Text

Revisions to Emergency Plan Implementing Procedures
	ML031960476
Person / Time
Site:	North Anna
Issue date:	07/03/2003
From:	Heacock D; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	03-395
	Download: ML031960476 (152)
	v • d • e

{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 3, 2003 U.S. Nuclear Regulatory Commission Serial No. 03-395 Attention: Document Control Desk NAPS/MPW Washington, D.C. 20555 Docket Nos. 50-338/339 License Nos. NPF-4/7 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 REVISIONS TO EMERGENCY PLAN IMPLEMENTING PROCEDURES Pursuant to 10 CFR 50.54(q), enclosed are recent revisions to the North Anna Power Station Emergency Plan Implementing Procedures. These revisions do not implement actions that decrease the effectiveness of our Emergency Plan. The Emergency Plan and Implementing Procedures continue to meet the standards of 10 CFR 50.47(b). Please update your manual by performing the actions described in Attachment 1, Tabulation of Changes. Very truly yours,

    / D,!.Heacock L/te      Vice President Commitments Stated or Implied: None.

Enclosures cc: U.S. Nuclear Regulatory Commission (2 copies) Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 Mr. M. J. Morgan NRC Senior Resident Inspector North Anna Power Station

ATTACHMENT I TABULATION OF CHANGES VIRGINIA ELECTRIC AND POWER COMPANY REVISIONS TO NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES Enclosed are recent revisions to the North Anna Power Station Emergency Plan Implementing Procedures (EPIPs). Please take the following actions in order to keep your manual updated. REMOVE AND DESTROY DATED INSERT EFFECTIVE DATE EPIP - 1.01, Rev. 37 12/18/02 EPIP - 1.01, Rev. 38 07/01/03 EPIP - 4.01, Rev. 19 04/08/03 EPIP - 4.01, Rev. 20 07/01/03 EPIP -4.02, Rev. 14 05/12/03 EPIP -4.02, Rev. 15 07/01/03 EPIP-4.09, Rev. 13 06/19/02 EPIP-4.09, Rev. 14 07/01/03 EPIP -4.22, Rev. 13 04/02/93 Delete Delete EPIP - 4.23, Rev. 14 04/09/02 Delete Delete EPIP - 4.25, Rev. 8 07/23/93 Delete Delete EPIP -4.26, Rev. 11 09/13/01 EPIP -4.26, Rev. 12 07/01/03 EPIP - 4.35, Rev. 0 07/01/03 EPIP - 5.07, Rev. 11 08/02/00 EPIP - 5.07, Rev. 12 07/01/03 Emergencv Plan Privacy and Proprietarv Material has been removed. Reference Generic Letter No. 81-27.

. D p 4. r 03-06-30 ( NORTH ANNA POWER TAT1CU LIST OF NAPS EMERGENCY PLAN IPLEHENlATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION APPROVAL EFFECT* DOCUMENT NUMBER REV **DATE** **DATE** DOCUMENT TITLE EPIP-l.0l 038 06/24/03 07/01/03 EMERGENCY ANAGER CONTROLLING PROCEDURE EPIP-1.0Z 011 09/07/99 10/01/99 RESPONSE TO NOTIFICATION OF UNUSUAL EVENT EPIP-1.03 014 09/07/99 10/01/99 RESPONSE TO ALERT EPIP-1.04 014 09/07/99 10/01/99 RESPONSE TO SITE AREA EMERGENCY EPIP-1.05 016 09/07/99 10/01/99 RESPONSE TO GENERAL EMERGENCY EPIP-1.06 004 09/05/01 09/oso/1 PROTECTIVE ACTION RECOMMENDATIONS EPIP-2.01 02s 08/13/02 08/28/02 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS EPIP-2.02 01s 08/13/02 08/28/02 NOTIFICATION OF NRC EPIP-3.02 021 03/04/03 03/17/03 ACTIVATION OF TECHNICAL SUPPORT CENTER EPIP-3.03 013 03/04/03 03/17/03 ACTIVATION OF OPERATIONAL SUPPORT CENTER EPIP-3. 04 01s 07/14/98 07/20/98 ACTIVATION OF LOCAL EMERGENCY OPERATIONS FACILITY EPIP-3.05 002 04/02/03 04/08/03 AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION EPIP-4.01 020 06/24/03 07/01/03 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE EPIP-4.02 - 01s 06/24/03 07/01/03 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE EPXP-4.03 011 12/20/93 01/01/9' DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE EPIP-4.04 009 11/21/94 11/28/9' EMERGENCY PERSONNEL RADIATION EXPOSURE EPIP-4.05 009 01/28/00 e2/e4/00 RESPIRATORY PROTECTION AND KI ASSESSMENT EPZP-4.06 009 12/21/95 12/28/95 PERSONNEL MONITORING AND DECONTAMINATION EPIP-4.07 014 09/29/00 10/06/00 PROTECTIVE EASURES EPIP-4.08 014 0S/10/02 06/19/02 INITIAL OFFSITE RELEASE ASSESSMENT EPIP-4.09 014 06/24/03 07/01/03 SOURCE TERM ASSESSMENT EPIP-4.10 011 08/13/02 08/28/02 DETERnINA)ION OF X/Q EPIP-4.13 009 09/29/00 10/06/00 OFFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA

D PA~ 2003-06-30 2 NORTH ANNA POWER STATION ( ( LIST OF NAPS EHERGENCY LAN IMPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION APPROVAL EFFECT** DOCUMENT NUMBER REV *DATE** **DATE** DOCUMENT TITLE EPIP-4.14 007 12/20/93 01/01/94 INPLANT MONITORING EPIP-4.15 o1l 02/18/00 02/28/00 ONSITE ONITORING EPIP-4.16 01S 12/13/02 12/18/02 OFFSITE MONITORING EPIP-4.17 016 12/13/02 12/18/02 MONITORING OF EMERGENCY RESPONSE FACILITIES EPIP-4.18 013 12/13/02 12/18/02 MONITORING OF LEOF EPIP-4.21 008 12/20/93 01/01/94 EVACUATION AND REMOTE ASSEMBLY AREA MONITORING EPIP-4.22 014 04/05/02 04/09/02 POST ACCIDENT SAMPLING OF CONTAINMENT AIR EPIP-4.23 014 04/05/62 04/09/02 POST ACCIDENT SAMPLING OF REACTOR COOLANT EPIP-4.24 013 04/02/03 04/08/03 GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY EPIP-4.25 008 07/23/93 07/23/93 LIQUID EFFLUENT SAMPLING DURING AN EERGENCY EPIP-4.26 012 06/24/03 07/01/03 HIGH LEVEL ACTIVITY SAMPLE ANALYSIS EPIP-4.28 007 01/09/97 01/14/97 TSC/LEOF RADIATION MONITORING SYSTEM EPIP-4.30 085 04/05/02 04/09/02 USE OF MIDAS CLASS A ODEL EPIP-4.31

003 06/20/94 06/20/94 USE OF MIDAS CLASS B MODEL EPIP-4.33 003 11/28/00 11/30/00 HEALTH PHYSICS NETWORK COMMUNICATIONS EPIP-4.34 003 12/13/02 12/18/02 FIELD TEAM RADIO OPERATOR INSTRUCTIONS EPIP-4.35 000 06/24/03 67/01/03 CHEMISTRY SAMPLING EPIP-5.01 11 12/11/96 12/17/96 TRANSPORTATION OF CONTAMINATED INJURED PERSONNEL EPIP-5.03 016 02/18/00 02/28/00 PERSONNEL ACCOUNTABILITY EPIP-5.04 010 03/04/03 03/17/03 ACCESS CONTROL EPIP-5.0s 013 06/25/96 07/02/96 SITE EVACUATION EPIP-S.07 012 06/24/03 07/01/03 ADMINISTRATION OF RADIOPROTECTIVE DRUGS EPIP-5. 08 008 04/02/03 04/08/03 DAMAGE CONTROL GUIDELINE

ok O PA., 2003O0 3 30 ( NORTH ANNA POWER STATION (. LIST O NAPS EMERGENCY PLAN IPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT IN=DRMATION APPROVAL EFFECT** DOCUMENT NUMBER REV **DATE** **DATE** DOCUMENT TITLE EPIP-5.09 004 08/02/02 08/15/02 SECURITY TEAM LEADER CONTROLLING PROCEDURE EPIP-6.01 007 05/12/99 05/17/99 RE-ENTRY/RECOVERY GUIDELINE

VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 (With 3 Attachments) PAGE I of 7 PURPOSE To assess potential emergency conditions and initiate corrective actions. LEVEL 2 DISTRIBl p 0 j Ths Document'o Should nd Afntated Bt verlf'ed A ConrroIlled Source As Req ulred to pertomir Worx ENTRY CONDITIONS Any of the following:

1. Another station procedure directs initiation of this procedure.

2. A potential emergency condition is reported to the Shift Manager. I Approvals on File Effective Date I l

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 PAGE L ~~~~~~~~~~~~~~~~~~~~2 of 7 -AHJ D-ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Declaration of the highest emergency class for which an Emergency Action Level is exceeded shall be made. NOTE: The PCS is potentially unreliable in the event of an earthquake. Therefore, PCS parameters should be evaluated for accuracy should this situation occur. _____1 EVALUATE EMERGENCY ACTION LEVELS: a) Determine event category using Attachment 1. EMERGENCY ACTION LEVEL TABLE INDEX b) Review EAL Tab associated with event category c) Use Control Room monitors, PCS. and outside reports to get indications of emergency conditions listed in the EAL Table d) Verify EAL - CURRENTLY EXCEEDED d) IF basis for EAL no longer exists when discovered AND no other reasons exist for an emergency declaration, THEN do the following:

RETURN TO procedure in effect.
GO TO VPAP-2802, NOTIFICATIONS AND REPORTS, to make one-hour, non-emergency reports for classification without declaration.

I IF EAL was NOT exceeded. THEN RETURN TO procedure in effect. (STEP 1 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 PAGE L- ~~~~~~~~~~~~~~~~~~ of 7 1-n -Gi ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED F-1 EVALUATE EMERGENCY ACTION LEVELS: (Continued) e) Record procedure initiation:

By:

Date: Time: f) Initiate a chronological log of events g) Declare position of Station Emergency Manager NOTE: Assembly, accountability and/or initiation of facility staffing may not be desired during certain situations (e.g., security event. severe weather, anticipated grid disturbance) or may have already been completed. These activities should be implemented as quickly as achievable given the specific situation. _____2 CHECK - CONDITIONS ALLOW FOR IF deviation from normal emergency NORMAL IMPLEMENTATION OF EMERGENCY response actions warranted, THEN RESPONSE ACTIONS do the following: a) Refer to Attachment 3, Considerations for Operations Response Under Abnormal Conditions. b) Consider applicability of 50.54(x). c) IF classification/assembly announcement deferred, THEN GO TO Step 4.

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 PAGE 4 of 7 l~ -AEH ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED 4- _____3 NOTIFY PLANT STAFF OF ALERT OR HIGHER CLASSIFICATION: a) Check classification - ALERT OR a) GO TO Step 4. HIGHER b) Check if emergency assembly and b) Do the following: accountability - PREVIOUSLY CONDUCTED 1) Have Control Room sound EMERGENCY alarm and make announcement on station Gai-Tronics system as follows:

                                                         "(Emergency classification) has been declared as the result of (event)
                                                         "All Emergency Response personnel report to your assigned stations" "All contractor personnel not responding to the emergency and all visitors report to the Security Building" "All other personnel report to your Emergency Assembly Areas"

2) Repeat RNO Step 3.b.1.

3) GO TO Step 4.

c) Have Control Room sound EMERGENCY alarm and make announcement on station Gai-CTronics system as follows:

             "(Emergency classification) has been declared as the result of (event) d) Repeat Step 3.c 7

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 PAGE L- ~~~~~~~~~~~~~~~~~~ of 7 -1EEi-ACTION/EXPECTED RESPONSE F-l RESPONSE NOT OBTAINED -

      *   * * *  * * *  *  * *  * * * * * *  *

a * *
a *
a a * *
a a *
a a * *
CAUTION: Continue through this and all further instructions unless otherwise directed to hold.
a a a a a *
a a a a
a a a a a *
a a a a *
a a a a a a a a a a a a a

_____4 INITIATE SUPPORTING PROCEDURES: a) Direct Emergency Communicators to initiate the following procedures:

1) EPIP-2.01, NOTIFICATION OF STATE AND LOCAL GOVERNMENTS

2) EPIP-2.02, NOTIFICATION OF NRC b) Direct HP to initiate EPIP-4.01, RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE c) Establish communications with Security Team Leader:

1) Provide Security with current emergency classification

2) Notify Security which Operations Shift is designated for coverage

3) Direct Security to initiate EPIP-5.09, SECURITY TEAM LEADER CONTROLLING PROCEDURE

NUMBER PROCEDURE TITLE EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE ACTION/EXPECTED RESPONSE l l RESPONSE NOT OBTAINED. _____ 5 CHECK TSC - ACTIVATED IF TSC NOT activated, THEN do the following: a) Have STA report to the Control Room. b) Notify Manager Nuclear Operations or Operations Manager On Call. c) Consider having Radiological Assessment Director report to the Control Room. d) WHEN relief SEM arrives, THEN perform turnover using EPIP-1.01, Attachment 2, Turnover Checklist. _____6 IMPLEMENT EPIP FOR EMERGENCY CLASSIFICATION IN EFFECT:

Notification of Unusual Event -

GO TO EPIP-1.02, RESPONSE TO NOTIFICATION OF UNUSUAL EVENT

Alert -

GO TO EPIP-1.03, RESPONSE TO ALERT

Site Area Emergency -

GO TO EPIP-1.04, RESPONSE TO SITE AREA EMERGENCY

General Emergency -

GO TO EPIP-1.05, RESPONSE TO GENERAL EMERGENCY

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 PAGE L__ ~~~~~~~~~~~~~~~~~~ of 7 EiH H-H H-ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _____7 NOTIFY OFFSITE AUTHORITIES OF EMERGENCY TERMINATION: a) State and local governments (made by LEOF or CEOF when activated) b) NRC _____8 NOTIFY STATION PERSONNEL ABOUT THE FOLLOWING:

Emergency termination
Facility de-activation
Selective release of personnel
Completion and collection of procedures
Recovery

_____9 TERMINATE EPIP-1.01:

Give completed EPIPs, forms and other applicable records to Nuclear Emergency Preparedness (TSC Emergency Procedures Coordinator if TSC activated)
Completed By:

Date: Time:

                                          -END -

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT PAGE L-1I ~ ~~~~~~~INDEX 1o CAUTION:

Declaration of the highest emergency class for which an EAL is exceeded shall be made.
Emergency Action Levels shall be conservatively classified based on actual or anticipated plant conditions.

EVENT CATEGORY: TAB

1. Safety, Shutdown, or Assessment System Event ...................... A

2. Reactor Coolant System Event ...................................... B

3. Fuel Failure or Fuel Handling Accident ............................ C

4. Containment Event ................................................ D

5. Radioactivity Event ............................................... E

6. DELETED

7. Loss of Secondary Coolant ......................................... G

8. Electrical Failure ................................................ H

9. Fire ................................................ I

10. Security Event ................................................ J

11. Hazard to Station Operation ....................................... K

12. Natural Events ................................................ L

13. Miscellaneous Abnormal Events ..................................... M fI

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38. ATTACHMENT (TAB A) PAGE SAFETY, SHUTDOWN, OR ASSESSMENT 1 SYSTEM EVENT 2 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION CAUTION: EAL C.2 is duplicated below for cross-reference/comparison to EAL A.1: C.2. Probable large Loss of Main Feedwater GENERAL radioactivity System, Condensate System EMERGENCY release initiated and Auxiliary Feedwater by loss of heat System sink leading to core degradation MODES 1, 2. 3 & 4

1. Loss of function

Total loss of the SITE AREA needed for unit HSD Charging/SI System EMERGENCY condition OR MODES 1. 2 3 & 4 Total loss of the Main Feedwater and Auxiliary Feedwater systems

2. Failure of the

Reactor trip setpoint and SITE AREA Reactor Protection coincidences - EXCEEDED EMERGENCY System to initiate and complete a AND required trip while at power . Automatic trip from RPS -

FAILED MODES 1 & 2 AND

Manual trip from Control Room - FAILED

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB A) PAGE SAFETY. SHUTDOWN. OR ASSESSMENT PG 1 SYSTEM EVENT 3f42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION-

3. Inability to monitor

Most (>75%) or all SITE AREA a significant annunciator alarms on EMERGENCY transient in panels "A' to "K" - NOT progress AVAILABLE MODES 1, 2 3 & 4 AND
All computer monitoring capability (e.g.. PCS)

                                       - NOT AVAILABLE AND

Significant transient - IN PROGRESS (e.g., reactor trip, SI actuation, turbine run back >25% thermal reactor power, thermal power oscillations >10%)

AND

Inability to directly monitor any one of the following using Control Room indications:
Subcriticality
Core Cooling
Heat Sink
Vessel Integrity
Containment Integrity

4. Evacuation of Main Evacuation of the Control Room SITE AREA Control Room with with local shutdown control not EMERGENCY control not established within 15 minutes established within 15 minutes ALL MODES I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB A) PG SAFETY. SHUTDOWN, OR ASSESSMENT PAGE 1 SYSTEM EVENT l _____________ 4 of _42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

5. Total loss of

Secondary system cooling ALERT function needed for capability - UNAVAILABLE unit CSD condition AND MODES 5 & 6
Loss of any of the following systems:
Service Water
Component Cooling
RHR AND
RCS temperature GREATER THAN 140 F

6. Failure of the

Reactor trip setpoint and ALERT Reactor Protection coincidences - EXCEEDED System to complete a trip which takes the AND Reactor Subcritical
Automatic trip from RPS -

MODES 1 & 2 FAILED AND

Manual trip - REOUIRED AND
Manual trip from Control Room - SUCCESSFUL I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB A) PAGE SAFETY, SHUTDOWN. OR ASSESSMENT PG 1 SYSTEM EVENT ______________~~~~~~~~~~~~~ S of _42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

7. Unplanned loss of

Unplanned loss of most ALERT safety system (>75%) or all annunciator annunciators with alarms on panels A" to "K" compensatory for GREATER THAN 15 minutes indicators unavailable or a AND transient in progress
All computer monitoring capability (e.g., PCS)

MODES 1 2 3 & 4 - NOT AVAILABLE OR Significant transient - INITIATED OR IN PROGRESS (e.g.. reactor trip. SI, turbine runback > 25% thermal reactor power, thermal power oscillations

                                                   > 10%)

8. Evacuation of Main Evacuation of the Control Room ALERT Control Room with shutdown control required established within 15 minutes ALL MODES

9. Inability to reach

Intentional reduction in NOTIFICATION required mode within power. load or temperature OF UNUSUAL technical IAW T.S. Action Statement - EVENT specification limits HAS COMMENCED MODES 1, 2, 3 & 4 AND
T.S. Action Statement time limit for mode change -

CANNOT BE MET

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB A) PG SAFETY. SHUTDOWN, OR ASSESSMENT PAGE 1 SYSTEM EVENT _____________~~~~~~~~~~~~~~~ 6 of _42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION .

10. Failure of a safety RCS NOTIFICATION or relief valve to OF UNUSUAL close after pressure

RCS pressure - LESS EVENT reduction, which may THAN 2000 psig affect the health and safety of the public NDT Protection System -

MODES 1. 2 3. 4 & 5 IN SERVICE AND

Any indication after lift or actuation that Pressurizer Safety or PORV - REMAINS OPEN AND
Flow - UNISOLABLE
Main Steam
Excessive Steam Generator Safety, PORV or Decay Heat Release flow as indicated by rapid RCS cooldown rate AND
Main Steam pressure greater than 100 psi below setpoint of affected valve

11. Unplanned loss of

Unplanned loss of most NOTIFICATION most or all safety (>75%) or all annunciators OF UNUSUAL system annunciators on panels "A" to K" for EVENT for greater than 15 GREATER THAN 15 minutes minutes MODES 1, 2. 3 & 4 I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.O1 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB A) PG SAFETY. SHUTDOWN, OR ASSESSMENT PAGE 1 SYSTEM EVENT l _ _ _ __ _ _ 7 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

12. Loss of

Station PBX phone system - NOTIFICATION communications FAILED OF UNUSUAL capability EVENT AND ALL MODES
Station Gai-tronics system - FAILED AND
Station UHF radio system -

FAILED 4I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB B) PAGE REACTOR COOLANT SYSTEM EVENT PAGE 1 ____________ 8 of_42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Loss of 2 of 3 Any two of a), b) or c) exist GENERAL fission product and the third is imminent: EMERGENCY barriers with potential loss of a) Fuel clad integrity failure 3rd barrier as indicated by any of the following:

ALL MODES RCS specific activity greater than or equal to 300.0 pCi/gram dose equivalent I-131 OR 5 or more core exit thermocouples greater than 1200 F OR Containment High Range Radiation Monitor RM-RMS-165. -166 or RM-RMS-265, -266 GREATER 2 THAN 1.88x10 R/hr b) Loss of RCS integrity as indicated by any of the following:

                                       . RCS pressure greater than 2735 psig OR Loss of Reactor Coolant in progress c)   Loss of containment integrity as indicated by any of the following:

Containment pressure greater than 60 psia and not decreasing OR Release path to environment -EXISTS

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB B) PG ATTACHMENT REACTOR COOLANT SYSTEM EVENT PAGE 1 _____________ ~~~~~~~ of_42~~~~~9 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

2. Fuel failure with Any two of a), b) or c) exist and the GENERAL steam generator third is imminent: EMERGENCY tube rupture a) Fuel clad integrity failure as ALL MODES indicated by any of the following:

                                   . RCS specific activity greater than 300 pCi/gram dose equivalent I-131 OR 5 or more core exit thermocouples GREATER THAN 1200 F OR High Range Letdown radiation monitor 1-CH-RI-128 or 2-CH-Ri-228 GREATER THAN 5.9 x 104 mR/hr b) Steam Generator tube rupture as indicated by both of the following:

SI coincidence - SATISFIED AND
Steam Generator tube rupture -IN PROGRESS c) Loss of secondary integrity associated with ruptured steam generator pathway as indicated by any of the following:
Steam Generator PORV - OPEN OR Main Steam Code Safety Valve - OPEN OR Loss of secondary coolant outside containment - IN PROGRESS

ATTACHMENT TITLE REVISION EMERGENCY ACTION LEVEL TABLE 38 (TAB B) PG REACTOR COOLANT SYSTEM EVENT 10 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. RCS leak rate exceeds

Primary system leak (LOCA) SITE AREA makeup capacity - IN PROGRESS EMERGENCY MODES 1 2 3. & 4 AND
Safety Injection - REQUIRED AND
RCS subcooling based on Core Exit Thermocouples -

LESS THAN 300 F RCS inventory cannot be maintained based on pressurizer level or RVLIS indication

4. Gross primary to

Steam Generator Tube SITE AREA secondary leakage Rupture - IN PROGRESS EMERGENCY with loss of offsite power AND MODES 1, 2 3, & 4
Safety Injection - REQUIRED AND
Vent Vent A MGPI Monitor I RM-VG-179 GREATER THAN 1.25 x 108 pCi/sec OR Steam Generator Blowdown monitor on affected pathway RM-SS-122, -222 RM-SS-123, -223 RM-SS-124, -224 GREATER THAN 1x106 cpm AND
A subsequent loss of offsite power indicated by zero voltis on voltmeters for 4160V buses D, E. & F

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 L~~~ ATTACHMENT II ~~REACTOR (TAB B) COOLANT SYSTEM EVENT PAGE PAGEf CONDITION/APPLICABILITY INDICATION CLASSIFICATION

5. RCS leak rate limit

Pressurizer level cannot be ALERT

        - EXCEEDED                    maintained greater than 20%

with one (1) Charging/SI MODES 1 2, 3 & 4 pump in operation AND

RCS inventory balance indicates leakage - greater than 50 gpm

6. Gross primary to Steam Generator Tube Rupture - ALERT secondary leakage IN PROGRESS MODES 1, 2, 3. & 4 AND Safety Injection - REQUIRED

7. Excessive primary to

Intentional reduction in ALERT secondary eakage power. load or temperature with loss of offsite IAW T.S. 3.4.13 primary-power to-secondary leakage LCO Action Statement MODES 1 2. 3. & 4 AND
Vent Vent A MGPI Monitor

[ RM-VG-179 GREATER THAN 1.73 x 106 Ci/sec OR Steam Generator Blowdown monitor on affected pathway RM-SS-122, -222 RM-SS-123, -223 RM-SS-124. -224 GREATER THAN lxID 5 cpm AND

A subsequent loss of offsite power indicated by zero volts on voltmeters for 4160V buses D. E. & F

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB B) PAGE

ATTACHMENT REACTOR COOLANT SYSTEM EVENT PAGE 1

__ ___ ___ 12 of_42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

8. RCS operational Intentional reduction in power NOTIFICATION leakage requiring load or temperature IAW T.S. OF UNUSUAL plant shutdown 3.4.13 leakage limit action EVENT IAW T.S. 3.4.13 statement - HAS COMMENCED MODES 1, 2 3. & 4 l

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 L-1 ATTACHMENT

                      ~    ~~~FUEL (TAB C)CI FAILURE OR FUEL HANDLING ACCIDENT E

PAGE4Z CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Probable large

Loss of reactor coolant in GENERAL radioactivity progress EMERGENCY release initiated by LOCA with ECCS AND failure leading to core degradation
RCS specific activity -

greater than 300 PCi/gram ALL MODES dose equivalent I-131 OR Containment High Range Radiation Monitor RM-RMS-165. -166 or RM-RMS-265. -266 GREATER THAN 1.88x10 2 Rhr AND

High or low head ECCS flow not being delivered to the core (if expected by plant conditions)

CAUTION: EAL A.1 is duplicated below for cross-reference/comparison to EAL C.2: A.1. Loss of function . Total loss of the SITE AREA needed for unit Charging/SI System EMERGENCY HSD condition OR MODES 1, 2 3 & 4 Total loss of the Main Feedwater and Auxiliary Feedwater systems

2. Probable large Loss of Main Feedwater System, GENERAL radioactivity Condensate System and Auxiliary EMERGENCY release initiated by Feedwater System loss of heat sink leading to core degradation MODES 1 2. 3 & 4

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB C) PG ATTACHMENT FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE l 1I l _ _ _ _ _ _ 14_of_42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. Probable large

Rx nuclear power after a GENERAL radioactivity trip - greater than 5% EMERGENCY release initiated by failure of AND protection system to bring Rx subcritical
RCS pressure greater than and causing core or equal to 2485 psig degradation OR ALL MODES Containment pressure and temperature rapidly increasing

4. Probable large

Loss of all onsite and GENERAL radioactivity offsite AC power EMERGENCY release initiated by loss of AC power and AND all feedwater
Turbine Driven Auxiliary ALL MODES Feedwater Pump not operable AND
Restoration of either of the above not likely within 2 hours

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT L~~~~

      ---                               (TAB C)CI FUEL FAILURE OR FUEL HANDLING ACCIDENT E

PAGE4 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

5. Probable large

Loss of reactor coolant in GENERAL radioactivity progress EMERGENCY release initiated by LOCA with loss of AND ECCS and containment cooling
High or low head ECCS flow not being delivered to the ALL MODES core (if expected by plant conditions)

AND

Containment RS sump temperature greater than 1900F and NOT decreasing OR All Quench Spray and Recirculation Spray systems

                                        - NOT OPERABLE

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB C) PG ATTACHMENT FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE 1 ______________ ~~~ ~~~~~~~~~16 of _42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

6. Core damage with a) Fuel clad failure as SITE AREA possible loss of indicated by any of the EMERGENCY coolable geometry following:

MODES 1 2. 3. & 4

RCS Specific activity greater than 60 pCi/gram dose equivalent I-131 OR High Range Letdown radiation monitor 1-CH-RI-128 or 2-CH-RI-228 GREATER THAN 1.2x104 mR/hr AND b) Loss of cooling as indicated by any of the following:
5 confirmed core exit thermocouples greater than 1200 F OR Core delta T - zero OR Core delta T - rapidly diverging

ATTACHMENT TITLE REVISION EMERGENCY ACTION LEVEL TABLE 38 (TAB C) PG FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE 17 of 4? CONDITION/APPLICABILITY INDICATION CLASSIFICATION

7. Major fuel damage

Water level in Rx vessel SITE AREA accident with during refueling below the EMERGENCY radioactivity top of core release to containment or fuel OR buildings Water level in spent fuel ALL MODES pool below top of spent fuel AND
Verified damage to irradiated fuel resulting in readings on Vent Vent "B" MGPI monitor I RM-VG-180 GREATER THAN 2.69 x 108 Ci/sec

8. Severe Fuel Clad

High Range Letdown ALERT Damage radiation monitor MODES 1, 2 3. & 4 1-CH-RI-128 or 2-CH-RI-228 Increases to GREATER THAN Hi Hi Alarm setpoint (representing 1% fuel failure) within 30 minutes and remains for at least 15 minutes OR RCS specific activity -

greater than 300 FiCi/gram dose equivalent I-131

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB C) PG FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE 1 __ _ _ __ _ _ 18 of 42 . CONDITION/APPLICABILITY INDICATION CLASSIFICATION

9. Fuel damage accident

Verified accident involving ALERT with release of damage to irradiated fuel radioactivity to containment or fuel AND buildings
Health Physics confirms fission ALL MODES product release from fuel OR Vent Vent "B" MGPI monitor RM-VG-180 GREATER THAN 1.99 x 106 pCi/sec

10. Potential for fuel Continuing uncontrolled ALERT damage to occur decrease of water level in during refueling Reactor Refueling Cavity or MODE 6 Spent Fuel Pool

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT 1~ LI (TAB C) FUEL FAILURE OR FUEL HANDLING ACCIDENT PAGE PAGE l _ _ _ _ _ _ 19 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

11. Fuel clad damage Intentional reduction in NOTIFICATION indication ower. load or temperature OF UNUSUAL TAW reactor coolant EVENT MODES 1 2, 3 & 4 activity T.S. Action Statement - HAS COMMENCED OR High Range Letdown radiation monitor 1-CH-RI-128 or 2-CH-RI-228 Increases to GREATER THAN Hi Alarm setioint (re resentin 0.1t fuel failure) within 30 minutes and remains for for at least 15 minutes

12. Independent Spent Verified Sealed Surface NOTIFICATION Fuel Storage Storage Cask (SSSC) seal OF UNUSUAL Installation leakage EVENT (ISFSI) event OR ALL MODES Sealed Surface Storage Cask (SSSC) dropped or mishandled

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB D) PAGE CONTAINMENT EVENT __ __ _ __ __ _20 of_42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Extremely high

Containment High Range GENERAL containment radiation monitor EMERGENCY radiation, pressure and temperature RM-RMS-165, -166 or RM-RMS-265, -266 MODES 1 2, 3, & 4 GREATER THAN 3.76 x 102 R/hr AND
Containment pressure greater than 45 psia and not decreasing OR Containment temperature greater than 2800F

2. High-high

Containment High Range SITE AREA containment radiation monitor EMERGENCY radiation, pressure, and temperature RM-RMS-165. -166 or RM-RMS-265. -266 MODES 1, 2 3. & 4 GREATER THAN 1.88 x 102 R/hr AND a Containment pressure -

greater than 27.75 psia and not decreasing OR Containment temperature - greater than 200 F I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.O1 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB D) PAGE I- -1 ~ ~~~~~CONTAINMENT EVENT21o4 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. High Containment

Containment High Range ALERT radiation, pressure radiation monitor and temperature RM-RMS-165, -166 or MODES 1, 2. 3 & 4 RM-RMS-265. -266 GREATER THAN 81.5 R/hr AND
Containment pressure -

greater than 17 psia OR Containment temperature - greater than 150OF I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT 1~ L (TAB E) RADIOACTIVITY EVENT PAGE l _ _ _ __ _ _ 22 of_42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Release imminent or

HP assessment indicates GENERAL in progress and site actual or projected doses EMERGENCY boundary doses at or beyond site boundary projected to exceed greater than 1.0 Rem TEDE 1.0 Rem TEDE or 5.0 or 5.0 Rem Thyroid CDE Rem Thyroid CDE ALL MODES

2. Release imminent or

HP assessment indicates SITE AREA in progress and site actual or projected dose at EMERGENCY boundary doses or beyond Site Boundary projected to exceed exceeds 0.1 Rem TEDE or 0.5 0.1 Rem TEDE or 0.5 Rem Thyroid CDE Rem Thyroid CDE ALL MODES I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB E) PAGE RADIOACTIVITY EVENT 1______________ 23 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

3. Effluent release a) Any of the following ALERT greater than 10 monitors indicate valid times ODCM allowable readings above the limit specified values for greater than 15 minutes ALL MODES

                                 . Clarifier Effluent RM-LW-111 GREATER THAN 4.8 x 105 cpm

Discharge Canal RM-SW-130 or -230 GREATER l THAN 5 x 104 cpm Vent Vent A MGPI a

RM-VG-179 GREATER THAN 1.73 x 106 Ci/sec Vent Vent B MGPI RM-VG-180 GREATER THAN 1.99 x 106 Ci/sec Process Vent MGPI RM-GW-178 GREATER THAN 1.35 x 107 Ci/sec OR b) HP assessment (sample results or dose projections) indicate greater than 10 times ODCM allowable limit

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB E) PAGE L~~~~L ~~~RADIOACTIVITY EVENT24o4 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

4. High radiation or Valid readings on any of the ALERT airborne following monitors have contamination levels increased by a factor of 1000 indicate a severe and remain for at least 15 degradation in minutes:

control of radioactive material

Ventilation Vent Multi-sample gaseous or ALL MODES particulate monitor IRM-VG-106 or -105
Control Room Area IRMS-157
Aux. Bldg. Control Area RMS-154 a Decon. Bldg. Area I RMS-151 I
Fuel Pool Bridge Area lRS153 l
New fuel storage Area LMS-152
Laboratory Area l RMS-158 l
Sample Room Area I RMS-156 I I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB E) PAGE RADIOACTIVITY EVENT 25 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

5. Effluent release a) Any of the following NOTIFICATION greater than ODCM monitors indicate valid OF UNUSUAL allowable limit readings above the EVENT secified value for more ALL MODES tCan 1 hour:

Clarifier Effluent RM-LW-111 GREATER THAN 4.8 x 10 cpm Discharge Canal RM-SW-130 or -230 GREATER THAN 5 x 103 cpm a Vent Vent A MGPI IRM-VG-179 GREATER THAN 1.73 x 105 pCi/secl 6 Vent Vent B MGPI RM-VG-180 GREATER THAN 1.99 x 105 pCi/sec S Process Vent MGPI RM-GW-178 GREATER THAN l 11.35 x 106 pCi/secl OR b) HP assessment (sample results or dose projections) indicates greater than ODCM allowable limit 7

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB G) PG ATTACHMENT LOSS OF SECONDARY COOLANT PAGE 1 _______________ ~~~ ~~~~~~~~26 of _42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Major secondary Conditions a) and b) exist with c): SITE AREA line break with a) Uncontrolled loss of secondary EMERGENCY significant primary coolant - IN PROGRESS to secondary leakage and fuel AND damage indicated b) RCS specific activity exceeds MODES 1 2, 3. & 4 limits of T.S. Figure 3.4.16-1 OR High Range Letdown radiation monitor 1-CH-RI-128 or 2-CH-RI-228 GREATER THAN Hi Alarm setpoint AND c) Vent Vent A MGPI Monitor RM-VG-179 GREATER THAN 6.21 x 107 liCi/sec OR Affected pathway Steam Generator Blowdown monitor RM-SS-122. -123, -124.

                                         -222. -223, -224 GREATER THAN 1 x 106 cpm OR Affected pathway Main Steam Line High Range monitor RM-MS-170, -171, -172,
                                         -270. -271, -272 GREATER THAN 12.2 mR/hr

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB G) PG LOSS OF SECONDARY COOLANT PAGE 1 ______________ ~~~ ~~~~~~~~~27 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

2. Major secondary line

Uncontrolled loss of ALERT break with secondary coolant - IN significant primary PROGRESS to secondary leakage AND MODES 1 2, 3. & 4
Vent Vent A MGPI Monitor RM-VG-179 GREATER THAN 1.76 x 106 pCi/sec I

OR Steam Generator Blowdown monitor on affected pathway RM-SS-122, -123, -124 RM-SS-222, -223. -224 GREATER THAN 1x10 5 cpm OR Main Steam Line High Range monitor on affected pathway RM-MS-170, -171, -172 RM-MS-270. -271, -272 GREATER THAN 0.14 mR/hr

3. Major secondary line Uncontrolled loss of secondary NOTIFICATION break coolant - IN PROGRESS OF UNUSUAL EVENT MODES 1. 2, 3. & 4

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB H) PAGE . ~ L ELECTRICAL FAILURE28 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Loss of offsite and The following conditions exist SITE AREA onsite AC power for for greater than 15 minutes: EMERGENCY more than 15 minutes

Ammeters for 4160V Reserve ALL MODES Station Service Buses D. E.

                                        & F all indicate - zero (0) amps AND

Ammeters for 4160V Station Service Buses A, B. & C all indicate - zero (0) amps AND
Ammeters for 4160V Emergency Buses H & J both indicate - zero (0) amps

2. Loss of all onsite The following conditions exist SITE AREA DC power for greater for greater than 15 minutes: EMERGENCY than 15 minutes

All station battery ALL MODES voltmeters indicate zero (0) volts AND
No light indication available to Reserve Station Service breakers 15D1, 15E1 and 15FI I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB H) PAGE IL~~~~L I ~~ELECTRICAL 1~~~~~~~~~~~-? FAILURE 29o CONDITION/APPLICABILITY INDICATION CLASSIFICATION CAUTION: EAL A.1 is duplicated below for cross-reference/comparison to EAL H.3: A.1. Loss of function

Total loss of the SITE AREA needed for unit Charging/SI System EMERGENCY HSD condition OR MODES 1. 2 3 & 4 Total loss of the Main Feedwater and Auxiliary Feedwater Systems

3. Loss of all offsite . Ammeters for 4160V Reserve ALERT and onsite AC power Station Service Buses D. E

                                       & F all indicate - zero (0 ALL MODES                     amps AND Ammeters for 4160V Station Service Buses A. B. & C all indicate - zero (0) amps AND Ammeters for 4160V Emergency Buses H and J both indicate - zero (0) amps

4. Loss of all onsite . All station battery ALERT DC power voltmeters indicate - zero (0) volts ALL MODES AND

No light indication available to Reserve Station Service Breakers 15D1, 15E1 and 15F1 t

0

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB H) PAGE 1 L-1 ~ ~~~~~ELECTRICAL FAILURE 3

                .                                     .                  ~~~~~~~~~~~~~~~~~~

of 42 l CONDITION/APPLICABILITY INDICATION CLASSIFICATION

5. Loss of offsite

Unit main generator and NOTIFICATION power or both emergency diesel OF UNUSUAL onsite AC power generators out of service EVENT capability OR ALL MODES Loss of all 34.5 KV reserve station service buses t

I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB I) PAGE 1 l _ _ _ __ _ _ 31 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION-

1. Fire resulting in Fire which causes major SITE AREA degradation of degradation of a safety EMERGENCY safety systems system function required for protection of the MODES 1. 2. 3, & 4 public AND

Affected systems are caused to be NOT operable as defined by Tech. Specs.

2. Fire potentially Fire which has potential for ALERT affecting station causing a safety system not to safety systems be operable as defined by Tech.

Specs. MODES 1. 2. 3. & 4

3. Fire lasting greater Fire within the Protected Area NOTIFICATION than 10 minutes in or Service Water Pump/Valve OF UNUSUAL Protected Area or House which is not under EVENT Service Water control within 10 minutes after Pump/Valve House Fire Brigade - DISPATCHED ALL MODES

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT 1 L~~~~~~~ (TAB J)

                               ~~SECURITY EVENT32o PAGE l _  _ _  __ _  _                                                              32 of 42  .

CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Loss of physical

Shift Manager/Station GENERAL Station control Emergency Manager has been EMERGENCY informed that the security ALL MODES force has been neutralized by attack, resulting in loss of physical control of station OR Shift Manager/Station Emergency Manager has been informed of intrusion into one or more Vital Areas which are occupied or controlled by an aggressor

2. Imminent loss of Security Shift Supervisor has SITE AREA physical Station notified the Operations Shift EMERGENCY control Manager/Station Emergency Manager of imminent intrusion ALL MODES into a Vital Area

3. Ongoing Security Security Shift Supervisor has ALERT compromise notified the Operations Shift Manager/Station Emergency ALL MODES Manager of a confirmed unneutralized intrusion into the Protected Area or ISFSI IW

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB J) PAGE 1 I SECURITY EVENT33 o CONDITION/APPLICABILITY INDICATION CLASSIFICATION

4. Security threat, Any of the following when NOTIFICATION unauthorized determined to have potential OF UNUSUAL attempted entry, or for degrading the level of EVENT attempted sabotage safety of the plant or ISFSI ALL MODES

Receipt of a credible site-specific threat from Security. NRC or FBI
Confirmed hostage situation
Civil disturbance
Discovery of a bomb device (other-than on or near a safety-related system which represents an on-going security compromise)
Confirmed attempted intrusion (Protected Area or ISFSI)
Attempted sabotage

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB K) PG HAZARD TO STATION OPERATION PAGE . _____________ 34 of CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Aircraft damage to Aircraft crash which affects SITE AREA vital plant systems vital structures by impact or EMERGENCY fire MODES 1 2 3 & 4

2. Severe explosive Explosion which results in SITE AREA damage severe degradation of any of EMERGENCY the following systems required MODES 1. 2, 3 & 4 for safe shutdown:

CVCS System OR ECCS System OR Main/Auxiliary Feedwater System

3. Entry of toxic or

Uncontrolled release of SITE AREA flammable gases into toxic or flammable agents EMERGENCY plant vital areas greater than life other than the threatening or explosive Control Room limits in Vital Areas MODES 1, 2. 3, & 4 AND a Evacuation of Vital Area other than Control Room -

REQUIRED OR Significant degradation of plant safety systems resulting in loss of a safety system function required for protection of the public I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB O A PAGE L~ 1 HAZARD TO STATION OPERATION PAGE CONDITION/APPLICABILITY INDICATION CLASSIFICATION

4. Severe missile Missile impact causing severe SITE AREA damage to safety degradation of safety systems EMERGENCY systems required for unit shutdown MODES 1, 2 3, 4

5. Aircraft crash on Aircraft crash within the ALERT the facility Protected Area or Switchyard ALL MODES

6. Explosion damage to Unplanned explosion resulting ALERT facility in damage to plant structure or equipment that affects plant ALL MODES operations

7. Entry of toxic or Notification of uncontrolled ALERT flammable gases or release of toxic or flammable liquids into plant agent which causes:

facility

Evacuation of personnel ALL MODES from plant areas AND
Safety related equipment is rendered inoperable

8. Turbine failure or Failure of turbine/generator ALERT missile impact rotating equipment resulting in casing penetration MODES 1 & 2

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE - 38 ATTACHMENT (TAB K) PG ATTACHMENT HAZARD TO STATION OPERATION PAGE 1 . __ _ ____36 of_42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

9. Missile damage to Notification of missile impact ALERT safety related causing damage to safety equipment or related equipment or structures structures MODES 1, 2 3. & 4

10. Aircraft crash or

Confirmed notification of NOTIFICATION unusual aircraft aircraft crash within the OF UNUSUAL activity site boundary EVENT ALL MODES OR Unusual aircraft activity in the vicinity of the site as determined by the Operations Shift Manager/

Station Emergency Manager or the Security Shift Supervisor

11. Train derailment Confirmed report of train NOTIFICATION within Protected derailment within Protected OF UNUSUAL Area Area EVENT ALL MODES

12. Explosion within Confirmed report of unplanned NOTIFICATION Protected Area explosion within Protected OF UNUSUAL Area EVENT ALL MODES

13. Onsite or nearsite Notification of unplanned NOTIFICATION release of toxic or release of toxic or flammable OF UNUSUAL flammable liquids or agents which may affect safety EVENT gases - of station personnel or equipment ALL MODES 0V

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT 1 ~ L (TAB K) HAZARD TO STATION OPERATION PAGE PAGE . _ _ _ _ _ _ 37 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

14. Turbine rotating Failure of turbine/generator NOTIFICATION component failure rotating equipment resulting in OF UNUSUAL with no casing immediate unit shutdown EVENT penetration MODES 1 & 2

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TAkLE 38 ATTACHMENT (TAB L) PAGE L ~~~~~~L ~~NATURAL EVENTS38o CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Earthquake greater

Confirmed earthquake SITE AREA than or equal to DBE which activates the Event EMERGENCY levels Indicator on the Strong Motion Accelerograph MODES 1. 2. 3, & 4
aND
Alarms on the Peak Shock Annunciator indicate a horizontal motion of greater than or equal to 0.12 g or a vertical motion of greater than or equal to 0.08g

2. Sustained winds in Sustained winds 150 mph SITE AREA excess of design OR GREATER experienced EMERGENCY levels experienced or projected or projected MODES 1 2, 3. & 4

3. Flood or low water Either condition a) or b) exists SITE AREA level above design EMERGENCY levels a) Flood in the Lake Anna Reservoir with indicated MODES 1 2 3, & 4 level - greater than 264 feet MSL OR b) Low water level in the Lake Anna Reservoir with indicated level - less than 244 feet MSL AND Inability to satisfy action requirements of TR 3.7.4 for North Anna Reservoir

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB L) PAGE NATURAL EVENTS __ _ _ __ _ _39 of _4 CONDITION/APPLICABILITY INDICATION CLASSIFICATION*

4. Earthquake greater

Confirmed earthquake which ALERT than or equal to OBE activates Event Indicator levels on the Strong Motion Accelerograph ALL MODES AND
Alarms on the Peak Shock Annunciator indicate a horizontal motion of greater than or equal to 0.06 g or a vertical motion of greater than or equal to 0.04g

5. Tornado striking Tornado visually detected ALERT facility striking structures within the Protected Area or Switchyard ALL MODES

6. Hurricane winds Hurricane winds 120 mph ALERT near design basis OR GREATER experienced level experienced or projected or projected ALL MODES

7. Flood or low water

Flood in the Lake Anna ALERT level near design Reservoir with indicated levels level - greater than 263 feet MSL ALL MODES Low water level in the Lake Anna Reservoir with indicated level - less than 244 feet MSL

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB L) PAGE NATURAL EVENTS 1 of a40 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

8. Earthquake detected Confirmed earthquake which NOTIFICATION activates the Event Indicator OF UNUSUAL ALL MODES on the Strong Motion EVENT Accelerograph

9. Tornado within Tornado visually detected NOTIFICATION Protected Area or within Protected Area or OF UNUSUAL Switchyard Switchyard EVENT ALL MODES

10. Hurricane force

Confirmation by Weather NOTIFICATION winds projected Center that hurricane force OF UNUSUAL onsite within 12 winds (greater than 73 mh) EVENT hours projected onsite within 12 hours ALL MODES-

11. 50 year flood or low

Flood in the Lake Anna NOTIFICATION water level Reservoir with indicated OF UNUSUAL level - greater than 254 EVENT ALL MODES feet MSL OR Low water level in the Lake Anna Reservoir with indicated level less than 246 feet MSL I

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB M) PG MISCELLANEOUS ABNORMAL EVENTS PAGE 1 ~~~~~~~~~~~~~~~~41 of 42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

1. Any major internal Shift Manager/Station Emergency GENERAL or external events Manager judgement EMERGENCY I which singly or in combination cause massive damage to station facilities or may warrant evacuation of the public ALL MODES

2. Station conditions Shift Manager/Station Emergency SITE AREA which may warrant Manager judgement EMERGENCY I notification of the public near the site ALL MODES

3. Station conditions Shift Manager/Station Emergency ALERT which have the Manager judgement I potential to degrade or are actually degrading the level of safety of the station ALL MODES

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB M) PG ATTACHMENT MISCELLANEOUS ABNORMAL EVENTS PAGE 1 ______________ of _42

                                                                             ~~~ ~~~~~~~~42 CONDITION/APPLICABILITY          INDICATION                       CLASSIFICATION

4. Station conditions Shift Manager/Station Emergency NOTIFICATION which warrant Manager judgement that any of OF UNUSUAL increased awareness the following exist: EVENT of state and/or local authorities Unit shutdown is other than ALL MODES a controlled shutdown OR Unit is in an uncontrolled condition during operation OR A condition exists which has the potential for escalation and therefore warrants notification

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 TURNOVER CHECKLIST 38 ATTACHMENT PAGE 2 1 of 1 Conduct a turnover between the onshift and relief SEM in accordance with the following checklist. Use placekeeping aid at left of item, ___", to track completion.

1. Determine the status of primary responder notification.

2. Determine the status of Report of Emergency to State and Local Governments." EPIP-2.01. Attachment 2. Get completed copies if available.

3. Determine status of the Report of Radiological Conditions to the State." EPIP-2.01, Attachment 3. Get completed copy if available.

4. Determine status of Emergency Notification System (ENS) communications and completion status of NRC Event Notification Worksheet (EPIP-2.02 Attachment 1).

5. Review classification and initial PAR status.

6. Review present plant conditions and status. Get copy of Critical Safety Functions form.

7. Review status of station firewatches and re-establish if conditions allow.

8. Determine readiness of TSC for activation.

9. After all information is obtained, transfer location to TSC. (Consider direct transfer of State & local notifications to LEOF/CEOF.)

10. Call the Control Room and assess any changes that may have occurred during transition to the TSC.

11. When sufficient personnel are available, the relief SEM is to assume the following responsibilities from the onshift Station Emergency Manager:

a. Reclassification.

b. Protective Action Recommendations until LEOF activated.

c. Notifications (i.e.. state, local. & NRC). Upon LEOF activation.

transfer notification responsibilities except for the NRC ENS.

d. Site evacuation authorization.

e. Emergency exposure authorization.

f. Command/control of onsite response.

12. Formally relieve the Interim SEM and assume control in the TSC.

Announce name and facility activation status to facility.

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 CONSIDERATIONS FOR OPERATIONS RESPONSE 38 ATTACHMENT UNDER ABNORMAL CONDITIONS PAGE 3 ~~~~~~~~~~~~~~~~~ of 1 This attachment provides procedural guidance for controlling selected emergency response actions when their implementation would have adverse results. Station Emergency Manager (SEM) approval is required before any required action is postponed. suspended or modified. The guidance below is not all-inclusive. UNANTICIPATED HAZARD EXISTS (e.a.. security event. tornado or toxic release): IF implementation of emergency response actions could compromise Security Plan response strategies. THEN consider postponing or suspending emergency response actions until threat has been resolved. e.g., on-site announcement directing assembly and emergency response facility activation, pager activation and call-out per EPIP-3.05. AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION, dispatch of Security Team members to the LEOF per EPIP-3.04, ACTIVATION OF LOCAL EMERGENCY OPERATIONS FACILITY, and staging of road blocks per EPIP-5.04. ACCESS CONTROL. IF assembling on-site personnel for accountability or activation of emergency response facilities could endanger plant personnel. THEN consider postponing emergency assembly until hazardous conditions are resolved. (Consider having Corporate Security notify corporate emergency response organization only using CPIP-3.4. INNSBROOK SECURITY SUPPORT, and notifying personnel in unaffected areas on-site selectively.) IF notifying augmentation could create a safety hazard for personnel coming to the station. THEN consider postponing augmentation notification. (Consider having Corporate Security notify corporate emergency response organization only using CPIP-3.4, INNSBROOK SECURITY SUPPORT, or defering notifications until hazardous conditions are resolved.) ANTICIPATED SITUATION (e.g., forecasted severe weather or grid disturbance): IF all or part of the ERO has been staged in anticipation of a predicted event. THEN notify Security to omit performance of augmentation notification (as described in EPIP-3.05. AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION). IF adequate controls have been established to continually account for personnel staged in anticipation of a predicted event. THEN notify Security to omit performance of initial accountability (as described in EPIP-5.03. PERSONNEL ACCOUNTABILITY). IF a decision has been made to staff the Central EOF in lieu of the LEOF, THEN notify Security that performance of EPIP-3.04, ACTIVATION OF LOCAL EMERGENCY OPERATIONS FACILITY, is not required. IF environmental conditions are hazardous. THEN consult with Security Team Leader about suspending procedural requirements for staging road blocks (IAW EPIP-5.04, ACCESS CONTROL).

VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-4.O1 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20

                                        ~~~PROCEDURE                            2 (With 2 Attachments)                        PAGE 1 of   28 PURPOSE To initially assess emergency conditions. provide recommendations for protective measures, establish an emergency organization and direct Health Physics response to an emergency.

[ ,E'VLD , DISMFBUnON Thi Dcumnent Should e erified An~d Anriotmet To A C.0Shelled ource ENTRY CONDITIONS ss-u,..rin nk Activation by EPIP-1.01. EMERGENCY MANAGER CONTROLLING PROCEDURE. Approvals n File Effective Date 0G53

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE l - - 2 of 28 -Ei~ ACTION/EXPECTED RESPONSE F-I . RESPONSE NOT OBTAINED F- _____ 1 INITIATE PROCEDURE: a) By: Date: Time: b) Assume position of Radiological Assessment Director (RAD) c) Initiate a chronological log to record sequence of events, key decisions, action taken, and other applicable information related to the event _____2 GO TO THE CONTROL ROOM IF conditions require your presence in another location, THEN inform SEM AND Report to the Control Room immediately upon completion of task. NOTE: During the initial stages of the emergency the Operations Shift Manager may assume the position of Station Emergency Manager. I _____3 ASK SM FOR BRIEFING ON THE FOLLOWING PARAMETERS:

Plant status
Emergency Action Levels (EALs) exceeded
Emergency Classification

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE L~~~~~~~~~~~~~~~ ~~~~3 of 28 i{E ACTION/EXPECTED RESPONSE 1-H S RESPONSE NOT OBTAINED A-~ _____4 CHECK IF EMERGENCY FACILITIES ARE GO TO Step 6. BEING ACTIVATED _____5 MOVE TO TSC NOTE: A minimum of 2 (two) Offsite Monitoring Teams must be dispatched (i.e.. sent into the field) upon a Site Area Emergency or higher emergency class. _____6 CHECK HP SUPPORT - REQUIRED IF HP support NOT immediately required, THEN do the following:

WHEN HP support required, THEN GO TO Step 7.
WHEN emergency is terminated, THEN GO TO Step 39.

_____7 CHECK IF EVENT INVOLVES GO TO Step 25. ACTUAL OR POTENTIAL OFFSITE RELEASE _____8 INITIATE SAMPLING OF EFFLUENT IF unable to get effluent sample. PATHWAY THEN initiate source term sampling. _____9 DIRECT INITIATION OF EPIP-4.03, DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE

             ._                                                              4 of  28 EEIE          ACTION/EXPECTED RESPONSE       F-]         RESPONSE NOT OBTAINED      F-

_____10 DIRECT INITIATION OF EPIP-4.30, IF MIDAS NOT operable. THEN USE OF MIDAS CLASS A MODEL initiate back-up assessment using desk-top calculations:

EPIP-4.08, INITIAL OFFSITE RELEASE ASSESSMENT.
EPIP-4.09. SOURCE TERM ASSESSMENT.
EPIP-4.10, DETERMINATION OF XO.

_____11 DIRECT RPS TO INITIATE EPIP-4.02, RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE _____12 DETERMINE EVENT CLASSIFICATION: ASSESSMENT RESULTS CLASSIFICATION Normal range monitors ONSCALE N/A: Below classification and indicate < 100% TS limits Normal range monitors ONSCALE Notification of Unusual and indicate 100% TS (but < 1000%) Event

          % TS calculations indicate 2 1000%             Alert Site Boundary dose    100 mrem TEDE            Site Area Emergency 500 mrem Thyroid CDE Site Boundary dose    1 Rem TEDE               General Emergency or 5 Rem Thyroid CDE

_____13 GIVE ASSESSMENT BASED CLASSIFICATION TO SEM

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE 20 PAGE L- -- ~~~~~~~~~~~~~~~~5 of 28 -1EH ACTION/EXPECTED RESPONSE H-I - RESPONSE NOT OBTAINED H-14 CHECK NOTIFICATION OF UNUSUAL GO TO Step 15. EVENT IN EFFECT OR EVENT IS BELOW CLASSIFICATION LIMITS: a) Report percent Tech. Spec. and Site Boundary dose rate to Station Emergency Manager b) Get backup sample of the b) IF unavailable, THEN GO TO effluent release path Step 20. c) Have sample analyzed using Health Physics Procedures d) GO TO Step 20 for follow up assessment _____15 INITIATE RESPONSE ACTIONS FOR IF event NOT Limiting Fault, THEN CONDITION IV LIMITING FAULT GO TO Step 20. ACCIDENT:

Fuel Handling Accident - GO TO Step 16
Steam Generator Tube Rupture -

GO TO Step 17

Main Steam Line Rupture - GO TO Step 18
LOCA - GO TO Step 19 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE L_ ~~~~~~~~~~~~~~~~~~6 of 28 _FE ACTION/EXPECTED RESPONSE F-] RESPONSE NOT OBTAINED H-NOTE: Analysis of accidents involving decayed spent fuel should include consideration of onsite skin dose due to Kr-85. _____16 INITIATE RESPONSE ACTIONS FOR FUEL HANDLING ACCIDENT: a) Recommend evacuation of the Fuel Building and affected containment b) Restrict access until radiological assessment can be made c) Have EPIP-4.06. PERSONNEL MONITORING AND DECONTAMINATION, initiated to monitor individuals evacuated from accident area d) Report dose assessment (MIDAS or desk-top) results to SEM e) GO TO Step 21 t

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE l~~ 7 of 28 {Ed ACTION/EXPECTED RESPONSE F-I . RESPONSE NOT OBTAINED F-

   ~~17   INITIATE RESPONSE ACTIONS FOR STEAM GENERATOR TUBE RUPTURE:

a) Get release parameters from SEM:

1) Note length of time between initiation of release and when Air Ejector diverted to containment: (min.)

(if Air Ejector diverted)

2) Number of Steam Generator Relief or Safety Valves which have lifted:_

3) Length of time Relief or Safety Valves remained open:

(min.)

4) Number of relief or Safety Valves which may potentially lift:

5) Status of main steam supply to the Steam Driven Auxiliary Feedwater Pump:

Steam isolation from Aw S/G at (time) wBW S/G at "C" S/G at

6) Current Steam Generator Blowdown pathway:

f) Length of time until blowdown isolated: (min.) b) Check Air Ejector - DIVERTED TO b) IF Air Ejector NOT diverted. CONTAINMENT THEN GO TO Step 17.d. c) Request immediate evacuation of containment building I (STEP 17 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE 8 of 28 -i l-ACTION/EXPECTED RESPONSE I-I _ RESPONSE NOT OBTAINED 17 INITIATE RESPONSE ACTIONS FOR STEAM GENERATOR TUBE RUPTURE: (Continued) d) Check Steam Driven Auxiliary d) IF SDAFWP Turbine NOT ISOLATED, Feedwater Pump (SDAFWP) Turbine THEN do the following:

             - ISOLATED

1) Ask SEM to isolate main steam supply from affected generator to Steam Driven Auxiliary Feedwater Pump.

2) GO TO Step 17.f.

e) Disregard SDAFWPT as a release pathway f) Ask SEM for placement of individual to report the following data:

1) Initial monitor readings

2) Increase or decrease in Main Steam and SDAFWP exhaust radiation monitors

3) Meteorological panel indications g) Report dose assessment (MIDAS or desk-top) results to SEM I

(STEP 17 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE 9 of 28 -EI{ r ACTION/EXPECTED RESPONSE F-] . RESPONSE NOT OBTAINED 17 INITIATE RESPONSE ACTIONS FOR STEAM GENERATOR TUBE RUPTURE: (Continued) h) Restrict access in the following areas until survey(s) confirm no radiological hazards:

Steam Generator Blowdown Cooler area
Steam Generator Blowdown Lines and Vent area
Steam Generator Relief Valve area
Steam Driven Auxiliary Feedwater Pump Turbine exhaust area
Powdex Area - Turbine Building, 303' level
Main Steam Valve House i) Consider sampling of Steam Generator Blowdown and Main Steam of affected unit j) Determine potential for liquid release pathway through the Main Steam Safety Valve k) GO TO Step 21 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE 20 PAGE L~~~~~~~~~~~~~~~~ ~~~~10 of 28 STE P ~ACTION/EXPECTED RESPONSE HRESPONSE NOT OBTAINED 18 INITIATE RESPONSE ACTIONS FOR MAIN STEAM LINE RUPTURE: a) Ask SEM for release parameters:

1) Location of steam break

2) Status of actual or potential Main Steam Safety Valve lift

3) Number of valves lifted:

4) Length of time valves remained open: (min.)

5) Status of Steam Driven Auxiliary Feedwater Pump isolation

6) Monitor reading on Main Steam Monitors and Steam Driven Auxiliary Feedwater Pump exhaust radiation monitors b) Check station ventilation vent b) IF NO release indicated, THEN radiation monitors for release do the following:

indication

1) Notify SEM that potential for source term development will be evaluated because monitors do not indicate release.

2) GO TO Step 18.e.

c) Evaluate release consequences: I) Assess onsite dose rate in area of break (after break is isolated)

2) Assess offsite dose rate d) Report dose assessment (MIDAS or desk-top) results to SEM e) Determine potential for source term to develop inside containment or from Main Steam Relief Valve lift f) GO TO Step 21

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE 11 of 28 iE}{ ACTION/EXPECTED RESPONSE [-H RESPONSE NOT OBTAINED H- _____19 INITIATE RESPONSE ACTIONS FOR LOCA: a) Ask SEM for location of break b) Ask SEM for status of Containment Isolation - Phase "Aw or "B". and any leak paths from the containment c) Recommend evacuation of Auxiliary Building and Safeguards Building to SEM AND Restrict entry until survey(s) confirm no radiological hazard exist d) Determine CHRRMS readings (RMS-165. 166 or RMS-265. 266) e) Check release occurred through e) Do the following: monitored pathway(s)

1) Direct initiation of EPIP-4.03, DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE.

2) Assess actual (unmonitored) or potential release from containment.

f) Report dose assessment (MIDAS or desk-top) results to SEM g) GO TO Step 21 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20

               .                       ~~~~~~~PROCEDURE PAGE 12 of 28 AHEE           ACTION/EXPECTED RESPONSE          F-I      _

RESPONSE NOT OBTAINED F- _____20 INITIATE RESPONSE ACTIONS FOR GO TO Step 25. RADIOLOGICAL RELEASE: a) Record release pathway(s): b) Verify event limited to plant b) IF radiological event at ISFSI. systems THEN refer to Attachment 2. Response to ISFSI Event. c) Report dose assessment (MIDAS or desk-top) results to SEM d) Ask SEM to place an individual at the monitor of interest to report increase or decrease in readings e) Get sample of effluent pathway e) IF sample NOT available. THEN use monitor readings for follow-up assessment. f) Analyze samples using normal Health Physics procedures g) Consider initiation of EPIP-4.26, HIGH LEVEL ACTIVITY SAMPLE ANALYSIS h) Verify that an exposure control individual is available to supply dosimetry (STEP 20 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE 13 of 28 F-A F- -E{E ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

         . 20 INITIATE RESPONSE ACTIONS FOR RADIOLOGICAL RELEASE: (Continued) i) Have RPS coordinate HP coverage needed for any of the following activities:

Damage Control Teams
Emergency Security activities
Access control
Personnel monitoring
Sample analysis j) Consider having RPS prepare for dispatch of Offsite Monitoring Teams:
Team assembly
Preparation of equipment and vehicles

_____21 ENSURE 40CFR302 EPA NOTIFICATION REQUIREMENTS AND REPORTABLE QUANTITY CALCULATIONS ARE EVALUATED IN ACCORDANCE WITH NORMAL HP PROCEDURES _____22 CHECK IF RESULTS OF OFFSITE GO TO Step 24. RELEASE ASSESSMENT INDICATE SITE BOUNDARY DOSE RATE 50 mrem/hr TEDE OR 250 mrem/hr THYROID CDE

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 220 PROCEDURE PAGE L~~~~~~~~~~~~~~~~ ~~~~14 of 28 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _____23 DETERMINE OFFSITE PROTECTIVE MEASURES: a) Get an estimate of release a) Use 2 hour default. duration (hours) from SEM b) Direct initiation of EPIP-4.07, PROTECTIVE MEASURES c) Give recommendation to SEM _____24 CHECK LEOF (CEOF) HAS LEAD FOR Do the following: OFFSITE DOSE ASSESSMENT a) Assure dose assessment result identification number recorded on all pages. b) Record initials on each page to document approval for issuance of results. c) Review offsite release assessment results with SEM. d) Give applicable dose assessment report to State/Local Emergency Communicator:

MIDAS Radiological Status Report (2 pages).
EPIP-4.03, DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE, Attachment 1.

e) Provide updated dose assessment results when any of the following occur:

Every 60 minutes during Alert or higher classification.
Within 15 minutes after a classification change.
Change in radiological conditions.

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE 15 of 28 -iEJ-ACTION/EXPECTED RESPONSE H-I RESPONSE NOT OBTAINED 1-NOTE:

The following step lists response actions that may have to be coordinated by the RAD. These actions are not listed in order of priority.
A minimum of 2 (two) Offsite Monitoring Teams must be dispatched (i.e., sent into the field) upon a Site Area Emergency or higher emergency class.

_____25 REVIEW HP RESPONSE ACTIONS AND WHEN all necessary response INITIATE RESPONSES ON A PRIORITY actions addressed, THEN GO TO BASIS: Step 37. IF HP response action(s) needed, THEN do the following: Limiting Fault event (LOCA, Main Steam Line RETURN TO Step 15. Break, SGTR or Fuel Handling Accident) occurs New radiological release occurs RETURN TO Step 20. Event at ISFSI RETURN TO Step 20. New dose assessment results available RETURN TO Step 12. Initiate EPIP-4.04. Emergency exposure authorization needed EMERGENCY PERSONNEL EXPOSURE AUTHORIZATION Establishment of HP organization GO TO Step 28. Dispatch of Offsite Monitoring Team(s) GO TO Step 29. Dispatch of Inplant/Onsite Monitoring Team(s) GO TO Step 31. Dispatch of Chemistry Team(s) GO TO Step 32. Dispatch of LEOF Monitoring Team GO TO Step 30. Establishment of Access Control Areas GO TO Step 32. Evaluation of need for respiratory protection GO TO Step 34. Issuance of radioprotective drugs GO TO Step 35. Response to injured contaminated individual(s) GO TO Step 26. Evacuation of non-essential personnel GO TO Step 36. Radiological/Meteorological parameters needed Have Attachment 1. from Main Control Room (due to unavailability Radiological Data of data to HP staff from plant computers) Worksheet, completed. Turnover duties to relief GO TO Step 27.

NUMBER PROCEDURE TITLE REVISION EPIP-4.O1 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING20

                                          ~~~~PROCEDURE                                2 PAGE L~~~~~~~~~~~~~~~                            ~~~~16                of 28

-AH- ACTION/EXPECTED RESPONSE F-H RESPONSE NOT OBTAINED 1-NOTE: First Aid considerations must be given priority over decontamination of individual. _____26 INITIATE RESPONSE TO INJURED CONTAMINATED INDIVIDUAL: a) Check if individual requires a) RETURN TO Step 25. offsite medical treatment b) Direct initiation normal HP procedure(s) for response to contaminated injured personnel c) Have RPS review personnel c) RETURN TO Step 25. contamination surveys and confirm personnel contaminated d) Check if clothing removal d) IF individual remains and/or onsite decontamination contaminated, THEN do the eliminates contamination following: AND 1) Have HP Technician accompany the individual. Internal contamination is NOT suspected 2) Recommend transport to MCV. e) RETURN TO Step 25 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.O1 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 EPIP-4.01 ~~~~PROCEDURE 2 PAGE ,~ 17 of 28 -EE ACTION/EXPECTED RESPONSE F-H RESPONSE NOT OBTAINED F-27 GIVE TURNOVER TO RELIEF: a) WHEN a more Senior Health Physics individual arrives onsite OR Relief - NEEDED, THEN brief successor on:

Existing plant conditions
Offsite release assessment performed
Health Physics actions currently underway b) Notify SEM of position change c) Have relief remain for about 30 minutes to ensure proper turnover d) RETURN TO Step 25

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING

                                             ~~~~PROCEDURE                                 20 2

PAGE l - 18 of 28 -{EE 1-ACTION/EXPECTED RESPONSE F-] . RESPONSE NOT OBTAINED _____28 ESTABLISH HP EMERGENCY ORGANIZATION: a) Establish Dose Assessment Team:

1) Assign 1 Team Leader and 2 Team Members

2) Assign EPIP-4.03, DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE b) Establish RPS position AND Assign EPIP-4.02. RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE c) RETURN TO Step 25 NOTE:

A minimum of 2 (two) Offsite Monitoring Teams must be dispatched (i.e.. sent into the field) upon a Site Area Emergency or higher emergency class.
The function of plume tracking/offsite monitoring will be the responsibility of the Radiological Assessment Coordinator upon LEOF activation.

_____29 ASSESS NEED FOR OFFSITE MONITORING: a) Evaluate need for offsite monitoring with Dose Assessment Team Leader b) Check if command and control of b) GO TO Step 29.d. Offsite Monitoring Teams has been transferred to the LEOF I c) RETURN TO Step 25 (STEP 29 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE l~~ 19 of 28 _STEP _ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 ASSESS NEED FOR OFFSITE MONITORING: (Continued) d) Have RPS initiate EPIP-4.16. OFFSITE MONITORING e) Evaluate protective measures for offsite teams:

TEDE exposure may exceed 10CFR20 annual limits:

Initiate EPIP-4.04. EMERGENCY PERSONNEL RADIATION EXPOSURE

Thyroid COE may exceed 25 Rem: Initiate EPIP-5.07.

ADMINISTRATION OF RADIOPROTECTIVE DRUGS

Consider placing teams further downwind f) Discuss provisions with RPS:

1) Number of monitoring teams required

2) Protective clothing

3) Respiratory protection

4) Standby assembly of teams.

vehicles and equipment

5) Notification of TSC prior to

                - team dispatch

6) Initial team placement

7) Relay of samples/supplies between teams and station

8) Relief of teams g) RETURN TO Step 25

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE l~~ 20 of 28 . STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _____30 ACTIVATE LEOF: a) Have RPS initiate EPIP-4.18, MONITORING OF LEOF b) Brief RAC on the following parameters:

Existing plant conditions
Current offsite dose projections
HP actions underway c) Have Dose Assessment Team Leader brief RAC on the following parameters:
Offsite dose assessment
Status and location of offsite monitoring teams d) Have Dose Assessment Team Member continue transmittal of status information to LEOF:
Meteorological data
Monitor data
Sample analysis data e) RETURN TO Step 25 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE 21 of 28 _fHH ACTION/EXPECTED RESPONSE F-A RESPONSE NOT OBTAINED F- _____31 INITIATE IN-PLANT / ONSITE MONITORING: a) Review parameters with RPS:

Plant conditions
Selection of monitoring and sample locations
Protective gear (clothing, respirators). dosimetry and special precautions for teams
Elevated radiation level readings
Access control points
Recent survey results b) Have RPS assign EPIP-4.14, INPLANT MONITORING AND EPIP-4.15, ONSITE MONITORING AND EPIP-4.17, MONITORING OF EMERGENCY RESPONSE FACILITIES AND EPIP-4.18, MONITORING OF LEOF I

(STEP 31 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.O1 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING20 PROCEDURE PAGE 22 of 28 -"E- ACTION/EXPECTED RESPONSE F-H RESPONSE NOT OBTAINED H-31 INITIATE IN-PLANT / ONSITE MONITORING: (Continued) c) Notify RPS c) GO TO Step 31.d. AND Ask for repeat survey of emergency response facilities for any of the following conditions:

Radiological release occurred
Release severity increases
Change in plume direction toward facility d) Check if survey data dictates the placement of control points to limit exposure and the spread of contamination e) RETURN TO Step 25

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE I ~~~~~~~~~~~~~~~~~~ of 28 -LH4 ACTION/EXPECTED RESPONSE [-1 . RESPONSE NOT OBTAINED F-NOTE: Stop work dose rates at the Primary Sample Room, together with other indications of fuel failure, suggest dose equivalent iodine (DEI) levels in excess of 300 Ci/mL. This is a threshold used by the SEM for event classification. _____32 INITIATE CHEMISTRY SAMPLING: I a) Check normal sample system - a) Evaluate implementation of AVAILABLE (< 300 Ci/mL DEI Contingency Plan considering anticipated) the following:

CH-94.300. HIGH RADIATION SAMPLING SYSTEM CONTROL. I
TSC Technical Support Team input (information contained in Emergency Response Guideline Executive Volume section on Evaluations by Plant Engineering Staff may support informed decision).

b) Review the following with RPS:

                . Preferred sample point

Analysis required for sample
Use of normal sampling procedures or contingency sample plan
Need to promptly report indication of stop work dose rates in the Primary Sample Room c) Have RPS assign EPIP-4.35, CHEMISTRY SAMPLING d) RETURN TO Step 25 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 20. PAGE L~~~~~~~~~~~~~ ~~~~~~24 of 28 -EIA ACTION/EXPECTE RESPONSE RESPONSE NOT OBTAINED F- _____33 ESTABLISH ACCESS CONTROL AREAS: a) Evaluate radiological hazards a) GO TO Step 34. before permitting entrance into access controlled areas b) Arrange for HP coverage of emergency evolutions directed by SEM c) Consider having RPS generate an RWP for controlled area entrance requirements d) RETURN TO Step 25 _____34 EVALUATE RESPIRATORY PROTECTION REQUIREMENTS: a) Assess results of air sample analyses b) Recommend relocation of non-essential personnel from areas where high airborne activity is expected or airborne activity > 0.30 DAC c) Initiate EPIP-4.05. RESPIRATORY PROTECTION AND KI ASSESSMENT d) RETURN TO Step 25

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE 25 of 28 AHi) ACTION/EXPECTED RESPONSE F-] RESPONSE NOT OBTAINED NOTE: Administration of Potassium Iodine Tables is preferably done prior to exposure. although administration of the drug within 2 hours is considered acceptable. _____35 DETERMINE NEED FOR ISSUANCE OF RADIOPROTECTIVE DRUGS: a) Direct initiation of EPIP-4.05, RESPIRATORY PROTECTION AND KI ASSESSMENT b) Determine if actual or b) RETURN TO Step 25. projected exposure 25 Rem Thyroid CDE c) Ask SEM for approval to c) IF approval NOT granted, THEN administer radioprotective drugs RETURN TO Step 25. d) Initiate EPIP-5.07, ADMINISTRATION OF RADIOPROTECTIVE DRUGS e) Get supply of tablets from e) Get alternate supply from Surry Health Physics Office Power Station. f) RETURN TO Step 25 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE 1 ~~~~~~~~~~~~~~~~~~ of 28 {IEH ACTION/EXPECTED RESPONSE F-I RESPONSE NOT OBTAINED H- _____36 EVALUATE NEED TO EVACUATE/SHELTER NON-ESSENTIAL PERSONNEL: a) Ask SEM for duration of release b) Determine onsite exposure of non-essential personnel:

1) Ask RPS for results of plant surveys and samples

2) Check TEDE dose in occupied areas of station

3) Determine radioiodine dose commitment from concentration (Ci/cc) based on air sample data and exposure duration:

                        .j4tCi/cc x 1.57E+6 x      hrs  =       Rem c) Check results indicate onsite           c) Do one of the following:

exposure greater than or equal to the following:

IF exposure greater than 0.5 Rem TEDE or 1 Rem Thyroid
1 Rem TEDE CDE, THEN recommend sheltering OR AND
5 Rem Thyroid CDE RETURN TO Step 25 OR
IF exposure less than 0.5 Rem TEDE and 1 Rem Thyroid CDE, THEN RETURN TO Step 25 d) Recommend that the SEM evacuate non-essential personnel I

(STEP 36 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 20 PROCEDURE PAGE L_ ~~~~~~~~~~~~~~~~~ of 28 _EH ACTION/EXPECTED RESPONSE [-A RESPONSE NOT OBTAINED 1-36 EVALUATE NEED TO EVACUATE/SHELTER NON-ESSENTIAL PERSONNEL: (Continued) e) Assist in evacuation planning:

1) Review offsite release assessments

2) Check plume direction

3) Determine appropriate evacuation route and remote assembly area f) Have RPS assign EPIP-4.21, EVACUATION AND REMOTE ASSEMBLY AREA MONITORING g) Keep SEM informed about Emergency Assembly Area monitoring status h) RETURN TO Step 25

_____37 BRIEF SEM AND RPS ON EMERGENCY STATUS AND RADIOLOGICAL TRENDS _____38 CHECK IF EMERGENCY HAS BEEN RETURN TO Step 11. TERMINATED _____39 NOTIFY RPS AND RAC OF EVENT TERMINATION _____40 CONSIDER EXTENDED USE OF MONITORING TEAMS FOR DATA COLLECTION

NUMBER PROCEDURE TITLE REVISION EPIP-4.01EPIP-4.O1 RADIOLOGICAL ASSESSMENT POEUE20 DIRECTOR CONTROLLING 2 PROCEDURE PAGE 28 of 28 -EI} F-A F-ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _____41 REVIEW RECOVERY PHASE PARAMETERS WITH SEM:

Access control to outside contaminated areas
Return to normal access control throughout site
Additional HP support personnel
Radwaste packaging and disposal
Assistance with decontamination

_____42 TERMINATE EPIP-4.01:

Give completed EPIPs, forms, and other applicable records to the Nuclear Emergency Preparedness (TSC Emergency Procedures Coordinator if TSC activated)
By:

Date: Time:

                                            - END -

NUMBER ATTACHMENT TITLE REVISION EPIP-4.01 RADIOLOGICAL DATA WORKSHEET 20 ATTACHMENT PAGE 1 1 of 1 DATE: TIME: UNIT:_ Meteorological Data: WIND DIRECTION (from): SECTORS AFFECTED: WIND SPEED (mph): PRECIPITATION: STABILITY CLASS: RADIATION SYSTEM ....MONITORING DATA VENT VENT A (VG-104) cpm (VG-179) uCi/sec VENT VENT B (VG-113) cpm (VG-180) uCi/sec \ '- PROCESS VENT (GW-102) cpm (GW-178) uCi/sec AIR EJECTOR (SV-121) cpm (SV-221) cpm VENT VENT A (VG-174) mR/hr VENT VENT B (VG-175) mR/hr PROCESS VENT (GW-173) mR/hr mR/hr MAIN STEAM: (MS-170) (MS-171) (MS-172)1 (MS-270) (MS-271) (MS-272)- AFPT: (MS-176) (MS-276) CONTAINMENT MONITORS: R/hr (RMS-161) (RMS-164) )- J(RMS-261) (RMS-264)4 (RMS-162) (RMS-165)-_ (RMS-262))- (RMS-265) (RMS-163)_ _ (RMS-166) - (RMS-263)_ (RMS-266)_

NUMBER ATTACHMENT TITLE REVISION EPIP-4.01 RESPONSE TO ISFSI EVENT 20 ATTACHMENT PAGE 2 1 of 4

1. Determine the following from Security or Operations (as appropriate):

Any restrictions affecting personnel response to ISFSI.
Readings on personal dosimetry (if available).
Any visible breach in casks, e.g.. number of casks affected.

size of breach, etc.

Any indication that cask contents dispersed from cask(s).
Any indication that cask seal(s) lost.
Estimated wind speed and direction.

2. IF simultaneous response to both plant event and ISFSI event required, THEN prioritize HP response(s) based upon potential for adverse radiological consequences.

NOTE: Dose rates from holes offset by 900 or more are not additive.

3. IF breach in cask(s) identified or anticipated. THEN do the following:

a) Notify Security to have responders avoid exposure from direction of breach. b) IF cask contents dispersed from cask(s), THEN notify Security of potential for external and internal exposure hazards. (STEP 3 CONTINUED ON NEXT PAGE)

NUMBER ATTACHMENT TITLE REVISION EPIP-4.01 RESPONSE TO ISFSI EVENT 20 ATTACHMENT PAGE l 2 2 of 4 NOTE:

The dose rate table and graph below are based on a 1-foot diameter hole. Therefore, smaller holes are bounded.
The neutron dose rate is negligible relative to the gamma dose rate. approximately 0.1X.

3. IF breach in cask(s) identified or anticipated. THEN do the following: (continued) c) Determine potential external exposure.

1) Use table or graph below for an approximate 1-foot diameter hole (Source: Calculation PA 0204):

Location Gamma Dose Rate Neutron Dose Rate (meters) (Rem/hr) (Rem/hr) Surface 5369.8 2.7804 3 57.95 0.01981 10 5.86 0.00239 50 0.19 < 0.0001 75 0.07 < 0.0001 100 0.04 < 0.0001 125 0.02 < 0.0001 DOSE RATE (Rem/hr) 10000 1000 100 10 1 0.1 0.01 0.001 0 10 20 30 40 50 60 70 80 90 100 110 120 130 DISTANCE (Meters) (STEP 3 CONTINUED ON NEXT PAGE)

NUMBER ATTACHMENT TITLE REVISION EPIP-4.01 RESPONSE TO ISFSI EVENT 20 ATTACHMENT PAGE 2l3 of 4 NOTE:

Holes larger than 1-foot diameter may not respond as a point source. Therefore, in this case the reduction in dose rates over distance would be less. Thus, the multiplier factor of 5 as shown below.
Exposure rates decrease in accordance with the inverse square rule.

3. IF breach in cask(s) identified or anticipated. THEN do the following: (continued) c) Determine potential external exposure. (continued)

2) IF more than 1 hole facing same direction, THEN calculate dose rate using the following formula:

Dose Rate from x # of holes Dose Rate, Dose Rate Table mrem/hr

3) IF hole(s) greater than 1-foot diameter. THEN multiply dose rate(s) by 5.

d) Notify the following of potential exposure determined above:

SEM
Security (via the Emergency Administrative Director when TSC activated)
RPS

4. Give the RPS guidance and direction for briefing and equipping team AW EPIP-4.15, ONSITE MONITORING.

Monitoring location and surveys required
Hazards (radiological and physical safety)
Protective gear (respirators, SCBA. protective clothing,

             - dosimetry, shielding)

Monitoring equipment (alpha and neutron survey equipment may be needed if cask contents damaged or dispersed)

IF access to ISFSI restricted, THEN notify RPS to assemble and hold team. WHEN conditions allow for dispptch of Onsite Monitoring Team. THEN have RPS coordinate approach of Onsite Monitoring Team with Security Team.

NUMBER ATTACHMENT TITLE REVISION EPIP-4.01 RESPONSE TO ISFSI EVENT 20 ATTACHMENT PAGE 2 ~~~~~~~~~~~~~~~~~4 of 4 NOTE: Most of the information needed for the Report of Radiological Conditions to the State will be unknown or not applicable, particularly early in an event at the ISFSI. Therefore. Radiological Status form Item 10. Remarks, will have to provide a description of a radiological event at the ISFSI. _ 5. Use EPIP-4.03, DOSE ASSESSMENT TEAM CONTROLLING-PROCEDURE, Attachment 1 Radiological Status, to provide the State and Local Emergency Communicator event information for transmittal to the Virginia EOC (refer to example remarks below).

IF survey information available. THEN consider remarks such as:

              .Survey results indicate affected area limited to _ meters from affected cask in a - direction. Survey readings at a distance of - meters from the affected cask are below     __

IF external exposure estimate available, THEN consider remarks such as: "Preliminary analysis indicates direct exposure hazard at meters."
IF dosimetry information available. THEN consider remarks such as: "Dosimetry readings for personnel _ meters from the affected area are below _.'
IF no information available, THEN consider remarks such as:

               "Access to the Independent Spent Fuel Storage Installation (ISFSI) is restricted due to        concerns. No radiological information is available. It is anticipated information may be available in - hours."

_ 6. Assure Dominion Nuclear Analysis & Fuel (NAF) Department notified. The NAF Fuel Performance Analysis Group is responsible for developing calculational methods for producing accident radiation doses for the ISFSI and storage casks. Results of this analysis may not be available during the accident response phase. _ 7. RETURN TO procedure in effect. I

VIRGINIA POWER NORTH ANNA POWER EMERGENCY PLAN IMPLEMENTING STATION

           ------       i-                                                 PROCEDURE NUM4BE         lAIATION                      PROCEDURE  TITLE EPIp-4.0    2 EPIP-4.02RAD                       PROTECTION SUPERVISOR                            I CONTROLLING                RYSiO PROCEDURE                                l15 l                                                                                  \
                                                   ~~~(With No Attachments)                         l       PAG l    1 of   3 PURPOSEtDrco To assist Radiological l~~

protection program AssessmentDrco during an emergencY. netbihn ineabshgterdain\ LEVEL 2 h aito

                                                                        ~~~~~~~ DI$lTRWW'IlO This Docuiment Shotu Nl le e Veried And Annorwaed C A (;uftLroied Suarce As Required o J'rtoin Work ENTRY CDITIONS\

Any one of the following:

1. ALERT or higher a en elrd emergency classification l q\ 2. Activation by has been declared.

                   ~~PROCEDURE.      EPIP-4.01, RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING

3. As deemed necessary by the Radiological Assessment Director.

Approvals on ile

     \
                                    ~~~~~~Effective Date 0r3

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE PAGE L-- ~~~~~~~~~~~~~~~~~~2 of 13 -ED4 ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED H-NOTE: A sequence of events (e.g.. data transmission, team dispatch) should be recorded as accurately as time allows. Event times and your initials should be included. _____1 INITIATE PROCEDURE:

By:

Date: Time: _____2 ESTABLISH RADIATION PROTECTION SUPERVISOR OFFICE: a) Evaluate HP area radiation levels:

1) Do surveys and sampling

2) Use frisker, personnel contamination monitors and Count Room analysis equipment to check for abnormal indications b) Verify HP area - HABITABLE: b) IF HP area NOT habitable. THEN do the following:

1) Establish RPS office in a habitable area (e.g., OSC, Emergency Switchgear Room).

2) Notify Exposure Control of new work area.

3) GO TO Step 2.d.

c) Establish RPS Office in HP Shift Supervisor area d) Establish continuous monitoring (e.g.. ratemeter, DAD)

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE 3 of 13 -ElH ACTION/EXPECTED RESPONSE [-4 . RESPONSE NOT OBTAINED F-3 ESTABLISH COMMUNICATIONS WITH TSC: a) Establish telephonic communication (e.g.. RAD, Dose Assessment) b) Establish radio communications:

1) Set radio call group to EPA"

2) Verify capability to contact 2) Notify RAD of radio TSC using radio inoperability.

NOTE: The Emergency Plan has an augmentation goal of 14 HP personnel for Alert or higher classification. _____4 NOTIFY RAD OF NUMBER OF HP PERSONNEL AVAILABLE _____5 ASK RAD FOR BRIEFING:

Emergency Classification
Plant Status
Assistance required I

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE 4 of 13 3{E~ ACTION/EXPECTED RESPONSE F-] . RESPONSE NOT OBTAINED F- _____6 ESTABLISH EXPOSURE CONTROL: a) Ensure an individual is available to staff the Exposure Control station b) Verify Exposure Control area - b) Evaluate relocation to OSC. HABITABLE c) Have Exposure Control do the following:

1) Ensure a supply of TLDs is available for issue

2) Maintain exposure records

3) Assign dosimetry in accordance with normal HP procedures I

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIAT1ON PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE I ~~~~~~~~~~~~~~~~~~ of 13 -AH ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINED F-NOTE:

The following step lists response actions coordinated by the RPS.

These actions are not listed in order of priority.

A minimum of 2 (two) Offsite Monitoring Teams must be dispatched (i.e.. sent into the field) upon a Site Area Emergency or higher emergency class.

_____7 REVIEW HP RESPONSE ACTIONS AND INITIATE RESPONSES ON A PRIORITY BASIS: IF HP response action(s) needed, THEN do the following: Inplant Monitoring GO TO Step 8. Onsite Monitoring GO TO Step 9. Offsite Monitoring GO TO Step 10. Control Room/TSC/OSC/LEOF Monitoring GO TO Step 11. Personnel injury/contamination GO TO Step 12. Evacuation Monitoring GO TO Step 13. Chemistry Sample Monitoring GO TO Step 14. Initiate EPIP-4.24, GASEOUS Gaseous effluent sampling EFFLUENT SAMPLING DURING AN EMERGENCY. Access Control Limits - EXCEEDED: Establish access control(s):

Airborne contamination exceeds 0.30 DAC
HP notification prior to entry.
Contamination 2 1000 dpm per 100 cm2
Use of RWPs.
Survey indicates 1000 mR/hr
Roping/posting affected areas.

Sample analysis results - AVAILABLE Give results to RAD. HP area habitability problem - IDENTIFIED RETURN TO Step 2. Relief shift or additional staff - NEEDED GO TO Step 15. Turnover duties to relief GO TO Step 16. Emergency - TERMINATED GO TO Step 17. I

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE 6 of 13 STEP ACTION/EXPECTED RESPONSE 4 RESPONSE NOT OBTAINED _____8 INITIATE INPLANT MONITORING: a) Ask RAD for the following:

Required monitoring locations (consider ERFs, Security and Chemistry)
Type of surveys required b) Evaluate possible radiological hazards in survey area(s) c) Assign Inplant Monitoring Team Leader and Member (only one must be an HP Technician) d) Initiate EPIP-4.14. INPLANT MONITORING e) Notify Inplant Monitoring Team Leader of the location and surveys required f) Ensure protective gear and monitoring equipment is provided, as necessary:
Respirators
Protective Clothing
Dosimetry
Monitoring Equipment
Air Sampling Equipment g) Identify routes of entry that may reduce exposure h) Assign portable radios and Radio Call Group (Radio use restricted in Radio Frequency Interference (RFI) areas.

Gai Tronics may also be used.) i) Send out team(s) j) Notify RAD of survey information, when received k) RETURN TO Step 7 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE 7 of 13 ACTION/EXPECTED RESPONSE HRESPONSE NOT OBTAINED NOTE: Onsite monitoring teams should be dispatched upon an Alert classification, or as specified by Radiological Assessment Director. _____9 INITIATE ONSITE MONITORING: a) Ask RAD for the following:

Monitor location
Surveys required
Radiological Hazards b) Coordinate transportation (if required):
Health Physics truck
Site Vice President's Vehicle
Station Manager's Vehicle c) Assign On-site Monitoring Team Leader and Member (only one must be an HP Technician) d) Initiate EPIP-4.15, ONSITE MONITORING e) Notify Onsite Team leader of location and surveys required f) Ensure protective gear and monitoring equipment is provided, as necessary:
Respirators
Protective Clothing
Dosimetry
Monitoring Equipment
Air Sampling Equipment g) Assign Radio Call Group h) Send out monitoring team(s) i) Establish radio contact with monitoring team(s) j) Notify RAD of survey information, when received k) RETURN TO Step 7

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE Il~~ 8 of 13 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Two Offsite Monitoring Kits. one Onsite Monitoring Kit and one Remote Assembly Area Monitoring Kit are located in the Exposure Control Facility. _____10 INITIATE OFFSITE MONITORING: a) Ask RAD for the following:

1) Offsite monitoring locations

2) Number of offsite teams

3) Assessment of offsite radiological hazards

4) Assessment of need to issue radioprotective drugs to monitoring teams b) Assign Offsite Monitoring Team Leader and Member (only 1 need be an HP Technician) c) Initiate EPIP-4.16. OFFSITE MONITORING d) Assist in obtaining vehicle:

Health Physics truck
Site Vice President's Vehicle
Station Manager's Vehicle e) Assign emergency kit/equipment:
Battery powered air sampler
RM-14 with H.P. 210 probe
Record number of Emergency Kits issued f) Give team briefing (include initial reporting location) g) Review protective gear required:
Respirator and/or radioprotective drugs
Protective clothing
Dosimetry h) Assign Radio Call Group i) Send out Monitoring Team(s) j) RETURN TO Step 7

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE 9 of 13 4H ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED H-NOTE: Monitoring of emergency response facilities (ERFs) should begin within 60 minutes following an ALERT classification. _____11 INITIATE CONTROL ROOM/TSC/OSC/LEOF MONITORING: a) Evaluate the following when determining monitoring frequency:

Spread of contamination from service buildings
Status of effluent release
Increase in emergency classification
Change in plume direction b) Assign the following EPIP(s):
EPIP-4.17. MONITORING OF EMERGENCY RESPONSE FACILITIES
EPIP-4.18. MONITORING OF LEOF
EPIP-4.28. TSC/LEOF RADIATION MONITORING SYSTEM c) Notify RAD about ERF habitability and survey results d) RETURN TO Step 7 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE 10 of 13 ACTION/EXPECTED RESPONSE H-] _ RESPONSE NOT OBTAINED 1- _____12 CHECK PERSONNEL - CONTAMINATED: RETURN TO Step 7. a) Check personnel - INJURED a) GO TO Step 12.c. b) Initiate normal station HP procedure for responding to contaminated injured personnel c) Assign EPIP-4.06. PERSONNEL MONITORING AND DECONTAMINATION d) Update RAD on status e) RETURN TO Step 7 NOTE: EPIP-4.21. EVACUATION AND REMOTE ASSEMBLY AREA MONITORING, contains instructions for surveying parking areas to determine contamination levels prior to evacuation if a radiological release occurred and time is available. _____13 INITIATE EVACUATION MONITORING: a) Initiate EPIP-4.21. EVACUATION AND REMOTE ASSEMBLY AREA MONITORING b) Notify RAD when team is dispatched c) RETURN TO Step 7 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15.

.PI114of21PROCEDURE3 PAGE L~~~~~~~~~~~~~~~~                       ~~~~11                of 13 i{~             ACTION/EXPECTED RESPONSE      I           RESPONSE NOT OBTAINED F-

_____14 INITIATE CHEMISTRY SAMPLING: a) Consult with RAD about the following:

Preferred sample point
Analysis required for sample
Use of normal sampling procedures or contingency sample plan b) Assign in-plant survey to determine dose rate at sample station c) Notify RAD of survey results d) Initiate RWP (if required) e) Initiate EPIP-4.35. CHEMISTRY SAMPLING f) Ensure HP coverage available during sampling and sample preparation g) RETURN TO Step 7

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE .~~ 12 of 13 -AEH H-ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _____15 EVALUATE NEED FOR ADDITIONAL PERSONNEL: a) Ask RAD about projected duration of emergency b) Check relief shift and/or b) RETURN TO Step 7. additional personnel - NEEDED c) Prepare relief schedule and/or increased staffing schedule d) Give schedule to RAD for approval e) Initiate callout of scheduled personnel (if needed) f) Notify RAD when callout complete g) RETURN TO Step 7 _____16 CHECK TURNOVER - REQUIRED (due to arrival of a more senior HP representative or relief): a) Provide successor briefing on plant conditions and HP actions underway b) Notify RAD of position change c) Stay with relief for approximately 30 minutes d) RETURN TO Step 7 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.02 RADIATION PROTECTION SUPERVISOR CONTROLLING 15 PROCEDURE PAGE 13 of 13 F-A F-3{H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _____17 TERMINATE EMERGENCY RESPONSE: a) Notify HP staff when emergency is terminated b) Review recovery actions with RAD c) Maintain access control as required d) Initiate replacement of procedures and equipment used during the emergency _____18 TERMINATE EPIP-4.02: a) Give completed EPIP-4.02. all other applicable EPIPs, forms and records to the Radiological Assessment Director b) Completed By: Date: Time:

                                         - END -

I

VIRGINIA POWER NORTH ANNA POWER STATION EktERENCY PLAN IMPLEMENTING POCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 (With 6 Attachments) PAGE 1 of 12 PURPOSE Provide guidance and data to Dose Assessment Team to more accurately predict offsite releases. ENTRY CONDITIONS Any of the following:

1. Entry from EPIP-4.01, RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE.

2. Entry from EPIP-4.03, DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE.

Approvals on file Effective Date / 3

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 PAGE L- ~~~~~~~~~~~~~~~~~~2 of 12

-fHH~~ACTION/EXPECTED            RESPONSE                  RESPONSE NOT OBTAINED      F-

_____1 INITIATE PROCEDURE:

By:

Date: Time: NOTE:

Source term is expressed in Ci/sec.
Source term calculations derived from monitor readings should be used only for initial assessment and to establish trends. Sampling should also be performed to more accurately determine the source term.
Source term derived from Containment High Range Monitors or Containment sampling is used for analysis following a LOCA.

Sampling of Containment atmosphere following a LOCA should be considered after plant conditions have stabilized only. 2 DETERMINE METHOD FOR SOURCE TERM CALCULATION:

Station Monitors - GO TO Step 3
Sample Effluent - GO TO Step 4
Sample of Station Inventory - GO TO Step 7
Containment High Range Monitor (Inner Crane Wall) - GO TO Step 8
Sample of Containment Air - GO TO Step 9 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 PAGE 3 of 12 -iE ACTION/EXPECTED RESPONSE [-1 RESPONSE NOT OBTAINED F-NOTE:

The following monitors may used until removed by Design Change 99-006, Ventilation Radiation Monitoring System Replacement:

GW-102. VG-104. VG-113. GW-173, VG-174 and VG-175.

MGPI Normal Range Noble Gas monitors: 178-1. 179-1 and 180-1.

MGPI High Range Noble Gas monitors: 178-2. 179-2 and 180-2.

Should Vent Vent or Process Vent Normal Range monitors be inoperable or offscale. assessments should continue using High Range and/or MGPI monitors.
The Condenser Air Ejector may be diverted to containment.

_____3 DETERMINE SOURCE TERM FROM STATION MONITORS: a) Get monitor readings and a) IF monitor readings NOT effluent flow rates (cfm) for available, THEN GO TO Step 4. release pathways of concern:

Vent Vent A: VG-104. VG-179, VG-174
Vent Vent B: VG-113. VG-180.

VG-175

Process Vent: GW-102, GW-178.

GW-173

Condenser Air Ejector:

SV-121, SV-221

Main Steam:

MS-170. MS-171. MS-172. MS-270. MS-271, MS-272

AFWPT: MS-176, MS-276 l

(STEP 3 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 PAGE l 4 of 12 -EAH - ACTION/EXPECTED RESPONSE F-I . RESPONSE NOT OBTAINED F-3 DETERMINE SOURCE TERM FROM STATION MONITORS: (Continued) b) Record the following information on Attachment 1:

Date
Time
Flow rate (when applicable) and monitor reading for pathway(s) of concern:

Normal Range: cpm (use NET cpm: Gross - Background) MGPI: pCi/sec or 1+/-Ci/cc High Range: mR/hr c) Determine accident type d) Determine status of effluent charcoal filtration e) Determine Monitor Conversion Factors (MCF) and Iodine Conversion Factors (Iodine CF) using Attachment 2 f) Record conversion factors on Attachment 1 g) Use Attachment 1 to calculate Iodine and Noble Gas release rates. Ci/sec h) Add Ci/sec for all pathways of concern AND Record results at end of 7 Attachment 1 i) Give results to RAD or RAC

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 PAGE L- ~~~~~~~~~~~~~~~~~5 of 12 -EK{ ACTION/EXPECTED RESPONSE H-] . RESPONSE NOT OBTAINED H-NOTE:

In the event that a release involves multiple pathways. Step 4 should be repeated for each pathway. Results of each analysis are then added to determine the total source term.
The Condenser Air Ejector may be diverted to containment.

eliminating need to assess source term. _____4 DETERMINE SOURCE TERM FROM EFFLUENT SAMPLE: a) Ask Radiation Protection a) IF source term determination Supervisor to initiate from effluent sample NOT EPIP-4.24. GASEOUS EFFLUENT required, THEN GO TO Step 7. SAMPLING DURING AN EMERGENCY. for sample of appropriate pathway:

Vent Vent A
Vent Vent B
Process Vent
Condenser Air Ejector b) Get monitor reading:
Maximum:_
Reading at time of sample:

c) Have Count Room analyze sample:

Request initiation of EPIP-4.26. HIGH LEVEL ACTIVITY SAMPLE ANALYSIS, for high activity samples I

(STEP 4 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 PAGE . - 6 of 12 -EKq F-] F-

           -                                         P      -

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 DETERMINE SOURCE TERM FROM EFFLUENT SAMPLE: (Continued) d) Record nuclide activity on Attachment 3. left column AND Add results to determine Noble Gas and Iodine gross activity, pjCi/ml e) Check if this is an initial e) GO TO Step 4.g. source term assessment f) Check if sample taken at f) IF sample NOT taken at maximum maximum monitor reading monitor reading. THEN do the following:

1) Determine corrected pCi/cc for gross Noble Gas and for Iodine:

MAX READING x Ci - CORRECTED

                                                                           -- -      jci/cc READING AT       cc TIME OF SAMPLE

2) Record results on Attachment 4.

3) GO TO Step 4.h.

g) Get Noble Gas activity from Attachment 3 and record activity on to Attachment 4 h) Get effluent flow rate (cfm) i) Record cfm on Attachment 4 j) Record Iodine activity on Attachment 4 (STEP 4 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 PAGE 7 of 12 -E3q ACTION/EXPECTED RESPONSE [-1 . RESPONSE NOT OBTAINED F-4 DETERMINE SOURCE TERM FROM EFFLUENT SAMPLE: (Continued) k) Use Attachment 4 to calculate Noble Gas and Iodine source term (Ci/sec)

1) Add Ci/sec for applicable pathways at end of Attachment 4

_____5 DETERMINE DDE. TEDE AND THYROID CDE DOSE CONVERSION FACTORS BASED ON SAMPLE RESULTS: a) Use Attachment 3 that was a) Do Steps 4.a through 4.d previously filled out for gross activity determination AND GO TO Step 5.b. b) Do calculations on Attachment 3 to determine the following conversion factors:

Sample DDE DCF
Sample TEDE DCF
Sample THY CDE DCF c) Determine TEDE/DDE ratio:

TEDE DCF = Ratio TEDE/DDE DDE DCF d) Give source term results. Ci/sec, and TEDE/DDE ratio to RAD or RAC I

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENt 14 PAGE 1 ~~~~~~~~~~~~~~~~~~ of 12 -EEH ACTION/EXPECTED RESPONSE 1-I RESPONSE NOT OBTAINED I- _____6 DETERMINE SITE BOUNDARY DOSE RATES BASED ON EFFLUENT SAMPLE RESULTS: a) Ask RAD or RAC if Site Boundary a) GO TO Step 7. dose rate calculation based on effluent sample - DESIRED b) Record TEDE and THY CDE DCFs from bottom of Attachment 3 on to Attachment 5:

Record on calculation line for each affected pathway c) Get effluent flow rate (cfm) for each affected pathway d) Record CFM on Attachment 5 NOTE:
Main Tower Delta T is the preferred source of stability class.

Sigma Theta (Backup Tower) is the secondary source.

Primary source of wind speed is the Main Tower Lower Level indicator. Alternates sources are (1) Backup Tower, and (2)

Main Tower Upper Level. e) Determine Stability Class and wind speed:

Ask RAD or RAC f) Use Attachment 5 Site Boundary X/Q value for appropriate Stability Class and divide by wind speed g) Record corrected X/Q value on calculation line for each affected pathway h) Do calculations to determine I Site Boundary TEDE and THY CDE dose rate. mrem/hr i) Give results to RAD or RAC

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 PAGE 9 of 12 -EH F-A F-ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _____7 DETERMINE SOURCE TERM FROM STATION INVENTORY: a) Check if release originated a) GO TO Step 8. from a gas storage tank (ie. Waste Gas Decay Tank. Volume Control Tank. etc.) b) Have tank sampled c) Ask Dose Assessment Team Leader to get information on volume of release from Emergency Technical Director d) Get sample activity results, pCi/ml. for total of Noble Gas and Iodine:

Use Count Room results or completed Attachment 3 e) Record the following on Attachment 4:
Noble Gas activity
Iodine activity
Volume of release, ml
Duration of release, sec f) Use Attachment 4. Station Inventory section, to determine Nobfe Gas and Iodine release rate, Ci/sec g) Give results to RAD or RAC

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 PAGE L~~~~~~~~~~~~~~~~ ~~~~10 of 12 H-t ACTION/EXPECTED RESPONSE k-H RESPONSE NOT OBTAINED F- _____8 DETERMINE SOURCE TERM FROM CONTAINMENT HIGH RANGE MONITOR (INNER CRANE WALL): a) Check if LOCA conditions exist a) GO TO Step 10. b) Get dose rate (R/hr) from Containment High Range Monitor (Inner Crane Wall) of affected unit:

Unit 1 Higher of RMS-165 or RMS-166:_
Unit 2 Higher of RMS-265 or RMS-266:_

C) Determine length of time (hours) since unit shutdown d) Use Attachment 6 to estimate Curies Noble Gas (Ci NG) and Curies Iodine (Halogens) available for release e) Calculate release rate: Ci Noble Gas x 4.35E-8 = Ci/Sec Noble Gas Ci Iodine x 4.35E-8 = Ci/sec Iodine f) Give results to RAD or RAC I

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 PAGE 11 of 12 -BEEN ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED H- _____9 DETERMINE SOURCE TERM FROM CONTAINMENT AIR SAMPLE: a) Check if LOCA conditions exist a) GO TO Step 10. b) Check plant conditions - STABLE b) Wait until plant conditions are stable before taking sample. c) Check normal sample system - c) Evaluate implementation of AVAILABLE (< 300 tCi/mL DEI Contingency Plan considering anticipated) the following:

CH-94.300. HIGH RADIATION SAMPLING SYSTEM CONTROL.
TSC Technical Support Team input (information contained in Emergency Response Guideline Executive Volume section on Evaluations by Plant Engineering Staff may support informed decision).

d) Determine the following:

Preferred sample point
Analysis required for sample
Use of normal sampling procedures or contingency sample plan e) Ask RPS assign EPIP-4.35, CHEMISTRY SAMPLING f) Record sample results (nuclide concentration) on Attachment 3, left column g) Determine gross activity, pCitml, for Noble Gas and Iodine h) Calculate release rates:

pCi/ml x 2.25E+3 x 1.OE-6 = Ci/Sec i) Record results Ci/sec Noble Gas Ci/sec Iodine I j) Give results to RAD or RAC

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 14 PAGE L~~~~~~~~~~~~~~~~ ~~~~12 of 12 Hi{- 1-I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H- _____10 TERMINATE EPIP-4.09:

Give completed EPIP-4.09, forms, and other applicable records to the Radiological Assessment Director
Completed by:

Date: Time:

                                         -END -

I

NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 MONITOR Ci/sec WORKSHEET 14 ATTACHMENT PAGE 1 1 of 2 NOTE:

Monitor Conversion Factors (MCF) and Iodine Conversion Factors (Iodine CF) are provided on Attachment 2.
MGPI Normal Range Noble Gas monitors: 178-1. 179-1 and 180-1. MGPI High Range Noble Gas monitors: 178-2, 179-2 and 180-2.

Date: : Time:_ IODINE NOBLE GAS VENT VENT A: - C1/sec Ci/sec CPM x MCF x CFM - Cl/sec Highest Ci/sec VG-104: x x - { r H & r ~~~~~Ci/sec NGl VG-179: pCi/sec x MCF x 1.OOE-6 - Ci/sec l I/sec NG1 (-1.-2) x x l.OOE-6 - I X MINUS ! VG-179: pCi/cc x MCF x CFM x 4.72E Cl/sec IODINE CF l Ci/sec lod.l (-l.-2) _________ x -_ x x 4.72E-4 - l (Att. 2): -- VG-174: mR/hr x x MCF x x CFM - Cl/sec

                                                                   -         1                                 -

VENT VENT B: CPM x MCF x CFM - Ci/sec Highest C/sec VG-113: x x i rC1 - Ci/sec NGI VG-lAO: pCi/sec x MCF x 1.OOE-6 - Ci/sec

                                                                      =        ~~~~~~~~~~~I l

(-1.-2) x x l.OOE-6 X MINUS I VG-180: pCi/cc x MCF x CFM x 4.72E-4 - Ci/sec I IIODINE CF I ICi/sec lod.l (-I.-2) x x x 4.72E-4 - I I(Att. 2): ! I I I I I I I I mR/hr x MCF x CFM - Ci/sec I VG-175: x x AIR EJECTOR: CPM x MCF x CFM -i Cl/sec SV-121: _ _ _ _ _ x _ _ _ _ x __ _ _ _ _ CPM x MCF x CFM -l Ci/sec SV-221: x x - SUM Ci/sec Ci/sec NG MINUS IODINE CF C1/sec lod.j i X - (Att. 2):j-

NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 MONITOR Ci/sec WORKSHEET 14 ATTACHMENT PAGE L 1 2 of 2 IODINE NOBLE GAS PROCESS VENT: Cl/sec Ci/sec CPM x MCF x CFM - Ci/sec Highest Ci/sec GW-102: x x r I m i 1 r -jCi/sec NGI GW-178: gCi/sec x MCF x 1.00E-6 - Ci/sec (-I.-2) _ _ x x .OOE-6 XI MINUS I I GW-1J8: pCi/cc x MCF x CFM x 4.72E Ci/sec IODINE CF Ci/sec Iod.l (-1.-2) x x _ x 4.72E (Att. 2): - I mR/hr x MCF x CFM - Ci/sec GW-173: x x MAIN STEAM: mR/hr x f valves HCF Ci/sec SUM OF Ci/sec MS-170: x x - - MS-171: x x = - r - ci/sec NGI MS-172 : _ _ x _ _ x _ _ ---- -- I___ MS-270: x x - l X MINUS MS-271: x x - ' r ' --- '-- MS-272: x x - l l IODINE CF ICi/sec lod.l (Att. 2): ! AFWPT: mR/hr x MCF Ci/sec SUM OF Ci/sec MS-176: x I -I II MS-276: x H I I r fCi/sec NGI XI MINUS I IIODINE CF I I Ci/sec Iod.; l (Att. 2): - I I

                                                                         !                  I I                     I TOTAL Curies/sec: Sum above results for Iodine and for Noble gas (separately).

I TOTAL I I TOTAL I ICi/sec 1001 ICi/sec NGI I I I I Completed by: II II II II Date/Time: / I

NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 MONITOR CONVERSION FACTORS 14 ATTACHMENT AND IODINE CONVERSION FACTORS PAGE _ _ _ _2 1 of 2 NOTE: The following monitors may be used until removed by Design Change 99-006. Ventilation Radiation Monitoring System Replacement: VG-104 and VG-174. MONITOR CONVERSION FACTORS (MCF) for Vent Vent A: MONITOR MSLB SGTR NORMAL VG-104 9.7E-11 7.OE-11 4.7E-11 VG-174 2.4E-2 1.8E-2 1.1E-2 VG-179-1 8.8E-4 8.6E-4 8.1E-4 VG-179-2 1.OE-3 1.OE-3 1.1E-3 NOTE: The following monitors may be used until removed by Design Change 99-006. Ventilation Radiation Monitoring System Replacement: VG-113 and VG-175. MONITOR CONVERSION FACTORS (MCF) for Vent Vent B: MONITOR FHA LOCA MELT LOCA GAP LOCA PC NORMAL VG-113 1.4E-11 4.OE-11 4.3E-11 1.9E-11 1.4E-11 VG-175 5.9E-2 1.8E-3 1.7E-3 4.1E-3 5.8E-2 VG-180-1 9.2E-4 7.9E-4 8.2E-4 8.5E-4 9.2E-4 VG-180-2 1.OE-3 7.3E-3 6.8E-3 1.5E-3 1.OE-3 MONITOR CONVERSION FACTORS (MCF) for Air Ejector: MONITOR MSLB SGTR NORMAL SV-121,-221 3.1E-7 2.2E-7 1.4E-7 (CONTINUED ON NEXT PAGE) I

NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 MONITOR CONVERSION FACTORS 14 ATTACHMENT AND IODINE CONVERSION FACTORS PAGE 2 ______________ ~~~~~~~~~~~~2 of _2 NOTE: The following monitors may be used until removed by Design Change 99-006. Ventilation Radiation Monitoring System Replacement: GW-102 and GW-173. MONITOR CONVERSION FACTORS (MCF) for Process Vent: MONITOR WGDT VCT NORMAL GW-102 6.1E-11 1.1E-10 2.3E-10 GW-173 5.OE-2 2.3E-2 2.7E-2 GW-178-1 7.7E-4 9.OE-4 9.3E-4 GW-178-2 1.1E-3 1.OE-3 1.1E-3 MONITOR CONVERSION FACTOR (MCF) for Main Steam: MONITOR MSLB SGTR LKD. ROTOR NORMAL MS-1(2)70 MS-1(2)71 5.3E+O 6.9E+O 3.9E-1 5.7E+O MS-1(2)72 MONITOR CONVERSION FACTORS (MCF) for AFWPT: MONITOR LOCA MELT LOCA GAP LOCA PC MS-176 1.9E+O 4.2E+O 4.3E-1 MS-276 2.6E+O 5.7E+O 5.6E-1 IODINE CONVERSION FACTORS (ICF): OAML .iO L.C GA AP K. OO MSL FH .GT MSLB SGTR FHA WGDT LOCA MELT LOCA GAP LOCA PC LKO. ROTOR UNFILTERED Z.OE-1 5.IE-3 2.4E-3 1.bE-5 S.4E-1 8.8E-2 6.2E-2 2.6E-1 FILTERED 5.4E-4 I 5.2E-5 2.4E-4 1.8E-6 S.4E-2 8.8E-3 6.2E-3

NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 NOBLE GAS, IODINE AND DOSE CONVERSION ACTOR WORKSHEEI 14 ATTACHMENT USING SAMPLE ANALYSIS RESULTS PAGE 3 1 of 1 Sample Identification: Sample Time: NOTE:

Total Noble Gas and Iodine activity, pCi/ml, are for use on Attachment 4.
Total TEDE DCF and THY CDE DCF are for use on Attachment 5.

NUCLIDE ACTIV. EPA SAMPLE EPA SAMPLE EPA pCi/ml DDE DDE TEDE TEDE THY CDE DCF DCF DCF Kr-83M NA Kr-85 x 1.3 xl1 Kr-85M x 93 xl1 Kr-87 x 510 xl1 Kr-88 x 1300 xl1 Kr-89 x 1200 xl1 Xe-131M x 4.9 xl1 Xe-133 x 20 xl1 Xe-133M x 17 xl1 Xe-135 x 140 xl1 Xe-135M x 250 xl1 Xe-137 x 110 xlI Xe-138 x 710 xl1 TOTAL NOBLE GAS. Ci/ml: CONTINUE CONTINUE ADDING ADDING DOWN DOWN I I 1-125 x 6.3 x 4762 x 32 = I-129 x 4.8 x 43750 x 33 = 1-131 x 220 x 241 x 24.5 = I-132 x 1400 x 3.5 x 1.6 = I-133 x 350 x 43 x 14.6 = I-134 x 1600 x 1.9 x 0.43 = 1-135 x 950 x 8.5 x 4.7 = TOTAL IODINE, pCi/ml: TOTAL TOTAL DDE DCF: TEDE DCF: Completed by: Date/Time: /

NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 SAMPLE EFFLUENT Ci/sec WORKSHtET 14 ATTACHMENT PAGE 4 1 of 1 Ci/sec MONITOR MCi/Iml CFM NOBLE GAS IODINE VV A: N.G. x CFM x 4.72E-4 x x 4.72E-4 IOD. x CFM x 4.72E-4 x x 4.72E-4 VV B: N.G. x CFM x 4.72E-4 x x 4.72E-4 IOD. x CFM x 4.72E-4 x x 4.72E-4 PV: N.G. x CFM x 4.72E-4 x x 4.72E-4 = IOD. x CFM x 4.72E-4 x x 4.72E-4 AIR EJECTOR #1: N.G. x CFM x 4.72E-4 x x 4.72E-4 IOD. x CFM x 4.72E-4 x x 4.72E-4 AIR EJECTOR #2: N.G. x CFM x 4.72E-4 x x 4.72E-4 IOD. x CFM x 4.72E-4 x x 4.72E-4 STATION INVENTORY: N.G. x VOLUME (mis) x 1.OE-6 / SECONDS x x 1.OE-6 / SCN= I00. x VOLUME (mis) x 1.OE-6 I SECONDS x x 1.OE-6 / __= SUM Ci/sec: NG IOD Completed by: by: I Date: Completed Time:

NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 SAMPLE EFFLUENT SITE BOUNDARY DOSE RATE WORKSHEET 14 ATTACHMENT PAGE L 5 1 of 1 NOTE: TEDE and Thyroid CDE factors from Attachment 3 are to be applied to this worksheet. X/O, SITE BOUNDARY: I STABILITY CLASS TEDE OCF OR X/O TEDE THY. CDE MONITOR THY COE DCF CFM WINOSPEED mrem/hr mrem/hr VV A: TEDE x CFM x 4.72E-1 x X/O/WINDSPEED x x 4.72E-1 x THY CDE x CFM x 4.72E-I x X/O/WINDSPEEO _ __ __ x x 4.72E-1 x VV B: TEDE x CFM x 4.72E-1 x X/O/WINDSPEEO x x 4.72E-1 x THY CDE x CFM x 4.72E-1 x X/O/WINDSPEED _ __ x x 4.72E-1 x PV: TEDE x CFM x 4.72E-1 x X/0/WINDSPEED _ __ x x 4.72E-I x THY CDE x CFM x 4.72E-I x X/O/WINDSPEED _ _ __ _ x x 4.72E-I x AIR EJECTOR #: TEDE x CFM x 4.72E-I x X/O/WINDSPEED _ __ _ __ x x 4.72E-1 x THY CDE x CFM x 4.72E-I x X/O/WINDSPEED _ _ ___ x x 4.72E-1 x AIR EJECTOR #2: TEDE x CFM x 4.72E-1 x X/O/WINDSPEED _ __ _ __ x x 4.72E-I x THY CDE _x CFM x 4.72E-I x X/O/WINDSPEED x x 4.72E-I x STATION INVENTORY: TEDE x VOLUME (mis) x 1.OE-3 / SECONDS x X/O/WINDSP. __ x x 1.OE-3 / _ x _ - THY CDE x VOLUME (ms) x I.OE-3 / SECONDS x X/O/WINDSP. _ _ x x 1.OE-3 / x - Completed by: SUM mrem/hr: TEDE THY CDE Date/Time: /

NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 MATRIX: 14 ATTACHMENT PAGE CHRRMS - EVENT - AVAILABLE CUIIES 6 1 of 2

                                 -~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

NOTE: No letdown or sprays are assumed available. Containment Air concentration (i/cc) - Ci Cont. Air x 1.92E-5. 0 RCS concentration (Ci/cc) - Ci Cont. Air x 3.765E-3. Data is given for 0. 1 2 and 4 hours after LOCA occurs. HOURS CHRRMS EVENT DESCRIPTION Ci N.G. Ci IODINE RCS AFTER R/hr Cont. Air (HALOGEN) D.E. I-131 LOCA Cont. Air pCi/ml 0 1.5E+6 100% NG. 50 HAL 8.2E+8 Ci 4.4E+8 Ci 1.99E+5 Released to Cont. Air pCi/ml 1.5E+5 10% NG. 5% HAL 8.2E+7 Ci 4.4E+7 Ci 1.99E+4 Released to Cont. Air pCi/ml 1.5E+4 1% NG, .5% HAL 8.2E+6 Ci 4.4E+6 Ci 1.99E+3 Released to Cont. Air pCi/ml 1.9E+3 100% GAP 1.74E+6 Ci 1.59E+6 Ci 2.76E+3 Released to Cont. Air pCi/ml 1.9E+2 10% GAP 1.74E+5 Ci 1.59E+5 Ci 2.76E+2 Released to Cont. Air pCi/ml 1.9E+1 1% GAP 1.74E+4 Ci 1.59E+4 Ci 2.76E+1 Released to Cont. Air pCi/ml 9.0 1% Failed Fuel 6.12E+4 Ci 2.OOE+3 Ci 2.40E+O Primary Gas Release pCi/ml HOURS C RRMS EVENT DESCRIPTION Ci N.G. Ci IODINE AFTER R/hr Cont. Air (HALOGEN) LOCA Cont. Air Lr 5.5E+5 100% NG, 50% HAL Released to Cont. Air 3.57E+8 Ci 2.72E+8 Ci 5.5E+4 10% NG, 5% HAL 3.57E+7 Ci 2.72E+7 Ci Released to Cont. Air 5.5E+3 1% NG. .5% HAL 3.57E+6 Ci 2.72E+6 Ci Released to Cont. Air 1.75E+3 100% GAP 1.69E+6 Ci 1.45E+6 Ci Released to Cont. Air 1.75E+2 10% GAP 1.69E+5 Ci 1.45E+5 Ci Released to Cont. Air 1.75E+1 1% GAP 1.69E+4 Ci 1.45E+4 Ci Released to Cont. Air 8.0 1% Failed Fuel 6.01E+4 Ci 1.84E+3 Ci Primary Gas Release

NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 MATRIX: 14 ATTACHMENT PAGE CHRRMS - EVENT - AVAILABLE CURIES 6 2 of 2 NOTE:

No Letdown or Sprays are assumed available.

Containment Air concentration (Ci/cc) - Ci Cont. Air x 1.92E-5. 0 RCS concentration (Ci/cc) - Ci Cont. Air x 3.765E-3. Data is given for 0, 1, 2 and 4 hours after LOCA occurs. HOURS CHRRMS EVENT DESCRIPTION Ci N.G. Ci IODINE AFTER R/hr Cont. Air (HALOGEN) LOCA Cont. Air 2 4.OE+5 100% NG. 50% HAL 3.14E+8 Ci 2.26E+8 Ci Released to Cont. Air 4.OE+4 10% NG. 5% HAL 3.14E+7 Ci 2.26E+7 Ci Released to Cont. Air 4.OE+3 1% NG. .5% HAL 3.14E+6 Ci 2.26E+6 Ci Released to Cont. Air 1.5E+3 100% GAP 1.65E+6 Ci 1.37E+6 Ci Released to Cont. Air 1.5E+2 10% GAP 1.65E+5 Ci 1.37E+5 Ci Released to Cont. Ai r 1.5E+1 1X GAP 1.65E+4 Ci 1.37E+4 Ci _ ~Released to Cont. Air_ 7.5 1% Failed Fuel 6.OOE+4 Ci 1.73E+3 Ci Primary Gas Release HOURS 'CHRRMS EVENT DESCRIPTION Ci N.G. Ci IODINE AFTER R/hr Cont. Air (HALOGEN) LOCA Cont. Air 4 2.75E-i5 100% NG, 50% HAL 2.70E4-8 Ci 1.78E+8 Ci Released to Cont. Air 2.75E+4 10% NG, 5% HAL 2.70E+7 Ci 1.78E+7 Ci Released to Cont. Air 2.75E+3 1% NG. .5% HAL 2.70E+6 Ci 1.78E+6 Ci Released to Cont. Air 1.2E+3 100% GAP 1.59E+6 Ci 1.25E+6 Ci Released to Cont. Air 1.2E+2 10% GAP 1.59E+5 Ci 1.25E+5 Ci Released to Cont. Air 1.2E+l 1% GAP 1.59E+4 Ci 1.25E+4 Ci Released to Cont. Air 7 1% Failed Fuel 5.85E+4 Ci 1.56E+3 Ci Primary Gas Release

VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-4.26 HIGH LEVEL ACTIVITY SAMPLE ANALYSIS 12 (With 2 Attachments) PAGE 1 of 6 PURPOSE To provide guidance for a nalyzn i durin Rng PM m gency. This D)ocumnent Should Be Verified And Annotated To A Controlled Source As Required to Perforn Work ENTRY CONDITIONS Any one of the following:

1. Activation by EPIP-4.35. CHEMISTRY SAMPLING.

I

2. Activation by another EPIP.

3. Detector dead time exceeds 10X.

4. Sample activity greater than 10 mrem/hr.

Approvals on file Effective DateA c3

NUMBER PROCEDURE TITLE REVISION EPIP-4.26 HIGH LEVEL ACTIVITY SAMPLE ANALYSIS 12 - PAGE 2 of 6 r4IE ACTION/EXPECTED RESPONSE F-H RESPONSE NOT OBTAINED p-n _____1 INITIATE PROCEDURE:

By:

Date: Time: _____2 VERIFY HP COUNT ROOM AREA IF use of alternate analysis RADIATION LEVELS PERMIT SAMPLE facility required, THEN establish ANALYSIS alternate analysis facility in Admin Annex HP Lab. IF alternate facility NOT available. THEN do the following: a) Ask RPS for assistance in preparation for sample shipment offsite. b) GO TO Step 13. NOTE: Gross failure of fuel cladding may yield significant quantities of noble gases or volatiles, as well as fission products, in the sample. Use of protective clothing and respiratory protection is advisable during sample preparation. _____3 ACTIVATE RWP FOR POST-ACCIDENT IF NOT analyzing a post-accident SAMPLE OF REACTOR COOLANT OR reactor coolant or containment air CONTAINMENT AIR sample, THEN ask RPS to assess need for RWP. I

NUMBER PROCEDURE TITLE REVISION EPIP-4.26 HIGH LEVEL ACTIVITY SAMPLE AALYSIS 12 PAGE 1 ~~~~~~~~~~~~~~~~~ of 6 H-AHH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _____4 DETERMINE RESPONSE ACTIONS BASED ON SAMPLE ACTIVITY LEVEL: IF the following condition exists: THEN do the following: Sample activity GREATER THAN GO TO Step 6. 1000 mR/hr Sample activity GREATER THAN a. Take sample to Hot Lab or HRSS hood. 10 mR/hr (but LESS THAN 1000 mR/hr) b. GO TO Step 5. Sample activity yields GREATER a. Take sample to Hot Lab or HRSS hood. THAN 10% detector dead time b. GO TO Step 5. Sample activity LESS THAN 10 mR/hr a. Take sample to Count Room.

b. GO TO Step 11.

_____5 DETERMINE FOLLOW-UP ACTIONS:

Dilute sample: GO TO Step 6
Allow sample to decay: GO TO Step 9
Reduce sample volume: GO TO Step 10
Analyze sample in elevated position: GO TO Step 12 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.26 HIGH LEVEL ACTIVITY SAMPLE ANALYSIS 12 PAGE 4 of 6 F-] F-HH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _____6 VERIFY LIQUID OR GAS SAMPLE TO BE IF diluting radioiodine or DILUTED: particulate air sample, or if sample dilution is NOT acceptable. a) Use a Fume Hood when doing THEN GO TO Step 9. dilutions in Hot Lab or HRSS hood b) Verify LIQIUD sample to be b) IF diluting GASEOUS sample. diluted THEN do the following:

1) Perform a 1:100 dilution (0.01 times original volume).

2) GO TO Step 11.

c) Verify liquid sample from c) IF sample activity of liquid source other than Sentry System sample from Sentry System LESS THAN 1000 mR/hr. THEN GO TO Step 6.d. IF sample activity of liquid sample from Sentry System GREATER THAN 1000 mR/hr, THEN GO TO Step 7. d) Do LIQUID sample dilution:

1) Determine appropriate dilution ratio. e.g.. 1:10 dilution (0.1 times original volume). 1:1000 dilution (0.001 times original volume)

2) Perform dilution

3) Check sample activity - 3) IF sample activity still too WITHIN LIMITS high. THEN do additional dilution(s) to yield an acceptable activity level.

4) GO TO Step 11 I

NUMBER PROCEDURE TITLE REVISION EPIP-4.26 HIGH LEVEL ACTIVITY SAMPLE ANALYSIS 12 PAGE L~~~~~~~~~~~~~~ ~~~~~~5 of 6 i{E ACTION/EXPECTED RESPONSE F-] RESPONSE NOT OBTAINED F- _____7 GET THE FOLLOWING EQUIPMENT:

Operable Fume Hood
1,000 ml volumetric flasks partially filled with demineralized water ( 800 ml)
Dilutor Assembly
Lead bricks (as needed)
Phillips-head screwdriver
Adjustable wrench
Vent tube with attached needle
One squeeze bottle of dilution water
Grease pencil
Three tape strips ( 4 each)
Sample containers

_____8 INITIATE ATTACHMENT 2 DILUTE SAMPLE USING SENTRY SYSTEM _____9 CHECK TIME AVAILABLE TO ALLOW IF air sample. THEN do the SAMPLE DECAY PRIOR TO ANALYSIS: following: a) Isolate sample to prevent 1) Separate particulate and silver personnel exposure zeolite cartridges. b) Keep sample for later analysis 2) Count particulate and silver zeolite cartridge separately. c) GO TO Step 11

3) GO TO Step 12.

IF sample volume to be reduced. THEN GO TO Step 10. IF sample to be analyzed, THEN GO TO Step 11.

NUMBER PROCEDURE TITLE REVISION EPIP-4.26 HIGH LEVEL ACTIVITY SAMPLE ANALYSIS 12 PAGE . - 6 of 6 -AH 1-F-I 2 - ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _____10 REDUCE SAMPLE VOLUME: a) Verify GAS sample a) IF LIOUID sample, THEN do the following:

1) Put desired sample volume in suitable container with a calibrated geometry.

2) Dilute sample (to appropriate mark) with water.

b) Record volume of undiluted sample in the container _____11 VERIFY BOTH THE FOLLOWING RETURN TO Step 5. CONDITIONS EXIST:

Verify sample dose rate reads LESS THAN 10 mR/hr
Calibrated elevated geometry NOT available for use

_____12 TAKE SAMPLE TO COUNT ROOM FOR ANALYSIS IAW NORMAL HP PROCEDURES _____13 TERMINATE EPIP-4.26:

Give completed EPIP-4.26. forms, and other applicable records to the RPS
Completed by:

Date: Time: I

                                           -END -

NUMBER ATTACHMENT TITLE REVISION EPIP-4.26 HRSS DILUTOR ASSEMBLY 12 ATTACHMENT 1 PAGE 1 1 of 4 FIGURE 1 Grwphws HRSS DILUTOR ASSEMBLY DILUTOR ASSEMBLY INCLUDES SYRINGE AND CHANEY ASSEMBLIES

(

                                                                                                      .,.)    a

( ( a m Dz" a Plunger Handle Sample 4

,L.

i @ Full Range Of I i _,,Assembly Space C -C = Mr > :X: This figure illustrates the withdrawal m o4 - of the plunger handle to capture ; -0 a > 2.0 ml sample. m~- FIGURE 2 Graptks No: BP'S6 CHANEY ADAPTER

                                                                                           ~ m~ ~ ~

I*.3 .

                                                                                                           -B 0

z

( Ch (. D -4 Plunger Catch Bar n1 > M, -( = x Rear Bar Rest I - Figure illustrates the resting of the plunger catch bar on the rear bar rest following the withdrawal of sample. FIGURE 3 Grajphirs Ni: 81'56 .4 CHANEY ADAPTER f0n "f

                                                                                              .W    m rn 0 la       d

I IV (: ( ( - Doll

1 m DIP a

Cn 3 c t = sI M M O. F4 Sample 0-_ rl M GM TIC = Bar Rest C - Figure illustrates the expulsion of sample into flask or tared vial. Plunger catch bar rr travels from rear b front bar rest. FIGURE 4 Grphics .o I'S6.1.4 CHANEY ADAPTER

                                                                                            -P.             M~~~TI 4   ,>          -

C 0 4!~-z

NUMBER ATTACHMENT TITLE REVISION EPIP-4.26 DILUTE SAMPLE USING SENTRY SYSTEM 12 ATTACHMENT PAGE L 2 1 of 2

1) Place 1000 ml volumetric flask in fume hood.

2) Position cask near the fume hood.

3) Remove auxiliary shield hold-down bolts. as needed.

4) Remove needle plug.

5) IF radiation levels increase when plug is removed, THEN use lead bricks tto reduce streaming.

6) Place end of vent tube in strong vacuum area of hood and tape down to inside of the hood.

7) Carefully insert vent needle into guide and puncture septum to vent vial.

8) Remove needle and store in hood.

9) Place support blocks in appropriate locations so that dilutor rest brackets will sit squarely on them (see Attachment 1. Figure 1).

10) Ensure syringe plunger is in the fully expelled position.

11) Carefully insert needle of dilutor into guide and bring to rest on support blocks.

12) Slowly withdraw maximum amount of sample (greater than 2.0 mls) by withdrawing plunger handle full range of assembly space (see Attachment

1. Figure 2).

13) Bring the plunger catch bar to rest on the rear bar rest (see Attachment 1, Figure 3).

14) Carefully remove dilutor assembly from needle guide by pulling up in one straight motion.

15) Carefully insert needle into neck of volumetric flask.

16) Carefulli touch tip of needle to wall of flask while slowly expelling contents of syringe and depress plunger handle only as far as front bar rest (see Attachment 1. Figure 4). This expells exactly 2.0 mls.

17) Add dilution water to volumetric flask to bring level up to 1000 mls.

NUMBER ATTACHMENT TITLE REVISION EPIP-4.26 DILUTE SAMPLE USING SENTRY SYSTEM 12 ATTACHMENT PAGE 2 2 of 2

18) Label 1 liter volumetric flask with date, time of sample, sample location, and one of the following:

0.002 RCS for diluted HRSS OR
2 mls for an undiluted sample.

19) Check 1 liter volumetric flask is LESS THAN 10 mR/hr. then GO TO Step 20 of this Attachment 2 OR IF NOT LESS THAN 10 mR/hr. THEN GO TO EPIP-4.26, Step 5.

20) Get HP assistance and select a suitable sample container with a calibrated geometry.

21) Measure diluted sample from Step 18 above into selected sample container with the calibrated geometry.

22) Label container with date, sample time, sample location and actual mls of RCS in the sample geometry:

Actual = mls sample from SteD 18 x mls solution from Step 21 mis RCS 1000

23) Remove temporary shielding (if installed) and replace auxiliary shield on cask. Replace needle shield when time permits.

24) GO TO EPIP-4.26, Step 12.

I

VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0 (With No Attachments) PAGE 1 of 11 PURPOSE To provide controls for chemistry sampling of the Reactor Coolant System, I containment atmosphere and containment sump. LEVEIL 2 STPRIuBtrr N

                                              'ITis Document Should Be Verified ind Annotated To A Conuolle Source As Required to Perfon Workc ENTRY CONDITIONS Any one of the following:

1. Alert or higher emergency classification has been declared.

2. Activation by EPIP-4.02. Radiation Protection Supervisor Controlling Procedure.

3. As deemed necessary by the Radiological Assessment Director.

Approvals on ile Effective Date I °03

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0 PAGE 2 of 11 AHH ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED H- _____1 INITIATE EPIP-4.35:

By:

Date: Time: _____2 CHECK WITH RADIATION PROTECTION IF sampling to be conducted under SUPERVISOR TO ENSURE NORMAL provisions of the Contingency CHEMISTRY SAMPLING IS ACCEPTABLE Plan. THEN GO TO Step 13. _____3 CHECK IF SAMPLE POINT IS AVAILABLE IF sample point is NOT available IN PRIMARY SAMPLE ROOM in primary sample room, THEN determine location of alternate sample point. NOTE: Prompt notification of RPS upon detection of stop work dose rates at the Primary Sample Room is essential for timely classification decision-making. _____4 BRIEF SAMPLE PERSONNEL: a) Review sampling procedure b) Review ingress and egress routes c) Review RWP requirements d) Review enroute hazards e) Review operation of RABBIT sample transfer system f) Review criteria for promptly reporting stop work dose rate I

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0 PAGE L__ ~~~~~~~~~~~~~~~~~~3 of 11 743H ACTION/EXPECTED RESPONSE F-H RESPONSE NOT OBTAINED H- _____5 DISPATCH SAMPLING PERSONNEL: a) Assure sampling personnel have proper materials and personal protection equipment b) Give sampling personnel a copy of this procedure _____6 GO TO SAMPLE LOCATION: a) Use pre-planned travel route to sample location b) Continuously monitor radiation dose rates c) Verify radiation dose rates - c) IF unexpected radiation dose EXPECTED rates are found. THEN leave area. CAUTION:

Do not open RABBIT transfer system while sending sample.
Samples may become stuck in the RABBIT system (e.g. due to loss of vacuum). System piping can be monitored to determine the location of the stuck RABBIT. The Radiation Protection Supervisor should be notified if this occurs.

___7 PERFORIM SAMPLING: I (STEP 7 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0 PAGE l - 4 of 11 AH ACTION/EXPECTED RESPONSE H-I S RESPONSE NOT OBTAINED I-7 PERFORM SAMPLING: (Continued) a) Verify sampling from Primary a) IF NOT performing sample from Sample Room Primary Sample Room, THEN do the following:

1) Perform sampling in designated alternate location.

2) Leave sample area.

a) Monitor sample dose rates. b) Maintain ALARA (reduce exposure). c) GO TO Step 7.e. b) Collect required sample volume c) Turn on RABBIT sample transfer c) IF NOT operable. THEN do the system at primary sample room following:

1) Transfer sample manually in accordance with HP Technician instructions.

2) Leave sample area.

a) Monitor sample dose rates. b) Maintain ALARA (reduce exposure). c) GO TO Step 7.e. d) Send sample to Hot Lab e) Leave sample area by pre-planned route

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0 PAGE 5 of 11 F-] {4HH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I _____8 PREPARE SAMPLE FOR ANALYSIS: a) Put sample in a clean poly bag b) Label sample with the following:

Date and time
Sample type
Sample volume
Dose rate

_____9 CHECK SAMPLE ACTIVITY - LESS THAN IF sample activity GREATER THAN 10 mR/HR 10 mR/hr. THEN do the following: a) Take sample to Hot Lab for dilution IAW EPIP-4.26, HIGH LEVEL ACTIVITY SAMPLE ANALYSIS. b) GO TO Step 11. _____10 TAKE SAMPLE TO COUNT ROOM _____11 NOTIFY THE FOLLOWING THAT SAMPLING IS COMPLETE:

Radiological Assessment Director
Radiation Protection Supervisor
Shift Manager

_____12 GO TO STEP 28

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0. PAGE 6 of 11 -EEH- ACTION/EXPECTED RESPONSE F-H RESPONSE NOT OBTAINED F-NOTE: CH-94.300. HIGH RADIATION SAMPLING SYSTEM, describes Contingency Plan sampling considerations. _____13 REVIEW SYSTEM DESIGN BASES: IF sampling is for. THEN consider the following: Reactor Coolant

Design basis RCS estimated sample dose rates:

                                     - 1000 Rem/hr surface, undiluted OR                  - 1 Rem/hr surface, diluted
                                     - 650 mRem/hr at surface of cask when cover Containment Sump           is NOT in place, undiluted

Design basis Liquid Sample Panel (LSP) dose rate is 365 mRem/hr at 1 meter
LSP is maintained at negative pressure Containment Air
CASP design basis dose rates equal 30 mR/hr at three feet
Containment Air Sample design basis dose rates:

                                     - 8,000 mR/hr surface
                                     - 100 mR/hr at one foot

CASP is maintained at a negative pressure
Dose rates and airborne contamination levels at the PCP/CCP are not normally affected by the sampling process I

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0 PAGE L - 7 of 11 AH~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H-14 GIVE SAMPLE TEAM COPY OF SAMPLING PROCEDURE(s): IF sampling is for, THEN give Sample Team the following: Reactor Coolant

CH-41.120 (UNIT 1) / CH-42.120 (UNIT 2). HIGH RADIATION SAMPLING SYSTEM RCS DILUTED LIOUID SAMPLING OR CH-41.121 (UNIT 1) / CH-42.121 (UNIT 2). HIGH RADIATION SAMPLING SYSTEM RCS UNDILUTED LIQUID SAMPLING
EPIP-4.26. HIGH LEVEL ACTIVITY SAMPLE ANALYSIS Containment Sump
1-OP-12.5. HIGH RADIATION CONTAINMENT SUMP SAMPLING
EPIP-4.26, HIGH LEVEL ACTIVITY SAMPLE ANALYSIS Containment Air CH-41.310 (UNIT 1) / CH-42.310 (UNIT 2). HIGH RADIATION SAMPLING SYSTEM CONTAINMENT AIR SAMPLING I

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0 PAGE L- ~~~~~~~~~~~~~~~~~~8 of 11 ACTION/EXPECTED RESPONSE l l RESPONSE NOT OBTAINED + NOTE: Prompt notification of RPS upon detection of stop work dose rates at the Primary Sample Room is essential for timely classification decision-making. _____15 BRIEF SAMPLE TEAM: a) Review sampling and analysis procedures, as appropriate b) Establish and review entry and exit routes (use ALARA) c) Review RWP requirements for sample locations (e.g., PCP, LSP. PCP/CCP. CASP. as appropriate):

Stay times
Protective clothing
Dosimetry
Respiratory equipment
Monitoring d) Review criteria for promptly reporting stop work dose rate e) Review cautions:
High radiation levels
High activity sample level(s)

(for Containment Air samples. estimate the correct volume of sample to be collected using the gas sampler (RCT))

High sample pressure (for Reactor Coolant samples)
Open valves slowly f) Give team a copy of this procedure

_____16 HAVE SAMPLE TEAM DRESS OUT IAW RWP

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0 PAGE 9 of 11 H-H H- {ED4 ACTION/EXPECTED RESPONSE NOTIFY _____ 17 RPS THAT SAMPLE TEAM IS RESPONSE NOT OBTAINED

         .17  NOTIFY RPS THAT SAMPLE TEAM IS READY FOR DISPATCH

_____18 ASK RPS FOR CURRENT PLANT STATUS _____19 GIVE UPDATE TO TEAM MEMBERS _____20 DISPATCH SAMPLE TEAM _____21 CHECK SAMPLE - CONTAINMENT AIR IF Reactor Coolant or Containment Sump sample. THEN GO TO Step 26. _____22 VERIFY SAMPLE PREPARED FOR TRANSPORT: a) Sample container labelled with the following information:

Sample ID and Unit #
Sample volume
Date and time
Dose rate b) Glass bottle and syringe assembly put in separate bags/containers

_____23 CHECK SAMPLE CONTACT READING - IF sample contact reading GREATER LESS THAN 10 MR/HR THAN 10 mR/hr, THEN have HP initiate EPIP-4.26. HIGH LEVEL ACTIVITY SAMPLE ANALYSIS.

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0 PAGE 10 of 11 _i3i ACTION/EXPECTED RESPONSE l I RESPONSE NOT OBTAINED 1- _____24 TAKE SAMPLE TO COUNT ROOM: a) Use pre-planned route b) Monitor radiological conditions during transit c) Check dose rates along route c) Do the following: within expected levels

1) Notify RPS.

2) Identify route of lowest dose.

d) Maintain ALARA _____25 GO TO STEP 27 _____26 HAVE REACTOR COOLANT SAMPLE ANALYZED: a) Refer to EPIP-4.26, HIGH LEVEL ACTIVITY SAMPLE ANALYSIS, for sample dilution b) Transport sample to Hot Lab or HRSS hood for dilutions c) Implement appropriate Chemistry procedure for analysis d) Check if diluted HRSS sample is d) GO TO Step 27. to be flushed back through system for disposal e) Implement affected unit HIGH RADIATION SAMPLING SYSTEM SAMPLE DISPOSAL OR STORAGE procedure Unit 1 - CH-41.820 I Unit 2 - CH-42.820

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 0 PAGE .~~ 11 of 11 -IEH ACTION/EXPECTED RESPONSE F-H RESPONSE NOT OBTAINED H- _____27 NOTIFY THE FOLLOWING INDIVIDUALS ONCE SAMPLING HAS BEEN COMPLETED:

Radiation Protection Supervisor
Shift Manager
Station Emergency Manager

_____28 TERMINATE EPIP-4.35:

Give completed EPIP-4.35, forms and other applicable records to the Radiation Protection Supervisor
Completed by:

Time: Date:

                                            -END-

VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTIGH PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-5.07 ADMINISTRATION OF RADIOPROTECTIVE DRUGS 12 (With 2 Attachments) PAGE 1 of 4 PURPOSE To obtain authorization and medical advice concerning administration of radioprotective drugs, and to provide information regarding dose and side effects to individuals who may be asked to take KI. LEVEL 2 DISTRJE oN I Document Thould 13 Verified And Annotated TO A Curitrolled) Source As Required to rellbz Work ENTRY CONDITIONS Any one of the following:

1. Activation by another EPIP.

2. Activation by CPIP-6.2, RADIOLOGICAL ASSESSMENT COORDINATOR.

3. Survey results indicate inhalation dose may have exceeded 25 Rem.

4. Entry into high airborne activity area where inhalation dose may exceed 25 Rem.

Approvals on file Effective Date

NUMBER PROCEDURE TITLE REVISION EPIP-5.07 ADMINISTRATION OF RADIOPROTECTIVE DRUGS 12 PAGE 1 ~~~~~~~~~~~~~~~~~ of 4

                                                     .        -       -                l

-EDA ACTION/EXPECTED RESPONSE [-H RESPONSE NOT OBTAINED 1- _____1 INITIATE PROCEDURE:

Initiated By:

Date: Time: NOTE: The Recovery Manager (RM) may authorize administration of KI for Offsite Monitoring Teams and LEOF personnel. _____2 GET AUTHORIZATION FROM SEM/RM: IF authorization NOT granted. THEN GO TO Step 10. a) Review criteria for administering radioprotective drugs from controlling procedure with SEM/RM:

EPIP-4.05, RESPIRATORY PROTECTION AND KI ASSESSMENT
CPIP-6.2, RADIOLOGICAL ASSESSMENT COORDINATOR b) Ask SEM/RM to approve use of radioprotective drugs c) Record SEM/RM approval in event log

_____3 HAVE INDIVIDUAL(s) RECEIVING KI IF individual does NOT sign READ AND COMPLETE ATTACHMENT 1. Attachment 1. THEN do the RADIOPROTECTIVE DRUG DOSAGE. SIDE following: EFFECTS AND MEDICAL STATEMENT a) Do NOT issue KI to individual b) IF other individual(s) selected, THEN continue procedure for processing other I individuals. IF NO other individual requires KI. THEN GO TO Step 10.

NUMBER PROCEDURE TITLE REVISION EPIP-5.07 ADMINISTRATION OF RADIOPROTECTIVE DRUGS 12 PAGE 3 of 4 -BEER ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H-NOTE: Copies of the Emergency Personnel Notification List (EPNL) are maintained by Security, in the TSC, and in the LEOF/CEOF. _____4 NOTIFY MEDICAL STAFF: IF medical staff can NOT be notified immediately, THEN do the a) Use EPNL (Position 291) to get following: telephone number for medical staff 1) Continue this procedure. b) Notify medical staff of need to 2) Repeat attempts to contact issue KI and to whom it will be medical staff. issued c) Ask if KI should be issued to individual(s) who checked box

2. 3 or 4 of Attachment 1.

Section III _____5 CHECK EITHER OF THE FOLLOWING IF Box 5 checked. THEN do the CONDITIONS EXIST: following:

Individual(s) checked Box 1 a) Do NOT consider individual for emergency work.
Medical consent given for individual(s) who checked Box 2. b) Do NOT issue KI.

3 or 4 c) GO TO Step 10. IF medical consent NOT given. THEN GO TO Step 10. _____6 GET TABLETS FROM NAPS MEDICAL Get alternate supply from Surry FACILITY OR COUNT ROOM Power Station.

NUMBER PROCEDURE TITLE REVISION EPIP-5.07 ADMINISTRATION OF RADIOPROTECTIVE DRUGS 12 PAGE 4 of 4 I AiH - ACTION/EXPECTED RESPONSE H-H . RESPONSE NOT OBTAINED F-

      *   *  * *    *  * *  * * *  * * * * *

a * * * * * * * * * * * * * * * * * * * * *
CAUTION: Potassium iodide should not be used by people allergic to iodine without prior medical consent.

NOTE: Administration of radioprotective drugs is preferably done prior to exposure, although administration within 2 hours after exposure is considered acceptable. _____7 GIVE RADIOPROTECTIVE DRUGS TO DESIGNATED INDIVIDUAL _____8 COMPLETE ATTACHMENT 2. POTASSIUM IODINE ISSUE LOG _____9 DO FOLLOW-UP ASSESSMENT IAW NORMAL STATION PROCEDURES: a) Wait at least 24 hours after exposure was received b) Do follow-up assessment _____10 TERMINATE EPIP-5.07:

Give EPIP-5.07. forms, and other applicable records to the Radiological Assessment Director/Radiological Assessment Coordinator
Completed by:

Date: Time:

                                                      -END  -

NUMBER ATTACHMENT TITLE REVISION EPIP-5.07 RADIOPROTECTIVE DRUG DOSAGE. 12 ATTACHMENT PAGE SIDE EFFECTS AND MEDICAL STATEMENT 1 1 of 1 SECTION I: DOSAGE AND SIDE EFFECTS CAUTION Potassium Iodide should not be used by people allergic to Iodine. Keep out of reach of children. In case of overdose or allergic reaction, contact a physician or public health authority. DIRECTIONS FOR USE: ADULTS: One (1) tablet once a day. DONOT take tablet for more than 10 days. SIDE EFFECTS: Usually, side effects occur when people take higher doses for longer periods of time. Do not take more than the recommended dose and do not take dose for longer than the time that is recommended to you. Side effects are unlikely due to low doses over short periods of time. Possible side effects are skin rashes, swelling of salivary glands, and iodism (metallic taste, burning of mouth and throat, sore teeth and gums, symptoms of head cold, and sometimes stomach upset and diarrhea). A few people have an allergic reaction with more serious symptoms. These could be fever and Joint pains, swelling of parts of the face and body, and severe shortness of breath, requiring immediate medical attention. Taking iodide may rarely cause overactivity of the thyroid gland, underactivity of the thyroid gland, or enlargement of the thyroid gland (goiter). WHAT TO DO IF SIDE EFFECTS OCCUR: If side effects are severe or if you have an allergic reaction, stop taking potassium iodide and call a doctor. SECTION II:

1. [ I I have read Section 1. DOSAGE AND SIDE EFFECTS'.

SECTION III: Note: Items 1 through 4 below should be answered to the best of your knowledge. I. [ I I have no known sensitivity to Iodine, nor do I have a medical condition that would make me reluctant to take Iodine tablets.

2. [ I have a known sensitivity to Iodine.

3. [ I have a medical condition that may negate my being able to take K tablets, e.g.,

hyperthyroidism. hypothyroidism. etc.

4. [ ] I am currently taking thyroid hormone tablets.

5. [ ] I am a Declared Pregnant Worker under provisios of, or hereby state my intention to declare pregnancy in accordance with. VPAP-2101, Radiation Protection Program.

NAME:

DATE:_

(print) (signature)

NUMBER ATTACHMENT TITLE ' REVISION EPIP-5.07 POTASSIUM IODINE 12 ATTACHMENT ISSUE LOG PAGE 2 1 of 1 TIME OF TIME OF INITIAL NAME SS NUMBER EXPOSURE KI DOSE ISSUED BY i}}

ML031960476

Text

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