ML031110477

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Revisions to Emergency Plan and Implementing Procedures
ML031110477
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/10/2003
From: Heacock D
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML031110477 (74)
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Text

/r-VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIROrNIA 23261 April 10, 2003 U.S. Nuclear Regulatory Commission Serial No.03-261 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 AND 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, 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 Aoc--5

I ATTACHMENT I TABULATION OF CHANGES VIRGINIA ELECTRIC AND POWER COMPANY REVISIONS TO NORTH ANNA POWER STATION EMERGENCY PLAN AND 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 - 3.05, Rev. 01 10/01/99 EPIP - 3.05, Rev. 02 04/08/03 EPIP - 4.01, Rev. 18 04/09/02 EPIP - 4.01, Rev. 19 04/08/03 EPIP -4.24, Rev. 12 08/15/02 EPIP -4.24, Rev. 13 04/08/03 EPIP - 5.08, Rev. 07 11/30/00 EPIP - 5.08, Rev. 08 04/08/03 Emergency Plan Privacy and Proprietary Material has been removed. Reference Generic Letter No. 81-27.

DA PA C.

2003-04-08 1

(

NORTH ANNA POWER STATION LIST OF NAPS EMERGENCY PLAN IMPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION APPROVAL EFFECT**

DOCUMENT NUMBER REV N*DATEN* **DATE** DOCUMENT TITLE

_-____________0_____ ____________________________________________________________

EPIP-1.01 037 12/13/02 12/18/02 EMERGENCY MANAGER CONTROLLING PROCEDURE EPIP-1.02 011 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 09/05/01 PROTECTIVE ACTION RECOMMENDATIONS EPIP-2.01 025 08/13/02 08/28/02 NOTIFICATION OF STATE AND LOCAL GOVERNMENTS EPIP-2.02 015 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-3.04 015 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-4.01 019 04/02/03 04/08/03 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE EPIP-4.02 013 12/13/02 12/18/02 RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE EPIP-4.03 011 12/20/93 01/01/94 DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE EPIP-4.04 009 11/21/94 11/28/94 EMERGENCY PERSONNEL RADIATION EXPOSURE EPIP-4.05 009 01/28/00 02/04/00 RESPIRATORY PROTECTION AND KI ASSESSMENT EPIP-4.06 009 12/21/95 12/28/95 PERSONNEL MONITORING AND DECONTAMINATION EPIP-4.07 014 09/29/00 10/06/00 PROTECTIVE MEASURES EPIP-4.08 014 05/10/02 06/19/02 INITIAL OFFSITE RELEASE ASSESSMENT EPIP-4.09 013 05/10/02 06/19/02 SOURCE TERM ASSESSMENT EPIP-4.10 011 08/13/02 08/28/02 DETERMINATION OF X/Q EPIP-4.13 009 09/29/00 10/06/00 OFFSITE RELEASE ASSESSMENT WITH ENVIRONMENTAL DATA

< Di PA, 2003-04-08 2

NORTH ANNA POWER STATION (3 (

LIST OF NAPS EMERGENCY PLAN IMPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION APPROVAL EFFECTMW DOCUMENT NUMBER REV *E*DATE**~ **DATE***

  • EDATERSW DOCUMENT TITLE EPIP-4.14 007 12/20/93 01/01/94 INPLANT MONITORING EPIP-4.15 011 02/18/00 02/28/00 ONSITE MONITORING EPIP-4.16 015 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 04/05/02 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 EMERGENCY EPIP-4.26 011 07/26/01 09/13/01 HIGH LEVEL ACTIVITY SAMPLE ANALYSIS EPIP-4.28 007 01/09/97 01/14/97 TSC/LEOF RADIATION MONITORING SYSTEM EPIP-4.30 005 04/05/02 04/09/02 USE OF MIDAS CLASS A MODEL 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-5.01 011 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-5.05 013 06/25/96 07/02/96 SITE EVACUATION EPIP-5.07 011 07/25/00 08/02/00 ADMINISTRATION OF RADIOPROTECTIVE DRUGS EPIP-5.08 008 04/02/03 04/08/03 DAMAGE CONTROL GUIDELINE EPIP-5.09 004 08/02/02 08/15/02 SECURITY TEAM LEADER CONTROLLING PROCEDURE

' DA/ 2003-04-08 PAGL 3 NORTH ANNA POWER STATION LIST OF NAPS EMERGENCY PLAN IMPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION APPROVAL EFFECTXE DOCUMENT NUMBER REV W*DATEWW UNDATE** DOCUMENT TITLE P_-6________________ R-ENTRY/RECOVERY_______________________GUIDELINE____________

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-3.05 AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION 2 (With No Attachments) PAGE L I i 1 of 6 PURPOSE Provide guidance for notifying the augmentation emergency response organization (ERO).

[ LEVEL 2 DtSTR1BUIONl This Document Should 6e Verified And Annotated To A Controlled Source As Requisred to Performn Workl ENTRY CONDITIONS Any one of the following:

1. Declaration of an Alert, Site Area Emergency or General Emergency.
2. Direction of the Station Emergency Manager through the on-duty Security Team Leader.

Approvals on File Effective Date 0

NUMBER PROCEDURE TITLE REVISION EPIP-3.05 AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION 2 PAGE 1 2 of 6 AHD ACTION/EXPECTED RESPONSE H-H S RESPONSE NOT OBTAINED 1-

___1 INITIATE PROCEDURE:

  • By:

Date:

Time:

___2 USE INSTRUCTIONS IN SEALED ENVELOPE TO ACTIVATE NORTH ANNA AND INNSBROOK GROUP PAGERS

___3 USE INSTRUCTIONS IN SEALED ENVELOPE TO DIRECT COMMUNITY ALERT NETWORK (CAN) TO IMPLEMENT NOTIFICATION

NUMBER PROCEDURE TITLE REVISION EPIP-3.05 AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION 2 1 PAGE 1 ~3 of 6

-LFEH ACTION/EXPECTED RESPONSE H-] RESPONSE NOT OBTAINED 1-4 CHECK CAN - ABLE TO PERFORM IF CAN NOT able to perform AUGMENTATION NOTIFICATION augmentation notification. THEN do the following:

a) Notify Innsbrook Security.

b) Call 8-730-2020 (Network)

((804) 273-2020 (Public))

c) Provide the following information:

1) Title/Name
2) Location
3) Emergency classification
4) Indicate results of pager activation attempts:
  • North Anna Group Pager
  • Innsbrook Group Pager d) Direct Innsbrook Security to initiate back-up ERO augmentation notification using CPIP-3.4. INNSBROOK SECURITY SUPPORT.

e) GO TO Step 6.

NUMBER PROCEDURE TITLE REVISION EPIP-3.05 AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION 2 PAGE 4 of 6 ACTION/EXPECTED RESPONSE H EPNENTOTAINED-

.5 NOTIFY INNSBROOK SECURITY:

a) Call 8-730-2020 (Network)

((804) 273-2020 (Public))

b) Provide the following information:

1) Title/Name
2) Location
3) Emergency classification

___6 NOTIFY HYDROELECTRIC PROJECT TECHNICAL ASSISTANT:

a) Call 9-872-3531 (Local Public) b) Provide the following information:

1) Title/Name
2) Indicate emergency in effect

NUMBER PROCEDURE TITLE REVISION EPIP-3.05 AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION 2 PAGE

. 5 of 6 11" l

-1F{ ACTION/EXPECTED RESPONSE F-] RESPONSE NOT OBTAINED H-

___7 NOTIFY OPERATIONS SHIFT DESIGNATED FOR COVERAGE BY OPERATIONS:

a) Find list of shift callout points-of-contact in EPNL "A" Shift Position #491 "BH Shift Position #492 "C" Shift Position #493 "D" Shift Position #494 "E" Shift Position #495 b) Call one Operations shift callout point-of-contact for designated shift c) Provide the following information:

1) Title/Name
2) Emergency classification
3) Indicate that entire Operations shift is to be called-in for support

___8 USE INSTRUCTIONS IN SEALED ENVELOPE TO SEND POP-UP MESSAGE

NUMBER PROCEDURE TITLE REVISION EPIP-3.05 AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION 2 PAGE 6 of 6

.1

{ED4 ACTION/EXPECTED RESPONSE [-A RESPONSE NOT OBTAINED -Il--

___9 TERMINATE EPIP-3.05:

  • Give completed EPIP-3.05. forms and other applicable records to Security Team Leader
  • Completed by:

Date:

Time:

-END -

VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE (With 2 Attachments) PAGE 1 of 27 PURPOSE To initially assess emergency conditions, provide recommendations for protective measures, establish an emergency organization and direct Health Physics response to an emergency.

LEVEL 2 DISTRIBLUTION This Document Should Be Verified And Annotated To A Cntt oiled Source

-As Required to Performn Work ENTRY CONDITIONS Activation by EPIP-1.01, EMERGENCY MANAGER CONTROLLING PROCEDURE.

Approvals on File Effective Date

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE ________

PAGE 2 of 27 a;D ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED 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 requi re 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 Supervisor may assume the position of Station Emergency Manager.

___3 ASK SEM 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 19 PROCEDURE PAGE 3 of 27 1-

-EA ACTION/EXPECTED RESPONSE

__j RESPONSE NOT OBTAINED

___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 38.

___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 19 PROCEDURE PAGE L _ 4 of 27

-Li1EC ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H-

___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 X/O.

___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 2 100% TS (but < 1000%) Event

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

___13 GIVE ASSESSMENT BASED CLASSIFICATION TO SEM

NUMBER PROCEDURE TITLE REVISION EPI-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 EPIP-4.Ol PROCEDURE 19 PAGE 1 5 of 27 F-] H-A-EH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

___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

GO TO Step 17

  • LOCA - GO TO Step 19

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE 19 PAGE

.~ 6 of 27 i

-LJH ACTION/EXPECTED RESPONSE F-I 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

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE 1 7 of 27 STPACTION/EXPECTED RESPONSE HRESPONSE NOT OBTAINED

___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 'A' S/G at (time)

"B"S/G at "C"S/G at

6) Current Steam Generator Blowdown pathway:
7) 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 (STEP 17 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE PAGE L_ 8 of 27 AEH ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED F-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 (STEP 17 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE L - ~9 of 27 AHD ACTION/EXPECTED RESPONSE I-] RESPONSE NOT OBTAINED F-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 Driven Auxiliary Feedwater Pump Turbine exhaust area a 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

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE 19 PAGE L- 10 of 27

-AEH ACTION/EXPECTED RESPONSE F-] .

RESPONSE NOT OBTAINED F-

___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:

1) Assess onsite dose rate in area of break (after break is isolated)
2) Assess offsite dose rate (STEP 18 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE 11 of 27 AHE- ACTION/EXPECTED RESPONSE F-] .

RESPONSE NOT OBTAINED F-18 INITIATE RESPONSE ACTIONS FOR MAIN STEAM LINE RUPTURE: (Continued) 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) Direct initiation of EPIP-4.22, POST ACCIDENT SAMPLING OF CONTAINMENT AIR AND EPIP-4.23, POST ACCIDENT SAMPLING OF REACTOR COOLANT g) GO TO Step 21

NUMBER PROCEDURE TITLE EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE

-EiE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED F-

___19 INITIATE RESPONSE ACTIONS FOR LOCA:

a) Ask SEM for location of break b) Ask SEM for status of Containment Isolation - Phase "A" 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) Direct initiation of EPIP-4.22, POST ACCIDENT SAMPLING OF CONTAINMENT AIR AND EPIP-4.23, POST ACCIDENT SAMPLING OF REACTOR COOLANT h) GO TO Step 21

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE 13 of 27 l

{EEH ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED H-

___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 EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE

-LFJ-L ACTION/EXPECTED RESPONSE F-]

RESPONSE NOT OBTAINED H-.

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 2 50 mrem/hr TEDE OR 250 mrem/hr THYROID CDE

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 1 PROCEDURE 19 PAGE 15 of 27 SPACTION/EXPECTED RESPONSE l l RESPONSE NOT OBTAINED

___23 DETERMINE OFFSITE PROTECTIVE MEASURES:

a) Get an estimate of release a) Use 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 19 PROCEDURE PAGE L _ ~16 of 27

_[EK ACTION/EXPECTED RESPONSE [-1 .

RESPONSE NOT OBTAINED F-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 36.

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 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 33.

Issuance of radioprotective drugs GO TO Step 34.

Response to injured contaminated individual(s) GO TO Step 26.

Evacuation of non-essential personnel GO TO Step 35.

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-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE

. 17 of 27 .

-EE: ACTION/EXPECTED RESPONSE F-H r

RESPONSE NOT OBTAINED I-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

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE

. - 18 of 27

-EEH 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 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 19 PAGE 19 of 27 s . .

-LFH ACTION/EXPECTED RESPONSE 4-] RESPONSE NOT OBTAINED F-

___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 Jeader b) Check if command and control of b) GO TO Step 29.d.

Offsite Monitoring Teams has been transferred to the LEOF c) RETURN TO Step 25 (STEP 29 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE 19 PAGE I 20 of 27 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:

Initiate EPIP-4.04, EMERGENCY PERSONNEL RADIATION EXPOSURE

  • Thyroid CDE 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 19 PROCEDURE PAGE L_ 21 of 27 ACTION/EXPECTED RESPONSE HRESPONSE 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 a-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

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE L~ 22 of 27

-AFH l

ACTION/EXPECTED RESPONSE F-] RESPONSE NOT OBTAINED H-

___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 (STEP 31 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE 23 of 27

_fH1_1 ACTION/EXPECTED RESPONSE H-I 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

___32 ESTABLISH ACCESS CONTROL AREAS:

a) Evaluate radiological hazards a) GO TO Step 33.

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

NUMBER PROCEDURE TITLE REVISION EPIP-4.O1 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE 24 of 27

-EEH ACTION/EXPECTED RESPONSE H-H .

RESPONSE NOT OBTAINED H-

___33 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 NOTE: Administration of Potassium Iodine Tables is preferably done prior to exposure, although administration of the drug within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is considered acceptable.

___34 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 2 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

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE 1 25 of 27 H-]

AEH. ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

___35 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 ([tCi/cc) based on air sample data and exposure duration:

iPCi/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

  • 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 (STEP 35 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROC EDURE PAGE L- 26 of 27

-LF-i ACTION/EXPECTED RESPONSE F-] RESPONSE NOT OBTAINED 35 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

___36 BRIEF SEM AND RPS ON EMERGENCY STATUS AND RADIOLOGICAL TRENDS

___37 CHECK IF EMERGENCY HAS BEEN RETURN TO Step 11.

TERMINATED

___38 NOTIFY RPS AND RAC OF EVENT TERMINATION

___39 CONSIDER EXTENDED USE OF MONITORING TEAMS FOR DATA COLLECTION

NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 19 PROCEDURE PAGE 1 27 of 27

-EEF4 ACTION/EXPECTED RESPONSE F-] RESPONSE NOT OBTAINED

___40 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

___41 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 19 ATTACHMENT PAGE 1 of 1 I 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) _iCi/sec VENT VENT B (VG-113) cpm (VG-180) uCi/sec PROCESS VENT (GW-102) cpm (GW-178) pCi/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)-

(MS-270) (MS-271) (MS-272) 7 AFPT: (MS-176) (MS-276)-

CONTAINMENT MONITORS: R/hr (RMS-161) (RMS-164) (RMS-261) __ (RMS-264)

(RMS-162) (RMS-165) (RMS-262) __ (RMS-265)

(RMS-163) (RMS-166) (RMS-263) 3)- (RMS-266) -

NUMBER ATTACHMENT TITLE REVISION EPIP-4.01 RESPONSE TO ISFSI EVENT 19 ATTACHMENT PAGE I~ 2 I1 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 90 ° 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)

TITLE REVISION NUMBER ATTACHMENT ATTACHMENT TITLE REVISION EPIP-4.01 RESPONSE TO ISFSI EVENT 19 ATTACHMENT PAGE 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 0.1%.
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 0.1 0.01 0.001 T 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 19 ATTACHMENT PAGE 2 3 of 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)

_ 4. Give the RPS guidance and direction for briefing and equipping team IAW 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 dispatch 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 19 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.

VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-4.24 GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY 13 (With 1 Attachment) PAGE L- 1 of 9 PURPOSE Provide guidance to personnel responsible for sampling high level radioactive gaseous effluents.

LEVEL 2 01.STRJBUTiON This Document Sriould Be verIfied And Annotated Ito A~cnirolled Source As Requireo to Perforn, wori.

ENTRY CONDITIONS Any one of the following:

1. Direction by the Radiation Protection Supervisor.
2. Direction by Dose Assessment Team Leader.
3. Direction by the Radiological Assessment Director.
4. Activation by another EPIP.

Approvals on File Effective Date A l

NUMBER PROCEDURE TITLE REVISION EPIP-4.24 GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY 13 PAGE 2 of 9 AHJ- ACTION/EXPECTED RESPONSE F-I RESPONSE NOT OBTAINED F-

___1 INITIATE PROCEDURE:

  • By:

Date:

Time:

NOTE: Expertise and exposure should be considered when designating team members.

___2 ASSEMBLE SAMPLING TEAM

___3 CONSIDER USE OF SHIELDING FOR SAMPLE TRANSPORT

___4 CHECK IF EMERGENCY RADIATION IF emergency radiation exposure EXPOSURE - REQUIRED NOT needed, THEN GO TO Step 6.

___5 ASK RAD TO INITIATE EPIP-4.04, EMERGENCY PERSONNEL RADIATION EXPOSURE

NUMBER PROCEDURE TITLE REVISION EPIP-4.24 GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY 13 PAGE 1 ~3 of 9 a NOTE: 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.

___6 BRIEF SAMPLE TEAM:

  • Sampling location and monitor manufacturer
  • Sampling procedures
  • Sample type (e.g., Noble gas, Tritium, Iodine/Particulate)
  • Dose rates in sample location
  • Emergency dose authorization (if appropriate)

. RWP requirements:

  • High and low range dosimetry or use of DADs

. Wrist, head, and ankle TLDs

  • Protective clothing
  • Respiratory protection
  • "Buddy System" criteria

. Ingress and egress routes considering:

  • Lowest dose fields
  • Hazards (i.e.. high pressure steam, structural damage)

NUMBER PROCEDURE TITLE REVISION EPIP-4.24 GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY 13 PAGE i 4 of 9 AH] ACTION/EXPECTED RESPONSE 1-] RESPONSE NOT OBTAINED F-

___7 REVIEW SAMPLE LOCATIONS:

MONITOR PRIMARY BACKUP Process Vent 274' Aux. Bldg. near 307' Service Bldg.

charcoal filter banks Vent Vents Aux. Bldg. roof near 310' Turbine Bldg.

A and B elevator shaft behind elevator shaft Unit 1 Air 303' Turbine Bldg. near None Ejector Powdex Resin Control Panel Unit 2 Air 279' Turbine Bldg. at the None Ejector Condenser Air Ejectors

___8 GET SAMPLE EQUIPMENT:

  • Poly bag labelled with:
  • System to be sampled
  • Date
  • Time

. Volume

. 100 cc gas bomb

  • Silver zeolite cartridge and particulate patch
  • Silver zeolite sample holder
  • Tritium bubbler with 20 mls demineralized water
  • Tygon tubing and flow meter
  • Maps and sampling procedures

. Portable monitoring equipment

  • MGPI grip tongs

___9 EVALUATE METHODS AND MATERIALS FOR TRANSPORTATION OF HIGH ACTIVITY SAMPLES (MGPI shield cart)

NUMBER PROCEDURE TITLE EPIP-4.24 GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY I

PACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED i

___10 NOTIFY RPS THAT TEAM IS BEING DISPATCHED

___11 GO TO SAMPLE LOCATION:

a) Use pre-planned route b) Verify dose rates within b) IF unexpected radiological expected levels during transit conditions are encountered along the route, THEN do the following:

1) Use route of lowest dose field.
2) Notify RPS of radiological conditions.

c) Maintain ALARA NOTE: The intent of the transport equipment inspection is to identify:

  • Deformation, cracks or excessive wear on any part of the lifting device.
  • Loose or missing fasteners.

[Required per VPAP-0906, Control of Fabricated or Modified Tools]

___12 INSPECT SAMPLE TRANSPORT EQUIPMENT FOR WELD AREA OR BOLT DEFECTS (IF USED):

  • Lifting device

. MGPI shield cart

NUMBER PROCEDURE TITLE REVISION EPIP-4.24 GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY 13 PAGE 1 6 of 9 AEEH ACTION/EXPECTED RESPONSE F-I RESPONSE NOT OBTAINED

___13 GET IODINE/PARTICULATE SAMPLE:

a) Maintain continuous exposure surveillance b) Check if normal gaseous b) IF using MGPI. THEN do the effluent sampling systems to be following:

used

1) Use Attachment 1, High-Range Sampling Using MGPI, to take sample.
2) GO TO Step 14.

c) Remove iodine/particulate sample assembly d) Determine sample volume on first iodine/particulate sample (assume sample started at beginning of accidental release)

NUMBER PROCEDURE TITLE REVISION EPIP-4.24 GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY 13 PAGE I 1 7 of 9

-LFH ACTION/EXPECTED RESPONSE H-] RESPONSE NOT OBTAINED H-14 CHECK NOBLE GAS SAMPLE - REQUIRED: IF noble gas sample NOT required, THEN do the following:

a) Assure charcoal cartridge (located in assembly upstream 1) Assure iodine/particulate of noble gas chamber) is removed sample assembly is installed with a silver zeolite cartridge b) Assure particulate patch is in and particulate patch in place.

place

2) GO TO Step 15.

c) Attach 100 cc sample chamber to the two sample valves at grab sample skid with flexible hose CAUTION: Closing MGPI bypass valve (V-8) more than 450 may dead head pump.

d) Establish flow through gas chamber:

1) Open both sample valves
2) Open petcocks on gas chamber
3) Slowly close bypass valve
4) Maintain flow to purge chamber e) Isolate gas chamber:
1) Open bypass valve
2) Close sample valves and petcocks f) Remove gas chamber

NUMBER PROCEDURE TITLE REVISION EPIP-4.24 GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY 13 PAGE 8 of 9

-Dli ACTION/EXPECTED, RESPONSE [-1 .

RESPONSE NOT OBTAINED F-CAUTION: Make sure to open the flowmeter side (supply) before opening the bubbler (discharge). Opening the discharge first may cause air pressure to push water from the bubbler into the flowmeter.

___15 CHECK TRITIUM SAMPLE - REQUIRED: GO TO Step 16.

a) Assure both particulate patch and charcoal filter are in place b) Attach tritium sampler:

1) Facing sample station, connect flowmeter hose to supply valve
2) Open flowmeter needle valve 3 turns
3) Connect bubble hose/bubbler assembly to discharge valve c) Establish flow through tritium sampler:
1) Open both sample valves at about the same time
2) Slowly close bypass valve to establish a flowrate of about 2 1pm
3) Adjust ratemeter, as necessary, to obtain 2 lpm
4) Allow flow for about 5 minutes:
  • Collect at least 500 mls (to meet LLD)
  • Note actual sample duration d) Isolate tritium sampler:
  • Open bypass valve
  • Close both sample valves at about the same time e) Remove tritium sampler apparatus

NUMBER PROCEDURE TITLE REVISION EPIP-4.24 GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY 13 PAGE 1 9 of 9 16 DETERMINE WHERE TO TRANSPORT SAMPLE:

IF sample reads THEN prepare sample for:

GREATER THAN OR EQUAL TO 10 mR/hr Hot Lab LESS THAN 10 mR/hr Count Room

.__17 DELIVER SAMPLE:

a) Place sample in clean poly bag b) Quickly leave area by preplanned route c) Record the following on sample:

  • Date
  • Time
  • Sample type
  • Volume (if normal gaseous effluent system used) d) Deposit sample in Count Room or Hot Lab IAW Step 16

_18 NOTIFY RPS SAMPLING COMPLETE

.,_19 TERMINATE EPIP-4.24:

a) Give completed EPIP-4.24, forms and other applicable records to the RPS b) Completed by:_

Date:

Time:_

-END-

NUMBER ATTACHMENT TITLE REVISION EPIP-4.24 HIGH-RANGE SAMPLING USING MGPI 13 ATTACHMENT PAGE 1 1 of 5 NOTE: Ball valves V-li and V-12 are used to turn on or shut off "accident sampling flow through the first shielded Particulate/Iodine Sampler (PIS#1). V-13 and V-14 are used for the second shielded Particulate/

Iodine Sampler (PIS#2).

I. PREPARE FOR SAMPLING

1. Verify shielded Particulate/Iodine (P/I) sample is loaded in PIS#1 or PIS#2.

IF P/I sample NOT loaded, THEN do the following:

a. Verify which PIS to be loaded.
b. Prepare a new P/I holder.
c. Line up PIS#1 (PIS#2) by opening V-13 (V-il) and V-14 (V-12).
d. Close V-il (V-13) and V-12 (V-14).
e. Open the PIS door.
2. Insert the new holder into the PIS and close the door.
3. Notify Control Room of sampling for any alarms.

NUMBER ATTACHMENT TITLE REVISION EPIP-4.24 HIGH-RANGE SAMPLING USING MGPI 13 ATTACHM ENT PAGE 1 2 of 5 CAUTION: Although analog outputs will be frozen at last value, digital ports and log commands remain operational while in Program Mode.

NOTE:

  • Flow rate through the PIS is totalized by FIT-2 (the flow transmitter for the accident sampling flow path) and by the Local Processing Unit (LPU). Both totalizers must be reset when switching or replacing PIS samples. Only the Local Display Unit (LDU) totalizer resets when the vent monitor switches from NORMAL mode to ACCIDENT mode and places the shielded PIS in service.
  • The keypad sequence to escape is CC.

a The keypad sequence for HELP is HH.

  • The display will continue to scroll options while in normal operation.

II. RESET THE FIT-2 TOTALIZER (USING THE MASS FLOW TRANSMITTER KEYPAD)

1. Turn (unscrew) cover to access keypad.
2. Press P key on Mass Flow Transmitter keypad.

The following message screens will appear for about 3 seconds each:

! WARNING ! NO WHILE IN OUTPUT UPDATES PROGRAM MODE (SECTION II CONTINUED ON NEXT PAGE)

NUMBER ATTACHMENT TITLE REVISION EPIP-4.24 HIGH-RANGE SAMPLING USING MGPI 13 ATTACHMENT PAGE L 1 3 of 5 II. RESET THE FIT-2 TOTALIZER (USING THE MASS FLOW TRANSMITTER KEYPAD)

[continued]

3. WHEN the "ENTER ACCESS CODE" message screen appears, ENTER ACCESS lCODE:l THEN enter the user access code followed by the E key (ENTER).

ENTER ACCESS CODE: 123456 (Press E key.)

The following messages will alternate on the display screen:

[PRESS E TO SET llPRESS P TO SEE l SYSTEM OF UNITS NEXT CHOICE OR

4. Press the P key (NEXT).

The following messages will alternate on the display screen:

PRESS E TO PRESS P TO SEE RESET TOTALIZER NEXT CHOICE OR

5. Press the E key (ENTER) to reset the totalizer.

The following message will appear: ARE YOU SURE?

/\=YES \/=NO : NO

6. Press the /\ (Up Arrow) (YES) key.

The following message will appear: lARE YOU SURE?

=\YES \/=NO : YES

7. Press the E key (ENTER) to complete totalizer reset.
8. Press C key twice (CC) (ESCAPE) to close.

NUMBER ATTACHMENT TITLE REVISION EPIP-4.24 HIGH-RANGE SAMPLING USING MGPI 13 ATTACHMENT PAGE 1 4 of 5 III. RESET THE FIT-2 TOTALIZER DISPLAY ON THE LOCAL DISPLAY UNIT

1. Record the FIT-2 totalizer reading from the LDU (for example:

D PISTotal 3 RT-3-P, where the final character is vent being monitored, #-P for Process Vent, #-A for Vent A, #-B for Vent B).

2. Reset the FIT-2 totalizer display on the LDU.
a. Press Sel key on LDU keypad repeatedly until COMMAND screen is displayed.
b. Press up or down key on LDU keypad repeatedly until R/FIT-2 is highlighted.
c. Press Sel key on LOU keypad repeatedly until field to right of the command changes to "1".
d. Press up or down key on LDU keypad repeatedly until cursor is at first (next) digit in 4-digit password field. Password is 0000 (four zeroes).
e. Press Sel key on LOU keypad repeatedly until digit changes to first digit of the password.
f. Repeat steps d and e until all four digits of password entered.
g. Press up or down arrow repeatedly until Confirm is highlighted.
h. Press Sel key on LDU keypad to confirm the command
i. Press up or down key on LDU keypad repeatedly until R/FIT-2 is highlighted.
j. Press Sel key on LOU keypad repeatedly until field to right of the command changes to "A".
k. Press up or down key on LDU keypad repeatedly until cursor is at first (next) digit in 4-digit password field. Password is 0000 (four zeroes).
1. Press Sel key on LOU keypad repeatedly until digit changes to first digit of the password.
m. Repeat steps k and 1 until all four digits of password entered.
n. Press up or down arrow repeatedly until Confirm is highlighted.
o. Press Sel key on LDU keypad to confirm the command.
p. Press Sel key on LDU keypad to confirm the command.

NUMBER ATTACHMENT TITLE REVISION EPIP-4.24 HIGH-RANGE SAMPLING USING MGPI 13 ATTACHMENT PAGE 1~ 5 of 5 NOTE: For PIS#1 to be in service, V-li and V-12 are open. and V-13 and V-14 are closed. For PIS#2 to be service V-13 and V-14 are open, and V-il and V-12 are closed.

IV. REMOVE SAMPLE AND DELIVER TO COUNT ROOM

_ 1. Verify which PIS to be changed.

2. Prepare a new P/I holder to replace the one to be removed.
3. Change out PIS#1 (PIS#2) by opening V-13 (V-li) and V-14 (V-12).
4. Close V-li (V-13) and V-12 (V-14).
5. Use grip tong to open PIS door and grab P/I holder.
6. Place P/I holder inside shielded cart and close cart door.
7. Insert new holder into PIS and close PIS door.
8. Deliver sample to Count Room.

NOTE: Part V. Install New Particulate/Iodine Holder, below is applicable when there is no P/I sampler installed.

V. INSTALL NEW PARTICULATE/IODINE HOLDER

1. Verify which PIS to be loaded.
2. Prepare a new P/I holder.

_ 3. Line up PIS#1 (PIS#2) by opening V-13 (V-li) and V-14 (V-12).

4. Close V-1l (V-13) and V-12 (V-14).
5. Open the PIS door.
6. Insert the new holder into the PIS and close the door.

VIRGINIA POWER NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-5.08 DAMAGE CONTROL GUIDELINE 8 (With 6 Attachments) PAGE L~ 1 of 6 PURPOSE To provide guidance, including task definition and evaluation, to the Emergency Maintenance Director and Maintenance Support Team personnel

\This during an emergency.

LEE 2 DI i erifted Documnent Shoud13e1 eurifed And Annotated TO a~ CoUntrolld Sur As Required to 'erfoflnWofk ENTRY CONDITIONS Any one of the following:

1. Declaration of an Alert. Site Area Emergency or General Emergency.
2. Entry from another EPIP.
3. Direction by the Station Emergency Manager.

Approvals on File Effective Date 4 3

NUMBER PROCEDURE TITLE REVISION EPIP-5.08 DAMAGE CONTROL GUIDELINE 8 PAGE L - ~2 of 6 F-] F-

-E{- ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 INITIATE EPIP-5.08:

  • By:

Date:

Time:

___2 VERIFY SUPPORT STAFF HAS GUIDELINES:

. Maintenance Support Team Leader:

Attachment 1

  • Maintenance Support Team:

Attachment 2

. Field Team Coordinator:

Attachment 3

  • Damage Control Coordinator (in HP): Attachment 4

___3 DETERMINE TASK REQUIREMENTS:

a) Consult with Station Emergency Manager (SEM) b) Check type of support required:

  • System or General Walkdown
  • Damage Assessment
  • Damage Repair
  • Contamination Control
  • System Modification
  • Radwaste Processing
  • Other (as specified by SEM) c) Consider having a pool of craft personnel and operators staged at HP Clean Change for quick dispatch

NUMBER PROCEDURE TITLE REVISION EPIP-5.08 DAMAGE CONTROL GUIDELINE 8 PAGE 1 ~3 of 6 NOTE: More than one maintenance support evolution may be conducted concurrently.

___4 ASSIGN TASK NUMBER(S)

___5 DETERMINE PRIORITY:

a) Evaluate task against other tasks required or underway b) Confer with SEM c) Assign priority

___6 INITIATE ATTACHMENT 5. TASK ASSIGNMENT SHEET(S):

a) Fill out Items 1 - 4 b) Assign task to Maintenance Support Team Leader c) Brief Maintenance Support Team Leader on the following:

  • Task requirements
  • Task priority d) Give Attachment 5 to Team Leader

NUMBER PROCEDURE TITLE REVISION EPIP-5.08 DAMAGE CONTROL GUIDELINE 8 PAGE 4 of 6 r

-EEH ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED

___7 CHECK IF ADDITIONAL MAINTENANCE GO TO Step 8.

SUPPORT TEAM PERSONNEL ARE NEEDED FOR TASK PLANNING:

a) Evaluate availability and expertise of onsite support personnel b) Request additional personnel resources through the Emergency Administrative Director

.__8 CHECK IF SUPPORT IS NEEDED FROM GO TO Step 9.

OTHER DEPARTMENTS:

a) Consult with Emergency Directors b) Have Maintenance Support Team Leader assist with interface to coordinate planning and assignments

___9 CHECK IF OFFSITE ASSISTANCE IS GO TO Step 10.

REOUIRED:

a) Evaluate need for support from any of the following:

  • A & E Vendor
  • Corporate resources
  • Other organizations as deemed necessary b) Ask Emergency Administrative Director to coordinate resource requests through LEOF

NUMBER PROCEDURE TITLE REVISION EPIP-5.08 DAMAGE CONTROL GUIDELINE 8 PAGE 5 of 6

-AH.

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED F-

_ 10 GIVE PERIODIC TASK STATUS UPDATES TO SEM AND COGNIZANT EMERGENCY DIRECTOR(s) (Consult with Maintenance Support Team Leader about status of tasks in progress)

___11 CHECK - TASK PRIORITIES CHANGED: GO TO Step 12.

a) Consult with SEM b) Assign new priorities c) Notify Maintenance Support Team Leader 12 ASSURE THE FOLLOWING ARE KEPT CURRENT:

  • TSC Status Board
  • Attachment 6, Task Log

___13 CHECK IF NEW TASKS HAVE BEEN GO TO Step 15.

IDENTIFIED

___14 RETURN TO STEP 3

.__15 CHECK EMERGENCY - TERMINATED RETURN TO Step 10.

NUMBER PROCEDURE TITLE REVISION EPIP-5.08 DAMAGE CONTROL GUIDELINE 8 6 PAGE I 1 6 of 6

-AFH ACTION/EXPECTED RESPONSE 1-] RESPONSE NOT OBTAINED H-

___16 TERMINATE EPIP-5.08:

a) Consult with SEM on restoration actions b) Notify Damage Control Coordinator (in HP) of status c) Collect documentation d) Give EPIP-5.08, forms and other applicable records to Emergency Procedures Coordinator e) Completed by:

Date:

Time:

-END -

NUMBER ATTACHMENT TITLE REVISION EPIP-5.08 MAINTENANCE SUPPORT TEAM LEADER GUIDELINES 8 ATTACHMENT PAGE 1 1 of 1

1. Get Attachment 5, Task Assignment Sheet, from Emergency Maintenance Director NOTE: The Field Team Coordinator is a Maintenance Support Team member assigned to oversee task planning and control of teams dispatched to the field.
2. Record name of assigned Field Team Coordinator on Attachment 5, Item 5
3. Record Priority. Task Number, and Task Description on the following:
  • Attachment 6. Task Log
  • TSC Status Board
4. Give Attachment 5, Task Assignment Sheet, to Field Team Coordinator and brief individual on task requirements
5. Have Maintenance Support Team Members support Field Team Coordinator in task planning:
  • Procedures needed to perform task
  • Schematics and drawings
  • Identification/acquisition of parts and equipment
  • Determination of protective gear required
6. Check status of tasks in progress:

a) Confer with Field Team Coordinator b) Update Attachment 6. Task Log c) Update TSC Status Board

NUMBER ATTACHMENT TITLE EPIP-5.08 MAINTENANCE SUPPORT TEAM GUIDELINES ATTACHMENT NOTE: The Maintenance Support Team has overall responsibility for the following:

  • Developing proposed repair action plans
  • Assisting the Field Team Coordinator in task planning
  • Specifying/acquiring drawings, procedures, tools, equipment, and parts necessary for task performance
1. Get task assignment from Maintenance Support Team Leader
2. Consider the following when evaluating task requirements:

a) Walkdowns and damage assessment/repair:

  • Ingress/egress routes
  • Special procedural requirements
  • Damage Control Kit
  • Materials for temporary repair (including non-qualified material for temporary function restoration)
  • Sources of materials (alternate unit, Surry) b) Contamination control:
  • Isolation of systems or components
  • Manual containment isolation Isolation of severely contaminated rooms or buildings, including access, piping and ventilation
  • Radiological clean-up
  • Pumping of spills to radwaste systems c) System modifications:
  • Emergency changes to existing systems/structures
  • Changes to setpoints or controls
  • Alterations to liquid or gaseous flowpaths
  • Temporary shielding
  • Alterations to radwaste systems
  • Temporary/altered electrical systems d) Radwaste:
  • Location of spills (e.g.. outside containment)
  • Chemical addition for radioiodide control
  • Contingencies for processing of radwaste which exceeds capacity of existing systems

NUMBER ATTACHMENT TITLE REVISION EPIP-5.08 MAINTENANCE SUPPORT TEAM GUIDELINES 8 ATTACHMENT PAGE 2 1 2 of 2

3. Identify hazards that may be associated with task:
  • Electrical
  • Toxic gases/chemicals
  • High pressure steam
  • Structural damage
  • Radiological
  • Confined entry
  • Other
4. Determine protective measures required NOTE: Temporary procedures developed for performance of emergency tasks may be approved by the Station Emergency Manager. SNSOC review should be obtained as time permits.
5. Get procedures:
  • Use existing procedures OR
  • Get approval of modified/new procedures for task
6. Identify personnel resources/expertise needed to fulfill task
7. Identify and acquire drawings, schematics, maps, tools, equipment and parts, as necessary, to perform task
8. Coordinate provisions to provide plans, procedures, supporting documents, tools, etc. to Damage Control Team through Field Team Coordinator

NUMBER ATTACHMENT TITLE REVISION EPIP-5.08 FIELD TEAM COORDINATOR GUIDELINES 8 ATTACHMENT PAGE L 3 1 of 3 NOTE: The Field Team Coordinator is a member of the Maintenance Support Team and has overall responsibility for the following:

  • Using Maintenance Support Team resources to support task planning, logistics, and determination of procedures and equipment needed to perform task.
  • Field Team preparation and control.
  • Direct interface with Damage Control Coordinator in HP.
1. Get Attachment 5. Task Assignment Sheet, from Maintenance Support Team Leader and do the following:

a) Review task assignment and resolve any questions b) Complete Task Assignment Sheet as you continue through this guideline

2. Consider phased approach to work task:

a) Consider dispatch of a team to analyze/assess task requirements and use assessment results in determination of parts. equipment. personnel resources needed to complete task b) Report assessment results (if performed) to EMD and evaluate any significant deviations from the expected task

3. Call Damage Control Coordinator (in HP) and inform individual of proposed task and to initiate preparations with HP NOTE: Damage Control Team members are not designated prior to initiation of this procedure. They are selected based on availability and expertise.
4. Designate Damage Control Team personnel to work task:

a) Consider use of existing Damage Control Teams and OSC resources b) Select team members based on expertise, task requirements and allowable exposure c) Record Team ID and names of personnel on Task Assignment Sheet

5. Consider use of dry-run for practice, ALARA versus urgency of task

NUMBER ATTACHMENT TITLE REVISION EPIP-5.08 FIELD TEAM COORDINATOR GUIDELINES 8 ATTACHMENT PAGE L 3 2 of 3

6. IF HP briefing required, THEN have Damage Control Coordinator ask RPS for
6. IF HP briefing required, THEN have Damage Control Coordinator ask RPS for assistance.
7. Ask RAD for evaluation of emergency radiation exposure limits
8. Determine if special hazards briefing is required:
  • Electrical hazards
  • High pressure steam
  • Toxic gases/chemicals
  • Structural damage
  • Confined entry
  • Other
9. Specify protective measures required of team members
10. Determine briefing location
11. Specify tools, equipment, and procedures to be used on Task Assignment Sheet
12. Get task approvals
13. Have team get a radio and report to briefing location
14. Brief team:
  • Use Attachment 5. Task Assignment Sheet, to do briefing and give copy to team OR
  • Send Task Assignment Sheet to Damage Control Coordinator in HP and have Damage Control Coordinator do briefing

NUMBER ATTACHMENT TITLE REVISION EPIP-5.08 FIELD TEAM COORDINATOR GUIDELINES 8 ATTACHMENT PAGE 3 3 of 3

15. Control task evolution:

a) Direct task performance b) Maintain communications with team or set up relay network with Damage Control Coordinator c) Check status and update EMD, Maintenance Support Team Leader and Damage Control Coordinator d) Get resources through Maintenance Support Team Leader as needed

16. WHEN task complete, THEN do the following:

a) Notify Maintenance Support Team Leader and Damage Control Coordinator b) Check if follow-up tasks required c) Complete Task Assignment Sheet

NUMBER ATTACHMENT TITLE REVISION EPIP-5.08 DAMAGE CONTROL COORDINATOR GUIDELINES 8 ATTACHMENT PAGE 14 1 of 2

1. Establish contact with TSC Maintenance Support Field Team Coordinator
2. Ask to have Task Assignment Sheet sent to you (via fax, if possible)
3. Review Task Assignment Sheet and resolve any issues with Field Team Coordinator
4. Ask Radiation Protection Supervisor (RPS) to initiate the following:

a) Determine RWP (a Special RWP may have to be created for task) b) Check if continuous HP coverage is required c) Check availability of the following (as necessary):

  • Protective clothing
  • Dosimetry
  • Survey Instrumentation d) IF emergency radiation exposure authorization required, THEN ask RPS to have EPIP-4.04, EMERGENCY PERSONNEL RADIATION EXPOSURE, initiated e) Determine ingress and egress routes (considering identified hazards) for each task
5. Brief Damage Control Team (if not performed by Maintenance Support Team Leader or Field Team Coordinator):

a) Review Task Assignment Sheet with team b) Task objectives c) Ingress/egress routes d) Specific assignments e) Radiological considerations (ask RPS for assistance) f) Radio Frequency Interference (RFI) area considerations (as appropriate)

6. Ensure team has the following:
  • Means of communication (radio or contingency method)
  • Copy of Task Assignment Sheet

NUMBER ATTACHMENT TITLE REVISION EPIP-5.08 DAMAGE CONTROL COORDINATOR GUIDELINES 8 ATTACHMENT PAGE 4 2 of 2

7. Dispatch team
8. WHEN team returns, THEN do the following:
  • Notify Field Team Coordinator of return
  • Have team representative contact Field Team Coordinator in TSC and discuss need for follow-up tasks, special circumstances, etc.
  • Have team representative ensure Task Assignment Sheet completed
  • Have team representative ensure Task Assignment Sheet is returned to the Field Team Coordinator

NUMBER ATTACHMENT TITLE EPIP-5.08 TASK ASSIGNMENT SHEET ATTACHMENT l5

1. TASK NUMBER:
2. DATE/TIME ASSIGNED: I
3. TASK DESCRIPTION:

[] System or General Walkdown

[] Damage Assessment

[] Damage Repair

[] Contamination Control

[] Emergency System Modification (e.g., Jumpers)

[] Radwaste Processing

[] Special:

4. DESCRIBE TASK: .
5. NAME OF MAINTENANCE SUPPORT FIELD TEAM COORDINATOR:
6. HP BRIEFING REQUIRED: [] YES; E] NO
7. DOSE EXTENSION REQUIRED: [I YES: [] NO. LIMIT IS:
8. SPECIAL HAZARDS BRIEFING REQUIRED: [I YES; [] NO IF YES, DEFINE HAZARDS: [] ELECTRICAL [] TOXIC GASES/CHEMICALS

[] HIGH PRESSURE STEAM [] STRUCTURAL [I RADIOLOGICAL

[] CONFINED ENTRY [] OTHER:

9. PROTECTIVE MEASURES REQUIRED:
10. BRIEFING WILL BE CONDUCTED AT:

[] OSC; [] TSC; [] HP (Fax this sheet); [] OTHER:

11. TOOLS/EQUIPMENT TO TAKE:

NUMBER ATTACHMENT TITLE REVISION EPIP-5.08 TASK ASSIGNMENT SHEET 8 ATTACHMENT PAGE 5 2 of 2

12. PROCEDURES:

[] NONE: [] STANDARD: SPECIFY -

[] SPECIAL: PROVIDE COPY OF PROCEDURE

13. APPROVALS:

[I MAINTENANCE SUPPORT TEAM LEADER:

[I EMD:

[] SEM:

14. TEAM ID:

PERSONNEL ASSIGNED TO TEAM:

15. REPORTING INTERVAL: CAUTION:

[I Report to _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _:DO NOT USE RADIOS

[I Every 30 minutes IN RADIO FREQUENCY

[] Other: INTERFERENCE (RFI)

[] Upon task completion AREAS.

16. HP BRIEFING (IF REQUIRED) GIVEN BY:
17. TASK TEAM BRIEFING CONDUCTED BY:
18. DATE/TIME TEAM DISPATCHED:
19. DATE/TIME TEAM RETURNED:
20. NOTES/COMMENTS (e.g.. follow-up actions required. special circumstances encountered, other):
21. DATE/TIME TASK COMPLETED: /

NUMBER ATTACHMENT TITLE REVISION EPIP-5.08 TASK LOG 8 ATTACHMENT PAGE 6 1 of 1 PRIORITY TASK TASK TEAM STATUS NUMBER DESCRIPTION ID 4- 4 4 4 4- 4 4- 4 4 t + I 4 1 4 4 r 1 -t I

  • + 4 4-I 4-- 4 +

.I

£ ________________________________________ I

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