ML021190521
| ML021190521 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/22/2002 |
| From: | Blount R Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 02-262 | |
| Download: ML021190521 (92) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 22, 2002 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.02-262 SS&LJBAG RO Docket No.
50-280 50-281 License No. DPR-32 DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 REVISIONS TO EMERGENCY PLAN IMPLEMENTING PROCEDURES Pursuant to 10 CFR 50.54(q), enclosed are revisions to five Surry Power Station Emergency Plan Implementing Procedures. The 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 the enclosed tabulation of changes.
Very truly yours, Richard H. Blount, Site Vice President Surry Power Station Enclosure Commitments contained in this letter: None.
cc:
U. S. Nuclear Regulatory Commission, Region II (2 copies)
Sam Nunn Atlanta Federal Center 61 Forsyth Street S.W., Suite 23 T85 Atlanta, Georgia 30303-8931 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station
-Ptloq-6
Serial No.02-262 Surry EPIP Revisions VIRGINIA ELECTRIC AND POWER COMPANY REVISION TO SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE Enclosed are revisions to Surry Power Station Emergency Plan Implementing Procedures. Please take the following actions in order to keep your manual updated with the most recent revisions.
REMOVE AND EFFECTIVE INSERT:
EFFECTIVE DESTROY:
DATE:
DATE:
EPIP-4.01, Rev. 16 04/19/00 EPIP-4.01, Rev. 17 04/10/02 EPIP-4.08, Rev. 14 11/29/01 EPIP-4.08, Rev. 15 04/10/02 EPIP-4.09, Rev. 12 11/29/01 EPIP-4.09, Rev. 13 04/10/02 EPIP-4.22, Rev. 04 10/20/94 EPIP-4.22, Rev. 05 04/10/02 EPIP-4.23, Rev. 08 10/20/94 EPIP-4.23, Rev. 09 04/10/02 Emergency Plan Privacy and Proprietary Material have been removed.
Reference Generic Letter No. 81-27
Serial No.02-262 Surry EPIP Revisions bc page 1 of 1 bc:
Mr. Michal Small/B. A. Garber - SPS (electronic) (w/o enclosure)
Mr. J. B. Costello - IN2NE (electronic) (w/o enclosure)
Records Management - (IN) c/o Corp Licensing (M. McClure)
GOV 02-054B, IN2SE, Corp Licensing (M. McClure) (w/o enclosure)
CONCURRENCE See Station Correspondence Review and Approval Form Commitments (Stated or Implied)/Action Plan None Verification of Accuracy:
- 1.
Memorandum R.H. Kulp to Mike Small, dated April 11, 2002, Transmittal of EPIP Revisions to the NRC.
Required Changes to the UFSAR or QA Topical Report None
LEVEL 2 DISTRIBUTION VIRGINIA POWER This Document Should Be Verified SURRY POWER STATION And Annotated to A Controlled Source EMERGENCY PLAN IMPLEMENTING PROCEDURE As Required to Perform Work NUMBER PROCEDURE TITLE REVISION EPIP-4.O1 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 APROCEDURE (With 1 Attachment)
PAGE 1 of 30 PURPOSE To initially assess emergency conditions, provide protective measures recommendations, establish an emergency organization and direct Health Physics response to an emergency.
ENTRY CONDITIONS Activation by EPIP-1.01, EMERGENCY MANAGER CONTROLLING PROCEDURE.
Approvals on File Effective Datez4 oz.
-LFTJ-ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1
INITIATE PROCEDURE:
- By:
Date:
Time:
NOTE:
- During the initial stages of an emergency, the Operations Shift Supervisor may assume the Station Emergency Manager (SEM) position and the HP Shift Supervisor may assume the Radiological Assessment Director (RAD) position. The RAD may report to the Control Room if the TSC is not activated.
- Notification of an Alert or higher emergency classification is normally made via Gai-Tronics.
The SEM normally informs the RAD of a Notification of Unusual Event declaration via telephone.
2 ASK SEM FOR BRIEFING:
"* Existing plant conditions
"* Emergency Action Levels (EALs) exceeded
"* Emergency Classification 3
CHECK IF OFFSITE RELEASE IS OCCURRING OR HAS OCCURRED 4
DIRECT INITIATION OF EPIP-4.30, USE OF MIDAS CLASS A MODEL GO TO Step 5.
IF MIDAS NOT available, THEN evaluate release using desk-top calculations:
"* EPIP-4.08, INITIAL OFFSITE RELEASE ASSESSMENT
"* EPIP-4.09, SOURCE TERM ASSESSMENT
"* EPIP-4.10, DETERMINATION OF X/1 NUMBER PROCEDURE TITLE REVISION EPIP-4.Ol RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 PROCEDURE1 PAGE 2 of 30 1-m
ACTION/EXPECTED RESPONSE 5 CHECK EMERGENCY CLASSIFICATION 5
CHECK EMERGENCY CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT 6
CHECK HP SUPPORT REQUIRED RESPONSE NOT OBTAINED GO TO Step 7.
IF HP support NOT immediately required, THEN standby to provide support AND GO TO Step 7 when support is required OR WHEN emergency is terminated, THEN GO TO Step 32.
7 EVALUATE ASSIGNING EPIP-4.02, RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE 8 PROVIDE SUPPORT FOR EMERGENCY OPERATING PROCEDURE (EOP)
AND ACCIDENT MITIGATION TASK ACTIVITIES, AS NECESSARY:
a)
Notify RPS when an EOP or Accident Mitigation Task is planned or in progress b)
Make sure priority is given to expediting EOP and Accident Mitigation Task activities NUMBER PROCEDURE TITLE REVISION EPIP-4.O1 RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 EPIP-401.
- PROCEDU-RE-PAGE 3 of 30
- ISJ-Z I-l l
ACTION/EXPECTED RESPONSE 9
CHECK EVENT LIMITING FAULT:
I.
RESPONSE NOT OBTAINED GO TO Step 14.
"* LOCA - GO TO NOTE prior to Step 10
"* Main Steam Line Rupture GO TO NOTE prior to Step 11
"* Steam Generator Tube Rupture GO TO Step 12
"* Fuel Handling Accident - GO TO NOTE prior to Step 13 NOTE:
A LOCA may not initially result in a large release, but may produce a large potential for release from containment.
10 INITIATE RESPONSE TO LOCA:
a)
Ask SEM to evacuate Auxiliary Building and Safeguards b) Block entry until surveys confirm radiological hazards c) Evaluate manpower support for Post Accident Containment Air or Reactor Coolant sampling d) Determine crane wall radiation monitor reading e)
GO TO Step 14 NUMBER PROCEDURE TITLE REVISION EPIP-4.Ol RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 EPIP4.01PROCEDURE-
"PAGE 4 of 30 F-
-LFJ-L ACTION/EXPECTED RESPONSE F-H RESPONSE NOT OBTAINED NOTE:
Potential releases from a Main Steam Line Rupture Containment, Main Steam Safety or AFWPT exhaust.
11 INITIATE RESPONSE TO MAIN STEAM LINE RUPTURE:
a) Check station ventilation effluent monitors b)
Ask SEM for the following data:
"* Location of steam break
"* Status of actual or potential Main Steam Safety Valve lift Number valves lifted:
"* Length of time valves remained open (if lifted):
(min.)
"* AFWPT status
"* Main Steam and AFWPT exhaust monitor readings
"* Assistance in flow rate (lbs/hr) determination may develop from c)
GO TO Step 14 NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLIN 17 EP I P-4.01,-
P ROC EDURE-1 PAGE 5 of 30 H-l
ACTION/EXPECTED RESPONSE 12 INITIATE RESPONSE TO STEAM GENERATOR TUBE RUPTURE:
a) Ask SEM for the following data:
"* Status of Air Ejector divert
"* Number of Main Steam Relief Valves lifted or that may potentially lift:
"* Length of time valves remained open (if lifted):
min.
"* Assistance in flow rate (lbs/hr) determination
"* Status of Main Steam supply to AFWPT
"* Steam Generator Blowdown status b)
Check steam supply to AFWPT ISOLATED c)
Ask SEM place personnel in Emergency Switchgear Room to report Main Steam and AFWPT exhaust monitor readings b) ill steam supply to AFWPT NOT
- isolated, THEN ask SEM to initiate isolation.
(STEP 12 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.O1 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 PRC R-PAGE 6 of 30 RESPONSE NOT OBTAINED I
~ACTION/EXPECTED
RESPONSE
I RESPONSE NOT OBTAINED 12 INITIATE RESPONSE TO STEAM GENERATOR TUBE RUPTURE: (Continued) d) Consider blocking access to the following areas until surveyed:
"* Service Building Hallway
"* Turbine Deck
"* Steam Generator Blowdown Cooler, Turbine Building Basement
"* Steam Generator Blowdown lines, Auxiliary Building Basement
"* Relief Valves, Safeguards Roof
"* AFWPT exhaust, Unit #1 or #2 all eyway
"* Condensate Polishing Building e) Evaluate sampling:
"* Steam Generator Blowdowns
"* Air Ejectors
"* Main Steams f)
GO TO Step 14 NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 EP I P-4. 011-PROCEDURL 1-AG PAGE 7 of 30
ACTION/EXPECTED RESPONSE l
RESPONSE NOT OBTAINED NOTE:
Analysis of accidents involving decayed spent fuel should include consideration of onsite skin dose due to Kr-85.
13 INITIATE RESPONSE TO FUEL HANDLING ACCIDENT:
a)
Check event - Fuel cask drop or suspected seal leak b) Evaluate the following:
"* Access control in affected area
"* Neutron monitoring
"* Air sampling to confirm fission product release c)
GO TO Step 14 d)
Do the following for Fuel Handling Accident in Spent Fuel Pool or Containment:
- 1) Ask SEM to evacuate all non-essential personnel from Fuel Building and affected Containment
- 2) Isolate purge of affected Containment
- 3) Consider potential radiological problems with Reactor Cavity or Spent Fuel Clean-up System a)
GO TO Step 13.d.
NUMBER PROCEDURE TITLE REVISION EPIP-4.Ol RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 EPIP-4.01-PROCEDURE-PG PAGE 8 of 30 1-I
.a
-LFH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:
e Additional manpower may be needed to assist in offsite dose calculations.
e Initial offsite release assessments should be made using EPIP-4.30, USE OF MIDAS CLASS A MODEL, to quickly assess the release and to recommend protective measures.
14 CHECK EVENT -
RADIOLOGICAL RELEASE:
a) Initiate effluent sampling if manpower permits b) Give consideration to initiating EPIP-4.03, DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE c) Initiate EPIP-4.30, USE OF MIDAS CLASS A MODEL GO TO Step 18.
a)
Use monitor readings for follow-up assessment.
c) IF MIDAS NOT available, THEN evaluate release using desk-top cal cul ati ons:
"* EPIP-4.08, INITIAL OFFSITE RELEASE ASSESSMENT
"* EPIP-4.09, SOURCE TERM ASSESSMENT
"* EPIP-4.10, DETERMINATION OF X/O d) Consider having RPS prepare for dispatch of Offsite Monitoring Teams:
"* Team assembly
"* Preparation of equipment and vehicles e) Direct initiation of 40CFR302 EPA Notification Requirements and Reportable Quantity calculations in accordance with normal HP procedures NUMBER PROCEDURE TITLE REVISION EPIP-4.O1 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 EPIP-4.01PROCEDURE
=
PAGE 9 of 30 a
l
ACTION/EXPECTED RESPONSE 15 VERIFY EMERGENCY CLASSIFICATION:
a) Check results of offsite release assessment at Site Boundary greater than or equal to the following:
- 250 mR/hr Thyroid CDE b) Get estimate of current or potential release duration (hours) from SEM c) Calculate projected dose:
a)
GO TO Step 16.
b)
IF estimate NOT available, THEN assume 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
IDuration (hours) x Dose Rate = Projected DoseI d) Confirm emergency classification:
e) Notify SEM of emergency classification NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DI RECTOR-CONTROLLING 17
- DTD~nlLI.-*.*.
PROCEDUR-E-
.PB PAGE 10 of 30
-4 RESPONSE NOT OBTAINED HI RESULTS OF CALCULATION EMERGENCY CLASSIFICATION Projected dose greater than or equal to General Emergency 1 Rem TEDE or 5 Rem Thyroid CDE Projected dose greater than or equal to Site Area Emergency 0.1 Rem TEDE or 0.5 Rem Thyroid CDE
% Technical Specifications greater than Alert or equal to 1000%
% Technical Specifications greater than Notification of or equal to 100%
Unusual Event Below 100% Technical Specifications N/A
ACTION/EXPECTED RESPONSE V-H 16 DETERMINE OFFSITE PROTECTIVE MEASURES FOR GENERAL EMERGENCY CLASSIFICATION:
a)
Use Site Boundary 2, 5 and 10 mile TEDE and Thyroid CDE doses from EPIP-4.30, USE OF MIDAS CLASS A MODEL RESPONSE NOT OBTAINED IF classification NOT a General Emergency, THEN GO TO Step 17.
a) IF MIDAS NOT available, THEN use dose rates from desk-top calculations:
"* EPIP-4.08, INITIAL OFFSITE RELEASE ASSESSMENT
"* EPIP-4.09, SOURCE TERM ASSESSMENT
"* EPIP-4.10, DETERMINATION OF X/0 b) Initiate EPIP-4.07, PROTECTIVE MEASURES c) Make recommendations to SEM that address the following:
"* Protective measures offsite
"* Distance protective measures are required NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING EPIP-4.01 17PROCEDURE7 "PAGE 11 of 30 I-l
__F'*-*
ACI N/EXPECTED RESPONSE I
I EPNSE NOT OBTAINED 17 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,.
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-4.0l RADIOLOGICAL ASSESSMENT DIRECTORKCONTROLLING 17 EPIP-4.01PROCEDURE PAGE 12 of 30
STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:
The following response actions may have to be coordinated by the RAD.
These actions are not listed in order of priority.
18 EVALUATE HP RESPONSE ACTIONS WHEN all necessary response actions addressed, THEN GO TO AND Step 29.
DETERMINE RESPONSES ON A PRIORITY BASIS:
"* Offsite monitoring: GO TO NOTE prior to Step 19
"* Injured contaminated personnel:
GO TO NOTE prior to Step 20
"* Inplant / Onsite radiological assessment: GO TO NOTE prior to Step 21
"* TSC activated, establish organization: GO TO Step 22
"* Offsite release assessment: GO TO Step 23
"* Evacuate non-essential personnel: GO TO Step 24
"* Activate LEOF:
GO TO Step 25
"* Dosimetry for offsite assistance (Fire, rescue squads): GO TO Step 26
"* Respiratory Protection: GO TO Step 27
"* Relief: GO TO Step 28
"* Limiting Fault event (LOCA, Main Steam Line Break, SGTR or Fuel Handling Accident): RETURN TO Step 9
"* Radiological release: RETURN TO Step 14 NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING EPIP-4.01 PROCEDUREI 17 PAGE 13 of 30
ACTION/EXPECTED RESPONSE
-A RESPONSE NOT OBTAINED NOTE:
° A minimum of 2 (two) Offsite Monitoring Teams must be dispatched (i.e., sent into the field) at a Site Area Emergency or General Emergency.
- Plume tracking/offsite monitoring will be the responsibility of the Radiological Assessment Coordinator (RAC) upon LEOF activation.
19 EVALUATE NEED FOR OFFSITE MONITORING:
a) Consult with Dose Assessment Team Leader:
"* Meteorological conditions
"* Number of teams needed
"* Need for protective clothing
"* Projected Whole Body and Thyroid dose rates
"* Respiratory protection
"* Team location and placement (STEP 19 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 EPIP-4.01 RADIOLOGIPROCEDURE 17 PAGE 14 of 30 I
I
-ThJ-t ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 EVALUATE NEED FOR OFFSITE MONITORING: (Continued) b) Check if TEDE exposure is expected to exceed 5 Rem:
o Do calculation using sample results, MIDAS runs or default TEDE/DDE ratio table:
b)
GO TO Step 19.c.
FORMULA:
Exposure time x
Dose rate x
Ratio TEDE/DDE
=
Estimated TEDE dose hours x
Rem/hr x
Ratio
=
Rem TEDE TEDE/DDE RATIO TABLE:
ACCIDENT TYPE RATIO ACCIDENT TYPE RATIO MSLB 49 VCT Rupture 1
- Gap, PC) 3 Fuel Handling 1.5 Locked Rotor 13 WGDT Rupture 1
SRF 1
- Consider placing downwind team further
- Consider initiation of EPIP-4.04, EMERGENCY PERSONNEL RADIATION EXPOSURE (STEP 19 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 EPIP-4-01,-.
-PROCEDURE PG PAGE 15 of 30 1-I
ACTION/EXPECTED RESPONSE
-1 19 EVALUATE NEED FOR OFFSITE MONITORING: (Continued) c) Check if Thyroid CDE expected to exceed 25 Rem:
RESPONSE NOT OBTAINED c)
GO TO Step 19.d.
- 1) Do calculation using concentration (jiCi/cc) based on survey results and actual or projected exposure duration (hours):
jiCi/cc x 1.57E+6 x hours =
- 2) Ask SEM for approval to administer radioprotective drugs
- 3) Consider initiation of EPIP-5.07, ADMINISTRATION OF RADIOPROTECTIVE DRUGS d) Notify RPS of resource and equipment requirements:
"* Number teams required
"* Protective clothing required
"* Respiratory protection required
"* Have teams assemble equipment and vehicles AND Have teams notify TSC via radio prior to dispatch e)
RETURN TO Step 18 NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 EPIP-4.01.--
PROCEDURE 17 PAGE 16 of 30
- ýSTEP
ACTION/EXPECTED RESPONSE NOTE:
First aid considerations must be efforts.
20 INITIATE RESPONSE TO CONTAMINATED INJURED INDIVIDUAL:
a)
Determine the following information:
"* Offsite medical treatment REQUIRED
"* Contamination survey confirms personnel contamination
"* Clothing removal cannot be used to clear individual b)
Check data indicates need to transport contaminated personnel to hospital c)
Have RPS direct initiation of normal HP procedures for response to contaminated injured personnel d)
Have HP representative accompany victim RESPONSE NOT OBTAINED given priority over decontamination b)
RETURN TO Step 18.
e)
RETURN TO Step 18 NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 EPIP-4.01-PROCEDURE-P PAGE 17 of 30 I
ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
Inplant/Onsite monitoring teams shall be used to assess radiological conditions within the site boundary and to accompany Damage Control, Sample Analysis and Post Accident Sample Teams.
21 INITIATE INPLANT/ONSITE RADIOLOGICAL ASSESSMENT:
a) Consult with RPS:
"* Plant conditions
"* Equipment failure
"* Elevated radiation monitor readings
"* Radiological release points.
plume direction and affected areas
"* Access control points established
"* Recent survey results b) Help RPS select the following:
"* Monitoring and sample locations
"* Protective clothing and respiratory protection
"* Dosimetry and monitoring devices (STEP 21 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 EPIP-4.01 PROCEDURE PAGE 18 of 30 I
-1 ýSTEP I
I
ACTION/EXPECTED RESPONSE I-]
21 INITIATE INPLANT/ONSITE RADIOLOGICAL ASSESSMENT: (Continued) c) Check if survey results (pCi/cc) and exposure time indicate exposure greater than 25 Rem Thyroid CDE:
RESPONSE NOT OBTAINED I
c)
GO TO Step 21.d.
- 1) Do calculation:
_ji Ci/cc x 1.57E+6 x
-hours
=
- 2) Consider use of SCBA
- 3)
Ask SEM for approval to administer radioprotective drugs
- 4) Initiate EPIP-5.07, ADMINISTRATION OF RADIOPROTECTIVE DRUGS
- 5)
Get supply of drugs from TSC closet (STEP 21 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.0l RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 EPIP-4.01
-PROCEDUR-Ez_
PG PAGE 19 of 30 I
l I
ACTION/EXPECTED RESPONSE 21 INITIATE INPLANT/ONSITE RADIOLOGICAL ASSESSMENT: (Continued) d) Check if projected TEDE exposure exceeds 5 Rem:
- Do calculation using sample results, MIDAS runs or default TEDE/DDE ratio table:
RESPONSE NOT OBTAINED d)
GO TO Step 21.e.
FORMULA:
Exposure time x
Dose rate x
Ratio TEDE/DDE
=
Estimated TEDE dose hours x
Rem/hr x
Ratio
=
Rem TEDE TEDE/DDE RATIO TABLE:
ACCIDENT TYPE RATIO ACCIDENT TYPE RATIO MSLB 49 VCT Rupture 1
- Gap, PC) 3 Fuel Handling 1.5 Locked Rotor 13 WGDT Rupture 1
SRF 1
- Initiate EPIP-4.04.
EMERGENCY PERSONNEL RADIATION EXPOSURE e) Check if entry required to monitor Damage Control Teams:
"* Brief RPS on planned activity
"* Verify team briefing prior to dispatch e)
GO TO Step 21.f.
(STEP 21 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 EPIP-4.01.-.
PROCEDUR-17 "PAGE 20 of 30 I
ACTION/EXPECTED RESPONSE I-1 21 INITIATE INPLANT/ONSITE RADIOLOGICAL ASSESSMENT: (Continued) f)
Determine if radiological conditions require monitoring of emergency response facilities:
"* Have RPS initiate EPIP-4.17, MONITORING OF EMERGENCY RESPONSE FACILITIES
"* Have RPS initiate EPIP-4.18, MONITORING OF LEOF g)
WHEN Post Accident Primary Coolant or Containment Air sample requested, THEN do the following:
f)
GO TO Step 21.g.
g)
GO TO Step 21.h.
- 1) Determine system to be used:
"* Normal sampling systems OR
"* Contingency sampling systems
- 2) Notify RPS of preferred sampling system
- 3)
Ask RPS to support Post Accident sampling (STEP 21 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 EPIP-4.01-
.PROCEDURE-17 PAGE 21 of 30 RESPONSE NOT OBTAINED H-
-11111"Fs T 1, DEP -j
-LJ-t ACTION/EXPECTED RESPONSE I.
RESPONSE NOT OBTAINED 21 INITIATE INPLANT/ONSITE RADIOLOGICAL ASSESSMENT: (Continued) h)
WHEN radiological release and plume direction changes or release increases, THEN do the following:
"* Notify RPS
"* Consider need for re-surveys
"* Direst establishment of new access control points based on revised survey data i)
RETURN TO Step 18 22 ESTABLISH EMERGENCY ORGANIZATION:
a)
Establish Dose Assessment Team:
"* Assign one team leader and two team members
"* Assign EPIP-4.03, DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE b) Establish Radiation Protection Supervisor position AND Assign EPIP-4.02, RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE h) RETURN TO Step 18.
c)
RETURN TO Step 18 NUMBER PROCEDURE TITLE REVISION EPiP_4.01_
RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 EPIP*4.01.
-PROCEDURE 17 PAGE 22 of 30 l
ACTION/EXPECTED RESPONSE 23 REVIEW OFFSITE RELEASE ASSESSMENTS:
a) Check radiological monitoring and meteorological parameters available to Dose Assessment Team from ERFCS (MIDAS imports ERFCS automatically) b)
Review offsite release assessments a) IF parameters NOT available from ERFCS.
THEN give completed copy of Attachment 1 to Dose Assessment Team.
b) RETURN TO Step 18.
c)
RETURN TO Step 15 24 EVALUATE NEED TO EVACUATE/SHELTER NON-ESSENTIAL PERSONNEL:
a) Determine onsite exposure of non-essential personnel:
- 1)
Review plant surveys and samples
- 2)
Calculate iodine dose commitment using radioiodine concentration (IiCi/cc) based on air sample data and actual or projected exposure duration (hours):
pCi/cc x 1.57E+6 x hours =
Rem THY CDE (STEP 24 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.O1 RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 EPIP-4.01PROCEDURE--
PAGE 23 of 30 RESPONSE NOT OBTAINED I
- ýSTEP
-LFJ-t ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 EVALUATE NEED TO EVACUATE/SHELTER NON-ESSENTIAL PERSONNEL: (Continued) b)
Check if results indicate onsite exposure of non-essential personnel greater than 1 Rem TEDE or 5 Rem Thyroid CDE b)
Do one of the following:
- IF onsite exposure for non-essential personnel greater than or equal to 0.5 Rem TEDE or 1 Rem Thyroid
- IF onsite exposure for non-essential personnel less than 0.5 Rem TEDE or 1 Rem Thyroid CDE, THEN GO TO Step 24.d c)
Make recommendation to SEM for evacuation of non-essential personnel d) Consider early release of personnel upon Alert if plant conditions appear to degrade e)
Do the following if non-essential personnel are to be evacuated:
"* Review offsite release assessments
"* Check direction of plume
"* Determine appropriate evacuation route and remote assembly area (STEP 24 CONTINUED ON NEXT PAGE) e)
RETURN TO Step 18.
NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 EPIP-4.01-_
PROC.EDURE-PG PAGE 24 of 30 1-I
-LIý-EP ACTION/EXPECTED RESPONSE I
RESPONSE NOT OBTAINED 24 EVALUATE NEED TO EVACUATE/SHELTEF, NON-ESSENTIAL PERSONNEL: (Continued) f) Have RPS assign EPIP-4.21, EVACUATION AND REMOTE ASSEMBLY AREA MONITORING g)
Have RPS do the following:
- 1) Tell survey team to notify TSC when departing from station and arriving at Remote Assembly Area
- 2) Dispatch Remote Assembly Area monitoring team h) Notify SEM of Emergency Assembly Area monitoring status i)
RETURN TO Step 18 NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 E P I P - 4. 0 1.-
P R O C E D U R E --
P A G PAGE 25 of 30 I
ACTION/EXPECTED RESPONSE 25 INITIATE LEOF ACTIVATION:
a)
Give information to Radiological Assessment Coordinator:
"* Existing plant conditions
"* Current offsite dose projections
"* HP actions underway b)
Have Dose Assessment Team Leader brief Radiological Assessment Coordinator:
"* Status and location of Offsite Monitoring Teams
"* Meteorological data
"* Radiation Monitoring System data
"* Sample analysis data c)
Have RPS assign EPIP-4.18, MONITORING OF LEOF d)
RETURN TO Step 18 NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING 17 EPIP-4.01.-
PROCEDURE-1 PAGE 26 of 30
-1 RESPONSE NOT OBTAINED I
-LFH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 HAVE DOSIMETRY ISSUED TO OFFSITE RESPONDERS:
a) Consult with RPS:
"* Arrival time of offsite support (fire, rescue squads)
"* Dosimetry requirements b) Ask RPS to consider having individual meet fire or rescue squad prior to entry onsite in order to supply dosimetry c)
RETURN TO Step 18 27 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 d) RETURN TO Step 18 NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING "EPIP-4.O1 PROCEDURE-17 PAGE 27 of 30 I-B q
F.....
ACTION/EXPECTED RESPONSE V-LI RESPONSE NOT OBTAINED 28 GIVE TURNOVER TO RELIEF:
a)
WHEN a more senior HP individual arrives onsite OR WHEN relief is needed, THEN brief successor:
- Existing plant conditions
- Emergency Classification
- Offsite release assessments
- HP actions underway b) Notify SEM of change in position c) Stay with relief for about 30 minutes to ensure proper turnover d)
RETURN TO Step 18 29 CHECK EMERGENCY CONTINUES GO TO Step 32.
30 CONSULT WITH SEM AND RPS AS TO INCREASING OR DECREASING TRENDS 31 RETURN TO NOTE PRIOR TO STEP 2 NUMBER PROCEDURE TITLE REVISION RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 EPIP-4.01 PROCEDUREP PAGE 28 of 30 W
PROCEDURE TITLE RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING PROCEDURE REVISION 17 PAGE 29 of 30 ACTION/EXPECTED RESPONSE
.I RESPONSE NOT OBTAINED I
32 INITIATE EVENT TERMINATION AND RECOVERY ACTIONS:
a) Verify SEM declared event TERMINATED b) Notify RPS and RAC of event termination c) Evaluate continued use of monitoring teams for data collection d) Consult with SEM about recovery phase:
- Access control to outside contaminated areas
- Return to normal access control areas throughout site
- Assistance requirements:
"* Decontamination efforts
"* HP support personnel
"* Radwaste packaging and disposal 33 INITIATE REPLACEMENT OF PROCEDURES AND EMERGENCY EQUIPMENT NUMBER EPIP-4.01 I
i I
-LH ACTION/EXPECTED RESPONSE 1-F RESPONSE NOT OBTAINED 34 TERMINATE EPIP-4.01:
- Give completed EPIP-4.01, forms and other applicable records to the Emergency Procedures Coordinator in the TSC
- Give to STA.
- Completed by:
Date:
Time:
-END-NUMBER PROCEDURE TITLE REVISION EPIP-4.01 RADIOLOGICAL ASSESSMENT DIRECTOR-CONTROLLING 17 EPIP-4.01 PROC.ED[JRE--
"PAGE 30 of 30 I
Date:
METEOROLOGICAL DATA Wind Direction (from):
Affected Sectors:
Wind Speed (mph):
Stability Class:
Precipitation:
RADIATION SYSTEM MONITORING DATA Vent Vent:
VG-110:
cpm VG-123: _mR/hr VG-131:
'mCi/sec "pCi /cc Process Vent:
GW-102:
cpm GW-130:
4Ci/sec "Ci /cc GW-122: _mR/hr Containment, Inside:
High Range:
RMS-127:
mR/hr RMS-227: _mR/hr RMS-128:
mR/hr RMS-228:
mR/hr Containment, Outside:
High Range:
RMS-161:
mR/hr RMS-261: _mR/hr Air Ejector:
SV-111:
cpm SV-211:
cpm Main Steam:
MS-124:
mR/hr MS-224: _mR/hr MS-125:
mR/hr MS-225:
mR/hr MS-126:
mR/hr MS-226:
mR/hr MS-129:
mR/hr NUMBER ATTACHMENT TITLE REVISION EPIP-4.01 RADIOLOGICAL DATA WORKSHEET 17 ATTACHMENT PAGE 1
1 of 1 Name:
Time:
MS-229:
-mR/hr AFWPT:
VIRGINIA POWER SURRY POWER STATION LEVEL 2 DISTRIBUTION EMERGENCY PLAN IMPLEMENTING PROCEDIAý Document Should Be. Verified NUMBER PROCEDURE TITLE As Required to Perfo'rEVVMcS*ON EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 15 PAGE (With 6 Attachments) 1 of 12 PURPOSE Use of backup (manual) dose assessment calculations to assess consequences of actual or potential offsite releases.
ENTRY CONDITIONS Any of the following:
- 1. EPIP-4.01.
RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE.
- 2.
EPIP-4.03.
DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE.
- 3.
CPIP-6.2.
RADIOLOGICAL ASSESSMENT COORDINATOR.
- 4.
Direction by the Station Emergency Manager.
Approvals on File Effective Datec4 1,Q t
-LFJ-t ACTION/EXPECTED RESPONSE I
RESPONSE
NOT OBTAINED 1 INITIATE PROCEDURE:
By:
Date:
Time:
NOTE:
An initial offsite release assessment should be performed within 15 minutes of declaration of a General Emergency.
2 CHECK IF CURRENT CLASSIFICATION UNUSUAL EVENT OR EVENT NOTIFICATION OF ALERT IF unknown, THEN GO TO Step 3 OR IF Site Area or General Emergency, THEN GO TO NOTE prior to Step 6.
NOTE:
Evaluation of percent release limits in this procedure makes assumptions about flow rate, isotopic mixture and detector response.
Further analysis upon completion of this procedure will be necessary to quantify releases.
3 CHECK IF EMERGENCY INVOLVES LIQUID RELEASE GO TO NOTE prior to Step 5.
NUMBER PROCEDURE TITLE REVISION EPIP-4.08-INITIAL OFFSITE RELEASE ASSESSMENT 15 "2
- PAGE 2 of 12 H-
SA--
-C-,-TIO,,EXPEC-,Eo, RSPONSE R
,ESPONSE NOT, OBT"AINED NOTE:
Results of Discharge Tunnel and SRF Liquid Monitor are not additive.
The Discharge Tunnel is considered the final liquid effluent release point.
4 DETERMINE PERCENT RELEASE LIMIT FOR LIQUID RELEASE:
a)
Get monitor indications:
"* Discharge Tunnel: __cpm
"* SRF RRM-131:
cpm b)
Use the following equations:
Discharge Tunnel:
cpm x 3.OE-3 = % Release Limit x 3.OE-3 =
RRM-131:
cpm x 3.37E-4 = % Release Limit x 3.37E-4 =
c) Compare percent release limit with emergency classification criteria:
"* Percent release limit GREATER THAN OR EQUAL TO 1000% -
ALERT
"* Percent release limit GREATER THAN OR EQUAL TO 100%
NOTIFICATION OF UNUSUAL EVENT
- Percent release limit LESS THAN 100% -
RELEASE WITHIN LIMITS d) Notify RAD or RAC of event classification based on percent release limit for liquid release NUMBER PROCEDURE TITLE REVISION EPIP-4.08+
INITIAL OFFSITE RELEASE ASSESSMENT 15 PAGE 3 of 12
-LJ-C ACTION/EXPECTED RESPONSE H-]
RESPONSE NOT OBTAINED NOTE:
Surry Radwaste Facility (SRF)
Vent Monitor RRM-101 information is available from the SRF Control Room.
5 DETERMINE PERCENT RELEASE LIMIT FOR GASEOUS RELEASE:
a)
Get highest value of the following:
IF NO gaseous release, THEN GO TO Step 10.
a)
IF all values are NOT available, THEN get value of monitor in alarm.
"* VG-110 (cpm)
"* VG-131 (jtCi/sec and gCi/cc)
"* GW-102 (cpm)
"* GW-130 ( 1iCi/sec and 1iCi/cc)
"* SV-111 (cpm)
"* SV-211 (cpm)
"* RRM-101 (cpm) b) Get vacuum (inches following:
Hg) for the
"* VG-110
"* GW-102 b)
IF all values or value for monitor in alarm NOT available.
THEN ask RAD or RAC to determine (as applicable):
"* If monitor count rate correction needed.
"* Estimated vacuum values for monitor(s).
c) Check -
INCHES Hg > 3 d) Correct monitor count vacuum Monitor cpm (30 - inches Hg)/30 c)
GO TO Step 5.e.
rates for Corrected cpm (STEP 5 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 15 "PAGE 4 of 12 F-l
.a
ACTION/EXPECTED RESPONSE I I[
RESPONSE NOT OBTAINED 5
DETERMINE PERCENT RELEASE LIMIT FOR GASEOUS RELEASE: (Continued) e) Get effluent flow rate (cfm) of the following:
"* Vent Vent flow rate
"* Process Vent flow rate
"* Air ejector flow rate
"* SRF Vent flow rate f)
Record on Attachment 1 AND Determine total percent release limit g) Compare percent release limit with emergency classification criteria:
"* Percent release limit GREATER THAN OR EQUAL TO 1000% -
ALERT
"* Percent release limit GREATER THAN OR EQUAL TO 100%
NOTIFICATION OF UNUSUAL EVENT
"* Percent release limit LESS THAN 100% -
RELEASE WITHIN LIMITS h) Notify RAD or RAC of event classification based on percent release limit for gaseous release e) IF flow rate NOT available, THEN use design flow rate:
"* Vent Vent = 172,000 cfm
"* Process Vent = 310 cfm
"* Air Ejector = 25 cfm
"* SRF Vent = 51,340 cfm NUMBER PROCEDURE TITLE REVISION EPIP-4.08-INITIAL OFFSITE RELEASE ASSESSMENT 15 PAGE 5 of 12 1-P
ACTION/EXPECTED RESPONSE H-]
RESPONSE NOT OBTAINED NOTE:
e No release through Air Ejector(s) should be assumed if Air Ejector is diverted to containment.
e The total dose rate from each pathway should be calculated using,
3 and/or 4 if the release is from more than one pathway.
6 DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr)
FOR VENTILATION RELEASE:
a) Ask SEM (via RAD or RAC) to have someone observe the increasing or decreasing trends of the monitor b)
Check if release pathway is through any of the following:
"* Process Vent
"* Vent Vent b)
IF release is through the Main Steam System, THEN GO TO Step 7 OR IF release is from containment
- leakage, THEN GO TO Step 8.
"* Air Ejector
"* SRF Vent (STEP 6 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.08-INITIAL OFFSITE RELEASE ASSESSMENT 15 PAGE 6 of 12 I
AI!Ei-C ACTION/EXPECTED RESPONSE I -1 RESPONSE NOT OBTAINED 6
DETERMINE SITE BOUNDARY DOSE RAT (mrem/hr)
FOR VENTILATION RELEASE: (Continued) c) Check if monitors for affected pathway OPERABLE:
"* Kaman Science
"* Eberline (SRF)
"* Victoreen c)
IF Kaman Science Monitor inoperable or offscale, THEN do the following:
- 1)
Get parameters:
"* Stability Class
"* Wind Speed (mph)
"* mR/hr from VG-123 or GW-122
"* Flow rate (cfm)
- 2)
GO TO Step 6.e.
OR IF SRF Eberline Monitor inoperable, THEN ask RAD or RAC for guidance OR IF Victoreen Monitor offscale or inoperable, THEN do the following:
- 1) Use Kaman Science Monitor
- 2)
GO TO Step 6.d.
(STEP 6 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 15 PAGE 7 of 12 I-11
RESPONSE NOT OBTAINED 6
DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr)
FOR VENTILATION RELEASE:
(Continued) d) Get the following information from RAD or RAC:
- 1) Monitor number of interest
- 2) Highest cpm (corrected for vacuum if necessary),
ýiCi/sec and ý+/-Ci/cc from monitor of interest
- 3)
Flow rate (cfm) for release pathway
- 4) Stability Class
- 5) Wind Speed e) Record above data (less Stability Class) on Attachment 2 f) Get X/O and conversion factors from Attachment 5:
"* Site Boundary X/O for Stability Class in effect
"* Monitor Conversion Factor (MCF) based on accident type
"* TEDE DCF
"* THY DCF g)
Record X/O and conversion factors on Attachment 2 h) Determine Site Boundary TEDE and THY COE, mrem/hr, using i) Record results of Attachment 2 on Attachment 6 NUMBER PROCEDURE TITLE REVISION EPIP-4.08-INITIAL OFFSITE RELEASE ASSESSMENT 15 "PAGE 8 of 12 I
- 111ýýý::;-T AC-TION/ EXPECTED RESPONSE I
I
-LFJ-C ACTION/EXPECTED RESPONSE F-I RESPONSE NOT OBTAINED NOTE:
e No release is assumed from the AFWPT pathway if the AFWPT is isolated.
- Results of Attachments 2 and 3 are cumulative if the release is through both the Main Steam System and Ventilation System.
7 DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr)
- MAIN STEAM SYSTEM:
a)
Check if actual or potential release pathway through Main Steam Safety Valves or Auxiliary Feedwater Pump Turbine Exhaust (AFWPT) b) Get number and mR/hr of the monitor(s) of interest from SEM (via RAD or RAC):
a) GO TO Step 8.
c) Get the following information from RAD or RAC:
"* Stability Class
"* Wind Speed
"* Number of Main Steam Safety Valves that have lifted or may potentially lift
- Status of AFWPT isolation (STEP 7 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 15 PAGE 9 of 12 HI Unit 1 Unit 2 Main Steam Main Steam MS-124 (A Safety Valves)
MS-224 (A Safety Valves)
MS-125 (B Safety Valves)
MS-225 (B Safety Valves)
MS-126 (C Safety Valves)
MS-226 (C Safety Valves)
Unit 1 AFWPT Unit 2 AFWPT MS-129 MS-229 I
ACTION/EXPECTED RESPONSE 7
DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr)
- MAIN STEAM SYSTEM: (Continued) d) Get X/O and conversion factors from Attachment 5:
"* Site Boundary X/Q for Stability Class in effect
"* Monitor Conversion Factor (MCF) based on accident type
"* TEDE DCF
"* THY DCF e) Record monitor readings (mR/hr),
X/Q, wind speed,
- valves and conversion factors on Attachment 3 f)
Determine Site Boundary TEDE and THY CDE, mrem/hr, using g)
Record results of Attachment 3 on Attachment 6 NUMBER PROCEDURE TITLE REVISION EPIP-4.08-INITIAL OFFSITE RELEASE ASSESSMENT 15 PAGE 10 of 12 RESPONSE NOT OBTAINED 1-l-1
-LZJ-t ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:
Results of Attachments 2, 3 arid 4 are cumulative if the release is through the Ventilation System, Main Steam System and Containment.
8 DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr)
CONTAINMENT LEAKAGE:
a)
Check if actual or potential release pathway from Containment Leakage b) Get CHRRMS reading, R/hr Unit 1 Unit 2 RMS-127 RMS-227 RMS-128 RMS-228 c)
Get the following information from RAD or RAC:
- Stability Class
- Wind Speed d)
Get X/O and conversion factors from Attachment 5:
"* Site Boundary X/O for Stability Class in effect
"* Monitor Conversion Factor (MCF) based on accident type
- TEDE DCF
& THY DCF e) Record highest monitor reading for affected unit(s) (R/hr),
X/Q, wind speed and conversion factors on Attachment 4 f)
Determine Site Boundary TEDE and THY CDE, mrem/hr, using g) Record results of Attachment 4 on Attachment 6 a)
IF NO release pathway from containment, THEN GO TO Step 9.
NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 15 "PAGE 11 of 12 H-I
SACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED l
9 DETERMINE DOSE RATES (mrem/hr)
AT 2,
5 AND 10 MILES:
a) Use Attachment 6 b) Add results of appropriate release pathways:
"* Vent (Attachment 2)
"* Main Steam (Attachment 3)
"* Containment (Attachment 4) c) Determine Stability Class correction factor for distance of interest d)
Do calculation AND Determine TEDE and THY CDE at 2,
5 and 10 miles e) Report results to RAD or RAC 10 TERMINATE EPIP-4.08:
"* Give completed EPIP-4.08, forms and other applicable records to the RAD or RAC
"* Completed by:
Date:
Time:
-END-NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 15 "PAGE 12 of 12
Date:_
Time:
% RELEASE LIMIT VENT VENT:
CPM*
x CFM x
CF VG-110:
x x
4.96 E-8 jiCi/sec x
CF VG-131:
x 3.52 E-3 uiCi/cc x
x x
1.66
- Correction for vacuum may be necessary.
Refer PROCESS VENT:
CPM*
x CFM x
CF GW-102:
x x
3.07 E-9 1iCi/sec x
CF GW-130:
x 2.18 E-5 jiCi/cc x
x x
1.03 E-2
- Correction for vacuum may be necessary.
Refer Highest %
to Step 5.c.
Highest %
to Step 5.c.
UNIT 1 AIR EJECTOR:
CPM x
CFM x
CF SV-111:
x x
7.16 E-8
=
UNIT 2 AIR EJECTOR:
CPM x
CFM x
CF SV-211:
x x
7.16 E-8
=
SURRY RADWASTE FACILITY:
CPM x
CFM x
CF RRM-101:
x x
1.74 E-6
=
Completed by:
Date/Time:
TOTAL % RELEASE LIMIT:
/
NUMBER ATTACHMENT TITLE REVISION EPIP-4.08
% RELEASE LIMITWORKSHEET 15 ATTACHMENT PAGE 1
1 of 1
NOTE:
- Site Boundary X/O and Monitor Conversion Factors (MCF) are provided on.
- VG-123 and GW-122 should only be used when KAMAN or Normal Range Monitors are offscale or inoperable.
Date:
VENT VENT:
Time:
VG-110:
( CPM
- x CFM x
X/O x
MCF
)
x x
x
_)
VG-131: (ýiCi/sec x 1.OE-3 x X/O ) / WINDSPEED
(.
x 1.OE-3 x
) /
VG-131: (jiCi/cc x
CFM x 4.72E-1 x X/Q
)
(
x x 4.72E-1 x
)
VG-123: ( mr/hr x
CFM x
X/O x
MCF
)
x x
x
)
- Correction for vacuum may be necessary.
Refer to Steps 6.d.2 and 5.c.
Record highest Vent Vent value (mrem-Ci/Rem-m 3 )
/ WINDSPEED
/
I I
/
Val ue Value Value Value WINDSPEED WINDSPEED above on Page 3 of Attachment 2.
AIR EJECTOR:
SV-111: (
x x
x x
CFM CFM x
x x
x X/O X/O Record sum of Air Ejector values on X
MCF
) I WINDSPEED x
) /
x MCF
) / WINDSPEED x)/
TOTAL OF AIR EJECTORS Page 3 of Attachment 2.
NUMBER ATTACHMENT TITLE EPIP-4.08 VENT RELEASE SITE BOUNDARY BOSE RATE ATTACHMENT 2
Value Value
NOTE: e Site Boundary X/Q and Monitor Conversion Factors (MCF) are provided on.
- VG-123 and GW-122 should only be used when KAMAN or Normal Range Monitors are offscale or inoperable.
PROCESS VENT:
GW-102:
( CPM
- x CFM x
X/O x
MCF
) I WINDSPEED
___x x
x
) /
GW-130: (jiCi/sec x 1.OE-3 x X/O ) / WINDSPEED
(
x 1.OE-3 x
) /
GW-130: ( 1iCi/cc x
CFM x 4.72E-1 x X/O
) I WINDSPEED
(
x x 4.72E-1x
) /
GW-122:
( mr/hr x
CFM x
X/O x
MCF
) / WINDSPEED
(_
x x -_
x
) /
- Correction for vacuum may be necessary.
Refer to Steps 6.d.2 and 5.c.
Record highest Process Vent value (mrem-Ci/Rem-m 3 ) above on Val ue Value Value Value Page 3 of.
SURRY RADWASTE FACILITY:
RRM-101:
(
CPM x
CFM x
X/O x
MCF
) / WINDSPEED
(
x x
x
) /
Record Surry Radwaste Facility value on Page 3 of Attachment 2.
NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 VENT RELEASE-SITE BOUNDARY DOSE RATE 15 ATTACHMENT PAGE 2
2 of 3
=
Value
- 1.
Record the following monitor values in left-hand column of table below:
Highest Vent Vent value from Attachment 2 Page 1 Sum of Air Ejector values from Attachment 2 Page 1 Highest Process Vent value from Attachment 2 Page 2 Surry Radwaste Facility value from Attachment 2 Page 2
- 2.
Record TEDE and THY CDE Dose Conversion Factors (DCFs) from Attachment 5 in top box of middle and right-hand columns in table below.
- 3.
Multiply monitor values in left-hand column by Record result(s) in intersecting space.
- 4.
Sum values in middle and TEDE and THY CDE mrem/hr right-hand columns to for vent release.
determine Site Boundary TEDE DCF from :
AL I;
HIGHEST VENT VENT VALUE:
SUM OF AIR EJECTOR VALUES:
HIGHEST PROCESS VENT VALUE:
H 11 11 THY CDE DCF from :
SURRY RADWASTE FACILITY:
N/A SUM OF VENT VENT, PROCESS SUM TEDE mrem/hr:
SUM THY CDE mrem/hr:
- VENT, AIR EJECTORS AND SURRY RADWASTE FACILITY Completed by:
Date/Time:
/
NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 VENT RELEASE SITE BOUNDARY DOSE RATE 15 ATTACHMENT PAGE 2
3 of 3 0
0 0
0
NOTE:
Monitor Conversion Factors (MCF) and Site Boundary X/O are provided on.
Date:_
Time:
UNIT 1 MAIN STEAM:
mR/hr x
- Valves x
X/O x
MCF
) / WINDSPEED =
Value MS-124:(_
x x
x
) I
=
MS-125:(
x x
x
) I
=
MS-126:(
x x
x
) /
=
TOTAL OF UNIT 1 MAIN STEAM =
UNIT 1 AFWPT:
(
mR/hr x
X/Q x
MCF
) / WINDSPEED =
Value MS-129:(
x x
) /
=
UNIT 2 MAIN STEAM:
(
mR/hr x
- Valves x X/O x
MCF
) / WINDSPEED =
Value MS-224:(
x x
x
) /
=
MS-225:(
x x
x
) I MS-226:(
x x
x
) /
=
TOTAL OF UNIT 2 MAIN STEAM =
UNIT 2 AFWPT:
(
mR/hr x
MCF x
X/O
) / WINDSPEED =
Value MS-229:(
x x
) /
=
NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 MAIN STEAM RELEASE-SITE BOUNDARY DOSE RATE 15 ATTACHMENT PAGE 3
1 of 2
- 1.
Record the following monitor values in left-hand column of table below (enter N/A if unit NOT affected):
"* Total Main Steam value for affected unit(s)
"* AFWPT value for affected unit(s)
- 2.
Record TEDE and THY CDE Dose Conversion Factors (DCFs) from Attachment 5 in top box of middle and right-hand columns in table below.
Record result(s) in intersecting space.
- 4.
Sum values in middle and right-hand columns to determine Site Boundary TEDE and THY CDE mR/hr for Main Steam release (sum of Main Steam and AFWPT).
TEDE DCF from :
'I THY CDE DCF from :
TOTAL OF UNIT 1 MAIN STEAM VALUES:
UNIT 1 AFWPT VALUE:
TOTAL OF UNIT 2 MAIN STEAM VALUES:
UNIT 2 AFWPT VALUE:
SUM OF AFFECTED UNIT('s)
TEDE mrem/hr:
THY COE mrem/hr:
MAIN STEAM AND AFWPT Completed by:
Date/Time:/
NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 MAIN STEAM RELEASE -- SITE BOUNDARY DOSE RATE 15 ATTACHMENT PAGE 3
2 of 2
NOTE:
- Monitor Conversion Factors (MCF),
Site Boundary X/0, TEDE Dose Conversion Factors (TEDE DCF) and Thyroid CDE Factors (THY DCF) are provided on Attachment 5.
a The CHRRMS Monitor Conversion Factor is calculated for design leak rate of 0.1% per day.
Date:
Time:
CONTAINMENT:
RMS-127 or RMS-128 RMS-227 or RMS-228:
(
R/hr x
X/O x
MCF
) / WINDSPEED =
(___ x x
)/
=
Xx
)
- 1. Record result of calculation above in left-hand column of table below (enter N/A if unit NOT affected):
- 2. Record TEDE and THY CDE Dose Conversion Factors (DCFs) from Attachment 5 in top box of middle and right-hand columns in table below.
- 3.
Multiply monitor value in left-hand column by TEDE DCF and THY CDE DCF.
Record result(s) in intersecting space.
- 4.
Sum values in middle and right-hand columns to determine Site Boundary TEDE and THY CDE mrem/hr for Containment release.
TEDE DCF from :
THY CDE DCF from :
UNIT 1 CONTAINMENT VALUE:
UNIT 2 CONTAINMENT VALUE:
SUM OF AFFECTED UNIT('s)
TEDE mrem/hr:
HY COE mrem/hr:
CONTAINMENT(s)
Completed by:
Date/Time:
/
NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 CONTAINMENT RELEASE -S.ITE BOUNDARY DOSE RATE 15 ATTACHMENT PAGE 4
1 of 1 Value
XI/,
SITE BOUNDARY:
ISTABILITY CLASS A
B C
D -
I E
F G
4.82 E-5 1.61 E-4 3.28 E-4 7.54 E-4 1.2 E-3 1.87 E-3 2.44 E-3 MONITOR CONVERSION FACTORS (MCF):
MONITOR MSLB SGTR FHA WGDT VCT
[LOCA MELTILOCA GAPI LOCA PC LKD.
ROTORI NORMAL SRF I
I I
I I
I I
I I
F I
VG-11o 1.3E-8 1.3E-8 1.4E-8 7.6E-9 7.OE-9 1.3E-8 I 1.4E-8 I
F I
I F
I I
F I
VG-123 22.8 15.3 56.6 1.47 1.40 16.2 3
36.6 FI F
+
I I
F I
I I
IF GW-102 I -
- 1.07E-7 1.31E-7 I
I---- I----- I I 1.38E7I----
I FII I
I I
I I
I I
I GW-122
---- --- 8.1 17.4 37.5 I I IF+
I I
F F
FI I
I MS-1(2)24 I
I I
I MS-1(2)25 5.6E+3 4.5E+3 I
3.87E+2 3.1E+3 MS-1C2)26 I
I I
I FII 1
I 4
I I
F I
I I
I MS-1(2)29 1.2E+4 I 1.25E+41 I
I I
I I
I 1.9E+3 I 7.E+ I ---- I
-I I
I-I I
I i
I I
I sv-I I
I I----
I I
I I
I I
I SV-211 2.3E-9 1.8E-9 I
I 2.3E-1O I2.3E-1OI 1.7E-9 I 2.4E-10 I 1.7E-9 I
I I
I I
I I
I F
I I
I RMS-1(2)27 I
I I
I I
I I
I I
I I
RMS-1(2)28 I
I I
I I 7.3E-2 6.9E-2 1.6E-1 I
I I
I II I
I F
1 I
I I
I I
I RRM-101 I----
I------------ -
I----
I I
-1.9E8 2.6E-7I I
________I ______IJ____IJ
____I I_____II ____I J_______j______I TEDE DOSE CONVERSION FACTORS (TEDE DCF):
MSLB SGTR FHA WGDT VCT 1LOCA MELTiLOCA GAPILOCA PCi LKO.
ROTORi SRF I I I IL IT CLASSI I
I I
I I
I I
I I
7.2E+3 I 2.1E+2 THYROID CDE DOSE CONVERSION I
MSL i
i WGDT i VCT iLOCA MELTILOCA GAPILOCA PC I LKD.
ROTORI SiI I
I II NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 SITE -BOUNDARY X/Q VALUES, 15 ATTACHMENT MONITOR CONVERSI:ON
1Of UNFILTERED 2.E+4 I
0.7EI 0
7.9E+3 I 1.6E+4 6.6E+1 3.7E+4 0
FILTEREO 2.5E+2 6.9E+I 6.8E-2 0
0 7.9EI-+2 1.6E+3 6.6E-O 0
SRF
--I I
STABILITY CLASS CORRECTION FACTOR MILES A
B C
D E
F G
2 1.37E-2 1.12E-2 4.27E-2 6.37E-2 8.33E-2 1.28E-1 2.38E-1 5
6.02E-3 2.36E-3 8.84E-3 1.59E-2 2.42E-2 3.74E-2 7.79E-2 10 3.11E-3 1.24E-3 2.80E-3 5.84E-3 1.OOE-2 1.55E-2 3.24E-2 CALCULATION:
SUM OF TEDE:
ATT.
2:
ATT.
3:
l_CORRECTION FACTOR TEDE mrem/hr ATT.
4:
2 miles:
2 miles:
SUM:
TEDE DOSE RATE, CORRECTION FACTOR TEDE mrem/hr SITE BOUNDARY x
5 miles:
5 miles:
mrem/hr CORRECTION FACTOR TEDE mrem/hr 10 miles:
10 miles:
SUM OF THY CDE:
ATT.
2:
ATT.
3:
ATT.
4:
SUM:
THY.
CDE DOSE RATE SITE BOUNDARY mrem/hr CORRECTION FACTOR THY CDE mrem/hr 2 miles:
2 miles:
CORRECTION FACTOR THY CDE mrem/hr 5 miles:
5 miles:
CORRECTION FACTOR THY CDE mrem/hr 10 miles:
10 miles:
NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 DETERMINATION OF-2, 5 AND_10 MILE DOSE RATES 15 ATTACHMENT PAGE 6
1 of 1 I
L
LEVEL 2 DISTRIBUTION VIRGINIA POWER This Document Should Be Verified SURRY NIA POWER SAnd Annotated to A Controlled Source S U R R Y P O W E R S T A T I O NA s R q i e t o P r r m W k EMERGENCY PLAN IMPLEMENTING PROCEDURE AsRequiredtoperorm Work NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 13 PAGE (With 6 Attachments) 1 of 13 PURPOSE To provide guidance for assessing radioactive releases.
ENTRY CONDITIONS Any of the following:
- 1. EPIP-4.01, RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE.
- 2.
EPIP-4.03.
DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE.
- 3.
CPIP-6.2, RADIOLOGICAL ASSESSMENT COORDINATOR.
Approvals on File Effective Date c(<A
\\vz) z>7"
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 INITIATE PROCEDURE:
- By:
Date:
Time:
NOTE:
e Unless otherwise indicated, the Radiological Assessment Director/
Radiological Assessment Coordinator should be consulted when requesting action or information.
"* Source term units are expressed in Ci/sec.
"* Source term calculations based on monitor readings should be used for initial assessment and to establish trends. Sampling should be performed to more accurately determine source term.
2 CHECK IF ACTUAL OR POTENTIAL FOR RELEASE FROM CONTAINMENT EXISTS IF event does NOT involve potential or actual containment release, THEN determine source term from any of the following:
"* Effluent sample: GO TO Step 4 OR
"* Sample of Station Inventory:
GO TO Step 7 OR
"* Station monitors: GO TO Step 8.
NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 13 PAGE 2 of 13 HI
-L!EJ-ACTION/EXPECTED RESPONSE I-]
RESPONSE NOT OBTAINED 3
DETERMINE CONTAINMENT SOURCE TERM FROM ANY OF THE FOLLOWING:
"* Containment Air Sample: GO TO Step 9 OR
"* Containment High Range Monitor:
GO TO Step 10 NOTE:
Results of each pathway analysis should be recorded on separate worksheets if more than one pathway is sampled.
4 DETERMINE SOURCE TERM FROM EFFLUENT SAMPLE:
a)
Request initiation of EPIP-4.24, GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY, for sampling of appropriate effluent pathway:
"* Ventilation Vent
"* Process Vent
"* Air Ejector(s) b)
Get monitor reading:
Maximum:
"* Reading at time of sample:
c)
Have Count Room analyze sample:
- Request initiation of EPIP-4.26, HIGH ACTIVITY SAMPLE ANALYSIS, for high activity samples (STEP 4 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 13 PAGE 3 of 13 l
ACTION/EXPECTED RESPONSE
-4 4
DETERMINE SOURCE TERM FROM EFFLUENT SAMPLE: (Continued) d) Record nuclide activity on, left column AND Add results to determine Noble Gas and Iodine concentration e) Continue if this is an initial source term assessment f)
Check if sample taken at maximum monitor reading RESPONSE NOT OBTAINED d) IF iodine sample NOT taken, THEN continue assessment AND RETURN TO Step 4.d when results are available.
e)
GO TO Step 4.g.
f)
IF sample NOT taken at time of maximum reading, THEN determine corrected [iCi/cc for both Noble Gas and Iodine:
MAX READING x
READING AT TIME OF SAMPLE jCi/cc = CORRECTED
.iCi /cc g) Get effluent flow rate (cfm) h)
Record flow rate on Attachment 2 i)
Record Noble Gas and Iodine concentration on Attachment 2:
- Use corrected jiCi/cc from Step 4.f (if required)
- IF correction was NOT required, THEN use activity from Attachment 1.
j) Use Attachment 2 to determine Noble Gas and Iodine release rate, Ci/sec for each pathway k) Add Ci/sec for applicable pathways at end of Attachment 2 NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 13 PAGE 4 of 13 1-I
-LFH ACTION/EXPECTED RESPONSE h-I I
I RESPONSE NOT OBTAINED I
5 DETERMINE DDE, TEDE AND THYROID CDE DOSE CONVERSION FACTORS BASED ON SAMPLE RESULTS:
a)
Use Attachment 1 that was previously filled out for gross activity determination a)
Do Steps 4.a through 4.d AND GO TO Step 5.b.
b)
Do calculations on Attachment 1 to determine the following for each nuclide:
"* Sample DDE DCF
"* Sample TEDE DCF
"* Sample THY CDE DCF c)
Add results of Sample DDE, Sample TEDE and Sample THY CDE columns to determine total DDE
Determine TEDE/DDE ratio:
TEDE DCF
=
DDE DCF Ratio TEDE/DDE e) Give source term results, Ci/sec, and TEDE/DDE ratio to RAD or RAC NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 13 PAGE 5 of 13 I
ACTION/EXPECTED RESPONSE 6 DETERMINE SITE BOUNDARY DOSE RATES BASED ON EFFLUENT SAMPLE RESULTS:
a) Ask RAD or RAC if Site Boundary dose rate calculation based on effluent sample - DESIRED b) Record Sample TEDE DCF and Sample THY CDE DCF from on to Attachment 3 c) Get effluent flow rate (cfm) for each affected pathway d)
Record CFM on Attachment 3 e) Determine Stability Class and wind speed:
- Ask RAD or RAC f)
Use Attachment 3 Site Boundary X/O 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 Site Boundary TEDE and THY CDE dose rate, mrem/hr i) Give results to RAD or RAC j)
GO TO Step 13 NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 13 "PAGE 6 of 13 RESPONSE NOT OBTAINED a)
GO TO Step 13.
1 1
-LFJ-t ACTION/EXPECTED RESPONSE
-4 RESPONSE NOT OBTAINED NOTE:
An error in calculation of gas in a tank. Water volume should the tank if the tank has water volume may result due to water level be subtracted from design volume of in it.
7 DETERMINE SOURCE TERM FROM STATION INVENTORY:
a)
Check if release originated from a gas storage tank (e.g.,
Waste Gas Decay Tank, Volume Control Tank, etc.)
a)
RETURN TO Step 2.
b) Have sample taken from appropriate tank c) Have Count Room analyze sample:
Request initiation of EPIP-4.26, HIGH ACTIVITY SAMPLE ANALYSIS, for high activity samples d) Record sample activity on, left column e) Use Attachment 1 to calculate gross Noble Gas and Iodine activity f) Determine release volume (in ft 3 ):
VOLUME (ft 3 ) = P1 x V1 x T2 T1 x P2
"* Pi = Pressure before release, PSIA
"* P2 = Pressure after release, PSIA
"* V1 = Design volume of tank, ft 3
"* Ti = Temperature before release, OK
= [(OF - 32)/1.8] + 273
"* T2 = Temperature after release, OK
= [(OF - 32)/1.8] + 273 (STEP 7 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 13 PAGE 7 of 13 F-
SACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 7
DETERMINE SOURCE TERM FROM STATIQN INVENTORY:
(Continued) g) Determine release volume in milliliters (mls):
x 2.832 E+4 =
mls VOLUME (ft 3 ) x 2.832 E+4 = VOLUME (mls) h)
Record results on Attachment 2, Station Inventory section:
"* Noble Gas activity
"* Iodine activity
"* Volume of release in mls
"* Duration of release in seconds i)
Use Attachment 2 to determine Noble Gas and Iodine release rate, Ci/sec j) Add Ci/sec from all pathways of concern at bottom of k) Give results to RAD or RAC
- 1) GO TO Step 13 NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSE-SSMENT 13 PAGE 8 of 13
SACTIONEXPECTEO RESPONSE i
RESPONSE
NOT OBTAINED NOTE:
e Effluent flow rates may not be needed for Kaman, Main Steam, AFWPT or Containment monitor calculations.
- Kaman monitors are the primary method of assessment.
Should Kaman monitors be inoperable, then assessments should continue using Vent Vent or Process Vent Normal and/or High Range monitors.
8 DETERMINE SOURCE TERM FROM STATION MONITORS:
a) Get monitor readings and effluent flow rates (cfm) for release pathway(s) of concern:
"* VG-110, VG-131 and VG-123
"* GW-102, GW-130 and GW-122
"* SV-111
"* SV-211
"* Main Steam Readings
"* AFWPT readings
"* Unit 1 Containment:
Higher of RMS-127 or -128
"* Unit 2 Containment:
Higher of RMS-227 or -228 b)
Record monitor readings and flow rates (where applicable) on Attachment 4 c) Determine accident type d) Determine status of effluent charcoal filtration e) Determine Monitor Conversion Factors (MCF) and Iodine Conversion Factors (Iodine CF) from Attachment 5 f)
Record Conversion Factors on g)
Do calculations on Attachment 4 to determine Iodine and Noble Gas release rates, Ci/sec h) Add Ci/sec from all pathways of concern i)
Give results to RAD or RAC j)
GO TO Step 13 NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSE-SSMENT 13 PAGE 9 of 13
-LJ-t ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:
Source term is expressed as Curies in Step 9 below.
9 DETERMINE SOURCE TERM FROM CONTAINMENT SAMPLE:
a)
Ask RAD/RAC if a Containment Air sample is required b)
Record sample results on, left column c)
Determine gross activity for Noble Gas and Iodine (sum results) d)
Record results on Attachment 2, Containment Sample section e) Check release -
IN PROGRESS a)
IF containment air sample NOT
- required, THEN GO TO Step 10.
b) IF sample results NOT immediately available, THEN GO TO Step 10 AND RETURN TO Step 9.b when results are available.
e)
GO TO Step 9.i (STEP 9 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 13 PAGE 10 of 13
=
m
-LH ACTION/EXPECTED RESPONSE h-I RESPONSE NOT OBTAINED 9
DETERMINE SOURCE TERM FROM CONTAINMENT SAMPLE: (Continued) f)
Record effluent flow rate (cfm) on Attachment 2 f)
IF effluent flow rate NOT
- known, THEN do the following:
- 1)
Ask Technical Support Team or Engineering Department for flow rate assessment
- 2) Get containment pressure (P1, psia) and temperature (Ti, 0 K)
- 3) Calculate volume (mls):
1.05E+12 x P1 T1, where Ti = (°F
- 32/1.8) + 273
- 4) Determine total Curies available for release:
NG (gCi /ml )
Iodine (1iCi/ml )
x Volume x 10-6 =
(mls) x __
x 10-6 =
x Volume (mls) x _
NG Curies x 10-6 = Iodine Curies x 10-6 =
- 5) GO TO Step 11.
g)
Use Attachment 2 to determine source term (Ci/sec) h) GO TO Step 11 (STEP 9 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 13 PAGE 11 of 13 1-
= VOLUME (mls)
I-
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAIN11ED,
9 DETERMINE SOURCE TERM FROM CONTAINMENT SAMPLE: (Continued) i)
Determine potential source term (Ci/sec):
- 1) Record 1.3 cfm for containment flow rate on
- 2)
Use Attachment 2 to calculate Ci/sec
- 3)
GO TO Step 11 10 DETERMINE SOURCE TERM FROM CONTAINMENT MONITOR:
a)
Record dose rate (R/hr) from Containment High Range Monitor of affected unit:
Unit 1 Higher of RM-127 or RM-128:
Unit 2 Higher of RM-227 or RM-228:
b)
Record number of hours since LOCA:
c)
Use Attachment 6 to determine Curies (Ci)
Noble Gas and lodines in containment air available for release d)
Determine release rate (Ci/sec):
Ci Noble Gas x 3.5E-8 =
Ci/sec Noble Gas Ci Iodine x 3.5E-8 =
Ci/sec Iodine e) Give results to RAD or RAC 11 CHECK IF MORE THAN ONE RELEASE GO TO Step 13.
PATHWAY INVOLVED NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 13 PAGE 12 of 13
-F-
ýTE ACTION/EXPECTED RESPONSE I.
RESPONSE NOT OBTAINED 12 RETURN TO STEP 2 13 TERMINATE EPIP-4.09 AND RETURN TO PROCEDURE IN EFFECT:
"* Give completed EPIP-4.09, forms and other applicable records to the Radiological Assessment Director/Radiological Assessment Coordinator
"* By:
Date:
Time:
-END-NUMBER PROCEDURE TITLE REVISION EPIP-4.09
-SOURCE TERM ASSESSMENT 13 "PAGE 13 of 13 F-I
Sample Identification:
- Sample Time
NOTE:
e Total Noble Gas and Iodine activity, pCi/ml. are for use on Attachment 2.
Kr-83M Kr-85 Kr-85M Kr-87 Kr-88 Kr-89 Xe-131M Xe-133 Xe-133M Xe-135 Xe-135M Xe-137 Xe-138 NA x 1.3 x 93 x 510 x 1300 x 1200 x
x x
x x
x 4.9 20 17 140 250 110 x 710 CONTINUE ADDING DOWN x
x x
x x
x x
1-125 1-129 1-131 1-132 1-133 1-134 1-135 Completed by:
Date/Time:
6.3 4.8 220 1400 350 1600 950 I
NUMBER ATTACHMENT TITLE REVISION EPIP-4.09-NOBLE GAS,-IODINE AND DOSE CONVERSION FACTOR WORKSHEET 13 ATTACHMENT USING SAMPLE ANALYSIS-RESULTS PAGE 1
1 of i x
x x
x x
x x
x x
x x
x 1
1 1
1 1
1 1 1
1 1
1 1
CONTINUE ADDING DOWN x
x x
x x
x x
4762 43750 241 3.5 43 1.9 8.5 x
x x
x x
x x
32 33 24.5 1.6 14.6 0.43 4.7 I
MONITOR MCi/ml VENT:
N.G.
x x
PV:
IOD.
N.G.
x x
x x
IOD.
x x
AIR EJECTOR #1:
N.G.
IOD.
AIR EJECTOR #2:
N.G.
CFM x
x CFM x
x x
IOD.
x x
CFM CFM x
x x
x x
x x
x x
x 4.72E-'
4.72E-4 4.72E-4 4.72E-4 4.72E-4 4.72E-4 4.72E-4 4.72E-4 4.72E-4 4.72E-4 "x 4.72E-4 "x 4.72E-4 x
x x
x 4.72E-4 4.72E-4 4.72E-4 4.72E-4 STATION INVENTORY:
N.G.
x x
VOLUME (mls) x x
IOD.
x VOLUME (mls) x x
x 1.OE-6
/
i.OE-6
/
1.OE-6
/
1.OE-6
/
CONTAINMENT SAMPLE:
N.G.
x CFM x
IOD.
x CFM x
x 4.72E-4 x
4.72E-4 x
4.72E-4 x
4.72E-4 SUM Ci/sec:
Completed by:
Date/Time:
NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 SAMPLE EFFLUENT Ci/sec WORKSHEET 13 ATTACHMENT PAGE 2
1 of 1 Ci /sec NOBLE GAS IODINE SECONDS SECONDS I
NG IOD
NOTE: TEDE and Thyroid CDE factors from Attachment 1 are to be applied to this worksheet.
X/Q, SITE BOUNDARY:
STABILITY-CLASS A
B C
D E
F G
4.82E-5 1.61E-4 3.28E-4 7.54E-4 1.20E-3 1.87E-3 2.44E-3 Windspeed Windspeed Windspeed Windspeed Windspeed Windspeed Windspeed TEDE DCF OR MONITOR THY COE DCF CFM VENT:
TEDE x
CFM x
4.72E-1 x
x x
4.72E-1 x
THY COE x
CFM x
4.72E-1 x
x x
4.72E-1 x
PV:
TEDE x
CFM x
4.72E-1 x
x x
4.72E-1 x
THY COE x
CFM x
4.72E-1 x
x x
4.72E-1 x
AIR EJECTOR #1:
TEDE x
CFM x
4.72E-1 x
x x
4.72E-1 x
THY COE x
CFM x
4.72E-1 x
x x
4.72E-1 x
AIR EJECTOR #2:
TEDE x
CFM x
4.72E-1 x
x x
4.72E-1 x
THY COE x
CFM x
4.72E-1 x
x x 4.72E-1 x
X/O WINDSPEED Site Boundary TEDE mrem/hr Site Boundary THY.
COE mrem/hr X/O/WINDSPEED X/O/WINDSPEED X/O/WINDSPEED X/O/WINDSPEED X/O/WINDSPEED X/O/WINDSPEED X/O/WINDSPEED X/O/WINDSPEED STATION INVENTORY:
TEDE x
VOLUME (mls) x 1.OE-3 / SECONDS x
X/O/WINDSP.
x x
1.0E-3 /
x
=
THY CDE x
VOLUME (mls) x 1.OE-3 / SECONDS x
X/D/WINDSP.
x x
1.E-31 __
x
=
CONTAINMENT SAMPLE:
TEDE x
CFM x
4.72E-1 x
X/O/WINDSPEED x
x 4.72E-1 x
THY CDE x
CFM x
4.72E-1 x
X/O/WINOSPEED x
x 4.72E-1 x
Completed by:
SUM mrem/hr:
NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 SAMPLE-EFFLUENT SITE BOUNDA-RY DOSE RATE WORKSHEET 13 ATTACHMENT PAGE 3
1 of 1
NOTE: Monitor Conversion Factors (MCF) and Iodine Conversion Factors (Iodine CF) are provided on Attachment 5).
Date:
- Time
- _
IODINE NOBLE GAS VENT VENT:
Ci/sec Ci/sec CPM x
MCF x
=
Ci/sec Highest Ci/sec VG-110:
x x
1
--I I-Ci/sec NGI 1iCi/sec x
1.DOE-6 Ci/sec j
I I
I I
VG-131:
x 1.OOE-6 x I MINUS I
I I
I IL LI I
fici/cc x 4.72E-4 x
CFM Ci/sec IODINE CF I Ci/sec Iod.j VG-131:
x 4.72E-4 x
I (Att. 5): I I
II I
mR/hr x
MCF x
CFM Cil/sec I
I VG-123:
x x
PROCESS VENT:
CPM GW-102:
pCi/sec GW-130:
pCi /cc GW-130:
mR/hr GW-122:
x x
x x
x x
x x
MCF x
=
Ci/sec
-x 1.OOE-6 Ci/sec 1.OOE-6 4.72E-4 x
=
Ci/sec 4.72E-4 x
=
MCF x
CFM Ci/sec x
Highest Ci/sec F*
1
[
Ji/sec NGI I
I I
x I MINUS II I"I I
IJ IODINE CF Ci/sec lod.i (Att.
5):
II I
I IJ I
J AIR EJECTOR:
CPM x
MCF x
-J Ci/sec SV-111:
x x
=_
CPM x
MCF x
-J Ci/sec SV-211:
x
=_
II 1SUM Ci/sec I Ci/sec NG IIII llI MINUS I
i I
l Ir I
i I IODINE CFI IC/isec Iod.I L.X (Att. 5):
=
I I
I I
I I
L
~J NUMBER.
ATTACHMENT TITLE REVISION EPIP-4.09 MONITOR Ci/sec WORKSHE-T 13 ATTACHMENT PAGE 4
1 of 2
IODINE Ci/sec MAIN STEAM:
mR/hr MS-124:
MS-125:
MS-126:
MS-224:
MS-225:
MS-226:
AFWPT:
MS-129:
mR/hr MS-229:
x x
x x
x x
x
- valves x x x
x x
X MCF Ci/sec 1
-I Ci /sec x
MCF x
x NOBLE GAS Ci/sec SUM OF Ci/sec
- -]Ci/sec NGI I
I I
X I MINUS I
I IODINE CF Ci/sec Iod.I (Att. 5) :
I I
I I
I I
I I
I SUM OF Ci/sec I
I X I MINUS j
II r I I
I IODINE CF Ci/sec Iod.j (Att.
5):
I II I
NT:
NOTE:
Monitor Conversion Factor includes 0.1% design basis leak rate.
I R/hr x
MCF Ci/sec SUM OF Ci/sec Ii i
-I xxj X
(
CAtt.
5):
I I
I LI~
TOTAL Curies/sec:
Sum above results of applicable pathways for Iodine and for Noble gas.
Completed by:
Date/Time:
I I
-*Cil/sec NGI MINUS I
I I Cil/sec Iod.i I
I I
I TOTAL I
i TOTAL jCi/sec Io10 Ici/sec NGI I
I I I
I I I I
I I
II NUMBER ATTACHMENT TITLE REVISION
.EPIP-4.09 MONITOR Ci/sec WORKSHEET 13 ATTACHMENT PAGE 4
2 of 2 CONTAINME RMS-127 or RMS-128 RMS-227 or RMS-228 I
MONITOR CONVERSION FACTORS (MCF):
MNTR MSLB ISGTR jFHA i
GT1 VT ILOCA MELTiLOCA GAP LOCA PC iLKD O. OiNRA R
II I
F I
I I
I
+
I VG-11o 1.3E-11 1.3E-111 1.4E-111 I
7.6E-12 1 7.OE-12 1.3E-11 I 1.4E-111 ----- I I
I I
I I
I I
I I
+
I I
VG-123 12.28E-2 I1.53E-21 5.66E-21 II 1.47E-3 1.40E-3 1.62E-2 1 I 3.66E-21 ------
I I
+
I I
I I
I I
I I
F GW-102 I -- --
I.
I I-.07E-101 1.31E-10o I
I 1.38E-101 ------ I I
I I
I I
+
I I
+
I I
GW-122 I......
I S.81E-21 1.74E-2
-- - I ----
3.75E - I
+
I I
F
+
I I
I 1
I "MS-1(2)24 I
I I
I I
I I
MS-1(2)25 5.6E+O 4.5E+O I
I......
3.87E-1 3.IE+o l MS-1 2)2 I
I I
I I
I I
I I
MS-1(2)29 1.2E+
I 1.25E+11 ------ I II I
I.
1.9E+O I
FI I
I I
I I
I
+
+
F I
I sv-1 1 I
I I
I I
I I
I I
I I
Sv-211 2.3E-12 I 1.E-121 I ------ I -----
2.3E-13 2.3E-13 1.7E-12 2.4E-13 1.7E-121 F
I F
+
I I
F I
+
I I
I I RMS-1(2)27 I
I I
I I
I I
I I
I RMS-1(2)28 I
I----
I I
I 6.9E-5 1.6E-4 I
I 1
I I
F I
I F
I I
I IRRM'101 I
I I
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IODINE CONVERSION FACTORS (IODINE CF):
I MSLB I
,CT iLOCA MELTILOCA GAPI LOCA PC i LKo. ROTORI NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 MONITOR CONVERSION FACTORS 13 ATTACHMENT AND IODINE CONVERSIONW-ACTORS PAGE I
I of 1 N T R I
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I 1
I 3
i i
i UNFILTEREDI1.7E-1.OE-1 2.4E-3 1 0
0 I
3.8E-1 5.4E-1 I3.2E-2 2.5-1 0
F I
I I
I I
I I
I I
IFILTERED j 2.1E-3 I.'E-31 2'4E41 0
I 0
I
'E-2 I.4E-2 3I 1 3'
-1 I 0 III I
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I I
I I
I I
SRF I
I
No letdown or sprays are assumed available.
Containment Air concentration (pCi/cc) = Ci Cont. Air x 1.96E-5.
RCS concentration (pCi/cc) = Ci Cont. Air x 3.83E-3.
Data is given for 0, 1, 2 and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after LOCA occurs.
1.3E+6 100% NG, 50% HAL Released to Cont. Air 7.2E+8 Ci HOURS CHRRMS EVENT DESCRIPTION Ci N.G.
Ci IODINE RCS AFTER R/hr Cont. Air (HALOGEN)
D.E.
1-131 LOCA Cont. Air ACi/ml 1.77E+m LCi /ml 1.3E+5 10% NG, 5% HAL 7.2E+7"Ci 3.87E+7 Ci 1.77E+4 Released to Cont. Air jiCi/ml 1.3E+4 1% NG,
.5% HAL 7.2E+6 Ci 3.87E+6 Ci 1.77E+3 Released to Cont. Air pCi/ml 4.5E+4 100% GAP 2.16E+7 Ci 1.55E+7 Ci 7.11E+3 Released to Cont. Air pCi/ml 4.5E+3 10% GAP 2.16E+6 Ci 1.55E+6 Ci 7.11E+2 Released to Cont. Air PCi/ml 4.5E+2 1% GAP 2.16E+5 Ci 1.55E+5 Ci 7.11E+1 Released to Cont. Air pCi/ml 1.54 1% Failed Fuel 1.49E+4 Ci 5.05E+2 Ci 6.20E-1 Primary Gas Release pCi/ml EVENT DESCRIPTION Ci N.G.
Ci IODINE Cont. Air (HALOGEN)
Cont.
Air 100% NG, 50% HAL 3.13E+8 Ci 2.38E+8 Ci Released to Cont.
Air 10% NG, 5% HAL 3.13E+7 Ci 2.38E+7 Ci Released to Cont.
Air 1% NG..5%
HAL 3.13E+6 Ci 2.38E+6 Ci Released to Cont. Air Ci 9.54E+6 Ci 9.33E+6 100% GAP Released to Cont.
1.80E+3 10% GAP 9.33E+5 Ci 9.54E+5 Ci Released to Cont.
Air 1.80E+2 1% GAP 9.33E+4 Ci 9.54E+4 Ci Released to Cont. Air 1.3 1% Failed Fuel 1.47E+4 Ci 4.60E+2 Ci Primary Gas Release 1.80E+4 Ai r NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 MATRIX:
13 ATTACHMENT CHRRMS EVENT AVAILABLE-CURIES PAGE 1 of 2 NOTE:
0 C1
- 3. 87E+8
No Letdown or Sprays are assumed available.
Containment Air concentration (pCi/cc) = Ci Cont. Air x 1.96-5.
RCS concentration (pCi/cc) = Ci Cont. Air x 3.83-3.
Data is given for 0, 1, 2 and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after LOCA occurs.
HOURS CHRRMS EVENT DESCRIPTION Ci N.G.
Ci IODINE AFTER R/hr Cont. Air (HALOGEN)
LOCA Cont.
Air 2
3.7E+5 100% NG, 50% HAL 2.75E+8 Ci 1.97E+8 Ci Released to Cont. Air 3.7E+4 10% NG, 5% HAL 2.75E+7 Ci 1.97E+7 Ci Released to Cont. Air 3.7E+3 1% NG,
.5% HAL 2.75E+6 Ci 1.97E+6 Ci Released to Cont.
Air 1.4E+4 100% GAP 8.24E+6 Ci 7.92E+6 Ci Released to Cont.
Air 1.4E+3 10% GAP 8.24E+5 Ci 7.92E+5 Ci Released to Cont. Air 1.4E+2 1% GAP 8.24E+4 Ci 7.92E+4 Ci Released to Cont. Air 1.2 1% Failed Fuel 1.45E+4 Ci 4.28E+2 Ci Primary Gas Release HOURS CHRRMS EVENT DESCRIPTION Ci N.G Ci IODINE AFTER R/hr Cont. Air (HALOGEN)
LOCA I Cont. Air Ci
- 1. 56E+8 Ci 2.36E+8 100% NG, 50% HAL Released to Cont.
Air 2.80E+4 10% NG, 5% HAL 2.36E+7 Ci 1.56E+7 Ci Released to Cont.
Air 2.80E+3 1% NG,
.5% HAL 2.36E+6 Ci 1.56E+6 Ci Released to Cont.
Air 8.6E+3 100% GAP 7.17E+6 Ci 6.26E+6 Ci Released to Cont. Air 8.6E+2 10% GAP 7.17E+5 Ci 6.26E+5 Ci Released to Cont.
Air 8.6E+1 1% GAP 7.17E+4 Ci 6.26E+4 Ci Released to Cont.
Air 1.0 1% Failed Fuel 1.43E+4 Ci 3.83E+2 Ci Primary Gas Release 2.80E+5 NUMBER ATTACHMENT TITLE REVISION EPIP-4.09 MATRIX:
13 ATTACHMENT CHRRMS EVENT AVAILABLE CURIES PAGE I
1 2 f 2 NOTE:
- 1 4
LEVEL 2 DISTRIBUTION VIRGINIA POWER This Document Should Be Verified SURRY POWER STATION And Annotated to A Controlled Source EMERGENCY PLAN IMPLEMENTING PROCEDUA&, Required to Perform Work NUMBER PROCEDURE TITLE REVISION EPIP-4.22 POST ACCIDENT SAMPLING OF CONTAINMENT AIR 5
PAGE (With No Attachments) 1 of 8 PURPOSE Provide for monitoring during the collection of post accident containment air samples.
ENTRY CONDITIONS Any one of the following:
- 1. Entry directed by the Radiological Assessment Director.
- 2. Entry directed by the Radiation Protection Supervisor.
Approvals on File Effective Date Sz
ACTION/EXPECTED
RESPONSE
F-A RESPONSE NOT OBTAINED 1
INITIATE PROCEDURE:
- By:
Date:
Time:
NOTE:
The minimum sampling team complement should consist of one Chemistry Team member and one Monitoring Team member at the Containment Air Sampling Panel (CASP) on the Auxiliary Building 27'
- level, and one Chemistry Team member at the Process Control Panel (PCP)/Containment Air Sampling Control Panel (CASCP) in Unit 1 Cable Spreading Room.
2 REVIEW SYSTEM DESIGN BASIS:
"* CASP design basis dose rates equal 30 mrem/hr at three feet
"* Containment Air Sample design basis dose rates equal 8000 mrem/hr surface and 100 mrem/hr at one foot
"* CASP is maintained at a negative pressure
"* Dose rates and airborne contamination levels at the PCP/CASCP are not normally affected by the sampling process NUMBER PROCEDURE TITLE REVISION EPIP-4.22 POST ACCIDENT SAMPLING OF CONTAINMENT AIR 5
PAGE 2 of 8 H-
ACTION/EXPECTED
RESPONSE
H-H RESPONSE NOT OBTAINED NOTE:
Protective measures should be considered for the individual operating the PCP/CASCP in the Unit 1 Cable Spreading Room.
3 EVALUATE PROTECTIVE MEASURES:
a)
Dosimetry:
"* Head
"* Trunk
"* Gonad
"* Leg
"* Arm
"* Wri st b) Protective clothing:
"* Full protective clothing
"* Single gloves
"* Tape all seams c)
Respiratory protection IAW general area conditions in the Auxiliary Building d)
Consider temporary shielding e)
Check anticipated exposure EXCEEDS LIMITS f)
Initiate EPIP-4.04.
EMERGENCY PERSONNEL RADIATION EXPOSURE 4
ASSIGN SAMPLE TEAM MEMBERS e)
IF emergency exposure limits NOT exceeded, THEN GO TO Step 4.
NUMBER PROCEDURE TITLE REVISION EPIP-4.22 POST ACCIDENT SAMPLING OF CONTýAINMENT AIR 5
PAGE 3 of 8 I
I
STE ACTION/EXPECTED
RESPONSE
RESPONSE NOT OBTAINED 5 IDENTIFY INGRESS/EGRESS ROUTES:
a)
Ask RPS about current plant conditions b)
Check radiation monitoring system for general area dose rates and vent exhaust capacity c)
Check recent airborne and general area surveys d)
Establish route 6 GIVE BRIEFING TO SAMPLE TEAM:
a)
Review this procedure b)
Review ingress/egress routes c)
Review sample volume requirements as determined by expected plant conditions d)
Review requirements for PCP/CASCP and the CASP:
"* Stay times
"* Protective clothing
"* Dosimetry
"* Respiratory equipment
"* Monitoring e)
Review cautions:
"* High radiation levels
"* High activity samples
"* Opening valves slowly f)
Give team a copy of this procedure NUMBER PROCEDURE TITLE REVISION EPIP-4.22 POST ACCIDENT SAMPLING OF CONTAINMENT AIR 5
PAGE 4 of 8
ACTION/EXPECTED
RESPONSE
RESPONSE NOT OBTAINED 7
NOTIFY RPS THAT SAMPLING TEAM IS 7NOTIFY RPS THAT SAMPLING TEAM IS READY FOR DISPATCH 8
ASK RPS FOR CURRENT PLANT STATUS 9
GIVE PLANT STATUS UPDATE TO TEAM 10 SEND OUT SAMPLE TEAM NUMBER PROCEDURE TITLE REVISION EPIP-4.22 POST ACCIDENT SAMPLING OF CONTAINMENT AIR 5
PAGE 5 of 8 F-]
II II
HEEl-C ACTION/EXPECTED
RESPONSE
RESPONSE NOT OBTAINED NOTE:
Chemistry Team members will use the High Radiation Sampling System Containment Air Sampling Procedure to get a containment air sample.
Performance of the following activities requires HP surveillance.
11 MONITOR SAMPLING PROCESS:
a)
Monitor set-up of Containment Air Sample Panel:
- 1) Check Chemistry Team member verifies negative pressure alarm -
- 2) Verify alarm -
ON
- 2) GO TO Step 18 AND Evaluate respiratory protection requirements.
- 3)
WHEN Chemistry Team member closes rear door, THEN check alarm -
OFF
- 3) GO TO Step 18 AND Evaluate respiratory protection requirements.
b)
Monitor sampling of Containment Air:
- 1) Chemistry team member will notify HP prior to entry into sampling mode
- 2) Prepare for containment air to enter CASP
- 3)
Monitor dose rates on front of panel and on sample container NUMBER PROCEDURE TITLE REVISION EPIP-4.22 POST ACCIDENT SAMPLING OF CONT=AINMENT AIR 5
PAGE 6 of 8 H-
-LIIJ-E ACTION/EXPECTED
RESPONSE
[-I RESPONSE NOT OBTAINED 12 PREPARE SAMPLE FOR TRANSPORT:
a)
Put glass bottle and syringe assembly in separate plastic bags b)
Record the following information on sample containers (bags):
"* Sample identification
"* Unit number
"* Sample volume
"* Date
"* Time
"* Dose rate 13 CHECK SAMPLE CONTACT READING LESS THAN 10 mrem/hr IF sample contact reading GREATER THAN 10 mrem/hr, THEN ask HP to initiate EPIP-4.26, HIGH ACTIVITY SAMPLE ANALYSIS.
14 TAKE SAMPLE TO COUNT ROOM:
a)
Use pre-planned route b) Monitor radiological conditions during transit c)
Check dose rates along route within expected levels c)
Do the following:
I) Notify RPS.
- 2) Identify route of lowest dose field.
d)
Maintain ALARA NUMBER PROCEDURE TITLE REVISION EPIP-4.22 POST ACCIDENT SAMPLING OF CONTýAINMENT AIR 5
PAGE 7 of 8 H-l I
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 CALCULATE SAMPLE VOLUME:
a) Ask Chemistry for the number of aliquots of containment air taken b) Calculate volume:
- Aliquots x 0.1 cc = Volume x 0.1 cc =
c) Adjust calculation for containment pressure:
Containment Pressure x
14.7 Volume = Corrected Volume x
14.7 16 HAVE SAMPLE ANALYZED 17 NOTIFY RADIATION PROTECTION SUPERVISOR THAT SAMPLING IS COMPLETE 18 TERMINATE EPIP-4.22:
"* Give completed EPIP-4.22, forms and other applicable records to the Radiation Protection Supervisor
"* Completed by:
Date:
Time:
-END-NUMBER PROCEDURE TITLE REVISION EPIP-4.22 POST ACCIDENT SAMPLING OF CONT1ANMENT AIR 5
PAGE 8 of 8 H-F I--
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.-- S T
ýEP
VIRGINIA POWER SURRY POWER STATION EMERGENCY PLAN IMPLEMENTINGPROCEDURE LEVEL 2 DISTRIBUTION This Document Should Be Verified And Annotated to A Controlled Source As Required to Perform Work NUMBER PROCEDURE TITLE REVISION EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT 9
PAGE (With No Attachments)
I of 8 PURPOSE To provide instructions for monitoring during the collection of a reactor coolant sample.
ENTRY CONDITIONS Any of the following:
- 1.
Entry directed by the Radiological Assessment Director (RAD).
- 2.
Entry directed by the Radiation Protection Supervisor (RPS).
Approvals on File Effective Date
-111EV ACTION/EXPECTED RESPONSE H-H
RESPONSE
NOT OBTAINED I INITIATE PROCEDURE:
- By:
Date:
Time:
NOTE:
Sampling teams should consist of one Chemistry Team member and one Monitoring Team member at the Liquid Sample Panel (LSP) in the Auxiliary Building, and one Chemistry Team member at the Process Control Panel (PCP) in the Unit I Cable Spreading Room.
2 REVIEW SYSTEM DESIGN BASIS:
- Reactor coolant design basis dose rates:
- 1000 rem/hr surface, undiluted
- I rem/hr surface, diluted
- 650 mrem/hr, undiluted, at the surface of the cask when the cover is NOT in place
- LSP design basis dose rates:
365 mrem/hr at three feet e LSP is maintained at a negative pressure NUMBER PROCEDURE TITLE REVISION EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT 9
PAGE 2 of 8 1-I I
.- STJ-E ACTION/EXPECTED
RESPONSE
F-I RESPONSE NOT OBTAINED NOTE:
Protective measures should be considered PCP in the Unit 1 Cable Spreading Room.
3 EVALUATE PROTECTIVE MEASURES:
a)
Dosimetry for LSP:
"* Head
"* Trunk
"* Gonad
"* Leg
"* Arm
"* Wri st b) Protective clothing for LSP:
"* Full protective clothing
"* Plastic suit
"* Single gloves c) Respiratory protection IAW general area conditions in the Auxiliary Building d) Consider temporary shielding e) Check anticipated exposure EXCEEDS LIMITS f)
Initiate EPIP-4.04, EMERGENCY PERSONNEL RADIATION EXPOSURE 4
ASSIGN SAMPLING TEAM MEMBERS for the individual at the e)
IF emergency exposure limits NOT exceeded, THEN GO TO Step 4.
NUMBER PROCEDURE TITLE REVISION EPIP-4.23 POST ACCIDENT SAMPLING OF REA4YTOR COOLANT 9
PAGE 3 of 8 F-l II
STEP ACTION/EXPECTED RESPONSE I
I
RESPONSE
NOT OBTAINED 5 IDENTIFY INGRESS/EGRESS ROUTES:
a)
Ask RPS about current plant conditions b) Check radiation monitoring system for general area dose rates and vent exhaust activity c) Check recent airborne and general area surveys d) Establish routes 6
GIVE BRIEFING TO SAMPLE TEAM:
a)
Review sampling procedure b)
Review ingress/egress routes c)
Review requirements for the PCP and the LSP:
"* Stay times
"* Protective clothing
"* Dosimetry
"* Respiratory equipment
"* HP monitoring d)
Review cautions:
"* High radiation levels
"* High sample activity levels
"* High pressure sample
"* Buddy system
"* Open valves slowly NUMBER PROCEDURE TITLE REVISION EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT 9
PAGE 4 of 8
-LEi-t ACTION/EXPECTED RESPONSE F-F
RESPONSE
NOT OBTAINED 7
CONSULT WITH RPS:
"* Notify RPS that sample team is ready for dispatch
"* Ask RPS about current plant status
"* Have RPS notify RAD and Shift Supervisor (Operations) upon team dispatch 8
GIVE PLANT STATUS UPDATE TO TEAM 9
DISPATCH SAMPLE TEAM NOTE:
Chemistry Team members use Chemistry Procedures to obtain a liquid sample and to perform chemical analyses.
The following sampling
- process, as directed by the Chemistry Procedure, requires HP surveillance.
10 MONITOR SAMPLING PROCESS:
NUMBER PROCEDURE TITLE REVISION EPIP-4.23 POST ACCIDENT SAMPLING OF REACGTOR COOLANT 9
PAGE 5 of 8 H-11
ACTION/EXPECTED
RESPONSE
[-I RESPONSE NOT OBTAINED 10 MONITOR SAMPLING PROCESS: (Continied) a)
Monitor set-up of the LSP
- 1) Check Chemistry Team member verifies negative pressure alarm -
- 2) Verify alarm - ON
- 2) GO TO Step 16 AND Evaluate respiratory protection requirements.
- 3)
Verify alarm OFF
- 3)
GO TO Step 16 AND Evaluate respiratory protection requirements.
b)
Establish initial purge to panel of liquid:
- Have Chemistry Team member notify Monitoring Team prior to initiating purge c)
Chemistry analysis -
PERFORMED e No sample taken d) Check stripped gas sample and hydrogen analysis:
- 15 ml vial with 0.024 mls of reactor coolant off-gas,
e) Check diluted liquid sample:
- 60 ml vial with 0.024 mls of liquid sample diluted with 24 mls of demineralized water (1:1000 dilution) c)
GO TO Step 1O.d.
d)
GO TO Step 1O.e.
e)
GO TO Step 10.f.
NUMBER PROCEDURE TITLE REVISION EPIP-4.23 POST ACCIDENT SAMPLING OF REACTfOR COOLANT 9
PAGE 6 of 8 F-D l
AsZ-Ei-H ACTION/EXPECTED RESPONSE I-I RESPONSE NOT OBTAINED 10 MONITOR SAMPLING PROCESS: (Contin-Ued) f) Undiluted sample -
OBTAINED g) Monitor cask and cart as it is removed from the sample station h) Get dose rate of cask and cart after auxiliary shield is installed 11 MONITOR LIQUID SAMPLE DILUTION:
a)
Verify sample remains in shield cask b)
Verify diluter hole shield plug REMOVED c)
Get dose rate (with plug removed) d)
Get dose rates from diluted sample 12 RECORD INFORMATION ON SAMPLE CONTAINER PRIOR TO TRANSPORT:
"* Date
"* Time
"* Sample identification
"* Unit number
"* Sample volume
"* Dose rates 13 ISOLATE AND FLUSH PANEL (IF REQUIRED):
- Monitor Chemistry Team member activities while isolating and flushing panel f)
GO TO Step 11.
NUMBER PROCEDURE TITLE REVISION EPIP-4.23 POST ACCIDENT SAMPLING OF REACfOR COOLANT 9
PAGE 7 of 8 I
ACTION/EXPECTED RESPONSE
[-I RESPONSE NOT OBTAINED 14 TAKE SAMPLES TO COUNT ROOM:
a)
Use pre-planned route b) Monitor radiological conditions during transit c)
Check dose rates along route within expected levels c)
Do the following:
- 1) Notify RPS.
- 2)
Identify route of lowest dose field.
d) Maintain ALARA e) Deliver samples 15 MAKE NOTIFICATIONS FOLLOWING SAMPLE DELIVERY:
"* RPS
"* RAD
"* Shift Supervisor (Operations) 16 TERMINATE EPIP-4.23:
"* Give completed EPIP-4.23, forms and other applicable records to the Radiation Protection Supervisor
"* Completed by:
Date:
Time:
END NUMBER PROCEDURE TITLE REVISION EPIP-4.23 POST ACCIDENT SAMPLING OF REACTOR COOLANT 9
PAGE 8 of 8 H-I l