ML20027A389

Responds to 780914 NRC Ltr Requesting Inclusion of Early Warning of Local Auth in Facil Emergency Plan.Plan Rev Will Be Completed by 790131.Forwards Ltrs of Agreement & Procedures of Determining Dose Received

ML20027A389
Person / Time
Site:	Oyster Creek
Issue date:	11/16/1978
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Ziemann K Office of Nuclear Reactor Regulation
References
NUDOCS 7811240194
Download: ML20027A389 (27)

Text

{{#Wiki_filter:af$ o F Jersey Central Power & Light Company i -q *s L c',. cd.,, +,,b. .al-. y') l .( Madison Avenue at Punch Bowl Road Mornstown. New Jersey 07960 (201)455-8200 November 16, 1978 Mr. Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, DC 20555 ' ' ' ~. .... w_ :

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Emergency Plan, Revision 2 o Enctosure i to your letter of September 14, 1978 concludes that the Oyster Creek Emergency Plan should be revised to provide early notification to the local authorities. We have discussed this matter with the New Jersey Department of Environmental Protection and have advised them that we plan to follow the NRC guidance. Therefore, the Oyster Creek Emergency Plan will be revised to make evident that the local authorities and organizations capable of providing as.sistance will be notified directly by the Station Superintendent. Copies of the revised pages of the plan will be forwarded to you no later than January 31, 1979 i "In. compliance with your request for additional information relating to the Emerge 6cy Pla'n, we are forwarding with this letter (1) copies of letters of agreement with off site response organizations and (2) copies of the procedures used for determining the dose received at various distances from the plant following four (4) design basis accidents. Haps that reflect the information called for in Regulatory Guide 1.70, Section 13.3-6a and 6b are being prepared and will be forwarded to you with the revised pages to the Emergency Plan discussed above. Very truly yours, . hub b Ivan R. Finfrock, J7 Vice President es 4Dl} Enclosures $0/ll6 u,

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.m.,,_....a____., ".[_. R.V. SILVA. M.D. - D.D. USTARIS, M.D. 77 Highway 37 West Toms River, New Jersey 08753 ~. - 6 ~. TELEPHONE 20134&7077 i!!k s j D,.,s.,,I r.

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Mr. Edward Scalsky did . %;th[ Oyster Creek Nuclear Generating Plant Post Office Box 366 l ~ 4.,f, \\ D;.: Forked River, N.J. 08731 L.1 .m . a +c{. .G%t.wf;ii:s . ';7 ':..fikh..y.% .li.' I ? c .g. :.r s,;z2A4. ii.. e August 8, 1978 l +.Wm . S.- .t \\ q 1 ;. Attention Mr. Edward Scalsky ' e'd@p '; i.:Iu :' l a:.f&nf:., .s We would like to inform you that we would be ..I.'.'. .iM. &n. '.;.v 3: ' t, nu.:!; x-{,ipp.y.;.ig ( available for any emergency that would arise at the i l. A.- .i 24 s.e Power Plant. c-- f = We can be contacted day or night by calling our . g.,, pg,g .. 5 offica at 34-7077. T'M t '# c l If we can be of any other service please notify /g t. us.

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.. oy. Res actfully, . (..' m p* u < > U. (% D *. '. bWL i .:. c.g.g Rt. pen Silva, M.D.- ..:n== .t T^ Dog.nmy. g d e -u<.a is,p .a. or p s, _.,....-,..-...m...~---e----~.---

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h. 9 9 HIGHWAY 37 WEST TOMS RIVER, NEW JERSEY 08753 349 8000 Area Code 201 a;,

dy f-d ACCREDITED BY THE JOINT COMMISSION ON ACCREDITATION OF HOSPITAL 5 i April 18, 1978 Mr. Edward Scalsky, Radiation Protection Supervisor Oyster Creek Nuclear Generating Station PO Box 388 Forked River, New Jersey 08731

Dear Mr. Scalsky:

This will confirm the continued availability of emergency services at Community Memorial Hospital for Jersey Central employees injured at the Oyster Creek Generating Station. We are prepared to receive routine emergency patients and contaminated patients. Please do not hesitate to contact me if I can be of further assistance. k Very truly yours, b'M f$ i . RW Joseph M. De ilippo Adminis tra$5r ' 0 JMD:mam cc: Mr. Schuessler . " * ~ _ L, ,,~,, ~ T t_f C D A TfC klT f f* Attn ntt n n n r= f=

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~ wt% s W g Department of Energy Brookhaven Area Office { v. Upton, New York 11973 January 17, 1978 f.f 41 Mr. Edward D. Scalsky L._. Radiation Protection Supervisor ' /. Oyster Cfjek Nuclear 2 [ Generating Station f. P. O. Box 388 ~ '. y} Forked River, New Jersey 08731

Dear Mr. Scalsky:

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SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION Since your nuclear facility is located in Region I, the Brookhaven Area Office is charged with the responsibility for providing radio-logical assistance in the event of an. emergency. Such assistance can be requested, at all times, by calling 516-345-2200 and asking '~ for radiological assistance indicating the nature of the incident, the location, and how to contact responsible authorities to coordi-nate our response. The Department of Energy (DOE) will respond to requests for radio-P, - f( logical assistance from licensee.. Eederal, state and local agencies, 7s private organizations, or ind">ib iis involved in or cognizant of an

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) incident believed to invo? a a ut , byproduct, or special nuclear b'f material as defined by tb, Q3 .arrgy Act of 1954, as amended, or '7 i other ionizing radiation s surces. .,( t 7 17 Unless the DOE or a DOE contractor is responsible for the activity, Q~l. ionizing radiation source, or radioactive material involved in an incident, DOE radiological assistance will be limited to advice and i emergency action essential for the control of the in: mediate hazards Il to health and safety. Radiological emergency assistance will be hJ terminated as soon as the emergency situation is under control. There-L'h fore, responsibility for postincident recovery, including further action for the protection of individuals and the public health and $f'$ safety,. should' be assumed by the appropriate responsible Federal, state I or local government, or private authority as soon as the emergency 7-- conditions are stablized. j l l l

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~.. _. ' ' (j I ? l ir 2 Iw R' If you have any further questions or desire further information, feel free to contact me. Ver'- ruly yours, f p l? Q* d M Robert A Friess, Acting Chief I, Operations & Safety Branch f ec: B. H. Grier, Office of Inspection & Enforcement, Nuclear Regulatory Commission, Region I H. Hollister, Director, Division of Operational and I~ Environmental Safety, HQ t l' w 4 1 E' tN ( vJ L., kd, i.i: i l '[]

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KLJ L % L To. oF LACEY TOWNSHIP - FORKED RIVER, N. J. 08731 I i February 15, 1978 ( Ur. Edward D. Scalsky Oyster Creek Nuclear Generating Sta. P. O. Box 388 Forked River, IT. J. 08731

Dear Mr. Scalsky:

In answer to your letter of January 12, 1978, the Forked River Volunteer Fire Co. confirms the renewal of our agreement with you as stated in our letter of March 19, 1976. Yours very truly, feA W { Kenneth Buntain,. Chief L Forked River Tol. Fire Co. t e er.., e e e =, e., O

g "." 17 January 1978 Mr. Joseph Carroll Superintendent Oyster Creek Nuclear Generating Station Forked River, New Jersey 08731 SURJECT: Emergency Medical Assistance Program

Dear Mr. Carroll:

This confims an agreement between Radiation Management Corporation (E!C) and Jersey Central Power 4 Light Company (JCPSL), wherein blC f. agrees to furnish certain services to nuclear generating stations 1 operated by JCP6L. These services comprise a program that is iden-tified by D1C as an Emergency Medical Assistance Program (EMAP). With regard to Oyster Creek Nuclear Generating Station, the BLIAP contains the following provisions: 1. Semi-annual review of plant and hospital procedures, equipment and supplies; one of these audits will be in conjunction with (6.) below; 2. Twenty-four-hour per day availability of expert consultation on management of radiation accidents; 3. Availability of Bioassay Laboratory for evaluation of radiation accidents; { 4. Twenty-four-hour-per day access to a Radiation Emergency Medical Team consisting of a physician, pgfgl, gn certified health physicist, and technicians with I uu. UI. Ull portable instrumentation to location of accident maDa08m80L 5. Availability and access to a medical center equipped-01,;. DD for the definitive evaluation and treatment of radiation injuries; 6. Annual training for the plant, ambulance and hospital UNWASW CU personnel who may be directly or indirectly involved sciruct crurra in the execution of the radiation medical emergency Program; 3508 MARKET STREET ' - ~ 7. Preparation of an "A ident" scenario for use as a ~ PHILADELPHIA, PA 19104 (zis) 243 29so tygining gid {n a Tadi1 tion medical emergency drill; 8. Coordination of a radiation medical emergency drill based on the scenario; umpired, video-taped and critiqued by DIC. a

] g ~' Mr. Joseph Carroll 17 January 1978 Page 'Iko 9. Submission of two Drill Evaluation Reports; one relating to the observations made at the station, and another relating to observations made at the hospital; and 10. Participation in an annual one-day seminar in Philadelphia on the management of radiation accidents for physicians. Each plant site may send one person, and each utility company may send one person. Accident Response Consultation and laboratory services by RMC personnel are at no charge, except incremental costs associated with consultative activities, such as travel, lodging and other related expenses. RADIATION MANAGRENT CORPORATION i /\\ ,1 \\ i 3 V oger f. Linnemann, M. D. President ( REL:pg 'u.... ~

o I .c :L f"fBJhxs LACEY TOWNSHIP POLICE DEPARTMENT i 818 WEST L ACEY ROAD FORKED RIVER, N EW JERSEY 08731 609 - 693-6636 aAt. o'.,f.**l' ..,. - @. ;M. T - g% =~ THOM AS R. DARMODY cMesr or potecs January 17, 1978 i Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, New Jersey 08731 Attn: Mr. Edward D. Scalsky Radiation Protection Supervisor

Dear Mr. Scalsky:

In answer to your letter of January 12, 1978 in regard to response to the Oyster Creek Nuclear Generating Station by the Lacey Township Police Department. I wish to inform you that the Lacey Township Police Department will continue to provide requested services. <( You may accept this letter as a renewal of our agreement of 11-4-74. Very truly yours, N L9 Thomas R. Darmody Chief of Police -v :.. -. -.. .,i... . :~~ TRD/jh* ~ ~ ~~ "~ 4 "#'

{Eacey Gofunsljip ](irst pih $guah, $nt. Parker and Oak Streets Forked River, New Jersey 7' February 13, 1978 Lir. Edward D. Scalsky Oyster Creek Nuclear Generating Station P.O. Box 388 Forked River, N.J. 08731

Dear Mr. Scalsky,

This is to confirm that Lacey Township First Aid Squad agrees to transport patients arising from radiation accidents at Oyster Creek Generating Station, Forked River, New Jersey. ~ l Mattie M. Si son ()] sfn i-b*Q% ~ uapta.tn / Lacey Township First Aid Squad --c. ~ ,___---3-:-- -- = :. [ P - _i g..-:- .3_ _ --- e 9

]Eaccg EfuusIip girst pih $ quad, FJuc. Parker and Oak Streets Forked River. New Jersey February 1978 Synopsis of operating procedure The duty officers vehicle will respond from 6 P.M. to 6 A.M. Monday through Thursday and from 6 P.M. Friday to 1 6 A.M. Monday. An ambulance will respond shortly after the duty officer. An ambulance willIsspond alone at any other time or if the duty officer is otherwise disposed. The duty officers vehicle normally carries only the duty officer, but it is not unusual for there to be another member riding with him/her. The ambulance will respond with two to five persons. In the event we are not able to handle a call because members are.:unavailabl, we will abk our police dispatcher to call for mutual aid from either Vlaretown or Bayville. ( All patients will be transported to Community Memorial Hospital unless they request to go to another, hospital in our service area. (SOCH, Paul Kimball or Point Pleasant). If the duty officer or member in charge fells the injury does not warrant an ambulance he/she will so inform the patient. All squad members have been informed to follow any directions given them by security guards or plant employees. ~ These~procedu.re may be changed.or updated periodically, ,.i. i ~ ^

• ile will attemp't' to keep yoil informed of same.

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{!Iaceg EfuusIip girst pih $quah, dur. Parker and Oak Streets Forked River. New Jersey Below is a list of our officers effective Nov. 1, 1977 to Nov. 1, 1978. Captain L*.attie M. Simpson 693-9661 P.O. Box 26 Lanoka Harbor, N.J. First Lieutenant Emery Miszlay 693-7909 1704 Fleetwood Dr. Forked River, N.J. Second Lieutenant and President Richard Tatham 693-5971 1829 Lakeside Dr. South 1 Forked River, N.J. l l Third Lieutenant and Vice President Craig Miller 693-1485 l Beach Blvd. [ Forked River, N.J. Secretary l Dorris Wolverton 693-5356 h Richard Road h Forked River, N.J. i g. }_ .4p.~:;5.-L.: a w,. .. g.

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4 i s 's, I i t ENCLOSURE 2 l Copies of Procedures Used for Determining the Doses ) Received at Various Distances Following Design Basis Accidents i I a 1 i i i 4 h l' 1 f 2 i t i d n ,w ---,--r

~ Procedure No. l. Jersey Central l@ 90s.18 Pag 3 1 of 3 j ' Power & Light Company 1(f, j%55/f8 E e } e}a;y9 0 Re ision No. Date ubject: Initial Estirate of Offsite Exposure for " . Line Break Outside Authorized By ,%acab anildim" Accident Station Superintendent Pit KCAWLL 30 r Oyster Cree.' 'uclear Generating Statien LIST OF EFFECTIVE PAGES DATE REVISICN NUMBER 1 6/30/78 0 2 6/30/78 0 3 6/30/78 0 ( ^'O N-CO,\\7R O L L ED D cument will Not Be Kept s Up to Ogg l A

Form 16l. Ict. Proccdure No. 905.18 Pags 2 OI Pagts 3 Initial Estimate of Offsite Expcsure for " Steam Revision No. Date Lire Break Outside Feactor Building" ;ccident 0 6/30/78 1.0 APPLICABILITY This procedure describes the method for estimating off-site exposures due to ' ~ releases from the design basis accident " Steam Line Break Outside the Reactor Building". 2.0 m rae.SCES 2.1 FDSAR Section XIII Safety Analysis 2.2 Main Steam Line Rupture Outside the Drywell 516.1 2.3 Assessment of Ccnditions 905.38 3.0 PREREQUISITFS 3.1 Class IV accident 4.0 PRECAUTICNS 4.1 The data are to be used as prelinunary estimates cnly and should represent the maxu:un exposure possible due to the release frcm the facility. 5.0 PROCEDURE NOIE: The data frcm the " Steam Line Break Outside the Reactor 91ildirg" ( 4 represents releases to the envirens for, a short time thru the turbine building walls and ventilation ducts. 5.1 Frcm the table belcw determine the postulated off-site doses at distances frcm the site. NOIE: The deses are for a conservative wind mnditiicn of 50 mgh. Distance Passing Cloud Whole Body Dose (RDI) Miles -6 1/4 3.6 x 10 -6 1/2 2.0 x 10 -7 I 1 8.6 x 10 ~7 2 3.2 x 10 -8 5 6.6 x 10 10 1.9 x 10-8 l

. Form 164 Subj:ct: Procedurs No. Initial Es.timato of Offsite Exposure for " Steam 905.18 Page 3 of 3 Pag:s Line Break outside Peacter Buildirs" Accident Revision No. Date g 5.2 Subsequently nere refined " Steam Line Break Cutside the Beacter Building" offsitp exposure extirates shall be performd requirim the use of Procedure 905.38 " Assessment of Conditiens". NCTIE: A " Steam Line Break Outside the Reactor Building" accident can be described as a sudden eczglete break of one of the two rain steam lines in the pipe tunnel outside the drywell which would instantly discharge high pressure steam until the reactor side-is isolated f in a short ti:m by the main steam isolation valves and the turbine side is isolated by the turbine admission valves.

pg, Procedure No. l* 905.17 Paga 1 of 4 Jersey Central Power & Light Company i(f l)*dS/Nd E"*tiy,^t* ,, g Revision No. Date Initial Esti: rate of Offsite 0 6/30/78 . abject: E:cosure for "Icss of Coolant Ins'de Drywell" Accident Authorized ByStation Superintendent ~ Ma 4 b h b k. OysterC#hkNuclearGeneratingStation Pr et: LIST T EFETIVE PAGES DATE REVISION NUMBER 1 (j 6/30/78 0 ./' 2 6/30/78 0 3 6/30/78 0 4 6/30/78 0 ( ( hoX-COW ~90LL D This Document Will Not Be Kept UpIo Date I i l i C P-1 1

Form 164) Subj;ct: Proc: dura No. 905.17 Pago 2 Of Pag;s 4 Initial Estimte cf Offsite E:qcsures for Revision No. Date "Icss of Coolant Inside Drywell" Accident 0 6/30/78 L0 APPLICABILITY This procedure describes the meth:d for estimating off-site exposures for the design basis accident "Icss of Coolant Inside the Dry

• ell".

2.0 Re m e CES 2.1 FDSAR Section XIII Safety Analysis 2.2 Small Piping Leaks in Dryan11515.3 2.3 Piping Rupture Inside Dryonll, Offsite Pcwer Available 516.2 2.4 Piping Rupture Inside Drywell with Ioss of Offsite Pcwer 516.3 2.5 Piping Rupture Inside Drywell with Icss of Offsite Pcwer and Cne Diesel Generator Incperable 516.5 2.6 Assessment of Conditiens 905.38 2.7 Ioss of Coolant Inside the Drp' ell Offsite E:q:osure Est.unation Calculation . heet HP-905-25 S 3.0 PRERECUISITES 3.1 Class IV accident t 4.0 PRECAUTICNS 4.1 Die data in the table in this precedure is to be used for only prelinunary estizrates of off-site exposures. 5.0 PRCuuum 5.1 "Ioss of Coolant Inside the Drywall" off-site ep.sure estimation. (perform estimation en form HP-905-25) 5.1.1 Determine the wind speed (MPH) 5.1.2 Datermine the ter.perature differential betaeen 400 ft. and 33 ft. elevation (AT) (*F). t 5.1.3 De* amine the metecrolcgical ccndition.

Form 164 ) Subj et: Procedura No. { 905.17 Paga 3 of 4 Pa0Esl Initial Estimate of Offsite Exposures for Revision No. Date "Ioss of Coolant Inside Drywell" Accident 5.1.3.1 If AT is higher than -1.l'F (nore positive) the condition is stable. 5.1.3.2 If aT is between -1.l'Fand -3.3 F, the condition is neutral. 5.1.3.3 If AT is less than -3.3*F (nure negative). the condition is unstable. 5.1.4 Fran the table below, detennine the postulated off-site dose for j the given meteorological condition and distance fran the site. Whole Body Passing Cloud Dose (REM) Distance First 2 hour dose Miles Stable Neutral Unstable -6 6 -5 1/4 8.2 x 10 8.3 x 10 1.2 x 10 -6 -6 -5 1/2 7.0 x 10 7.6 x 10 1.1 x 10 i -6 -6 -6 1 5.1 x 10 6.3 x 10 5.6 x 10 -6 -6 -6 2 3.2 x 10 4.0 x 10 2.1 x 10 ( 5 10 NOIE: The doses specified above are for a wind speed of 2 MPH. 5.1.5 Determine the wind speed correction facter by dividing the actual wind speed by the " basis" wind speed of 2 MPH. 5.1.6 Detentune the corrected off-site dose by dividing the dose value determined in step 5.1.4 by the wind speed cm.Tection factor in step 5.1.5. NorE: Die release was frcm the Reactor Building thru the stack by way of the starxiby gas treatment system which consists of high efficie.y filters and due=gnated charcoal filters.

Form 166 i

Subject:

Procedura No. 905.17 Paga 4 of 4 Pagss, Initial Escinate of Offsite Exposures for Revision No. Date j "Icss of Coolant Inside Drywell" Accident 5.2 Subsequently more refined "Icss of Coolant Inside the Dryaell" off-site, exposdre estimates shall be perforred requiring the use of Procedure 905.438 " Assessment of ConditiCns". ? NCTIE:- "Icss of Coolant Inside the Drywell"; the accident is defined as while the reactor is at full pow r, a break occurs in the primary systen equal in area to twice the flew area of a recirculaticn f line. Depressurization occurs, primary coolant is expelled into i the contalment, a scram is initiated, the cere terrperature rises 4 causing a pertien of the fuel reds to perforate and release the i fission prcducts stored in the fuel rod gas plenums. Some of the activity leaks into the Reactor Bnilaing, nest of the activity renains in the drywell system. (. l 2 e 1 e

Proceduro No. Jersey Central i es.is Paga i of 3 - Power & Light Company '(, f' i Date issued Effective Data l 6/30/78 7/7_7/17/78 i Revision No. Date Initial Estircates of Offsite 0 6/30/78 .ueject: E posures for Control Fed Drcp Authorized Bsuperintende.nt ) Station Icp? dent Y. 9n. hTCractL W Project: Oyster Creek lear Generating Station LIST T t.nu;nVE PAGES DATE REVISION hL M 1 6/30 /78 0 / 2 6/30/78 0 3 6/30/78 0 l (. N O N-CONT ROLL ED This Document Will Not Be Kept Up To Date i l l C P.1 1

Form 166 Subj:ct: Procedura No. 905.16 Page 2 of 3 Pag:s' Initial Estimates of Offsite Exposures for Control Rcd Drop Jccident Revision No. Date 0 6/30/78 1.0 APPLICABILITY This procedure describes the method for estimating off-site expcsures for tP design basis accident " Control Pod Drep". 2.0 REFERE;CES 2.1 FDSAR Section XIII Safety Analysis 2.2 Bod Drop 506.1 2.3 Assessment of Corditiens 905.38 / ~ 2.4 " Control Pod Drop" off-site epsure est.unation calculation sheet FP-905-24 3.0 PREREQUISITES 3.1 Class IV accident 4.0 PRECAUTIONS 4.1 The data in the table in this prccedure is to be used for cnly prel.uninary ( estimates of off-site exposures. 5.0 PROLc.uule 5.1 Control Pod Drop off-site exposure estimation. (Perfonn estimation on form 7( HP-905-24) 5.1.1 Detennine the wind speed (MPH) 5.1.2 Detenm.ne the temperature differential between 400 ft. and 33 ft. elevation (AT) (*F). 5.1.3 Detennine the meteorological condition. 5.1.3.1 If AT is higher than -1.l*F (nore psitive) the condition is stable. 5.1.3.2 If AT is between -1.l*Fand -3.3*F, the condition is neutral. 5.1.3.3 If AT is less than -3.3*F (ncre negative) the condition is unstable.

Form 164 l ' Subj:ct: Procedure No. 905.16 Pa93 3 of 3 Pag:s l Initial Estimates of Offsite Exposures R vision No. Date for Centrol Rod Drop Accident 8 6/30/78 5.1.4 Frcm the table belcw, dete.rmine the postulated off-site dose for the given meteorological ccrdition and distance frcm the site. Whole Ecdy Passino Cloud Dese (PDD Distance First 2 hour dose Miles 5 table Neutral Unstable -1 -1 -1 1/4 3.2 x 10 3.3 x 10 4.8 x 10 -1 ~1 ~ 1/2 2.8 x 10 3.0 x 10 4.2 x 10 y; -1 -1 -1 1 2.0 x 10 2.5 x 10 2.2 x 10 -1 -1 -1 2 1.3 x 10 1.6 x 10 8.3 x 10 5 10 NCTTE: The doses specified above are for a wird speed of 2 MPH. 5.1.5 Detezmine the wind speed correction factor by dividing the actual wind speed by the " basis" wind speed of 2 MPH. b 5.1.6 Deternune the corrected off-site dose by dividing the dose value determined in step 5.1.4 by the wind speed correction factor in step 5.1.5. 5.2 Subsequently nere refined Control Rod Drop off-site exposure estimates shall be perfonned requiring the use of Precedure 905.38 " Assessment of Conditions". NC7TE: A control red drcp accident is defined as a power excursion caused by the accidental removal of a centrol rod frcm the core at a more rapid rate than can be achieval by use of the control drive mechanism. A fully inserted control red is assimi to drop out of the core after beccming disconnected frcm its drive and after the drive has been renoved to the fully withdrawn pcsition.

I* Procedure No. 90s.15 Page i er 3 Jersey Central L gj Power & Light Company p(f ^T)W/li A9 EHec Initial Estimate of Off-Site b"' 6/30/78 .uNect: Exposures for "Fefueling Iccident" orized B Au Etaucn Yuperintendent g,, '^ Y N M Mk faJTcus<.c M. CysterheekNuclearGeneratingStation Pro

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LIST OF mu;nVE PAGES DATE IL"JISION hu!BER 1 6/30/78 0 K 2 6/30/78 0 ~ 3 6/30/78 0 (.. NOX-C0Y RO'_L D This Document Will Not Be Kept Up To Date I i . gP.1 1

Form 164 Subj ct: Proc:: dure No. 905.15 Pags 2 of 3 Pages Initial Esti: rate of Off-Site Exposures for "Pefueling Accident" Revision No. Date 0 6/30/78 1.0 APPLICABILITY 'Ihis precedure describes the method for estirating off-site e.p sures for the-design basis accident "Pefueling Accident". 2.0 bu<dCES 2.1 FDSAR Section XIII Safety Analysis 2.2 Hazardous Condition en the Pefueling Floor 521 2.3 Assessment of Conditiens 905.38 1 2.4 "Pefueling Accident" offsite expDsure estimation calculaticn sheet F2-905-23 3.0 PRERECUISITES 3.1 Class IV accident 4.0 PRECAUTIONS 4.1 'Ihe data in the table in this prccedure is to be used for cnly preliminary i est:tmates of off-site ergosures. 5.0 PROCEDURE 5.1 "Pefueling Accident" off-site e.gsure estimation. (Perform estilnation cn (- form HP-905-23) 5.1.1 Deternune the wind speed (MPH) 5.1.2 Determine the temperature differential between 400 ft. and 33 ft. elevation (AT) (*F). 5.1.3 Deternine the meteorological condition. 5.1.3.1 If aT is higher than -1.l'F (ncre positive) the condition is stable. 5.1.3.2 If AT is between -1.l*Fand -3.3*F, the condition is neutral. 5.1.3.3 If AT is less than -3.3*F (ncre negative) the conditicn is unstable.

Form 164 S"bj:ct: Proc; dura No. 905.15 Pagg 3 of 3 Pag;4 Initial Estd: rate of off-site Exposures Revision No. Date for " Refueling Accident" 0 6/30/78 5.1.4 Frcm the table belcw, deter:nne the postulated off-site dose for l l the given meteorological ccnditicn and distance fran the sitel Whole Body Passine Cloud Dese GEM) Distance First 2 hour dose Miles Stable Neutral Uns*d le ~4 -4 -4 1/4 2.8 x 10 2.8 x 10 4.4 x 10 ~4 ~4 ~4 1/2 2.3 x 10 2.5 x 10 3.8 x 10 -4 -4 -4 1 1.6 x 10 2.1 x 10 1.9 x 10 -5 -4 -5 2 9.7 x 10 1.3 x 10 6.9 x 10 5 10 l l NOIE: The doses specified above are for a wind speed of 2 MPH. 5.1.5 Dete=:nne the wind speed correction factor by dividus the actual I wind speed by the " basis" wind speed of 2 MPH. ( 5.1.6 Deterrune the corrected off-site dose by dividing the dose value deternined in step 5.1.4 by the wind speed correction factor in step 5.1.5. 1 NOIE: The release was fran the Beactor Anilaing thru the stack by way of the standby gas treatment system which consists of high efficiency filters and impregnated charcoal filters. 5.2 Subsequently more refined "Pefueling Accident" off-site exposure estimates shall be perfonned requiring the use of Precedure 905.38 " Assessment of Conditions". NOIE: The "Befueling Accident" represents the maximum fission prcduct release to the secondary centainnent if a fuel bundle is accidently drcpped en to the tcp of the core during fuel handling operation. _ _ _ _ _ _}}