERMINAL) BOX JUNCT10N BOX Figure 3.6 Tyical electrical penetration.
ISOLATION VALVES ENCLOSURE BUILDING CONTAINMENT WALL SLEEVE - OC
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ends of this resulting assembly are welded to 8" weld neck flanges which are through-bolted to the inner and outer isolation valves. These valves are 8" diameter butterfly valves having fail-safe pneumatic operators. The weld be-tween the pipe sleeve and the containment liner is equipped with a leak chase for pressure testing. These on-line purge penetrations are very similar to those for 36" lines shown earlier. 3.2.3 Leakage Rate Calculation . Under severe accident conditions the pressure inside the containment builds up in the range of 75 to 200 psi. At these pressures, any leakage through the containment holes will essentially be choked. The leakage under choked flow condition is given as (Ref.10): k+1 2 k-1 W= k(kT1) A8 (1) where W = discharge rate (kg/s), A = leak area (m2), P = absolute pressure (N/m2), p = mixture density (kg/m3), and k = ratio of specific heat at constant pressure to that at constant volume. For air and water vapor mixture, k - 1.3. If the mixture density is expressed by perfect gas law p= (2) where R = gas constant, and T = the absolute temperature,
- Then Eq.(1) becomes k+1 W=
2 k-1 k(k+1) [P A V RT (3) The mass of mixture can be written as M=Vp or, M=h (4) where V is the free mixture volume in the containment. Equations (3) and (4) can be combined to get the leakage rate, in terms of mass fraction, as
k+1 W 2 k-1 i g= k(yg) yATA (5) Note that the leakage rate, when expressed in terms of mass fraction, depends only on the leakage area. For Seabrook-1, using V = 2.704x10s ft3 and T = 296 F, Eq.(5) gives Leakage Rate = 0.721 Ain w/o per hour (6) where Ain is the leakage area in in 2 . Alternately, Leakage Rate = 17.3 Ain w/o per day. (7) The essentially intact containment leakage of 0.2 w/o per day, thus, corre-sponds to an equivalent leakage area of 0.012 in2 (or, an equivalent hole of 1/8-in diameter). A leakage area of 4 to 10 in2 would correspond to the leak-age rate of 2.9 to 7.2 w/o per hour. In other words, it will take about 14 hours to leak the entire content to the environment through a 10-in2 hole.
-3.2.4 Containment Failure Model 3.2.4.1 Leak-Before-Failure During accident sequences involving core damage, the containment struc-ture will be exposed to pressures and temperatures beyond those used in the design basis accident (DBA).- Response of the containment building to these severe conditions is evaluated in SSPSA by employing, for the first time, a leak-before-failure model . In this model allowance is made for continuous leakage from the containment to the surroundings. This mode of containment failure is termed local failure. The containment leakage can occur at many locations and discontinuities such as mechanical and electrical penetraticns, personnel lock, equipment hatch, fuel transfer tube, welds, and in between the liner and concrete. Depending upon the size of leakage area and the accident sequence, local failures may gradually relieve pressure, thereby gross con-tainment failure may be averted.
The leak-before-failure model is a realistic one. The extent of leakage and the health consequences must, however, be carefully studied. In order to explain this issue, it is observed that traditionally probabilistic risk as-sessment is made by using what is termed a threshold model. In the threshold model, the containment is considered intact until the internal loading equals or exceeds a pressure threshold (which may also be temperature dependent), at which it is deemed to have suffered a failure (gross). If the internal load-ing is below this threshold value, the containment is considered intact and hence the risk is quite low. In the leak-before-failure model, the release of activity, which is considerably small compared with that for the gross failure mode, must be considered in health consequences. However, such leakages can potentially prevent the internal pressure from approaching the threshold value and thus a catastrophic or gross failure may be avoided.
, . l l
3.2.4.2 Classification of Failure The SSPSA report has classified containment failures in three categories:
. Containment Failure Category A. Includes containment failures that develop a small leak that is substantially larger than the leak ac-ceptable from an intact containment, but not large enough to arrest the pressure rise in the containment. Category A failures thus cause an early increase in the rate of leakage of radionuclides ^over the de-sign basis leak rate but pressurization of the containment continues until either a category B or C containment failure occurs.
The intact containmer.t is defined as the one in which leakage is lim-ited by the Technical Specification value. For Seabrook-1, this vclue is 0.2 w/o per day at the calculated peak accident pressure of approx-imately 47 psig. Note that the SSPSA study has used 0.1 volume per-cent per day for this leakage, although prior to the most recent . amendment dated August 1984, the FSAR has cited both 0.1 volume per-cent and 0.1 w/o per day. The 10CFR50, Appendix J mandates the allow-a51e leakage to be quoted as w/o per day. The higher value noted here is based on Amendment 53, August 1984.*
. Containment Failure Category B. Includes failure modes that develop a large enough leak area so that the pressure in the containment no longer increases. The time during which a substantial fraction of the radionuclide source term is released is longer than approximately 1 to 2 hours. Category B failures include self-regulating failure modes where the leak area is initially small but increases with pressure so that it becomes sufficient to terminate the pressure rise before a category C containment failure occors.
The definition of " substantial" fraction is unclear.
. Containment Failure Category C. Includes those containment failure modes that develop a large leak area. A large fraction of the total radionuclide source term is released over a period of less than 1 hour. All gross failure modes are included in category C.
Mathematically, these three failurt. categories can be expressed in terms of leakage areas as follows: . i ADBA < AA 1 ANP Type A ANP < AB 1 AP Type B (8) AC > AP Type C where ADBA = leakage area corresponding to the technical specification limit for containment leakage,
*There appears to be substantial update / changes in the Engineered Safety Features flow diagram, including arrangements of motor operated valves and bypass lines, which may substantially change the frequency of events. BNL, however, is not reviewing this part of SSPSA.
l
ANP = leakage area not large enough to arrest pressurization, and Ap = leakage area sufficient to release 100 w/o in one hour. The leakage area required to release a substantial fraction of the radio-nuclide source term in approximately an hour can be computed using Eq. (6). l Assuming one-hundred percent turnover as " substantial" fraction in one hour, Eq. (6) gives the required leakage area to be equal to 138 in2 or about 1 ft 2 . If one were to use 50% turnover as " substantial" in an hour, the corre-sponding leakage area would be 60 in2 or about 0.5 ft 2. For the purpose of defining an . upper bound for type B, it seems justified to use 1 ft , hence, leakage area in excess of this value should be considered type C failure. Al-though this estimate of the leak area is a factor of two too high from the value stated in SSPSA, it is not significant in the risk evaluation since , failure categorization is somewhat arbitrary. The leakage area required to arrest containment pressurization is in the range of 4 to 10 square inches. A leak area of about 6 square inches will re-sult in-bound upper the release leak area of about 100Aw/o for Type of activity failure is takeninasa 4dag in . (see Eq. 7). The This corresponds to release of the radioactive source term (100% turnover) in about 36 hours. The Category B leak area is, thus, in the range of 4 in2 to 1 ft2 . Figure 3.8 is a pictorial representation of these leakage categories. 3.2.5 Containment Pressure Capacity 3.2.5.1 Concrete Containment The Seabrook PSA has examined failure modes for the containment structure itself, the steel liner, all penetrations, equipment and personnel lock hatch-es, and the secondary containment. The containment structure includes the cylindrical wall, the hemispherical dome, the base slab and the base slab and containment wall junction. The most critical membrane tension was found to occur in the cylinder in the hoop direction. The median pressure which causes yield of both the liner steel and the reinforcing bars was found to be approx-imately 157 psi, with a coefficient of variation of 0.084. The ultimate hoop load in cylinder is 216 psig. The containment wall is, thus, assumed to fail at this pressure. At pressures beyond this, very large irreversible deforma-tions occur which will cause cracks in the reinforced concrete but the loss of integrity of the pressure boundary may not occur until the liner tears. The compiled radial deformations of the containment wall are shown in Figure 3.9. Note that the radial strain at the expected failure pressure of 216 psi is 4.7% (ar/r). The hemispherical dome was calculated to yield at a slightly higher pres-sure (163 psig). The failure pressure is predicted at 223 psig. The median pressure for flexural failure of the base slab is 400 psig, with a logarithmic standard deviation of 0.25. However, the shear mode of failure is more restrictive. For this mode, the median failure pressure is estimated in SSPSA as 323 psig, with a logarithmic standard deviation of 0.23. Although the uncertainty for failure of the base slab is large, the
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. probability of failure is small because the median capacities are high. Thus, failure of the base slab is not considered to be a critical failure mode and an estimation of leak areas was, therefore, not considered for this mode of failure.
Secondary stresses in the cylindrical portion of the containment occur at discontinuity such as at the base slab containment wall junction, at the l springline, and where the amount of reinforcing changes. The flexural yield j at the base of the cylinder occurs at 175 psi. At higher pressures, a plastic ' hinge forms with considerable cracking of the concrete. These cracks, how-ever, are small enough so as not to threaten the integrity of the liner. The loss of integrity of the liner is not expected until a median pressure of 408 psi is reached. Thus, the failure of the base slab and containment wall junc-tion is not limiting. In summary, the containment wall is expected to undergo significant de-formation (=4.7% ar/r) prior to its failure at 216 psig. At this pressure, , Type C (i.e., gross) failure occurs. 3.2.5.2 Liner The elongation capacity of the steel liner is computed by neglecting the friction forces between the liner and the concrete. The possibility that the liner stresses and strains could be different between two different pairs of tees was, however, considered. The SSPSA computed an elongation of 8.1 per-cent under unaxial conditions, or an elongation of 4.7 percent under plane strain conditions can be achieved without fracture. This would ensure integ-rity of the liner until fracture of the reinforcing bars. Additionally, the leakage of the containment at penetrations is considered likely before hoop failure of the liner. occurs. 3.2.5.3 Penetrations At all major penetrations, the containment wall is thickened and addi-tional reinforcement is provided to resist stress concentrations. None of the meridional or hoop reinforcing bars are terminated at penetrations. Instead, they are continued around the penetrations, thus ensuring that excess hoop and meridional capacity is available. Table 3.2 lists all piping penetrations. As the containment pressure increases beyond its yield value (157 psi), large radial deformations begin to occur. This induces stresses in the pipes by relative displacements between the containment wall and the pipe whip re-straints. Therefore, the most critical penetrations are the areas where the pipe is supported close to the penetration. Also, stronger and stiffer pipes develop higher forces et the penetrations for a given relative displacement. The SSPSA study selected the following penetrations for investigation as being among the lines most likely to fail: Penetration X-23 12" schedule 40 carbon steel (also X-20 to X-22 by similarity) Penetration X-26 4" schedule 160, stainless steel (also X-24, X-25, X-27)
n , 28- - . l Penetration X-71 1" - multiple pipe penetration (also X-72 and possibly others) Penetration X-8 18" main feedwater schedule 100, (also X-5 to X-7) carbon steel
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Fuel Transfer Tube Convoluted Bellows ~ The probability of failure at these penetrations was computed by (a) establishing a pressure-displacement relation, (b) estimating the failure probability as a function of radial displacement and then (c) combining the two. The radial displacements for the containment wall were shown earlier (Fin. 3.9). The vertical displacement due to meridional strains is small (less than 3 inches) and hence its impact on the penetrations was ignored. Since most of these penetrations are in the lower part of the containment,
- the radial displacements experienced by them due to plastic deformation of '
containment would also be small. The multiple penetration (X-71 and X-72) would not fail even for the most unfavorable forces which these pipes could sustain. For penetrations X-23 and X-26, the most likely location for failure is at the partial penetration fil-let welds which join the pipe to the end plate. When failure of this weld oc-curs, the pipe remains in the hole provided in the end plate. The gap between the pipe and the end plate is likely to remain small unless the pipe wall buckles. Exact gap size is hard to compute. The SSPSA appears to use a uni-form gap size of 0.04 in., and 0.10 in as median and upper estimates, respec-tively. The corresponding leak areas for X-23 (as well as X-20 to X-22) and X-26 (as well as X-24, X-25, and X-27) penetrations are shown in Table 3.3. The median failure pressure for X-23 penetration, is higher than the hoop failure pressure (216 psig) of the containment wall. These leak areas, there-fore, are not expected to develop. 1
- Penetration X-26 is expected to fail at a median pressure of 166 psig.
The combined leak area for all safety injection penetrations is obtained by independently adding individual median leak area of 0.5 in2 , Penetrations X-71 and X-72 are not likely to contribute to the overall j leak area, as stated earlier. The main feedwater lines (penetrations X-5 to X-8) are 18-in. diameter, Schedule 100 pipes. The failure mode of most concern is failure of the flued head due to axial loads in the pipe at the penetration. At a median pressure of 180 psig, each one of these penetrations is likely to result in a leak area of 50 in2 each. A leakage area of 50 in2 , either from the failure of one or more - feedwater line(s), will result in a substantial pressure reduction and thereby further deterioration of leakage area may not materialize. Neverthe- , less if all four lines were to fail simultaneously, total leakage area of 200
- in2 may result. In this case it will be category C failure.
i The fuel transfer tube is fixed to an elevated floor inside the contain-ment. As the pressure in the containment increases, the containment wall moves outwards and thereby exerts pressure on the bellows. The most pertinent I-
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( . 29-Table 3.3 Leak Area Estimates for Mechanical Penetrations Median Median Line Penetration Leak Area Failure Pressure Size in2 p3jg X-20 to X-23 6.0 >216 - 12" CCW Surply and Return X-24 to X-27 2.0 166 4" Safety Injection X-71 and X-72 Negligible < l'
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Sample / Control X-5 to X-8 50 to 200 180 18" Main Feedwater Fuel Transfer Tube 3 172 -- X-16, X-18 See Text 8" On-line Purge HVAC-1,2 See Text 36" Containment Purge 40
f bellows from the viewpoint of containment leakage is the one inside the con-tainment (EP-2). Three potential failure modes, in their order of decreasing probability of failure, considered are (a) failure due to overall buckling of the bellows, (b) failure due to local buckling within the convolute, and (c) failure due to meridional bending strains. The SSPSA has estimated median leak area of about 3 in2 at a pressure of about 172 psig. This is a Type A failure. . There are two sets of containment penetrations which are open to the containment atmosphere on the inside. The on-line penetrations (X-16 and X-18) are the 8-inch purge suction and discharge lines and containment purge suction and discharge lines (HVAC-1 and 2) are the 36-inch lines. Each one of these four lines has two containment isolation valves, one inside and one outside the containment. All eight valves are pneumatically operated butter-fly valves. At elevated temperatures, the seal material (usually ethylene propylene) on these valves may deteriorate and lose its sealing function. . Any deposition of radioactive aerosols could further deteriorate the sealant material. Considering sealant degradation due to temperature alone, ethylene propylene seal life (Ref.10) is 5 hours, 40 mts, or 20 mts if exposed to 400, 500 or 600 F, respectively. _ In the event of the failure of the sealant material, a narrow crack leak path may develop and containment atmosphere may begin to leak into the space between the two isolation valves. Since the isolation valves are closed from the containment isolation signal system, the leakage of containment atmosphere to the environment can occur only if the sealant of the outer containment iso-lation butterfly valve also fails. The time duration elapsed before this happens can be significantly long (of the order of hours). The SSPSA has es-timated it to be larg compared to the containment failure by other causes. The SSPSA study, therefore, has disregarded this release path. The available leakage area due to sealant degradation has been estimated (Ref.10) by assuming an equivalent clearance of 1/16 inch between valve disc and body for ' low' and 1/8 inch for 'high' estimates. This gives a total leakage area of 17 inz as low value and 34 in2 as high value. As noted ear-lier, the outer butterfly valves must also experience high temperatures prior to a through release path. This leak area is of Category B. The SSPSA study has argued that such a leak path is not likely to result prior to a gross containment failure (Category C). Electrical penetrations can fail primarily due to overheating of the pot-ting compound. The SSPSA study has concluded that the failure of electrical penetrations is not expected to make a significant contribution to containment failure for any accident sequence. This conclusion, appears justified for the wet case, but, for the dry case, it is based on their estimate of slow over-heating of the potting compound. A careful thermal conduction calculation should be made to check this assessment. Such a calculation, similar to the problem of vent / purge line butterfly isolation valve failure, is beyond the scope of this work and hence it was not done. The equipment hatch and personnel lock penetrations can fail either due to pressure loading or degradation of the sealant material (generally sili-cone). The structural failure, prior to containment failure, appears unlike-ly. The sealant material can degrade at high temperatures typical of a
(, ,
., 1 '!, i severe acciderd. According to the 0-Ring Handbook (see Ref.10), silicone can survive for twenty hours when exposed to 500 F temperature. Furthermore, the personnel air loc,b is a double door system so even if the sealant around one door were to become ineffective, substantial time delay would be required to make the second scalant also ineffective. It, thus, appears that the equip-ment hatch and personnel lock penetrations do not contribute significantly to Type B failure.
3.2.5.4 Containment Failure Probability l The calculation of the probability of containment failure as a function of the pressure is quite involved. The method used and results reported in the SSPSA study seem reasonable except for the impact of all four main feed-water lines failure. The SSPSA has categorized the failure of X-8 (onc of the four main feedwater lines) penetration as Type B since anticipated it.ak area is 50 in2 It appears to us that when one such penetration fails, the remain-ing three will also fail at nearly the same pressure of 180 psig (195 psia). Any depressurization due to a 50-in2 hole is not likely to be fast enough to
- reduce the containment pressure substantially prior to the failure of the three remaining penetrations. Assuming that all four main feedwater lines fail at 180 psig, an equivalent leak area of 200 in2 will result. This fail-ure, therefore, should be classified as Type C. The impact of this change on the containment. failure probability numbers will be to reduce the rate for Type B with a corresponding increase in Type C. The total failure rate is not likely to; change. Estimated containment failure fractions are compared with the SSPSA results in Fig. 3.10. Use of the modified failure fractions do not seem to cause any appreciable change in the risk estimates.
3.2.5.5 Containment Enclosure The containment enclosure building is designed to withstand 3.5 psi pres-sure difference between the enclosure and the environment. During normal operation, the internal pressure is about -0.25 inches of water gauge. The SSPSA study has calculated its pressure capacity to range from more than 1 psid to 10 psid. In view of relatively strong primary containment, the role of the secondary containment is important primarily for Type B failures of the primary containment. In the event of Type C failure, the secondary enclosure building might not play any significant role as far as the source term calcu-lation is concerned. The SSPSA study, however, has not taken any credit for the enclosure but1 ding. , 3.3 Definition of Plant Damage States and Containment Response Classes The grouping of accident sequences into plant damage states proceeds from the premise that the broad spectrum of many plant failure scenarios can be discretized into a manageable number of representative categories for which a single assessment of core and containment response will represent the response of all the individual scenarios in that category. The plant damage states classify events in accordance to the following three parameters:
- 1. Initiating Er ris "A" -
Large loss of Coolant Accident "S" - Small Loss of Coolant Accident "T" - Transient s.
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