ML020840584
| ML020840584 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/21/2002 |
| From: | Olshan L NRC/NRR/DLPM/LPD2 |
| To: | |
| References | |
| TAC MB3537, TAC MB3538, TAC MB3539 | |
| Download: ML020840584 (25) | |
Text
NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-1999)
TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed)by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed form, and the attached copy of meeting handout materials,will be sent to the Document Control Desk on the same day of the meeting; under no circumstanceswill this be done later than the working day after the meeting.
Do not include proprietarymaterials.
DATE OF MEETING The attached document(s), which was/were handed out in this meeting, is/are to be placed 03/21/2002 in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:
Docket Number(s) 50-269, 50-270, 50-287 Plant/Facility Name OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 TAC Number(s) (ifavailable) MB3537, MB3538, MB3539 Reference Meeting Notice 3/6/02 Purpose of Meeting (copy from meeting notice) TO DISCUSS 10/16/01 AMENDMENT REQUEST CONCERNING ALTERNATE SOURCE TERM AND CONTROL ROOM HABITABILITY NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE L. N. OLSHAN PROJECT MANAGER OFFICE NRR DIVISION DLPM BRANCH PD 11-1 Distribution of this form and attachments:
Docket File/Central File PUBLIC (
NRC FORM 658 (9-1999) PRINTED ON RECYCLED PAPER This form was designed using Int-orms
MEnuke Wnergy Oconee Nuclear Station Alternative Source Term License Amendment Request March 21, 2002
- Duke fdEnergy Agenda Regulatory Position - Larry Nicholson
- - Overview of Dose Analysis Work - Steve Schultz
- o Discussion of RAI Responses - Christie Taylor 2
I
ftDuke EEnergy Meeting Agenda
- . 9:00 Introductions L. Nicholson L. Olshan 9:05 Purpose & Background to Meeting L. Nicholson
+ 9:15 Overview of Submittal and Status S. P. Schultz 9:30 ONS Control Room Testing S. P. Schultz 9:45 Submittal Review & Amplification C. B. Taylor, et al.
10:15 Break 10:30 Submittal Review & Amplification C. B. Taylor, et al.
11:15 Discussion All 11:45 Action Items and Schedule Plan S. P. Schultz 12:00 Adjourn L. Olshan 3
MDuke Radiological WEnergy I B I IIIII""--'¸ EngineeringProgram Duke Power Radiological Engineering Program Staff profile and capabilities Program Objectives Oconee NS is the Lead AST Application General Analysis Features
- Alternative Source Term LOCADOSE analyses
- ARCON96x/Q evaluation and analyses
- Full scope in-house analysis
- Consultant support in specialty areas 4
2
ODuke ConsultantSupport EEnergy Profile Resources to support full scope applications of AST technology Bechtel Corporation LOCADOSE Polestar Source term chemistry; spray washout Duke Engr & Services Directed calculation support NISYS SCALE/ORIGEN source term Duke Power EHS ARCON96 reviews Decision-making and final analyses by Duke Power 5
ADuke IWMEnergy LOCADOSE Application Extensive code Verification / Validation calculation Code and applications training Multi-plant applications Multi-purpose applications Duke Power training process integration Bechtel code applications support & interaction 6
3
D-kDuke rEnergy ARCON96 Application Oconee Nuclear Station Application
- DE&S -4 Duke Power -4 C. B. Taylor
- Duke Power Environmental Health & Safety
- - Catawba & McGuire Nuclear Station Application
- Duke Power Environmental Health & Safety
- Duke Power Radiological Engineering
- DE&S review (Brad Harvey)
NRC Draft Guidance/ NEI 99-03/ DG-1111 7
Duke E-Energy Site Support Schedule Duke Power Radiological Engineering Site Support Schedule Oconee LOCA -------- FHA ----- -- Other Catawba FHA ----- > LOCA --------------- >SGTR McGuire FHA ----- LOCA --.--- Other Radiological Engineering committed as full force applications program
- Staff expertise and applications breadth
- Plant and analysis experience 4
DUke Control Room WEnergy Testing Program
-:- Tracer Gas Testing performed in 1998 and 2001 Both test programs performed by NCS Corporation and Lagus Applied Technologies, Inc System improvements and sealing work was performed between tests
-:- Additional test performance and data analysis lessons-learned applied in the 2001 testing program
- - Tracer gas mixing and sampling locations for flow measurements
- Calculation of measured values and uncertainties Results demonstrate that these changes caused a significant improvement in performance ODuke Control Room WEnergy Testing Results Tracer Gas Testing performed in 1998 and 2001 Control Test 1998 2001 Room Configuration Results Results 1 &2 Normal 1065 +/-61 869 +/-31 1 &2 Emergency- 1 Fan 80 +/-55 0 +/-18 1 &2 Emergency- 2 Fan [0 - 128] 0 +/-30 3 Normal 534 +/-30 467 +/- 16 3 Emergency - 1 Fan 73 +/- 25 0 +/- 13 3 Emergency - 2 Fan [0 - 236] 0 +/- 39 Control room pressurization system performance improvement 10 5
Mk-Duke LOCADOSE Code EEnergy - --- . . . . . (RI)
LOCADOSE computer code used in dose analyses
+ LOCADOSE input used for LOCA and FHA will be provided.
>- NRC Preference: Input decks or description of input parameters may be preferable (RADTRAD) SAlter LOCADOSE output obtained for LOCA and FHA will be provided.
Level of detail desired 11 MkDuke Site Layout WOEnergy (R2)
Site Layout Sketch can be provided showing:
- Site Building Layout
>- Control Room Intake Locations
"÷Current single CR intake locations
"*Proposed dual CR intake locations
>- Source Term Release Point Locations Level of detail desired 12 6
- EDuke tE uergy e PRVS and SFPVS (R3)
Probabilistic Risk Analysis
>- ONS PRA is a full scope Level 3 PRA
- Neither PRVS nor SFPVS is credited in the PRA
- Removal of PRVS and SFPVS from T.S. will not invalidate any assumptions made in PRA Severe Accident Management Program
)- The Oconee Severe Accident Guideline does not credit PRVS nor SFPVS
- Removal of PRVS and SFPVS from T.S. will not adversely impact the severe accident management program 13 M9 1 uke nergy Dual CR Intake Intakes Piping and Instrumentation Diagrams
- Design of new CR intake system is in early stages
- Sketches of system can be provided Dilution Effects
- - The system will be designed to achieve equal flowrates
)- Post-modification testing will be performed
- Any flow imbalance will be included in dose analyses Schedule Implementation schedule will be established Fall 2002 14 7
Mk-Duke HP!/LPI Discharge rWEnergy (R5)
Piping and Instrumentation Diagram
- Design of new CR intake system is in early stages
- Sketches of system can be provided Schedule
- Implementation schedule will be established Fall 2002 15 EfDuke E"-'Energy Passive Caustic I - -. - . (R6)
Reactor Building Sump Water pH Transient Calculation SThe pH profile is based on 300 cubic feet of trisodium phosphate dodecahydrate (TSP-C).
- The initial water pH value is calculated to be 5.21 at actual sump temperatures.
- Total sump water inventory ranges from 6.8E+05 Ibm at accident initiation to 3.1 E+06 Ibm when the entire BWST inventory has been emptied into the sump.
- The inventory of chloride-bearing cable is 45,700 Ibm.
16 8
kDuke Passive Caustic VOEnergy (R6)
+:. Reactor Building Sump Water pH Transient Calculation
- - Nitric acid generation is based on NUREG/CR-5950 methodology, and is calculated to be 7.3 x 10-9 mol HNO3 perg H20 per Mrad.
- The hydrochloric acid generation rate for PVC cable insulation is 33.12x10-4 mol of HCL per lb of PVC insulation per Mrad.
- Containment dose in the Reactor Building following an accident is based on data inthe ONS post-accident shielding calculation.
Schedule schedule will be established Fall 2002 SImp 17 MDuke FissionProducts fWAEnergy (R7)
Specifics of fission product release model:
>- The particulate iodine removal constant for removal by aerosol deposition (natural processes) are calculated using methodology from NUREG/CR-6189.
- Particulate washout values are obtained using NUREG/CR-0009 and SRP 6.5.2 methodology. At 25 minutes post-accident, the recirculation phase begins, and a new lambda is calculated based on the recirculation spray flowrate.
- The time for reaching a particulate decontamination factor of 50 by containment spray is approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> post-accident.
18 9
MkDuke Fission Products EEnergy ýý--1 (R7)
Specifics of fission product release model:
- Elemental iodine decontamination factor does not reach 200 by containment spray in calculation based on NUREG/CR-5950 methodology.
- Elemental iodine DF is approximately 82 when equilibrium elemental iodine concentration is reached.
- The maximum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose for the EAB occurs during the time period from 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following accident initiation.
19 MkDuke Iodine Spray Removal WEnergy (R8)
Containment Atmosphere Iodine Spray Removal Analysis
- - Reactor Building spray flowrates and timing determined 6.5.2 guidance for containment spray coverage
- Spray flowrate correction for spray interaction with containment wall
- Elemental and particulate iodine spray lambdas calculated based on SRP 6.5.2 and NUREG/CR-0009
- Iodine washout model developed based on ANSI/ANS-56.5
- Results are spray removal rate constants (lambdas) for elemental and particulate iodine for use in LOCADOSE modeling 20 10
BkDuke Iodine Spray Removal WEnergy (R8)
Iodine Re-volatilization Analysis
- Iodine Re-volatilization Methodology is based on NUREG/CR-5950
- Iodine tranforms to volatile form in low pH conditions
- - Elemental iodine can re-volatilize into containment atmosphere as sump solution is recirculated as containment spray Level of detail desired 21 MkDuke Spray Lambdas EEnergy (R9)
Elemental Iodine Spray Lambdas calculations are documented in the same calculations described in previous slides.
22 11
ODuke EEnergy ECCS Leakage (RIO)
ECCS leakage begins at earliest time of recirculation:
25 minutes post-accident Maximum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose at EAB occurs between 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> post-accident v Doses from ECCS portion of LOCA model:
- Control Room 0.7 rem TEDE 23 MDuke ridEnergy BWST Release (R11)
BWST back-leakage begins at earliest time of recirculation: 25 minutes post-accident 4,. BWST leakage is tested and monitored against the assumption of 5 gpm each outage by Duke procedures Iodine partition coefficient varies from a value of 34 at back leakage initiation to 9 at the end of leakage BWST volume is time-dependent. Initial volume at the end of the spray injection period is approximately 4,000 gallons.
Increases to 219,000 gallons at the end of ECCS back leakage.
24 12
Duke BWST Release EEnergy (RIu)
The maximum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose for the EAB occurs during the time period from 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following accident initiation.
The calculated EAB, LPZ and control room doses for the BWST are a subset of the small total dose due to ECCS leakage shown on the ECCS leakage slide, and are not calculated separately.
25 MkDuke Unffitered CR Inleakage IWEnergy ,.. (R12)
The measured inleakage values, with uncertainty, obtained from 1998 tracer gas testing performed by NCS Corporation are as follows:
Control Ventilation Current Room Mode Inleakagie Analysis Value U1/U2 Normal 1065 +/- 61 (ACFM) 1150 cfm U1/U2 Emergency Fan 80+1- 55 (SCFM) 150 cfm U3 Normal 534 +/- 30 (ACFM) 600 cfm U3 Emergency Fan 73 +/- 25 (SCFM) 100 cfm
26 13
MkDuke Single Assembly FHA EEnergy (R13)
The Maximum Linear Heat Generation Rate is 6.0 kW per foot, based on Oconee specific fuel parameters, burnup of 62,000 MWD/MTU and a peaking factor of 1.65.
Fractions of fission products in the fuel gap follow Regulatory Guide 1.183 Position 3.2.
Assemblies are decayed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in accordance with ONS T.S. prohibition of fuel movement until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> post shutdown.
5.6E+04 curies released to environment for single assembly accident 27 WEnDuke W~ergy Multiple Assembly FHA (R14)
The Maximum Linear Heat Generation Rate is 3.8 kW per foot, based on Oconee specific fuel parameters, core average inventory and a peaking factor of 1.2.
Fractions of fission products in the fuel gap follow Regulatory Guide 1.183 Position 3.2 Various decay times are assumed for each postulated event.
Freshly discharged fuel is decayed from 55 to 70 days. All other fuel is conservatively assumed decayed for one year.
+ 5.6E+05 curies released to environment for bounding cask drop case 28 14
Ekner Duke ISFS! Cask Drop 1ergy5 It is postulated that an ISFSI transfer cask is dropped onto the spent fuel pool racks.
The dropped cask is postulated to impact and damage numerous assemblies stored in the SFP racks.
The entire gap activity of the impacted assemblies is released.
Fractions of fission products in the fuel gap follow Regulatory Guide 1.183 Position 3.2.
Various decay times are assumed for each postulated event, as in previous slide.
29 ODuke Equipment Hatch r-Energy Closure (R16)
- - NRC expectation - Equipment Hatch closure within 30 minutes Equipment Hatch closure is achievable in 30 minutes Worker exposure can be a concern in some maximum DBA analyses Programmatic controls on closure process being examined at Catawba NS (2002/2003)
Results will be applicable to Oconee NS (2003/2004) 30 15
M&Duke EEnergy y/Q Values (R17)
- X/Q values were calculated for each release point by analyzing the corresponding release from each unit (1, 2 and 3) to each control room intake location.
- Maximum bounding X/Q values are applied, so that the calculation is bounding for all 3 Oconee units.
A description of which specific X/Q values were used for the specified release points will be provided.
31 MkDuke rWEnergy Iodine DF (R18)
Calculated overall effective DF values are based on an elemental DF of 500 and organic DF of 1 for a water level greater than or equal to 23 feet.
Corresponding DFs for Oconee's 21.34 feet water depth are 430 and 1, with a resultant overall effective DF = 262 32 16
Gas Injection ports used in 1998 test - Units 1 & 2 Ductwork at inlet of Unit 1 & 2 CR filters. Injection Ports are at upper right at column. Note there is not much distance between the injection point and the sample point. The sample points are on the bottom of the duct in the lower left portion of the picture. The same sample ports were used in the 2001 test with the gas injection on the roof at the outside air intake.
WV U
I'1 J WI A View from farther back showing filter train, 1998 injection ports and sample ports. Uncertainty was reduced by injecting gas on roof.
IW*Iiý N
K (7
Gas injection tubing at outside air intake for Units I & 2 2001 Test
J.
IA 4
Gas injection manifold inside duct and fans to promote mixing 2001 Test
K" 5*'j V~
,, ' \* I it, '1 Sample pump and tubing in ventilation equipment room.
Also note sealant on filter unit and ductwork 2001 Test
Air Handling Unit Access Door and Sealant mv Z') or WI (V
zz:3 0
EL>
(V m
?M 0 U
Co C
C 0 .0) z C,) 0)4-0 0 :3
>5 0)
C :)
-v
= co m
C C
I 0 I
4-0 C a: co
- 0) 06 .0) z LI C-) >5 Ui) 0o LU 0 (
CL a CU)>
Dw 1 CO0I