ML11224A064
| ML11224A064 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 08/05/2011 |
| From: | - No Known Affiliation |
| To: | Division of Operating Reactor Licensing |
| References | |
| Download: ML11224A064 (16) | |
Text
WBN2Public Resource From: Boyd, Desiree L [dlboyd@tva.gov]
Sent: Friday, August 05, 2011 12:24 PM To: Epperson, Dan; Poole, Justin; Raghavan, Rags; Milano, Patrick; Campbell, Stephen Cc: Crouch, William D; Hamill, Carol L; Boyd, Desiree L
Subject:
TVA letter to NRC_08-05-2011_FSAR Ch 15.5 Dose Response Attachments: 08-05-2011_FSAR Ch 15.5 Dose Response_Final.pdf Please see attached TVA letter that was sent to the NRC today.
Thank You,
~*~*~*~*~*~*~*~*~*~*~*~
Désireé L. Boyd WBN 2 Licensing Support Sun Technical Services dlboyd@tva.gov 423-365-8764 1
Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 465 Mail Envelope Properties (7AB41F650F76BD44B5BCAB7C0CCABFAF219CAC36)
Subject:
TVA letter to NRC_08-05-2011_FSAR Ch 15.5 Dose Response Sent Date: 8/5/2011 12:23:42 PM Received Date: 8/5/2011 12:24:26 PM From: Boyd, Desiree L Created By: dlboyd@tva.gov Recipients:
"Crouch, William D" <wdcrouch@tva.gov>
Tracking Status: None "Hamill, Carol L" <clhamill@tva.gov>
Tracking Status: None "Boyd, Desiree L" <dlboyd@tva.gov>
Tracking Status: None "Epperson, Dan" <Dan.Epperson@nrc.gov>
Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov>
Tracking Status: None "Raghavan, Rags" <Rags.Raghavan@nrc.gov>
Tracking Status: None "Milano, Patrick" <Patrick.Milano@nrc.gov>
Tracking Status: None "Campbell, Stephen" <Stephen.Campbell@nrc.gov>
Tracking Status: None Post Office: TVANUCXVS2.main.tva.gov Files Size Date & Time MESSAGE 312 8/5/2011 12:24:26 PM 08-05-2011_FSAR Ch 15.5 Dose Response_Final.pdf 301659 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 August 05, 2011 10 CFR 50.34(b) 10 CFR 100 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
Subject:
Watts Bar Nuclear Plant (WBN) Unit 2 - Final Safety Analysis Report (FSAR) - Chapter 15.5 Design Basis Accident Dose Analysis
References:
- 1. TVA letter to NRC dated June 27, 2011 Watts Bar Nuclear Plant (WBN) Unit 2 - Final Safety Analysis Report (FSAR) - Response to Request for Additional Information (RAI) Regarding Accident Dose Analysis Basis This letter provides revised FSAR Design Basis Accident (DBA) dose analysis results.
The submittal of these analyses was a TVA commitment to NRC described in Reference 1. provides updated FSAR tables for each of the DBAs discussed in FSAR Section 15.5 with the exception of the Fuel Handling Accident. The updated tables will be included in a future FSAR Amendment. The results reflect the use of the most recent meteorology data for the 20 year period of 1991 to 2010 as opposed to the 1976 to 1993 data used for licensing Unit 1. The use of the more recent meteorological data resulted in minor changes to the results but no regulatory dose limits were exceeded and margins to the limits were virtually unchanged. A change in the main control room isolation time from 20.6 seconds to 40 seconds was included in the analyses. A revised Fuel Handling Accident will be provided in a separate correspondence by August 31, 2011. A list of new commitments is provided in Enclosure 2.
U.S. Nuclear Regulatory Commission Page 3 August 05, 2011 bcc (Enclosures):
Stephen Campbell U.S. Nuclear Regulatory Commission MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Charles Casto, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257
Enclosure 1 WBN Unit 2 Revised FSAR Section 15.5 Accident Dose Analysis Results Tables The following revised FSAR Chapter 15.5 DBA Tables are provided in this enclosure:
Table 15.5.2 Doses from Loss of A/C Power Table 15.5-5 Doses from Gas Decay Tank Rupture Table 15.5-9 Doses from Loss-of-Coolant Accident Table 15.5-13 Doses From Recirculation Loop Leakage Following A LOCA Table 15.5-14 Atmospheric Dilution Factors At The Control Building Table 15.5-17 Doses From Main Steam Line Break Table 15.5-18 Parameters Used In Steam Generator Tube Rupture Analysis Table 15.5-19 Doses From Steam Generator Tube Rupture Table 15A-2 Accident Atmospheric Dilution Factors (sec/m3)
E1-1
WATTS BAR Table 15.5-2 Doses From Loss Of A/C Power Conservative Analysis (rem) 2HR EAB 30 DAY LPZ CONTROL ROOM Gamma 7.45E-04 4.18E-04 2.12E-04 Beta 4.48E-04 2.52E-04 2.55E-03 Thyroid - ICRP-30 4.57E-02 2.57E-02 2.11E-02 2HR EAB 30 DAY LPZ CONTROL ROOM Realistic Analysis (rem)
Gamma 1.80E-08 1.01E-08 5.11E-09 Beta 1.66E-05 9.29E-06 1.81E-04 Thyroid - ICRP-30 1.10E-06 6.18E-07 5.09E-07 15.5-28 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS
WATTS BAR Table 15.5-5 Doses From Gas Decay Tank Rupture Regulatory Guide 1.24 Analysis 2HR EAB 30 DAY LPZ CONTROL ROOM (rem)
Gamma 5.96E-01 1.67E-01 8.43E-01 Beta 1.61E+00 4.51E-01 7.28E+00 Thyroid - ICRP-30 1.29E-02 3.60E-03 6.99E-03 2HR EAB 30 DAY LPZ CONTROL ROOM Realistic Analysis (rem)
Gamma 2.88E-02 8.05E-03 3.81E-02 Beta 1.10E-01 3.08E-02 5.01E-01 Thyroid - ICRP-30 1.21E-02 3.37E-03 6.50E-03 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS 15.5-31
WATTS BAR Table 15.5-9 DOSES FROM LOSS-OF-COOLANT ACCIDENT (rem) 2Hr EAB 30 Day LPZ Control Room Gamma 2.12 2.18 1.05 Beta 1.25 2.61 9.10 Thyroid - ICRP - 30 40.4 14.33 3.75 Breakdown of Control Room Personnel Dose (rem) Airborne Shine Ingress/Egress Total Gamma 1.02 0.005 0.027 1.05 Beta 9.04 0.000 0.060 9.10 Thyroid - ICRP - 30 3.66 0.000 0.090 3.75 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS 15.5-37
WATTS BAR Table 15.5-13 Doses From Recirculation Loop Leakage Following A LOCA (rem) 2HR EAB 30 Day LPZ Control Room Gamma 4.14E-03 2.28E-02 1.51E-03 Beta 1.36E-03 8.54E-02 1.62E-02 Thyroid - ICRP - 30 1.40E-03 1.53E-01 3.69E-02 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS 15.5-41
WATTS BAR Table 15.5-14 Atmospheric Dilution Factors At The Control Building DILUTION FACTOR (sec/m3)
LOSS OF A/C Time Period (hr) LOCA/FHA SGTR/MSLB POWER WGDT 0-2 1.09E-03 3.85E-03 2.61E-03 2.56E-03 2-8 9.44E-04 3.22E-03 2.15E-03 1.17E-03 8-24 1.56E-04 N/A N/A 7.26E-04 24-96 1.16E-04 N/A N/A 5.21E-04 96-720 9.59E-05 N/A N/A 4.30E-04 GENERAL CONTROL ROOM PARAMETERS Volume 257,198 cu ft Makeup/pressurization flow 711 cfm Recirculation flow 2889 cfm Unfiltered intake 51 cfm Filter efficiency 95% first pass 70% second pass 0% for noble gases, Tritium Isolation time, T 40 seconds Occupancy factors:
0-24 hr 100%
1-4 days 60%
4-30 days 40%
15.5-42 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS
WATTS BAR Table 15.5-17 Doses From Main Steam Line Break 1 gpm Primary- Control Room SRP 30-Day LPZ (rem) 2-Hour EAB (Site SRP to-Secondary Operator Guidance boundary (rem) Guidance for Leakage (rem) for GDC 19 10CFR100 (ARCON-96 Limits (rem) Limits (rem) x/Q)
Accident Initiated Iodine Spike Case (0.265 Ci/gm steady state)
Gamma: 8.10E-03 5 1.25E-01 1.04E-01 2.5 Beta: 6.52E-02 30 3.02E-02 2.54E-02 30 Inhalation 10.4E+00 30 4.78E+00 3.09E+00 30 (ICRP-30):
Pre-Accident Iodine Spike Case (14 Ci/gm max peak)
Gamma: 4.36E-03 5 1.11E-02 2.74E-02 25 Beta: 4.00E-02 30 4.20E-03 8.80E-03 300 Inhalation 7.44E+00 30 1.21E+00 2.41E+00 300 (ICRP-30):
ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS 15.5-45
WATTS BAR Table 15.5-18 Parameters Used In Steam Generator Tube Rupture Analysis Primary Side Activity Technical Specification Limit Secondary Side Activity ANSI/ANS-18.1-1984 (Expected levels, 150 gpd/SG)
Iodine Spiking Factor Case 1: Accident initiated spike of 500 times equilibrium iodine concentration Case 2: Pre-accident spike of 14 Ci/gm I-131 dose equivalent Iodine Partition Factor 100 Secondary Side Mass Release (Ruptured Steam Generator) 0 -2 hours 103,300 lbm 2 - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 32,800 lbm Secondary Side Mass Release (Intact Steam Generator) 0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 492,100 lbm 2 - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 900,200 lbm Primary Coolant Mass Release (Total) 0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 191,400 lbm Primary Coolant Mass Release (Flashed) 0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 10,077.2 lbm Atmospheric diffusion coefficients for control room 2.61 x 10 (0 - 2 hrs)
Operator doses 2.15 x 10 (2 - 8 hrs) 15.5-46 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS
WATTS BAR Table 15.5-19 Doses From Steam Generator Tube Rupture Pre-Accident Initiated Spike Case (14 Ci/gm maximum peak)
(rem) 2 HR EAB 30 DAY LPZ CONTROL ROOM Gamma 3.78E-01 1.11E-01 6.28E-02 Beta 2.26E-01 6.92E-02 7.07E-01 Thyroid - ICRP-30 1.39E+01 3.79E+00 1.24E+01 Accident Initiated Iodine Spike Case (0.265 Ci/gm steady state)
(rem) 2 HR EAB 30 DAY LPZ CONTROL ROOM Gamma 5.46E-01 1.60E-01 5.76E-02 Beta 2.51E-01 7.73E-02 6.70E-01 Thyroid - ICRP-30 7.19E+00 2.12E+00 2.03E+00 ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS 15.5-47
WATTS BAR Table 15A-2 Accident Atmospheric Dilution Factors (sec/m3)
Conservative And Regulatory Guide Analyses Low Population Zone (4828 Time Period (hours) Exclusion Area Boundary* meters) 0-2 6.382E-04 1.784E-04 2-8 8.835E-05 8-24 6.217E-05 24-96 2.900E-05 96-720 9.811E-06
- The dilution factors were calculated for a travel distance of 1100 meters, the distance from the 100 meter radius release zone to the 1200 meter radius exclusion boundary (See Section 2.3.4).
THYROID INHALATION DOSE 15A-5
Enclosure 2 Regulatory Commitments
- 2. Submit a letter with a revised Fuel Handling Accident by 08/31/2011 E2-1