Text

Emergency Plan Implementing Procedures
	ML030420402
Person / Time
Site:	Cooper
Issue date:	02/03/2003
From:	Hutton J; Nebraska Public Power District (NPPD)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NLS2003014
	Download: ML030420402 (57)
	v • d • e

H Nebraska Public Power District Nebraska's Energy Leader NLS2003014 February 3, 2003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Emergency Plan Implementing Procedures Cooper Nuclear Station, NRC Docket 50-298, DPR-46 Pursuant to the requirements of 10 CFR 50, Appendix E, Section V, "Implementing Procedures,"

Nebraska Public Power District is transmitting the following Emergency Plan Implementing Procedures (EPIPs):

EPIP 5.7.6 Revision 37 "Notification" EPIP 5.7.17 Revision 29 "Dose Assessment" EPIP 5.7.20 Revision 16 "Protective Action Recommendations" Should you have any questions concerning this matter, please contact me.

Sincerely, Plant Manager

/cb Enclosures cc: Regional Administrator w/enclosures (2) NPG Distribution w/o enclosures USNRC - Region IV Records wv/o enclosures Senior Resident Inspector w/enclosures USNRC Cooper Nuclear Station P.O Box 98/ Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 http //www nppd corn

ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS Correspondence Number: NLS2003014 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the NL&S Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE None I PROCEDURE 0.42 1 REVISION 12 1 PAGE 14 OF 16

SOIUSE: REFERENCE CNS OPERATIONS MANUAL EFFECTIVE: 1/15/03 EPIP PROCEDURE 5.7.6 APPROVAL: SORC/IQA I

OWNER: R. J. FISCHER NOTIFICATION DEPARTMENT: EP

1. PU RPO SE ............................................................ 1

2. PRECAUTIONS AND LIMITATIONS ..................................... 1

3. ENTRY CONDITIONS .................................................. 2

4. CONTROL ROOM ACTIONS ............................................. 2

5. EOF ACTIONS ........................................................ 3

6. RECORDS ............................................................ 3 ATTACHMENT 1 COMPLETING NOTIFICATION FORM WITH CNS-DOSE AVAILABLE ........................................ 4 ATTACHMENT 2 COMPLETING NOTIFICATION FORM WITH CNS-DOSE NOT AVAILABLE .................................... 5 ATTACHMENT 3 COOPER NUCLEAR STATION NOTIFICATION REPORT.. 8 ATTACHMENT 4 SHIFT COMMUNICATOR ............................. 9 ATTACHMENT 5 OFF-SITE COMMUNICATOR ......................... 11 ATTACHMENT 6 INFORMATION SHEET ............................. 13

1. PURPOSE Provide instructions for initial, follow-up, and termination notifications to responsible State and Local governmental agencies, NRC notifications, initial generation of press releases to the Media, and notifications to other off-site support agencies.

2. PRECAUTIONS AND LIMITATIONS

[1 2.1 Initial notifications to State/Local agencies shall be performed within 15 minutes of each declaration of an Emergency and/or change in Protective Action Recommendations (PARs).©

[1 2.2 NRC notification shall be performed immediately following notification of responsible State and Local governmental agencies, and not later than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the time of declaration of one of the emergency classes.

[1 2.3 At an ALERT or higher classification, follow-up notifications to responsible State and Local governmental agencies shall be performed approximately every 60 minutes, or sooner if there is a significant change in the status of the emergency.© PROCEDURE 5.7.6 REVISION 37 PAGE 1 OF 15

[ ] 2.4 Section 8, "Release Information" of the Notification Report, is completed only when both of the following conditions exist:

[] 2.4.1 Follow-up notification.

[] 2.4.2 A release of Airborne Radioactive material greater than ODAM limits is occurring or occurred during the event.

[ ] 2.5 Notification of termination to off-site agencies shall be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the termination of the emergency.

[ ] 2.6 If the Control Room must be evacuated and off-site notification responsibilities have not been transferred to the EOF, the Shift Communicator shall perform off-site notifications over the State Notification Telephone from the TSC or EOF.

2.7 If making a notification for an Emergency that occurred but was not reported (e.g., the condition occurred yesterday but was not caught at that time), make the notification to State/Local agencies by performing an initial notification with the Event Declared and Terminated as the same time.

[ ] 2.8 The Emergency Director shall be immediately notified of any difficulties or delays in completing this procedure.

3. ENTRY CONDITIONS

[ ] 3.1 An Emergency has been declared per Procedure 5.7.1.

4. CONTROL ROOM ACTIONS

[] 4.1 NOTIFICATIONS FROM CONTROL ROOM.

[ ] 4.1.1 Emergency Director (ED) direct Operator or Shift Technical Engineer to complete Notification Report per Attachment 1.

[ ] 4.1.2 ED review form for accuracy.

[ ] 4.1.3 ED add remarks to the remarks section as appropriate.

[ ] 4.1.4 ED sign form including date/time.

[1 4.1.5 If FAX available, ED authorize notification to be faxed to State/Local agencies, NRC Operations Center, TSC, and EOF by providing password to Operator or Shift Technical Engineer.

[1 4.1.6 ED direct Shift Communicator to make notifications per Attachment 4.

PROCEDURE 5.7.6 REVISION 37 I PAGE2O 0 15

5. EOF ACTIONS

[] 5.1 NOTIFICATIONS FROM EOF

[1 5.1.1 Emergency Director (ED) direct Off-Site Communicator to complete Notification Report per Attachment 1.

[] 5.1.2 ED review form for accuracy.

[1 5.1.3 ED add remarks to the remarks section as appropriate.

[ ] 5.1.4 ED sign form including date/time.

[1 5.1.5 If FAX available, ED authorize notification to be faxed to State/Local agencies, NRC Operations Center, TSC, and EOF by providing password to Off-Site Communicator.

[] 5.1.6 ED direct Off-Site Communicator to make notifications per Attachment 5.

6. RECORDS

[1 6.1 Attachments 3, 4, and 5 from actual events shall be forwarded to the EP Manager within 5 working days of their completion (Quality Record upon completion).

PROCEDURE 5.7.6 REVISION 37 PAGE 3 OF15

ATTACHMENT 1 COMPLETING NOTIFICATION FORM WITH CNS-DOSE AVAILABLE S] ]CAUTION - If CNS-DOSE is not available, notify ED and complete Notification Form using Attachment 2.

1. COMPUTER DOSE PROJECTION/AUTOMATED NOTIFICATION REPORT

[1 1.1 On a PMIS terminal, enter turn-on code "DOSE".

[1 1.2 Complete Notification Report using on-line instructions.

[1 1.3 Deliver printed Notification Report to the ED to complete the remarks section and approve the notification.

[ ] 1.4 Verify ED signature, date, and time are on the Notification Report and fax using the on-line instructions.

[1 1.5 Provide completed Notification Report to the Communicator.

PROCEDURE 5.7.6 1 REVISION 37 1 PAGE 4 OF 15 j

A'TTACHMENT 2 COMPLETING NOTIFICATION FORM WITH CNS-DOSE NOT AVAILABLE

1. COMPLETE NOTIFICATION FORM

[ ] 1.1 Obtain copy of Attachment 3, Notification Report.

[ ] NOTE 1 - Initial Notifications: Steps 1.2 through 1.19 and 1.28 are required.

[ ] NOTE 2 - Follow-Up Notifications: Steps 1.2 through 1.28 are required.

[ ] NOTE 3 - Termination Notifications: Steps 1.2 through 1.9 are required.

[ ] 1.2 Notification Report Number: Enter 1 or the next sequential number if more than one has been generated during the event.

[ ] 1.3 Time of Transmittal: Leave blank.

[ ] 1.4 Initial or Follow-Up Report:

[] 1.4.1 Check Initial Report for EAL classifications or change in PAR.

[] 1.4.2 Check Follow-Up Report for all others including termination.

[] 1.5 Name of CNS Communicator: Leave blank.

1]1.6 Classification: Check the Emergency Classification.

[ ]1.7 EAL Number: Enter the EAL number (e.g., 1.1.2).

[ ]1.8 Event Declared (Date/Time): Enter time and date of the Emergency Declaration in military format (e.g., 14:18).

[1 1.9 Event Terminated (Date/Time): Enter time and date of the termination in military format (e.g., 14:18).

RELEASE DEFAULT POINT PRIMARY BACKUP VALUES 13 mph and D CNS DOSE or 100 M MET 60 M MET abi C ERP Stability Class All Other Points CNS DOSE or 10 M MET 60 M MET 8mph and D I_ I I Stability Class

[ ] 1.10 Wind Speed: Enter wind speed in MPH.

I PROCEDURE 5.7.6 1 REVISION 37 1 PAGE 5 OF 15

ATTACHMENT 2 COMPLETING NOTIFICATION FORM WITH CNS-DOSE NOT AVAILABLE 1.11 Wind From: Enter the direction (e.g., if the wind is coming from the east, enter 90.

[ ] NOTE - If it is currently raining, SPDS MET will have message "It is raining".

[1]1.12 Precipitation (Yes/No): Check Yes if there is precipitation. Check No if it is not.

[1 1.13 Stability Classification (A-G): Check Stability Class (A-G).

[1 1.14 Release Status (Is/Was/Will-Be):

[] 1.14.1 Is: Enter Is if release is currently in excess of ODAM limits or no release in progress/expected.

[] 1.14.2 Was: Enter Was if release is now less than ODAM limits.

[1 1.14.3 Will-Be: Enter Will-Be if release in excess of ODAM limits is expected.

[ ] 1.15 Release Type (None/Airborne/Liquid):

[] 1.15.1 None: Check None if releases are currently below ODAM limits.

[] 1.15.2 Airborne: Check Airborne if release is, was, or will-be in excess of ODAM limits for airborne activity.

[1 1.15.3 Liquid: Check Liquid if release is, was, or will-be in excess of ODAM limits for liquid activity.

[ ] 1.16 Protective Action Recommendations: Enter PARs. Verify PAR includes previous PARs if they have changed.

[1 1.17 Prognosis (Stable/Unstable):

[] 1.17.1 Check Stable if the event is not likely to degrade.

[] 1.17.2 Check Unstable if the event is degrading (e.g., RPV level is lowering or Containment Rad Monitors are trending upward).

[ 1 1.18 Plant Status (at Power/Shutdown): Check appropriate box.

I PROCEDURE 5.7.6 1 REVISION 37 1 PAGE 6 OF 15

ATTACHMENT 2 COMPLETING NOTIFICATION FORM WITH CNS-DOSE NOT AVAILABLE

[1 1.19 Remarks: Enter information that will be useful to the off-site agencies in understanding the event, plant conditions, or release information. If dose projections at 10 miles are greater than or equal to 1 REM TEDE or 5 REM CDE, enter "Projected dose at or beyond 10 miles exceed evacuation criteria".

S] 1.20 Section 8, "Release Information" of the Notification Report is completed only when both of the following conditions exist:

[1] 1.20.1 Follow-up notification.

[1] 1.20.2 A release of airborne radioactive material greater than ODAM limits is occurring or occurred during the event.

[ ] 1.21 Release From: Check the location that was or is exceeding ODAM limits.

[ ]1.22 Release Height: 100 M for ERP and 10 M for any building release. Other is checked if the release is not from a building.

[ ] 1.23 Release Duration: If duration is unknown, use the default of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

[ ] 1.24 Start Time: Enter release start time (e.g., 14:18)

[ ] 1.25 Stop Time: Enter release stop time if known; otherwise, enter "UNK".

[ ] 1.26 Release Rate (pCi/sec): Enter release rate in jICi/sec.

[I]1.27 Projected Integrated Dose (Rem) and Projected Dose Rate (Rem/hr):

Are obtained from CNS DOSE or by hand calculations per Procedure 5.7.17.

[ 1 1.28 Deliver to ED to add remarks, signature, date, and time.

I PROCEDURE 5.7.6 REVISION 37 1 PAGE 7 OF 15

ATTACHMENT 3 COOPER NUCLEAR STATION NOTIFICATION REPORT Notification Report Number: A of Transmittal:

Time

[ ] Initial Report (Complete Sections 1-7 only) [ ] Follow-Up Report

1) Name of CNS Communicator: Call Back Number: 402-825

2) Classification: [ ] NOUE; [ ] Alert; [ ] Site Area; ----------- [ General I.EAL Number:

Event Declared (Date/Time): I Event Terminated (DatelTime):

3) Meteorological Wind Speed: MPH Wind From: Degrees Precipitation: []Yes; ]No Conditionsl

t------------------------- -------------------

I-------

Stability Class: [ ]A; [ B; [I ]C; [ ]D; [ ] E; [ ]F;[ ]G

4) ODAM Airborne Release Values: There [ ] is [ ]no Release of Radioactive Material Greater ERP = 7.28E5 pCi/sec than ODAM Limits.

TG Bldg = 3.6E4 pCi/sec RX Bldg = 3.3E4 pCi/sec [ ]was [ ] an airborne ARW Bldg = 3.6E4 pCilsec

[ ] will be ]aliquid a

5) Protective Action Recommendations (PARS): General Emergency Automatic PAR - Evacuate 2 ml r~rdi,,il_ ml rlnwnwindl no indoors, and monitor EASIEBS remainder 10 ml EPZ.

-.- - ..-.---- - - ~- - --- - - ---- ---- ---

-, None ' Evacuate Sectors - Go indoors and monitor EASIEBS in Sectors

I ---------- I 4I 0-2 Miles' Mie 4- -------- 4----------------------4 ----------------------------------

2-5 Miles,,

2-ie--------I S

4-------------------------------4---------------

I 5-10 Miles ,

6) Prognosis: [ ]Stable; [] Unstable Plant Status: f]at Power; [ ] Shutdown

7) Remarks: -----------------------------

8) Release Information (required on follow-up Notification with airborne release > ODAM limits):

Release From: [ ] ERP; [ ] Reactor Building; [1 Turbine Building; [ Aug Radwaste Building; []Other: .

Release Height: [1100 M (ERP); [110 M (RB, TB, ARWB); [ Other: ft I Release Rate (pCi/sec)

------------------ J Estimated Duration: (Hours) Noble Gas: pCVsec Start Time: Iodides: N/A Stop Time: Particulate: N/A Distance Projected Integrated Dose (Rem Projected Dose Rate (Remlhr)

~----------------------- r ---------D l------ ------------ ' --------

From Plant TEDE CDE (Thyroid) a TEDE ' CDE (Thyroid)

4 ------ - - --- ---- -----------------.- - - -

Site Boundary II I 'I

. M.. . 4------------. - -------------.------ ----------

2 Milles 11 1 1 1

--le I 4 I I I------------------------

10 Miles _ _ _ _ , ,

Emergency Director Signature: Date: Time:

PROCEDURE 5.7.6 REVISION 37 PAGE 8 OF 15 I

ATTACHMENT 4 SHIFT COMMUNICATOR Notification Report Number:

[ ] 1.1 When directed to perform notification to State and Local Government agencies, perform the following:

[ ] 1.1.1 Verify ED signature/date/time and remarks section (optional) on Notification Report.

[1 1.1.2 Print your name and call back number on Notification Report, Block 1.

[1 1.1.3 Contact State/Local Agencies using State Notification Telephone System by pressing the "Group Call" button or 7450 from any phone.

NOTIFY FOLLOWING I ISPEED IO TIME AGENCIES Ii PHONE DIAL #' !ON LINE NAME OF CONTACT NEMA via Nebraska State I ' 04 Patrol 11 0

1 --------- I --- ----- L-----------i------------------------

Nemaha County EOC via 1 iState ' 20 0 It Nemaha County Sheriff ItNotification I--........

-- - - - - ---------- I ---- -- -- - - --f- - - - - - - - - - - - - - - - -

Atchison County EOC via 1 Telephone 1 1 I I 19 Atchison County Sheriff I System ,-

--------- * ------ - ---- -- I--- -- --- ---- -----

Missouri SEMA via22 Missouri Misour Hihwa Higwa ParolI

_____Patrol

[ ] NOTE - If communication is lost with one or more agencies, continue to make notifications to on-line parties. When notifications are complete, call back agencies missing and make report.

[1 1.1.4 Record time last party on line as "Time of Transmittal" on Notification Report.

[] 1.1.5 When all parties are on line, verify that they have received the faxed notification. Only information on the form is allowed to be communicated unless authorized by the ED.

[] 1.1.5.1 If FAX not received, read the Notification Report line by line.

[ ] 1.1.6 Notify ED notification to State/Local agencies is complete and time follow-up notification is required.

PROCEDURE 5.7.6 1 REVISION 37 PAGE 9 OF 15

ATTACHMENT 4 SHIFT COMMUNICATOR

[ ] 1.2 Contact NRC Headquarters via ENS immediately after Step 1.1.6 and not later than 60 minutes after declaration of an emergency.

NRC CNS TELEPHONE ALTERNATE PERSON CONTACTED TIME Dial # on Phone ETD or Speed Dial Sticker 10

[ 1.3. When contacted by ENS Communicator in TSC, transfer NRC notification responsibilities and notify ED. ENS communications from the TSC are performed in accordance with Procedure 5.7ENS.

NAME OF ENS COMMUNICATOR PERFORMED BY TIME

[] 1.4. When contacted by Off-Site Communicator in EOF, transfer off-site notification responsibilities and notify ED.

NAME OF OFF-SITE COMMUNICATOR PERFORMED BY TIME Communicator Signature: _ Date:

I PROCEDURE 5.7.6. REVISION 37 PAGE 10 OF 15

ATTACHMENT 5 OFF-SITE COMMUNICATOR Notification Report Number:

[ ] 1.1 When directed to perform notification to State and Local Government agencies, perform the following:

[1 1.1.1 Verify ED signature/date/time and remarks section on Notification Report.

[] 1.1.2 Print your name and call back number on Notification Report, Block 1.

[ ] 1.1.3 Contact State/Local agencies using State Notification Telephone System by pressing the "Group Call" button or 7450 from any phone.

NOTIFY FOLLOWING , TIME AGENCIES PHONE ON LINE I

1* NAME OF CONTACT NEMA via Nebraska State I a

S I Patrol Patrol------------- a----------- -------------------------------------------

Nemaha County EOC via State

'Notification i

Nemaha County Sheriff 1 Telephone

t---------

Atchison County EOC via System Atchison County Sheriff Missouri SEMA via Missouri Highway Patrol 1

[I ] NOTE - If communication is lost with one or more agencies, continue to make notifications to on-line parties. When notifications are complete, call back agencies missing and make report.

[1 1.1.4 Record time last party on line as "Time of Transmittal" on Notification Report.

[ ] 1.1.5 When all parties are on line, verify that they have received the faxed notification. Only information on the form is allowed to be communicated unless authorized by the ED.

[1 1.1.5.1 If FAX not received, read the Notification Report line by line.

[] 1.1.6 Notify ED that notification to State/Local agencies is complete and time follow-up notification is'required.

PROCEDURE 5.7.6 1 REVISION 37 PAGE 11 OF 15

ATTACHMENT 5 OFF-SITE COMMUNICATOR

[ ] 1.2 Perform notifications to the following support agencies, as soon as possible, after the declaration of an ALERT or higher emergency classification, but not until after all notifications are completed as required in Section 1.

AGENCY PHONE PERSON CONTACTED TIME INPO (800) 321-0614 American Nuclear (860) 561-3433 Insurers (ANI)

Communicator Signature: Date:

I PROCEDURE 5.7.6 REVISION 37 1 PAGE 12 OF 15 1

I ATTACHMENT 6 INFORMATION SHEET

1. DISCUSSION 1.1 All notifications and communications will be handled from the Control Room (CR) until the Technical Support Center (TSC) and Emergency Operations Facility (EOF) are activated. The responsibility of generating press releases to the media may be transferred to NPPD Corporate Communications Department personnel prior to activation of the Joint Information Center (JIC).

1.2 During a declared Emergency at CNS, Emergency notifications to the State of Nebraska; State of Missouri; Atchison County, Missouri; and Nemaha County, Nebraska are accomplished through the State Notification Telephone System.

The CNS State Notification Telephone System is a conference-calling system.

When the handset to this hotline is picked up, and the "Group Call" button is pushed, dedicated telephones will automatically ring at Nebraska State Patrol, Missouri Highway Patrol, Atchison County Sheriffs Department, and Nemaha County Sheriffs Department. The utilization of law enforcement agencies as initial points of contact provides for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage. The dedicated lines listed also have extension lines which ring at the following facilities respectively: Nebraska Emergency Management Agency EOC, Missouri State Emergency Management Agency EOC, Atchison County EOC, and Nemaha County EOC. Once the EOCs become operational, notifications may be made using the extension lines at the EOCs with concurrence between the respective EOC and law enforcement agency.

1.3 Notifications to the NRC are normally accomplished through the Emergency Notification System (ENS). The Emergency Notification System is a dedicated telephone system which is manned 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by the Duty Officer at the NRC Headquarters Operations Center.

1.4 During any notification activity, if the primary communications system fails, communication methods shall be attempted such as alternate telephones, National Warning System (NAWAS), base station radio, or relay through a third party. Alternate telephone numbers are listed in the Emergency Telephone Directory.

1.5 At an ALERT or higher emergency classification, to receive continuous and detailed information, the NRC will likely request an open line of communication with the Control Room (CNS) until the TSC is operational.

I PROCEDURE 5.7.6 REVISION 37 1 PAGE 13 OF 15

ATTACHMENT 6 INFORMATION SHEET 1.6 The Public Affairs Duty Officer (PADO) shall be notified by pager by the CNS ANS and instructed to contact the Shift Communicator in the Control Room.

Upon being contacted by the PADO, the Shift Communicator will ensure all information from the Initial CNS Notification Report is relayed to the PADO.

In such cases, that it is not feasible to relay the information via telephone in a timely manner, the Notification Report may be faxed to the PADO. PADO functions shall be superseded by the activation of the Joint Information Center (JIC). The JIC shall receive follow-up information from the Technical Information Coordinator in the EOF.

1.7 The On-Call Emergency Preparedness Coordinator should assume the responsibility of coordinating press releases after being notified and responding to a Notification of Unusual Event (NOUE).

1.7.1 Assist the Shift Communicator in ensuring communications are established with the PADO and information from the CNS Notification Reports is relayed to the PADO per Procedure 5.7.23.

1.7.2 This responsibility shall be for the period immediately after the declaration of the NOUE and continue until the responsibility is transferred to appropriate NPPD Corporate Communications Department personnel.

1.7.3 Any press release that is generated during this period should be reviewed and approved by the Emergency Director.

1.8 Authorized Representatives of the Governors of Nebraska and Missouri may be represented in the EOF and set up Forward Command Posts at some other location.

2. REFERENCES 2.1 CODES AND STANDARDS 2.1.1 10CFR50.

2.1.2 NPPD Emergency Plan for CNS.

2.2 PROCEDURES 2.2.1 Emergency Plan Implementing Procedure 5.7.1, Emergency Classification.

I PROCEDURE 5.7.6 REVISION 37 1 PAGE OF 154

ATTACHMENT 6 INFORMATION SHEET 2.3 MISCELLANEOUS 2.3.1 CNS Emergency Telephone Directory.

2.3.2 NRC Inspection Report 89-35, Item 1.

2.3.3 NCR 93-52.

2.3.4 NRC Inspection Report 94-11.

2.3.5 NRC Inspection Report 94-29, Item 1.

2.3.6 QA Observation 93-05A.

2.3.7 QA Report 86-06.

2.3.8 RCR 2001-0181, Action #2, Require State/Local Notification within 15 minutes of a PAR or change in PAR.

2.4 NRC COMMITMENTS 2.4.1 © NRC Inspection Report 92-14. Commitment affects Steps 2.1 and 2.3.

2.4.2 © NRC Inspection Report 98-12 (NLS980074-05 and NLS980074-06).

Commitment affects Steps 2.1 and 2.3.

PROCEDURE 5.7.6 1 REVISION 37 1 PAGE 15 OF 15 1

USE: REFERENCE i EFEC E: /70 CNS OPERATIONS MANUAL APPROVA: R/IQA EPIP PROCEDURE 5.7.17 APPROVAL: SORC/IQA DOSE ASSESSMENT OWNER: J. A. BEDNAR DPRMN:E DEPARTMENT: EP

1. PU RPO SE ............................................................ 1

2. PRECAUTIONS AND LIMITATIONS ..................................... 2

3. REQUIREM ENTS ...................................................... 2

4. COMPUTER DOSE PROJECTION (CNS-DOSE) ............................ 3

5. HAND-CALCULATED DOSE PROJECTION (CENTERLINE) ................. 5

6. HAND-CALCULATED DOSE PROJECTION (NON-CENTERLINE) ............ 8

7. CORRELATING OFF-SITE SAMPLE RESULTS WITH DOSE PROJECTIONS©

............................................................... .... ..... 12 C) 8. CORE DAMAGE ESTIMATE USING IN-CONTAINMENT HI-RANGE RADIATION M ONITORS ............................................... .......... 14 C) ATTACHMENT 1 HAND-CALCULATED DOSE PROJECTION (NON CENTERLINE) ..................................... 15 ATTACHMENT 2 TRANSIT TIMES AND EFFECTIVE AGES OF NOBLE GASES AT RECEPTOR SITES ........................ 17 ATTACHMENT 3 HAND-CALCULATED DOSE PROJECTION (CENTERLINE)

......... . ... ............. . ......... ............ 18 ATTACHMENT 4 CORRELATING OFF-SITE SAMPLE RESULTS WITH DOSE PROJECTIONS ..................................... 20 ATTACHMENT 5 METEOROLOGICAL AND RADIOLOGICAL DATA SOURCES FOR CNS-DOSE .................................... 21 ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE .................... 22 ATTACHMENT 7 CORE DAMAGE ESTIMATION ....................... 29 ATTACHMENT 8 INFORMATION SHEET ............................. 30

1. PURPOSE H [ ] 1.1 This procedure provides instructions for performing a dose projection using the CNS-DOSE Computer Program.

[ ] 1.2 This procedure provides a manual backup method for performing dose assessment.

[ ] 1.3 This procedure provides instructions for making a rapid gross estimation of core damage based on in-containment high range radiation monitor readings 0 for primary containment LOCA events.

PROCEDURE 5.7.17 REVISION 29 PAGE 1OF32

[ ] 1.4 This procedure provides instructions for obtaining meteorological data from alternate sources if the primary sources are not available. The general order of preference will be PMIS, National Weather Service, and then the use of historically determined default values.

2. PRECAUTIONS AND LIMITATIONS

[ ] 2.1 Actual dose rates will vary as a function of:

[ ] 2.1.1 The total curies released.

[1 2.1.2 Release rate.

[1 2.1.3 The duration of the release.

[ ] 2.1.4 The isotopic mixture of the release.

II] 2.1.5 Meteorological conditions.

/

[ ] 2.2 Update and refine dose calculations upon significant changes in one or more of the above parameters.

[ ] 2.3 Should a release occur which necessitates rapid decision making concerning the recommendation of protective actions, the guidance contained in Procedure 5.7.20 should be followed.

[ ] 2.4 Attachment 7 should be used to estimate core damage only in cases where the high range in-containment radiation monitors are exposed to coolant or steam (i.e., only for primary containment LOCA situations). For other accident sequences, a Reactor Coolant System (RCS) sample and Core Damage Assessment Program (CORDAM) must be used. The Post-Accident Sampling System (PASS) may be used, as required, to obtain the RCS sample.

[ ]2.5 If the needed KAMAN monitor(s) is (are) inoperable, Release Rate Determinations shall be performed using Procedure 5.7.16.

3. REQUIREMENTS

[ ] 3.1 Ensure following equipment and materials are available, as needed:

[] 3.1.1 COMPUTERIZED DOSE PROJECTION (CNS-DOSE)

[ ] 3.1.1.1 Computer terminals.

[ ] 3.1.1.2 Computer printers.

I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 2 OF 32 j

[ ] 3.1.2 MANUALLY CALCULATED DOSE PROJECTION

[ ] 3.1.2.1 Environs map.

[1 3.1.2.2 X/Q isopleths (off-centerline only).

[ ] 3.1.2.3 Scientific calculator.

[ ] 3.2 A release of airborne radioactive material has or may occur.

NOTE 1 - When Meteorological or Radiological data needed to perform dose assessment is unavailable or "unhealthy", refer to Attachment 5 for alternate sources of data. Health "quality codes" are defined in Attachment 6.

[ ] NOTE 2 - If the user is not familiar with the use of PMIS, Attachment 6 provides an overview and instructions on access and selected use of PMIS.

4. COMPUTER DOSE PROJECTION (CNS-DOSE)

[ ] 4.1 To start the dose projection program on a PMIS terminal, enter the turn-on code "DOSE" on a terminal logged into either the Primary or Backup System.

[ ] 4.2 The dose projection program can also be run on a non-PMIS terminal.

However, this is reserved for personnel having access to an account on the computer and familiar with its use. To start the dose projection program on a non-PMIS terminal, on either PMIS computer, login to an account that has privileges to run PMIS software and run program

[NPPD.EXECUTE]NPDOSEZ.

[ 3 4.3 Each time the program is started or the "New Sample" option is selected, new data will be loaded into the program. Verify that Field 1 correctly indicates the origin of the release and the data displayed is "healthy" and correct.

Health "quality codes" are defined in Attachment 6. Alternate sources of meteorological and radiological data needed to run CNS-DOSE or perform a hand-calculation are found in Attachment 5.

[ ] 4.4 Estimate the duration of release (consult with Operations and/or Engineering for this time estimate) in hours. If the estimated duration of release cannot be determined, use the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months default value.

[ ] 4.5 Determine if SGT is in the effluent stream and if it is functional. Consult with Radiological, Operations, and Engineering personnel for this determination, if available.

I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 3 OF 32

[ ] NOTE - The Iodine to Noble Gas ratio is very dependent on the answer to the core degraded question and has a significant impact on the resultant dose projection calculations. The core is considered to be degraded if any of the following listed conditions are met OR if they were met and have subsequently dropped below the condition threshold. The answer to the core degraded question is coordinated between Radiological Protection, Chemistry, Operations, and Engineering, if available.

[1 4.6 Determine if the core is degraded (fuel cladding loss) as indicated by any of the following conditions:

[] 4.6.1 15,000 mrem/hr on SJAE monitor.

[ ] 4.6.2 Reactor Coolant Sample > 300 jiCi/gm Dose Equivalent 1-131.

[ ] 4.6.3 LOCA with DW Rad Monitor reading > 2500 REM/hr.

[ ] 4.6.4 Non-LOCA with DW Rad Monitor reading > 115 REM/hr.

[ ] 4.6.5 Main Steam Line Radiation Monitor Readings > 1200 mremlhr.

[ ] 4.6.6 Reactor water level below 0" FZ (Fuel Zone).

[] 4.7 DETERMINE IF RELEASE BYPASSES SECONDARY CONTAINMENT

[ ] 4.7.1 If release bypasses secondary containment (i.e., direct venting of drywell or a release from the Turbine Building), then enter Y.

[ ] 4.7.2 If release does not bypass secondary containment, then enter N.

[ ] 4.8 Make corrections or changes, as necessary.

[ ] 4.9 Use the ENTER key to accept data and move to the next field.

[ ] 4.10 Press the RESULTS option to display the dose projections.

[ ] 4.11 Select either the PRINT or HARD COPY option to make a hard copy of the results.

[ ] 4.12 Select the "New Sample" or "Edit" option to return to the previous display and obtain new data or make additional changes.

[ ] 4.13 Exit the program by entering "Q" or pressing the "CANC" key on PMIS terminals.

[ ] 4.14 Select the "Help" option for additional program operational information.

I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 4 OF 32

5. HAND-CALCULATED DOSE PROJECTION (CENTERLINE)

[ ] NOTE - This method reflects the methodology used in the CNS-DOSE Program. It gives only downwind dose values for plume centerline at distances of 1, 2, 5, and 10 miles from the site. For calculating doses at specific receptor locations, the method in Section 6 is used.

[ ] 5.1 Obtain release rate from effluent KAMAN monitor digital readout in [+/-Ci/sec and record value in Block 1 on Attachment 3. If KAMAN is inoperable, complete the appropriate attachment of Procedure 5.7.16 and record the noble gas release rate value ([iCifsec) in Block 1 on Attachment 3.

[ ] NOTE - The answer to the question concerning the status of the Standby Gas Treatment System has a significant impact on the resultant dose projection calculation. The answer to this question is coordinated with Radiological, Operations, and Engineering personnel, if available.©

[1 5.2 Determine if SGT is in the effluent stream.

[] 5.2.1 If SGT is in the effluent stream, enter 0.01 in Block 2 of Attachment 3.

[1 5.2.2 If SGT is not in the effluent stream, enter 1 in Block 2 of Attachment 3.

[ ] NOTE - The Iodine to Noble Gas ratio is very dependent on the answer to the core degraded question and has a significant impact on the resultant dose projection calculations. The core is considered to be degraded if any of the following listed conditions are met OR if they were met and have subsequently dropped below the condition threshold. The answer to the core degraded question is coordinated between Radiological Protection, Chemistry, Operations, and Engineering, if available.

[ ] 5.3 Determine if the core is degraded (fuel cladding loss) as indicated by any of the following conditions:

[] 5.3.1 15,000 mrem/hr on SJAE monitor.

[ ] 5.3.2 Reactor Coolant Sample > 300 [iCi/gm Dose Equivalent 1-131.

[ ] 5.3.3 LOCA with DW Rad Monitor reading > 2500 REM/hr.

[1 5.3.4 Non-LOCA with DW Rad Monitor reading > 115 REM/hr.

[1 5.3.5 Main Steam Line Radiation Monitor Readings > 1200 mrem/hr.

[1 5.3.6 Reactor water level below 0" FZ (Fuel Zone).

PROCEDURE 5.7.17 REVISION 29 PAGE 5 OF 32

5.3.7 If core is degraded, obtain the Iodine to Noble Gas ratio from Table 1 of Attachment 3 and enter that value in Block 3 of Attachment 3.

[] 5.3.8 If core is not degraded, enter 1.86E-7 in Block 3 of Attachment 3.

[1 5.4 Obtain the Noble Gas energy factor (MeV/dis) based on time since reactor shutdown in hours from Table 2 on Attachment 3 and enter this value in Block 4 on Attachment 3.

I [] 5.5 Obtain the wind speed in miles per hour (mph) from PMIS and record the value in Block 5 of Attachment 3. If wind speed is not available from PMIS, call the National Weather Service (NWS) in Valley, NE and request an estimate of wind speed at CNS for the appropriate elevation. The telephone number for the NWS may be found in the Emergency Telephone Directory Federal TAB.

[] 5.5.1 If the release is from the ERP, use wind speed at the 100 meter level.

If 100 meter data is unavailable, use the 60 meter data. If wind speed is unavailable from PMIS, and the NWS cannot be contacted, then use the historical default wind speed value of 13 mph.

[] 5.5.2 If the release is from any other source, use the wind speed at the 10 meter level. Either MET tower 10 meter level is acceptable. If 10 meter data is unavailable, use the 60 meter data. If wind speed is unavailable from PMIS, and the NWS cannot be contacted, then use the historical default wind speed value of 8 mph.

[ ] 5.6 Determine the atmospheric stability class ("A" through "G") from PMIS and record in Block 6 on Attachment 3. If the stability class cannot be obtained from PMIS and the National Weather Service cannot be contacted, use "D" as the default stability class.

[1 5.6.1 If using temperatures from the NWS to develop delta-T-based stability class, request the temperatures (10 meter (M) and 100 M) in degrees Centigrade. Determine degrees Centigrade (C) delta-T and the appropriate stability class using the following formula and table:

100 M 'C - 10 M 'C = delta-T 'C delta-T °C < -1.7 -1.7 to -1.5 -1.5 to -1.3 -1.3 to -0.45 -0.45 to 1.3 1.3 to 3.6 > 3.6 Stability Class A B C D E F G I PROCEDURE 5.7.17 REVISION 29 1 PAGE 6 OF 32 1

[ 5.7 DETERMINE IF RELEASE BYPASSES SECONDARY CONTAINMENT

[ ] 5.7.1 If release bypasses secondary containment (for example, direct venting of drywell or a release from the Turbine Building), then enter 1 in Block 7 on Attachment 3.

[ ] 5.7.2 If release does not bypass secondary containment, then enter 0.5 in Block 7 on Attachment 3.

[1 5.8 Obtain TEDE Noble Gas Dose Conversion Factor from Table 3 of Attachment 3 and record in Block 8 on Attachment 3.

[ ] 5.9 Obtain TEDE Iodine Dose Conversion Factor from Table 3 of Attachment 3 and record in Block 9 on Attachment 3.

[ ] 5.10 Obtain CDE Iodine Dose Conversion Factor from Table 3 of Attachment 3 and record in Block 10 on Attachment 3.

[ ] 5.11 Compute TEDE "sub-calculation" value and record in Block 11 of Attachment 3.

[(Block 1)(Block 4)(Block 8)1 + [(Block 1)(Block 2)(Block 3)(Block 7)(Block 9)1 (Block 5)

[ 5.12 Using the appropriate release point (ERP or other) and stability class (Block 6), obtain the mixing factors (x/Qs) for distances 1, 2, 5, and 10 miles from Table 4 on Attachment 3 and record in Block 12 of Attachment 3.

] 5.13 Compute the TEDE dose rate for each distance and record values in Block 13 on Attachment 3.

(Block 11) x (Block 12)

] 5.14 Estimate the duration of the release (consult with Operations and/or Engineering for this time estimate) in hours and record value in Block 14 on Attachment 3. If the estimated duration of release cannot be determined, use 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months as a default value.

[ ] 5.15 Compute integrated TEDE doses for each distance and record values in Blocks 15 on Attachment 3.

(Block 13) x (Block 14)

[ 5.16 Compute CDE "sub-calculation" value and record in Block 16 of Attachment 3.

(Block 1)(Block 2)(Block 3)(Block 7)(Block 10)

(Block 5)

PROCEDURE 5.7.17 REVISION 29 ] PAGE 7 OF 32

[] 5.17 Compute the CDE dose rate for each distance and record values in Block 17 on Attachment 3.

(Block 16) x (Block 12)

[ ] 5.18 Compute the CDE dose for each distance and record values in Block 18 on Attachment 3.

(Block 17) x (Block 14)

[ ] 5.19 Refer to Procedure 5.7.1 to determine if an emergency should be declared due to radiological effluent (dose rate or integrated dose to a member of the public) calculated at or beyond 1 mile.

[ ] 5.20 Refer to Procedure 5.7.20 to determine if any protective action recommendations should be made to off-site authorities.

[ ] 5.21 Recalculate dose projections whenever conditions change significantly.

[ ] 5.22 Record name, time, and date at the bottom of Attachment 3.

6. HAND-CALCULATED DOSE PROJECTION (NON-CENTERLINE)

[ ] 6.1 Obtain release rate from effluent KAMAN monitor digital readout in [XCi/sec and record value in Block 1 on Attachment 1. If KAMAN is inoperable, complete appropriate attachment of Procedure 5.7.16 and record the noble gas release rate value (iiCi/sec) in Block 1 on Attachment 1.

[ ] NOTE - The answer to the question concerning the status of the Standby Gas Treatment System has a significant impact on the resultant dose projection calculation. The answer to this question is coordinated with Radiological, Operations, and Engineering personnel, if available.

[1 6.2 Determine if SGT is in the effluent path.

[] 6.2.1 If SGT is in effluent path, enter 0.01 in Block 2 on Attachment 1.

[ ] 6.2.2 If SGT is not in effluent path, enter 1 in Block 2 on Attachment 1.

I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 8 OF 32 J

[ ] NOTE - The Iodine to Noble Gas ratio is very dependent on the answer to the core degraded question and has a significant impact on the resultant dose projection calculations. The core is considered to be degraded if any of the following listed conditions are met OR if they were met and have subsequently dropped below the condition threshold. The answer to the core degraded question is coordinated between Radiological Protection, Chemistry, Operations, and Engineering, if available.

[ ] 6.3 Determine if the core is degraded (fuel cladding loss) as indicated by any of the following conditions:

] 6.3.1 15,000 mrem/hr on SJAE monitor.

[ ] 6.3.2 Reactor Coolant Sample > 300 iCi/gm Dose Equivalent 1-131.

[ ] 6.3.3 LOCA with DW Rad Monitor reading > 2500 REM/hr.

[ ] 6.3.4 Non-LOCA with DW Rad Monitor reading > 115 REM/hr.

[7] 6.3.5 Main Steam Line Radiation Monitor Readings > 1200 mremlhr.

17] 6.3.6 Reactor water level below 0" FZ (Fuel Zone).

[ ] 6.3.7 If core is degraded, obtain the Iodine to Noble Gas ratio from Table 1 of Attachment 1 and enter that value in Block 3 on Attachment 1.

[1 6.3.8 If core is not degraded, enter 1.86E-07 in Block 3 on Attachment 1.

[ ] 6.4 Determine the energy factor (MeV/dis) based on time since reactor shutdown in hours and Table 2 on Attachment 1, and enter value in Block 4 on Attachment 1.

I 17] 6.5 Obtain the wind speed in miles per hour (mph) from PMIS and record the value in Block 5 on Attachment 1. If wind speed is not available from PMIS, call the National Weather Service (NWS) in Valley, NE and request an estimate of wind speed at CNS for the appropriate elevation. The telephone number for the NWS may be found in the Emergency Telephone Directory Federal TAB.

[] 6.5.1 If the release is from the ERP, use wind speed at the 100 meter level.

If 100 meter data is unavailable, use the 60 meter data. If wind speed is unavailable from PMIS, and the NWS cannot be contacted, then use the historical default wind speed value of 13 mph.

I PROCEDURE 5.7.17 REVISION 29 PAGE 9 OF 32

[ ] 6.5.2 If the release is from any other source, use the wind speed at the 10 meter level. Either MET tower 10 meter level is acceptable. If 10 meter data is unavailable, use the 60 meter data. If wind speed is unavailable from PMIS, and the NWS cannot be contacted, then use the historical default wind speed value of 8 mph.

I [] 6.6 Determine the wind direction (from) in degrees from PMIS and record in Block 6 on Attachment 1. If wind direction is not available from PMIS, call the National Weather Service (NWS) in Valley, NE and request an estimate of wind direction at CNS for the appropriate elevation. The telephone number for the NWS may be found in the Emergency Telephone Directory - Federal TAB.

I [ ] 6.7 Determine the atmospheric stability class ("A" through "G") from PMIS and record in Block 7 on Attachment 1. If the stability class cannot be obtained from the PMIS and the NWS cannot be contacted, use "D" as the default stability class.

[] 6.7.1 If using temperatures from the NWS to develop delta-T-based stability class, request the temperatures (10 meter (M) and 100 M) in degrees Centigrade. Determine degrees Centigrade (C) delta-T and the appropriate stability class using the following formula and table:

100 M °C - 10 M 'C = delta-T °C

[] 6.8 DETERMINE IF RELEASE BYPASSES SECONDARY CONTAINMENT

[I 6.8.1 If the release bypasses secondary containment (for example direct venting of the drywell or a release from the Turbine Building), then enter 1 in Block 8 on Attachment 1.

[ ] 6.8.2 If the release does not bypass secondary containment, then enter 0.5 in Block 8 on Attachment 1.

[ ] 6.9 Obtain TEDE Noble Gas Dose Conversion Factor from Table 3 of Attachment 1 and record in Block 9 on Attachment 1.

[ ] 6.10 Obtain TEDE Iodine Dose Conversion Factor from Table 3 of Attachment 1 and record in Block 10 on Attachment 1.

[] 6.11 Obtain CDE Iodine Dose Conversion Factor from Table 3 of Attachment 1 and record in Block 11 on Attachment 1.

I PROCEDURE 5.7.17 REVISION 29 1 PAGE 10 OF 32

[ ] 6.12 Obtain the mixing factor (x/Q) for the receptor point or location.

[] 6.12.1 Record location or receptor point ID at the top of Attachment 1.

[] 6.12.2 Obtain the proper x/Q isopleth overlay based on stability class and release point.

[] 6.12.2.1 Overlays are available in the TSC or EOF for both elevated and ground level releases for each stability class.

Use ground level isopleths for all releases which are not from the ERP.

[ ] 6.12.3 Place the isopleth overlay on an Emergency Planning Zone map scaled to 1" per mile. The preferred map is the "Cooper Nuclear Station 20 Mile Plume Exposure" map with sectors, radii, and wind direction labeled. One is posted in the TSC and EOF.

[ ] 6.12.4 Orient the isopleth overlay so the centerline of the isopleth is over the wind direction radius, the open end of the isopleth is downwind, and the asterisk is over CNS.

[1 6.12.5 Lightly mark the desired receptor location on the isopleth with a pencil.

[] NOTE -All x/Qs have negative exponents.

[] 6.12.6 Using the legend in the lower right hand corner of the isopleth overlay, linearly interpolating as necessary, determine a x/Q value for the receptor site.

[] 6.12.7 Record the x/Q value in Block 12 on Attachment 1.

[ ] 6.13 Compute TEDE dose rate (REM/hr) and record in Block 13 on Attachment 1.

[(Block 1)(Block 4)(Block 9)1+[(Block 1)(Block 2)(Block 3)(Block 8)(Block 10)1 x (Block 12)

(Block 5)

[ ] 6.14 Estimate the duration of the release (consult with Operations and/or Engineering for this time estimate) in hours and record the value in Block 14 on Attachment 1. If the estimated duration of release cannot be determined, use 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months as a default value.

[1 6.15 Compute the integrated TEDE dose (REM) and record in Block 15 on Attachment 1.

(Block 13) x (Block 14)

I PROCEDURE 5.7.17 I REVISION 29 II PAGE PAE1F2 11 OF 32 I1 I PRCDR .. 7 EIIN2

[ ] 6.16 Compute CDE dose rate (REM/hr) and record in Block 16 on Attachment 1.

(Block 1)(Block 2)(Block 3)(Block 8)(Block 11) x (Block 12)

(Block 5)

[ ] 6.17 Compute CDE dose (REM) and record in Block 17 on Attachment 1.

(Block 14) x (Block 16)

[ ] 6.18 Record name, time, and date at the bottom of Attachment 1.

7. CORRELATING OFF-SITE SAMPLE RESULTS WITH DOSE PROJECTIONS©

[ ] NOTE 1 - This section describes the methodology to be used to correlate CNS-DOSE results (estimated gross iodine concentrations) with gross iodine concentrations sampled in the field.

[ ] NOTE 2 - This section is to be used by dose assessment personnel in the EOF once field teams have been dispatched and sample results become available.

[ ] NOTE 3 - Initial dose projections (computer and hand-calculated) are based upon assumed radionuclide concentrations until actual concentrations have been measured. Off-site sample results are used to determine a dose correction factor which may be applied to adjust the CNS-DOSE Program.

[] 7.1 FIELD TEAM SAMPLE TO CNS-DOSE COMPARISON

[] 7.1.1 Radiological Assessment Supervisor shall:

[ ] NOTE 1 - Prior to comparing field team air sample results, ensure that the time of the field team air sample and the time of "CNS-DOSE" dose assessment are comparable.

[] NOTE 2 - If the field team air sample is reported from a distance other than 1, 2, 5, or 10 miles, use the appropriate stability class/release point isopleth to determine what CNS-DOSE predicted iodine air sample results would be at that distance prior to performing the field team sample comparison.

[1 7.1.1.1 Compare the field team iodine air sample concentrations with the predicted CNS-Dose iodine air sample concentrations using the decision tree in Step 7.1.2.

[ ] 7.1.1.2 Radiological Control Manager shall review the field team corrected dose assessment results and communicate any change in PARs or Classification to the Emergency Director.

PROCEDURE 5.7.17 1 REVISION 29 PAGE 12 OF 32

[ ] 7.1.2 Validate Inputs to the CNS-Dose Model puts Correct?

N I

Correct Inputs and 1` re-perform dose Correct Inputs and Inputs Correct? assessment and atl. 4 to Radiological Control* END Manager. .__ _

[] 7.2 APPLYING FIELD TEAM CORRECTION TO CNS-DOSE

[ ] 7.2.1 Apply the correction to CNS-Dose using the "Field Adjust" OPTION of CNS-DOSE.

[1] 7.2.1.1 At the MAIN CNS-DOSE screen, select option "Field Adjust".

I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 13 OF 32 1

[ ] 7.2.1.2 Enter the radius distance from CNS in miles at the prompt (1, 2, 5, and 10 are the only options).

[ ] 7.2.1.3 Enter the gross iodine concentration (in iCi/cc) obtained from the field at the prompt.

[ ] 7.2.1.4 After obtaining new Results from CNS-DOSE, compare new PARs to any PARs previously transmitted to off-site authorities.

8. CORE DAMAGE ESTIMATE USING IN-CONTAINMENT HI-RANGE RADIATION MONITORS

[ ] NOTE 1 -Attachment 7 is only used for core damage estimates where the in-containment radiation monitors are exposed to coolant or steam (i.e., only for primary containment LOCA situations). For other accident sequences, a Reactor Coolant System (RCS) sample and Core Damage Assessment Program (CORDAM) must be used. The Post-Accident Sampling System (PASS) may be used, as required, to obtain the RCS sample.

[ ] NOTE 2 - The release from the core may bypass the containment, be retained in the primary system, or not be uniformly mixed. Therefore, a low containment radiation reading does not guarantee a lack of core damage. The levels of damage indicated by the value in Attachment 7 are considered minimum levels unless there are inconsistent monitor readings.

[ ] NOTE 3 - Inconsistent monitor readings may be due to the uneven mixing in containment (e.g., steam rising to the top of the dome). It may take hours for uniform mixing.

[1 8.1 The Chem/RP Coordinator or designee shall perform following steps to determine an estimate of core damage, if decisions must be made which are based on core conditions and PASS results are not available.

[] 8.1.1 Obtain highest in-containment hi-range radiation monitor reading from RMA-RM-40A(B), DRYWELL RAD MONITOR, and record in Block 1 on Attachment 7.

[ ] 8.1.2 Complete the calculations on Attachment 7.

[] 8.1.3 Report results to the TSC Director.

I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 14 OF 32 j

ATTACHMENT 1 HAND-CALCULATED DOSE PROJECTION (NON-CENTERLINE)

Location or Receptor ID.

(1) Noble Gas Release (2) Release Path (3) Iodine/Noble Gas (4) Energy Factor (5) Wind Speed (mph) (6) Wind (7) Stability (8) Secondary Rate from KAMAN or through SBGT? Ratio Direction Class Containment 5.7.16 (ptCi/Sec) Bypassed9 Yes = 0 01; No = 1 (from Table 1) (from Table 2) ERP = 13; Other = 8 (° from) Default = D No = 0.5; Yes 1 For Columns 5, 6, and 7, use PMIS, NWS, or Defaults.

Mixing Factor Conversion Factors (from Table 3) (from Isopleths)

TEDE Noble Gas (9) (12)

TEDE Iodine (10)

CDE Iodine (11)

TEDE Dose Rate (13): (REM/hr) Duration (Hours) TEDE Dose (REM)

Default = 4 hrs (Block 13) x (Block 14)

[(Block 1)(Block 4)(Block 9)]÷[(Block l)(Block 2)(Block 3)(Block 8)(Block 10)1 x (14) (15)

(Block 5) x (Block 12)

CDE Dose Rate (16)" (REM/hr) CDE Dose (REM)

(Block 14) x (Block 16) r(Block 1)(Block 2)(Block 3)(Block 8)(Block 11)1 x (Block 12) (17)

(Block(Block 5)

5) (7 Name/Time/Date:

I PROCEDURE 5.7.17 REVISION 29 PAGE 15 OF 32

ATTACHMENT 1 HAND-CALCULATED DOSE PROJECTION (NON-CENTERLINE)

TABLE 1 - IODINE TO NOBLE GAS RATIO VS. TABLE 2 - ENERGY FACTORS TIME SINCE SHUTDOWN TIME SINCE IODINE/NOBLE GAS RATIO TIME SINCE ENERGY SHUTDOWN NON-DEGRADED DEGRADED SHUTDOWN FACTOR (hrs) CORE CORE (hrs) (MeV/dis) t<1 1.86 E-7 2.71 E-1 t<1 0.75 1* t<2 1.86 E-7 3.57 E-1 1<t < 2 0.60 2:< t < 4 1.86 E-7 3.41 E-1 2:5 t < 4 0.40 4 < t < 10 1.86 E-7 2.81 E-1 4:5 t < 10 0.25 10*_ t < 30 1.86 E-7 2.30 E-1 10 < t < 30 0.15 30:< t < 100 1.86 E-7 1.65 E-1 30

t < 100 0.09 100 < t 1.86 E-7 1.40 E-1 100 < t 0.07 TABLE 3 - DOSE CONVERSION FACTORS NON-DEGRADED CORE DEGRADED CORE TEDE Noble Gas 1.48 E-3 9.19 E-4 TEDE Iodine 8.77 E-2 2.98 E-2 CDE Iodine 2.04 E 0 4.96 E-1 I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 16 OF 32

ATTACHMENT 2 TRANSIT TIMES AND EFFECTIVE AGES OF NOBLE GASES AT RECEPTOR SITES

1. Effective Age is defined as time elapsed (hrs) since shutdown. For off-site locations, the effective age of the isotopic mixture may be obtained through summarizing following components:

[ ] 1.1 The effective age at the time of release onset.

[ ] 1.2 The transit time from the release point to the receptor site (refer to Section 2 below).

2. CALCULATION OF TRANSIT TIME FROM THE RELEASE POINT TO THE RECEPTOR LOCATION

[ ] 2.1 Estimate the downwind distance (miles) to the receptor location.

[ ]2.2 Divide the distance in miles by the 100m meter level wind speed (mph) to determine the plume transit time.

(1) RECEPTOR SITE (2) 100 METER LEVEL (3) PLUME TRANSIT DOWNWIND DISTANCE WIND SPEED TIME (hrs)

(miles) (mph) (1) -(2)

3. DETERMINATION OF EFFECTIVE AGES AT RECEPTOR SITES (3) EFFECTIVE AGE OF (1) EFFECTIVE AGE OF (2) TRANSIT TIME FROM ISOTOPIC MIXTURE AT MIXTURE AT TIME RELEASE POINT TO RECEPTOR LOCATION OF RELEASE ONSET RECEPTOR LOCATION (hrs)

(hrs) (hrs) (1) + (2) 4 4-Name/Time/Date: I I I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 17 OF 32

ATTACHMENT 3 HAND-CALCULATED DOSE PROJECTION (CENTERLINE)

(1) Noble Gas Release Rate (2) Release Path (3) Iodine/Noble Gas (4) Energy Factor (5) Wind Speed (mph) (6) Stability (7) Secondary from KAMAN or through SBGT? Ratio (MeV/dis) Class Containment 5.7.16 ([iCiSec) Bypassed?

Yes = 0 01; No = 1 (from Table 1) (from Table 2) Defaults ERP = 13; Other = 8 Default = D No = 0 5; Yes = 1 For Columns 6 and 6, use PMIS, NWS, or Defaults TEDE Sub-Calculation (11):

Conversion Factors (from Table 3)

TEDE Noble Gas (8) r(Block 1)(Block 4)(Block 8)1+r(Block 1)(Block 2)(Block 3)(Block 7)(Block 9)1 TEDE Iodine (9) (Block 5)

CDE Iodine (10)

Duration (hours)

TEDE RATE (REM/hr) TEDE Dose (REM)

Mixing Factors (from Table 4) (Block 11 x Block 12) Default = 4 hrs (Block 13 x Block 14) 1 Mile (12) 1 Mile (13) (14) 1 Mile (15) 2 Mile (12) 2 Mile (13) 2 Mile (15) 5 Mile (12) 5 Mile (13) 5 Mile (15) 10 Mile (12) 10 Mile (13) 10 Mile (15)

CDE Rate (REM/hr) CDE Dose (REM)

CDE Sub-Calculation (16). (Block 16 x Block 12) (Block 14 x Block 17) 1 Mile (17) 1 Mile (18)

[(Block 1)(Block 2)(Block 3)(Block 7)(Block 10)A 2 Mile (17) 2 Mile (18)

(Block 5) 5 Mile (17) 5 Mile (18) 10 Mile (17) 10 Mile (18)

Name/Time/Date- / I I PROCEDURE 5.7.17 REVISION 29 1 PAGE 18 OF 32

ATTACHMENT 3 HAND-CALCULATED DOSE PROJECTION (CENTERLI TABLE 1 - IODINE TO NOBLE GAS RATIO VS. TABLE 2- ENERGY TIME SINCE SHUTDOWN FACTORS IODINE/NOBLE GAS RATIO TIME SINCE ENERGY TIME SINCE NON-DEGRADED DEGRADED SHUTDOWN FACTOR SHUTDOWN (hrs) CORE CORE (hrs) (MeV/dis) t<1 1.86 E-7 2.71 E-1 t<1 0.75 1:<t<2 1.86 E-7 3.57 E-1 15 t<2 0.60 2* t < 4 1.86 E-7 3.41 E-1 2*< t < 4 0.40 4 < t < 10 1.86 E-7 2.81 E-1 4 < t < 10 0.25 10

t < 30 1.86 E-7 2.30 E-1 10:5 t < 30 0.15 30 < t < 100 1.86 E-7 1.65 E-1 30 < t < 100 0.09 100 *_t 1.86 E-7 1.40 E-1 100

t 0.07 TABLE 3 - DOSE CONVERSION FACTORS NON-DEGRADED CORE DEGRADED CORE TEDE Noble Gas 1.48 E-3 9.19 E-4 TEDE Iodine 8.77 E-2 2.98 E-2 CDE Iodine 2.04 E 0 4.96 E-1 TABLE 4 - PLUME CENTERLINE XIQ'S (MIXING FACTORS)

RELEASE STABILITY POINT CLASS A B C D E F G 1 MILE 2.87E-6 6.04E-6 1.17E-5 8.35E-6 1.03E-6 2.35E-11 1.31E-23 ERP 2 MILE 7.94E-7 1.78E-6 4.55E-6 8.21E-6 4.98E-6 8.12E-8 5.62E-13 (ELEVATED) 5 MILE 1.50E-7 3.42E-7 1.18E-6 3.77E-6 4.66E-6 1.09E-6 5.67E-9 10 MILE 4.51E-8 1.03E-7 4.58E-7 1.82E-6 3.13E-6 1.44E-6 4.00E-8 OTHER I MILE 3.01E-6 6.90E-6 1.73E-5 5.10E-5 1.09E-4 3.07E-4 7.67E-4 THAN ERP 2 MILE 8.03E-7 1.84E-6 5.15E-6 1.78E-5 3.86E-5 1.09E-4 2.71E-4 (GROUND 5 MILE 1.50E-7 3.44E-7 1.21E-6 4.98E-6 1.25E-5 3.52E-5 8.81E-5 LEVEL) 10 MILE 4.51E.8 1.03E-7 4.63E-7 2.07E-6 6.43E-6_- 1.81E-5 4.52E-5 PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 19 OF 32

ATTACHMENT 4 CORRELATING OFF-SITE SAMPLE RESULTS WITH DOSE PROJECTIONS CORRECTION FACTOR DETERMINATIONS USING OFF-SITE SAMPLING DATA (3) FIELD GROSS (4) CNS-DOSE (5)

(2) IODINE IODINE CORRECTION (1) SAMPLE SAMPLE CONCENTRATION CONCENTRATION FACTOR (CF)

LOCATION TIME (jICi/cc) (1iCi/cc) (3) - (4)

Name/Time/Date: / I

3. Route completed form to Emergency Preparedness Department.

I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 20 OF 32 1

ATTACHMENT 5 METEOROLOGICAL AND RADIOLOGICAL DATA SOURCES FOR CNS-DOSE NOTE 1 - When the normal source of meteorological data (PMIS MET screen) is not available or is "unhealthy", attempt to obtain the data by PMIS point ID. If PMIS is not available, call the National Weather Service (NWS) in Valley, NE to obtain the data. The telephone number is contained in the Emergency Telephone Directory - Federal TAB. If the NWS cannot be contacted, use default values.

NOTE 2 - If the user is not familiar with the use of PMIS, Attachment 6 provides an overview and instructions on access and selected use of PMIS.

NOTE 3 - The Turn-On-Code "VALUE" is used to display single point values and qualities.

NOTE 4 - The Turn-On-Code "MET" is used to display most meteorological point values and stability classes.

I PMIS POINT ID DESCRIPTION MET001 100M LVL SIGMA THETA (15 MIN AVE)

MET004 100M LVL TEMPERATURE MET005 DELTA TEMPERATURE (10OM-10M)

MET006 100M LVL WIND DIR. (15 MIN AVE)

MET007 100M LVL WIND SPEED (15 MIN AVE)

MET009 60M LVL SIGMA THETA (15 MIN AVE)

MET012 60M LVL TEMPERATURE MET013 DELTA TEMPERATURE (10OM-60M)

MET014 60M LVL WIND DIR. (15 MIN AVE)

MET015 60M LVL WIND SPEED (15 MIN AVE)

MET017 10M LVL SIGMA THETA (15 MIN AVE)

MET020 10M LVL TEMPERATURE MET021 DELTA TEMPERATURE (60M-10M)

MET023 10M LVL WIND DIR. (15 MIN AVE)

MET024 10M LVL WIND SPEED (15 MIN AVE)

MET027 PRECIPITATION (15 MIN PERIOD)

MET028 10M TWR SIGMA THETA (15 MIN AVE)

MET029 10M TWR TEMPERATURE MET030 10M TWR WIND DIR. (15 MIN AVE)

MET031 10M TWR WIND SPEED (15 MIN AVE)

N8000 RX BLDG EFFLUENT FLOW AVE N8001 TURB BLDG EFF HI RAD MON AVE N8002 TURB BLDG EFF NORM RAD MON AVE N8003 TURB BLDG FLOW AVE N8004 AOG & RW EFF HI RAD MON AVE N8005 AOG & RW EFF NORM RAD MON AVE N8006 RX BLDG EFF RAD MON AVE N8007 AOG & RW BLDG EFF FLOW AVE N8010 ERP HI RAD MON AVE N8011 ERP NORMAL RAD MON AVE N8012 ERP FLOW AVE N8013 SGT FLOW TO ERP AVE I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 21 OF 32

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE PLANT MANAGEMENT INFORMATION SYSTEM (PMIS) 1.1 The PMIS System (PMIS) is a set of programs and hardware provided by NPPD that make use of VMS functions and additional peripherals (Data Concentrators) which provides access to plant parameters.

2. PMIS COMPUTERS 2.1 PMIS computers share a common set of peripherals (disk drives, tape drives, terminals, etc.) and software.

3. VMS OPERATING SYSTEM 3.1 The VMS Operating System (VMS) is the host operating system for the PMIS computers. It is a set of programs that interface with the computer hardware and peripherals, and allows the computers to recognize and process commands.

4. PMIS MODES 4.1 PMIS has three operational modes, Primary, Primary/Backup, and Backup, and will operate on either computer in one of the three modes. A computer with PMIS operating in either the Primary or Primary/Backup Mode is referred to as the Primary System and the one with PMIS operating in the Backup Mode is referred to as the Backup System.

4.2 The Primary and Primary/Backup Modes provide full PMIS capabilities, consisting (in part) of data acquisition and conversion, data display, data archiving, alarm processing, self monitoring, and many other functions that perform specialized calculations and displays.

4.3 The Backup Mode monitors the Primary System, transfers information necessary to keep the Backup System files and tables up-to-date, and automatically changes to the Primary Mode when a loss of the Primary System is detected (referred to as a FAILOVER). Although many functions are available on the Backup System, their use is discouraged because the lack of real-time data results in the display of inaccurate information (CNS-DOSE is an exception).

5. PMIS ACCESS 5.1 Access to PMIS is gained through various video display terminals, printer/plotters, and printers, including color graphic Information Display Terminals (IDTs) dedicated exclusively for PMIS access in the Control Room, TSC, and EOF.

PROCEDURE 5.7.17 REVISION 29 PAGE 22 OF 32

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE 5.2 The IDTs and printers are selectively connected to either computer through a switching device controlled by PMIS. At system start or during a FAILOVER, all terminals and printers are switched to the Primary System. However, the SWITCH position may be changed at any time after that.

6. SCREEN FORMAT 6.1 When a terminal is under control of PMIS (instead of VMS), the screen display will be in a standard format consisting of four areas, OCA, GGDA, SSA, and FKA.

6.2 The OCA (Operator Communication Area) consists of the top two (one and two lines on the screen. This area is generally used to prompt-for and receive user inputs and display advisory and warning messages. In addition, some displays that require only one or two lines of screen use the OCA for display. Also (though technically not part of the OCA), the current date and time (updated once a second) is displayed at the right side of the screen on lines 1 and 2.

6.3 The GGDA (General and Graphic Display Area) consists of lines 4 through 47 and is used for most displays. In addition, some displays (chiefly functions requiring significant editing) also prompt-for and receive user inputs in the GGDA.

6.4 The SSA (SPDS Status Area) consists of lines 45 through 48 and contain four boxes that represent (by color code) the status of the SPDS (Safety Parameter Display System), which is a software system that monitors selected plant parameters and determines overall plant safety status.

6.5 The FKA (Function Key Area) consists of the bottom two (50 and 51) lines of the screen. The FKA is used to indicate which of the definable function keys are enabled. It also indicates which mode PMIS is in, the Plant Mode, and whether or not a PMIS "event" has occurred.

7. SCREEN-COPY FUNCTION 7.1 The screen-copy function, which is activated by pressing the HARD COPY key, provides full screen reproduction in color on a printer located in the same general area as the terminal.

8. PRINTER 8.1 The printers are connected to a specific computer and are generally accessed when a "...PRINT..." option is selected and a "logical name" is entered.

PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 23 OF 32

I ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE

9. LOGICAL NAME 9.1 Printers and terminals are usually referenced by "logical names", in the format of TTOO, TT01, etc. (IDTs), and LA00, LA01, etc. (printers). The "logical name" for a device can usually be found on a tag on the device.

10. RESET FUNCTION 10.1 This function, which is activated by pressing the RESET key (PC keyboard) or CONTROL-RESET keys (IDT keyboard), clears the screen, sounds the bell, and resets internal parameters to the default settings, producing the same effect as a re-boot or turning power off and on.

11. IDE FIELD 11.1 User input to PMIS Programs is through an open IDE (Interactive Data Entry) field on the terminal. An open IDE field is denoted by a yellow box that appears in the OCA or GGDA area. Anything typed on the keyboard will be echoed in the box. Erasing or back-spacing is accomplished with the DEL key.

All entries into an IDE field must be terminated by pressing the ENTER key unless the field is overfilled or a function key is pressed (the terminal automatically adds a carriage return character in those cases).

12. TURN-ON-CODE 12.1 The Turn-On-Code (TOC) is the mechanism by which commands are issued to PMIS. This is a one to eight character code which is interpreted by PMIS and a corresponding command is issued.

13. PMIS DATABASE 13.1 All plant parameters (or additional data based on plant or PMIS parameters) that are processed by PMIS SYSTEM are defined in the PMIS DATABASE, which is a file that specifies the origin of the data, the frequency at which it is processed, the type of processing to be performed, etc. Each parameter is referred to as a "point" and is identified by a one to eight character name or POINT-ID (PID).

14. PMIS DATA PROCESSING 14.1 Some PMIS points are processed by scanning plant sensors (through the Data Concentrator) while others are calculated based on the values of previously processed points or PMIS parameters. All points values are then assigned a quality code stored in the Current Value Table (CVT).

PROCEDURE 5.7.17 1 REVISION 29 PAGE 24 OF 32

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE 14.2 Data in the CVT is considered to be "real-time" and representative of current plant and system conditions.

14.3 At regular intervals (and other special circumstances) point values are also stored in an Archive File, which provides - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of on-line historical information.

15. PMIS DATA ACCESS 15.1 All point values in the CVT and Archive File are accessed by the POINT-ID.

16. QUALITY CODES 16.1 The Quality Code, assigned when point values are assigned, represents the general status and "health" of the point, and determines how it is used by PMIS Programs. The following is a list of PMIS quality codes and related information.

CODE DESCRIPTION COLOR HEALTH UNK Value unknown - not yet processed White Bad DEL Processing has been disabled Magenta Bad INVL Data concentrator error Magenta Bad RDER Data concentrator error Magenta Bad OIC Data concentrator error Magenta Bad BAD Outside instrument range Magenta Bad STAG Point failed stagnation check Magenta Bad UDEF Undefined (spare) Magenta Bad REDU Fails redundant point check Magenta Bad HALM Above high alarm limit Red Good LALM Below low alarm limit Red Good HWRN Above high warning limit Yellow Good LWRN Below low warning limit Yellow Good ALM State/Change-of-State alarm Red Good SUB Value has been substituted Blue Good DALM Alarm checking has been disabled Green Good NCAL Value cannot be calculated White Good INHB Alarm inhibited by cut-out point Green Good GOOD Passes all other checks Green Good 16.2 Not listed above is quality code OSUB (Operator Substituted), which is treated the same as SUB, and indicates that the value was substituted within that program. OSUB is not used in the CVT.

PROCEDURE 5.7.17 REVISION 29 PAGE 25 OF 32

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE

17. PMIS LOGIN 17.1 If the current date and time is displayed in the OCA and is being updated about once a second:

17.1.1 If"ENTER PASSWORD..." is displayed on line 2, press the ENTER key.

17.1.2 If"SELECT FUNC. KEY OR TURN ON CODE..." and an open IDE field is displayed on line 2, the IDT is logged into PMIS. No further action is necessary.

17.1.3 If a display is operating, press the CANC key.

17.1.4 If terminal does not respond or does not meet any of the above criteria, press the XOFF key once. The terminal should be automatically reset (screen clears and the bell sounds) after about 30 seconds, and either the "ENTER PASSWORD..." or

"...TURN-ON-CODE..." prompt should be displayed. Refer to the applicable previous step for more instruction.

17.2 If the current date and time is NOT displayed or is displayed but is not being updated:

17.2.1 Press the RESET key (PC keyboard) or CONTROL-RESET keys (IDT keyboard), wait at least 10 seconds, and press the ENTER key. If the date and time appear and began updating, refer to the previous (date and time updating) step.

17.2.2 If a "$" is displayed at the left of the screen, enter "LO" and press the ENTER key. After the "...LOGGED OFF..." message is displayed, press the ENTER key again.

17.2.3 After "Username:" is displayed, enter "PMIS" and press the ENTER key. A welcome message followed by "PMIS LOGGED OUT..." will be displayed. Do not press any keys for 5 minutes or until the PMIS login display appears. When the "ENTER PASSWORD..." prompt is issued, refer to the previous (date and time updating) step and login to PMIS.

17.3 If neither of the above criteria is met or the specified sequence of events does not occur, contact the Nuclear Information Services (NIS) Department for assistance.

I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 26 OF 32 j

ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE

18. ACTIVATING A TURN-ON-CODE 18.1 If a display is currently operating in the area of the screen that the desired TOC requires, press the CANC key.

18.2 When "SELECT FUNC. KEY OR TURN ON CODE..." is displayed followed by an open IDE field, enter one of following:

18.2.1 A TOC (i.e., "GROUP" -- activates the Group Display Program; the program will then prompt the user to select a menu option).

18.2.2 A TOC followed by a space and optional text (i.e., "PLOT ARMI" -

activates the Real-Time Plot Program and plots the group "ARMI" without further user input; note that optional text is recognized by only selected TOCs).

18.2.3 Press one of the programmable function keys on the right hand key pad or top row of function keys (i.e., blue "GROUP DISP" key -

functions the same as the first example).

18.3 Refer to the FKA for the function keys that are enabled and their descriptions.

Use other options as provided by each program.

18.4 To exit a program, use the specified exit option (if provided) or press the CANC function key.

19. DETERMINING TO WHICH SYSTEM A TERMINAL IS CONNECTED The PMIS System to which a terminal is connected is indicated by the "CONSOLE =..." on the bottom line of the FKA as follows:

CONSOLE = PRIMARY -- Connected to the Primary System operating in the Primary Mode.

CONSOLE = PRIM/BAC -- Connected to the Primary System operating in the Primary/Backup Mode.

CONSOLE = BACKUP -- Connected to the Backup System.

CONSOLE = UNKNOWN -- PMIS is in a transition or unknown state.

I PROCEDURE 5.7.17 REVISION 29 1 PAGE 27 OF 32 ]

I ATTACHMENT 6 PMIS SYSTEM ACCESS AND USE

20. SWITCHING A DEVICE TO THE OTHER SYSTEM 20.1 On a terminal located in the same area as the device to be switched and connected to either PMIS System, activate the TOC "SWITCH".

20.2 A list of all devices that can be switched from that terminal will be displayed.

Included will be their logical names, description, and the CPU to which the device is connected.

20.3 To switch a device, press function key F1 and then enter the logical name at the prompt.

20.4 If the device is an IDT, it will be logged off PMIS.

20.5 If the device being switched is a terminal other than the one running SWITCH, both are connected to the same system and a TOC is currently active, a message will be displayed to that effect, and the user will be asked if it is to be switched anyway. If the answer is not YES, the device is not switched.

I PROCEDURE 5.7.17 REVISION 29 1PAGE 28 OF 32

I ATTACHMENT 7 CORE DAMAGE ESTIMATION NOTE - This attachment is only used for core damage estimates where the in-containment radiation monitors are exposed to coolant or steam (i.e., only for primary containment LOCA situations). For other accidents sequences, utilize the Post-Accident Sampling System (PASS) and Core Damage Assessment Program (CORDAM).

(1) HIGHEST DRYWELL (3) CORE (5) PERCENT RAD MONITOR (2) 100% MELT (4) PERCENT CLAD READING CORE MELT FRACTION CORE MELT FAILURE (RMA-RM-40A,B) FACTOR (1) - (2) (3) x 100 (4) x 10 2.44E+6 Report the results of the core damage estimate (Blocks 4 and 5) to the TSC Director.

Name/Time/Date: / /

I PROCEDURE 5.7.17 REVISION 29 R 1 PAGE 29 OF 32

ATTACHMENT 8 INFORMATION SHEET

1. DISCUSSION 1.1 This procedure covers dose projection. Dose projection represents calculation of an accumulated dose at some time in the future if current conditions continue.

1.2 The CNS-DOSE Computer Program is a software application operated on the PMIS computers. It makes use of current meteorological and radiological data from PMIS and manually entered data to perform dose projection for the area surrounding CNS. CNS-DOSE is the primary method of dose projection.

1.2.1 The PMIS Computer System consists of two computers operating in a Primary and Backup Mode. Historical data may be obtained from either system; however, current data may be obtained only from the Primary System.

1.2.2 Personal unfamiliar with the operation of PMIS should reference procedures governing the operation of PMIS or refer to Attachment 6.

1.3 The manual dose projection methods in this procedure are intended to be used when CNS-DOSE is unavailable. Where possible, data used is from the same source as that used by the computer programs. The hand calculations are divided into two sections. Section 5 is intended to be used by the on-shift personnel for centerline dose projections. Section 6 is intended for dose assessment personnel in projecting non-centerline values.

1.4 The correlation methodology as described in Section 8 provides EOF dose assessment personnel with a means of correlating field team iodine concentration data with CNS-DOSE projected iodine concentration. Such a correlation is necessary to determine if initial Protective Action Recommendations (PARs) were adequate to protect the health and safety of the public.

1.5 Containment radiation level provides a measure of core damage, because it is an indication of the inventory of airborne fission products (i.e., noble gases, a fraction of the halogens, and a much smaller fraction of the particulates) released from the fuel to the containment (refer to NEDO-22215, Pages 1 and 2; NEDC 02-009).

I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 30 OF 32 J

I ATTACHMENT 8 INFORMATION SHEET

2. REFERENCES 2.1 CODES AND STANDARDS 2.1.1 NRC Regulatory Guide 1.109, Revision 1, October 1977, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, Iodine Inhalation Dose Factors.

2.1.2 NRC Regulatory Guide 1.111, July 1977, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.

2.1.3 NRC Regulatory Guide 1.145, August 1979, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants.

2.1.4 Health Physics Journal, November 1981, Noble Gas Dose Rate Conversion Factors.

2.1.5 ICRP 59, Working Breathing Rate.

2.1.6 EPA 400-R-92-001, May 1992, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.

2.2 DRAWINGS (MAPS) 2.2.1 NPPD Drawing CNS-MI-102, Atmospheric Dispersion Model (EPM2)

Special Receptor Points, 10 Mile Radius.

2.2.2 NPPD Drawing CNS-MI-03, Preselected Radiological Sampling and Monitoring Points in the Vicinity of Cooper Nuclear Station, 10 Mile Radius.

2.2.3 NPPD Drawing 2.2 (P3-A-45), Revision 1, Cooper Nuclear Station Site and Property Boundary, 1 Mile Radius.

2.2.4 Cooper Nuclear Station 50 Mile Emergency Planning Zone, Revision 2, 50 Mile Radius.

I PROCEDURE 5.7.17 1 REVISION 29 1 PAGE 31 OF 32 1

ATTACHMENT 8 INFORMATION SHEET 2.3 VENDOR MANUALS 2.3.1 CNS Number 0984, PMIS Operator's Manual - SAIC Document 502-85500107-72.

2.4 PROCEDURES 2.4.1 Emergency Plan Implementing Procedure 5.7.1, Emergency Classification.

2.4.2 Emergency Plan Implementing Procedure 5.7.16, Release Rate Determination.

2.4.3 Emergency Plan Implementing Procedure 5.7.20, Protective Action Recommendations.

2.5 MISCELLANEOUS 2.5.8 Engineering Evaluation EE 02-056, Elimination of Meteorological Instrumentation System Strip Chart Recorder References.

2.5.1 General Electric Corporation, NEDO-22215, Procedures for the Determination of the Extent of Core Damage Under Accident Conditions.

2.5.2 NEDC 02-004, Estimation of the Steam Jet Air Ejector Radiation Monitor, RMP-RM-150A(B), Readings Following a 1% Fuel Clad release (Degraded Core) in the Reactor Coolant System.

2.5.3 NEDC 02-009, Estimation of Primary Containment High Range Monitor, RMA-RM-40A(B), Readings Following 1% Clad Failure in the RCS under Non-LOCA Conditions.

2.5.4 NEDO-31400, Safety Evaluation for Eliminating the BWR MSIV Closure Function and Scram Function for the MSL Rad Monitors.

2.5.5 NRC Inspection Report 89-35.

2.5.6 © NRC Inspection Report 91-12, Emergency Preparedness Annual Inspection Report. Affects Section 7 and NOTE prior to Step 5.2.

2.5.7 NRC Inspection Report 92-14, Emergency Preparedness Annual Inspection Report.

PROCEDURE 5.7.17 1 REVISION 29 PAGE 32 OF 32

USE:

UE REFERENCE EEEC CNS OPERATIONSCNS OERATINS MANUAL ~EFFECTIVE: 1/15/03 EPIP PROCEDURE 5.7.20 APPROVAL SORC[0Q APPROVAL: SORC/IQA I

OWNER: J. A. BEDNAR PROTECTIVE ACTION RECOMMENDATIONS DERTMENT: EP DEPARTMENT: EP

1. PU RPOSE ............................................................ 1

2. PRECAUTIONS AND LIMITATIONS ..................................... 1

3. REQUIREM ENTS ...................................................... 1

4. PAR DETERMINATION ................................................ 2

5. MAKING THE PROTECTIVE ACTION RECOMMENDATION ................. 4 ATTACHMENT 1 AFFECTED SECTOR DETERMINATION ................ 5 ATTACHMENT 2 EPA 400 INFORMATION ............................. 6 ATTACHMENT 3 COOPER NUCLEAR STATION 10 MILE EMERGENCY PREPAREDNESS ZONE MAP ......................... 7 ATTACHMENT 4 INFORMATION SHEET .............................. 8

1. PURPOSE This procedure provides a basis for relating actual or projected dose or plant conditions to the EPA Protective Action Guides (PAGs) to determine the appropriate Protective Action Recommendations (PARs) to be made to the County or State governments.

2. PRECAUTIONS AND LIMITATIONS

[ ] 2.1 Conditions beyond the scope of this procedure may exist which, in the opinion of the Emergency Director, override the criteria contained in this procedure.

[] 2.2 Both plant conditions and off-site release of radioactive material are considered in the determination of PARs.

3. REQUIREMENTS

[ ] 3.1 PARs are warranted for the following:

[1 3.1.1 Projected Total Effective Dose Equivalent (TEDE) and Committed I Dose Equivalent (CDE) dose have been calculated per I Procedure 5.7.17 and exceed 0.1 REM TEDE or 0.5 REM CDE at or beyond the boundary of the Owner Controlled Area (OCA); or,

[] 3.1.2 A GENERAL EMERGENCY has been declared.

I PROCEDURE 5.7.20 1 REVISION 16 1 PAGE 1 OF 8

4. PAR DETERMINATION CAUTION 1 - The Emergency Director can not delegate the responsibility tor approving PARs.

CAUTION 2 - If determined that PARs are warranted or any changes to PARs are warranted, notification to State and County governmental agencies shall be made within 15 minutes per Procedure 5.7.6.

[ NOTE - The Radiological Control Manager and EOF Director assist and advise the Emergency Director in formulation of the appropriate PAR.

[ 4.1 The Emergency Director shall perform the following in determination of PARs:

[ ] 4.1.1 DETERMINE PARs based on available information from plant conditions and off-site dose estimates.

4.1.1.1 If a release greater than ODAM release limits has occurred or is occurring, perform the following:

[ a. Direct that off-site dose estimates per Procedure 5.7.17 be calculated and results promptly provided to the Emergency Director.

[ ] b. Consider results of off-site dose estimates in determining PARs.

4.1.1.2 If emergency classification is GENERAL EMERGENCY and off-site dose estimates are not available, perform the following:

S] a. Issue PARs to States/Counties based on available plant condition information.

II b. Provide follow up off-site dose estimates and any changes in PARs to States/Counties promptly following receipt of information per Procedure 5.7.6.

[1 4.1.2 If CNS DOSE is available, use CNS DOSE PARs and go to Step 4.1.4.

I PROCEDURE 5.7.20 1 REVISION 16 1 PAGE 2 OF 8 1

[1] 4.1.3 If CNS DOSE is not available, DETERMINE most restrictive PAR based on plant conditions and off-site dose estimates using table below:

0-2 MILES 2-5 MILES 5-10 MILES GENERAL ALL SECTORS AFFECTED SECTORS ALL SECTORS "GO EMERGENCY "EVACUATE" "EVACUATE" INDOORS AND (MINIMUM) REMAINING MONITOR EAS" SECTORS "GO INDOORS AND MONITOR EAS" OFF-SITE DOSE 0-2 MILES 2-5 MILES 5-10 MILES ESTIMATES TEDE J.1 REM = "NONE" : .1 REM = "NONE" !<.1 REM = "NONE"

> .1 REM BUT > .1 REM BUT > .1 REM BUT

<IREM=ALL <I REM=ALL <IREM=ALL SECTORS "GO SECTORS 0-2 MILES SECTORS 0-2 MILES, INDOORS AND AND AFFECTED AFFECTED SECTORS MONITOR EAS" SECTORS 2-5 MILES 2-5 MILES AND "GO INDOORS AND 5-10 MILES MONITOR EAS" "GO INDOORS AND MONITOR EAS" 1REM= ALL I REM= Ž 1REM=

SECTORS AFFECTED SECTORS AFFECTED SECTORS "EVACUATE" "EVACUATE" "EVACUATE" CDE < .5 REM = "NONE" <-.5 REM = "NONE" :< .5 REM = "NONE" I

> .5 REM BUT > .5 REM BUT > .5 REM BUT

< 5 REM = ALL < 5 REM = ALL < 5 REM = ALL SECTORS "GO SECTORS 0-2 MILES SECTORS 0-2 MILES, INDOORS AND AND AFFECTED AFFECTED SECTORS MONITOR EAS" SECTORS 2-5 MILES 2-5 MILES AND "GO INDOORS AND 5-10 MILES MONITOR EAS" "GO INDOORS AND MONITOR EAS" 5 REM = ALL 51REM= Ž5 REM=

SECTORS AFFECTED SECTORS AFFECTED SECTORS "EVACUATE" "EVACUATE" "EVACUATE" 4.1.4 If dose at 10 miles is projected to meet or exceed 1 REM TEDE or 5 REM CDE, perform the following:

4.1.4.1 Include in the remarks section of the CNS Notification Report Form (Procedure 5.7.6) that "Projected Dose at or beyond 10 miles exceed evacuation criteria".

4.1.4.2 Assist State/Counties in determining affected areas beyond 10 miles to be evacuated.

I PROCEDURE 5.7.20 1 REVISION 16 1 PAGE 3 OF 8 1

[ ] 4.1.5 Ensure correct PARs are written on CNS Notification Report Form (Procedure 5.7.6) for States/Counties.

I I] 4.1.5.1 If CNS DOSE not available, determine affected sectors using Attachment 1.

[ ] 4.1.6 Approve PARs by signing CNS Notification Report Form (Procedure 5.7.6).

I [ ] 4.1.7 Verify notifications are performed to States/Counties within 15 minutes of the approval of PARs.

5. MAKING THE PROTECTIVE ACTION RECOMMENDATION

[ ] 5.1 If State, Federal, or Local dose assessment personnel are present in the EOF and are conducting independent dose assessments, these personnel MAY be consulted or their results reviewed in the process of making a PAR.

[ ] 5.2 If Nebraska and Missouri State Representatives are present in the EOF, official communication of the PAR will be made to these individuals. The Emergency Director will make the PAR to these authorities verbally and JI should provide written information concurrently via the Cooper Nuclear Station Notification Report (Attachment 3 of Procedure 5.7.6).

I [ ]5.3 If Nebraska and Missouri State Representatives are not present in the EOF, I official communication of the PAR is via the Cooper Nuclear Station Notification Report (Attachment 3 of Procedure 5.7.6). The Emergency Director will ensure the person making off-site notifications is immediately notified of the PAR for inclusion on the Off-Site Notification Form.

I PROCEDURE 5.7.20 1 REVISION 16 1 PAGE 4 OF 8 1

I ATTACHMENT 1 AFFECTED SECTOR DETERMINATION

1. Determine the affected sectors using the chart below and the following:

[ 1.1.1 Wind speed and direction can be obtained from PMIS (primary), meteorological instrumentation in the Control Room (1st alternate), or National Weather Service (backup).

[1 1.1.1.1 Fifteen minute average should be used.

1] 1.1.1.2 If National Weather Service is used, obtain 15 minute average data, if available, or 15 previous 1 minute readings.

1 1.1.2 If the wind direction is > 3600, the wind direction is determined by subtracting 3600 from the indicated number. Wind direction should be rounded to the nearest whole number.

[ ] 1.1.3 Wind direction is always given as "wind from" (an easterly wind, or wind direction 90°,

means that the wind is blowing from east to west).

1 1.1.4 When determining the sectors affected, the adjacent sectors on both sides of the actual downwind sector are included. Three sectors will typically be listed.

l [ 1.1.5 The below table is designed to add an additional sector if the wind direction is within 30 of a sector edge.

[ 3 1.1.6 If wind shift is observed following an initial PAR issue, then add affected sectors from wind shift to existinglinitial PAR sectors. (Do not delete sectors.)

1 1.1.7 Determine the affected sectors from the below table.

WIND FROM SECTORS WIND FROM SECTORS WIND FROM SECTORS 0 AFFECTED 0 AFFECTED 0 AFFECTED 351 to 9 H, J, K 126 to 144 P, Q, R 261 to 279 D, E, F 10 to 13 H, J, K, L 145 to 148 P,Q,R,A 280 to 283 D, E, F, G 14 to 31 J, K, L 149 to 166 Q, R, A 284 to 301 E, F, G 32 to 35 J, K, L, M 167 to 170 Q, R, A, B 302 to 305 E, F, G, H 36 to 54 K, L, M 171 to 189 R, A, B 306 to 324 F, G, H 55 to 58 K, L, M, N 190 to 193 R, A, B, C 325 to 328 F, G, H, J 59 to 76 L, M, N 194 to 211 A, B, C 329 to 346 G, H,J 77 to 80 L, M, N, P 212 to 215 A, B, C, D 347 to 350 G, H, J, K 81 to 99 M, N, P 216 to 234 B, C, D 100 to 103 M, N, P, Q 235 to 238 B, C, D, E There is no 0 Sector 104 to 121 N, P, Q 239 to 256 C, D, E 122 to 125 N, P, Q, R 257 to 260 C, E, D, F There is no I Sector I PROCEDURE 5.7.20 1 REVISION 16 1 PAGE 5 OF88

I ATTACHMENT 2 EPA 400 INFORMATION EPA 400 PROTECTIVE ACTION GUIDES (PAGs)

FOR THE EARLY PHASE OF A NUCLEAR INCIDENT PROTECTIVE PROJECTED DOSE (PAG)

ACTION COMMENTS Evacuation 1 rem TEDE rem" Evacuation or, for some situations, or sheltering"' should normally be 5 rem CDE initiated at 1 rem. Further guidance is provided in Section 2.3.1 of EPA 400.

Sheltering (i.e., "Go indoors and monitor EBS") may be the preferred protective action when it will provide protection equal to or greater than evacuation, based on consideration of factors, such as, source term characteristics, and temporal or other site-specific conditions (refer to Section 2.3.1 of EPA 400).

The sum of the effective dose equivalent resulting from exposure to external sources and the committed effective dose equivalent (CDE) incurred from all significant inhalation pathways during the early phase. Committed dose equivalents to the thyroid and to the skin may be 5 and 50 times larger, respectively.

I 3 Evacuation will be recommended by NPPD for areas with projected TEDE dose of

> 1 rem or CDE dose of > 5 rem.

Go indoors and monitor EAS/EBS can be recommended by NPPD for areas with projected dose > 0.1 rem TEDE, but < 1.0 rem TEDE or > 0.5 rem CDE, but < 5 rem CDE thyroid.

I PROCEDURE 5.7.20 REVISION 16 PAGE 6 OF 8

I 3 COOPER NUCLEAR PREPAREDNESS STATION ZONE SATTACHMENT MAP 10 MILE EMERGENCY I J ri huh" Figure 1 I PROCEDURE 5.7.20 1 REVISION 16 PAGE 7 OF88

I ATTACHMENT 4 INFORMATION SHEET

1. DISCUSSION 1.1 Dose estimates are calculated according to the dose assessment methodology described in Procedure 5.7.17. These dose estimates are referred to as projected dose. A protective action is an action taken to avoid or reduce a projected dose when the benefits derived from such action are sufficient to offset any undesirable features of the protective action.

1.2 Protective action recommendations are automatic at a GENERAL EMERGENCY and may be warranted at lesser classifications due to off-site dose estimates.

2. REFERENCES 2.1 CODES AND STANDARDS 2.1.1 Environmental Protection Agency EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, May 1992.

2.1.2 NPPD Emergency Plan for CNS.

2.1.3 NUREG BR-0150, Volume 1, Revision 1.

2.1.4 NUREG 0654/FEMA-REP-1, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

2.1.5 Reactor Safety Study, Appendix VI, WASH 1400, October 1975.

2.2 PROCEDURES 2.2.1 Emergency Plan Implementing Procedure 5.7.6, Notification.

2.2.2 Emergency Plan Implementing Procedure 5.7.17, Dose Assessment.

2.3 MISCELLANEOUS 2.3.1 Evacuation Time Estimates for Nebraska and Missouri.

2.3.2 RCR 2002-0260, Action 2.

2.3.3 RCR 2001-0181, Action 3.

PROCEDURE 5.7.20 1 REVISION 16 PAGE 8 OF 8

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