Text

Transmittal of Changes to Emergency Plan Implementing Procedures (EPIP)
	ML041140430
Person / Time
Site:	Fort Calhoun
Issue date:	04/14/2004
From:	Herman J; Omaha Public Power District
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LIC-04-0048
	Download: ML041140430 (98)
	v • d • e

P u Omaha Pub/k POsheJDbSfrkf 444 South 16th Street Mall Omaha NE 68102-2247 April 14, 2004 LIC-04-0048 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

Transmittal of Changes to Emergency Plan Implementing Procedures (EPIP)

In accordance with 10 CFR 50.54(a), 10 CFR 50, Appendix E, Section V, and 10 CFR 50.4(b)(5), please find EPIP, EPF and RERP change packages enclosed for the Document Control Desk (holder of Copy 165) and the NRC Region IV Plant Support Branch i

Secretary (holder of Copies 154 and 155).

IN, The document update instructions and summary of changes are included on the i

Confirmation of Transmittal form (Form EP-1) attached to each controlled copy change package. Please return the Confirmation of Transmittal forms by May 31, 2004.

AIM The revised documents included in the enclosed package are:

e FC-EPF Index pages 1 and 2 issued 04/06/04 FC-EPF-34 RI issued 03/31/04 FC-EPF-1 R8 issued 03/31/04 FC-EPF-36 R5 issued 03/31/04 FC-EPF-2 R4 issued 04/02/04 FC-EPF-37 RI issued 03/31/04 FC-EPF-8 R7 issued 04/02/04 FC-EPF-38 R7 issued 03/31/04 FC-EPF-12 R4 issued 03/31/04 FC-EPF-41 RI issued 03/31/04 FC-EPF-13 RI issued 03/31/04 FC-EPF-43 RI issued 04/06/04 FC-EPF-15 R4 issued 03/31/04 RERP Index page 1 of I issued 04/06/04 FC-EPF-17 R4 issued 04/06/04 RERP-Section L RI 1 issued 01/27/00 FC-EPF-27 R4 issued 04/02/04 EPIP Index pages 1 and 2 issued 04/02/04 FC-EPF-29 R2 issued 03/31/04 EPIP-EOF-6 R33 issued 04/02/04 FC-EPF-31 R3 issued 03/31/04 EPIP-RR-25 R22 issued 04/02/04 FC-EPF-32 RI issued 03/31/04 EPIP-RR-72 R14 issued 04/02/04 A _0 qff, Employment with Equal Opportunity

U. S. Nuclear Regulatory Commission LIC-04-0048 Page 2 If you have any questions regarding the enclosed changes, please contact Mr. Carl Simmons at (402) 533-6430.

Sincerely,

/. Herman abager - Nuclear Licensing JBH/ckf Enclosures c: NRC Region IV Plant Support Branch Secretary (2 sets)

Alan Wang, NRC Project Manager (w/o enclosures)

J. G. Kramer, NRC Senior Resident Inspector (w/o enclosures)

Emergency Planning Department (w/o enclosures)

FORM EP-1 Rev. 6 (04/29/99)

OMAHA PUBLIC POWER DISTRICT Confirmation of Transmittal for Emergency Planning Documents/lnformation rz71 Radiological Emergency Emergency Plan P Ening V..ŽN Response Plan (RERP) (EImpleetngPoedrsForms (EPF)

D Emergency Planning Department Manual E Other Emergency Planning Document(s)/

Information (EPDM)

Transmitted to:

Name: Document Control Desk CoDY No: 165 Date:

Plant Support Branch Secretary Cogv No: 154 Plant SuDport Branch Secretary CODy No: 155 The following document(s) / information are forwarded for your manual:

REMOVE SECTION INSERT SECTION FC-EPF Index pages 1 and 2 issued 12/16/03 & 01/29/04 FC-EPF Index pages 1 and 2 issued 04/06/04 FC-EPF-1 R7 issued 11/29/01 FC-EPF-1 R8 issued 03/31/04 FC-EPF-2 R3 issued 03/15/01 FC-EPF-2 R4 issued 04/02/04 FC-EPF-8 R6 issued 07/23/02 FC-EPF-8 R7 issued 04/02/04 FC-EPF-12 R3 issued 02/14/02 FC-EPF-12 R4 issued 03/31/04 FC-EPF-13 RO issued 01/17/91 FC-EPF-13 Ri issued 03/31/04 FC-EPF-15 R3 issued 07/11/97a FC-EPF-15 R4 issued 03/31/04 FC-EPF-17 R3 issued 11/06/99 FC-EPF-17 R4 issued 04/06/04 FC-EPF-27 R3 issued 11/07/00 FC-EPF-27 R4 issued 04/02/04 FC-EPF-29 RI issued 12/30/93 FC-EPF-29 R2 issued 03/31/04 FC-EPF-31 R2 issued 03/14/02 FC-EPF-31 R3 issued 03/31/04 FC-EPF-32 RO issued 06/10/93 FC-EPF-32 RI issued 03/31/04 FC-EPF-34 RO issued 06/23/93 FC-EPF-34 RI issued 03/31/04 FC-EPF-36 R4 issued 12/16/03 FC-EPF-36 R5 issued 03/31/04 FC-EPF-37 RO issued 07/11/95 FC-EPF-37 RI issued 03/31/04 FC-EPF-38 R6 issued 12/05/00 FC-EPF-38 R7 issued 03/31/04 FC-EPF-41 RO issued 09/30/98 FC-EPF-41 RI issued 03/31/04 FC-EPF-43 RO issued 11/29/01 FC-EPF-43 RI issued 04/06/04 RERP Index page 1 of 1 issued 01/06/04 RERP Index page 1 of 1 issued 04/06/04 RERP-Section L RI 1 issued 01/27/00 RERP-Section L Ri 1 issued 01/27/00 EPIP Index pages 1 and 2 issued 03/11/04 EPIP Index pages 1 and 2 issued 04/02/04 EPIP-EOF-6 R32 issued 01/23/02 EPIP-EOF-6 R33 issued 04/02/04 EPIP-RR-25 R21 issued 05/15/03 EPIP-RR-25 R22 issued 04/02/04 EPIP-RR-72 R13 issued 07/09/02 EPIP-RR-72 R14 issued 04/02/04 Page I of 2

Summary of Changes:

FC-EPF 1,2,8,12,13,15,17,27,29,31,32,34,36,37,38,41,43 were all revised due to being converted toe WP8. RERP Section L was revised due to being converted to WP* with Documentable Error incorporated. EPIP-EOF-6 was revised to add note telling when to use fax and to clarify instructions on how to use imminent release. EPIP-RR-25 was revised to add note to clarify when HPN is used, to delete sign-off/time on steps that are performed multiple times. EPIP-RR-72 was revised to correct Step 3 of Attachment 6.1 to include directing the field teams to synchronize their w tches time.

1?-(91 Supervisor - Emergency Planning I hereby acknowledge receipt of the above documents/informatlon and have Included them In my assigned manuals.

Signature: Date:_

Please sign above and return by to:05131104 Beth Nagel Fort Calhoun Station, FC-2-1 Omaha Public Power District 444 South 1 6th Street Mall Omaha, NE 68102-2247 NOTE: If the document(s)/information contained in this transmittal is no longer requested or needed by the recipient, or has been transferred to another individuals, please fill out the information below.

El Document(s)/Information No Longer Requested/Needed

[ Document(s)/Information Transferred to:

Name: Mailing Address:

Page 2 of 2

Fort Calhoun Station Emergency Planning Forms Index Page 1 of 2 FC-EPF Document Document Title Revision/Date FC-EPF-1 Alert Notification System Accidental Activation Report Form R8 03-31-04 FC-EPF-2 Offsite Monitoring Log R4 04-02 FC-EPF-3 Administration of Potassium Iodide Tablets R1 11-07-00 FC-EPF-4 NCR Radiological Emergency Team Briefing Checklist R3 07-29-03 FC-EPF-5 Emergency Worker Extension R5 02-14-03 FC-EPF-6 Estimated Exposure Worksheet R4 11-07-00 FC-EPF-7 Estimated Exposure Log R2 04-01-98 FC-EPF-8 Sample Worksheet R7 04-02-04 FC-EPF-9 OSC 24-Hour Staffing Schedule R14 01-16-03 FC-EPF-10 CR/TSC 24-Hour Staffing Schedule R16 01-16-03 FC-EPF-1 I- EOF 24-Hour Staffing Schedule R12 01-16-03 FC-EPF-12 MRC 24 Hour Staffing Schedule R4 03-31-04 FC-EPF-1 3 Emergency Response Organization Log Sheet R1 03-31-04 FC-EPF-14 Emergency Response Organization Assignment Form R13 01-29-04 FC-EPF-1 5 Drill Exercise Comment Form R4 03-31-04 FC-EPF-17 Pager Response Follow Up Questionnaire R4 04-06-04 FC-EPF-19 Process and Area Monitor Locations R7 04-22-03 FC-EPF-20 Site Boundary/Owner Control Area R2 06-03-03 FC-EPF-21 Fort Calhoun Station Sector Map R2 05-15-97 FC-EPF-27 Onsite/Offsite Dose Comparison Data Record (Using Eagle R4 04-02-04 Program)

FC-EPF-29 Estimation of Unmonitored Release Rates R2 03-31-04 FC-EPF-31 / Stability Class Chart R3 03-31-04 FC-EPF-32 Area Monitor Trending R1 03-31-04 April 6, 2004 8:44 AM

Fort Calhoun Station Emergency Planning Forms Index Page 2 of 2 FC-EPF Document Document Title Revision/Date FC-EPF-33* Emergency Response Facility Computer System (ERFCS) RI 07-02-96 FC-EPF-33A ERFCS Function Key Mapping RO 10-08-02 FC-EPF-34 MRC Director Checklist RI 03-31-04 FC-EPF-35: Iowa EOC Route Map (double-sided) RO 06-21-94 FC-EPF-36 Briefing Guidelines R5 03-31-04 FC-EPF-37 Operations Liaison Out of Service Equipment List RI 03-31-04 FC-EPF-38 Blair Industrial Park CO-OP R7 03-31-04 FC-EPF-41 Emergency Planning Simulator Critique RI 03-31-04 FC-EPF-42 Emergency Action Levels Ri 05-02-02 FC-EPF-43 Update Report to Offsite Authorities RI 04-06-04 April 6, 2004 8:44 AM

Distribution Authorized This procedure does not contain any proprietary information, or such information has been censored. This Issue may be released to the public document room. Proprietary Information includes personnel names, company telephone numbers, and any Information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-1 EMERGENCY PLAN FORM R8 ALERT NOTIFICATION SYSTEM ACCIDENTAL ACTIVATION REPORT FORM

1. Date: Initial Contact Time:

OPPD Person Taking Information:

2. Person Reporting Siren Sounding:

3. Organization or Address of Individual:

4. Siren Location:

5. Siren Number(s) (if known):

6. Description of Problem:

7. Emergency Planning Contact Person Notified

[ l N/A" or Name: Time:

8. KFAB Notified Name: Time:

9. Electric Operations Dispatcher Notified

[ I N/A" or Name: Time:

10. Applicable County Sheriff Notified

[ ] "N/A' or Name: Time:

11. NRC Resident Inspectors Office Notified Name: or

[I message left on phonemail/answering machine l Time:

12. NRC Operations Center Notified EN: Time:

Name:

Record Condition Report Number (CR No.):

And Route This Form To:

Supervisor, Emergency Planning, FC-2-1 (SO-R-1 5)

Distribution Authorized This procedure does not contain any proprietary information, or such information has been censored. This issue may be released to the public document room. Proprietary information includes personnel names, company telephone numbers, and any information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-2 EMERGENCY PLAN FORM R4 OFFSITE MONITORING LOG TEAM COLOR (circle one): RED BLUE TEAM MEMBERS TIMEIDOSIMETER READING (mrem)

INSTRUMEN'

r SERIAL NUMBERS TYPE Cal Due Seral No. TYPE Cal Due Seral No.

PLUME SEARCH DATA Time Location Dose Rate . Time Location Dose Rate Time Location Dose Rate (mrem/hour) (mrem/hour) (mrem/hour) 4 4. 41* 4. 4 41 4. 4.

4 4. II. 4. 4 41 4. 4.

.4 1. ii. 4. 4 AL 4. 4.

9 1 II 4. 9 E 4. I A & LI. £ .1 AL 4. 4.

SURVEY/SAMPLE DATA Beta-Gamma (open) Gamma (closed) Sample Act. (pCVcc) Smears (mremfhr) (mrem/hr)

Time Sample Location Waist Ground Waist Ground 1131 Gross dpm/100 Level Level Level Level Part. cm2

- -m-et- -

Comments:

Distribution Authorized This procedure does not contain any proprietary information, or such information has been censored. This issue may be released to the public document room. Proprietary information Includes personnel names, company telephone numbers, and any information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-8 EMERGENCY PLAN FORM PAGE 1 OF 2 R7 SAMPLE WORKSHEET Sample #: _ _ Time: Location: Team ORed OBIuEII

1. Counting Samples Using the ASP-2E with SPA-9 Probe I A. Iodine Activity: Wrap cartridge in plastic. Place cartridge in shielded holder, collected side up.

sp/ cpm bkg cpm net cpm x(EFF- 1-131) 1.59E - 11

( ft3 ) = activity (uCi/cc)

NOTE: If background is *500 cpm, the MDA is <1 .OE-08 uCi/cc or calculate MDA as follows: (ARQ use graph)

MDA = MDCR X 4.5E- 7 EFF(I-131) X Vol (ft 3 ) X 28317 MDCR = - + 3.29-+

t9 tg tb tg = sample count time (min) tb = background count time (min)

Rb = background count rate (cpm)

MDA uCi/cc

2. Counting Samples Using the Frisker A. Smear Activity: Use 100cm2 smear. Use GM pancake probe. Use only slow response mode.

- = X 10 = dpm/100cm2 spl cpm bkg cpm net cpm E.F. activity B. Particulate Activity: Use GM pancake probe. Use only slow response mode.

- X 1.59E-10 -

spl cpm bkg cpm ncpm ( ft3 ) activity NOTE: If sample counts are less than or equal to background counts, report results as "background".

(EPIP-EOF-3)

m mm K O m D U

m 0

-U

'1 1-131 MDA vs Background CPM

-<0

-D 2 2::-V - -: r ZO z0 Q--

r: z0 O

1.P(F-08' I . < E ¢Assuirning:

4* ;1 131 Ffficioncy 4 ft3 salIJip!e v04*nIC o1 ':ir)collilt times 1.'4flE -0 8i' i..... ....... ......

. 0:; ; i:-.;

.......... .; ..- :..;;:... ... . ..;.t.:.:...

5.

70, / Fj i ,5" X, :0 t ' S170;(

ASP= ISPA 9 Akq cpm M-n m 0) mo 00

~m n

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FORT CALHOUN STATION FC-EPF-1 2 EMERGENCY PLANNING FORM R4 MRC 24-HOUR STAFFING SCHEDULE Date: 24 HOUR SCHEDULE Time: Shift 1 Shift 2 Optional Shift Times:

CHECK WHEN NOTIFIED Corporate Spokesperson(2279)

Media Release Center Manager(2250)

MRC Clerical Supervisor(2252)

MRC Information Specialist(2257/2258)

MRC Technical Liaison(2255)

Pub Infor & Rumor Control Supervisor(2280/2281)

Public Information Specialist(2283)

Public Information Specialist(2284)

Public Information Specialist(2285)

Public Information Specialist(2286) .

Public Information Specialist(2287)

Public Information Specialist(2288)

Public Information Specialist(2289)

Public Information Specialist(2290)

Public Information Specialist(2291)

Public Information Specialist(2292)

Others:

NOTE: The expectation is to have a 24-hour schedule developed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AFTER the center is declared OPERATIONAL for the 15' shift and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for the 2nd shift.

Approved Signature: Date/Time:

Distribution Authorized This procedure does not contain any proprietary Information, or such information has been censored. This Issue may be released to the public document room. Proprietary information Includes personnel names, company telephone numbers, and any Information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-1 3 EMERGENCY PLAN FORM Rl EMERGENCY RESPONSE ORGANIZATION LOG SHEET Name: I Position:

Date: Page of Time Log Entries

+

4 4

4 SIGNATURE:

(SIGN LOG SHEET WHEN RELIEVED AND UPON EMERGENCY TERMINATION)

Distribution Authorized This procedure does not contain any proprietary information, or such information has been censored. This issue may be released to the public document room. Proprietary information includes personnel names, company telephone numbers, and any information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-15 EMERGENCY PLAN FORM R4 PAGE 1 OF 2 DRILL/EXERCISE COMMENT FORM Name: lMail Stop:l Location: lEmergency Position:

Date:

Equipment Comments Requiring Corrective Action:

(1)

(2)

(3)

Procedure/Training Comments Requiring Corrective Action:

(1)

(2)

(3)

Facility Comments Requiring Corrective Action:

(1)

(2)

(3)

General Comments Not Requiring Corrective Action:

(1)

(2)

(3)

(Do Not Write On The Back Of This Form)

See Back For Comment Resolution Provided By The Emergency Planning Department

FORT CALHOUN STATION FC-EPF-1 5 EMERGENCY PLAN FORM R4 PAGE 2 OF 2 DRILL/EXERCISE COMMENT FORM Equipment Comments Corrective Action:

(1)

(2)

(3)

Procedure/Training Comments Corrective Action:

(1)

(2)

(3)

Facility Comments Corrective Action:

(1)

(2)

(3)

THANKS FOR YOUR PARTICIPATION!!!

Comment Resolutions Completed By:

(EP Department)

Comment Resolutions Reviewed By:

(Supervisor - Emergency Planning)

Distribution Authorized This procedure does not contain any proprietary information, or such information has been censored. This Issue may be released to the public document room. Proprietary information includes personnel names, company telephone numbers, and any Information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-17 EMERGENCY PLAN FORM R4 PAGER RESPONSE FOLLOW UP QUESTIONNAIRE Date:

From: Supervisor - Emergency Planning To:

Subject:

Notification Drill Pager Response Follow Up A pager Notification Drill was conducted at on 20 Test records indicate you did not respond to the pager test.

Please put an 'X" in the appropriate box at the bottom of this sheet.

If you did not receive the page, please check your pager for operability by paging yourself and then check the appropriate box below.

The requested information is vital in order to ensure the continued operability of the Emergency Pager System.

Please complete by: and return this form to:

Emergency Planning FC-2-1 C. F. Simmons Supervisor - Emergency Planning

[ ] Received the 5*5*5*5*5*5 page and could have responded to a real emergency.

[ ] Received the 5*5*5*5*5*5 page but, due to circumstances, would NOT have been able to respond to a real emergency (examples: watching children, fitness for duty, vacation, etc.).

[ ] Pager was turned off due to vacation, sickness, etc.

[ ] Did not receive 5*5*5*5*5*5 page. I have checked my pager for operability.

[ ] Pager is operable.

[ ] Pager is not operable. I have contacted Emergency Planning at extension 7307 to resolve the pager problem.

[ ] Other:

Distribution Authorized This procedure does not contain any proprietary information, or such information has been censored. This issue may be released to the public document room. Proprietary information includes personnel names, company telephone numbers, and any Information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-27 EMERGENCY PLAN FORM R4 ONSITE/OFFSITE DOSE COMPARISON DATA RECORD (USING EAGLE PROGRAM)

Instrument Reading Iodine Air Particulate Air Date/Time Location Distance (Rem/Hr) Concentration Concentration EAGLE (pCVcc) (pCi/cc)

EAGLE Actual _ _ _T l ~Actuall EAGLE l _ _ T l l ~Actual Actual l] TT_

~~EAGLET EAGLE TT_

Actual __r__

EAGLE l _ _

___ __ __ _Actual _ _TI EAGLE T TI Actual TI EAGLE _ _ _ _ _ _ _ _ _ _

l l Actual Actual l EPI P-RR-25

Distribution Authorized This procedure does not contain any proprietary Information, or such information has been censored. This issue may be released to the public document room. Proprietary information includes personnel names, company telephone numbers, and any information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-29 EMERGENCY PLAN FORM R2 SECTION G ESTIMATION OF UNMONITORED RELEASE

1. Date/Time:

2. Downwind Distance:

3. Wind From:

4. Delta T (AT): OC/1 0Om

5. Wind Speed: mph

6. Diffusion Factor:

7. Dose Rate (Field Team): Rem/hr

8. Iodine Air Concentration (Field Team): ICVcc

9. Particulate Air Concentration (Field Team): jLCVcc

10. Noble Gas Release Rate (ONG) from Field Team Dose Rate Data:

(2.5E-3) ( mph) ( R/hr) ( )= Ci/sec Noble Gas STEP 5 STEP 7 STEP 6 RESULT 10

11. Iodine Release Rate (Q.):

a. From Field Team Dose Rate Data:

( Cisec) (.02)= Ci/sec Iodine RESULT 10

b. From Field Team Air Sample Data:

( mph) ( tCvcc) ( )= C/sec Iodine STEP 5 STEP 8 STEP 6

12. Particulate Release Rate (0p):

mph) ( PCVcc) + ( )= Cisec Particulate STEP 5 STEP 9 STEP 6 Assessment Completed By: Time:

EIP-EOF-6

Distribution Authorized This procedure does not contain any proprietary information, or such Information has been censored. This issue may be released to the public document room. Proprietary information includes personnel names, company telephone numbers, and any Information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-31 EMERGENCY PLAN FORM R3 AT/aO STABILITY CLASS CHART ao AT Standard Deviation of the Temperature Change With Height Pasquill Stability Class Horizontal Wind Direction

("C/100 m)

(Degrees)

A

-1.9 aO g22.5 Extremely Unstable B

> -1.9 to s-1.7 22.5 >d017.5 Moderately Unstable C

> -1.7 to s-1.5 17.5 >aOs12.5 Slightly Unstable D

> -1.5 to s-0.5 12.5 >ae s7.5 Neutral E

> -0.5 to s1.5 7.5 >cO s3.8 Slightly Stable F

1.5 to :54.0 3.6 >a09 .2.1 Moderately Stable G

> 4.0 2.1 >aO Extremely Stable Delta Temperature (AT) is the temperature difference between 10 and 60 meters multiplied by two, in units of centigrade. The ERFCS displays AT as 'C/100 m.

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FORT CAL JN STATION -C-EPF-32 EMERGENI

PLAN FORM RI AREA MONITOR TRENDING I ITjI IniiniI =T -- l ll =T I! -*

c RM070 _ _ _ _ _ _ _ _ _

o RM071 T RM072 =

A RM073 N RM074A _ _ _ _ ___ ___

M RM075 E

N RMo91 A =IJ1 T RM091B C RM076 R RM077 R

R RM078 4 RM079 o RM080 0

R RM081 ! ! !-!!!1 R RM082 26 RM084 R RM085 0

o RM086 RM087 69 RM088 CR RM089 __+/-Iae Datp

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FORT CALHOUN STATION FC-EPF-34 EMERGENCY PROCEDURE FORM R1 MRC DIRECTOR CHECKLIST lBRIEFING #: lTIME:

Check item Agency/ person BMRC DIRECTOR:

when completed performing IR IETR

'ITEMS REQUIRING DISCUSSION BASED ON ACTIVATION LEVEL OF EMERGENCY Pre Briefing Checklist.

Copies of news releases are available.

Copies of Emergency Broadcast Messages are available.

Media Kits are available Staff members are available to handle inquires from the media.

Participants have name placeards stating name and agency on desk.

Log maintained of information provided to the media.

Pre briefing meeting held with all participants.

Required Topics of Discussion During Press Briefing.

Introduce self and members of panel to media.

Description of current emergency conditions at FCS, with reference to both the potential for or actual release of radioactivity and current emergency classification level (ECL).

Rumor control telephone numbers.

Information to address false and misleading rumors.

Use of public information brochures.

How to maximize protection when sheltering.

Instructions to transients without shelter.

What to leave behind and what to take along when evacuating.

Evacuation routes.

Location of reception centers / congregate care facilities.

Information and instructions to parents, concerning protective actions for students.

Information for transportation-dependant individuals.

'Information for special populations.

Information and instructions on protective actions for ingestion.

Information on relocation, re-entry or retum.

Distribution Authorized This procedure does not contain any proprietary information, or such information has been censored. This Issue may be released to the public document room. Proprietary Information Includes personnel names, company telephone numbers, and any information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-36 EMERGENCY PLAN FORM R5 BRIEFING GUIDELINES Approximately Ten (10) Minutes Prior To Conducting The Briefing Make An Announcement Over The Paging System Stating When And Where The Briefing Will Take Place - If Input From Others Will Be Requested, Let Them Know So They Can Prepare.

Stand-Up!! Get Everyone's Attention!!!!

If not an actual emergency: "This Is a Drill - This Is a Drill"

1. State Your Name and Position:

2. Current Emergency Level: NOUE ALERT SAE GE 2.1 Any indications which could lead to a higher classification?

2.2 Any indications to allow a deescalation or termination?

3. Command and Control is currently in the: CR TSC EOF Who: Name:

Title:

4. Status of the Plant and Safety Systems

5. Status of Radiological Concems/Release Pathway (if applicable)

6. Current Protective Actions 6.1 OPPD's PARs 6.2 State of Nebraska implementation (EOF only) 6.3 State of Iowa implementation (EOF only)

7. Current Response/Recovery Activities 7.1 OPPD 7.2 States (EOF only) 7.3 Federal Agencies (EOF only)

8. Current Priorities of OPPD ERO Personnel

9. Other Information, as needed

10. Remind personnel to use their procedures and complete their logs.

11. Remind personnel to use the Human Performance tools:

Effective Communication (2 and 3-way)

Procedural Compliance

Pre-Job Briefings

Questioning Attitude

Self and Peer Checking

200% Accountability

12. State Time of Next Planned Briefing

13. Ask for Questions or Comments If not an actual emergency: "THIS IS A DRILL - THIS IS A DRILL"

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FORT CALHOUN STATION FC-EPF-37 EMERGENCY PLANNING FORM R1 OPERATIONS LIAISON OUT OF SERVICE EQUIPMENT LIST Please Provide To Status Board Keeper And Ensure All Other Facility Operations Liaisons Are Informed Of The Update.

[ I ADD - [ ] REVISE [ ] REMOVE Item/Description:

Requested By (Initials):

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FORT CALHOUN STATION FC-EPF-38 EMERGENCY PLAN R7 BLAIR INDUSTRIAL PARK CO-OP EVENT NOTIFICATION FORM

1. Take roll call of responding members ( Blair Water/Sewer l [ ] Cargill [ ] Kelly Ryan (V by name of those responding) [ MACC [ Terra Nitrogen [] Blair AG, LLC Washington County Dispatch

2. Emergency Classification Code [ ] NOUE [] Alert [ ] Site Area [ General (Blue) (Green) (Yellow) (Red)

3. Classification: Date: Time:

Reported by (If other than OPPD):

4. Person making Report:

Title:

Call back #: Time:

Authorized By. lTitle: Time:

5. Incident facts Time of Event: Estimated Duration (hrs):

6. Event type (V all applicable) [] Explosion [ Fire [ Gas Release

[] Radiological [ River Release [ ] Spill

]Other; Please list:

Substance Involved (proper spelling?): l Volume Units DOT ID #: DOT Guide #:

Other Identifying characteristics [ ] Flammable Toxic T[ [ HazMat [ Other Precipitation?

7. Weather Direction (fromo): Wind Speed: MPH [ ] Yes [ ] No

8. Comments (At Site Area or General Emergency recommend that members tune to KFAB 1110 AM for EAS Message(s))

9. Was an attempt made to contact members that didn't answer Co-Op line? [ ] Yes [] No List those not contacted:

Distribution Authorized This procedure does not contain any proprietary Information, or such information has been censored. This issue may be released to the public document room. Proprietary information Includes personnel names, company telephone numbers, and any information, which could Impede emergency response.

FORT CALHOUN STATION FC-EPF-41 EMERGENCY PLANNING FORM R1 EMERGENCY PLANNING SIMULATOR CRITIQUE Date:

Participants:

Yes No Yes No Shift Manager Turbine Building Operator Senior Reactor Operator Water Plant Operator Licensed Operator Communicator Licensed Operator* Shift Chemist = =

Auxiliary Building Operator Shift HP Other: Other:

Objectives: Met Yes No Classifications are correctly made and are timely.

FC-1 188's are filled out correctly, approved and sent out promptly.

All notifications are made in the required time per EPIP-OSC-2.

Habitability checks are done correctly and verified during the drill.

Dose assessment performed correctly with results given to Shift Manager.

Any strengths or problems noted:

Attach a copy of the attendance sheet

Distribution Authorized This procedure does not contain any proprietary Information, or such information has been censored. This issue may be released to the public document room. Proprietary Information includes personnel names, company telephone numbers, and any information, which could impede emergency response.

FORT CALHOUN STATION FC-EPF-43 EMERGENCY PLAN FORM R1 UPDATE REPORT TO OFFSITE AUTHORITIES Use this form only when the EAGLE dose assessment program is unable to print.

This isa: [ ] Emergency [ ] DrilVExercise Contact/Fax Time:

Call Back #: [1 ] CHP Commercial (if CHP is unavailable) (402)

Fax to: [ ] Iowa [ ] Nebraska [ TSC [ ] EOF [ ] Control Room (Simulator if Drill) [ ] MRC Plume Calculation Time: Plume #: Dose Assessment Specialist:

Release Point [ ] Auxiliary Building Stack Flow

[ ] Condenser/Main Steam Flow

[ ] Containment Flow

[ ] Rad Waste Building Stack Flow Estimated Release Duration: Hours Quantity and Rate curies noble gas at curies/second curies iodine at curies/second curies particulate at curies/second Meteorological Atmospheric Mixing Condition:

Wind Speed: MPH Wind Direction: Degrees Delta T: Degrees Ambient Temperature: Deg. C Stability Class: Mixing Height: Meters Affected Sectors:

Projected Dose Rates (REMIHr) Projected Integrated Dose (REM)

TEDE CDE TEDE CDE Site Boundary 2 Miles 5 Miles 10 Miles All calculations done using Straight Une Gaussian Model. Doses/Dose Rates <1 E-4 are displayed as zero.

Reviewed by:

Fort Calhoun Station Radiological Emergency Response Plan Index Page 1 of 1 RERP Document Document Title Revision/Date RERP Definitions and Abbreviations R17 09-03-03 RERP-SECTION A Assignment of Organizational Responsibility (Organizational Ri 1 02-27-97c Control)

RERP-SECTION B Organizational Control of Emergencies R25 08-24-00 RERP-SECTION C Emergency Response Support and Resources R9 09-30-98a RERP-SECTION D Emergency Classification System RI0 09-17-02 RERP-SECTION E Notification Methods and Procedures R23 08-24-OOa RERP-SECTION F Emergency Communications RI 5 08-24-OOa RERP-SECTION G Public Education and Information RI 1 08-08-02 RERP-SECTION H Emergency Facilities and Equipment R30 08-08-02 RERP-SECTION I Accident Assessment R12 03-20-03 RERP-SECTION J Protective Response R18 05-28-03 RERP-SECTION K Radiological Exposure Control R10 04-03-03 RERP-SECTION L Medical and Public Health Support R11 01-27-OOb RERP-SECTION M Recovery and Reentry Planning and Post Accident Operations R14 03-11-97b RERP-SECTION N Exercises and Drills R13 12-07-01 RERP-SECTION 0 Radiological Emergency Response Training R13 09-23-97b RERP-SECTION P Responsibility for the Planning Effort: Development, Periodic RIO 10-23-97a Review and Distribution RERP-APPENDIX A Letters of Agreement R16 03-07-OOe RERP-APPENDIX B Supporting Emergency Plans R4 10-27-98 RERP-APPENDIX C NUREG/RERP/Implementing Procedure Cross Reference List R12 09-02-99c RERP-APPENDIX D OPPD Resolution #4731, Radiological Emergency Response R2 09-30-98a Plan Authority April 6, 2004 9:35 AM

WP10 Distribution Authorized This procedure does not contain any proprietary information, or such information has been censored. This issue may be released to the public document room. Proprietary Information Fort Calhoun Station includes personnel names, Unit No. 1 company telephone numbers, and any information, which could impede emergency response.

RERP-SECTION L RADIOLOGICAL EMERGENCY RESPONSE PLAN

Title:

MEDICAL AND PUBLIC HEALTH SUPPORT FC-68 Number: N/A Reason for Change: Converted from WP6.1 to WP8 with Documentable Error incorporated.

Initiator: Mark Reller Preparer: Sheila Rasmussen Correction (a): Page 5 (issue all pages) (01-06-04)

Correction (b): Page 4 (04-06-04)

ISSUED: 01-27-00 3:00 pm R11

FORT CALHOUN STATION RERP-SECTION L RADIOLOGICAL EMERGENCY RESPONSE PLAN PAGE 1 OF 5 MEDICAL AND PUBLIC HEALTH SUPPORT

1. ONSITE FIRST AID There are generally four types of response considered at the Fort Calhoun Station:

1) Minor injury, no contamination

2) Minor injury, contaminated

3) Major injury (requiring offsite treatment), no contamination

4) Major injury, contaminated The order of medical treatment will be:

1) Care of severe physical injuries

2) Decontamination of personnel

3) First aid to other injuries

4) Monitor for internal contamination

5) Definitive treatment and subsequent therapy as required All injuries at the station must be immediately reported to the Shift Manager, who will initiate response according to the Fort Calhoun Station Safety Manual.

When personnel are severely injured and contaminated, first aid shall take precedence over decontamination. In cases where internal exposure is suspected, a bioassay program may be performed as directed by the Radiation Protection Manual.

1.1 First Aid Facilities A First Aid Room is located in the TSC. This room is equipped with an examination table, examination chair, illuminating magnifier and a supply of bandages, splints, etc., to provide emergency first aid to injured personnel.

Other equipment located throughout the plant include first aid kits, Emergency Medical Technician (EMT) kits, personnel carriers, a wheelchair, and contaminated/injured personnel response kit. The Industrial Safety Coordinator inspects and maintains this equipment.

1.2 Medical Response 1.2.1 Minor Injury, No Contamination The Shift Manager or other evaluators will determine the extent of medical response required. This could include:

A. On the spot treatment by the individual or first aid qualified responders.

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FORT CALHOUN STATION RERP-SECTION L RADIOLOGICAL EMERGENCY RESPONSE PLAN -PAGE 2 OF 5 1.2.1 B. On the spot treatment by EMT qualified personnel.

C. Movement of the injured party to the first aid room by medical responders for access to additional equipment.

D. Other response determined necessary by responding personnel.

1.2.2 Minor Injury, Contaminated Personnel that are injured and are potentially contaminated will be treated as explained above, and will also be monitored for contamination by Radiation Protection personnel. Monitoring and decontamination will be performed in accordance with Radiation Protection procedures.

1.2.3 Major Injury, No Contamination Medical responders will be dispatched to the scene to perform first aid as required and prepare the victim for transport. The Shift Manager or designee will notify offsite authorities to provide victim transport to an available medical facility. Both air and ground transportation are available.

1.2.4 Major Injury, Contaminated Personnel that are severely injured and are potentially contaminated will be treated as explained above, and will also be monitored for contamination by Radiation Protection personnel. If feasible, monitoring and decontamination will be performed in accordance with Radiation Protection Procedures. If decontamination is successful, the victim may be transported to any available medical facility for treatment.

If decontamination is not successful or not feasible, the victim will be transported to the Nebraska Health System (NHS) University Hospital Regional Radiation Health Center, unless the on-scene medical responders or transportation personnel deem it medically necessary to proceed to a closer facility. If another facility other than NHS is used, additional Radiation Protection personnel should be sent to the facility to assist in monitoring, decontamination and clean up.

2. MEDICAL TRANSPORTATION 2.1 Blair Fire Department and Rescue Squad The Blair Fire Department and Rescue Squad Station is located less than four (4) miles from the Fort Calhoun Station. The Rescue squad furnishes transportation for the injured and administers first aid enroute to the hospital.

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FORT CALHOUN STATION RERP-SECTION L RADIOLOGICAL EMERGENCY RESPONSE PLAN PAGE 3 OF 5 2.2 Fort Calhoun Fire and Rescue Squad The Fort Calhoun Fire and Rescue Squad headquarters is located approximately 3-1/2 miles from the Fort Calhoun Station. This rescue squad serves as backup to the Blair Fire Department and Rescue Squad.

2.3 Missouri Valley Fire and Rescue Squad The Missouri Valley Fire and Rescue Squad is located approximately fifteen (15) miles from the plant.

2.4 Additional support is available to both the Biair Fire Department and Rescue Squad and the Fort Calhoun Fire and Rescue Squad by request through the Tri-Mutual Aid Association (Douglas, Sarpy, and Washington Counties).

2.5 Other Modes of Transportation If necessary, there are other modes of transportation for delivering injured personnel to appropriate medical facilities.

2.5.1 Medical Ambulance helicopter.

2.5.2 Onsite company vehicles.

2.5.3 Private autos of company personnel.

3. OFFSITE MEDICAL SUPPORT 3.1 Non-Contaminated Personnel The nearest medical facility is the Blair Memorial Community Hospital which is located five (5) miles from the plant. A physician is readily available as a general medical consultant. Other facilities may be used as determined necessary by medical response personnel.

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FORT CALHOUN STATION RERP-SECTION L RADIOLOGICAL EMERGENCY RESPONSE PLAN PAGE 4 OF 5 3.2 Contaminated Personnel Omaha Public Power District maintains an agreement with the NHS, University Hospital Regional Radiation Health Center to supply 24-hour treatment for all injuries involving contamination and/or personnel radiation exposure. The Regional Radiation Health Center is located approximately 25 miles from the plant in Omaha, Nebraska.

The facility is part of the NHS complex, and was established specifically for the treatment of injuries occurring from nuclear and radiation related incidents. A entrance is available for the ingress and egress of contaminated victims to a special assessment and decontamination facility. This entrance is from Forty-Second Street lI and Emile Street and is depicted in Figure L-1. Patients can also be transported to the facility via medical ambulance helicopters.

The NHS University Hospital Regional Radiation Health Center staff administers medical, decontamination, internal bioassay, and other nuclear medicine capabilities.

The staff maintains an appropriate Standard Operating Procedures Manual" which describes their responsibilities and roles. If additional hospital beds should be required during a major incident, the hospital maintains a mutual agreement with several other Omaha area hospitals to assist with decontaminated patients.

Due to the large, highly qualified-staff, the distance from the plant, the specialized capabilities, and the overall size of the NHS complex, the Fort Calhoun Station was granted an exemption from requiring a backup medical facility by the Federal Emergency Management Agency.

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FORT CALHOUN STATION RERP-SECTION L RADIOLOGICAL EMERGENCY RESPONSE PLAN PAGE 5 OF 5 Figure L-1 Entrance to Treatment Area NHS, University Hospital Regional Radiation Health Center II 1I I Lit&

DODGE STREET LEAVENWORTH ST I -

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Fort Calhoun Station Emergency Plan Implementing Procedure Index Page 1 of 2 EPIP Document Document Title RevisionlDate EPIP-OSC-1 Emergency Classification R35 05-02-02 EPIP-OSC-2 Command and Control Position Actions/Notifications R42 05-28-03a EPIP-OSC-9 Emergency Team Briefings R7 12-09-99

,EPIP-OSC-15 Communicator Actions R22 10-24-OOa EPIP-OSC-21 Activation of the Operations Support Center R13 03-02-04 EPIP-TSC-1 Activation of the Technical Support Center R25 03-02-04 EPIP-TSC-2 Catastrophic Flooding Preparations (RO 03-22-95) DELETED R5 11-13-03 (05-09-95) REINSTATED EPIP-TSC-8 Core Damage Assessment R15 10-28-03 EPIP-EOF-1 Activation of the Emergency Operations Facility R13 10-29-02 EPIP-EOF-3 Offsite Monitoring R19 07-29-03 EPIP-EOF-6 Dose Assessment R33 04-02-04 EPIP-EOF-7 Protective Action Guidelines R15 03-11-04 EPIP-EOF-10 Warehouse Personnel Decontamination Station Operation R10 01-13-OOa EPIP-EOF-11 Dosimetry Records, Exposure Extensions and Habitability R20 07-02-03 EPIP-EOF-19 Recovery Actions R8 07-17-03 EPIP-EOF-21 Potassium Iodide Issuance R4 11-07-00 EPIP-EOF-23 Emergency Response Message System R5 10-12-99 EPIP-EOF-24 EOF Backup Alert Notification System Activation R3 09-09-99 EPIP-RR-1 1 Technical Support Center Director Actions R14 02-29-OOa EPIP-RR-1 3 Reactor Safety Coordinator Actions R14 12-09-99a EPIP-RR-17 TSC Security Coordinator Actions R15 12-10-02a EPIP-RR-17A TSC Administrative Logistics Coordinator Actions R20 11-07-02a April 2, 2004 12:41 PM

Fort Calhoun Station Emergency Plan Implementing Procedure Index Page 2 of 2 EPIP Document Document Title Revision/Date OperationsLiaisonActions R6 04-15-03a EPIP-RR-21 Operations Support Center Director Actions R13 08-28-03 EPIP-RR-21A Maintenance Coordinator Actions R4 11-30-99a EPIP-RR-22 Protective Measures Coordinator/Manager Actions R23 09-09-03 EPIP-RR-22A Chemistry Coordinator Actions R6 12-07-01 EPIP-RR-25 EOF Dose Assessment Coordinator Actions R22 04-02-04 EPIP-RR-28 OSC Accountability and Dosimetry Technician Actions R8 09-25-01a EPIP-RR-29 EOF Administrative Logistics Manager Actions R20 11-07-02 EPIP-RR-39 Control Room Medical Responder Actions RO 03-27-01a EPIP-RR-63 EOF Dose Assessment Assistant Actions Rio 11-19-01 EPIP-RR-66 Communication Specialist Actions R8 08-31-99 EPIP-RR-72 Field Team Specialist Actions R14 04-02-04 EPIP-RR-87 Radiation Protection Coordinator Actions R9 08-28-03 EPIP-RR-90 EOFITSC CHP Communication Actions RO 10-24-00 April 2, 2004 8:44 AM

WP10 Distribution Authorized This procedure does not contain any proprietary Information, or such Information has been Fort Calhoun Station censored. This issue may be released to the public document Unit No. 1 room. Proprietary information includes personnel names, company telephone numbers, and any information, which could impede emergency response.

EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

DOSE ASSESSMENT FC-68 Number: EC 33610 Reason for Change: Revise for EAGLE 6.0 upgrade.

Requestor: M. Reller Preparer: M. Reller ISSUED: 04-02-04 3:00 pm R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 30 DOSE ASSESSMENT NON-SAFETY RELATED

1. PURPOSE 1.1 This procedure provides instructions for performing dose assessment for Ventilation Stack releases, Main Steam Line/Condenser Off-Gas releases, Containment leakage and Radwaste Building releases. It also provides instruction for estimating unmonitored release rates, and performing liquid release assessment.

2. REFERENCES/COMMITMENT DOCUMENTS 2.1 EPIP-EOF-7, Protective Action Guidelines 2.2 Ol-ERFCS-1, Operation of the Emergency Response Facilities Computer System 2.3 CH-SMP-PA-0005, Monitoring of Gaseous Effluent Releases Via the Auxiliary Building Ventilation Duct Pathway 2.4 TDB-IV.7, Process Monitor Setpoints 2.5 TDB-IV.8, Area Monitor Setpoints 2.6 User's Guide for EAGLE 6.00 2.7 EA-FC-03-002, Containment Area Monitor Response 2.8 EA-FC-03-003, Iodine to Noble Gas Particulate to Noble Gas Ratios for EAGLE 6.0 2.9 EA-FC-02-019, Secondary Side Source Term 2.10 EA-FC-02-020, Source Term Undamaged Core 2.11 EA-FC-02-030, Lateral Spread for EAGLE 6.0.0 2.12 EA-FC-02-031, Determination of Release Rate and Iodine/Noble Gas Ratios from Field Team Data 2.13 EA-FC-02-032, Imminent Projected Release from EAGLE 6.0.0 2.14 EA-FC-02-033, EAGLE 6.0.0 Source Term Damage Core 2.15 EA-FC-02-034, EAGLE 6.0.0 Methodology for Calculation of Ground Deposition and Ingestion Pathway R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 2 OF 30 2.16 EA-FC-02-035, Calculation of Release Mass Flow Rate from Main Steam 2.17 CHP-2002-21, Source Term for EAGLE 6.0.0 2.18 CHP-2003-01, Radiation Monitor Parameters for EAGLE 2.19 CHP-2003-04, Liquid Releases in EAGLE 6.0 2.20 EP-02-075, EAGLE 6.0.0 Receptor Locations 2.21 Commitments (other than Ongoing)

AR 10029, IER-89-24

AR 13302, IER-92-20

AR 17061, LIC-95-0049/LIC-95-0230 2.22 Protective Measure Basis Document, CHP-00-038, September 28, 2000

3. DEFINITIONS 3.1 DELTA T (AT) TEMPERATURE - the temperature difference between 10 and 110 meters, in units of centigrade. The value displayed on the ERFCS equates to a 100AT[(T ( 60m - T @ I Om) x 2].

3.2 DURATION OF RELEASE - the time in hours the release is expected to continue.

3.3 DOSE - the amount of ionizing radiation that results from an amount of energy being absorbed in the human body, in units of Rem.

3.4 DOSE RATE - Dose per unit time, in units of Rem/hour.

3.5 ERFCS - Emergency Response Facility Computer System.

3.6 IMMINENT RELEASE - An impending release of the radioactive gas in Containment.

3.7 CDE - Committed Dose Equivalent.

3.8 TEDE - Total Effective Dose Equivalent.

3.9 COMMAND AND CONTROL POSITION: The position that is currently in charge of the emergency response, either the Shift Supervisor, Control Room Coordinator, Site Director or Emergency Director.

3.10 RELEASE RATE (Q) - the emission rate of the effluent in units of Curies per second from the release point.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 3 OF 30

4. PREREQUISITES 4.1 A radioactive release is suspected, imminent, or known to be in progress.

5. PROCEDURE NOTE: If on-site meteorological data is not available, contact the National Weather Service (number in the Emergency Phone Book), and request wind speed and direction. For night time (sunset to sunrise) with no precipitation, use a AT of +2.0 and a stability class F. For all other conditions, use a AT of -1.0 and a stability class D.

5.1 To perform dose assessments in the Control Room, use Attachment 6.1.

5.2 To perform dose assessments in the TSC, use Attachment 6.2.

5.3 To perform dose assessments in the EOF, use Attachment 6.3.

5.4 When needed, perform dose assessments and updates to the states at least every 60 minutes. It is the goal of the Fort Calhoun Station to attempt to provide assessments and updates at 15 minute intervals. (AR 13302) 5.5 Retain all documentation (logs, assessments, etc.) generated or used during the emergency. At the termination, deliver all documentation to the TSC Administrative Logistics Coordinator in the TSC, or the EOF Administrative Logistics Manager in the EOF.

6. ATTACHMENTS 6.1 Dose Assessment in the Control Room 6.2 Dose Assessment in the TSC 6.3 Dose Assessment in the EOF 6.4 Computerized Dose Assessment 6.5 Unmonitored Release Assessments R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 4 OF 30 Attachment 6.1 - Dose Assessment In The Control Room Page 1 of 3

1. Using information from the Control Room as needed and Al-33A, B and C or ERFCS pages 197, 360 and 361 evaluate and determine the release pathways for dose assessment as follows:

NOTE: The sample Control Module for RM-052 must be in the VENT position (monitoring the Auxiliary Building Vent Stack) in order to be used for dose assessment.

NOTE: RM-0621063 are the preferred process monitors to be used for dose .ssessment on the Auxiliary Building Vent Stack. RM-062 is normally in-service and RM-063 is normally in Standby. When RM-062 count rate exceeds 5.0 E+06 cpm or if RM-063 exceeds 5.0 E-3 pC/cc; sample flow will automatically shift from RM-062 to RM-063 and the alarm "RM-063 AUX BLDG VENT STACK IN SERVICE" will annunciate on Al-33C. When RM-063 radiation level drops below 5.0 E-3 pC/cc, sample flow will shift to RM-062 and RM-063 will shift to Standby.

1.1 Evaluate the Auxiliary Building Vent Stack release pathway using RM-052, RM-062 and RM-063.

1.2 Evaluate the Condenser/Main Steam release pathway using RM-057, RM-064 and whether or not a primary to secondary leak has been confirmed.

1.2.1 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed, request that RM-064 be placed in service on the affected Main Steam Line.

1.2.2 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and if Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, request that Condenser Off-gas be aligned to the Auxiliary Building Vent Stack.

1.2.3 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, perform dose assessment with Condenser Off-gas as the release pathway, using a flow rate of 340 scfm.

1.2.4 If a primary to secondary leak is confirmed and RM-057 is not operable or is over ranged, and Condenser Off-gas is not aligned to the Auxiliary Building Vent Stack, this is an unmonitored release.

1.2.5 If there is a confirmed primary to secondary leak, and FW-10 is receiving steam from the affected Steam Generator, or the atmospheric Steam Dump Valve HCV-1040 is OPEN or a Steam Safety is lifting on the affected side, and RM-064 count rate is less than or equal to the background count rate as listed in TDB-IV.7, this is an unmonitored release.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 5 OF 30 Attachment 6.1 (continued) Page 2 of 3 1.3 Evaluate the Containment Leakage release pathway using Containment Area Monitors.

NOTE: If containment leakage is suspected to be greater than designed Containment leakage of 1.5 scfm, and the leakage is from the Containment to the stack or from the Containment to Controlled Areas of the Auxiliary Building to the Auxiliary Building Vent Stack, consideration may be given not to count the release twice if dose assessment will oe performed from the Auxiliary Building Vent Stack.

1.3.1 If Containment Area Monitors RM-070 through RM-075 are in High Alarm or RM-091A and B read 1.0 R/hr or higher, perform dose assessment using Containment leakage as a release pathway.

1.3.2 IF any area monitors indicate > 1000 times the background listed in TDB-IV.8, THEN inform the Command and Control position for classification information.

1.4 Evaluate the Radwaste Building Stack as a release pathway using RM-043 1.4.1 If RM-043 is in High Alarm, perform dose assessment using the Radiological Waste Building Vent Stack as a release pathway.

1.5 Evaluate the iiquid release pathways as follows:

1.5.1 If RM-055, Overboard Discharge Monitor is reading greater than tne High Alarm Setpoint as listed in TDB-IV.7 and the overboard discharge flow is not isolated, then a liquid release assessment must be performed.

1.5.2 If either RM-054A or RM-054B Steam Generator Blowdown Monitors are reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and blowdown flow is not isolated from the Steam Generator(s) with a primary to secondary leak, then a liquid release assessment must be performed.

1.6 Determine if there are any potentially unmonitored releases.

2. Perform dose assessment for monitored release pathways using Attachment 6.4 and for unmonitored release pathways per Attachment 6.5.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 6 OF 30 Attachment 6.1 (continued) Page 3 of 3

3. Review/Distribution NOTE: The information generated by EAGLE is for OPPD decision maker's information only. Actual PARs are determined by the Command and Control position. The PAR Worksheet should be one of the tools used for guidance in determining PARs.

3.1 If Command and Control is in the Control Room 3.1.1 Have the Command and Control position review the PAR Worksheet and the Update Report to Offsite Authorities.

NOTE: If a dose assessment results in a change in classification or a PAR change, ensure that the states are notified by the CR Communicator using an approved Emergency Notification form (FC-1 188) prior to faxing the Update Report to Offsite Authorities.

NOTE: If the Network is down or faxing is slow consider using the stand-alone fax machine.

3.1.2 Ifthe Command and Control position approves the assessment:

Click the Fax button at the bottom of the screen

Select the proper distribution list(s)

Click "OK" 3.2 If Command and Control is in the TSC:

3.2.1 Fax the unsigned PAR Information Worksheet and Update Report to State and County Authorities to the TSC.

3.2.2 Inform the TSC Protective Measures Coordinator of the transmittal.

3.2.3 Record transmittal time.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 7 OF 30 Attachment 6.2 - Dose Assessment In The Technical Support Center Page 1 of 3 NOTE: Dose assessment will only be performed in the TSC in the event that the EAGLE equipment in the Control Room is unavailable or inoperable. The TSC EAGLE equipment may also be used as a backup to the equipment located at the EOF.

1. Inform the Protective Measures Coordinator that you will be performing dose assessment in the TSC.

2. Using information from the Control Room as needed and Al-33A, B and C or ERFCS pages 197, 360 and 361 evaluate and determine the release pathways for dose assessment as follows:

NOTE: The sample Control Module for RM-052 must be in the VENT position (monitoring the Auxiliary Building Vent Stack) in order to be used for dose assessment.

NOTE: RM-062/063 are the preferred process monitors to be used for dose assessment on the Auxiliary Building Vent Stack. RM-062 is normally in-service and RM-063 is normally in Standby. When RM-062 count rate exceeds 5.0 E+06 cpm or if RM-063 exceeds 5.0 E-3 pC/cc; sample flow will automatically shift from RM-062 to RM-063 and the alarm URM-063 AUX BLDG VENT STACK IN SERVICE" will annunciate on Al-33C. When RM-063 radiation level drops below 5.0 E-3 pC/cc, sampie flow will shift to RM-062 and RM-063 will shift to Standby.

2.1 Evaluate the Auxiliary Building Vent Stack release pathway using RM-052, RM-062 and RM-063.

2.2 Evaluate the Condenser/Main Steam release pathway using RM-057, RM-064 and whether or not a primary to secondary leak has been confirmed.

2.2.1 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed, request that RM-064 be placed in service on the affected Main Steam Line.

2.2.2 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and if Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, request that Condenser Off-gas be aligned to the Auxiliary Building Vent Stack.

2.2.3 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, perform dose assessment with Condenser Off-gas as the release pathway, using a flow rate of 340 scfm.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 8 OF 30 Attachment 6.2 (continued) Page 2 of 3 2.2.4 If a primary to secondary leak is confirmed and RM-057 is not operable or is over ranged, and Condenser Off-gas is not aligned to the Auxiliary Building Vent Stack, this is an unmonitored release.

2.2.5 If there is a confirmed primary to secondary leak, and FW-10 is receiving steam from the affected Steam Generator, or the atmospheric Steam Dump Valve HCV-1040 is OPEN or a Steam Safety is lifting on the affected side, and RM-064 count rate is less than or equal to the background count rate as listed in TDB-IV.7, this is an unmonitored release.

2.3 Evaluate the Containment Leakage release pathway using Containment Area Monitors NOTE: If containment leakage is suspected to be greater than designed Containment leakage of 1.5 scfm, and the leakage is from the Containment to the stack or from the Containment to Controlled Areas of the Auxiliary Building to the Auxiliary Building Vent Stack, consideration may be given not to count the release twice if dose assessment will be performed from the Auxiliary Building Vent Stack.

2.3.1 If Containment Area Monitors RM-070 through RM-075 are in High Alarm or RM-091A and B read 1.0 R/hr or higher, perform dose assessment using Containment leakage as a release pathway.

2.3.2 IF any area monitors indicate > 1000 times the background listed in TDB-IV.8, THEN inform the Command and Control position for classification information.

2.4 Evaluate the Radwaste Building Stack as a release pathway using RM-043 2.4.1 If RM-043 is in High Alarm, perform dose assessment using the Radiological Waste Building Vent Stack as a release pathway.

2.5 Evaluate the liquid release pathways as follows:

2.5.1 IF RM-055, Overboard Discharge Monitor is reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and the overboard discharge flow is not isolated, then a liquid release assessment must be performed.

2.5.2 If either RM-054A or RM-054B Steam Generator Blowdown Monitors are reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and blowdown flow is not isolated from the Steam Generator(s) with a primary to secondary leak, then a liquid release assessment must be performed.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 9 OF 30 Attachment 6.2 (continued) Page 3 of 3 2.6 Determine if there are any potentially unmonitored releases.

3. Perform dose assessment for monitored release pathways using Attachment 6.4 and for unmonitored release pathways per Attachment 6.5.

4. Review NOTE: The information generated by EAGLE is for OPPD decision maker's information only. Actual PARs are determined by the Command and Control position. The Information Worksheet should be one of the tools used for guidance in determining PARs.

4.1 Obtain a printout of the Information Worksheet and the Update Report to Offsite Authorities.

4.2 Forwdrd printouts to the Protective Measures Coordinator.

5. Provide a detailed briefing to oncoming shift relief of emergency conditions and dose assessment status.

R33

FORT CALHOUN STATION .-4EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 10 OF 30 Attachment 6.3 - Dose Assessment in the Emergency Operation Facility Page 1 of 3

1. IF dose assessments are being performed in the Control Room, THEN contact the technician in the Control Room performing dose assessment and review all previous assessments using the fax copies.

2. IF dose assessments are being performed in the TSC, THEN contact the technician performing dose assessment in the TSC and review all previous assessments using the fax copies.

3. Standby to transfer dose assessment from the Control Room (or TSC) to the EOF, as directed by the Protective Measures Manager.

4. When directed to take over dose assessment, inform the technician in the Control Room (or TSC) of your actions.

5. Using information from the Control Room as needed and Al-33A, B and C or ERFCS pages 197, 360 and 361 evaluate and determine the release pathways for dose assessment as follows:

NOTE: The,sample Control Module for RM-052 must be in the VENT position (monitoring the Auxiliary Building Vent Stack) in order to be used for dose assessment.

NOTE: RM-0621063 are the preferred process monitors to be used for dose assessment on the Auxiliary Building Vent Stack. RM-062 is normally in-service and RM-063 is normally in Standby. When RM-062 count rate exceeds 5.0 E+06 cpm or if RM-063 exceeds 5.0 E-3 pC/cc; sample flow will automatically shift from RM-062 to RM-063 and the alarm "RM-063 AUX BLDG VENT STACK IN SERVICE" will annunciate on Al-33C. When RM-063 radiation level drops below 5.0 E-3 pC/cc, sample flow will shift to RM-062 and RM-063 will shift to Standby.

5.1 Evaluate the Auxiliary Building Vent Stack release pathway using RM-052, RM-062 and RM-063.

5.2 Evaluate the Condenser/Main Steam release pathway using RM-057, RM-064 and whether or not a primary to secondary leak has been confirmed.

5.2.1 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed, request that RM-064 be placed in service on the affected Main Steam Line.

5.2.2 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and if Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, request that Condenser Off-gas be aligned to the Auxiliary Building Vent Stack.

R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 11 OF 30 Attachment 6.3 (continued) Page 2 of 3 5.2.3 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, perform dose assessment with Condenser Off-gas as the release pathway, using flow rate of 340 scfm.

5.2.4 If a primary to secondary leak is confirmed and RM-057 is not operable or is over ranged, and Condenser Off-gas is not aligned to the Auxiliary Building Vent Stack, this is an unmonitored release.

5.2.5 If there Is a confirmed primary to secondary leak, and FW-10 is receiving steam from the affected Steam Generator, or the atmospheric Steam Dump Valve HCV-1040 is OPEN or a Steam Safety is lifting on the affected side, and RM1-064 count rate is less than or equal to the background count rate as listed in TDB-IV.7, this is an unmonitored release.

5.3 Evaluate the Containment Leakage release pathway using Containment Area Monitors NOTE: If containment leakage is suspected to be greater than designed Containment leakage of 1.5 scfm, and the leakage is from the Containmentto the stack or from the Containment to Controlled Areas of the Auxiliary Building to the Auxiliary Buiiding Vent Stack, consideration may be given not to count the release twice if dose assessment will be performed from the Auxiliary Building Vent Stack.

5.3.1 If Containment Area Monitors RM-070 through RM-075 are in High Alarm or RM-091A and B read 1.0 R/hr or higher, perform dose assessment using Containment leakage as a release pathway.

5.3.2 IF any area monitors indicate > 1000 times the background listed in TDB-IV.8, THEN inform the Command and Control position for classification information.

5.4 Evaluate the Radwaste Building Stack as a release pathway using RM-043 5.4.1 If RM-043 is in High Alarm, perform dose assessment using the Radiological Waste Building Vent Stack as a release pathway.

5.5 Evaluate the liquid release pathways as follows:

5.5.1 If RM-055, Overboard Discharge Monitor is reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and the overboard discharge flow is not isolated, then a liquid release assessment must be performed.

R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE ! PAGE 12 OF 30 Attachment 6.3 (continued) Page 3 of 3 5.5.2 If either RM-054A or RM-054B Steam Generator Blowqiown Monitors are reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and blowdown flow is not isolated from the Steam Generator(s) with a primary to secondary leak, then a liquid release assessment must be performed.

5.6 Determine if there are any potentially unmonitored releases.

6. Perform dose assessment for monitored release pathways using Attachment 6.4 and for unmonitored release pathways per Attachment 6.5.

7. Review NOTE: The information generated by EAGLE is for OPPD decision maker's information only. Actual PARs are determined by the Command and Control position. The Information Worksheet should be one of the tools used for guidance in determining PARs.

7.1 Obtain a printout of the Information Worksheet and the Update report to Offsite Authorities.

7.2 Forward printouts to the Dose Assessment Coordinator.

8. Provide a detailed briefing to oncoming shift relief of emergency conditions and dose assessment status.

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FORT CALHOUN i '

STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 13 OF 30 Attachment 6.4 - Computerized Dose Assessment Page 1 of 7

1. Logging on to Eagle 1.1 Is the Workstation on, with the EAGLE workstation status window showing?

NOTE: You can determine the status of all workstations by noting the color of the button on the icon located in the upper left hand corner of the screen: Blue = PC Mode, Green = Online Control Mode, Yellow = Offline, Red = Not available.

1.1.1 Yes Click the EAGLE Icon.

No Re-boot the system, EAGLE will automatically log itself in.

NOTE: If another workstation has network control and is performing dose assessment, coordinate the network synchronization accordingly. At the EOF, work with the EOF Dose Assessment Coordinator, to insure a smooth transfer of dose assessment responsibilities.

1.1.2 To take control, from the "Main Menu" screen, in the Status Box select "Network Control".

IF a process monitor reading increases by 50% while performing an assessment, or the Command and Control Position requests an immediate assessment, THEN complete the current assessment and immediately start another. (AR 10029)

2. Performing dose assessment, from the EAGLE "Main Menu" screen.

2.1 In the Mode box, select the appropriate selection.

2.2 In the Status box, select the appropriate selection (Network/Control is preferred) use PC standalone only if network is not working.

2.3 Click the 'Perform Dose Calculations" button.

NOTE: For this step of the procedure, select Normal Dose Projection. Imminent Release is discussed in Step 3 and Liquid Release in Step 4 of this Attachment.

2.3.1 The Input Data screen will appear, select 'Normal Dose Projection".

2.3.2 Click "OK".

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 14 OF 30 Attachment 6.4 (continued) Page 2 of 7 NOTE: It is possible to redo a plume by selecting that plume number at this point.

However all data for that plume and successive plumes will be lost.

2.3.3 The Plume Segment Number screen will appear, enter the desired number.

2.3.4 Click "OK".

NOTE: For unmonitored releases see Attachment 6.5.

2.4 Select "Monitored Release".

NOTE: There are four release points listed at this point. To simplify this procedure, guidance will only be given for the Auxiliary Building Stack. The method for doing other release paths is similar. Reference the EAGLE 6.0.0 User Manual if you need further guidance.

2.4.1 Select "Aux Building'.

A. Select other pathways, as needed.

B. Click"OK".

2.4.2 Core Damage A. Enter the highest Core Exit Thermocouple reading.

B. Enter the highest RM-091AIB reading (R/hr).

C. Click "OK".

D. At this point EAGLE will tell you if you have a damaged or undamaged core.

E. Click"OK'.

2.4.3 Aux Building Stack A. Click "the appropriate option" (the method used here will use radiation monitor data).

B. Select the appropriate rad monitor.

C. Enter the current rad monitor value.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 15 OF 30 Attachment 6.4 (continued) Page 3 of 7 NOTE: Step 2.4.3D to 2.4.3H is optional and used only if you want to change the default iodine/noble gas ratios OR the default isotopic spectrum.

2.4.3 D. Select 'Input Values".

E. Click 'Change Ratios" enter the desired values.

F. Click"OK".

G. Click'OK".

H. Select "Change Spectrum"

Zero the column desired by clicking the 'Zero "for the area of interest.

Enter the desired isotopic values (for each column total must equal 100%).

I. Click "OK".

2.4.4 The "Input Aux Building Stack Release Rates" screen will appear.

A. Enter the current uAux Building Vent Stack" flow (default is 72,500 CFM).

B. Click"OK".

2.5 Meteorological Data NOTE: For early dose assessments use the defaults for Atmospheric Mixing Conditions and Atmospheric Stability Class Method. The Protective Measures Group at the EOF should review Weather conditions and adjust assessments accordingly once the EOF has assumed command and control of the emergency.

2.5.1 Select the appropriate Atmospheric Mixing Conditions ("Unlimited Mixing Condition" is the default).

2.5.2 Select the Appropriate Atmospheric Stability Method ("Delta T Method" is the default).

2.5.3 Enter the slowest 10 meter wind speed.

2.5.4 Enter the wind direction the wind is coming from.

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FORT CALHOUN STATION A. LEPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE _PAGE 16 OF 30 Attachment 6.4 (continued) Page 4 of 7 2.5.5 Enter the ambient temperature in degrees Celsius.

2.5.6 Enter the most positive Delta T.

NOTE: If you chose an alternative Atmospheric Mixing or Atmospheric Stability Methods you will need to supply the information requested. in the windows that have opened.

A. Click"OK".

B. Enter the estimated release duration, click "OK".

NOTE: At this point, you may review your data to ensure that it is correct. Clicking on any of the buttons allows you to change one or all of the inputs in that specific section.

C. Click" Calc Plume".

D. The "Output Results" screen will appear,.

NOTE: Any projections that exceed limits established in EPIP-OSC-1 EAL's or EPIP-EOF-7 will be highlighted in red on the PAR Worksheet page.

E. With "Release Information" and "Offsite Document" selected, click

'Print".

F. Click on the "Worksheet" to obtain EAGLE projections.

G. Click "Print".

2.6 Graphic and Plume Data Printout 2.6.1 From the "Output Results" screen, select "Plume Data".

2.6.2 From the "Graph Display" screen, select "Display Graph".

2.6.3 Click Print".

2.6.4 Click "Quit".

2.7 Follow-up Actions 2.7.1 To go to the next plume segment, click "Run Next Segment".

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 17 OF 30 Attachment 6.4 (continued) Page 5 of 7 2.7.2 Go to Step 2.3.1 and follow guidance as needed to change inputs, as conditions require.

3. Imminent Release Assessment 3.1 Performing imminent release assessment, from the EAGLE "Main Menu" Screen.

3.1.1 In the Mode box, select the appropriate selection.

3.1.2 In the Status box, select the appropriate selection (Network Control is preferred) use PC standalone only if network is not working.

3.1.3 Click the 'Perform Dose Calculations" button.

NOTE: For this step of the procedure select Imminent Release. Normal Dose Projection is discussed is Step 2 and Liquid Release in Step 4 of this Attachment.

3.1.4 The Input Data screen will appear, select 'Imminent Release Dose Projection".

3.1.5 Click 'OK".

3.2 The Containment Imminent Release" screen will appear.

3.2.1 Select "Damaged" or "Undamaged" core based on plant conditions.

A. Enter time in hours, since accident.

B. Enter time until projected release.

C. Click "OK".

3.2.2 Select the flow rate method desired (Cubic feet per minute to Atmosphere is demonstrated here).

A. Enter the containment flow rate (default is 1.5 cfm).

B. Click 'OK".

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 18 OF 30 Attachment 6.4 (continued) Page 6 of 7 NOTE: For this procedure the Containment monitor reading will be,used. Refer to the EAGLE 6.0.0 User Manual for guidance on how to use the Isotopic Concentrations selection.

3.2.3 Select "Containment Area Monitor Reading (R/hr)".

A. Enter the Containment Monitor reading in Rem/hr.

B. Click 'OK".

3.3 Meteorological Data NOTE: For early dose assessments use the defaults for Atmospheric Mixing Conditions and Atmospheric Stability Class Method. The Protective Measures Group at the EOF should review weather conditions and adjust assessments accordingly once the EOF has assumed command and control of the emergency.

3.3.1 Select the appropriate Atmospheric Mixing Condition ("Unlimited Mixing Condition" is the default).

3.3.2 Select the Appropriate Atmospheric Stability Method (uDelta T Method" is the default).

3.3.3 Enter the slowest 10 meter wind speed.

3.3.4 Enter the wind direction the wind is coming from.

3.3.5 Enter the ambient temperature in degrees Celsius.

3.3.6 Enter the most positive Delta T.

NOTE: If you chose an alternative Atmospheric Mixing or Atmospheric Stability Method you will need to supply the information requested in the windows that have opened.

3.3.7 Click 'OK".

3.3.8 Enter the estimated release duration, click "OK".

3.3.9 The "Plume Centerline Straight-line Gaussian" screen will appear with the results of the imminent release calculation.

3.3.10 Click "Print" for a hard copy.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 19 OF 30 Attachment 6.4 (continued) Page 7 of 7

4. Liquid Release Assessment 4.1 Performing Liquid release assessment, from the EAGLE "Main Menu" Screen.

4.1.1 In the Mode box, select the appropriate selection.

4.1.2 In the Status box, select the appropriate selection (Network Control is preferred) use PC standalone only if network is not working.

4.1.3 Click the "Perform Dose Calculations" button.

NOTE: For this step of the procedure select Liquid Release. Normal Dose Projection is discussed is Step 2 and Imminent Release in Step 3 of this Attachment.

4.1.4 The Input Data screen will appear, select "Liquid Release".

A. Click"OK".

NOTE: IF one of the isotopes or the total of any of the isotopes exceeds 10 CFR 20 Appendix B limits you will be alerted to call MUD to have them shutdown their intake.

4.1.5 The "Liquid Release" Screen will appear.

A. Enter the activity for listed isotopes (available from chemistry).

B. Click "Print".

C. Click "OKn R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 20 OF 30 Attachment 6.5 - Determining Unmonitored Release Rates Page 1 of 11 NOTE: For determining projected release rates from the Ventilation Stack when RM-062/52 and 63 are off-scale/not available, refer to CH-SMP-PA-0005.

NOTE: For determining projected release rates from the Main Steam/Condenser Off-gas system when RM-057/64 are off-scale/not available, use Section 1.

NOTE: For determining projected release rates from Containment when RM-091AIB and RM-070 through RM-075 are off-scale/not available, use Section 2.

NOTE: For determining actual release rates using Field Team data, use Section 3.

1. For unmonitored releases via Condenser Off-gas/Main Steam System:

1.1 If RM-057 is off-scale or is not operable, and Condenser Off-gas is vented to the atmosphere via the Turbine Building Roof, perform dose assessment using RM-064 and a main steam flow in Ibm/hr from the affected Steam Generator (ERFCS page 353) per the following criteria:

1.1.1 If RM-064 is reading at or below background, use one (1) net count per minute (NCPM) for the RM-064 reading, and Attachment 6.4 to perform dose assessment.

1.1.2 If RM-064 is reading above background, use the indicated reading on RM-064, and Attachment 6.4 to perform dose assessment.

1.1.3 If RM-064 is off-scale high or is not operable, go to Section 1.3 below.

1.2 For unmonitored releases via FW-10, the Atmospheric Dump Valve (HCV-1040) or a Main Steam Safety Valve, perform dose assessment per the following criteria:

1.2.1 If RM-064 is reading at or below background use one (1) net count per minute (NCPM) for the RM-064 reading, a flow rate as determined from EAGLE, and Attachment 6.4 to perform dose assessment.

1.2.2 If RM-064 is reading above background, use the indicated reading on RM-064, a flow rate as determined from EAGLE, and Attachment 6.4 to perform dose assessment.

1.2.3 If RM-064 is off-scale high or is not operable, go to Section 1.3 below.

R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 21 OF 30 Attachment 6.5 (continued) Page 2 of 11 1.3 If RM-064 goes off-scale high or is otherwise known to be inoperable, perform the following:

1.3.1 Obtain direct radiation readings on the main steam lines in Room 81. Refer to Figure 6.5.1 for reading locations.

1.3.2 If the dose rate is between 0 and 100 mRem/hr, use the following equation to calculate the TEDE release rate:

QTEDE = (17.5) (Contact Dose Rate in mRem/hr) 1.3.3 If the dose rate is >100 mRem/hr, use the following equation to calculate the TEDE release rate:

QTEDE = (5) (Contact Dose Rate in mRem/hr) 1.3.4 Multiply the QTEDE from Step 1.3.2 or 1.3.3 by the following applicable step to obtain the noble gas, iodine and particulate release rate in curies per second:

A. For un-damaged core source term (other than secondary side listed below):

(QTde) (0.993) = noble gas release rate in curies per second.

(QTede) (0.007) = Iodine release rate in curies per second.

(QTede) (0.000) = Particulate release rate in curies per second.

B. For un-damaged core secondary side source term (Stm. Gen. Tube Rupture, Main Stm. Line Break, etc):

(QTdee) (0.9295) = Noble gas release rate in curies per second.

(Tede) (0.065) = Iodine release rate in curies per second.

(QTede) (0.00555) = Particulate release rate in curies per second.

R33

FORT CALHOUN STATION ; EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAG3E 22 OF 30 Attachment 6.5 (continued) Page 3 of 11 1.3.4 C. Damaged Core Source Term: The following equations should be used.

In these equations

t = time (hours) after the initiation of the damaged core source term.

It should be noted that it is important for EAGLE plume data to be entered every 15 minutes to maintain the accuracy of this and other calculation methods.

A = 0.02973e'447t + 0.2312e4 8"'4 - 0.0003404.

B = 0.0002911 e4327 + 0.01802e4 232' 6.056E-07 NOTE: If t > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , then A = 4.75E-4.

(QTde) (1-A) = noble gas release rate in curies per second.

(QTd.) (A) = Iodine release rate in curies per second.

NOTE: If t > 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , then B = 1.OE-6.

(QTd.) (B) = Particulate release rate in curies per second.

1.3.5 Input the Noble Gas, Iodine and Particulate Release Rate into the EAGLE dose assessment program to obtain the dose and dose rate results.

(AR 17061)

2. Containment Leakage 2.1 If all Containment Area Radiation Monitors are off-scale or inoperable, perform the following:

2.1.1 Obtain direct radiation readings on containment penetrations C-2 or H-4.

Refer to Figures 6.5.2 and 6.5.3 for reading locations.

2.1.2 Multiply this penetration reading by the Containment Multiplication Factor (CMF) using Figure 6.5.4, to determine an equivalent area monitor reading.

2.1.3 Insert the area monitor reading into the EAGLE dose assessment program to obtain the dose and dose rate results.

R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 23 OF 30 Attachment 6.5 (continued) Page 4 of 11

3. Determining actual release from Field Team Data.

NOTE: Field Teams must be dispatched, and data from the approximate plume centerline must be available in order to complete this step of this procedure. The Field Team Specialist should be consulted for field team data.

3.1 Performing unmonitored release assessment, from the EAGLE "Main Menu" screen.

3.1.1 In the Mode box, select the appropriate selection.

3.1.2 In the Status box select the appropriate selection (Network Control is preferred) use PC standalone only if network is not working.

3.1.3 Click the "Perform Dose Calculations" button.

3.1.4 The Input Data screen will appear select "Normal Dose Projection".

3.1.5 Click "OK".

NOTE: It is possible to redo a plume by selecting that number at this point. However all data for that plume and other sequential plumes will be lost.

3.2 The Plume Segment Number screen will appear, enter the desired number.

3.2.1 Click 'OK".

NOTE: For monitored releases see Attachment 6.4.

3.2.2 In the "Type of Release" section, select "Unmonitored".

3.2.3 Click 'OK".

3.3 The "Field Team Data" screen will appear.

3.3.1 In the Sector window, toggle down and highlight the affected sector.

3.3.2 In the Emergency Monitor Description, toggle down and highlight the Emergency Monitor.

3.3.3 In the Instrument Reading, enter the reading in mR/hr obtained by the Field Team Technician at the Emergency Monitor location.

R33

FORT CALHOUN STATION ;EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE - ; -PAGE 24 OF 30 Attachment 6.5 (continued) Page 5 of 11 3.3.4 If an air sample has been collected, select "Have Air Concentrations for lodines and Particulates'.

A. Enter the iodine and particulate concentrations provided by the field team technicians.

B. Click"OK".

3.3.5 If you do not have an air sample, select uAir Concentration for lodines and Particulates Not Available".

A. Click WOK".

3.3.6 You will be asked if the release is from the secondary side.

A. If Yes - Click WOK".

B. If No - You will be asked if the core is damaged.

If Yes - enter how long it has been damaged in the box.

Click "OK".

No - Click uOK".

3.3.7 Meteorological Data NOTE: For early dose assessments use the defaults for Atmospheric Mixing Conditions and Atmospheric Stability Class Method. The Protective Measures Group at the EOF should review weather conditions and adjust assessments accordingly once the EOF has assumed command and control of the emergency.

A. Select the appropriate Atmospheric Mixing Conditions ("Unlimited Mixing Condition" is the default).

B. Select the Appropriate Atmospheric Stability Method (Delta T Method is the default).

C. Enter the slowest 10 meter wind speed.

D. Enter the wind direction the wind is coming from E. Enter the ambient temperature in degrees Celsius.

R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 25 OF 30 Attachment 6.5 (continued) Page 6 of 11 3.3.7 F. Enter the most positive Delta T.

NOTE: If you chose an alternative Atmospheric Mixing or Atmospheric Stability Method you will need to supply the information requested in the windows that have opened.

G. Click"OK".

3.3.8 Enter the estimated release duration click 'OK".

A. An EAGLE message will appear informing you if a damaged or un-damaged core is being used for calculations.

B. Click "OK'.

NOTE: At this point, you may review your data to ensure that it is correct. Clicking on any of the buttons allows you to change one or all of the inputs in that specific section.

C. Click 'Calc Plume" 3.3.9 The 'Output Results" screen will appear.

NOTE: Any projections that exceed limits established in EPIP-OSC-1 EAL's or EPIP-EOF-7 will be highlighted in red on the worksheet page.

A. With "Release information" and 'Offsite Document" selected click "Print".

B. Click on the "Worksheet" to obtain EAGLE Projections.

C. Click"Print".

3.3.10 Graphic and Plume Data Printout A. From the "Output Results" screen, select "Plume Data".

B. From the 'Graph Display" screen, select "Display Graph".

C. Click "Print".

D. Click 'Quit'.

R33

FORT CALHOUN STATION . _ .I EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE -PAGE 26 OF 30 Attachment 6.5 (continued) Page 7 of 11 3.3.11 Follow-up Actions A. To go to next plume segment, click "Run Next Plume Segment".

B. Go to Step 3.3 and follow guidance as needed to change inputs, as conditions require.

R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 27 OF 30 Attachment 6.5 (continued) Page 8 of 11 Figure 6.5.1 - Main Steam Headers Radiation Dose Measurement Point Locations R33

FORT CALHOUN STATION , EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 28 OF 30 Attachment 6.5 (continued) Page 9 of 11 Figure 6.5.2 - Auxiliary Building - Plant Elevation 1007'-0" & 101 3'-0 R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 29 OF 30 Atiachment 6.5 (continued) Page 10 of 11 Figure 6.5.3 - Auxiliary Building - Plant Elevation 1036'-

R33

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 30 OF 30 Attachment 6.5 (continued) Page 11 of 11 Figure 6.5.4 - Containment Multiplication Factor (CMF) 1600 I

1 - - I I -I II 500- I I -I I I I I I I iI - I I I I II I I I I I I !If lf ,

.1. 4-1.-I-i I I I I 4- 4-4-4-1-1-4-I- 4 +

. A Il Ann A

- I I 4 -I J

SVV

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'A

. I . . . . . . . I .

A I vnf% ___ ___ I

I .1 . ... +-4-I--I--4I.I-I-I.

I.JVU -

0 .4- I------I-4-4 I I I I 4- 4-4-4-1-1-4-I 1 1-

- X

,C)120O0-rX4 E-I U 1100- _______

0 E-1000- _ - ___U - - ,

800-

_ T I

_T T~C.-2-=-__I r

=-____

6D0-0001 1 50 100 500 1000 TIME SINCE SHUTDOWN (HOURS)

R33

WP10 Distribution Authorized This procedure does not contain any proprietary information, or Fort Calhoun Station such Information has been Unit No. 1 censored. This issue may be released to the public document room. Proprietary information includes personnel names, company telephone numbers, and any information, which could impede emergency response.

EPIP-RR-25 EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

EOF DOSE ASSESSMENT COORDINATOR ACTIONS FC-68 Number: EC 33899 Reason for Change: Update for new Eagle 6.0.0, cnange capitalization.

Requestor: M. Reller Preparer: M. Reller ISSUED: 04-02-04 3:00 pm R22

FORT CALHOUN STATION EPIP-RR-25 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 7 EOF DOSE ASSESSMENT COORDINATOR ACTIONS NON SAFETY RELATED

1. PURPOSE 1.1 This procedure provides guidance to the EOF Dose Assessment Coordinator for performing actions in response to an emergency at Fort Calhoun Station.

2. REFERENCES/COMMITMENT DOCUMENTS 2.1 EPIP-EOF-6, Dose Assessment 2.2 EPIP-EOF-7, Protective Action Guidelines 2.3 EPIP-EOF-21, Potassium Iodide Issuance 2.4 EPIP-EOF-1 1, Dosimetry Records, Exposure Extensions and Habitability 2.5 FC-EPF-6, Estimated Exposure Worksheet 2.6 Commitment Documents

AR 13302, IER-92-20

3. DEFINITIONS None

4. PREREQUISITES None

5. PROCEDURE 5.1 The EOF Dose Assessment Coordinator will use Attachment 6.1 as an aid to completing required actions.

NOTE: When needed, perform dose assessments and updates to the states at least every 60 minutes. It is the goal of the Fort Calhoun Station to attempt to provide assessments and updates at 15 minute intervals. (AR 13302) 5.2 Use Attachment 6.2 as guidance in comparing field team data to dose assessment data.

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FORT CALHOUN STATION EPIP-RR-25 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 2 OF 7 5.3 Review the procedure and appropriate checklists, and accomplish the applicable steps both upon initial activation and periodically, as required, thereafter.

5.4 Retain all documentation (logs, calculation sheets, notes, etc.) generated or used during the emergency. At the termination, deliver all documentation to the Administrative Logistics Manager in the EOF.

6. ATTACHMENTS 6.1 EOF Dose Assessment Coordinator Checklist 6.2 Comparison of Field Team Data to Dose Assessment Data R22

FORT CALHOUN STATION EPIP-RR-25 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 3 OF 7 Attachment 6.1 - EOF Dose Assessment Coordinator's -Checklist Page 1 of 3 Maintain a log of all key activities

-W) INIT/TIME

1. Upon arrival:

1.1 Sign in on security roster 1.2 Put on personnel identification badge NOTE: If dose assessment is being performed at the EOF, proceed to Step 5. Otherwise continue with Step 2.

2. Instruct EOF Dose Assessment Specialist to:

2.1 Determine on-site dose assessment status.

2.2 Ensure that the EOF has a hard copy of all dose assessments.

2.3 Ensure that at least one EOF EAGLE machine is functional.

2.4 Stand by for transfer of dose assessment to the EOF.

3. Review the dose assessments to ensure proper response has been taken.

4. If required, direct transfer of dose assessment from the plant to the EOF:

4.1 Determine when the transfer of Command and Control will take place (ask the Protective Measures Manager or Emergency Director).

4.2 If possible coordinate the dose assessment transfer with the transfer of Command and Control.

4.3 Inform EOF Dose Assessment Specialist of time of transfer of Command and Control.

4.4 Ensure coordination of dose assessment transfer between on-site Dose Assessment Specialist and EOF Dose Assessment Specialist.

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FORT CALHOUN STATION EPIP-RR-25 EMERGENCY PLAN IMPLEMENTING PROCEDURE v PAGE4OF7 Attachment 6.1 Page 2 of 3 (continued) 1 INIT/TIME 4.5 Upon transfer ensure EOF Dose Assessment Specialist properly understands and is prepared to assume their duties. I NOTE: If field team direction is not yet at the EOF, check with the TSC Protective Measures Coordinator to determine their status.

5. Determine status of the Field Teams from the EOF Field Team I Specialist. I

6. Keep the Protective Measure Manager abreast of the status of dose assessment and the Field Teams. I

7. As data becomes available perform dose assessment and Field Team comparisons. Use Attachment 6.2. I

8. As conditions warrant contact the National Weather Service to obtain a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months forecast.

8.1 Determine the potential impact on dose assessment.

8.2 Determine the potential impact to the Field Teams.

NOTE: Do not activate the Health Physics Network (HPN) until requested to do so by the NRC.

9. As required, provide radiological information to:

9.1 The states/counties using the Conference Health Physics (CHP) Network or commercial line as a backup.

9.2 The NRC using the Health Physics Network (HPN) or commercial line as a backup.

10. If required, coordinate protective measures for Field Teams use:

EPIP-EOF-21, Potassium Iodide Issuance

EPIP-EOF-1 1, Dosimetry Issuance, Extensions and Habitability

FC-EPF-6, Estimated Exposure Worksheet R22

FORT CALHOUN STATION EPIP-RR-25 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 5 OF 7 Attachment 6.1 Page 3 of 3 (continued)

(V) INIT/TIME

11. As required, provide a detailed briefing to your relief covering:

Emergency conditions

Actions taken (current status) I _______

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FORT CALHOUN STATION ; EPIP-RR-25 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 6 OF 7 Attachment 6.2 - Comparison of Field Team Data to Dose Assessment Data Page 1 of 3 NOTE: This guideline should be used when field team data becomes available, to determine if dose projections match actual field team measurements. Based on these comparisons, the proper decision-makers may adjust Protective Action Recommendations (PARs) and Emergency Action Levels (EAL) accordingly.

1. Obtain an FC-EPF-27 Form(s).

1.1 Record the following data:

Date

Time 1.2 From the Field Team Specialist determine and record:

Field Team location

Approximate distance from site

Waist level dose rate (Rem/Hr) as reported by the Field Team

Iodine Concentration (pCi/cc) as reported by the Field Team

Particulate Air Concentration (pCi/cc) as reported by the Field Team 1.3 Using the EAGLE workstation 1.3.1 From EAGLE Main Menu:

Ensure EAGLE is in Network/Read

Select "Output Menu" 1.3.2 From the Plume Segment Screen enter the desired plume segment number.

1.3.3 Click "OK" 1.3.4 From the Output Results screen select "Plume Data" 1.3.5 Click 'Display Graph" 1.3.6 From the Graphic Screen

Click "EMER".

Using the pull down menu find the Emergency Monitor that the Field Team has reported on.

Click "Print".

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FORT CALHOUN STATION EPIP-RR-25 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 7 OF 7 Attachment 6.2 Page 2 of 2 (continued) 1.4 Recording Data 1.4.1 r-rom the EAGLE print out use the Field Team information 1.4.2 Record on the FC-EPF-27

The projected Field Team (Rem/Hr)

The projected Iodine 131 (pCi/cc)

The projected Particulate Air Concentration (pCi/cc) 1.5 Compare data and discuss any potential PAR correction with the Protective Measures Manager/Coordinator.

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WP110 Distribution Authorized This procedure does not contain any proprietary information, or such information has been Fort Calhoun Station censored. This issue may be Ureleased to the public document Uni o. room. Proprietary information includes personnel names, company telephone numbers, and any information, which could impede emergency response.

EPIP-RR-72 EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

FIELD TEAM SPECIALIST ACTIONS FC-68 Number: EC 34093 Reason for Change: Revise to inform Field Team Specialist that they now normally perform Field Team calculations. In accordance with change to EPIP-EOF-3.

Requestor: M. Reller Preparer: M. Reller ISSUED: 04-02-04 3:00 pmr R14

FORT CALHOUN STATION EPIP-RR-72 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 7 FIELD TEAM SPECIALIST ACTIONS NON-SAFETY RELATED

1. PURPOSE This procedure provides guidance to the EOF Field Team Specialist in performing actions in response to an emergency at Fort Calhoun Station.

2. REFERENCES/COMMITMENT DOCUMENTS 2.1 EPIP-EOF-3, Offsite Monitoring 2.2 FC-EPF-2, Offsite Monitor Log 2.3 FC-EPF-6, Estimated Exposure Worksheet 2.4 FC-EPF-7, Estimated Exposure Log 2.5 FC-EPF-8, Sample Worksheet 2.6 S.W. Gebers, CHP. ESTIMATES OF TOTAL EFFECTIVE DOSE EQUIVALENT:

USING DIRECT READING DOSIMETERS. December, 1993.

2.7 Radiological Health and Engineering, "Dose Assessment Model: Site Population Dose", Memorandum FC-RP-028-94 2.8 Radiological Analysis95-006, Halogen DCF Based on Field Air Sample

3. DEFINITIONS None

4. PREREQUISITES None

5. PROCEDURE 5.1 The EOF Field Team Specialist will use Attachment 6.1 as an aid to completing required actions.

5.2 Use Attachment 6.2 as guidance in directing Field Teams.

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FORT CALHOUN STATION , 1 EPIP-RR-72 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 2 OF 7 5.3 Review the procedure and appropriate checklists, and accomplish the applicable steps both upon initial activation and periodically, as required, thereafter.

5.4 Retain all documentation (logs, calculation sheets, notes, etc.) generated or used during the emergency. At the termination, deliver all documentation to the Administrative Logistics Manager in the EOF.

6. ATTACHMENTS 6.1 EOF Field Team Specialist Checklist 6.2 Plume Tracking Techniques R14

FORT CALHOUN STATION EPIP-RR-72 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 3 OF 7 Attachment 6.1 - EOF Field Team Specialist Checklist Page 1 of 3

Maintain a log of all key activities **

.W INITIAL/TIME

1. Obtain and put on Position Identification Badge. /

2. Contact the TSC Protective Measures Coordinator to receive briefing on status of field team activation, meteorological data, and radiological conditions. /

3. WVhen Field Teams initiate a radio check, direct the teams to synchronize their watches to ERF time and standby for further I direction. I

4. Brief the Field Teams on plant conditions and projected/known radiological conditions. I

5. Instruct the Field Teams to closely observe dosimeter readings and to immediately report if any dosimeters are approaching 150 mRem. I

6. Periodically review the following steps and perform, as required:

6.1 Keep the Field Teams updated on plant conditions and projected/known radiological conditions.

6.2 Coordinate with the EOF Dose Assessment Coordinator to direct the Field Teams to appropriate monitoring locations.

NOTE: Normally the EOF Field Team Specialist performs the following calculations, from information supplied by the TSC Field Teams.

6.3 Usina FC-EPF-8 and the data Drovided by the Field Teams perform the applicable calculations.

6.3.1 Record the results on FC-EPF-2. /

6.4 Record survey results and dosimeter readings from teams using FC-EPF-2. I R14

FORT CALHOUN STATION EPIP-RR-72 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 4 OF 7 Attachment 6.1 - EOF Field Team Specialist Checklist Page 2 of 3 (f) INITIAL/TIME 6.5 If any field team dosimeter readings approach or reach 150 mRem prior to performing a TEDE calculation, perform the following:

6.5.1 Instruct the teams to exit the area and report to either the EOF or plant site, as determined by the EOF Dose Assessment Coordinator.

6.5.2 Initiate an estimated TEDE determination for the team using FC-EPF-6.

A. IF an estimated TEDE cannot be calculated due to lack of data, THEN go to Step 6.5.3.

B. IF the estimated TEDE is greater than 1 Rem, THEN go to Step 6.5.3.

C. If the estimated TEDE is less than 1 Rem, team may again be dispatched upon approval from the Protective Measures Manager.

6.5.3 Initiate replacement of the team and a dosimetry/bioassay evaluation for the team through the EOF Dose Assessment Coordinator.

6.6 Use FC-EPF-6 to calculate estimated TEDE for the field teams, and inform them of the results.

6.6.1 If an estimated TEDE is greater than I Rem:

A. Instruct the teams to exit the area and report to either the EOF or plant site, as determined by the EOF Dose Assessment Coordinator.

B. Initiate replacement of the team and dosimetry/bioassay evaluation for the team through the EOF Dose Assessment Coordinator.

6.6.2 If an estimated TEDE is less than 1 Rem, team may continue.

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FORT CALHOUN STATION EPIP-RR-72 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 5 OF 7 Attachment 6.1 - EOF Field Team Specialist Checklist Page 3 of 3

(/) INITIAL/TIME 6.7 Post OPPD field team survey results. I 6.8 Submit completed FC-EPF-2 forms to the EOF Dose Assessment Coordinator for review and comparison to EAGLE data. I

7. Provide detailed briefing to oncoming shift relief of emergency conditions and status of field team monitoring. I R14

FORT CALHOUN STATION EPIP-RR-72 EMERGENCY PLAN IMPLEMENTING PROCEDURE ,- PAGE 6 OF 7 Attachment 6.2 - Plume Tracking Techniques Page 1 of 2 (W) INITIAL/TIME NOTE: Gamma radiation, above normal background, with no beta component may indicate the presence of a nearby elevated or horizontally displaced plume. A significant difference between open and closed window readings probably indicates immersion in the plume as the most energetic beta particle expected (3 MeV) would travel approximately 30 feet in air.

NOTE: An open air ion chamber becomes internally contaminated with noble gas after immersion in the plume for a short time. This condition gives the appearance of a "Gamma only response" (no difference between open and closed window). In this case, confirm background gamma radiation levels with GM detectors or other sealed chamber survey instruments.

1. If time and roadways allow, dispatch one team to a downwind location to intercept the Droiected center line of the plume and have them standby with dose rate instruments on. I

2. Dispatch the second team closer to the plant to continuously traverse the projected plume path with instruments on. Direct this team to notify you immediately upon locating the actual centerline. After the centerline has been located, direct the team to transverse the plume to determine the plume boundaries. l NOTE: As time to compare actual and projected dose is critical, give consideration to the roadway network and direct sampling by the team which can be placed closest to the centerline in the least amount of time.

3. Use the overlay map and plot the centerline path. As needed, move the first team to intercept the actual centerline and to take surveys as close to the centerline as dose rates and roadways allow. I

4. After the centerline surveys have been taken, direct the teams to determine the plume edges and remain outside the plume. Place teams on either side of the plume and periodically monitor the plume boundaries to ensure wind shift has not occurred. I

5. Based on radiological conditions and changes in plant status, additional surveys may be taken to confirm dose assessment projections. I R14

FORT CALhOUN STATION EPIP-RR-72 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 7 OF 7 Attachment 6.2 - Plume Tracking Techniques Page 2 of 2

(/) INITIAL/TIME

6. After plume passage and release termination, determine the following:

6.1 Boundaries of ground deposition 6.2 Beta and gamma dose rates from ground deposition 6.3 Surface contamination levels /

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LIC-04-0048, Transmittal of Changes to Emergency Plan Implementing Procedures (EPIP)

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