Text

Forwards Upgraded Draft Emergency Plan
	ML19290E470
Person / Time
Site:	Crystal River
Issue date:	03/07/1980
From:	Moore G; FLORIDA POWER CORP.
To:	Eisenhut D; Office of Nuclear Reactor Regulation
Shared Package
ML19290E471	List: ML19290E470;
References
	NUDOCS 8003110510
	Download: ML19290E470 (101)
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{{#Wiki_filter:,9 9se t sa%39,41[lh 6 ,s w, n~, o 4 : > w ;'. e sa 6 dCid ' j'(.) d @ 'sO M f ol cy$,}.hhf? Florida Power L 0 R P O M A T 10 N March 7, 1980 File: 3-0-5-g Mr. Darrell G. Eisenhut Acting Director Division of Operating Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Crystal River Unit No. 3 Docket No. 50-302 Operating License No. DPR-72 Upgraded Emergency Plan

Dear Mr. Ehenhut:

Your le er of October 10, 1979 requested Florida Power Corporation to submit by January 1,1980, an upgraded Emergency Plan for Crystal River Unit 3. In accordance with your October 10, 1979 request, Florida Power Corporation submitted our upgraded Emergency Plan for Crystal River Unit 3 on December 27, 1979. The Emergency Plan for Crystal River Unit 3 was upgraded utilizing Regulatory Guide 1.101, NUREG-0610, and Appendix E to 10 CFR Part 50. Following review of the upgraded plan by the Emergency Preparedness Task Group and subsequent public hearings, additional revisions have been i ncorporated. Florida Power Corporation hereby submits our revised Emergency Plan for Crystal River Unit 3. 2 c>c.3 l l O S W General Of fice 3201 ininy.tounn street soutn. P O Boa 14o42. st Petersburg Flonda 33733 813--866 5151

Mr. Darrell G. Eisenhut Page Two March 7, 1980 In addition, attachments to this letter provide supplemental information covering conments raised by Mr. William Axelton, Emergency Task Force Team Leader. These attachments cover the following topics: achment Topic 1 Offsite Radiological Support Plan 2 Letters of Agreement 3 Evacuation Time Estimates (After Notifica-tion) for Areas Near Nuclear Power Plants 4 Corporate Emergency Response Plan 5 Use of Potassium Iodide (KI) 6 Public Notification and Warning Systems 7 Public Information 8 Emergency Response TLD Locations 9 Capability for Field Iodine Sampling 10 Post-Accident Sampling and Analysis Procedures If you require any further discussion of our submittal, please contact this office. Very truly yours, FLORIDA POWER CORPORATION s1 /j$ I' f /m b. C. Moore d Assistant Vice President Power Production Hill (EmerTrans)DN89

1 STATE OF FLORIDA COUNTY OF PINELLAS G. C. Moore states that he is the Assistant Vice President, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, infonnation and belief. ,g lI 'lf ~ hN,',Y f A C G.'C. Moore Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 7th day of March,1980. ~ lyt v.,u $%w Notary Public Notary Public, State of Florida at Large, My Conrnission Expires: August 8, 1983. Hi11(EmerTrans)DN89

ATTACHMENT 1 FLORIDA POWER CORPURATION OFFSITE RADIOLOGICAL SUPPORT PLAN (!4SSD-17) MARCH 7, 1980 Offsite Radiological Report is provided by Florida Power Corporation as described in Procedure NSSD-17, which is enclosed for supplemental in-formation. Hil1(EmerTrans)Dil89

o NUCLEAR SUPPORT SERVICES N S S D -17 R EV_1_.

. Florida Power DEPARTMENT PROCEDURE D AT E. 03/06!60
- ' " " " ~ "

PAGE 1 0F 10 TITLE: GFFSITE RADIOLOGICAL SUPPORT PLAN 1.0 P11RPOSE This Offsite Radiological Sapport Plan is designed to help Company personnel respond quickly and eifectively to a radiological energency. Its primary goal is to assist and support the Florida State Radiological Reponse teams in limi ti ng offsite radiological

effects, providing lagistical/ procurement support for offsite emergency measures, providing iegal a nd administrative liaison se rv ices between Florida Power Corporation, State and Federal agencies, and the public.

2.0 SCOPE The Offsite Radiological Support Plan includes the lines of authority and descriptions of the duties applicable to those personnel designated in the referenced CR-3 Emergency Plan (Eti-100). The Offsite Radiological Support Plan is applicable to Site and General Emergencies as defined in E:1-100. 3.0 APPLICABLE REFERENCE DOCI'!1ENTS E!1-100, (CR-3 Eme rgency Plan) " Florida Power Corporation Crystal River Unit 3 Euergency Plan.' 4.0 DEFINITIONS The term "Offsite Radiological Emergency," when used in this plan, means the initiation of a Site or General Emergency by the Crystal River 3 Eme rge ncy Coordinator or the designated State representative. Other applicable definitions may be f ound in the referenced Company Plan. 5.0 RESPONSIBILITIES AND ACTIONS 5.1 STATE VS CO:1PANY RESPONSIBILITIES Action to protect the public and to control, contain, remove, and clean up offsite radioactive contamination is to begin as soon as possible. The responsibility for these actions rests with the State of Florida Department of llealth and Rehabilitat ive Se rv ic es. This agency will provide the necessary equipment and trained personnel to cope with the offsite as requested. emergency. Florida Power Corporation will assist The DHRS is responsible for the technical aspects of the State Radiological Emergency Plan and will require no technical assistance from Florida Power Corporation. NSSD-17(D93) i APPROVED Y: APPF0 BY: APPROVED BY: n, ad I 1 b(d 4 7r v 2 8 DATE h N YD DATE ) ATE

NSSD-17 REV. 3 s Florida NUCLEAR SUPPORT SERVICES I Power DEPARTMENT PROCEDURE ^I' 3' #" 8 LOmponat.cs g PAGE 2 OF 3 TITLE: OFFS 1TE RADIOLOGICAL SUPPORT PLAN _,,w Florida Power Corporation will be respons i ble for corporate public inforna-tion, transportation, corporate legal representative, communications, pro-curement and insurance. 5.2 DEPARTMENT llEADS RESPONSIBILITY lleads of all departments likely to be involved in offsite radiological sup-port are responsible for: 1. Advance assignment of personnel who might be needed in the event of an emergency. 2. Clear definition and distribution of duties of personnel in the eve nt of an emergency. 3. Orientation of personnel with advance assignments. 4. Rotation of personnel if an emergency occurs, realizing that long-term radiological recovery operations niy be necessary. 5.3 PLAN INITIATIOS This Plan will be initiated immediately after the Manager, Offsite Radio-logical Support, or his designated alternate, has received a request for offsite ra diologi ca l assistance from the Emergency Coordinator or the designated State representative. The Manager, Offsite Radiological Support will notify the Offsite Radio-1 gical Support Team and request they report immediately to the Emergency Operations Facility. See Attachment I for personnel and phone numbers. l Route of travel to or from the Emergency Operations Facility shall be de-signated by the Manager, Offsite Radiological Support. (At: ichment 2 is a map of the area. ) 5.4 CONTROL POINT The DHRS Health Physicist will normally designate the Florida Power Corpor-ation business office in Crystal River as the Emergency Operations Facili-ty. This site consists of a permanently maintained facility with: 1. Power supply 110 VAC. 2. Potable water supply. 3. Telephone and radio hook up f acilities. 4. Toilet facilities. 5.5 PUBLIC INFORMATION No statements regarding the offsite ra d iolog i ca l emergency will be made by any Company employee except as follows: NSSD-17(D93)

SSSD-17 RLV. 3 s Florida NUCLEAR SUPPORT SERVICES DATE~ 03/06/80 8 PO.o..e, mWr DEPARTMENT PROCEDURE <o. PACE 3 or 10 TITLE: OFFSITE RADIOLOGICAL SUPPORT PLA'; 1. Following implementation of the Emergency and Offsite Radiological Support Plans, all public announcements will be cleared through the FPC Public Information Representative. An exception to this is any statement of a regulatory nature required by the Emergency Coordina-tor, in accordance with Technical Specifications or CR-3 Emergency Plan requirements. 2. Before any detailed statements are issued regarding the offsite radiological support, the Public Information Representative will cl;ar any statements to be issued with the DilRS, who will concur with the accuracy, completeness, and timeliness of the statements. 3. See 5.6.3, Public Information Representative, for mere detailed guidelines. 5.6 DUTIES AND RESPONS1BILITIES OF OFFSITE RADIOLOGICAL SUPPORT TEA'1 !!L'BERS 5.6.1 Manager, Offsite Radiological Support 1. In conjunction with the Nuclear General Review Committee, provide a annuc1 review of the Company's Offsite Radio'ogical Support Plan. 2. Manage the Offsite Radiological Support Team of the Corporation. 3. Represent the Corporation in matters pertaining to the offsite effects of the radiological accident. 4. Establish communications with the Emergency Coordinator. 5. Transport the aerial maps and meteorological-concent ration overlays o the Emergency Operations Facility. 6. Provide a company representative to Citrus and/or Levy County Ener-gency Operations Center upon request. 5.6.2 Public Information Representative 1. Provid! regular briefings to press and governmental officials. 2. Obtain approval of Manager, Offsite Radiological Support and DilRS prior to any media re lea se concerning offsite activities, and approval of the Emergency Coordinator regarding onsite activities. 3. Transmit to corporate headquarters all verbal and written statements given to news media or government officials as soon as practical. The following guidelines apply to news releases and dialogue with reporters: NSSD-17(D93

I'SSD-17 REV. 3 s Florida NUCLEAR SUPPORT SERVICES DATE 03/06/80 I PO,o..ec.Wr DEPARTMENT PROCEDURE ,e co. PAGE 4 OF M TITLE: OFFSITE RADIOLOGICAL SUPPORT PLAN Initial press statements Give the name of the installation involved, the time of the accident, any any other facts that are not in dispute (such as the steps the Company and the DHRS have taken to contain, control, or handle the emergency). Note that cleanup experts a rc (on) (being called to) the scene to supervise the operation. Give the type of material released. Report whether the material has been cont rolled. Describe cleanup measures that have been taken and planned - types and quantities of equipment being used and manpower involved. Describe any special restrictions on local population. Statements to avoid unless cleared by headquarters Speculations concerning liability for the release or its legal consequences. Speculations regarding the cause of the release. An extended inquiry may be needed to determine the actual cause, and legal liability could be affected by what is said. Estimates of damage. Estimates of how long cleanup will take or of cleanup Costs. Promises that property, ecology, or anything else will be restored to norcul. Steps to correct false statements or unfounded speculations Provide the source with correct information. Ar ra nge for representatives to obse rve as much of the operation as possible to confirm Company's position. Avoid direct rebuttal of erroneous statements by scient is t s unless you use a compa ra ble scientific source to back up any statement you make. NSSD-17(D93)

MSSD-17 RE\\'. 3 t, Florida NUCLEAR SUPPORT SERVICES ^I' 3'"'8" <o.....e,<! Pow r DEPARTMENT PROCEDURE Pact 5 or to TITLE: OFFSITE RADIOLOGICAL SUPPORT PLAN 5.6.3 Transportation Specialist 1. Provide transportation for personnel and equipment as directed by the Manager, Offsite Radiological Support, or as requested by the designated DilRS representative. 2. Provide for maintenance and servicing as needed, for vehicles in use. 5.6.4 Legal Representative 1. Provide legal services to the

Manager, Offsite Radiological Support.

5.6.5 Finance and Accounting Representative 1. Process vouchers and claims. 2. Maintain records of expenditures and commitment of funds. 3. Apply verbal commitment of funds only as authorized by the Manager, Offsite Radiological Support or the Director, Nuclear Operations. 4. Disburse petty cash. 5.6.6 Communications Engineer 1. Provide communications as directed by the

Manager, Offsite Radiological Support, or as requested by the designated DiiRS re p re s e n t a t i ve.

2. Maintain a chronological log of emergency events. 3. Provide for mobile and fixed power supplies as needed. 5.6.7 Procurement Specialist 1. Obtain and issue equipment, supplies, and services as directed by the Manager, Offsite Radiological Support, or requested by the designa ted DilRS representat ive. 2. Provide for security of equipment, supplies, and facilities. 3. Maintain records on the issuance of equipment and supplies or contracted services. 4. Provide for the emergency

feeding, housing, and clothing of evacuees as directed by the Manager, Offsite Radiological Support, or as requested by the designated DilRS representative.

NSSD-17(D93)

NSSD-17 REV. 3 s Florida NUCLEAR SUPPORT SERVICES I f0WEtr DEPARTMENT PROCEDURE - 3

8"

"^" PAGE 6 OF _10 TITLE: OFFSITE RADIOLOGICAL Sl]PPORT PLAN 5. Provide for a potable water supply, food, and toilet facilities for Of f site Radiological Support Team membe rs. 6. Provide for housing of Offsite Radiological Support Team members. 5.6.8 Liaison Expediter { 1. Maintain liaison between Emergency Ope rat ions Facility and corporate headquarters. 2. Assist the Manager, Offsite Radiological Support as directed. 5.6.9 Crystal River Office Manager 1. Assist the Manager, Offsite Radiological Support as directed, se - { cure the Emergency Operations Facility upon notification and represent the corporation in matters pertaining to the offsite effects of the radiological accident until the Manager, Offsite Radiological Support arrives at the Emergency Operations Facility. l 5.6.10 Insurance Representative 1. Notify the insurance companies involved with Crystal River l' nit 3. 2. Receive and review claims pertaining to the offsite effects of a radiological emergency. 5.7 EMERGENCY TERMINATION The offsite emergency shall exist until such time as the Emergency Co-ordinator and DilRS determine that sa fe cond it ions have been restored for Company personnel and the general public and that offsite functions described above are no longer needed. 5.8 PLAN DRILLS AND REVIEWS At least one drill annually will be conducted jointly with the DilRS in accordance with Section 8.1.2 of the CR-3 Emergency Plan. Also, the Offsite Radiological Suppport Plan will be reviewed at least once y ea r l:. to assure that it is up to date. The Minager, Offsite Radiological Support and the Nuclear General Review Committee will provide such a review and recommend changes as required. 6.0 INTERPRETATION CONTACT Manager, Nuclear Support Services Department. NSSD-17(D93)

SSD-17 REV.

3 @I P.o..w..e, r Florida NUCLEAR SUPPORT SERVICES "^ 3' 6'8" DEPARTMENT PROCEDURE e. PAGE 7 O f _10 TITLE: OFFSITE RADIOLOGICAL SUPPORT PLA's

7. 0 REVISIOi HISTORY Rev. O Date:

1/19/80 Original Release Rev. 1 Date: 2/01/80 Revised to correct Offsite Radiological Support Team List Rev. 2 Date: 2/01/80 Revised for consis-tency and additional responsibility under Section 5.6.1. Rev. 3 Date: 3/06/8C Chanded " Control Point

to " Emergency Operations Facilty.'

NSSD-17(D93)

9+++ Powe..e. NSSD-17 REl'. 3 Florida NUCLEAR SUPPORT SERVICES ^ 3' 6'8 r DEPARTMENT PROCEDURE co co.. PAGE 8 OF 10 TITLE: OFFSITE RADIOLOGICAL SUPPORT PLAN A. Manager, Offsite Rad Support PHONE NUMBERS (Office) (Home) Member R. M. Bright 813/866-4283 813/867-5159 Alternate L. A. Hill 813/866-4422 904/726-3252 B. Public Information Representative Member T. L. Smith 305/646-8266 305/830-8031 { Alternate W. C. Johnson 813/866-4370 813/894-3231 C. Transportation Specialist Member W. J. Sullivan 813/866-4680 813/595-0o07 Alternate J. L. Parkec 813/893-9387 813/345-1090 or x 129-387 D. Legal Representative Member H. A. Evertz, III 813/866-5182 813/894-7545 Alternate J. A. McGee 813/866-5184 813/367-1167 E. Finance and Accounting Represeurative Member R. R. Peyinghaus 813/866-3074 813/391-7156 Alternate J. R. Miles 813/866-5141 813/321-7807 F. Communications Engineer Member H. A. Rargrove 904/454-1406 904/454-1670 or x 123-232 Alternate R. L. Feldhusen 813/893-9394 813/343-3036 G. Procurement Specialist Member G. Brilli 813/866-5425 813/596-3718 Alternate J. Nick 813/866-5546 813/546-5445 H. Liaison Expediter Member E. C. Simpson 813/866-4380 813/535-4228 Alternate H. M. Perry 813/866-4507 813/867-9290 l I. Crystal River Office Manager Member W. D. Ward 904/795-3145 904/795-3126 or x 123-227 Alternate L. D. Hurley 904/726-2461 904/726-2211 or x 123-233 J. Insurance Representative Member J. D. Freitag 813/866-4150 813/726-8662 Alternate S. G. Webber 813/866-4319 813/525-0276 NSSD-17(D93)

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3 Florida NUCLEAR SUPPORT SERVICES N S S D-17 REV 03 /06/80 Power DEPARTMENT PROCEDURE DATE 10 10

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PAGE OF TITLE: OFFSITE RADIOLOGICAL SUPPORT PLAN ATTACIDIENT 3 0FFSITE RADIOLOGICAL SUPPORT PLAN ORGANIZATION CHART STATE OF FLORIDA DEPARTMENT OF

DIRECTOR, HEALTH AND NUCLEAR REHABILITATIVE OPERATIONS SERVICES 8

i I ______________________________________a p_______ l i EMERGENCY

MANAGER,

[ COORDINATOR OFFSITE RADIOLOGICAL g SUPPORT i l I i t___________________-------- 7 r-------------- r 6 8 1 I e TRANSPORTiTION LEGAL PUBLIC FINANCE AND SPECIALIST REPRESENTATIVE INFORMATION ACCOUNTING REPRESENTATIVE REPRESENTATIVE C0!D!UNICATIONS INSURANCE PROCUREMENT LIAISON CRYSTAL RIVER ENGINEER REPRESEhTATIVE SPECIALIST EXPIDITER OFFICE MANAGER = Line of Communication _. Line of Authority NSSD-17(D93)

ATTACHMENT 2 FLORIDA POWER CORPORATION LETTERS OF AGREEMENT MARCH 7,1980 The enclosed are Letters of Agreement for medical services with off site agencies and a letter from the Bureau of Disaster Preparedness regarding the upgrade of the State of Florida's Radiological Emergency Plan for Fixed Nuclear Facilities. This material is provided for supplemental information and is also included in Appendix C of LN-100, Emergency Plan, Draft (3/7/80). Letters from the following of fsite agencies are enclosed: 1 Dr. S. R. Miller, Jr. 2 Dr. R. G. Ellis 3 Shands Teaching Hospital 4 Seven Rivers Hospital 5 Citrus Memorial Hospital 6 Citrus County keulance Service 7 Bureau of Disaster Prepareoness lii11(EmerTrans)Df489

Florida c"~"no oceT. e. o. o-s P. O. A 4 720 0 P. O. DAT, E: 12/21/79 { Power sT. ecTeassuno. r Lonio A 33733 PURCHASE ORDER CORPOH ATION esm. nasa nseuss,T,en Ny s 720-9016 TO: SHIP TO: FLORIDA POWER CORPORATION DR. S. R. MILLER P. BAYNARD, C-4 P. O. BOX 549 P. O. BOX 14042 3RD STREET ST. PETERSBWG, FL. 33733 a CRYSTAL RIVER, FL. 32629 f n ....n ....n A 11/01/82 o 4gww.pyy_,sq.nm.,pww.pww;q g.vn .,mmm ; n m . r,, OTHR MAN 571513 12/31/82 C F 91 my EMw:nTEUm.m.ww.un c%ua.u.- V r :-- m m n s;.ua w m m - , m y:ari.y n - f w a n i t-- c-01 720 2D0 51700 BLANKET AGREEMENT FOR SERVICES THIS AGREEMENT ENTERED INTO, BY AND BETREEN FLORIDA POWER CORPORATION, HEREINAFTER REFERRED TO AS THE COMPANY, AND DR. S. R. MILLER, HEREINAFTER REFERRED TO AS THE DOCTOR IS FOR THE PURPOSE OF RENDERING OF MEDICAL SERVICES BY THE DOCTOR, FOR THE COMPANY. THE TERM OF THIS AGREEMENT IS FROM DECEMBER 31, 1979 TO DECEMBER 31, 1982, OR UNTIL CANCELLED BY AN AUTHORIZED REPRESENTATIVE OF EITHER PARTY PROVIDING AT LEAST SIX (6) MONTHS ADVANCE NOTICE. THIS AGREEMENT SHALL BE IN ACCORDANCE WITH EXHIBIT "A""SPECIAL CONDITIONS" (ATTACHED). ALL TERMS ON THE REVERSE OF THIS FORM ARE NULL AND VOID. AGREED TO BY Miller, Jr., f _.D., P. A. NOT BILL FLORIDA SALES AND USE TAX SHIP VIA: BEST WAY WIE/dmg FOB: EST EXEMPTION CERTIFICATE NO 62 15 05029-99 INSTRUCTlONS FLORIDA POWER CORPOR ATION

1. PLE ASE SHOW PURCH ASE ORDER NO ON ALL PACK AGES, INVOICES. SHIPPING PAPERS AND CORRESPONDENCE.

2. PLEASE SUBMIT INVOICES IN TRIPLICATE TO P. O. BOX 14042. B 7 ACCOUNTS PAYABLE SECTION. ST. PETERSBURG, FLORIDA 33733.

sueJECT TO CONDITIONS ON I

3. PLE ASE SUPPLY ALL INFORMATION REOUESTED ON ACKNOWLEDGMENT AND e ACK OF THIS ORDE R sy

~ RETURN PROMPTLY.

4. PLEASE.S.HO.W. F P C P.A.R.T NO. FOR E ACH ITEM ON YOUR PACKING LIST AND W. L. G OLDEN, SR. BUYER

1 FLORIDA POWER CORPORATION SPECIAL CONIQTIONS_ 1. Florida Power Corporation, hereinafter referred to as the " Company", has constructed and is opera ting a nuclear power plant at a location known as Crystal River Unit No. 3 in Citrus County, Florida, hereina f ter referred to as the " Plant", and Dr. S. R. Miller hereina f ter referred to as the "D oc t or ", is in a position to furnish his services, such* availability shall be for the benefit of Company employees and members of the public who are involved in actual or suspected radiation exposure or c ontamina t ion result ing fro:n a nuclear incident occurring at the Plant. 2. Doctor shall t,reat all patients dispatched from the Plaat and where necessary shall utilize the radiological support provided by the plant staf f. (A credentialized list noting the qualifications of radiological support. personnel of the Plant shall be provided to the Doctor and shall be updated quarterly). 3. Company shall provide a training program to inform the Doctor, and appropriate Company personnel of the steps to be taken in the event of a radiation exposure accident. 4. Physicians fees for patient care services shall be based upon the current phys ic ia ns ' fees at the time of provision of service. 5. All costs of services rendered under this contre.ct will be borne by the Company. Doctor will render bills to the Company based on current rate schedule at the time of the billing, and all payments under this agreement will be made to Doctor. 6. All releases of information cencerning any Company personnel being treated by the Doctor in connection with a radiation exposure accident shall be provided and/or authorized by the Florida Power Corporation. 7. Only the Company's Nuclear Plant Manager or his designee shall be authorized to approve the treatment of an individual by the Doctor in the event of a radiation related accident / The Nuclear Plant Manager or his designee shall approve all invoices rendered under this Agreement.

Odda " a c *i a 5 '" a o c"' " o "o * ' * * *

ST. PETERSBURG, f*LORID A 3373 3

-P. O: A 47199 ~ P.O. OAT,E: 12/21/79 Power 8"... PURCHASE ORDER

" " " ^ " "

,o u...< ...v,. 720-9015 TO: SHIP TO: FLORIDA POWER CORPOR AT ON DR., ROBERT ELLIS P. BAYNARD C-4 P. O. BOX 1929 P. O. BOX 14042 7 RIVERS MEDICAL CENTER, S2B ST. PETERSBURG, FL. 33733 CRYSTAL RIVER, FL. 32629 {y ,,, u.. o, c..,.., q ....oo g,7f5srayy y yg u T.v m. ggregggememW A 11/01/82 o B E C F 91 GTHR 4AN 233193 12/31182_ Wrr,nlndv%5rA &&&gh& y 01 720 200 51700 BLANKET AGREEMENT F0F SERVICES THIS AGREEMENT ENTERED INTO, BY AND BETWEEN FLmIDA POWER CORPmATION HEREINAFTFR REFERRED TO AS THE COMPANY, AND DR. ROBERT ELLIS, HEREINAFTER REFERRED TO AS THE DOCTOR IS FOR THE PURPOSE OF RENDERING OF MEDICAL SERVICES BY THE DOCTOR, FOR THE COMPANY. THE TERM OF THIS AGREEMENT IS FROM DECEMBER 31, 1979 TO DECEMBER 31, 1982, OR UNTIL CANCELLT BY AN AUTHORIZED REPRESENTATIVE OF EITHER PARTY PROVIDING AT LEAST SIX (6) MONTHS ADVANCE NOTICE. THIS AGREEMENT SHALL BE Ili ACC mDANCE WITH g j' g/,,3' EXHIBIT "A", "SPECIAL CONDITIONS" (ATTACHED). N 'fd'D D ALL TERMS ON THE REVERSE OF THIS FORM ARE / NULL AND VOID. FOB SHIP VIA. DO NOT RILL FLORIDA SALES AND USE TAX DEST BEST_WAY WIB/dmg EXEMPTION CERTIFICATE NO. 62 15-05029 99 INSTRUCTIONS

1. PLEASE SHOW PURCHASE ORDER NO. ON ALL PACK AGES, INVOICES, SHIPP;NG PAPERS AND CORRESPONDENCE.

2. PLE ASE SUBMIT INVOICES IN TRIPLICATE TO P. O. BOX 14042, B 7 ACCOUNTS PAYABLE SECTION. ST PETERS 8URG. F:.ORIDA 33733-SusJect To concevsoNS ON

3. PLE ASE SUPPLY ALL INFORMATION REQUESTED ON ACKNOWLEDGMENT AND e.cx OF THIS ORDER gy C _

RETURN PROMPTLY.

4. PLEASE SHOW F. P. C. PART NO. FOR EACH ITEM ON YOUR PACKING LIST AND W. L. GOLDEN, SR. BUYE INVolcF WHFN APPLICARL E.

EX!;;B;T "n FLORIDA POWER CORPORATION SPECIAL CONDITIONS 1. Florida Power Corporation, hereinaf ter referred to as t he " Company", has cons tructed and is opera ting a nuc lear power plant a t a locat ion known a s Crys tal River Unit No. 3 in Citrus County, Florida, hereina f ter re ferred t o as the " Plant", and Dr. Robert Ellis hereina f ter re ferrt d t o as the "D oc t or ", is in a position to furnish his services, such availability shall be for the benefit of Company e >pl oy ees and members of the public who are involved in actual or suspected rad la t ion exposure or eontamination re ali'og Ir a a nuclear incident occurring at the Pla n t. 2. Doctor sha ll t reat all pa t icats dispatched from the Plant and where necessary shall ucilize the radiological s.pport provided by the plant staff. (A credentialized list noting the qualifications of radiological support personnel of the Plant shall be provided to the Doctor and shall be updated quarterly). 3. Company shall provide a t ra ining program to inform t he Doc t or, and appropriate Company personnel of the steps to be taken in the event of a radiation expcsure accident. 4. Physicians fees for patient care services shall be based upon the current phys ic ia ns ' fees at the time of provision of service. 5. All costs of services rendered under this contract will be borne by the Company. Doctor will render bills to the Company based on current rate schedule at the t it e of the billing, and all payments under this agreement will be made to Doctor. 6. All releases of information concerning any Co..,pany personnel being treated by the Doctor in connection wit h a radia tion exposure accident shall be provided and /or aut!,orized by the Florida Power Corporation. 7. Only the Company's Nuclear Plant "anager or his des ignee shall be authorized to approve the t rea tn ent of an individual by the Doctor in the event of a radiation relat ed accidc nt/ The Nuclear Plant Manager or his designee shall approve all invoices rendered under this Agreen ent. 4

GRANT THIS GRANT, dated as of [8! day of / '[1< a: 1979, by and between SHANDS TEACHING HOSPITAL AND CLINICS, part of the University of Florida, J. Hillis Miller Health Center, hereinafter called " Hospital," and FLORIDA POWER CORPORATION, hereinafter called " Company," a Flor'da Corporation. WHEREAS, the Company has constructed and is operating a nuclear power plant at a location known as Crystal River in Citrus County, Florida, and WHEREAS, proper and sufficient medical planning, consultation, examina-tions, facilities and equipment may be necessary and are desirable in connection with the operation of such plant, and WHEREAS, the Hospital is in a position to furnish such medical planning, consultation, examinations, facilities, and equipment and WHEREAS, certain equipment is needed to be purchased by Hospital in order to be prepared to diagnose and treat radiation injuries and personnel contamination. NOW THEREFORE, in consideration of benefits accruing to each, the parties agree as follows: 1. The Hospital, from January 1,1979, and thereafter for the term of this five (5) year grant, will provide for immediate availability of fully equipped local medical facilities with an adequate stai f of nurses and technical personnel skilled in the diagnosis and treatment of radiation injury and personnel contamination. Such availability shall be for the benefit of Company employees and members of the public who are involved in actual or suspected radiation exposure or contamination resulting from a nuclear incident occurring at the

2 Company's Crystal River Plant. The Hospital will establish plans, procedures and training programs for casualty reception, diagnosis and treatment. The Hospital will update such plans, procedures and programs thereafter as is necessary in order to conform to the latest developments in the state of the art, and/or changes in Hospital personnel and facilities. 2. The Hospital will furnish the Company original and updated plans, procedures and programs for inclusion in the Company's Emergency Plan. These plans, procedures and programs will be reviewed by and must be acceptable to the Company and any other governmental agency having jurisdiction. 3. The Hospital, annually, will test by drill or other means, the pro-ficiency of its own personnel and facilities with respect to paragraph one (1) above. 4. The Hospital will purchase for itself such equipment as it needs to be prepared to diagnose and treat radiation injury and personnel contamina-tion. 5. For the services and equipment needed to be purchased by the Hospital contemplated in items 1 through 4 above, the Company will pay Thirteen Thousand Four Hundred and Fifty Two Dollars ($13,452.00) per year and will include an inflationary figure to be determined by the Hospital Cost Index. (For planning and budgeting purposes, an inflationary figure of nine and six-tenths percent [9.6%) per year should be used.) The final amount to be paid the Hospital will be agreed annually.

5 Year Amount Inflation Total $14,743 1980 $13,452 + al,291 = 14,743 1981 13,452 + 1,291 = 14,743 1982 13,452 + 1,291 = 14,743 1983 13,452 + 1,291 = 14,743 1984 13,452 + 1,291 = Said annual amount will be billed semi-annually by the Hospital on or before January 31 and June 30 of each year. The Company will pay one-half of said amount on or before February 28 and July 31 of each year the grant is in effect. 6. The Hospital, at the request of the Company, will provide for Hospital treatment and laboratory services for those Company and other persons designated by the Company who allegedly have been involved in a radiation incident. Charges for such treatment and laboratory services shall be based upon the current hospital rates and will be borne by the Company. 7. Medical Records, including bio-assay records, will be maintained permanently by the Hospital and copies furnished to the Company upon request and upon cnsent of the individual patient involved as required by Florida Statutes. 8. Nothing herein shall be construed as prohibiting the Company from obtaining assistance, advice and consultations from other sources. 9. The Hoe.pital shall not incur an additional financial burden caused by performing the services specified for in this GRANT.

4 10. This GRANT shall be for a term of five (5) years, commencing on January 1, 1979. This GRANT will be reviewed automatically from year to year thereaf ter, provided, however, either party may cancel this grant at the end of the third year or any calendar year thereafter by notifying the other party at least six (6) months in advance of the end of any such calendar year. Notice of such cancellation on the part of the Hospital shall be given ,y the Executive Director of said SHANDS TEACHING HOSPITAL AND CLINICS. !.ikewise, notice by FLORIDA POWER CORPORATION shall be given to the Executive Director of said SHANDS TEACHING HOSPITAL AND CLINICS. IN WITNESS WHERE0F the parties have caused these presents to be executed and the corporate seals to be hereunto affixed. FLORIDA FDWER CORPORATION /' I r fl 3?.lD ATTEST: By [ ' j[, 6'/4 EbM bb7 < ~ ' t ? l. ~ ' ' 'N h I% hkm Title c -k klk'\\ Q /' ~ fo d E. Ives, Executive Hospital Director ATTEST: f e s iff{ I 'l Willia,m,B. Deal, M.D., Vice President for Health Affairs

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a
2 ST. PETERSBURG FLORID A nm P. O. ~

46961 P. O. DATE: 12/13/79 g

power PURCHASE ORDER i" an CORPOH AT BON

,......e.............. 711-9194 TO SHIP TO: FLORIDA POWER CORFORATION SEVEN RIVERS HOSPITAL P. BAYNARD C-4 2 ATIN Mt. M. HEINDEL/MR. RALPH = MITCHEu P. O. BOX 14042 P. O. BOX 458 ST. FETERSBURG, FL. 33733 CRYSTAlcRIVERrM2629 n g g 'Tz '. >, ' n efe ;w,3, .;y,5yg,g g,3gg,,,gg,,,Qg, J p mu,m q B E C F 91__OrHR _ MAN 181500 _12/3 ,,,,,,,m i-n n 4, ,r,, is L%<.:n u t h en.* "' " itu. >' " ",n r: v,,tr e z. m c e r m. =+.,ew, - e ups""" ~ & ~" ' " " 720 200 51700 BLANKET AGREEMENI FM SERVICES THIS AGREEMENT ENTERED INTO, BY(A BETWEEN FL MIDA POWER C E PORATf ( HEREINAFTER REFERRED ( TO AS THE COMPANY, 4 SEVENg1VER(410 SPITAL, HEREINAFTER REFERR $ A$THE HOSPITAL, IS FOR THE PURPOSE ORsRENDERDC SER-VICES BY THE UdhP,1TA.F0Et'THE NY. s THE TERM OF AGR OM DECEMBER 15, 1979p @$ AUT110RIZEdxREYR bECEM$ER 31%', UNTIL CAN-4nA TIVE OF CELLED,MdANIZAT10NSPRd/IDrfHGMT LEAST SIX EITHEIL (6) NORTHS'ADVA EtyII THIS AGR$iA CEDANCE WITH EXHIBtT A: M IAL C IONS" (ATTACHED). ALL' REVERSE OF THIS F(RM ARE NULL AND VOIDL M~ 9'J419 S8GN & RETURN AT ONCE rO8: SWP VIA: DE/4 HETURN

P.O. BO X 14047. ST. PETE f'58UR G, F L. 33 733

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PURCHASE ORDER A 46961 FLORIDA POWER CORPORATION SPECIAL CONDITIONS 1. Florida Power Corporation, hereinafter referred to as the " Company',' has constructed and is operating a nuclear power plant at a location known as Crystal River Unit No. 3 in Citrus County, Florida, hereinafter referred to as the "Pla nt ". Seven Rivers Hospital, hereinafter referred to as the " Hospital", is in a position to furnish the services of phys ic ians, such availability shall be for the benefit of Company employees and members of the public who are involved in actual or suspected radiation exposure or contamination resulting from a nuclear incident occurring at the Plant. 2 Hospital shall accept all patients dispatched from the Plant and where necessary shall utilize the radiological support provided by the plant stc f. (A credentialized list noting ~ the qualifications of radiological support personnel of the Plant shall be provided to the Hospital and shall be updated quarterly.) 3. Company shall provide a training program to inform the appro-priate Hospital physicians, nurses and technical personnel, and appropriate Company personnel of the steps to be taken in the event of a radiation exposure accident. 4. Physician fees for patient care services shall be based upon the current physicians ' fees at the Hospital at the tin.e of provision of service. 5. All costs of services rendered under this contract will be borne by the Company. Hospital will render bills to the Company based on current rate schedule at the time of the billing, and all payments under this agreement will be made to Hospital. 6. All releases of information concerning any Company personnel being treated at the Hospital in connection with a radiation exposure accident shall be provided and/or authorized by the Florida Power Corporation. Page 1 of 2 Pages

PURCHASE ORDER A 46961 EXHlDIT "A" 7. Only the Company's Nuclear Plant Manager or his designee shall be authorized to approve the admission of an indi;idual into the Hospital in the event of a radiation related accident. The Nuclear Plant Manager or his designee shall approve all invoices rendered under this agreement. Page 2 of 2 Pages

plOT da h " C " * " ' " *"' "- ~

""2 P.O. d -46960

~. 12/12/79 k'. A,g/ ' "" " ^ " " sr. ecTcassuno, rtonion 23-i

Power P O DATE:

PURCHASE ORDER ,e J ,o ..c.............~~o.. 711-9193 TO: SHIP TO: FLORIDA POWER CORPORATION CITRUS MEMORIAL HOSPITAL P. BAYNARD, C-4 = 502 HIGHIAND BOULEVARD P.O. BOX 14042 = INVERNESS, E 32650 ST. PETERSBURG, FL 33733 DR. BRIAN MCKAY/MR. CHARLES BLASBAND [I a v a..= s me.vs..y s.- .o., i o. -i o, ...io. g gm,az7wmv - w wwgwewnt.wwwmwwv.'ws.v.s.a.m7s g g 91 OTHR MAN 143370 12/31 C F , r-a 1, mo u r47. __ --"C '1" 'wt P "~ ' ' Is J'25Je., JL;I:L ':.n=t,="u_my,7 wx . s w,, ; r_a um h 720200f1700 BLANK 3T AGREEMENI FOR SERVICES THIS AGREEMENT ENTERED BY , ETWEEN FLORIDA POWER CORPORATIO!Q' REFERRED TO AS THE dANit MEMORIAL HOSPITAL REIN 4YTER R2 TO AS THE HOSP S FolhTl TORpodE OF RENDERING OF, MEDICA @ VIC s'>THE \\ HOSPITAL, FOR THE THE TERM S ON DECEMBERSIS,A197D TO %kCEMB

1982, OR UNTIC CANC IZED REPRESENTATIVE TIIE IZATION PROVIDING MT

$1X ( IONTHS ADVANCID V NOTIC$p' THIS A SHALL BE IN ACCORDANCE WITH EXHIBIT "A*, "SPECIAL CONDITIONS" (ATTACHED) ALL TERMS ON THE REVERSE OF THIS FORM ARE NULL _AND_ VOID. SHIP VtA: SIGN & RETURN AT ONCE FOB: DER ESTJAY D b RJ L U H J U. P 0. BOX 14042. ST. PETE RS8URG. FL 33733 O # .a. v"s a r.. -. - -,7 < -......t. / [ w ue t vs w A<W 2f5 ~.C2!- /

Purchase order #A 46960 EEmlT "6" FLORIDA POWER CORPORATION SPECIAL CONDITIONS 1. Florida Power Corporation, hereinaf ter referred to as the " Company", has constructed and is operating a nuclear power plant at a location known as Crystal River Unit No. 3 in Citrus County, Florida, hereinafter referred to as the " Plant, and Citrus Memorial Hospital hereinafter referred to as the " Hospital", is in a position to furnish the services of physicians, such availability shall be for the benefit of Company employees and members of the public who involved in actual or suspected radiation exposure or are contamination resulting from a nue. ear incident ocurring at the Plant. 2. Hospital shall accept all patients dispatched from the Plant and where necessary shall utilize the radiological support provided by the plant staff. (A credentialized list noting the qualifications of radiological support personnel of the Plant shall be provided to the Hospital and shall be updated quarterly.) 3. Company shall provide a training program to inform the appropriate Hospital physicians, nurses and technical per-sonnel, and appropriate Company personnel of the steps to be taken in the event of a radiation exposure accident. 4. Physicians fees for patient care services shall be based upon the current physicians' fees at the Hospital at the time of provision of service. 5. All costs of services rendered under this contract will be borne by the Company.. Hospital will render bills to the Company based on current rate schedule at the time of the billing, and all payments under this agreement will be made to Hospital. 6. All releases of information concer ting any Company personnel being treated at the Hospital in connection with a radiation exposure accident shall be provided and/or authorized by the Florida Power Corporation. Page 1 Of 2 Pages

Purchase Order # A46960 ExillBIT "A" 7. Only, the Company's Nuclear Plant Manager or his designee shall be authorized to approve the admission of an individual into the Hospital in the event of a radiation related accident. The Nuclear Plant Manager or his designee shall approve all invoices rendered under this Agreement. Page 2 of 2 Pages

Florida c~. a oc~. ox "a= P. O. A -4 6 9 o5 P. O. DATE: 01/03/80 sr. ecTonseunc, rooniD A 33733 ocy,f

Power PURCHASE ORDER

.Yej/ " " " ^ ' ' " ,o 720-0001 SHIP TO: FLORIDA POWER CORPORATION CITRUS COUNTY AMBULANCE SERVICE ATTN: MR. R. A. RINAKER, DIR. ATTN: P. BAYNARD C-4 502 HIGHLAND BLVD. P. O. BOX 14042 INVERNESS, FL. 32650 ST. PETERSBURG, FL. 33733 => r==m--m- ,+aw-mm-mmm-- % 1. OTHR MAN- - - -143354 12/31/82 c F 91 n r-4 7 n.-. R M W.TJam n d 'v5 w w n.w!" r T v ' ' ' ~ ' ' =uuww r' = - - - FM P "' ".W U""" " "' ' ^" 01 720 200 51700 AGREEMENT FOR AMBUIANCE SERVICES - LT 1 500.000 ESTIMATED COST - $500.00 NET AMBULANCE SERVICE TO PROVIDE ASSISTANCE IN THE EVENT OF AN EMERGENCY AT THE FLORIDA POWER CORPORATION CRYSTAL RIVER SITE UPON REQUEST FROM PLANT MANAGEMENT PERSONNEL. ACCEPTED BY: I THIS SERVICE WOULD PROVIDE FOR EMERGENCY MEDICAL TREATMENT AND/OR TRANSPORTATION TO RfCHARD A. RIdAKER A DESIGNATED HOSPITAL FACILITY. DYRECWR THE CONTRACT PERIOD FOR THIS AGREEMENT SHALL BE FROM JANUARY 1,1980 TO DECEMBER 31, 1982 o IN ACCORDANCE WITH: EXHIBIT A: CITRUS COUNIY AMBULANCE SERVICE LETTER DATED DECEMBER 6, 1979. EXHIBIT B: SPECIAL CONDITIONS SUPERSEDING THE STANDARD TERMS AND CONDITIONS IDENTIFIED ON THE REVERSE OF TilI5 URDER. N T PlLL FL Al A SALES AND USE TAX DEST BEST WAY DHL/dmg SHIP VfA-B N S T H _U C T,1 O_N_S

1. PLEASE SHOW PURCH ASE ORDE R NO. ON ALL PACK AGES. INVOICES, SHIPPING PAPE RS AND CORRESPONDF NCE.

2. PLE ASE SUBMIT INVOICE S IN TRIPLICATE TO P. O. BOX 14042. B-7 ACCOUNTS PAYABLE SECTION. ST. PE TE 4SBURG. FLORIDA 33733.

sunsect To coNoiveoNS oM

3. PLE ASE SUPPLY ALL INFORMATION REQUESTED ON ACKNOWLEDGMENT AND

.acx or Twes oporn .y RE TU RN PROMPT LY.

4. PLE ASE SHOW F. P. C. PART NO. FO 1 EACH ITEM ON YOUR PACKING LIST AND D* H. LACK CT ADM INISTRATOR 8

INVOICF WHFN APPt ICARL E.

~ EE.'.1.IT "8" FLORIDA POWER CORPORATION SPECIAL CONDITIONS 1. Florida Power Corporation, hereinaf ter referred to as the " Company", has constructed and is operating a nuclear power plant at a location known as Crystal River Unit No. 3 in Citrus County, Florida, herein-after referred to as the " Plant", and Citrus County Ambulance Service, hereinafter referred to as the " Service" is in a position to furnish Ambulance Services; such availability shall be for the benefit of Company employees and members of the public who are involved in actual or suspected radiation expo-sure or contamination resulting from a nuclear inci-dent occurring at the Plant. 2. The Service shril accept all patients dispatched from the Plant and where necessary shall utilize the radiological support provided by the plant staff. (A credentialized list noting the qualifications af radiological support personnel of the Plant shall be provided to the Service and shall be updated quarterly). 3. Fees for patient care services shall be based upon the current fees of the Service at the time of provi-sion of Ambulance Services. 4. All costs of services rendered under this contract will be borne by the Company. The Service will render bills to the Company based on current rate schedule at the time of the billing, and all payments under this agree-ment will be made to the Service. 5. All releases of information concerning any Company personnel being treated at the Hospital in connection with a radiation exposure accident shall be provided and/or be authorized by the Florida Power Corporation.

STATE OF FLORIDA THf STgS DEPARTMENT OF COMMUNITY AFFAIRS f' E. M ji 7 1$ y:1 DIVISION OF PUBLIC SAFETY PLANNING AND ASSISTANCE '...,,f*. ooo o-GOVEHNOR JOHN G BUHKE JoAN M HE GLN DIVISloN DlHECToH SECRETAHY December 18, 1979 Mrs. P. Y. Baynard Florida Power Corp. Mail Stop C-4 Box 14042 St. Petersburg, Florida 33733

Dear Patsy:

At our meeting in Wildwood Friday, Larry Hill asked me to write you regarding the updating of our Radiological Emergency Plan for Fixed Nuclear Facilities. Preliminary work for update is now in process. The initial draft of the basic plan is due in our office by January 10, annexes A-F, M, N, 0, AA, BB, CC by January 31. Agency S.O.P.'s and com-ments are due by March 31. Work with the counties to update annexes G thru L will be completed by July 1 following which, the entire plan will be submitted to the Department of Community Affairs for final review. The plan must then be submitted for approval under the Florida Administrative Procedures Act before it can be submitted to the NRC for concurrence. The concurrence process is another imponderable at this point. If the ground rules are the same as they were when the plan received concurrence initially, it should fly through quickly. Otherwise, who knows? TeMng an optomistic view of the above, I would estimate ve will have a new concurred plan by August, 1980. Our current con-currence expires on that date. Sincerely, Robert Kohler Radiological Defense RK/mc BUREAU OF DISASTER PREPAREDNESS 1720 SOUTH GADSDEN STREET. TALL AHASSEE, F LORIDA 32301 1904) 488-1320

ATTA'" MENT 3 FLORIDA POWER CORPORATION EVACUATION TIME ESTIMATES (AFTER fiOTIFICATION) FOR AREAS NEAR NUCLEAR POWER PLANTS i4ARCil 7,1980 The enclosed letter of January 31, 1980 from Florida Power Corporation to Mr. Brian K. Gaines, and attachment thereto, provides information relative to evacuation time estimates and is provided for supplemental information. Hill (EmerTrans)DN89

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Florida P...o..w...e..r.

January 31, 1980 Mr. Brian K. Grimer, Director Emergency Preparedness Task Group Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Crystal River Unit No. 3 Docket No. 50-302 Operating License No. DPR-72 Evacuation Time Estimates (After Notification) For Areas Near Nuclear Power Plants

Dear Mr. Grimes:

Your letter of November 29, 1979, requested Florida Power Corporation to submit, by January 31, 1980, evacuation time estimates (af ter notification) for areas near Crystal River Unit 3. In accordance with your November 29, 1979, request, Florida Power Corpora tion bereby submits evacuation time estimates (after notification) for areas near Crystal River Unit 3. Evacuation time estimates (af ter notification) for areas near Crystal River Unit 3 were developed and prepared by Mr. George J. Allen, Director of Disaster Preparedness, Citrus County, Florida; and Mr. John J. Bereznak, Civil Defense Director, Imyy County, Florida. General Office 320: Th <ty-fourth street soutn. P O Box 14042. St Petersburg. Florida 33733 e 813-866 5151

?* Mr. Brian K. Crimes Page Two nary 31, 1980 If you require any further discussion of our submittal, please contact this office. Very truly yours, FLORIDA POWER CORPORATION B. L. Cri in Senior Vice P esident Engineering & Construction LAHekcWa(D5) Attachment File Code: 3-0-5-g a

STATE OF FLORIDA COUNTY OF PINELLAS B. L. Criffin states that he ir the Senior Vice President, Engineering & Construction, Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information at-tached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief. 1 M ^ B. g. Gr Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 31st day of January, 1980. ~ Notary Public Notary Public, State of Florida at Large, My Commission Expires: August 8, 1983 CameronNotary 3(D12)

Citrus County Department of Disaster Preparedness o w eense e tionervi Acaonaaverese e twerness. Pierine sus) e phone taxiras4600, Exterwien 561 e Home Phone 5104) 726-5120 !anuary 25, 1980 Mr. Larry A. Hill, Licensing Specialist Florida Power Corporation Post Office Box 14042 St. Petersburg, Florida 33733

Dear Mr. Bill:

Reference your letter dated December 18, 1979.

Subject:

NRC Request for Evacuation Time Estimates (after notification) for Areas Near Nuclear Power Plants. The format for reporting information on areas for which you requested evacuation estimates will be keyed to numbers under required information as follows: Ref Distance Area a. 2 miles two 180 sectors b. 5 miles four 90 sectors c. about 10 miles four 90 sectors Requested information: Two estimates were requested in each of the areas defined above for a general evacuation of the population. A best estimate and an adverse weather estimate were requested for movement of the population. The information on areas for which evacuation estimates were requested encompass the entire area within e circle of about 10 miles radius, and are as follows: la. The first 180 sector A through H as shown on the map in the State of Florida Radiological Emergency Plan for Fixed Nuclear Facilities, the area two miles from the plant has no residents and _.a-site personnel are the only consideration. Florida Power Corporation and the Hollinswood Ranch own the property within thin radius. The Hollinswood Ranch is not involved in milk production. In the event of a major accident or continuing release, an assess-ment would have to be made regarding the cattle, coordinated with Departments of Health and Rehabilitative Services, Department of Agriculture, and Bureau of Disaster Preparedness. Sectors J through R were used in preparing this second estimate. There are no roads or homes located in these sectors. The waters along the shore line to include Crystal River and creeks which would have to be cleatr i of waterborne

traffic, Florida Marine Patrol Area 2103 in Crystal River est Laates that this area cou.'d be evacuated of waterborne traffic by Marine Patrol unics within 30 minutes during ideal weather conditions. Due to the units being out of the water during adverse weather, to dispatch personnel, launch units, and direct the heparedness is Survival

~ Page Two Mr. Larry Hill January 25, 1980 the movement of all waterborne traffic from these sectors of the low population zone would take approximately two hours. For the best estimate, I es t ima te 15 minutes warning and 45 minutes for evacuation. For the adverse weather estimate, I e-tim:Le 15 minutes for warning and 3 and 3/4 hours for evacuation. 14vy County: 2 miles-two 1800 eectors. As shown on the map, the area two miles from the plant would not affect Levy County so no planning has been considered. Ib. Sectors A, B, C, D, were used in preparing this first estimate. It is estimated that axpproximately 100 residents live within these sectors with-in 5 miles of the Florida Power Nuclear Plant. In the best response in simulat-ed evacuations in the yearly off-site exercises, it took less than one hour (15 minutes warning and 37 minutes evacuation) to warn and evacuate approximately 25 familes. TVo sheriff's deputies and two school buses were utilized. Deputies escorted the buses and completed data on a form for each family. In the longest it took approximately one hour and 30 minutes (15 minutes warning and one hour and fifteen minutes evacuation), Evacuscion is enchanced by radio receivers and radio sets in buses that can be used for this purpose. The number of homes and residents have increased partially offsetting time reduction estimates for these improvements. Under the best estimate, I would allow 15 minutes warning and 45 minutes for evacuation. For the adverse weather estimate, I would estimate 15 minutes for warning and I and 3/4 hours for evaucation. Sectors E,F,G, and F were used in preparing thic second estimate. It is estimated that approximately 100 residents live within these sectors within 5 miles of the Florida Power Nuclear Plant. Under the best estimate, I would allow 15 minutes warning and 45 minutes for evacuation. For the adverse weather estimate, I would estimate 15 minutes for warning and 1 and 3/4 hours for evacua-tion. J K, L, M, are the sectors of the third estimate. There are no residents in these sectors. Fort Island Beach and boat ramp are in the area. Most areas are waters of Crystal Bay, Crystal Reefs and the Gulf of Mexico. Warning for the beach could be effect in 15 minutes and evacuation could be completed within 45 minutes under best estimate. Under adverse it is doubtful that personnel would be on the beach; however, a check could be made and evacuation completed in an additional 45 minutes. The Florida Marine Patrol estimates 15 minutes warning and 3 3/4 hours for evacuation under best estimate. An additional two hours would be required under adverse conditions. N,P,Q,R, were used in preparing this fourth estimate. It is estimated that approximately 60 residents live within these sectors within 5 miles of the Florida Power Nuclear Plant. For land warning and evacuation under best estimate, I would allow 15 minutes for warning and one hour for evacuation. For adverse weather estimate, I would estimate 15 minutes for warning and two hours for evacuation. Ihe Florida Marine Patrol estimates 15 minutes warning and 3 3/4 hours for evacuation under best estimate. An additonal two hours would be required under adverse conditions. Levy County: Two 900 sectors would affect Levy County at the 5 mile range and these would be sectors Q & R - A & B. This would necessitate evacuation of the entire Yankeetown area with a population of 580. This could be accom-plished after notification within 2 h hours in adverse weather and I hours in good weather. This would complete evacuation in sectors Q,R.A.. Sector B

Page Three Mr. Larry Hill January 25, 1980 in the Inglis area with a population of 842 would be in the five mil _ area, but only a small area of the town would be subject to the five miles, arimeter. However, I understand when a municipality is af fected, all of the area must bk considered, therefore, the evacuation of the entire Inglis area vill be considered at this time. In adverse weather, conditions and approximate time of 3 hours and in good weather 2 h hours af ter notification. It is estimated that Ic. A-D are the sectors for the first estimate. 2,940 people live in these sectors in an area of about 10 miles in Citrus county around the Florida Power Nuclear Plant. Under the best estimate, I estimate 15 While I believe that minutes for warning and 2 and 3/4 hours for evacuation. most of the population would be evacuated within ih hours, the incapacitated and the unwilling or reluctant will extend the time to confirmation or when the For the adverse weather estimate, I estimate 15 minutes evacuation is complete. for warning and 5 and 3/4 hours for evacuation. During adverse weather the Sheriff's deputies, potential for power outages is increased significantly. police, firemen and volunteer organizations would be required to warn the public This delay in excess of 15 using vehicular public address units, sirens, etc. minutes is accounted for as evacuation time. It is estimated Sectors E-H were used in preparing this second estimate. approximately 9000 residents live within 10 miles of the Florida Power that In a recent population survey conducted by the Withlacoochee Nuclear Plant. Regional Planning Council, it was estimated that 7100 people live in the Crystal Under the best estimate, I estimate,15 minutes for warn-River Planning Area. ing and 2 and 3/4 hours for evacuation since approximately 75% of 12,000 within While I believe that most 10 miles or 9000 people live within these sectors. of the population would be evacuated within 1h hours, the incapacitated and the unwilling or reluctant will extend the time to confirmation or when the evacuation is complete. For the adverse weather estimate, I estimate 15 minutes for warning and 5 and 3/4 hours for evacuation. During adverse weather the Sheriff's deputies, potential for power outages is increased signifi antly.be required to warn the public police, firemen and volunteer organizations woult This delay in excess of 15 using vehicular public address units, sirens, etc. minutes is accounted for as evacuation time. There are no residents Sectors J-M, are tne sectors of the third estimate. Fort Island Beach and boat ramp are in the area. Most areas in these sectors. Warning for are waters of Crystal Bay, Crystal Reefs and the Gulf of Mexico. the beach could be effected in 15 minutes and evacuation could be completed Under adverse it is doubtful that within 45 minutes under best estimate. personnel would be on the beach; however, a check could be made and evacuation The Florida Marine Patrol estimates 15 completed in an additional 45 minutes. An additional minutes warning a 5 3/4 hours for evacuation under best estimate. two hours would be required under adverse conditions. The residents in Sectors N-R, were used in preparing this fourth estimate. this estimate are same as in Ib fourth estimate; in that Levy County borders Citrus County within 5 miles in these sectors. For land warning and evacuation under best estimate, I would allow 15 minutes for warning and one hour for For adverse weather estimate, I would estimate 15 minutes for evacuation. The Florida Marine Patro1' estimates 15 warning and two hours for evacuation. An additional minutes warning and 5 3/4 hours for evacuation under best estimate. two hours would be required under adverse conditions. e

Page Four Mr. Larry Hill January 25, 1980 Levy County: Notification of the second five mile area from the plant will be accomplished by sirens as the area is sparsely populated. Notification time should be very low-evacuation time increased. The evacuation of the area five miles beyond the first five miles would require approximately 2 hours in adverse weather and approximately 1 hour in good weather. Response to requested information: 2a. Not applicable. No special facilities within the area, 2b. Not applicable. No special facilities within the area. 2c. Several special facilities are located between the 5 mile radius and the about 10 mile radius. Under the best estimate, I estimate 15 minutes for warning and 1\\ hours for evacuation. The three schools located in these sectors have fire drills and have completed facility evacuation within 2 minutes. Alerting drivers, obtaining buses, and students operating privately owned automobiles could evacuate these sectors within an hour. The Seven Rivers Community Hospital was re-sponsive in their conduct of their part of the recent county emergency medical exercise. Under medium to light patient load and transportation availability (am-bulances for those requiring that degree of care), Hospital Safety and Citrus County Ambulance Service contends that the hospital could be evacuated in an hour. For the best estimate, I estimate 15 minutes for warning and I hour for evacuation. Under adverse weather estimate, I estimate 15 minutes warning and 2 and 3/4 hours for evacuation. Levy County: In the Yankeetown-Inglis area there are no special facilities. 3. In regards to confirmation of evacuation, we do not have special instru-crions to the public (e.g., tying a handkerchief to a door or a gate to indicate the occupant has left the premises). My opinion is that it is not a very effect-ive method. People who are reluctant to evacuate may tie the handkerchief and remain inside. People excited in the course of evacuating would forget to tie it in place. Several roads such as Ozello have only one access. Under the present procedures, I would call Mr. Thomas, the officer in charge of the Crystal River Post Office, for assistance. He would assign the mailman on that route to moniter people as they come out, asking if they knew of anyone remaining, and contacting this office as to residents believed to be in the area. Telephone communications would be attempted, shelter roster checked, and if necessary, police or firemen would be requested to enforce compliance with the evacuation order. Levy County: The time required for confirmation of evacuation should be in-dicated - Levy County does not have a confirmation plan at this time. 4. Perhaps our best planned and prompt notification system is our State of Florida Emergency Broadcast System Operational Plan. With one call to our Primary Common Program Control Station-1, the activation of EBS f acilities can broadcast situation summary, actions being taken by local government, and instructions to the public. We have planned a prograa to warn all residents in Citrus County within the 5 mile radius with a large siren system. Due to the lack of Federal matching funds, systems developed will be delayed until next year. Residents not hearing the EBS warning will be warned by police, firemen, and volunteer personnel using public address units, sirens, etc. Between the five mile radius and the about ten mile radius, firehouse sirens

Page Five Mr. Larry Hill January 25, 1980 will narn a saml1 percentage of population. Over 250 tone alert radio receivers are on the' county-wide fire alerting and warning frequency. When activated these .pdicated voluateer firemen respond to warn residents or issue protective actions Issued over the radio receiver. At the present time it is estimated that all of the population in the plume exposure emergency planning zone (EPZ or LPZ) can be warned within 45 minutes. Sheriff's deputies, police, firemen, and volunteers, have been effective in performing assigned warning tasks in past nuclear reactor accident exercises. Levy County-Notification of the second five mile area from the plant will 'be accomplished by sirens as the area is sparsely populated. Notification time should be very low-evacuation time increased. The evacuation of the area five alles beyond the first five miles would require approximately 2 hours in adverse weather and approximately 1 hour in good weather. 5. Citrus County is rural in nature. Alternative protective action in lieu of evacuation must be based on dose projections with consideration of release characteristics, meterological stability, vindspeed, dispersion or plume meandering, distance downwind, and air change rates in rooms or buildings to be used as shelters. No high density population areas are adjacent to the Florida Power Nuclear Plant. No special evacuation problems have been encountered. Levy County: There are no special evacuation problems. 6. The methods used to make these estimates and assumptions are based on four (4) nuclear reactor accident exercises conducted by this office. Mr. Buster Whitton, Supervisor of Transportation for the Citrus County School Board, with the support and direction of the Superintendent, provide Citrus County with a public transportation system during emergencies. Input on data and time estimates were presented by: Fire Chiefs, Citrus County Fire Protection and Taxing District Commis sion. M. Charles Dean, Director of General Services, Citrus County School Board. r Mr. Richard Rinaker, Manager, Citrus County Ambulance Service. Mr. Mark Slaughter, Risk Manager, Seven Rivers Community Hospital. Capt. D. F. (Tomcy) Williams, Florida Marine Patrol, Area 2103. Col. Fred Hess, Citrus County Composite Squadron, Civil Air Patrol. Mr. Dean R. Freeman, Citrus County RADEF Officer Mr. John B. Morrison Jr, City Manager, City of Crystal River In regards to routes, many areas such as Ozello, Indian Waters Shrimp Docks, Florida Power Plant Site, etc., have only one way in and out. People residing in this area if given the warning vill take feeder roads to arterial routes. Feeder routes have intentionally been eliminated from evacuation routes plans; in that, we feel it is unnecessary and could be a much greater potential problem. The Citrus County Composite Squadron of the Civil Air Patrol in cooperation I,.with the Radiological Defense Officer have estimated that in one hour aerialmo the nuclear plant. That they would be able to locate and plot the mainline of the plume and report readings observed by radio.

Page Six 'Mr. Larry Hill January 25, 1980 Levy County: 4he wethology used in making the estimates is that used by the State on evacuation plans for coastal areas in natural disasters using 800 vehicles per hour on single lane highways. This could mean evacuation could be completed quicker than allowed by my estimates, but I felt in a slow building natural disaster, the public would be informed and ready to move. The routes are generally accepted two lane highways and the transportation is by automobile. A l'ev people without cars are going to be bussed, this has been taken into con-sideration. No input was requested from the Citrus County Sheriff's Department; in that, past missions remain unchanged and data was available from these exercises. Sheriff Quinn and his staff have responded in an outstanding manner. If you have any questions, or if I can be of assistance, please do not hesitate to call on me. Sincerely, O Ce J1en Direclori isaster Preparedness GJA:rch Citrus C ty, FL M John J. Bereznak Director, Civil Defense Levy County, FL

ATTACHMENT 4 FLORIDA POWER CORPORATION CORPORATE EMERGENCY RESP 0 HSE PLAN MARCH 7,1980 Florida Power Corporation is developing a plan for corporate support to Crystal River Unit 3 in the event of an emergency. This plan will ad-dress response in areas similar to those covered in NSSD-17, Offsite Radiological Support Plan. Wherea s NSSD-17 provides support to the State Department of Health & Rehabilitative Services, the Corporate Emergency Response Plan will directly support Crystal River Unit 3. Among the areas to be addressed in this plan are the following: public af f ai rs/i nf oriliation, conriuni cati ons, security, logistics, procurement, transportation, engineering, technical consulting, legal, risk manage-ment, finance u " accounting. The corporate plan is to be conipleted in the Fall of 198L. Hill (EmerTrans)DN89

ATTACINENT 5 FLORIDA POWER CORPORATION USE OF POTASSIUM IODIDE (KI) MARCH 7, 1980 The Florida Power Corporation Medical Staff is presently reviewing the feasibility of using potassium iodide (KI) as a thyroid b!ocking agent during emergency situations. Upon completion of this review, a Corpo-rate Policy Statement will be issued and included in D.-100, Ei.ie rge rcy Plan, Draft (3/7/60). Hill (EmerTrans)Dii89

ATTACHMENT 6 FLORIDA POWER CORPORATION PUBLIC fiOTIFICATION AND WARNING SYSTU4S MARCH 7, 1980 The local governments of Citrus and Levy Counties are presently accepting bids for selection and installation of siren systems for public notification and warning in the event of an emergency at Crystal River Unit 3. Approximately four (4) sirens for each county are intended to be installed wit hi n a five-mile radius of CR-3. Upon conipletion of installation, public information will be provided as discussed in Attachment 7. Hill (EmerTrans)DN89

ATTACWENT 7 FLORIDA POWER CORPORATION PUBLIC INFORMATION MARCH 7, 1980 Upon implementation of EM - 100, Emergency Plan, Draft (3/7/80) and the State of Florida's revision of Radiological Emergency Plan for Fixed Nuclear Facilities, a public information program will be initiated by Florida Power Corporation. This will be performed in conjunction with the Civil Defense Directors of Citrus and Levy Counties to provide the citizens of these counties with emergency plan inforniation. The public information program will cover the early warning systen and actions to be tden by the general public in the event of an e;.iergency at Crystal River Unit 3. Pamphlets will be available to the residents of both counties within a ten (10) mile radius of Crystal River Unit 3. Plans are also being made to include emergency plan information in the next scheduled printing of the local telephone directories. Hill (EmerTrans)DN89

ATTACHMENT 8 FLORIDA POLER CORPCHATION EMERGENCY RESPONSE TLD LOCATIONS MARCH 7, 1980 The attached listing of emergency response TLD locations desc-ibes the locations in each sector at wtiich TLDs will be provided at the approxi-mate radii of 1, 5, and 10 miles from Crystal River - Unit 3. The State of Florida Department of Health & Rehabilitation Services (DHRS) proposed on June 5,

1979, and Florida Power Corporation concurred, the development of the program to provide these monitoring locations and capabilities. This program is based on the evalua? ion of State and Utility experience during and following the Three Mile Island incident.

TLDs wil l be provided at approximately 1, 5 and 10 mile distances from the plant except variations that are neces sa ry due to ease of collection or, in some instances, where the areas are not accessible. The monitoring stations will be in place by June 1,1980. The Nuclear Regulatory Cornission, in its Branch Technical Position on Regulatory Guide 4.8 (Revision 1, November 1979), has proposed the development of a similar ronitoring program and the DHRS program meets or exceeds that program. Hill (EmerTrans)DN89

EMERGEf;CY TLD LOCATIONS Sector 1 Mile 5 Mile 10 Mile f4 C60 C18 fiA I4NE C61 C03 C80 f(E C62 C04 C81 ENE C63 C74 C82 E C64 C75 C83 ESE C65 C7o C84 SE C66 C08 Cb5 SSE C67 C77 C86 S C68 C09 NA SSW C69 fiA NA SW C41 NA I4A WSW C70 C78 fiA W C27 C14G f;A Wi;W C71 fiA i;A NW C72 C01 NA T4N W C73 C79 NA lii 11(EmerTrans)Dfi89

EMERGENCY RESPONSE TLD LOCATIONS Station Distance troni Direction fro:a Number Location plant (miles) _gl_ apt C01 Levy Count

Dark 4.9 hw West end State Road 40 C03 Inglis NNL Adjacent to City Hall Fire Station C04 State Park Old Dam on River 6.3 NE near road intersection C08 Marine Science Station 5.1 SE (Mr. Hillard - Sec. Chief)

SR 44 Sec 24 R16E T18S C09 Citrus County Park 3.2 S West end State Road 44 C14G Gulf of Mexico end of 2.8 W Discharge Canal C18 Yankeetown City Well S.2 N C27 Ralston Purina Research 0.6 h Facility between Intake and Discharge Canals C41 On-site Meteorological U.4 S i. Tower C60 Not Determined h C61 Not Determined hNt C62 Not Determined NL C63 North side of north power 4400 ft. EhL line right of way C64 South side of access road 4400 ft. L 3920' from east side of guardhouse C65 Deepest forest penetrati on 1740 ft. ESL C66 Deepest forest penetration 1615 ft. S5 C67 Deepest forest penetration 1400 ft. SSL Hil l(EmerTrans)DNb9

Sample Station Location (Continued) Page 2 Station Distance from Direction from Number Location plant (miles) plant C68 Deepest forest penetration 1500 ft. S C69 Deepest ferest penetration 1780 ft. SSW C70 South intake canal road 4400 ft. WS '.. C71 Northwest corner of Ash 3600 ft. WN W Pond Dike C7' Not Determined hW C73 Not Determined hh-C74 Red Level, on power pole 5.4 EhL midway between the two curves on SR 488.9 mi east of U.S. 19 C75 First light pole on south side 4.5 L of plant access road 100' west of U.S. 19 C76 Highway 19, 1.7 miles south of 5.3 ESE access roaa C77 Crystal River,1.8 mi. past 3.8 SSE Marine Science Station, utility pole on south side of roa0way adjacent to abandoned road C78 West c.nd of North Intake Dike WSh C79 Yankeetown, SR 40 on utility 4.8 h!a. pole opposite Anchorage Ave. on north side of road 1.7 mi. west of Yankeetovn1 water tower C80 Highway Patrol Station 2.7 mi. 7.5 hht north of Inglis on Rt. 19. C81 Kitty Lane Drive and SR40, 10.9 hL 5.9 mi. east of U.S.19 Hill (EmerTrans)DN89

Sample Station Location (Continued) Page 3 Station Distance from Direction f roci Number Location plant (miles) plant C82 Rt. 488 and Rock Road, appror.. 10.9 Eid 7 mi. east of U.S.19 and 1.5 mi. east of bend in SR 488. Utility pole NW of 488 and Rock Road, a sign for Wright Groves is at intersection. C83 Rt. 495 and railroad crossing. 8.1 L Small pole supporting railroad warning signals NE of railroad and 495 intersection. C84 Rt. 44 and Rt. 486. 'vooden 10.4 ESE utility pole on SR 44 150' SE of intersection 44 and 486. C85 Rt. 494 and Rt. 19 10.5 SE C86 Ozello Volunteer Fire Station 9.4 SSE Hill (EmerTrans)DN89

ATTACHMENT 9 FLORIDA POWER CORPORATION CAPABILITY FOR FIELD IODINE SAMPLING MARCH 7,1980 Provisions have been made for the use of silver-zeolite cartridges as a sampling medium for field iodine measurements. Silver-zeolite cart-ridges are available on-site for this purpose and instructions for per-forming field measurements are covered in LM-208, Duties of the Radi-ation Emer gency Team. Additional provisions for offsite sei:ipli ng are covered by EM-210, Duties of the Environmental Survey Team. In response to Short-Term Lessons Learned recomaendations, a corriitment was made for tha the use of silver-zeolite for field surveys. In addi-tion, the use of a single-channel analyzer coupled to a cadinium-telur' 00 detector system is planned to quantify iodines and will be available for field use. This equipment is new and under evaluation, if it proves to be suitable for field use, the program is expected to be implemented by June, 1980. In the event that the cadmium-teluride system is found to be unsuitable for field use, the system will be replaced by a sodium iodiode detector. Hill (EmerTrans)DN89

ATTACHMLNT 10 FLORIDA P0kER CORPORATI0t. POST-ACCIDENT S41PLING AND ANALYSIS PROCEDURES MARCH 7, 1980 Procedures for post-accident radiological sampling and analysis are available and the following are enclosed for supplemental information as requested: EM-302 Post-Accident Sanpling and Analysis of Reactor Coolant EM-303 Post-Accident Saropling and An,i sis of Reactor Building Atmosphere EM-304 Post-Accident Sampling and Analysis of Effluent Releases from the Plant Hill (EmerTrans)DN89

I Rev. 0 2/15/80 - (".' = - 1 N F O R b,1/.s u e t 1l

c. F.

F. - ~ a EMERGENCY PLAN IMPLEMENTING PROCEDURE EM-302 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 POST-ACCIDE!.T SM1PLING AND ANALYSIS OF REACTOR C00LM.T REVIEWED BY: Plant Review Committe M ~ s Date 2/15/80 Meeting No. 80-7 APPROVED BY: Nucle r P nt ager h-dI" Date

1.0 PURPOSE 1.1 Procedural guidance is provided herein such that a sample of reactor coolant (RC) can be analyzed for pH, boron, dissolved gases (N, H, and 0 ), chloride, and gamma spectroscopy of 2 2 2 gases and liquid. Provisions are provided for sampling coolant for shipment off-site. The results of these analyses may aid in determining the severity of the accident and the steps necessary to minimize further impact of the event. Control is provided for sampling activities approaching 2 curies /ml of which noble gases predominate. 2.0 GENERAL GUIDELINES 2.1 The samples of RC are taken considering the consequences of LPe accident and the need for RC analyses. Radiological control is provided to insure that the dose to any individua] participating does not exceed quarterly dose limits. Coordi-nate all activities with the Emergency Coordinator. 2.2 If RC activities measured at the gas stripper expansion cham-ber are less than 10 R/hr. (contact), consider utilizing normal sample dilutions and conventional laboratory '.cch-niques.

3.0 REFERENCES

3.I NUREG-0578 3.2 10 CFR 20 Page 1 EM-302 Date 2/15/80 Rev. 0

i

3. 3 CH-261L, Determination of Radiogases in Pressurized Reactor Coolant and Auxiliary Systems

3. 4 CH-260L, Determination of Radionuclides Using Gamma Spectroscopy 3.5 CH-120L, Fisher-Hamilton !bdel 29 Cas Partitioner 3.6 CH-ll2L, Determination of Total Gas and Dissolved Cases (H2 and N ) in Pressurized Peactor Coolant and Auxiliary Systems 2

3.7 CH-Il4L, Determination of pil at 25'C Using the Fisher Accumet 420 3.8 CH-109L, Determination of pH With Orion 407-A pH Specific Ion !!eter 3.9 CH-10lL, Determination of Boron, tiannitol Complex Titration Method 4.0 ACCESS TO THE SA!!PLE STATION NOTE: Access to the Control Complex or Auxiliary Building vill be limited by released radioactivity and/or radiation from stationary sources. 4.1 Determine whether any RC sampling was in progress during the development of the accident. (See Shif t Supe rvist's Log. ) 4.2 Determine that CAV-1, 2, 3, and 126 are and have been closed. (See valve positions in Control Center. ) 4.3 Obtain appropriate Radiation Work Permit (P.WP), hi h range b survey instrument, high range dosimeter, protective clothing, and respiratory equipment. t Page 2 Di-302 Date 2/15/80 Rev. 0

NOTE 1: If sampling was in progress, the area near R:1-A7 may exceed 1,000 Rea/hr. and the Nuclear Sample Rocc may exceed 100 Ram /hr. Dose rates south of RMA-7 may exceed 10,000 Rem /hr. NOTE 2: Indications of extremely high dose rates in the Rt!A-7 area and the Nuclear Sample Room may be detected though the 2 ft. thick west walls of the Primary Laboratory and Counting Room. Assume 1/50 attenua-tion and correct for ambient local doses. N(;. 3: Down-scale readings on area and process monitors should be considered as indicating instrument failure and potentially high dose rate areas. 5.0 SAMPLING RC 5.1 INITIAL PRIMARY LABORATORY VALVE POSITIONS 5.1.1 Check that the post-accident sample bomb is properly coupled to the sample lines in the west Primary Laboratory hood. 5.1. 2 Check closed the post-accident sample bomb inlet and outlet valves, V-1 and V-2, and post-accident throttle valve, V-5. 5.1. 3 Note the dose rates at 2 f t. from the post-accident sample bomb. 5.2 VALVE ALIGNMENT IN NUCLEAP. SAMPLE ROOM NOTE: Once valves in the Nuclear Sample Room are positioned, realignment may be impossible af ter flow is estab-lished. ( Page 3 EM-302 Date 2/15/80 Rev. 0

5.2.1 Obtain permission from the Emergency Coordinator prior to entering the Auxiliary Building. NOTE: Approximate t1== to complete the Nuclear Sample Room alignment is 5 min.

5. 2. 2 Continuously monitor dose rate while proceeding toward RMA-7 area.

5.2.2.1 Return to Control Complex immediately if general area dose rate exceeds 30 R/hr. near RMA-7 area; if pot, go to Step

5. 2. 3.

5.2.2.2 Report observation to the Emergency Coordinator and await further instructions. 5.2.3 Determine dose rate at valve station in Nuclear Sample Room and check pocket dosimeter. 5.2.4 Align valves per Valve Check List I. (See Enclosure 1.) 5.2.5 Close any grab sample sink valves and close sample hood sash.

5. 2. 6 Note whether nuclear services cooling water is flowing to the primary sample coolers.

C5.2.7 Return to the Controf Complex. 5.3 PREPARATION OF PRIMARY LABORATORY

5. 3.1 Clear equipment f rom both primary hoods.

(20M) 5.3.2 Obtain post-accident sampling an,d analysis equipment from storage. 5.3.3 Set up shielding and position equipment per Enclosure 2. (45M) 5.4 EVACUATION OF GAS STRIPPER (See Enclosure 3.) Page 4 EM-302 Date 2/15/80 Rev. 0

5.5 STAdDARDIZATION OF GAS CHROMAT0 GRAPH (See CH-120L, Fisher-Hamilton Model 29 Gas Partitioner. )

5. 6 ESTABLISHMENT OF RECIRCULATION OF RC TO MUT-1 5.6.1 Notify Emergency Coordinator that laboratory is ready to begin recirculation and determine from Emergency Coordinator that nuclear services cooling is still operable.

5. 6. 2 Notify Control Center that CAV-126 and 2 are to be opened; close Vi5.

5. 6. 3 Slowly open V-1 and V-2 post-accident sample bomb inlet and outlet valves.

5.6.4 Throttle open post-accident sample bomb throttle valve, V-5. NOTE: Do not exceed 100 psig at discharge of throttle valve. See PI-G2. 5.6.5 At approximately 60 min. intervals, note throttle valve discharge pressure and determine dose rate at 2 ft. from sample bomb. (Record on Enclosure 4.) 5.6.6 Recirculate for 2 hrs. (assuming 0.5 gpm). NOTE: A constant dose rate may not indicate good RC sample since letdown may be isolated. 5.7 TERMINATION OF RECIRCULATION TO MUT-1 5.7.1 Close in order: post-accident sample bomb outlet (V-2), inlet (V-1), and throttle valve (V-5).

5. 7. 2 Notify Control Center to close CAV-126 and 2.

I Page 5 EM-302 Date 2/15/80 Rev. 0

6.0 ANALYSIS OF RC 6.1 EXCESS DISSOLVED GAS AND TEMPERATURE 6.1.1 Open V-8 and note pressure on PI-G2. NOTE: Pressure greater than 2 psig indicates high quantities of dissolved gases. Increasing pressure indicates leakage at isolation valves (V-1, V-2). Tighten valves if necessary. 6.1.2 Deterine temperature of sample obtained and cool to less than 150*F before proceeding. NOTE: Retire to low dose rate area during cooldown.

6. 2 DETERMINATION OF DISSOLVED OXYGEN IN RC 6.2.1 Open liquid sample port valve, V-7, and obtain a 1.5-ml sample of liquid with syringe. Hold Chemet rig with ampoule tip up.

6.2.2 Break tip by bending tubiag. NOTE: If color change occurs prior to liquid injection, obtain a second rig and repeat Step 6.2.2. 6.2.3 Insert syringe needle through septum and just into the Chemet ampoule. 6.2.4 Inject 1. 5-m1 of sample so that mixing occurs. 6.2.5 Compare with standard and record oxygen in range from lower limit of 100 ppb to upper limit of 1,000 ppb on Enclosure 4. 6.3 STRIPPING OF DISSOLVED CASES FROM RC 6.3.1 Follow instructions provided in Enclosure 5. 6.3.2 Record results on Form 912944. (See CH-ll2L, Determination 2 and N ) in Pressurized of Total Gas and Dissolved Cases (H 2 Reactor Coolant and Auxiliary Systems. i Page 6 EM-302 Date 2/15/80 Rev. O

6. 4 DETERMINATION OF pH AND BORON 6.4.1 Follow instructions provided in Enclosure 6.

6.4.2 Record results on data sheet. (See Enclosue 4.) 6.5 DETERMINATION OF GAS PHASE FISSION PRODUCTS, ETC. 6.5.1 Follow instructions provided in CH-261L, Determination of Radiogases in Pressurized Reactor Coolant and Auxiliary Systems. 6.5.2 Record dilutions on data sheet. (See Enclosure 4.) 6.5.3 Attach copy of isotopic analysis to Enclosure 4. 6.6 DETERMINATION OF LIQUID PRASE FISSION PRODUCTS, ETC. e.0.1 Follow instructions provided in CH-260L, Determination of Radionuclides Using Gamma Spectroscopy. b.6.2 Record dilutions on data sheet and attach isotopics. (See

nclosure 4.): 6. 7 DETERMINATION OF CHLORIDES 6.7.1 Follow instructions provided in CH-161L, Determination of Chloride, thrcuric Nitrate Titration Fkthod.

6.7.2 Record results on data sheet. (See Enclosure 4.) 6.8 DETERMINATION OF DISSOLVED H AND N2 2 6.8.1 Follow instructions provided in CH-112L, Determination of Total Gas and Dissolved Cases (H2 and N ) in Pressurized 2 Reactor Coolant and Auxiliary Systems, and CH-120L, Fisher-Hamilton }bdel 29 Gas Partitioner. 6.8.2 Record results on Form 912944 and attach to Enclosure 4. t Page 7 Eti-302 Date 2/15/80 Rev. 0

7.0 CALCULATIONS None 8.0 NOTIFICATION 8.1 Notify Emergency Coordinator of results obtained. 9.0 ENCLOSURES Valve Check List I Primary Laboratory Layout Evacuation of Gas Stripper Data Sheet Strip Noble Gases Determination of pH/ Boron i Page 8 EM-302 Date 2/15/80 Rev. 0

e i VALVE CllECK LIST I SYSTEM Post-Accident Pressurized Liquid Sample FLOW DIAGRAM NO. FD-302-672 Nuclear Sample Room MAR #80-2-6 VALVE NO. DESCRIPTION POSITION INITIALS VALVE NO. DEtCRIPTION POSITION INITIALS I CAV-323 Cooler Inlet open l CAV-324 Cooler Bypass Shut I CAV-330 Cooler Bypass Shut i CAV-329 Cooler Outlet Shut i CAV-333 Cooler outlet onen CAV-331 Sample Bomb Inlet Shut CAV-332 Sample Bomb Outlet Shut CAV-327 Flow Meter Iso. Shut i i CAV-309 Plow Meter Iso. Open CAV-336 Letdown Cooler outlet Shut CAV-337 Letdown Cooler outlet Shut Page 9 EM-302 Date 2/15/80 Rev. 0 ENCLOSURE 1

ENCLOSURE 2 (page 1 of 4) s. De N ) cq-Id N.-- I r ) %va'l o Q )H -ac r2 y 1H n NsQ ho N /2414= ta 1st Q N c s-y g \\ vz 1 a x ~ O Q 1 ~' at

k

'E 5 3{ t D 5W' 8 Ts ( Page 10 EM-302 Date 2/15/80 Rev. 0

ENCLOSURE 2 (page 2 of 4) t c [s 2 ,vc w g D f%k d ela M=R=$$g 4 2 4 t d S h =& o Mb 4h k geeswWORE4 d x4 a o l \\x d -a v% D % w / i 2 *$ e$ N ) kb E YN$ C o s t N Q l&R q* N ~

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~ Page 11 Di-302 Date 2/15/80 Rev. 0

ENCLOSURE 2 (page 3 of 4) ~ I ec ~' c cs N 4 et Q k b q d 9 k n%a $8i51' 0 k t u9 O T

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ENCLOSURE 2 (page 4 of 4)

1 Nuclear Sample Room
2 Primary Lab
3 Hood "A", Region 1
4 Hood "A", Region 2
5 Hood "B", Region 1
6 Hood "B", Region 2
7 Counting Room
8 Control Complex

( Page 13 EM-302 Date 2/15/80 Rev. 0

ENCLOSURE 3 EVACUATION OF GAS STRIPPER (~ 1. Evacuate rig from boundary valves (V-1 and V-2) outward. Open all valves except V-13 and V-6. 2. Purge with Argon, utilizing V-13 and V-6. Repeat Step 1. 3. Close V-7 and V-8. 4. Evacuate vacuum section. Observe manometer after clsing V-9 and V-10. 5. Record pressure changes on Form 912944. 6. Stop vacuum pump. ( AM 1 h v-13 l it V /2 A

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ENCLOSURE 4 DATA SHEET Date A. BKG Dose Rate at 2 ft. From Bomb: Initials R/hr. B. Outlet psig, Time Initials Outlet psig, Time Initials Dose R/hr., Time Initials Dose R/hr., Time Initials C. Dissolved 02 b PP, Initials D. pH , Initials E. Boron; Dilution

1, ml NaOH at 0.02N Boron ppm, Initials F.

Gas Final Dilution

1, Initials G.

Liquid Final Dilution

1, Initials H.

Chloride, Titrant al; Dilution

1, ppm Cl-I.

Dissolved H2 and N2 (See the attached.) Initials t Page 15 EM-302 Date 2,15/80 Rev. 0

ENCLOSURE 5 STRIP NOBLE GASES /N9 AND H7 / 1. Throttle open V-10 to expand to vacuum region. 2. If pressure is greater than 10 cm Hg, go to Step 5. 3. If pressure is less than 10 cm Hg, increase positive pressure by addition of Argon via V-6. Close V-6. 4. Drain water from glass chamber and close V-11. 5. Record pressure on Form 912944. 6. Remove 5-m1 and 10A of gas and store in syringes behind shield. 7. Close V-8; open V-11 and V-9; and evacuate. 8. Close V-9, open V-13, and bring pressure to 20 cm Hg. 9. Open V-8. NOTE: Additional liquid samples can now be taken at V-7. ( APC4M

V-13 ll V ##

-x = b v4cannt v-9

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ENCLOSURE 6 DETERMINATION OF pH/ BORON 1. Obtain a 0.5-m1 sample by syringe and dilute 100:1. 2. Determine pH per CH-109L, Determination of pH With Orion 407-A pH Specific Ion Meter, or CH-114L, Determination of pH at 25'C Using the Fisher Accumet 420. 3. Determine boron per CH-101L, Determination of Boron, Mannitol Complex Titration Method, utilizing 0.02N NaOH. f ( Page 17 EM-302 Date 2/15/80 Rev. O

Rev. 0 2/15/80 i ] is F O., ' . ~ :- :a p. joNL 9// d i EMERGENCY PLAN IMPLEMENTING PROCEDURE EM-303 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 POST--ACCIDENT SAMPLING AND ANALYSIS OF REACTOR BUILDING A20 SPHERE O REVIEWED BY: Plant Review Cocmittee O A Date 2/15/80 Heeting No. 80-7 APPROVED BY: Nucle r at Manager i N k-a s-ro ..t.

1.0 PURPOSE 1.1 The purpose of this procedure is to describe the actions taken to sample and analyze the Containment Suilding atmosphere for radionuclide concentration and hydrogen content under accident conditions described in EM-100, Emergency Plan. 2.0 CENERAL GUIDELINES 2.1 The methodology and techniques described are designed to limit the dose to an individual to within NRC, NUREG-0578 guide-lines.

3.0 REFERENCES

3.1 EH-100, Emergency Plan 3.2 0H-215, Post-Accident Reactor Building Purging

3. 3 EP-106, Loss of Reactor Coolant or Reactor Coolant Pre sure 3.4 CH-260L, Determination of Radionuclides Using Camma Spectroscopy 3.5 CH-112L, Determination of Total Gas and Dissolved Gases (H2 and N ) in Pressurized Reactor Coolant and Auxiliary Systems 2

4.0 ACCESS TO SAMPLE STATIO!j 4.1 Upon request to initiate sampling of Containment Building atmosphere, contact Health Physics for Radiation Work Permit (RWP) and entry precautions. 4.2 Before entry to obtain sample, notify the Emergency Coordina-tor of planned entry time and sampling team identification and i Page 1 EM-303 Date 2/15/80 Rev. 0

location. Door-to-sample station is on key-card lock for entry. 4.3 Sampling station located at 119 ft. elevation of Intermediate Building, north side of containment.

4. 4 Start at 95 ft. elevation of Control Complex and proceed per attached maps (Figures 1 thru 3).

Return path is reverse of entry path. 5.0 SAMPLING OF CONTAINMENT ATMOSPHERE 5.1 SAMPLING PRECAUTIONS AND PREPARATION 5.1.1 Review material Checklist I before proceeding to sample station. 5.1.2 Review valve list versus sample station flow diagram for familiarity (Checklist II and Figure 4). 5.1.3 Proceed cautiously to sample station and perform radiation surveys (area and airborne) as required. 5.1.4 Review Checklist I at sampling station. If equipment is missing, return to lab for further instructions. 5.1.5 Align valves per Checklist II. If there is a valving problem, return to lab for further instructions. 5.1.6 Align containment isolation valves for sampling as follows: Open LRV-45 and LRV-46; close LRV-63. -a. b. Open SAV-24 and SAV-122. NOTE: Perform dose rate survey during these operations. Monitor pocket dosimeter and do not exceed RWP limits! t Page 2 EM-303 Date 2/15/B0 Rev. 0

5. 2 OBTAINING SAMPLE 5.2.1 Valve in eductor by opening either V-12 or V-II (V-12 if gas bottle available).

NOTE: Use lead gloves for work on sample rig. 5.2.2 Valve in purge air by opening V-9 and V-3. Check for flow on flow meter. If gas bottle is used for eductor, adjust dis-charge pressure to maintain approximately I cfm on ficw meter. If station air is used, use flow meter to adjust to above value. 5.2.3 Valve in containment sample by closing V-9 and opening V-2, respectively. Check the flow meter and adjust the flow to between 0.5 and 1.5 cfm. Check area dose rate.

5. 2. 4 Note flow rate and sample time and retreat to a low dose rate area (i.e., Turbine Building). Allow sample rig to purge for approximately 5 min.

5.2.5 Af ter appropriate time has passed, re-enter the sampling area cautiously and. monitor for habitability. Open V-4 and close V-7 and V-8 simultaneously. Close V-6 and V-5.

5. 2. 6 Disconr.ec t sample bomb, open V-9, and close V-2.

Place sample bomb in Turbir.e Building and complete purge of sample rig. Purge for 1 to 2 min. 5.2.7 Close V-3, V-9, and V-11 or V-12. Assure no flow through sample flow meter. 5.3 TRANSPORT TO LAB 5.3.1 Transport the sample bomb (two people) to the lab via route listed in Section 4.0. Page 3 EM-303 Date 2/15/80 Rev. 0

5.3.2 Store in appropriate place in laboratory, label, and post area based on dose survey. 5.4 SAMPLE PREPARATION NOTE: Use shielding and lead gloves to reduce dose rate. 5.4.1 Using the apparatus listed in Figure 4, perform the following steps: a. Evacuate the 150-ce glass sphere and connnecting tube by attaching sample bomb at V-13; opening V-13, V-14, and V-15; and attaching vacuum source at V-15. b. Af ter expansion apparatus is evacuated, close V-15 and V-14. c. In order to evaluate pressure / vacuum status of sample bomb, slowly crack open V-8 and monitor pressure / vacuum gauge f or rapid changes. If no rapid changes occur (indicated by rapid pressurization of connecting tube), continue opening V-8 and allow bomb to equalize. d. If rapid pressurization occurs, shut V-8 and check total pressure on connecting tube. Shut V-13 and allow connect-ing tube to equalize with glass sphere. Determine pres-sure change on sphere. Open V-13 and carefully open V-8 to allow bomb and sphere to equilibrate. Record final pressure vacuum on rig. e. If sample rig is under a vacuum, pressurize to atmospheric (~0" on gauge) using Argon via V-7 adn V-17. Once pres-sure is obtained, isolate V-7 and V-17. I Page 4 EM-303 Date 2/15/80 Rev. 0

4 f. If sample rig is pressurized, vent to atmospheric through charcoal filter system in hood. g. Af ter the sample sphere (150-ec) is at atmospheric pres-sure, align the rig to the manometer by opening V-15 and V-16. Af ter the manometer stabilizes (D0 NOT SUCK OR BLOW OUT MERCURY; OPEN SLOWLY.), check manometer reading. If manometer indicates a pressure or vacuum less than 20 =m, apply Argon through V-17 to bring pressure to indicated value. h. Isolate the sample rib ing in order V-15, V-14 V-7, V-8, and V-16. 6.0 SAMPLE ANALYSIS 6.1 DILUTION OF SAMPLE 6.1.1 ' If the 150-ce glass sphere reads in excess of 1.5 R/hr. on contact, a two level dilution is required. 6.1. 2 If > 1.5 R/hr., perform the following: Remove 10-ul from the 150-ce glass sphere and inject it a. into a shielded 150-cc glass sphere. b. Remove 100-ul from the second 150-cc sphere and inject it into a 34-cc glass sphere for counting. 6.1.3 If < 1.5 R/hr., perform the following: Remove 10-ul f rom the 150-ce glass sphere and inject it a. into a 34-ce glass sphere for counting. f Page 5 EM-303 Date 2/15/80 Rev. O

6. 2 ISOTOPIC ANALYSIS 6.2.1 Place the 34-ce glass sphere for counting on the Ge(Li) detector in the Count Room.

6.2.2 Perform counting per CH-260L, Determination of Radionuclides Using Gamma Spectroscopy. 6.2.3 Analyze using GRWRAP and obtain printout. 6.3 HYDROCEN ANALYSIS 6.3.1 Set up gas partitioner and standardize per CH-il2L, Determina-2 and N ) in Pressur-tion of Total Gas and Dissolved Cases (H 2 ized Reactor Coolant and Auxiliary Systems. 6.3.2 Remove 5-cc from glass sphere in Step 5.4.1. 6.3.3 Inject the 5-cc into the gas partitioner and store used syringe in a shielded container. 6.3.4 Obtain relative peak height for sample and standards. 7.0 CALCULATIONS 7.1 ISOTOPIC ANALYSIS DATA REDUCTION 7.1.1 Apply dilution ratio from Section 6.1 to each isotope listed on GRWRAP printout. 7.2 HYDROGEN DATA REDUCTION 7.2.1 Compare hydrogen peak to standards previously run (value obtained in percent). 8.0 NOTIFICATION OF DATA 8.1 Inform supervisor of results immediately. If supervisor is not available, notify the Emergency Coordinator of results. t Page 6 EM-303 Date 2/15/80 Kev. O

9.0 ENCLOSURES F.gure 1, Map to Samp2e Station Figure 2, Map to Sample Station Figure 3, Map to Sample Station Checklist I, Material Needed to Obtain Containment Atmospheric Sample Checklist II, Valve List for Sample Station Figure 4, Containment Sampling Station and Dilution / Expansion Apparatus L Page 7 EM-303 Date 2/15/80 Rev. O

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ENCLOSURE 4 - CHECKLIST I - MATERIAL NEEDED TO OuTAIN CONTAINMENT ATMOSPHERIC SAMPLE 4 1. System Key - from Shift Stpervisor for locked valves 2. Flashlight 3. RWP - HP 4. Dosimetry - per HP; Includes extren'ty and WB TLD and high range pocket dosimeters. 5. Sample Bomb - sample station 6. Flow Meter - sample station 7. Shielding - sample station 8. Lead Gloves - emergency sampling kit 9. Radio - Emergency Coordinator 10. Valve Wrenches (2) - small (for "V" valves) medium (for containment isolation valves) O o ( Page 11 EM-303 Date 2/15/80 Rev. 0

ENCLOSURE 5 - CHECKLIST II - VALVE LIST FOR SAMPLE STATION Valve No. Position V-1 Closed V-2 Closed V-3 Closed V-4 Closed V-5 Open a V-6 Open V-7 Open V-8 Open V-9 Closed V-10 Full Open Closed V-ll V-12 Closed O I Page 12 EM-303 Date 2/15/80 Rev. 0

ENCLOSURE 6 Figure 4 A6wa.f _G- /4 J% A'~ 'f db y-t b v-2 v-3 n 14l-m.e m & V-c F n v-9 y., z v-/t Q4 h E0 acre,e O V-10 .Gewp's bed V-l'1 mrtescx ce omen

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Rev. 0 2/15/80 , s,/ 1 il N F O F. W. 2 l t*l

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EMERGENCY PLAN IMPLD4ENTING PROCEDURE EM-304 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 POST-ACCIDE!E SA!1PLING AND ANALYSIS OF EFFLUEIR RELEASES FROM THE PLA C 0 REVIEWED BY: Plant Review Committee h g-ate 2/15/80 Meeting No. 80-7 APPROVED BY: Nucle r ant } ager f M -h b Date

1.0 PURPOSE 1.1 The purpose of this procedure is to describe the actions to be taken to sample and analyze effluent releases from the plant under accident conditions as defined by EM-100, Emergency Plan. 2.0 GENERAL GUIDELIhTS 2.1 The methodology and techniques described are designed to sample and analyze plant effluents when the radiation monitor-monitoring system (RMS) is off-scale due to accident condi-conditions.

3.0 REFERENCES

3.1 Di-100, Emergency Plan 3.2 EM-204, Dose Assessment By Use of Meteorological Overlays 3.3 CH-260L, Determination of Radionuclides Using Gamma Spectroscopy 4.0 ACCESS TO SAMPLE STATION 4.1 Upon request to initiate samplinF of effluent releases from the Auxiliary Building, contact Health Physics for Radiation Work Permit (RWP) and entry precautions. 4.2 Before entry into Auxiliary Building to obtain sample, notify the Emergency Coordinator of planned entry time, sampling location and route, and sampling team identification. Page 1 EM-304 Date 2/15/80 Rev. 0

4. 3 Sampling station located at 143 ft. elevation of Auxiliary Building, east side of containment.

4.4 Start at 95 ft. elevation of Control Complex and proceed per attached maps (Figures 1 thru 3). Return path is reverse of entry path. 5.0 SAMPLING OF EFFLUENT RELEASES 5.1 SAMPLE PRECAUTIONS AND PREPARATION 5.1.1 Review material Checklist I before proceeding to sampling station. 5.1. 2 Review valve list versus sample station flow diagram for familiarity (Checklist II and Figure 4). 5.1.3 Proceed cautiously to sample station and perform radiation surveys (area and airborne) as required. 5.1. 4 Review Checklist I at sample station. If equipment is missing, return to lab for further instructions. 5.1. 5 Align valves pei Checkaist II. If there is a valving problem, return to lab for furthe instructions. 5.1.6 Align valves for sampling based on applicable duct to be sampled. For RM-A2, open V-3 and V-6 on sampling rig and close V-13 a. at RM-A2. b. For RM-Al, open V-3 and V-6 on sampling rig. NOTE: Perform dose rate survey during these operations! Monitor pocket dosimeter and oo not exceed RWP limits! t Page 2 EM-304 Date 2/15/80 Rev. O

5. 2 OBTAINING SAMPLE 5.2.1 While outside air is being purged through sampling rig per Step 5.1.6, check flow meter for positive indication and attach 34-ce glass sphere between V-9 and V-8.

5. 2. 2 Valve in RM-Al or RM-A2 5.2.2.1 For RM-A1, open (in order) V-8, V-10, V-11, V-9, and close V-7.

Open V-2 and close V-6. Sample should now be flowing through sample rig. If no flow exists, -heck valve lineup carefully. If there is no problem with valve lineup, it may be necessary to shut RM-Al off if it is running. Contact Emergency Coordinator for permission to shut RM-Al down. If permission is given, proceed cautiously to RM-Al and terminate pump operation. If dose along way exceeds 30 R/hr., stop and report inability to access area from as low a background area as possible. Adjust flow to 1 cfm. 5.2.2.2 For RM-A2, open (in order) V-8, V-10, V-11, V-9, and close V-7. Open V-1 and close V-6. Check for flow. If no flow, check valve lineup. If still no flow, report problem to Control Center / Emergency Coordinator for further instructions. Adjust flow to I cfm.

5. 2. 3 Record flow rate and time on.

Monitor dose rate from sample lines. 5.2.4 Set detector in suitable geometry per rigure 5. 5.2.5 Bypass sample sphere by opening V-7 and closing, simulta-neously, V-10 and V-II. Also close V-8 and V-9. t Page 3 EM-304 Date 2/15/80 Rev. O

5.2.6 Remove glass sphere and place it in detector holder from Step

5. 2. 4.

Obtain dose rate from detector and convert reading to uCi/cc using Figure 6. Report this value to the Control Center for use in EM-204, Dose Assessment By Use of Meteoro-logical Overlays. 5.2.7 Store sample sphere in suitable area (shielded if necessary) to await transport to lab for analysis. 5.2.8 Continue sampling through filter and charcoal cartridge for o approximately 15 mia. Re treat to a low dose aren (i.e., between fuel pools) until sampling is complete. 5.2.9 Isolate sampling rig from source by shutting either V-1 or V-2 and opening V-6. Allow filters to purge for 5 min. with out-side air. Re treat to low background for purge time. 5.2.10 Open V-4 End close V-3 and V-5. 5.2.11 Remove filters from holder, add new filters, and return to sample rig. 5.2.12 Place filters in bag in shielded area. O 5.2.13 Re-establifsh flow past detector by opening V-1 or V-2 (either RM-A2 or RM-A1), V-5, and V-3. Close V-4. Place detector in holder to monitor sample line. 5.3 TRANSPORT OF SAMPLES TO LAB 5.3.1 Transport sample sphere to lab via route listed in Section

4. 0.

Shield if necessary. 5.3.2 Store in designated area in lab, label, and post area based on dose survey. I Page 4 EM-304 Date 2/15/80 Rev. O

6.0 SAMPLE ANALYSIS 6.1 DILUTION OF SAMPLE 6.1.1 If sample sphere reads in excess of 1.5 R/hr., do a dilution as follows: a. Remove 100-ul of sample and inject it into a 34-ce glass sphere. 6.2 ISOTOPIC ANALYSIS 6.2.1 Place the 34-ce glass sphere on the Ge(L1) detector in the Count Room. 6.2.2 Count the sample per CH-260L, Determination of Radionuclides Using (amma Spectroscopy. 6.2.3 Analyze using GRWRAP and obtain printout. 7.0 CALCULATIONS 7.1 ISOTOPIC ANALYSIS 7.1.1 Apply dilution ratio from Section 6.1 to each isotope listed on GRWRAP printout. 7.2 EVALUATION OF EFFLUENT RELEASES FROM AUXILIARY BUILDING OR REACTOR BUILDING 7.2.1 Utilize EM-204, Dose assessment By Use of Meteorological Ove rlays, to calculate dose rate from source term determined in this procedure.

7.2.2 Alternately

total uCi/cc x cc/sec. (in duct) = uCi/sec. released (from GRWRAP or count rate) Page 5 EM-304 Date 2/15/80 Rev. O

7.2.3 If dose rate versus isotopic distribution is known (K-factor) for monitor at sampling station, the following formula can be used: dose rate x K-f actor (mR/hr/uCi/cc) x cc/sec. (in duct) = uCi/sec. released (count rate) 7.3 EVALUATION OF STEAM RELEASES 7.3.1 Evaluation of Releases Due to Atmospheric Steam Releases From Turbine Trip or Steam Vent 7.3.1.1 Obtain samples from secondary side and analyze for radio-nuclide concentration. a. Noble Gas Sample From RM-Al2 and Analysis (in uCi/ml) G(uci/cc) x 10/600 x S(lbs/hr.) x 1/3600 hrs /sec. x V s (cc/lb.) x R = uCi/sec. from both steam generators WHERE: G = uCi/cc in RM-Al2 sample 10/600 = Ratio of eductor makeup air to condenser in-leakage. S = Steam bypassed to condenser in lbs/hr. V, - Specific volume of steam to condenser. R = Ratio of total steam released to bypass steam (1bs/hr/lbs/hr), b. Io.:ine Sample From Generator, Condenser, or Steam I(uci/ce) x S(lbs/hr.) x 1/3600(hrs /sec.) x V (cc/lb.) x s R = uCi/cc of iodine WHERE: I = uCi/cc in sample of iodine R = Ratio of total steam to bypass steam. ( Page 6 EH-304 Date 2/15/80 Rev. O

S = Lbs/hr. of steam released. Vs " Specific volume of steam released. c. Calculation of Concentration of Steam Released and Total Ci Released T(uCi/sec. ) x R (sec. ) x 10-6 = Ci t WHERE: T = Total Release Rate - (1) + (2) in uCi/sec. Rt = Total release time from Control Center main steam pressure recorder. 10-6 = Number of C1/uC1. 7.4 EVALUATION OF GASEOUS RELEASES FROM TURBINE BUILDING 7.4.1 Obtain sample and analyze grab sample from Turbine Building atmosphere. T (uCi/cc) x R(cu. f t/ min.) x cfm/cc/sec. = uC1/sec. b WRERE: Tb = Activity in Turbine Building (uCi/cc) R = Flow Rate Out of Turbine Building (cf/m) 8.0 NOTIFICATION OF DATA 8.1 Inform supervisor of results immediately. If supervisor is not available, notify Emergency Coordinator of results. 9.0 ENCLOSURES Figure 1, Map to Sample Station Figure 2, Map to Sample Station Figure 3, Map to Sample Station Checklist I, lhterial Needed to Obtain Effluent Release Sample i Page 7 EM-304 Date 2/15/80 Rev. 0

Checklist II, Valve List for Sample Station Figure 4, Effluent Sample Station Enclosure Z. Figure 5, Detector Holder Figure 6, Detector R/h. Versus uCi/cc Curve ( Page 8 EM-304 Date 2/15/80 Rev. O

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ENCLOSURE 4 d - CHECKLIST I - MATERIAL NEEDED TO OBTAIN EFFLUENT RELEASE SAMPLE f 1. Status of Pump Operation for RM-Al snd RM-A2: RM-Al - Pump On Off Date/ Time / Initials RM-A2 - Pump On Off Date/ Time / Initials 2. Flashlight 3. Lead Gloves - Emergency Samuling Kit 4. Particulate and Charcoal Fitiers - Lab 5. 34-cc Sample Sphere - Lab or Eiergency Sampling Kit 6. Dosimetry - Lab (HP); Extremity and Whole Body TLD and High Range Dosimeter 7. Flow Meter - Sample station installed. 8. Filter Holder - Sample station with filters installed. 9. Detector Holder - Emergency Sampling Kit (Figure 5) i Page 12 EM-304 Date 2/15/80 Rev. O

ENCLOSURE 5 - CHECKLIST II - VALVE LIST FOR SAMPLE STATION Valve No. Position V-1 Closed V-2 Closed V-3 Closed V-4 Closed V-5 Open V-6 Closed V-7 Open V-8 Open V-9 Open V-10 Closed V-ll Closed V-12 Full Open V-13 Open ( Page 13 EM-304 Date 2/15/80 Rev. O

ENCLOSURE 6 EgNtee. Y ED76mf ~.re,,L J%a%b rnva g Ars AM AI AZ ro, << v 4M A.1. gv-3 y-2 f V-/ v-v W V-S~ g 1; Sash Im $ y-/g a g"V-lo , eaw c s-.a b b' geln f a he/Ju Y-9 0 &V-8 g V-V ~ 5fM ppm tf.3 nIbcar t' p b I .'.I (P c.) r _. __ _ _ __ i r VM - A2 Page 14 EM-304 Date 2/15/80 Rev. O

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R.Fdr 6 6 ENCLOSURE 8 y Carre ada M % : Aadiel59i& f % l4 k,<d% k, pose 131 ie f / / / ( / / r t N -,. 1 / J/ _p/ %/ W &, Y h/ Kv $ / 10 h l M.) / n W / d M O / /kg/ .V/ v < >T / / Wr/3_t/ 4%f'L f p / / t) k W / A N / rj f Wl i / / / / / / / f / Al / / / / / f e-k A01 s lY 106 gos 10r gas ,o /[*fC4 Page 16 Df-304 Date 2/15/80 Rev. 0 ..}}

ML19290E470

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Text

Subject:

Dear Mr. Ehenhut:

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Dear Patsy:

Subject:

Dear Mr. Grimes:

Dear Mr. Bill:

Subject:

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

7.2.2 Alternately

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Text

Subject:

Dear Mr. Ehenhut:

= =. = = = = =

Dear Patsy:

Subject:

Dear Mr. Grimes:

Dear Mr. Bill:

Subject:

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

7.2.2 Alternately

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