ML19249E870
| ML19249E870 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/10/1979 |
| From: | Stahle C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910020642 | |
| Download: ML19249E870 (16) | |
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p UNITED STATES l } ) #g ' gg NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 SEP 101979 Docket Nos:
50-424 50-425 FACILITY:
Alvin W. Vogtle Nuclear Plant, Units 1 & 2 APPLICANT:
Georgia Power Company
SUBJECT:
SUMMARY
OF HEETING ON REMOVAL 0F ENCLOSURE BUILDING FOR ALVIN W. V0GTLE NUCLEAR PLANT, UNITS 1 & 2
Background
At a meeting on August 8,1979, representatives from Southern Company Services / Georgia Power and the staff discussed the removal of the enclosure building from the Vogtle nuclear power units. A list of attendees and an
. outline of the applicant's presentation are enclosed.
The containment for each of the units, as presently described in the PSAR, is a double containment system.
It consists of a prestressed concrete, steel-lined, cylindrical structure, called the containment, and a steel-framed structure, called the enclosure building, which completely encloses the containment. The primary purpose of the enclosure building is to limit releases to the environment of radioisotopes which may lead from the contain-ment into the enclosure building under accident conditions. The enclosure building and its associated filtration and vent system functions as follows:
a.
The enclosure building atmosphere is exhausted to the environment through high efficiency particulate filters and charcoal filters to remove airborn radioactivity and to maintain a negative pressure within the enclosure build-ing.
This negative pressure ensures inleakage from the atmosphere to the enclosure building, preventing direct exfiltration of radioactivity to the environment.
b.
Multipass filtration of long term containment leakage by recirculation of a portion of the filtered air to improve fission product cleanup.
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1070 117
. c.
The design of the air distribution systems provides a minimum of 50 percent mixing in the space air. Mixing between 220 feet to 270 feet level is obtained through 40 air jets discharging vertically downwards from 267 feet level. These jets are located approximately 6 feet apart, center to center.
Each jet will entrain air from surrounding air.
During summer, warm air will tend stagnate near the top of the enclosure. Air is ducted from the top by two blowers of 9000 cfm each forcing air from below to rise into the annular space between the enclosure containment.
The 18000 cfm gives one air change per hour for the space above 270 foot level.
Summary The purpose of the meeting was to inform the staff of construction changes that are now taking place in the containment system; and to show that the design / construction changas meet all our requirements. Tne applicant stated that they were proceeding with modifications which remove the enclosure building above the 270 foot level and deletion of the building filter and exhaust system as described in the PSAR. A simple non-safety ventilation system will be installed. This modification deletes a safety function which was a consideration in the staff's review of the Vogtle engineered safety features at the time the construction permits were issued.
The new enclosure building is a group of steel-framed st.ructures with uninsulated metal siding and roof deck.
ealant requirements for this portion of the enclosure building are di ed. The enclosure building surrounds the containment from grade to the 270 foot level. There is no safety function, except that its failure will not damage safety-related equipment. The safety related equipment located within the new enclosure building is protected from tornado missiles.
The applicant asserted that the containment system changes mcet all our requirements. The bases for such a statement is the results of their re-analysis of possible radioactivity released to the environment in the event of a loss-of-coolant accident which show calculated doses do not exceed guideline values specified in 10 CFR 100. The analysis uses Regula-tory Guide 1.4, revision 2 and other approp:*iate current Regulatory Guides and criteria.
Assumptions used to calculate doses, calculate spray lambda for elemental iodine, and dose conversion factors were presented. A summary of the applicant's results are enclosed which were a part of their presentation. Also a draft of a supplement to the PSAR was provided.
1070 118
. The staff did not disagree with the applicant's analysis; however, it was stressed that we would perform an independent analysis to confirm their findings. There was a difference of opinion on the significance of the design changes.
A safety function has been deleted and the plant is not as conservative as described in the present PSAR.
We will assess the significance of this change in the near future.
Carl Stahle, Project Manager Light Water Reactors, Branch #4 Division of Project Management Enclosures :
1.
List of Attendees 2.
Applicant Outline of Presentation cc: See next page 4
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Georgia Power Company ccs:
Mr. I. S. Mitchell, III Mr. W. E. Ehrensperger Vice President and Secretary Senior Vice President Georgia Power Company Power Supply P. O. Box 4545 Georgia Power Company Atlanta, Georgia 30302 P. O. Box 4545 Atlanta, Georgia 30302 Mr. Ruble A. Thomas Vice President Southern Services, Inc.
P. O. Box 2625 Birmingham, Alabama 35202 Mr. J. A. Baily Project Licensing Manager Southern Company Services, Inc.
P. O. Box 2625 Birmingham, Alabama 35202 George F. Trowbridge, Esq.
Shaw, Pittman, Potts ar.d Trowbridge 1800 M Street, N. W.
Washington,D. C.
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1070 1t0
LIST OF ATTENDEES Southern Company Services
- 1. A. Bailey R. A. Thomas H. S. Anderson D. Dutton H. Majors Pickard, Lowe & Garrick T. Potter Westinghouse K. Rubin J. C. Connor J. L. Vota L. E. Elder Bechtel T. G. Wineteer B. L. Lex D. S. Jagannathan J. H. Bell S. J. Cereghind NRC C. Stahle - DPM D. Vassallo - DPM S. Varga - DPM L. Soffer - AAB L. Brown - HMB E. Markee - HMB D. Picket - CSB 1070 121
2 A \\
s GEORGIA POWER COMPANY ALVIN h'. VOGTLE NUCLEAR PLANT UNITS 1 AND 2 i
i REMOVAL OF ENCLOSURE BUILDING ABOVE 270 FT. LDTL AND i
DELETION OF ENCLOSURE BUILDING i
i FILTER AND EXHAUST SYSTEM i
AUGUST 8, 1979 I
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SUfeiARY OF EFFEC'.S ON DESIGN _
A.
. Safety function deleted New design simply deletes upper portion of E.B. which B.
is supported by containment.
Design of lower porLlon and roof deck remains unchanged C.
with exception of sealant requirements deletion.
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CONSERVATISM IN PL7EP DESIGN o
No credit taken for filtration of containment leakage r
,All penetrations are contained within EB, FHB, AB, CB o
o Electrical and Piping Penetration Filter Exhaust Systems are safety-related and coverage is not changed.
o 85% of penetrations are included within safety-t related negative pressure and filtration boundary.
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1070 125
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ASSltFTIONS USED TO CALCOLAE DOSES GR0diD l.EVEL ELEASE - EG, GUIE 1,4 X/0 SEC#f EG, GUIE 1,XXX BASIS 2-E 8-24 24-96_
96-720 SIE BOUNDARY
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6,3(-5) 3,2(-5) 2,2(-5) 1(-5) 3,3(. )
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WHERE1,6(-4)=1,6x10 BEAllilWG RATES Ff/SEC - R G,1,4 3,47(-4) 3.47(-4) 1,75(-4) 2.3(-4) 2,32(-4)
DOSE CONVERSION FACTORS EWCURIE ER EG, GUIE 1,109 I131 1,49(6)
I B2 1.43(4)
I 133 2,69(5)
I134 3,73(3)
I135 5,6(4) 1070 126
f ASSulPTIGIS USED TO CALCULATE SPRAY LAPDA FOR ELBEHAL 10 DIE SPRAY FALL EIGHT 130 FT 5
COEAlifEE VOUfE 2,750,000FT SPRAY FLOW RATE 2,600ees 0
N0fFAL CURAlifEE EFERATUE 120 F ACClibiT C0EAllfBR WPERATUE 271 F 0
SPRAY EFERATUE 120F SPRAYPH 9,8 PLAR POWER 3,565 mr LOG I40fFAL DROP DISTRIBUTIQ1 10/0 127
ASSLFFTIQ4S USED TO EVALUATE RADI0 ACTIVITY ELEASES FOR A LOSS OF ACC EGul.ATORY GUIDE 1,4, EVISIQ12 BASIS -
(filFORi MIXING Gi FISSIGi PRDIKTS 100 PCT OF CORE NOBLE CASES AND 25 eCT OF COE 10 DIE AVAILABLE FOR ELEASE FROM CONTAlifENT C0iTAlifENT LEAK RATE 0-24 ms,100 PCT OF DESIGN (0,3%/ DAY) 24 ms, 50 PCT OF DESIGN (0,15%/ DAY)
DISTRIBlHIONOFIODINE 91 PCT ELEMENTAL 4 PCT ORGANIC 5 PCT PARTICULATE MINIMUM SAFEGUARDS FA'1 COOLERS - 85,000 CFM 3
SPRAYED CGUAlifEliT V011E - 2,145,000 FT ELEFENTAL IODINE L#BDA --20,5 #1 ELBEiTAL 10 DIE DF - 100 FOR ENTIRE VOLUME PARTICULATE l#BDA - 0,5 il PARTICULATE DF - 100 FOR SPRAYED VOLUME 10/0 128
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COMPARISON OF DOSE CALCULATION RESULTS (REM)
LIMITS SER,(W/EB)
ESTIMATE New VNP CP OL Site Boundary Thyroid 0-2 hr 122
>200 93 150 300 Whole Body 0-2 hr 7
7.4 20 25 Low Population Zone Thyroid 30 Day.s 70 103 150 300 Whole Body 30 Day 8
5.5 20 25 e e 1070 129 4
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0 (Cont)
Description 'of Lower Portion bf Enclosure Building 'and Foof Deck Equipment Located Within Enclosure Building E.
o 220 Ft. Level CTB post-LOCA purge exhaust unit CTD purge exhaust unit Personnel lock Radiation monitoring station l
Equipment access hatch Tendon Gallery ran o
232 Ft. Level i
CTB purge supply unit F.
Ventilation Scheme for Enclosure Building s-o Simple ventilation plan o
No air conditioning i
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1070 130 k
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VNP CONTAINMENT PENETRATION VALVE ARRANGEMENT LOCATION
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VALVE TYPE NO.
SYSTEM ELEVATION AZIMUTH ~
FUNCTION SIZE
' INNER OUTER ~ ~
FLU 10 1
MAIN STEAM 229'-6" 180 STEAM HEADER 27-1/2" G ATE (2) ~
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MAIN STEAM 229'6" 00 STEAM STEAM HEADER 27-1/2" GATE (2)
STEAM 3
MAIN STEAM 229'-6" 08 STEAM HEADER 27-1/2" GATE (2)
STEAM 4
MAIN STEAM 229'-6" 180 STEAM HEADER 27-1/2" G ATE (2)
STEAM 8
18 FEE 0 WATER 202'-6" 0
FEED HEADER 16" CHECK SECONDARY 0
19 FEE 0 WATER 202'-6" 9 /3 48" FEED HEADER 16" CHECK SECONDARY 8
COOLANT i
20 FEE 0 WATER 202'6" 180 FEED HEADER 16" CHECK SECONDARY 8
COOLANT 21 FEE 0 WATER 202*6" 0
COOLANT 170 16'12" FEED HEADER 16" CHECK SECONDARY 28 ACCW 209'10" 184 51'-54 "
SUPPLY 10" BUTTERFLY BUTTERFLY DEMIN 8
COOLANT 29 ACCW 209'10" 182 55'57" RFTURN 10" BUTTERFLY BUTTERFLY DEMIN l
0 WATER t
42 SAFETY 202'-8" 182 25'-57" 8
WATER N SUPPLY TO 1"
CHECK GLOBE N2 INJECTION 2
ACCUMULATOR 83 CTB PURGE 240' 70" 32'-24" SUPPLY 24" BUTTERFLY
- BUTTERFLY
- CTS j
84 CTB PURGE -
240' 301 37'-18" EXHAUST 24" BUTTERFLY
- BUTTERFLY
- C18 0
ATMOSPHERE 100 POST-LOCA PURGE 264' 184 51'-54" EXHAUST 4"
BUTTERFLY BUTTERFLY CTB 8
ATMOSPHERE GLOBE ATMOSPHERE
- ISOLATED BY 24" PREACCESS PURGE VALVE AND 14" MINI PURGE VALVE.
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O 1070 131
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COMPARISON OF X/Q VALUES i
X/Q VALVE NETEOROLOGICAL 1-HOUR AVERAGE DOCUMENT DATA BASE SITE BDRY PSAR (RG 1.4)
SRL 3.4E-4 NRC Ser ("O 1.XXX)- R G l. '\\
Site 1972-1974 2.8E-4 Present Submittal (RG 1.XXX)
Site 1977-1978*
1.6E-4
- Site data 1972-1974 gii.res same results a
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MEETING
SUMMARY
DISTRIBUTION SEP 101979 s
H. Denton dDo ket File 2
=
Local PDR TIC NRR Reading Branch File #4 E. Case D. Bunch H. Berkow D. Ross D. Vassallo W. Gammill J. Stolz R. Baer
- 0. Parr S. Varga C. Heltemes L. Crocker D. Crutchfield F. Williams R. Mattson R. DeYoung Project Manager C. Stable Attorney, ELD M. Service IE (3)
ACRS (16)
R. Denise L. Rubenstein NRC
Participants:
L. Soffer L. Brown E. Markee D. Pickett B. Kirschner R. Houston L. Hulman W. Butler t