ML20203A341
| ML20203A341 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/28/1998 |
| From: | Raghavan L NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-M91823, NUDOCS 9802240005 | |
| Download: ML20203A341 (81) | |
Text
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% UNITED STATES 4
- { g NUCLEAR REGULATORY COMMISSION
- WASHINGTON, D.C. amHmoi
. . . . . ,o January 28, 1998 i
LICENSEE: Florida Power Corporation FACILITY: Crystal River Unit 3
SUBJECT:
SUMMARY
OF MEETING ON JANUARY 8,1998 TECHNICAL ISSUES RELATING TO CONTROL COMPLEX HABITABILITY ENVELOPE - JUSTlFICATION FOR CONTINUED OPERATION (TAC M91823) On January 8,1998, representatives of the Florida Power Corporation (FPC), licensee for Crystal I River Nuclear Plant, Unit 3 (CR3), met with U.S. Nuclear Regulatory Commission (NRC) staff { members at their Headquarters in Rockville, Maryland. Enclosure 1 is a list of attendees. ' Enclosure 2 is a copy of the handouts presented at the meeting - i The meeting involved working level technical discussions relating to control complex' habitability envelope (CCHE). Specifically, the licensee discussed its response to the U.S. Nuclear : l-Regulatory Commission (NRC) staffs request for additional information (letter dated L - December 24,1997) and presented details of its justification for continued operation (JCO), revision 5 (FPC letter dated January 7,1998). Based on the discussion, the staff indicat5d that the JCO may be acceptable for an interim - period with certain compensatory measures such as use of potassium iodide for control roora operators. For the long term, the staff. stated that FPC should revise its CCHE analysis using standard review plan (SEP) guidelines and provide acceptable technical justification for any - deviations from the SRP guidelines. The staff requested, and FPC agreed to submit within approximately 6 months after restart, a CCHE report to confirm that either the CCHE analysis is complete, or provide commitments and proposed plan for appropriate plant modifications etc. to ensure that doses would meet General Design Criterion 19 with acceptable assumptions and methods. The two stage approach (i.e., acceptable analysis at the 6 month mark or commitment for plant modifications), would provide flexibility for FPC to ensure that they identify any corrective actions with sufficient time to implement them by the end of the outage. In either case, the staff expects FPC to complete its effort including necessary staff approval, no later than restart after j the next refueling outage. FPC also agreed to consider adopting the SRP limits for steam generator tube rupture offsite dose in lieu of the current full 10 CFR Part 100. They quoted their design basis to be the full Part 100. The SRP requires a small fraction (e.g.,10%) of Part 100.
=
g UI'oj I I 9802240005 980128 PDR ADOCK 05000302 P PDR . I.llIlli.ll.Illlll1
I 2 FPC agreed with the above and indicated that it will provide a letter to document its commitment and propose appropriate license condition for the above interim and long term measures. L Raghavan, Project Manager Project Directorate 11-3 Division of Reactor Projects .1/11 Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosures:
- 1. Attendees List
- 2. Meeting handout I cc w/ enclosures: See next page l
l 4 V
2 FPC agreed with the above and indicated that it will provide a letter to document its commitment and propose appropriate license condition for the above interim and long term measures.
/S/
L. Raghavan, Project Manager Project Directorate ll-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulatin Docket No. 50-302 l
Enclosures:
- 1. Attendees List i
- 2. Meeting handout cc w/ enclosures: See next page t.
DISTRIBUTION: See next page Document Name: G:\ CRYSTAL \980108. SUM Office PM:PDil-3 LA:PDil-3 PD:PDil-3 Name LRaghavan BClayton 43 FHebdort Date 01Lk98 01h8 011b98 Copy hNo Yes kesho OFFICIAL RECORITCOPY l
Florida Power Corporation CRYSTAL RIVER UNIT NO. 3 GENERATING PLANT cc: Mr. R. Alexander Glenn Mr. Robert E. Grazio, Director Corporate Counsel Nuclear Regulatory Affairs (SA2A) Florida Power Corporation Florida Power Corporation MAC-ASA Crystal River Energy Complex P.O. Box 14042 15760 W. Power Line Street St. Petersburg, Florida 33733-4042 Crystal River, Florida 34428-6708 Mr. Charles Pardee, Director Senior Resident inspector Nuclear Plant Operations (NA2C) Crystal River Unit 3 Florida Power Corporation U.S. Nuclear Regulatory Commission Crystal River Energy Complex 6745 N. Tallahassee Road 15760 W. Power Line Street Crystal River, Florida 34428 Crystal River, Florida 34428-6708 Mr. James S. Baumstark Mr. Bruce J. Hickle, Director Director, Quality Programs (SA2C) Director, Restart (NA2C) Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Regional Administrator, Region ll Mr. Robert B. Borsum U.S. Nuclear Regulatory Commission Framatome Technologies Inc. 61 Forsyth Street, SW., Suite 23T85 1700 Rockville Pike, Suite 525 Atlanta, GA 30303-3415 Rockville, Maryland 20852 Mr. John P. Cowan Mr. Bill Passetti Vice President - Nuclear Production Oft e of Radiation Control (NA2E) Department of Health and Florida Power Corporation Rehabilitative Services Crystal River Energy Complex 1317 Winewood Blvd. 15760 W. Power Line Street Tallahassee, Florida 32399-0700 Crystal River, Florida 34428-6708 Attorney General Mr. Roy A. Anderson Department of Legal Affairs Senicr Vice President The Capitol Nuclear Operations Tallahassee, Florida 32304 Florida Power Corporation ATTN: Manager, Nuclear Licensing Mr. Joe Myers, Director Crystal River Energy Complex (SA2A) Division of Emergency Preparedness 15760 W. Power Line Street Department of Community Affairs Crystal River, Florida 34428-6708 2740 Centerview Drive Tallahassee, Florida 32399-2100 Mr. Kerry Landis U.S. Nuclear Regulatory Commission Chairman 61 Forsyth Street, SW., Suite 23T85 Board of County Commissioners Atlanta, GA 30303-3415 Citrus County 110 North Apopka Avenue Iverness, Florida 34450-4245
4
SUBJECT:
SUMMARY
OF MEETING OF JANUARY 8,1998, CONTROL COMPLEX HABITABILITY ENVELOPE l i Distribution HARD COPY
". Docket File -
PUBLIC Crystal River Reading OGC ACRS L.Raghavan J. Johnson, Ril E-Mail w/ Enclosure 1 i S. Collins /F. Miraglia (SJC1,FJM) R. Zimmerman (RPZ)
- 8. Boger (BAB2,RCN)
J. Zwolinski (JAZ) K. Landis (ADL) F. Hebdon (FJH) B. Clayton (BAC2) J, Joudan, Rll T. Martin (e-mail to SLM3) M. Tschiltz, EDO (MDT) S. Flanders (SCF) S. Cahill S. LaVie C. Miller C. Liang R. Emch M. Blumberg I
- . -. . .. _ . .- . . - . . - - . .-. .. - . . _ - - . _ - . ~ - . . -
CftYSTAL RIVER 3 MEETING I DECEMBER 2.1997 Name organization L.Raghavan NRC/NRR ! Fred Hebdon NRC/NRR
- Scott Flanders NRC/NRR i
Steve LaVie NRC/NRR i C. Miller NRC/NRR C. Liang NRC/NRR l R. Emch NRC/NRR M. Blumberg NRC/NRR S. Powell Florida Power Corp. M. Rencheck Florida Power Corp. L M. Clary Florida Power Corp. i V.M. Esquillo Florida Power Corp. I D. Studley Scintech - NUS M. Rutherford Framatome Technologies M. Parece Framatome Technologies W. DeLise Sargent & Lundy R. Aggarwal Sargent & Lundy J. Russell MPR & Associates Enclosure 1
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7.2.3.1.2 Leakage Induced by CREVS Operation In addition to the CCHE inleakage resulting from the wind load and stack efects, the operation of the CREVS will introduce some leakage due to the diferential pressures generated within the CCHE. This pressure distribution results in areas of slightly positive pressure due to the discharge firom the ventilation supply ducts and slightly negative pressure due to Bow into return ducts. In the areas of positive pressure, any leakage will be out of the CCHE, which will not contribute to the operator dose. The inleakage that occurs due to flow into the return ducts will be circulated through the CREVS charcoal Alter prior to retuming to an occupied area. The specific distribution of pressure within the CCHE has not been quantified. However, its impact on inleakage was measured as part of the testing performed to quantify the overall CCHE inleakage. During this test, the CREVS was operating so the efect of any CREVS induced leakage was measured as part of the total 462 cfm of measured inleakage. Total Inleakage = Differential Pressure Inleakage + CREVS Induced Inleakage The leakage resulting from CREVS operation is independent of the other CCHE inleakages since it is a characteristh of the ventilation system. The maximum pouible CREVS induced inleakage would result if all of the inleakage measured during the testing was the result of CREVS operation. (i.e. 462 cfin). As modeled by the Murphy-Campe guidance, the CREVS induced inleakage is analogous to return ductwork inleakage and is filtered by the CREVS before it contributes to the control room dose. Therefore the maximum possible contribution, in terms of unfiltered inleakage, from the CREVS operation would be: 462 cfm x 0.05 = 23.1 cfm using the 95% filter effectiveness of the CREVS charcoal filter. Some location specific mixing of the CREVS operation induced inleakage with the CCHE could occur prior to it being filtered. This would have an increased impact on the calculated dose. Therefore to - address this effect and produce a more conservative dose assessment, the value for the unfiltered inleakage due to CREVS operation was assumed to be 125 cfm, approximately 25% of the total-inleakage measured by the testing. This value was directly added to the wind induced inleakage in the dose calculation (i.e., the inleakage determined from the total inleakage measured during the test). In determining the wind induced inleakage, the total inleakage during the test was not retiuced by the assumed CREVS induced inleakage. This approach ensures that the CREVS operation impact is bounded by the dose calculation. (Refs 8 & 11 apply to above discussion.)
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Control Complex Habitability
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. , . . Submittals m Tracer Gas Test Results - November 10,1997 m License Amendment Request #222 - December 5, 1997 ts Justification for Continued Operation, Revision 3 -
December 15,199'7
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Crystal River 3 Steam Generator Tube ! Rupture I 4 h b ) : 1 Florida Power Corp 1 i
Historical Perspective e ' 98' - 34 minu:e e ' 997 - revised isola: ion scenario; FSAR to only s':eam as necessary ciscuss TRACC e ' 989 - revised scenario (fmore FSAR to incluce bouncing) scenario =or t TRACC - Tube Rupture Alternate Control Criteria: moni':ored (TRACC) BWsT inventory, steaming Con':inUous steaming time, oTse levei Florida Power Corp 2
l SGTR Acceptance Criteria i i e Radiological doses < ' O CFR 100:300 rem t1yroid,25 rem whole body e No addi:ional tube failures or degrada: ion of RCS pressure boundary 4 L 4 Florida Power Corp 4
O , e
- SGTR Sequence of Events
.= ;
-=-
e Doub e-encec e Iso ate a'fected gui lo:ine o= one ~:u ae OTSG i= a TRACC e Lea < ra e > makeup !imit is reaclec j e Rx tria on low RCS e Enc o= release (8 aressure (8 mins) 1rs) e HPI ini:ia':es, refills e Cool':0 Cold PZR slutc own (<200F) by DH removal e Coolcown using bot, OTSGs system Florida Power Corp 3
SGTR Raciological Assumptions e 1% defective fuel e 1 gpm leak in unaffected OTSG e Noble gases in RCS coolant transported to secondary are released immediately to environment e 435 gpm constant primary-secondary side leak rate e 10-4 gas-to-liquid lodine partition factor in condenser e 8 hours continuous steaming to condenser t. Florida Power Corp 5
! e. - I SGTR Consequences
- 2-Hour Integrated Dose at EAB l
T1yroid 0.514 Rem Wlole Bocy 0.252 Rem I 30-Day Integrated Dose at LPZ Thyroid 0.017
~
Whole Body 0.016 Florida Power Corp 6 2
l e, .. . . Sample Operational Data Key Parameter l RCS Coolant Activity l e 1993: ~0.04 microCi/cc DE l-131, Mode 1 l e 1994: ~0.05 microCi/cc DE l-131, Mode 1 l e 1995: ~0.03 microCi/cc DE I-131, Mode 1 e 1996: ~0.02 microCi/cc DE l-131, Mode 1 l I e Peak Mode 3 Activity, 1994: 0.48 microCi/cc DE l-131 e Peak Mode 3 Activity, 1996: 0.025 0.48 microCi/cc DE l-131 ITS 3.4.15 Limit: 1.0 microCi/gm Florida Power Corp 8
=. .. .
Comaarisons _ _
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Assumption C R-3 Plant A Plant B Plant C Plant D lodine Spiking No No No No No* Initial Coolant Activity 1% FF 1% FF 1% FF 1% FF 1% FF - 4 Single Failure No No No No No* LOOP (Condenser No No No Yes No* not available) t i i
- Analyses pending considering lodine spiking, single failure, LOOP :
Florida Power Corp 7 -
l Licensinoo Basis o 1974 SER, NRC accepts SGTR analysis with no excep': ions for Single Failure or Off-site power availability l e ' 983 etter to NRC including Updated FSAR
- pursuant to 10CFR 50.71(e), docketed similar i
analysis e ' 994 NRC letter recognizes LOOP coincident with SGTR is not in CR3's design basis j Florida Power Corp 9 i
Crystai River 3 Steam Generator Tube Rupture Florida Power Corp 1 t--- _ _ _ _ _ _ _ _ _ _ .
4-1 Historical Perspective 7, ; e ' 98' - 34 minu':e e 1997 - revised isolation scenario; FSAR to only
- s':eam as necessary discuss TRACC e ' 989 - revised scenario (fmore
=SAR to include bouncing) scenario for t TRACC - Tube Rupture Alternate Control Criteria:
monitored (TRACC) BWST inventory, Steaming Continuous steaming time, oTse ievei
?
Florida Power Corp 2
SGTR Acceptance Criteria
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e Radiological doses < 'O CFR 100:300 rem ~:1yroid,25 rem whole body o No additional tube failures or degradation of RCS pressure boundary Florida Power Corp 4
h . SGTR Sequence of Events e Doua e-enced e Isolate affected guillo':ine of one tube OTSG if a TRACC e Lea < rate > makeup 'imit is reached e Rx trip on low RCS e End of release (8 pressure (8 mins) hrs) e HPI initiates, refills e Cool to Cold PZR shutdown (<200F) by DH removal e Cooldown using system both OTSGs Florida Power Corp 3
SGTR Radiolggical Assumptions e 1% defective fuel e 1 gpm leak in unaffected OTSG e Noble gases in RCS coolant transported to secondary are released immediately to environment e 435 gpm constant primary-secondary side leak rate e 10-4 gas-to-liquid Iodine partition factor in condenser e 8 hours continuous steaming to condenser Florida Power Corp 5
i .. i SGTR Consequences 2-Hour Integrated Dose at EAB T1yroic 0.514 Rem
~
W1 ole Body 0.252 Rem 30-Day Integrated Dose at LPZ Thyroid 0.017 Whole Body 0.016 Florida Power Corp 6
Sam;ie Operational Data Key Parameter RCS Coolant Activity e 1993: ~0.04 microCi/cc DE l-131, Mode 1 e 1994: ~0.05 microCi/cc DE l-131, Mode 1 e 1995: ~0.03 microCi/cc DE l-131, Mode 1 e 1996: ~0.02 microCi/cc DE l-131, Mode 1 e Peak Mode 3 Activity, 1994: 0.48 microCi/cc DE l-131 e Peak Mode 3 Activity, 1996: 0.025 0.48 microCi/cc DE l-131 ITS 3.4.15 Limit: 1.0 microCi/gm Florida Power Corp 8 i
Comaarisons ._ MM. 5 M2P .","M,'M.',M
," ,Th.', mV d'J n,'N- // .b Y'S ) S .E ' ' 56'/d- -' <b b ,N < , a.m . 'b bbh44 ' .NN MM Assum ptio n C R-3 Plant A Plant B Plant C Plant D lodine Spiking No No No No No*
Initial Coolant Activity 1% FF 1% FF 1% FF 1% FF 1% FF l l Single Failure No No No No No* LOOP (Condenser No No No Yes N o* not available)
- Analyses pending considering lodine spiking, single failure, LOOP t
Florida Power Corp 7 E
l Licensing Basis L e ' 974 SER, NRC accepts SGTR analysis with l no exceptions for Single Failure or Off-site aower availability e ' 983 e':':er ':0 NRC including Updated FSAR pursuan~: to 10CFR 50.71(e), docketed similar ana ysis e ' 994 NRC letter recognizes LOOP coincident with SGTR is not in CR3s design basis
; i Florida Power Corp 9 i
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- Submitted
- New Source terms
- Restricted to "
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- Xumbered
- Added -
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4 Sections Appendix "A" = i@,
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et g Discussions ig
- Deleted Tables M..i
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AGENDA- 1 m hij JCO Revision History )t
}v Accident Scenarios - d, q
i u MHA w/ LOOP h MHA w/o LOOP $g
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ji SGTR
!,!j . Dose Summary )y ul Detailed Calc Review .
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w Time Step Unfiltered Filtered Total j r 0 to 8 Hrs 197 125 322 s i! 1 1 1 to 24. Hrs 212 125 337 ; s 1 to 4 Days 233 125 . 358 9,g y; 4 to 30 Days 284 125 409 1 1 1 i-ei 4 Ll Thyroid Dose: 26.5 REM with 22.8 Sq. In" .
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+8 to 9 min: Flow is Out MSRVs and to
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*9 min to 8 Hr: Flow is to Condenser :
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7.2.3.1.2 Leakage Induced by CREVS Operation
- In addition to the CCHE inleakage resulting from the wind load and stack effects, the operation of the
= CREVS will introduce some leakage due to the differential pressures generated vdthin the CCHE. This pressure distribution results in areas of slightly positive pressure due to the discharge from the ventilation supply ducts and slightly negative presrure due to flow into return ducts. In the areas of positive pressure, any leakage will be out of the CCHE, which will not contribute to the operator dose.
The inleakage that occurs due to flow into the return ducts will be circulated through the CREVS charcoal fdter prior to returning to an occupied area. The specific distribution of pressure within the CCHE has not been quantified. However, its impact on inleakage was measured as part of the testing performed to quantify the overall CCHE inleakage. During this test, the CREVS was operating so the effect of any CREVS induced leakage was measured as part of the total 462 cfm of measured inleakage. Total Inleakage = Differential Pressure Inleakage + CREVS Induced Inleakage The leakage resulting from CREVS operation is independent of the other CCHE inleakages since it is a characteristic of the ventilation system. The maximum possible CREVS induced inleakage would result if all of the inleakage measured during the testing was the result of CREVS operation. (i.e. 462 cfm). ! As modeled by the Murphy-Campe guidance, the CREVS induced inleakage is analogous to return ductwork inleakage and is filtered by the CREVS before it contributes to the control room dose. Therefore the maximum possible contribution, in terms of unfiltered inleakage, from the CREVS operation would be: 462 cfm x 0.05 = 23.1 cfm using the 95% filter effectiveness of the CREVS charcoal filter. Some location specific mixing of the CREVS operation induced inleakage with the CCHE could occur prior to it being filtered. This would have an increased impact on the calculated dose. Therefore to address this effect and produce a more conservative dose assessment, thc value for the unfiltered inleakage due to CREVS operation was assumed to be 125 cfm, approximately 25% of the total ir. leakage measured by the testing. This value was direct'y added to the wind i nduced inleakage in the dose calculation (i.e., the inleakage determined from the .otal inleakage measured during the test). In determining the wind induced inleakage, the total *nleakage during the test was not reduced by the assumed CREVS induced inleakage. This apr ioach ensures that the CREVS operation impact is bounded by the dose calculation. (Refs 8 & 11 appl to above discussion.)
POST-MAR
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,A i Rev 3 -
Rev 42 Revi5 le . ij j
- Submitted
- New Source terms
- Restricted to 3 p; Dec.15 for FHA & SGTR Below Mode 2
" I[
din
- Numbered
- Added j '
Sections Appendix "A" g i
..
- Expanded :
f! Discussions ; ee
- Deleted Tables :
l]l 2 Re: SGTR w
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Control Complex Habitability li= (i- Envelope (CCHE) AGENDA )j JCO Revision History : {f{ (fj! l Accident Scenarios i i I . MHA w/ LOOP. & lh[ 4 MHA w/o LOOP {s l m 4 y FHA !) 1 fd SGTR ha 2';jj d :4 h, Dose Summary j; g g Detailed Calc Review <g.t 2 i l$ 2 9g bh .+ N d'u?'
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*CREVS Isolates on 4 psig in RB j!!
! A 4 *CREVS Filtration starts within 30 minutes c r
.ABVS is not operating j:d b; 7
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i 7.2.3.1.2 Leakage Induced by CREVS Operation in addition to the CCHE inleakage resulting firom the wind load and stack effects, the operation of the
- CREVS will introduce some leakage due to the differential pressures generated within the CCHE. This i
- pressure distribution results in areas of slightly positive pressure due to the discharge from the ;
l ventilation supply ducts and slightly negative pressure due to flow into return ducts, in the areas of 1 positive pressure, any leakage will be out of the CCHE, which will not contribute to the operator dose. The inleakage that occurs due to flow into ad return ducts will be circulated through the CREVS ; ) charcoal filter prior to returning to an occupied area. ' j- The spwific distribution of pressure within the CCHE has not been quanti 6ed. However, its impact on i < inleakage was measured as part of the testing performed to quantify the overall CCHE inleakage.
- During th!
- test, the CREVS was operating so the effect of any CREVS induced leakage was measured i j i.s part of the total 462 cfin of measured inleakage.
Total Inleakage = Differential Pressure Inleakage + CREVS Induced Inleakage !
- The leakage resulting from CREVS operation is indepndent of the other CCHE inleakages since it is a
- characteristic of the ventilation system. The maximum possible CREVS induced inleakage would result
! If all of the inleakage measured during the testing was the result of CREVS operation. (i.e. 462 cfm). As modeled by the Murphy-Campe guidance, the CREVS induced inleakage is analogous to retum # l ductwork inleakage and is filtered I .he CREVS before it contributes to the control room dose. Therefore the maximum possible contribution, in terms of unfiltered inleakage, from the CREVS operation would be: l 462 cfm x 0.05 - 23,1 cfm using the 95% filter effectiveness of the CREVS charcoal filter. l Some location specific mixing of the CREVS operat$on induced inleaksge with the CCHE could occur ; i prier to it being filtered. This would have an increased impact on the calculated dose. Therefore to l address this effect and produce a more conservative dose assessment, the value for the unfiltered
; inleakage due to CREVS cperation was assumed to be 125 cfm, approximately 25% of the total ;
j inleakage measured by the testing. , This value was directly added to the wind induceo inleakage in the dose calculation (i.e., the inleakage l determined from the total inleakage measured during the test). In determining the wind induced L inleakage, the total inleakage during the test was not reduced by the assumed CREVS induced , ! inleakage. This approach ensures that the CREVS operation impact is bounded by the dose calculation. l- (Refs 8 & 11 apply to above discussion.)
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- -1 Refs:
SER for Amnd 145 re: TSP
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JCO Revision Summary j m m . j
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i w Rev 3 Rev 4 i ~
. lRev 5 3 g1
- 9 a Submitted
- New Source terms
- Restricted to q
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Dec.15 for FHA & SGTR Below Mode 2
/
- Numbered a!!
- Added .
S~ L. . Sections Appendix "A" -
;
- Expanded 3-
= i Discussions 4ll t 1
- Deleted Tables il l !
Re: SGTR
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Li Accident Scenarios 3 m l
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7.2.3.1.2 Leakage Induced by CREVS Operation In addition to the CCHE inleakage resulting from the wind load and stac'c effects, the operation of the j CREVS will introduce some leakage due to the differential pressures gere, rated within the CCHE. This pressure distribution results-in areas of slightly positive pressure du to the discharge Gom the ventilation supply ducts and slightly negative pressure due to flow ir.o retum ducts. In the areas of positive pressure, any leakage will be out of the CCHE, which will nr, contribute to the operator dose. The inleakage that occurs due to flow into the return ducts will W circulated through the CREVS l charcoal Siter prior to returning to an occupied area.- l 1 - 1 The specific distribution of pressure within the CCHE has not been quantified. However, its impact on i a inleakage was measured as part of the testing performed to quantify the overall CCHE inleakage, During this test, the CREVS was operating so the effect of any CREVS induced leakage was measured
- as part of the total 462 cfm of measured inleakage.
1 Total Inleakage = Differential Pressure Inleakage + CREVS Induced Inleakage The leakage resulting from CREVS operation is independent of the other CCHE inleakages since it is a
- characteristic of the ventilation system. The maximum possible CREVS induced inleakage would result
- if all of the inleakage measured during the testing was the result of CREVS operation. (i.e. 462 cfm).
I As modeled by the Murphy-Campe guidance, the CREVS induced inleakage is analogous to return ) ductwork inleakage and is filtered by the CREVS before it contributes to the ccv trol room dose.
- Therefore the maximum possible contribution, in terms of unfiltered inleakage, from the CREVS
- operation would be
- 462 cfm x 0.05 = 23.1 cfm ,
using the 95% filter effectiveness of the CREVS charcoal filter.
- Some location specific mixing cf the CREVS operation induced inleakage with the CCHE could occur 2
prior to it being filtered. This would have an increased impact on the calculated dose. Therefore to 4 address this effect and produce a more conservative dose assessment, the value for the unfiltered l inleakage due to CREVS operation was assumed to be 125 cfm, approximately 25% of the total j- inleakage measured by the testing. This value was directly added to the wind induced inleakage in the dose calculation (i.e., the inleakage determined from the total inleakage measured during the test). In determining the wind induced inleakage, the total inleakage during the test was not reduced by the assumed CREVS induced inleakage. This approach ensures that the CREVS operation impact is bounded by the dose calculation. (Refs 8 & 11 apply to above discussion.) 9 W.
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