ML19345A805
| ML19345A805 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/13/1975 |
| From: | Johnson W YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WYR-75-86, NUDOCS 8011250233 | |
| Download: ML19345A805 (13) | |
Text
._ __
Proposed Changa !!o. 127 1
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Telephone 617 366-90ll
- E.._IL3 COPY 750-390-0739 l
YANKEE ATOMIC ELECTRIC COMPANY urR,5-8s
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y 20 Turnpske Road Westborough, Massachusetts 01581
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x August 13, 1975 J
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United States Nuclear Regulatory Commission Washington, D. C.
20555 s
i Attention: Office of Nuclear Reactor Regulation i.
Reference:
(1)
License No. DPR-3 (Docket No. 50-29) i (2)
Proposed Change No. 112, Revised Technical Specificaticns and Final Safety Analysis Report submitted January 3, 1974
Dear Sir:
Pursuant to Section 50-59 of the Commission's Regulations, Yankee Atomic Electric Ccmpany hereby requests to make the following changes:
PRCPCSED CHANGE: Yankee proposes the following changes to the plant ventilation systems:
Installation of a filtration system to remove airborne radioactive particulates and iodine in the exhaust air frca potentially centaminated areas in the Plant before it is discharged to the environment from the primary vent stack.
The modifications shall include the necessary ductwork system and fans to convey the exhaust air to and frcm high efficiency filter assemblies.
PIASON FOR CHANGE: The exhaust air ventilation systems for the primary auxiliary building, waste disposal building, fuel building and vapor container at Yankee Rowe have no provisions for filtering the air before being dis-
. charged to the environment. The proposed modifications demonstrate Yankee's cornitment of maintaining all radioactive releases to the environment "as low as practicable".
l DESCRIPTION OF CHANGE:
1.
The air exhaust from the Waste Disposal Building (WDB) and Spent Fuel Pool Building (SFPB) have been ducted to the mechanical equipment room #3 where they are combined with the exhaust air efg p y from the Primary Auxiliary Building (PAB).
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'#3heairisthenfilteredbya23,000CFMfilterassemblyconsisting
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'of'prefilters, charccal and HEPA's.
The charcoal section of the
,.,q'[eremoveradioactiveiodine.
ali mbly consists of eighteen (18) vertically oriented beds which
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^y Each bed actually has two distinct parts;
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8011250 2 3 3 h
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United States Nuclear Regulatory Commission August 13, 1975 Attn: Office of Nuclear Reactor Regulation Page Two a one (1) inch thick guard bed and a four (4) inch thick primary bed.
Both are independent of each other, consequently,' the charcoal in either can be replaced without effecting the other. The-purpose of the one (1) inch guard bed is to redcce the replacement frequency of the four (4) inch primary bed.
The guard bed is normally filled with unimpregnated charcoal and the primary bed is filled with impregnated charcoal. The HEPA filters remove radioactive airborne particulates with an efficiency of 99.97 percent or better.
2.
The vapor container ventilating and purge air exhaust system is filtered by an identical filter assembly, also located in the mechanical equipment room. Because they are identical, either-assembly can be used to filter the PAB/WDB/SFPB or the containment.
In addition, both systems can be operated simultaneously.
3.
Each system has its own fan. Because both fans c e identical and their suction ductwork is cross-connected, either fan can be used in conjunction with either system.
4.
Various air and gaseous vents, ranging in size from one to four inches which are presently piped to the exhaust fan suction shsll be repiped so the vented gases are filtered before they are dir-charged. The vents emanate from the condenser air ejector, wasre disposal system and vapor container.
5.
Replace the attached below listed pages and figures appearing in the Final Hazards Summary Report (FHSR) :
Pages:
209:1, 209:6, 209:8, 209:10, 216:1, 228:3, 228:4.
Figures: Stone ar.d Webster Flcw Diagram, Radioactive Waste Disposal, 9699-RM-41F following page 209:12 in the FHSR.
Stone and Webster Drawing, Air Cooling and Purging System - Arrangement Vapor Container, 9699-FB-3H following page 216:1 in the FHSR.
Stone a.-d Webster Drawing, Fuel Transfer Pit, 9699-FM-21A following page'218:7 in the FHSR.
Stone and Webster Flow Diagram, Circulating Water,
. Screen Wash and Air Offtake Lines, FM-10A following page 221:1 in the FHSR.
Stone ad Webster 480V One Line Diagram, 9699-FE-lD, following page 226:1 in the FHSR.
Stone and Webster 480V Cne Line Diagram, SH2, 9699-RE-lF following-page 226:1 in the FHSR.
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a jj United States Nuclear Regulatory Commission August 13, 1975 Attn: Office of Nuclear Reactor Regulation Page Three 29 6.
Replace the attached below listed pages and figures appearing in the Final Safety Analysis Report (FSAR), Reference 2.
Pages:
9.4-1, 9.4-2, 11.2-1, 11.3-1, 11.3-3, 12.2-1, 12.2-2 and 16.4.17-2.
Tables:
11.3-2, 11.3-3 Figures:
6.2-8, 10.4-2, and 11.2-1, 11.3-1 SAFETY CONSIDERAT.!ONS: The proposed change does not present any significant hazards consideradion not described or implied in the reference license as amended.
The prorosed change has been reviewed by the Nuclear Safety Audit and Review Committee.
SCHEDULE OF CHANGE:
The above described propoced change will be accomplished
{
prior to our Octoboc, 1975 refueling period.
We trust you will find this information satisfactory; however, should you desire additional information feel free to contact us.
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,1 Respectfully submitted, I
YANKEE ATOMIC ELECTRIC COMPANY Wbr-, /^ irdnt W. P.
hnson Vice resident col'MONWEll.TH OF MASSACHUSETTS)
)ss.
COUNTY OF WORCESTER
)
Then personally appeared before me, W. P. Johnson, who being duly sworn,
- did state that he is a Vice President of Yankee Atomic Electric Ccepany, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company, and that the' statements therein are true to the best of his knowledge and belief.
t
,M dW c,
/
Armand R. Soucf Notary Public My Commission Expires September 9, 19T
209:1 Draft 209 RADIOACTIVE WASTE DISP] SAL SYSTEM General The waste disposal system receives, contains, adequately treats and safely disposes of all radicactive wastes ether than certain separately handled low activity wastes which may come from the secondary plant. The basic processes used in this system are:
natural decay of radioactive is,otopes, filtration to remove most of the radioactive particulate matter, evapora~ tion to concentrate radioactive constituents in a small volume of liquid waste to be solidified in concrete, incineration to concentrate activity in a reduced volume of solid wastes, filtration by charcoal and HEPA filters, and dilution of low activity liquid and gaseous discharge.
It is the objective to operate the nuclear plant and the waste disposal system in such a manner as to maintain a balanced water inventory in the waste disposal tankage, such that little or no purified liquid waste discharge from the plant is necessary.
This will be accomplished by recycling purified water to primary plant make-up.
Small surplus amounts of
' purified water, together with certain liquid wastes from the secondary plant, will be diluted with condenser cooling water and discharged, as they occur.
The waste disposal system consists of liquid and gas storage tanks, gas stripper, evaporator, incinerator, wet gas scrubber, pumps, compressors, heat exchangers, filters, instruments, piping and valves, all as shown on drawing No. 9699-RM-41F.
Although not a part of the waste disposal system, certain waste systems of the secondary plant are discussed in this section so that all wa.ste handling methods are described in one place.
The potential sources of radioactive liquid and gaseous wastes to be proc.essed by the waste disposal system are as follows:
bbin Coolant System Charging and Volume Control System Purification System Sampling System Chemical Shutdown System Vent and Drain System Shutdown Cooling System Vapor Container D, rain Liquid Safety Injection - Shield Tank Cavity Sy. stem Radioactive Laboratory, Decontamination Cubicle and Decontamination Pad Drain Liquids Contaminated Laundry Drain Liquid (If or. site laundry installed in future)
Contaminated Area Floor Drain Liquid Steam Generator Drain Liquid
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209:6 Draft Process,ed liquid wastes from the waste disposal system will be discharged only if the activity contained therein, in combination with any activity being released from the steam generator blowdown, is within the maximum permissible concentration, after dilution, which is established in AEC Regulations, Part 20.
Although it is planned to have all contaminated' clothing laundered under contract by a commercial laundry, all necessary facilities are provided for handling the waste liquids from an on site contaminated laundry. This will permit the installation and use of laundry equipment in the Service Building if this becomes necessary in the future.
The total volume of contaminated area floor drains and other miscellaneous drains cannot be determined.
However, it is expected that these liquids will consist of small and infrequent batches of low activity fluids.
Processed Gaseous Wastes The processed gaseous wastes consist almost entirely of hydrogen and radioactive fission product gases which are dissolyed in the liquid discharged to waste disposal, or which continuously leak through or are released inter-mittently to the primary drain collecting tank by the pressure control valve on the low pressure surge tank.
Fission gases and hydrogen are coll a ted from the distillate accumulator and from the vapor space of all reactor effluent liquid drain and hold-up tanks in a completely closed waste gas header system.
This is corpressed to a. gas surge drum, which is bled back to th'e compressor suction to maintain a constant pressure on the waste gas header and.a cushion to permit filling and emptying of tanks.
Initially, this system will be filled with nitrogen and this atmosphere may be maintained indefinitely at the option of the operator.
The net gas make collects gradually in the waste gas surge ' drum and is removed once each month from the compressor discharge line and stored under pressure in one of the three gas decay drun.s for about 60 days to reduce the activity. The decayed gas discharged from a gas decay drum is passed through a deep bed particulate filter and then released at a carefully controlled rate to either of two exhaust ventilation system filter. banks consisting of prefilters, charcoal and HEPA's. The primary auxiliary building filter train is normally used, however if this train becomes inoperative, the vapor container ventilation and purge train can be used.
Interlocks are'provided to shut off, automatically, the flow of waste disposal gas if either fan stops. After filtration, the decayed gas and exhaust ventilation air are discharged to the atmosphere from the primary vent stack.
The stack gases are continuously monitored. The processed gaseous waste equipment is designed and sized to accommodate the
. maximum expected activity emanating from the main coolant. Dilution is -150 provided so that all gaseous effluent accumulated during a period of ceni..aous plant operation can be discharged at acceptable' concentration during two-thirds of the hours in that period. This provides operating flexibility and allowance for equipment maintenance.
.209:8 Draft e
.In the ense of vaste disposal plant operation alone, and when a'veragi6s concentrations over a period of,one month or one year, the ITC
. calculated for continucus.crposure in an unrectricted area may be incroaced by a fe.ctor of 15, cince radioactive air is to be discharged only 20 out of every 30 days of plant operation. This givcc a corrected ITC in the air diccharged from the stack of h.5 x 10-7 nicrocuric per ml for krypton-85 or for xenon-133 Baced on the intermittent diccharge o'f a mixt.ure of air and radi'o-active krypten-85 and xenen-133 to the -cuction of cither.the Prinary Auxiliary Building exhaust fan or the vapor container purgo fan, the voluzec
.and activit) 1cvels of r >ccous vaste, assuming. cladding defects in If, of all fuel reds, are as fo1.wus:
Average volume of gaseous vastes, 20i -
scf par.nonth Average gross activity of gaseous vastes:
At zero decay, nicrocurie per n1 80.1 I.31 At 60 days decay, microcu-ie per ml 8
4 Discharge rate of decayed caseous vastes, OIG sof per hr*
Air dilution volume, cfm 23,000~.
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Averasc grocs activity 'of air discharge from the stack, nicrocurie per cl 1.35 x,10-6 Total activity dischar6ed to.t' e atmos-h phere, curie per ucnth 25 2 Total volume of radioactive ' krypton-65 icleased, ml per = cath 16.2 The air discharged from the stack during a 20 day period has a gross activity level about one-fifth that permitted by the AEC Regulations for mir.ed identified icotores in a restricted area.
In order to satisfy the AEC preposed ITC of 4 5 x 10-7 nicrocurie per ml for discharge two-thirds of the total time in an unrcotricted area, an additional dilution factor of c. bout h.6 is required.
Since the decayed gas.is being emitted at 26 fps, the dilution by entrain =cnt above the stack gives the required dilution, with vind speeds less than 10 fps, without recorting to the atmospheric diffucion away frcm the sourec.to produce the dilution. At vind opced: in execco of-10 fps, the turbulent atmosphere provides a di-lution facter of 5 vithin 30 ft of the stack. The formulae in Section 301, l' TEOROLOGy, show that the expected ma::imum ground level concentration, E
with vind. cp2eds of 10 ' fps, and an effcetive ctack heicht of 150 ft, is of the order.of 1/3,000 :h of the concentration at the top of the stack; i.e.,
a dilution factor of 3,000.
- Based on discharging decayed gas 20 days out of every 30 days-
. of p3 ant opciation.
u POOR 3EGMAL
209:10 Draft The analysis of the leakage hazard is based on the split of volatile and nonvolatile main coolant activitics given in Section 106 and max $m:n permissible cendentrations (??C 's) of radioisptopas appearing in the current text cf Al:0 Reculation 10, CIG Pa'rt 20.
17C 's for isotop:s not appearing in the current text are.obtained from the proposed amendment to Part 20.
Uhere the MPC for the soluble and insoluble forms of an iso-tope differ, the more rostrictive fenn is assumed.
No credit is taken for radioactive decay of nonvolatile isotopes during stcaa concrator holdup.
- Two general criteria for 16C's are used.
One set of criteria for mixtures of unidentified isotopes is used as a basis for selecting set points for continuous radiation tenitoring equipment. A second, less restrictive cet of criteria nay be ured after periodic scmplina and iso-topic determinations of steam Generator blowdown and air ejector effluent to permit.= ximum discharge rates consistent with 10 CIR Part 20.
The following IGC criteria are established to provide a basis
~ for continuous monitoring.
For " unrestricted area" vater-borne activity consisting a.
s of " unidentified beta or ga=a' emitters or any undetemined mixtures of beta c.
ca=a critters":
1.x 10-l/(c per ml at the circulating vr.ter discharce to Sherman Pond.
Steam concrator blevdown menitor clarm set points vill be established based on the availability of approximately 138,000 cpm of condenser circulating vate'r for dilution s
purposes which vill be assuacd to ecntain no natural or l
fallout activity. This dilution is less.than Sher =an Pond inflow during 1941, the driest recorded year, 'vhich averaged over 200,000 cym.
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. For "tinrestricted arca" air-borne activity consisting of b.
" unidentified beta or gar:r.: cmittcIs or any undetermined mixtures of beta or Ca=a emitters": 1 x 10-9 e per ml at the closest unrestricted area.
The air ejector effluent =cnitor alarm set point vill be j
cstablished based on tha availability of approximately g.
23,000 cfm of primary auxiliary building exhaust fan or I
vapor container purge fan capacity for dilution purposes which vill be assumed to contain no natural or fellout activity.
In additien, a dilaticn factor of 1,000 vill be assumed to be. available frca the '. top of the primary vcat stack to the closest unrestr.cted arca.
Smo):e tests per-romad under the most unraverabic acteorolo31 cal conditions -
that is, with a temperature inversion and licht novn-valley vinds - indicate that a dilution factor of approximately
.5,000 may be expected. These smoke tests are discussed on
' paces 301:3, 301:4, and ho3:7 PDORDE M AL i
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216:1 Draft I
216 VAPOR CONTAINER ATMOSPHERE CONTROL SYSTEMS General The vapor container is a spherical steel envelope designed to contain
^
all vapors, gases, liquids, and solid materials which may be the result of leakage from the primary system.
The atmosphere control systems limit the vapor container temperature to a minimum of 50 F in the winter' and 1200F during summer operation and will remove the airborne radioactivity during operation and after shutdown to facilitate refueling and maintenance operations. The systems are shown on drawing No. 517-F-417.
Ventilation to Outside Atmosphere Some airborne activity may still be present in the vapor container air after depressurizing the main coolant system. The ventilation and purge system reduces the activity levels in the vapor container to allow personnel access.
The purge system capacity is based on the radioactivity in the air of the vapor container at the time the main coolant system is depressurized.
This system filters the vapor container air until the concentration of airborne activity is reduced to tolerance IcVels as prescribed by the AEC Regulations (10 CFR Part 20).
Outside air is delivered into the vapor corJsiner through an air supply unit (consisting of filters and heating coils), fan and interconnected ductwork.
The exhaust air from the vapor container passes through a high efficiency filter assembly (consisting of prefilters, charcoal and HEPA's) before being discharged a the primary vent stack. Normally closed valves are provided at the vapor c,ntainer, to be opened only after the primary plant has been depressurized.
The air filters, heating coils, and exhaust fan are located in the machanical equipment room of the Primary Auxiliary Building. The inlet fan for the vapor i ontainer is located on the roof of the P. A. Building.
The supply and exhaust air valves are located at the container.
Tto valves, one 8 in, and one 30 in., are provided in the exhaust duct I
for control of the exhaust air rate. The air leaving the vapor container is I
discharged to the atmosphere through the prinary vent stack located betacen the Primary Auxiliary Building and the vapor container.
l The components of the ventilation system are shown on drawing No. 517-F-417.
I Recirculation, Heating and Cooling Heat released during plant operation from hot insulated and uninsulated l
surfaces, together with solar radiation, contribute to the heat gain of the vapor I
container air. The vapor container is completely sealed from the natural atmosphere and no air, other than that which leaks from the container and is replaced by the Icakage monitoring system, enters or 1 caves the container during operation. The v,entilation system cooling units limit the air temperature inside the container to values which will prevent damage
_.44
_m 228:3 Draft Roof exhaust fans are provided for summer hect removal for the machine shop and water treating plant.
Outdoor air for ventilation of the machine shop is drawn through open windows and doors and for the water treatment plant through louvered openings in the exterior wall.
Summer ventilation for plant stores, service office and contaminated instrument room is by natural means through open windows.'
The unit ventilator and air conditioning equipment for the supply air-are located in mechanical equipment roon No. 1 above the Service Building roof.
This room also houses the decontamination cubicle exhaust fan as well as water heating equipment, hot water heating system heat exchanger, expansion tank and circulators. The techanical equipment room is exhausted in the summer by a thermostatically controlled roof exhaust fan, interlocked with a motor operated damper associated with a louvered air intake in the exterior wall.
Office Building With the exception of the toilet and-locker rooms and the janitor's closet, ventilation of spaces in the Office Buildi,ng is by natural means through windows.
A unit /entilator serves the toilet and locker rooms. Air is exhausted from these spaces by a system connected to a fan located above the roof.
Prim 3rr auxiliary Building In the radioactivity clean portion of the Primary Auxiliary Building a :cof type exhaust fan provides summer ventilation with supply air entering through open windows and doorc.
Ventilation, heat removal, heating, dilution and filtration of possible l
hydrogen leakage in certain equipment compartment, during operation and main-tenance periods for the potentially contaminated portion of the Primary Auxiliary Building are provided by a supply system and an exhaust. system.
Filtered outdoor air, heated when required, is furnished by a supply unit ventilator located in mechanical equipment room No. 3 and is ;stributed by ducts to the potentially contaminated area. Air is exhausted from each of the shielded compartments through ducts connected to a high efficiency filter assembly (consisting of prefilters, charcoal and HEPA's) and an exhaust fan which discharges to the primary vent stack. The filter assembly and exhaust fan are located in the mechanical equipment room.
Provisions are made to permit the use of the vapor container purge filter assembly or fan for Primary Auxiliary Building exhaust in the event the Primary Auxiliary Building exhaust filter assembly or fan becomes inoperative.
The mechanical equipment room is ventilated by the systems serving the potentially contaminated areas of the building.
Waste Disposal Building Air from the waste disposal building is exhausted to the mechanical l
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228:4 Draft eguipment roon No. 3.
There, it is joined by the Primary Auxiliary Building exhaust air ventilation for filtering through the high efficiency filter assembly before being discharged to the primary vent stack by the Primary Auxiliary Building exhaust fan. There is a wall mounted exhaust fan in the waste gas compressor room that will automatically start in the event air flow in the duct system is lost. Make-up air is heated in the winter by unit heaters.
Fuel Transfer Pit House V.:ntilation for the fuel transfer pit house is also provided by the Primary Auxiliary Building exhaust fan via the high efficiency filter assembly.
After filtering the fan discharges the exhaust air to the primary vent stack.
Outdoor air enters the structure through a wall mounted supply louver.
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NRC DISTRIBUTION FOR PART S0 DOCKET MATERIAL (TEMPORARY FORM)
CONTROL NO: 977b FILE:
FROM: Y'.nkee Ato=ic Electric DATE OF DOC DATE REC'D LTR TWX RPT OTHER
' Westberough, Mass y p y,,1,.,,,,,,
8-13-75 8-18-75 XXX TO:
ORIG CC OTHER.
SENT NRC PDR XX N tc 3 signed XX SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
X D D'X 3
50-29 DESCRIPTION:
ENCLOSURES:
' tr netarized 8-13-75...trans the following:
Amdt doOL/ProposedChange#127toTechSpecs:
Consisting of change to tech specs E revised b0 h U.L3 m qq. g 7 and addl pgs to the FS AR with regard to the 1 md v installation of a filtration system to re=cve airberne radioactive particulates and iodine
.AC..,. m r-. -,DytD in ae e,. hanst,1r from potentia 1 contamination im u a areas in the plant before discharge.....
PLANT NAME: Yankee Rowe (40 cys enc 1 rec'd)
I FOR ACTION /INFORMATION q.yo. f3 g
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