ML17298B633
| ML17298B633 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/10/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| ANPP-31397-EEVB, NUDOCS 8412130287 | |
| Download: ML17298B633 (32) | |
Text
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REGUIATORY i FORMATION DISTRIBUTION SY M (RIDS)
ACCESSION NBR:841 FACIL:STN-50 528 STN 50 529 STN"50-530 AUTHiNAME VAN BRUNT ED ED REC IP ~ NAME, KNIGHTONiG ~ bf ~
2130287 DOC ~ DATE: 84/12/10 NOTARIZED: YES Palo Ver de Nuclear Stations Unit 1~ Arizona Pub I i Palo Verde Nuclear Station~
Unit 2< Arizona Publi Palo Verde Nuclear Station~ Unit 3i Arizona Publi AUTHOR AFFILIATION Arizona Public Service Co.
RECIPIENT AFFILIATION Licensing Branch 3
DOCKET 05000528 05000529 05000530
SUBJECT:
Forwards draft pr'oposed FSAR changes, that clarify details on radiation protection, Change also provided.to correct description of transfer path of decontamination
- wastes, Changes will be'ncorporated in FSAR Amend 14
'ISTRIBUTION CODEo 8001D COPIES RECEIVED:LTR 4
ENCL J, SIZE; TITLE: Licensing Submittal:
PSAR/FSAR-Amdts 8 Related Correspondence NOTES:Standardized plant.
Standardized plant ~
Standardized plant.
05000S28 050005?9 05000530 RECIPIENT ID CODE/NAME NRR/DL/ADL NRR L83 LA INTERNAL: ACRS 41 ELD/HDS3 IE/DEPER/EPB 36 IE/DQASIP/QA821 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DSI/ASB NRR/DS I/CSB 09 NRR/DSI/METB 12 AB 22 EG FILE 04
/MIB EXTERNAL: BNL(AMDTS ONLY)
FEMA REP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME NRR I.83 BC LICITRAgE 0 1 ADM/LFMG IE FILE IE/DEPER/IRB 35 NRR ROEiM ~ L NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18
'.NRR/DE/SAB 24 NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16'RR/DS I/PSB 19 NRR/DS I/RSB 23 RGNS DMB/DSS (AMDTS)
LPDR 03 NSIC 05 PNL GRUELiR COPIES LTTR ENCL 1
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TOTAL NUMBER OF COPIES REQUIRED; LTTR 54 ENCL 46
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Arizona Public Service Company ANPP-31397-EEVB/WFQ December 10, 1984 Director of Nuclear Reactor Regulation Mr. George W. Knighton, Chief Licensing Branch No.
3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3
Docket Nos.
STN 50-528/529/530 PVNGS FSAR Update Radiation Protection Design Features File:
84-056-026.
G.1.01.10
Dear Mr. Knighton:
Enclosed are draft proposed FSAR changes that clarify design details on radia-tion protection.
Included are changes that specify where PVNGS has used alter-native measures to achieve ALARA compliance, and that describe ALARA provisions for packaged, skid mounted, equipment.
A change is also provided to correct the description of the transfer path of decontamination facility wastes.
These wastes are now transferred to the chemical drain tanks, rather than the radwaste building sump, prior to processing.
These changes are expected to be incorporated in FSAR Amendment 14 to the FSAR which is scheduled for submittal in February l985.
Please contact William Quinn of my staff if you have any questions.
Very truly yours E. E.
Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director EEVB/WFQ/mb Enclosure 8412130287 841210
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COUNTY OF MARICOPA)
I, Edwin E.
Van Brunt, Jr.,
represent that I am Vice President, Nuclear Production of Arizona Public Service
- Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its
- contents, and that to the best of my knowledge and belief, the statements made therein are true.
e Edwin E.
Van Brunt, Jr.
Sworn to before me tbie~Ddey of 1984.
1l My Commission'Expires:
My Comnilsslon Expires April 6, 198I otary Publ c
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I Mr. 6.
W. Knighton
': PVNGS FSAR Update Radiation Protection Design Features ANPP-31397 Page 2
cc:
A. C. Gehr (w/a)
R. P.
Zimmerman (w/a)
E. A..Licitra (w/a)
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PVNGS FSAR RADIATION PROTECTION DESIGN FEATURES transferred to spent resin tanks prior to solidification, and that fresh resin can be loaded into the ion exchanger remotely.
Underdrains and downstream strainers are designed for full system pressure drop.
The ion exchangers and piping are presigned with provisions for being flushed with compressed nitrogen or demineralized water.
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chemical addition connections to allow the use of chemicals for descaling operations.
Space is provided to allow uncomplicated removal of heating tube bundles.
The ~M~ov-radioactive components are separated from those that are XeuP radioactive by a shield, wall.
RemMe&struments
.and controls gc.c <~f~f Qr PYg+0'~'e*<
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>are located on the Zone 2 side of the shield wall. )Palves in radioactive lines are hma@e4-oZ the Zone 2 side of the shield wall.
Val~esi~on -adieactivm&ne~ze.'berated-ouWide-the z&o~
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12.3. 1. 1.1.4
~Pum s.
Pumps in radioactive and potentially radioactive systems are provided with mechanical seals to reduce seal servicing time.
These pumps include those in the nuclear cooling water, essential cooling water, safety injection, containment
- spray, spent fuel pool cooling, radwaste, and chemical and volume control systems.
Pumps and associated piping are arranged to provide adequate space for access to the pumps for servicing.
Pumps in the above systems are provided with flanged connections for ease in removal.
Pump casings are provided with drain connections for draining the pump for maintenance.
Plant layout ensures that maintenance can be performed in such a way that exposure to "P
P 12.3-3
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PVNGS FSAR RADIATION PROTECTION DESIGN FEATURES 12.3.1.1.1a6 Heat Exchan ers.
Heat exchangers are provided with corrosion-resistant tubes of stainless steel or other suitable materials with tube-to-tube sheet joints welded or expanded to minimize leakage.
Impact baffles are provided, and tube side and shell side velocities are limited to minimize erosive effects.
12.3.1.1.1.7 Instruments.
Instrument. devices are located in low-radiation zones and away from radiation sources whenever practical.
Primary instrument devices, which are located in high-radiation zones for functional reasons, are designed for easy removal to a lower radiation zone for calibration.
'reanseitter~nd readout devices are located in low-radiation
- zones, such as corridors and the control room, for servicing.
Some instruments (such as thermocouples) in high-radiation zones are provided in duplicate to reduce access and service time, a
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aequi.ah.
In the containment most, instruments are located outside the secondary shield (area of lowest at-power and shutdown radiation).
Integral radiation check sources for response verification for airborne radiation monitors and safety-related area radiation monitors are provided.
This allows the remote removal of a shielding window to check th'e response of each detector.
12.3.1.1.1.8 Valves.
To minimize personnel exposures from valve operations, motor-operated, diaphragm, or other remotely actuated valves are used in systems that require frequent operations or are exposed to high radiation sources.
Valves are located in valve galleries, so that they are shielded separately from the major components.
Long runs of exposed piping are minimized in valve galleries.
In areas where manual valves are used in frequently operated process lines, either valve stem extenders or shielding are provided, so that personnel need not enter the high-r'adiation area for normal valve operation.
12.3-5
PVNGS FSAR RADIATION PROTECTION DESIGN FEATURES For valves located in radiation areas, provisions are made to drain adjacent radioactive components when maintenance is required.
Valves for clean, nonradioactive systems are separated from radioactive sources and are located in readily accessible areas.
Manually operated valves in the filter and high activity ion exchanger valve compartments required for normal operation and shutdown are equipped with reach rods extending through the valve gallery walls.
Personnel do not enter the valve galleries during flushing operations.
The valve gallery shield walls are designed for maximum expected filter and ion exchanger activities.
J For most larger valves (2-1/2 inches and larger) in lines carrying radioactive fluids, a double set of packing is provided.
Diaphragm or bellows seal valves are used on those systems where leakage is to be minimized.
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~an The piping in g'ape chases is designed for the life-time of the unit.
There are no valves or instrumentation in pipe chases.
Wherever radioactive pip-ing is routed through areas where routine maintenance is
- required, pipe chases are provided to reduce the radiation contribution from these pipes to levels appropriate for the inspection requirements.
Piping containing radioactive material is routed.to minimize radiation exposure to the unit.
personnel.
12.3.1.1.1.10 Floor Drains.
Floor drains and properly sloped floors are provided for each room or cubicle containing serviceable components containing radioactive liquids.
Local gas traps or porous seals are not used on radwaste floor drains.
Gas traps are provided at the common sump or-tank.
Amendment ll 12.3-6 April 1983
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I PVNGS FSAR RADIATION PROTECTION DESIGN FEATURES Major components (such as tanks, ion exchangers, and filters) in radioactive systems are isolated in individual shielded compartments.
Labyrinth entranceway shields or shielding doors are provided for each compartment from which radia'tion could stream or scatter to access areas and exceed the design radiation zone dose limits for those areas.
For potentially high-radiation components (such as ion exchangers and tanks),
completely enclosed shielded compartments with hatch openings are used.
For some infrequently serviced components, com-pletely enclosed shielded compartments with removable concrete block walls are used.
'(i Nonradioactive equipment that requires maintenance is located outside radiation areas.
Exposure from routine in-plant inspection is controlled by
- locating, whenever possible, inspection points in properly shielded low-background radiation areas.
Radioactive and nonradioactive systems are separated as far as practicable to limit radiation exposure from routine inspection of non-radioactive systems.
For radioactive
- systems, emphasis is placed on adequate space and ease of motion in a properly shielded inspection area.
Where longer times for routine inspection are required, and permanent shielding is not feasible, sufficient space for portable shielding is provided.
For example, a remotely operated device is provided for inservice inspections of the reactor vessel.
Access'to high-t radiation areas is under the supervision of the radiation protection personnel.
12 12.3.1.1.2.6 Field-Run Pi in Radioactive process piping design (i.e., routing or shielding) is not performed in the field.
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INSERT A TO Page 12.3-10 12.3.1.1.2.7 Packa e Units.
Each package unit is skid mounted with all motors and pumps located on the periphery at the skid for ease of access and for quick removal to low radiation area for maintenance or repair.
Package components are provided with provisions for flushing, draining and chemical cleaning.
Heat exhangers are readily accessible for maintenance.
As many control elements as possible are mounted remotely'rom the radioactive components so that the package can be remotely controlled and monitored.
Components are designed with a minimum of crevices to reduce the accumulation of radioactive materials.
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PVNGS FSAR RADIATION PROTECTION PROG~q are performed in the same machine which eliminates the pos-sibility of any accidental contamination during transfer between washers and dryers.
Radioactive waste is trapped by filters.
Aqueous or hydrocarbon.soluble contamination is separated during solvent distillation and re-condensation.
The liquid waste from the laundry is contained in the dry cleaning machines and processed separately from other liquid waste.
The dry, solid waste from the laundry is manually bagged and carried to the raCwaste baler in the Unit 1 Radwaste Building.
This waste is compacted into 55 gallon drums in preparation for offsite disposal.
The liquid wastes from the decontamination facility are piped gh~ fC,ca./ Ds n.;~
rmn/ZS to a line common to the laundry building which goes to the limni~
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The solid waste generated from the decontamination facility is handled in a manner similar to that discussed above.
12.5.3 PROCEDURES Radiation protection procedures are established to keep person-nel radiation exposures ALARA and within the limits of 10CFR20.
These procedures are discussed in section 13.5.2..
Policy and operational considerations fox maintaining personnel radia-tion exposures are discussed in sections 12.1.'and 12.1.3.
12.5.3.1 Radiation and Contamination Surveys Radiation protection personnel normally perform routine radia-tion and contamination surveys of 'accessible areas of the units.
These surveys consist of radiation-dose rate measure-ments and/or contamination smears as appropriate for the speci-fic area.
Air samples are routinely taken in accessible r
portions of controlled areas.
Surveys related to specific Amendment 12 12 '-13A y'ebruary 1984
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PWJGS FSAR ENSURING TEAT OCCUPATIONAL RADIATION ~QSURES AS LON AS IS REASONABLE ACEIEVABLE (AId'iRA)
Shielding design guidelines In S'crnificantly'adioactive components such as t~, 'filters, ion ezchangers,
- pumps, and heat.
'xchangers ~e located in shielded compartments.
2.
3.
6.
In those process systems whose components contain'ajor sources of radiation, valves and instrumen-tation are separated by shielding from the components.
Although use of permanent shielding is preferred,
'-portable or temporary shielding and convenient means for handling it is provided where shielding is required but fixed shielding is impractical.
. Access and the capability of the structure to support such portable or temporary shielding has been evaluated during design review.
Access to shielded compartments is generally by means of shielded labyrinth arrangements such that direct exposure to radioactive eouipment from normal access areas is eliminated.
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.highly -radioactive passive components such as
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ion exchangers,"and filters, completely enclosed compartments are provided.with access via a shielded hatch, et lpbyr'i Mal 8n<f.f Way'i < I+et Where space limitations preclude the use of ordinary concrete for shielding, lead, iron, or high density concrete is used instead.
Use of removable concrete shielding blocks for frequent personnel access or eguipment removal has been avoided by design when practical.
February 1984 12.1-9 Amendment 12
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PVNGS FSAR ZNSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOM AS IS REASONABLE ACHIEVABLE (ALA%~)
3.
If the radiation level within a valve gallery is high, valve stem extensions through the valve gallery wall to an adjacent corridor are supplied
.... for frequently operated valves so that'hey way be operated from a design radiation Zone 2 area.
4.
Sufficient, space is provided 'in valve galleries to facilitate maintenance on valves.
Radioactive piping design guidelines 2.
5.
6.
7.
8.
Radioactive piping is not field routed.
Piping is routed so'that it does not, exceed applicable design radiation zone level.
Radioactive piping routed through design radiation Zone 1 or Zone 2 areas is enclosed in a shielded pipe chase, if reauired.
Radioactive piping is routed through the highest design radiation zones practical.
Potentially radioactive piping is routed behind components or structures which provide shielding to areas where maintenance is likely to be performed.
.Radioactive pipes are routed close to floors, ceilings and walls where practical, but are kept away from doors and entrancesp ou4Side ~%a>~geg+.
Nhen,practical, radioactive piping is separated from nonradioactive piping.
If practical, valves or instrumentation should not be located within radioactive pipe chases.
Amendment 12 12.1-12 February 1984
PVHGS PSAR
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~ ?SURING THAT OCCUPATIONS RADIATIOh'XPOSURES
. M AS LON AS XS REASOHABLZ ACHIEVABL+ (ALUM)
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-..ddition, <qe following special considerations are
'-o i'~ing which processes spent resins:
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Ball, plug, or diaphragm valves are used, depend-ing upon the function, in spent resin lines.
- Strainer, check, and Y-valves are not utilized in piping systems which process spent resins.
16.
17.
20.
Orifices are not utilized in spent resin piping systems'utt welds are employed where practical for spent, resin piping regardless of size.
Large radius elbows, or large diameter-bends, are used where practical in routing all such piping.
Hinety-degree tees are not used in spent resin piping systems except to introduce clean services such as nitrogen or water, into such lines.
Dead legs are avoided and any necessary flushing connections are taken off above the horizontal centerplane of the resin piping.
Spent resin lines are sized to achieve turbulent flow to minimize resin deposits and subsequent r
buildup.
Provisions are made for the ion exchangers as well as the resin lines to be pressurized with nitrogen or water to clear plugged lines.
The water or nitrogen is introduced at a tee down-stream of each valve, and the leg of the tee is above the resin line to avoid clogging of the clean service inlet line.
February 1984 12.1-15 Amendment 12
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PIGS FSAR RADIATION PROTECTION DESIGN IMTiJRES
-'>.n~; b= rout=d through corridors or other low-radiation sr ielde<<pipeways are provided.
Whenever practical, valves and instruments are not placed in radioactive pipeways.
Whenever practical, ep~ipment compartments aw used as pipeways only for'hose pipes associated with equipment in the compartment.
When practical, radioactive and nonradioactive piping are sep-arated to minimize personnel exposure.
Should maintenance be
- reauired, provision is made to isolate and drain radioactive piping and associated ecuipment..
Piping is designed to minimize low points and dead legs.
Drains are provided on piping where low points and dead legs cannot be eliminated.
Long radius elbows, or bends of several pipe diameters are utilized whenever practicable for pipes C
carrying radioactive material.
Piping, carryi'ng resin slurries or evaporator bottom~
, is run vertically as much as possible.
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Whenever possible, branch lines having little or no flow during normal= operation are connected above the horizont-l midplane of the main pipe.
12.3.1.1.2.3 Penetrations.
'To minimize radiation streaming through penetrations, as many penetrations as practicable are located with an offset between the source and the accessible areas.
If offsets are not practical, penetrations, are located as far as possible above the floor elevation to reduce the e:closure to personnel.
If these two methods are not used, alternate means are employed, such as baffle shield walls or g"outing the area around the penetration.
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~, aV~aJGS FSAR RADIATION PROTECTION DESIGN Fr%TURKS 32.3.1.1.2.-"=
'ontamiriation Control.
Access control and p,--..=. ',;..-.'. t::.-;....r consid=red in'the basic plant layou to gin-:.-'..:.
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Eguipm'ent vents ana drains from highly radioactive systems are piped directly to the collection system instead of allowing any radioactive fluid to flow across to the floor drain.
All-welded piping systems are employed on radioactive systems to the maximum axtent practicable to reduce system leakage and crud builaup zt joints.
Decontam>>ination of potentially contaminated areas and eouip-
'm nt ~'itMn the plant is facilitated by the application of suitable smooth-surface coatings to the concrete floors ana valls.
Sloped floors and floor drains are provided in potentially contaminated areas of the plant.
.In addition, radioactive and potentially radioactive drain systems are separated from non-rad'oactive drain systems.
Rooms with equipment or tan3+ that contain radioactive fluids have curbs to contain potential spills or leaks.
Large tanks containing radioactive fluids a"e enclosed in water tight compartments or are surrounded by curbs.
In controlled access areas where contamination is expected, raaiation monitoring equipment is provided (sections 11.5 and 12.3.4).
Those systems that become highly radioactive, such as the spent resin lines in the radwaste
- system, are provided with flush and drain connections.
12.3.1.1.2.5 Ecui ment La out.
In systems where process C5~
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pumps, valves, and ins'ments ar separated from the process component.
This allows servicing and maintenance of these items in reduced radiat'cn areas.
Control panels are located in low-radiation ar as (Design Radiation Zones 1 or 2).
February 1984 12.3-9 Amendment 12
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F RADIATION PROTECTION DES IGN FEATURES
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-::.ajor co.ponants (such as tanks, ion exchangers, and filters)
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~~e isolated in individual shielded co part ents.
Labyrinth entranceway shields or shielding
..doors ar provided for each compartment from which radiation
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could stream or scatter to access areas and exceed the design radiation zone dose limits for those areas.
For potentially
'i2 I high-radiation components
{such as ion exchangeis and tanks),
completely enclosed shielded qompa~ents with hatch openings tdtQT g p~ ~++i Q~QS ~ t+4 (O~~ gR+CS are used..
For some znfreguentPy serviced component, com-pletely enclosed shielded compa~ents with removable concrete block walls'are used.'onradioactive equipment that reauires maintenance is located outside radiation areas.
Exposure from routine in-plant inspection is controlled by
- locating, whenever possible, inspection points in properly shielded,low-background radiation areas.
Radioactive and nonradioactive systems are separated as far as practicable to limit radiation exposure from routine inspection of non-radioactive systems.
For radioactive
- systems, emphasis is placed on adequate space and ease of motion in a properly shielded inspection area.
Were longer times for routine inspection are required, and permanent shielding is not feasible, sufficient space for portable shielding is provided.
/
For example, a remotely operated device is provided for inservice inspections of the reactor vessel.'ccess to high-radiation areas is under the supervision of the radiation protection personnel.
12.3.1.1.2.6 'ield-Run PiDin Radioactive process piping design (i.e., routing or "shielding) is not performed in the
'"eld.
Amendment 12 12.3-10 February 1984
l
ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LON AS IS REASONABLE ACHIEVABLE (ALARA)
Leakage of radioactive material is minimized by use of appropriate valve gaskets and valve packing.
For
- example, one of the following is provided for radio-active valves 2-1/2 inches and lar er:
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A double set of packing 4 ~
A packing gland with a leakoff connection which can be piped to a collection header.
Diaphragm or bellows seal valves ~~ ~~~~~ '
f~c~c W ~la'~o, Radiation tolerant materials are used in valves in accordance with their radioactive service.
Chemical seals are provided on instrument sensing lines for process piping which may contain highly radioactive solids to reduce the servicing time required to keep the lines free from solids.
O.
Primary instrument devices, which for functional reasons are located in high radiation areas, have been designed for uncomplicated removal for calibration or servicing.
Some instruments, such as.thermocouples are provided in duplicate in highly radioactive areas to reduce access and service time.
P.
The sample laboratory is equipped with adequate shielding and a fume hood.
The sample laboratory and sample stations are equipped with a sink or funnel arrangement.
so that sample lines may be purged to the LRS or chemical and volume control system prior to, sampling.
- Also, sample lines incorporate the capa-bility of being flushed.
Q.
An automated radwaste solidification system is employed to minimize exposure during radwaste processing.
Remotely operated equipment is provided where practical to minimize operator radiation exposure.
Amendment 12 12.1-22 February 1984
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