ML040280333
| ML040280333 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 01/21/2004 |
| From: | Grecheck E Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 04-016 | |
| Download: ML040280333 (11) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHmoND, VIRGINIA 23261 January 21, 2004 U.S. Nuclear Regulatory Commission Serial No.04-016 Attention: Document Control Desk NEP~jbc/mm RO Washington, D.C. 20555 Docket Nos.
50-280, 281 50-338, 339 License Nos.
DPR-32, 37 NPF-4, 7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA AND SURRY POWER STATIONS REVISION TO CORPORATE PLAN IMPLEMENTING PROCEDURE Pursuant to 10 CFR 50.54(q), attached is a revision to Corporate Plan Implementing Procedure.
This revision updates previous submittals of the Corporate Plan Implementing Procedures.
This revision does not decrease the effectiveness of our Emergency Plan and the plan, as revised, continues 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.
Your attention is also directed to the cover page of the enclosed procedure. This page provides a revision summary for the Corporate Plan Implementing Procedure and is intended to facilitate your review of the enclosed material.
No commitments are made by this letter. If you have any questions or require additional information, please contact Mr. David Sommers at (804) 273-2823.
Very truly yours, Eugene S. Grecheck Vice President - Nuclear Support Services Attachments 5Gal
SN 04-016 Docket Nos. 50-280/281 50-338/339 Letter-Page 2 cc:
U.S. Nuclear Regulatory Commission (4 copies)
Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23 T85 Atlanta, GA 30303-3415 Mr. S. R. Monarque (Letter only)
U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8H12 Rockville, MD 20852 Mr. C. Gratton (Letter only)
U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8G9 Rockville, MD 20852 NRC Senior Resident Inspector North Anna Power Station Mr. G. J. McCoy NRC Senior Resident Inspector Surry Power Station
V '
Serial No.04-016 CPIP Revision Attachment VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
REVISION TO CORPORATE PLAN IMPLEMENTING PROCEDURE Enclosed is a recent revision to a Corporate Plan Implementing Procedure (CPIP).
Please take the following actions in order to keep your manual updated with the most recent revisions.
Remove Title Rev Date Insert Rev Date CPIP-6.2 Radiological Assessment 7
12/11/02 CPIP-6.2 8
1/7/2004 Coordinator Emergency Plan Privacy and Proprietary Material has been removed.
Reference Generic Letter No. 81-27.
Sm minivon
~Corporate Emergency Plan Implementing Procedure
Title:
Radiological Assessment Coordinator Procedure Number:
[
Revision Number:
Effective Date:
CPIP-6.2 8
1 l/2004 Revision Summary:
Add clarification regarding frequency for updating Radiological Status reports for changing conditions (Step 8.g).
Updated position title (Step 13)
Add default Total Effective Dose Equivalent ('EDE)/Direct Dose Equivalent (DDE) ratio for unfiltered fuel handling accident developed using alternate source term assumptions (Attachment 2, Default Accident-Type Specific TEDE/DDE Ratios).
Approvals on File
CPIP-6.2 Page 1 of 5 Revision 8 RADIOLOGICAL ASSESSMENT COORDINATOR (Initials)
- 1.
Assign the following EPIPs to the Dose Assessment Team, as deemed necessary:
EPIP-4.03, DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE EPIP-4.08, INITIAL OFFSITE RELEASE ASSESSMENT EPIP-4.30, USE OF MIDAS CLASS A MODEL EPIP-4.31, USE OF MIDAS CLASS B MODEL NOTE:
A minimum of 2 (two) Offsite Monitoring Teams must be dispatched (i.e., sent into the field) at a Site Area Emergency or higher emergency class.
- 2.
Assign EPIP-4.34, FIELD TEAM RADIO OPERATOR INSTRUCTIONS, to the Field Team Radio Operator:
a) Assure Field Team Radio Operator tracks Offsite Monitoring Team personnel dose.
b) Give Field Team Radio Operator thresholds (exposure limits) for reporting Offsite Monitoring Team exposure (TEDE and Thyroid CDE).
c) Ask Field Team Radio Operator to alert staff if Offsite Monitoring Team exposure limits (EDE or Thyroid CDE) may be met.
NOTE:
The Health Physics Network (HPN) is established after the NRC announces over the Emergency Notification System (ENS, located in the TSC) that HPN communications is desired. The HPN Communicator may be assigned other duties until this occurs.
- 3.
Assign EPIP-4.33, HEALTH PHYSICS NETWORK COMMUNICATIONS, to the HPN Communicator.
- 4.
IF in LEOF, THEN verify facility surveillance procedures implemented:
EPIP-4.28, TSCJLEOF RADIATION MONITORING SYSTEM (North Anna)
EPIP-4.29, TSCJLEOF RADIATION MONITORING SYSTEM (Suny)
EPIP4.18, MONITORING OF LEOF (North Anna or Surry)
- 5.
IF emergency radiation exposure may be required for Offsite Monitoring Team members or LEOF staff (exposure GREATER THAN 5 Rem TEDE), THEN request Radiological Assessment Director initiate EPIP-4.04, EMERGENCY PERSONNEL RADIATION EXPOSURE.
CPIP-6.2 Page 2 of 5 Revision 8 I6.
IF KI authorization may be required for Offsite Monitoring Team members or LEOF staff (exposure GREATER THAN 25 Rem Thyroid CDE), THEN initiate EPIP-5.07, ADMINISTRATION OF RADIOPROTECTIVE DRUGS.
NOTE:
Dose assessment results may need to be further explained to other emergency responders in terms of the accident type used, application of default values, assumed release pathways and MIDAS averaging functions.
EPIP-4.30, USE OF MIDAS CLASS A MODEL, Attachment 2, Design Basis Accident Technical Overview, includes a discussion of technical bases related to the development of dose projections.
- 7.
IF the following table indicates a classification higher than that in effect, DOSE PROJECTION RESULTS CLASSIFICATION
> 1 Rem TEDE or GENERAL EMERGENCY 5 Rem Thyroid CDE
> 100 mrem TEDE or SITE AREA EMERGENCY 500 mrem Thyroid CDE
> 1000% of Release Limit ALERT
> 100% of Release Limit NOTIFICATION OF UNUSUAL EVENT
< 100% of Release Limit N/A THEN notify the following personnel immediately:
S0 Recovery Manager Radiological Assessment Director
- 8.
Coordinate review and distribution of offsite release assessment results:
a) Assure MIDAS Run # recorded on all pages-of each MIDAS run.
b) Initial each page to document RAC approval for issuance of results.
c) Review offsite release assessment results with the Recovery Manager.
(Step 8 continued on following page)
CPIP-6.2 Page 3 of 5 Revision 8
- 8.
Coordinate review and distribution of offsite release assessment results: (continued) d) IF any of the following conditions apply, release of radioactive material is occurring release of radioactive material has occurred and is terminated release of radioactive material is projected to occur THEN do the following:
- 1) Give Radiological Status Report to StateALocal Communicator immediately.
- 2)
Give Special Report to LEOF Services Coordinator for distribution (CERC Administrative Services Manager if in CEOF).
- 3)
GO TO Step 8.f e) IF conditions specified in Step 8.d do NOT apply, THEN give the following reports to the LEOF Services Coordinator for distribution (CERC Administrative Services Manager if in CEOF):
Radiological Status Report Special Report f) Review offsite release assessment results with the following:
Virginia Department of Health (VDH) State Radiological Assessment Officer as soon as practical (if present)
NRC Incident Response Team Protective Measures Coordinator (if present)
RAD (in TSC) or TSC Dose Assessment Team representative Radiological representative in CERC (if available) g) IF release of radioactive material is occurring, has occurred and is terminated or is projected to occur, THEN give State/Local Communicator information needed to complete EPIP-2.01, NOTIFICATION OF STATE AND LOCAL GOVERNMENTS, Attachment 3, Report of Radiological Conditions to the State:
Give updates every 60 minutes during an Alert or higher classification Within 15 minutes after a classification upgrade When radiological conditions change (only significant changes need to be provided more frequently than every 60 minutes or following a classification change, e.g., a change causing a modification to offsite protective actions)
CPIP-6.2 Page 4 of 5 Revision 8
- 9.
IF a General Emergency is declared, THEN implement EPIP-4.07, PROTECTIVE MEASURES.
NOTE:
- Dose assessment results may need to be further explained to other emergency responders in terms of the accident type used, application of default values, assumed release pathways and MIDAS averaging functions.
CPIP-6.2, RADIOLOGICAL ASSESSMENT COORDINATOR, Attachment 1, Comparison of Dose Assessment Codes: RASCAL Versus MIDAS, provides a summary of differences between the models.
- 10.
Coordinate offsite dose assessment activities with non-utility emergency responders:
a) Give updates to the following (if present):
Virginia Department of Emergency Management (DEM) On-Scene Coordinator Virginia Department of Health (VDH) State Radiological Assessment Officer NRC Incident Response Team Protective Measures Coordinator b) Ask VDH and NRC representatives if information to operate RASCAL is needed.
(Some of this data appears on the MIDAS Special Report.) Data needed by VDH and NRC may include (but not be limited to) the following:
Source term (based on release rate, concentration, user specified mix, plant conditions, containment monitors)
Shutdown time Hold-up time (e.g., time between release to containment and release to environment)
Meteorology (wind speed, wind direction, stability class, precipitation) c) Notify VDH and NRC representatives about the following:
Casualty-specific TEDE/DDE ratio (based on effluent sample analysis or MIDAS estimate appearing on Radiological Status report). IF casualty-specific TEDE/DDE ratio NOT available, THEN provide appropriate site-specific value from Attachment 2, Default Accident-Type Specific TEDE/DDE Ratios.
Decision to administer potassium iodide to licensee emergency workers
- 11.
Give updates to Recovery Manager as conditions change or as information becomes available regarding the following:
Offsite Release Assessment Radiological trends Protective Action Recommendations
CPIP-6.2 Page 5 of 5 Revision 8 NOTE:
Ping-3B Alert and High Alarns represent the following conditions:
Alert Alarm: Setpoint at which staytime in facility for event duration of 4 weeks (12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts at 6 days per week) would yield an emergency worker exposure of 5 Rem TEDE and/or 50 Rem Thyroid CDE High Abanm Setpoint established at 10 times the Alert Alarm setpoint, at which emergency worker TEDE and/or Thyroid CDE limits would be exceeded in about 1 day of continuous occupancy.
- 12.
IF LEOF activated and its habitability potentially affected by changes in radiological or meteorological conditions, THEN do the following:
- a. Evaluate HVAC for possible re-alignment.
- b. Check pressure gauge for positive pressure when operating in Emergency Mode.
- c. Assure pressure boundary doors are closed so that positive pressure is maintained:
Doors between LEOF Security area, Training Building and outside exits LEOF rear exit doors KJ
- d. Consider limiting eating and drinking in facility.
- e. Notify Recovery Manager about habitability restrictions and actions taken
- 13.
WHEN directed by Recovery Manager to enter Recovery or to secure from the emergency, THEN do the following:
Evaluate need for continued use of offsite teams for data/sample collection.
IF in LEOF, THEN have HP restore LEOF HVAC to Normal Mode (refer to EPIP-4.18).
Assure Offsite Teams are informed of status.
Review EPIP-6.01, RE-ENTRY/RECOVERY GUIDELINE, Attachment 2, Plume Pathway Assessment Guideline.
Give completed forms and records to the LEOF Services Coordinator (CERC Plan/Design/Construction Manager if in CEOF).
CPIP-6.2 Page 1 of 1 Revision 8 ATTACHMENT 1:
COMPARISON OF DOSE ASSESSMENT CODES:
RASCAL VERSUS MIDAS PARAMETER RASCAL*
MIDAS SOURCE TERM Nuclide specific and gross release rates.
Default accident mixes.
Percent nuclide mix category.
PCS/ERFCS input (monitor indications):
Plant conditions based (NUREG-1228).
- 15 min. processing Isotopic, core damage estimates, monitored User specified data.
releases, containment air samples, containment Nuclide specific release rates.
monitor, and spent fuel accident source terms WASH-1 400, NUREG 1228 mix options available.
available.
User specified event/release timing for decay.
Decay after reactor shutdown.
Decay during containment holdup.
DISPERSION Straight line Gaussian (TADPLUME).
Gaussian straight line, plume segmented for Lagrangian Puff (TADPUFF).
constant met (Model 3).
Gaussian plume segmented for variable met (Model 5).
Eight organs, seven pathways, 80 receptor locations.
METEOROLOGY User specified.
PCSIERFCS input:
Ground level with mixing layer height
- 5 - 10 second sampling No mixed mode releases.
- 15 min. averaging Puff trajectory uses spatial and temporal varying
- Hourly processing meteorological conditions.
User defined.
Wet and dry deposition.
Ground, elevated or mixed mode.
Deposition velocity: 0.003 in/sec.
Precipitation entry available.
Non-documented building wake correction Wet and dry depletion.
methodology.
Deposition velocity:
Wind speed:
- 0.01, lodines No correction from height of measurement to
- 0.001, Particulates height of release.
Building wake factor.
- Virtual source OUTPUT Maximum doses for 10, 25 and 50 miles:
EPIP-2.01, Attachment 3:
- User specified at 0.1 mile increments Report of Radiological Conditions to the State.
- Default distances at 0.5 mile increments Centerline and off-centerline dose rates and
- Not necessarily centerline integrated doses for Site Boundary, 2, 5 and 10 Plume characterization for individual releases:
miles:
- Location, dose
- Specific location of maximum dose
- Dose rates
- Ground shine and cloud shine
- TEDE/DDE Ratio (Federal Guidance Report No. 12)
Various plots, prints and reports.
- Open/Closed Window Dose Rates
- NUREG 1741, RASCAL 3.0: Description of Models and Methods
CPIP-6.2 Page 1 of 1 Revision 8 ATTACHMENT 2:
DEFAULT ACCIDENT-TYPE SPECIFIC TEDE/DDE RATIOS Table 1 North Anna Power Station ACCIDENT TYPE TEDE/DDE RATiO MSLB Main Stem Line Break 50 SGTR Steam Generator Tube Rupture 3
Fuel Handling Fuel Handling 1.5 WGDT Rupture Waste Gas Decay Tank Rupture 1
VCT Rupture Volume Control Tank Rupture 1
LOCA with melt Loss of Coolant Accident with melt 4
LOCA, no melt Loss of Coolant Accident with no melt 2
Locked Rotor Locked Rotor 13 Table 2 Surry Power Station ACCIDENT TYPE TEDE/DDE RATIO MSLB Main Stem Line Break 49 SGTR Steam Generator Tube Rupture 26 Fuel Handling (Filtered)
Fuel Handling (Filtered) 1.5 Fuel Handling (Unfiltered)
Fuel Handling (Unfiltered) 5 WGDT Rupture Waste Gas Decay Tank Rupture 1
VCT Rupture Volume Control Tank Rupture 1
LOCA Loss of Coolant Accident 3
Locked Rotor Locked Rotor 13 SRF Surry Radwaste Facility 1