ML17298B616
| ML17298B616 | |
| 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-31414-EEVB, NUDOCS 8412120083 | |
| Download: ML17298B616 (68) | |
Text
REGULATOMINFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBR;801 FAGIL:STN 50 528 STN~50 529 STN,50 530 AUTH BYNAME VAN BRUNTgE;ED REC IP ~ NAt4E KNIGHTONgG ~ N ~
2120083DOC. DATE: eg/12/10 NOTARIZED:
YES Palo-Verde Nuclear'tation~
Unit ii Arizona Publi Palo Verde Nuclear Station~
Unit 2E Arizona Publi Palo Verde Nuclear Station~
Unit 3i Arizona Publi AUTHOR AFFILIATION Arizona Public Service Co, RECIPIENT AFFILIATION I icensing Branch 3
DOCKET O5OOO528 05000529 05000530
SUBJECT:
Forwards draft proposed FSAR changes re, radwaste sys 8
effluent streams. Changes will be incorporated in FSAR Amend 14 scheduled for Feb 1985.
DISTRIBUTION CDDE: BOOID,COPIES RECEIVEDILTR ENCL SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts L Related Correspondence NOTES:Standardized plant.
Standardized plant; Standardized plant ~
05000528 05000529 05000530 RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB3 LA INTERNAI.: ACRS 1
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NRR/DL/SSPB NRR/DSI/ASB NRR/DSI/CSB 09 NRR/DSI/METB 12 NR 'AB 22 Og r
B EXTERNAL! BNL:(AMDTS ONLY)
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Arizona Public Service Company ANPP-31414-EEVB/WFQ December 10, 1984 Director of Nuclear Reactor Regulation Hr. 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 Radwaste Systems and Effluent Streams File:
84-056-026'.l.01.10 84-019-026
References:
(2)
Letter from E. E.
Van Brunt, Jr.,
APS, to G.
W. Knighton, NRC, dated June 14, 1984 (ANPP-29750),
Subject:
Monitoring of Gaseous Effluents for Palo Verde.
Letter from E. E.
Van Brunt, Jr.,
APS, to G.
W. Knighton, NRC, dated October 17, 1984 (ANPP-30885)
Subject:
Gaseous Effluents Monitoring
Dear Hr. Knighton:
Enclosed are draft proposed FSAR changes for your information that 1) identifies capabilities to use portable radwaste solidification systems, 2) deletes use of the crud filter subsystem by deleting the backflushable purifi-cation filter and 3) clarifies radiation monitoring capabilities and 4) makes minor editorial changes.
These changes are considered acceptable as 1) the use of a portable radwaste solidification is permitted by the Technical Specifications,
- 2) the imposition of 10 CFR 61 required a redesign of purifi-cation filtration due to size constraints, and 3) radiation monitor capabilities were enhanced as previously described in References 1 and 2.
These changes are expected to be incorporated in FSAR Amendment 14 to the FSAR which is scheduled for submittal in February 1985.
Please contact William
'uinn of my staff if you have any questions.
Very truly yo s,
CU'~
84i2120083 84i2i0 "PDR ADOCK 05000528 A
PDR EEVB/WFQ/mb Enclosure E. E.
Van Brunt, Jr.
APS Vzce President Nuclear Production ANPP Project Director
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ANPP-31414 STATE OF ARIZONA
)
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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.
Edwin E.
Van Brunt, Jr.
Seers to before me tbds~Oday of 1984.
ss My'ommission,.Expires:
M Commission Expires April 6, 1867 Q
otary Pub
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Mr. G.
M. Knighton
,i PVNGS FSAR Update-Radwaste Systems and Effluent Streams ANPP-31414 Page 2
cc:
A. C. Gehr (w/a)
R. P.
Zimmerman (w/a)
E.
A. Licitra (w/a)
0 1
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0" PVNGS FSAR APPENDIX llA filters and disposable crud filters are related to their cor-responding input activities provided in table 11.4-2.
RESPONSE
2.
7X < 5/Id>><g a55cunp 8e'rS'aÃre uh'/jib i n E5 lubliS ~isa
>A'5 euV~V aHi/icyin '7a I/i'l.1 &.:-
Evaporator concentrates are solidified and stored in 'the high activity storage area for one month (i.e.,
1 month decay) prior to shipment.
Spent resin beads are stored for 6 months prior to solidification.
Solidified resin is stored in the high activity storage area for 1 month (i.e.,
1 month decay) prior to shipment.
3.
.4 ~
Cartridge filters are solidified and stored in the high activity storage area for one month (i.e.,
1 month decay) prior to shipment.
Disposable crud filters are stored for one month (i.e.,
1 month decay in the high activity storage area prior to shipment.
OUESTION 11A.12 (NRC No. 460.18)
(11.5)
Ne have reviewed your submittal dated April 6, 1981, relating to TMI Action.Plans II.F.1, Attachments 1 and 2, and III.D.l.l of NUREG 0737.
Ne find your information scant and very inade-quate.
Please prov.de the information on these action items as required by NUREG-0737.
For guidance, you may refer to submittals on these action plans for other PWRs such as San Onofre, Units 2 and 3, and Summer Nuclear Station, which have been found acceptable by the staff.
RESPONSE
Amendment 1 to the PVNGS Lessons Learned Imple-mentation Report (LLIR) was submitted August 3, 1981. It contains an expanded discussion of noble gas monitoring and effluent sampling per Attachments 1 and 2 to NUREG 0737 Item II.F.1.
October 1981 llA-7 Amendment 6
la
PVNGS FSAR SOLID WASTE MANAGEMENT SYSTEM Topical Report for Radwaste Solidification System (Cement).
Instrumentation and control devices provided are shown on figure 11.4-2.
The capability is provided to perfo~'n-truck solidification of evaporator bottoms using various sizes of disposable liners if the need should arise. C I 4 SBR'T Prg 11.4.2.3.2 Dry Waste Disposal Potentially radioactive dry wastes are collected at appropriate locations throughout the plant as dictated by the volume of these wastes generated during operation or maintenance.
As necessary, these wastes are taken to the radwaste building for packaging, where they are first compressed in drums to minimize shipping volume.
Additional compressible material is added, and the drum contents are recompacted until a drum is filled.
The drums are then sealed and moved to the waste storage area until shipped offsite.
During compaction, the airflow in the vicinity of the compactor is directed by the compactor exhaust ran through a HEPA filter before it is discharged to the radwaste building ventilation exhaust.
Large or highly radioactive components and equipment that have been contaminated during reactor operation and that are not amenable to compaction or decontamination are handled either by qualified plant personnel or by outside contractors specializing in radioactive materials handling, and are packaged in shipping containers of an appropriate size and design.
J 11-4.2.3.3 Filter Handling and Disposal The filters are separated into four classifications:
Backflushable filter Completely disposable filter elements and vessel used in the backflushable filter crud collection system Cartridge type filters with disposable elements
- 11. 4-'
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INSERT A Insert A to FSAR Page 11.4-17 Should the waste solidification subsystem be under repair, portable solid-ification system bypass lines and connections are provided to enable spent resins from the spent resin tanks to be diverted from the waste feed tank and sent directly to a portable solidification system located in the truck bay area for solidification.
In addition, a bypass of the spent resin tanks is provided to allow sluicina.directly. fram..the. ian exchangers in the radwaste and auxiliary buildings to thYgporFa%TevPoaidxEica6.on system connection in the truck bay area.
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t PVNGS FSAR PROCESS AUXILIARIES Q.
Environmental 1.
The CVCS is provided with an environmental control system such that the safety-related equipment listed in appendix 3E operates within the environmental design limits specified in appendix 3E, as discussed in section 9.4.
R.
Mechanical Interaction Between Components.
The portions of the CVCS that are part of the reactor coolant pressure boundary are designed to tolerate the events described in CESSAR Table 9.3.4-2.
9.3.4.3 Crud Removal Subs stem 9.3.4.3.1
System Design
The CVCS crud removal subsystem is designed to facilit e the collection and removal of suspended solids in the le own which collects in the backflushable purification lter (shown in figure 9.3-13).
9.3.4.3.2 Components The crud removal subsystem has the llowing components:
crud
- tank, crud pump, crud filter, an crud tank vent filter.
The crud tank (CHN-X03) is ressure vessel designed in accordance with ASME Sec
- on VIII.
The tank is fabricated of austenitic stainless eel and is sized to accept backflushable purification filt discharges for one week.
The upper portion of the ank has a spray that prevents particulates from being.-
nted.
Both overpressure and vacuum relief valves are con cted to the tank.
Th crud pump (CHN-P03) is a centrifugal type horizontal pump.
It recirculates the contents of the crud tank to agitate any settled crud and bring it into suspension.
It also pumps the 9.3-91
~
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PVNGS FSAR ank's contents through the crud filter and into the equipm drain tank.
The crud filter (CHN-Fll) is a
5 micron rated dispo le cartridge filter with integral, reusable, lead ield.- Crud buildup on the filter is monitored by delt ressure drop across the filter.
The crud vent filter (CHN-F12) 1 micron rated disposable cartridge filter with inte
, reusable, lead shield.
This filter prevents radio ide particulates from being discharged to the auxiliary aiding HVAC system.
9.3.4.3 Safety Design Bases T
crud removal subsystem has no safety design bases.
9.3.5 STANDBY LIQUID CONTROL SYSTEM (BWRs)
This section is not applicable to PVNGS.
9.3.6 COMPRESSED GAS STORAGE SYSTEMS Compressed gas storage is provided for nitrogen (N2), hydrogen (H2), carbon dioxide (CO2), air, and Halon 1301.
Refer to section 9.5.1 for the description, safety design bases, and safety evaluation of the C02 and Halon 1301 storage subsystems.
Section 10.3.2 provides a description of the N2 accumulators I
for the atmospheric dump'alves and safety design bases and evaluations.
Compressed air system descriptions, safety design basis, and safety evaluations are provided in sections 9.3.1 and 9.5.6.
9.3-92
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PVHGS FSAR
(
11.4 SOT ID WASTE MANAGEMENT SYSTEM 1
Solid waste management is provided by the solid radwaste system (SRS) which, is designed to provide holdup, solidification, and packaging of radioactive wastes generated by plant operation, and to store these wastes until they are shipped offsite for burial.
The system is located in the radwaste building, which is designed to withstand an operating basis earthquake.
11.4.1 DESIGN BASES The design bases of the solid waste manag'ement system are:
A.
B-C.
The SRS provides the capability for solidifying and packaging concentrated waste solutions from the miscellaneous waste evaporator, spent resins from radioactive ion exchangers, and chemical drain tank wastes.
The SRS provides a means for packaging and disposal of spent radioactive cartridge filters and solid wastes from the LRS,
- CVCS, and laundry (Unit 1 only).
The SRS provides a means of compacting and packaging miscellaneous dry radioactive materials, such as paper,
'rags, contaminated clothing,'gloves, and shoe coverings, and a means for packaging contaminated metallic mater-ials and incompressible solid objects, such as small tool's and equipment parts.
D.
The SRS provides an alternate method of disposal of liquid and crud from the backflushable filt, d tank.
Note that the crud is normally remo a disposable filter and the liquid is n y processed by the chemical and vol ntrol system discussed in section 9-..
December 1981 11.4-1 lLmonRmont 7
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A.
0 PVNGS FSAR SOLID WASTE MANAGEMENT SYSTEM
'p W The SRS provides a method of solidifying and packaging blowdown demineralizer resin and condensate polishing resin in the event that they become contaminated.
The-maximum and expected input volumes to the SRS from each source of solid waste material are presented in table 11.4-1.
The SRS input activities associated with the expected input volumes are presented in table 11.4-2.
Codes and standards applicable to the solid radwaste system are listed in table 3.2-1.
Collection, solidification, packaging, and storage of radio-active wastes will be performed so as to maintain any potential radiation exposure to plant personnel to "as low as is reason-ably achievable" (AZdSA) levels, consistent with the recommen-dations of Regulatory Guide 8.8 and within the dose limits of.
Some of the design features incorporated to maintain AL'de% criteria include remote system operation, remotely actu-ated flushing, quick disconnect, equipment layout permitting the shielding of components containing radioactive materials, and use of shielded casks for in-plant movement of high activity waste.
Additional AIBA provisions of the SRS are described in section 12.1.
Packaging and transport of radioactive wastes will be in con-I formance with 10CFR71.
Packaged wastes will be shipped in con-formance with 49CFR170-178.
Collection, solidification, packag-
- ing, and storage of radioactive wastes will be performed in conformance with 10CFR50.
Laundry is cleaned by a dry<<cleaning system.
Solid wastes are manually transfered to the SRS for packaging.
Refer to section 12.5.2.
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SOLID WASTE MANAGEMENT SYSTEM Table 11.4-1 SRS INPUT VOLUMES (PER UNIT)
Source (Form)
Wet Waste Evaporator concentrates Spent resin Chemical drain tank Blowdown deminer-alizer resin Condensate polishing resin Dry Waste Compactable and noncompactable dry wastes Filters
~rtridge filters (dry)
Expected Vo)ume (ft /yr) 3,224 430 0
11, 091
. Maximum Vo)ume (ft /yr) 69,877 430 294
= 282
'1,872 11, 091 34.2 Bases Regulatory Guide 1.112 April, 1976 Reference 1
Note 1
Note 2
WASH 1258 I
A IF/NESP-008 (2)
Reference 1
10
'otal (ft /yr)
,"755 10 NOTES:
1.
2.
'ICEI
~NKPol~~em~
The chemical drain tank contents are normally processed by the liquid radwaste system.
Maximum volume is based on an additional complete flush of each tank directly
)10 to the SRS
-per year.
Blowdown demineralizer resin is not normally bio changed more than once per year.
Maximum volume is based on change out of both demineralizers during one year.
December 1982 11.4-3 Amendment 10
Table 11.4-2 SRS INPUT ACTIVITIES( ) (Ci/yr) (Sheet 1 of 4)
(PER UNIT)
Nuclide BR-83 BR-84 BR-85 I-129 I-130 I-131 I-132 I-133 I-134 I-135 RB-86 RB-88 RB-89 CS-134 CS-136 Evaporator Concentrates 0.0 00 0,0 OIO i,s (;os)
I I'3 Ii 1 L OQ-3.1 (-OI) 2,1 (-02) e 1 (-oz) o,O C,O O,g 3 2- (-O1) 1r o (-oO Spent Resin Beads
- 2. 8 t.'-~~)
~,s (.-uzi 3.S' o'1)
Q,O l'.2. C-ol)
> 2 Cto~)
3 LJ 1,e C+DX) 6,5(-O1) r.
I ("00 O.O 6, ~ (-01')
00 l(R (+03)
SC~OI)
Cartridge Filters 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Disposable Crud Filters 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.
0
'0
.0 0.0 Dry Wastes (b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b) a.
Expe'cted waste generation conditions only, maximum waste generation conditions are not tabulated because they are short-term inputs that are not representative of a year's continuous operation.
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Table 11.4-2 SRS INPUT ACTIVITIES( ) (Ci/yr)
(Sheet 2 of 4)
(PER UNIT)
Nuclide CS-137 CS-138 N-16 H-3 Y-90 Y-91M Y-91 Y-93 MO-99 SR-89 SR-90 SR-91 ZR-95 NB-95 TC-99M RU-103 RU-106 RII-103M RH-106 Evaporator Concentrates
- 2. l(-G~)
9 0 G.O t,S(~ u1) 1,P(~)
~,sC-o-'t) 90 s,SC~>)
li>
e,o C-o>)
1gC oo)
W a1';o~)
& f(->)
G,S (-
0 BC-o~)
l,>(-o~)
~.eC~)
1i 3(k ol)
Spent Resin Beads 1
00 1, O (-O'I)
OC',W(-o~3 6V(-o~)
lR 9, s'C-03) 1,2.(+ox) 0(
I 1,0 1,<l(-OO
, l,h 4I',1{ 01) 5,2 1'3C-o1) 8,1 (-ol)
~j i~f (-O'I) g ~( (-Q)
Cartridge Filters 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
- 0. 0 0.0 0.0 0.0 0.0 0.0 Disposable Crud Filter 0.0 0.0 0.0 0.0 0.0 i::iI 0.0 0.0 I
I 0.0 I
0.0 0.0 1.7 0.
0.
0.0
- g. 0-
.0
.0 Dry Wastes (b)
(b)
(b)
(b)
(b)
'b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
'b)
(b)
(b)
(b)
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Table 11.4-2 SRS INPUT ACTIVITIES(>) (Ci/yr) (Sheet 3 of 4)
(PER UNIT)
Nuclide TE-125M TE-127M TE-127 TE-129M TE-129 TE-131M TE-131 TE-132 TE-134 BA-137M BA-140, LA-140 CE-141 CE-143 CE-144 P R-143 PR-144 NP239 CR-51 Evaporator Concentrates Cr,O 5, l(->>)
OO I,S (o2) s, zl-oS)
O.O 010 v s(~)
C.O 2.Z(-o1) l,a(.-02) 1, f'.(-O2) 9,2(-O9 q 4 (-o5) q,2. f-Z) g q (-o1)
C,S (-I')
2 ( (-03) 1,cf (~2)
Spent Resin Beads 00 1,S(Io f')
1, <(-Of)
- 2. 9 (tOI )
g,'1(-o2) 0,0 C,o so&of) o,o 1, >(->>)
I,S f,a(-of)
I (2 z,w(-oz)
~ 2 S Q,f (-of)
~, 1(~)
li)
~IT Cartridge Filters 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
~~~~)
I 0.0 j
0.0 i
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
'.0 0.0 0.0 0.0I 0.0 0.
i'. 0
.0
/3.. 6 (+02)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
'(b)
(b)
(b)
(b)
Disposable JI Dry Crud Filters !
Wastes
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Table 11.4-2 SRS INPUT ACTIVITIES(a) (Ci/yr) (Sheet 4 of 4)
(PER UNIT)
Nuclide MN-54 FE-55 FE-59 CO-58 CO-60 TOTAL Evaporator Concentrates I,o(-o3)
O,O I i l C-02) i,z(-a) z,g(-o2) 3 I(+Op Spent Resin Beads
<,b 4-CS)
Cartridge Filters V.C.
,D l.5 3.8C~o2) z(+o.a)
G. o(~z)
Disposab Crud Fil rs T(S QIQ (I S C~o~)
1 i
(].02)
,8(~oz)
Dry Nastes (4)
C~)
(b Cb) g, o(~>)
hj Ul PlHU hf
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PVNGS FSAR SOLID WASTE MANAGEMENT SYSTEM H.
Radwaste Baler The radwaste baler is'used to package low-radiation level, solid compressible wastes in standard 55-gallon drums.
The primary function of the baler is to reduce the volume of wastes that often contain a large void space.
Potentially radioactive air which escapes from the drum during compaction is exhausted by the baler exhaust fan through a HEPA filter to the radwaste building ventilation exhaust.
The drums of compacted waste are moved by the bridge crane, forklift, or dolley to the low activity storage area to await off-site shipment.
11.4.2.3 S stem 0 eration 11.4.2.3.1 Liquid Waste and Spent Resin Disposal The waste solidification system operates on a batch basis to solidify chemical drain tank waste, evaporator concentrates, spent resins It is also used to encase spent radioactive cartridge filters and other miscellaneous contaminated objects.
The system is designed to solidify spent blowdown demineralizer resin and spent condensate polishing resin if required.
Sufficient capacity is provided to solidify radioactive wastes resulting from normal plant operations and anticipated operational occurrences.
Liquid inputs from the concentrate monitor tanks, the chemical drain tanks, and the spent resin tanks-are fed into the waste feed tank for hold up and chemical treatment prior to solidification.
The waste feed pump transfers waste from the waste feed tank through an in-line pH probe and a
three-way valve which directs waste back to the tank (reciicu-lation mode) or to the radwaste/cement mixer.
The recirculation mode is for sampling and chemical adjustment.
After the required chemical adjustments are
- made, the waste is pumped to ll. 4-14
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PVNGS FSAR SOLID WASTE MANAGEMENT SYSTEM Topical Report for Radwaste Solidification System (Cement).
Instrumentation and control devices provided are shown on figure 11.4-2.
The capability is provided to perform on-truck solidification of evaporator bottoms using various sizes of disposable liners if the need should arise.
11.4.2.3.2 Dry Waste Disposal Potentially radioactive dry wastes are collected at appropriate locations throughout the plant as dictated by the volume of these wastes generated during operation or maintenance.
As necessary, these wastes are taken to the radwaste building for packaging, where they are first compressed in drums to minimize shipping volume.
Additional compressible material is added, and the drum contents are recompacted until a drum is filled.
The drums are then sealed and moved to the waste storage area until shipped offsite.
During compaction, the airflow in the vicinity of the compactor is directed by the compactor exhaust fan through a HEPA filter before it is 'discharged to the radwaste building ventilation exhaust.
Large or highly radioactive components and equipment that have been contaminated during reactor operation and that are not amenable to compaction or decontamination are handled either by qualified plant personnel or by outside contractors, specializing in radioactive materials handling, and are packaged in shipping containers of an appropriate size and design.
11.4.2.3.3 Filter Handling and Disposal fu)o The filters are separated into ~classifications:
~
Cartridge type filters with disposable elements
PVNGS FSAR SOLID WASTE MANAGEMENT SYSTEM
~
Unshielded low activity filters with disposable elements One CVCS purification filter, located. at., the 120-ft elevation of'the auxiliary building, is backflushable.
The completely disposable filters utilized in the backflushable filter c d
collection system are shielded with a reusable lead ca The completely disposable filters employed are:
o One disposable shielded crud filter (s ion 9.3.4) o One disposable shielded crud vent ter (section 9.3.
These filters are located in the auxil'y building (eleva-tion 120) and are shown on figure 1
-6.
The disposable crud system fil s are located in a compartment which is accessed by removi panels above the lead shielded filters.
In order to ch e out a filter, the lead shield is unbolted from its fou ation and the filter is uncoupled from its piping system. + he lead shield encased filter is then lifted off of i.
foundation, using the monorail hoist, and the free pipe en are capped to prevent leakage.
The lead shield encased f'er is then transported via monorail to the radwaste buildi for subsequent shipment to an NRC approved burial sit.'he filter is removed from the shield and is disposed of the burial site and the shield is returned to the plant for reuse.
The following are cartridge type filters:
One reactor makeup water filter (section 9.3.4)
One boric acid filter (section 9.3.4)
One reactor drain tank filter (section 9.3.4)
Two seal injection filters (section 9.3.4)
Two fuel pool filters (section 9.1.3)
Two liquid radwaste system filters (section 11.2) purification filterS(section 9.3.4) 11.4-18
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Table 11.4-5 SRS OUTPUT VOLUMES PER UNIT Containers Shipped Source Wet Waste Expected Vo)ume (ft /yr)
Maximum Vo)ume (ft /yr)
I arge Containers (expected/
max/yr)
Drums of Solidified Waste (expected/
max/yr)
Drums of Baled Waste (expected/
max/yr)
Evaporator concentrates Spent resin beads Chemical drain tank effluent Dry Waste Baled waste Filters cartridge filters Total,,
4,299 1,147 3,697
'/A F303 93,169 6,891 420 3, 697 610 54/1,165 16/87 585/12,677 158/938 0/0 0/58 y65 /9g7M
/I;>>
503/503 503/503 Q
CA l>0 9
)gp
Table 11.4-6 SRS OUTPUT ACTIVITIES (Ci/yr/unit)
(Sheet 1 of 4)
(a)
Nuclide BR-83 BR-84 BR-85 I-129 I-130 I-131 I-132 I-133 I-134 I-135 RB-86 RB-88 RB-89 CS-134 CS-136 CS-137 Evaporator Concentrates QO a,O 0.0 z.sC-t i3 e.e C-<~)
- g. e (-oi)
~,q C-03) q,~C-oe) 0,0 o,gC->v) 5,0 G,O 0.0
~,'z(-oi)
- q. <-oz.)
2 ~l( Ol)
Spent Resin Beads 0,0 OiO OI0 2,6C-O7)
O,O
&8~~)
~ I(-i~)
0.0 AO 0,0 o,O Q,O
-00 i ('3 403)
I,c1 (~3)
), > C~os)
Cartridge Filters 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.
0 0
.0 0.0
/ 0.0 0.0 i
0.0 0.0 I
I III Disposable Crud Filters Dry, Wastes (b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b) a ~
b.
Expected waste generation conditions only.'aximum waste generation conditions are not tabulated because they are short-term inputs that are not representative of 1 year's continuous operation.
C
Table 11.4-6 SRS OUTPUT ACTIVITIES (Ci/yr/unit) (Sheet 2 of 4)
Nuclide CS-138 N-16 H-3 Y-90 Y-91M Y-91 Y-93 MO-99 SR-89 SR-90 SR-91 ZR-95 NB-95 TC-99M RU-103 RU-106 RH-103M RH-106 TE-125M Evaporator Concentrates 0,D gr0 I< 3(<of)
I S(-oq) l (->C))
so(oS) 2,3(-.f~
~3(-o~
3,3(-oa>
~q (-o~)
I, Pj (- I'I) 5, o(-oe) 6,S(-O'I) q, q(-02,)
sw(~)
I,S(-m)
~,g(-W)
I,S (-b'I )
0(0 Spent Resin Beads QO 9,o h,o g,g(-oi) oO I,<I(-oi )
00 8, f (->>)
6,+(-OI)
<,a(-oI) o,O 2,~((-OI) 8( OI.)-
(of-R) 3, I C-O~)
. r,.(( bl) 3 f(-b>)
r(, (-OI) oo Cartridge Filters 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 I. 3
%BR 7.0(-OI 0.0 0.0 0.0 0.0 0.0 0.0 Disposable Cr d Filters 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.
0.
1 7
.0 I.0 0.0 0.0 0.0 0.0 0.0 Dry Wastes (b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b.)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
Table 11.4-6 SRS OUTPUT ACTIVITIES (Ci/yr/unit) (Sheet 3 of 4)
Nuclide TE-127M TE-127 TE-129M TE-129 TE-131M TE-131 TE-132 TE-134 BA-137M BA-140 LA-140 CE-141 CE-143 CE-144 PR-143 PR-144 NP-239 CR-51 MN-54 FE-55 Evaporator Concentrates
<> i (-os) s.
i (-o+)
l, l (~A
~,e (-o')
o.O c,a
~.~ (os) 0,0 2,g(-O()
v,+(-os) e,q(-os)
~,s(~)
q,s(-oa)
<,0(-os) z, i(-oS)
~,s(-o8)
~l, I(<<)
i,q(-o,")
3, ci (-o>.)
Spent Resin Beads 3.6
'%8 y q(-o))
bo Q,O
~,~(-iv)
C,O I l(>03)
~,i (-~)
p,a(-os)
), n (-or) o,o l,Q
(,8 I'.-o~)
Ih 3,1( -2~3
.'. i (-o2')
J. (.
Cartridge Filters 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 9(~i).
- 2. 4 (+01)
R.Q r
isposable Crud Filters 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.
0 0
~ 6 (+02) 3.6 0.0 Dry Wastes (b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
(b)
,(b)
(b)
(b)
. (b)
(b)
l t)
Table 11.4-6 SRS OUTPUT ACTIVITIES (Ci/yr/unit) (Sheet 4 of 4)
(a)
Nuclide FE-59 CO-58 CO-60 TOTAL Evaporator Concentrates l,s(~ot)
Spent Resin Beads Cartridge Filters
<Co Cion)
Disposable Cr Filters Dry Wastes B,O hoi)
0 PVNGS FSAR RADIATION PROTECTION DESIGN FEATURES 12.3.1.1.1.1 Filters.
Filters in the auxiliary building that accumulate radioactive particles are supplied with the means o perform cartridge replacement with remote tools.
Cartridge replacement of the blowdown demineralizer filter will utilize long handled tools.
Cartridge filters have adequate space for removal, cask load-
- ing, and transport.
A filter handling system has been incorporated into PVNGS for all filters except the low activity blowdown demineralizer filter.
In use, the handling system is placed over the filter in the space normally occupied by its concrete hatch.
The lead base of the system adequately attenuates cartridge radiation.
A remote, closed circuit TV and a leaded glass window provide the operator with a complete view of the filter housing and cartridge while he is performing the changeout with remote tools.
The cartridge can then be lifted into a shield cask placed on the base.
The operator is never exposed to unattenuated radiation from the cartridge.
An overhead monorail is used to transport cask and cartridge to the r
radwaste storage area.
.Backflushable fil ers are designed so that filter inte s may be remotely removed and placed in a shielde for offsite shipping and disposal in the unlik ent that a filter loses its backflush capability.
c flushable filter compartments are designed to ooded for this operation, and long-handled s are provided for removal of filter internals fro the hatch above the flooded co 12.3.1.1.1.2 Ion Exchan ers.
With the exception of potentially radioactive blowdown processing system ion exchangers, ion exchangers for radioactive systems are designed so.that spent resins can be remotely and hydraulically Amendment 12 12 '
2 Februarv 1984
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PVNGS FSAR RADIATION PROTECTION DESIGN FEATURES 12.3.1.1.1.5 Tanks.
Tanks in radioactive and potentially radioactive systems are provided with sloped bottoms and bottom outlet connections whenever practical.
.- A.
Tanks with flat bottoms sloped toward the outlet include:
1, Reactor makeup water tank 2.
Radwaste holdup tanks 3.
Refueling water tank 4.
CVCS holdup tank 5.
Liquid radwaste evaporator condensate storage tanks 6.
Condensate storage tank 7.
Chemical waste tanks 8.
Liquid radwaste monitor tanks These tanks have outlet connections located on the side of the tank as near to the bottom as possible.
B.
Tanks with rounded bottoms and low point outlet connections include:
1.
Spent resin tanks g~
Volume control tank Reactor drain tank
~
Chemical drain tank
~
Equipment drain tank Overflow lines are directed to the liquid radwaste system to-control contamination within plant structures.
Tanks are contained in separate compartments with drains directed to the liquid radwaste system or the chemical and volume control system.
Amendment 12 12.3>>4 Ve'4 vs ~ a ee ~
1 0 0 A
4'
PVNGS FSAR RADIATION PROTECTION DESIGN FEATURES chemical and volume control system, the shutdown cooling
- system, the fuel pool cooling and cleanup system and the primary sampling system.
Shielding is provided as necessary around the following equip-ment in the auxiliary building to ensure the design radiation zone and access requirements are met for surrounding areas.
A.
Letdown heat exchangers and piping B.
Purification, preholdup, and deborating ion exchangers C.
D.
E.
F.
K.
L.
M.
N.
Chemical and volume control tank Charging pumps and piping Shutdown cooling heat exchangers Chemical drain tanks and pumps CVCS and radwaste filters Spent, fuel pool cleanup ion exchangers and filters Spent resin tanks and piping Gas stripper Seal injection heat exchanger Boronometer Process radiation monitor Seal injection filters Shielding is based upon operation with maximum activity conditions as discussed in sections 11.1, 11.2, 11.3, and 12.2.1.
Depending on the equipment in the compartments, the access varies from design radiation Zones 2 through 5.
Corridors are shielded to allow design radiation Zone 2 access.
Operator areas for valve galleries are designed for design radiation Zone 3 access.
Frequently operated valves in high radiation February 1984 12.3-17 Amendment 12
l S
'ADIATIONPROTECTION
(
DESIGN FEATURES areas are provided with remote actuators extending to design radiation Zone 2 or Zone 3 areas.
(See section 12.1.2.3.2M.)
Removable sections of block shield walls, or concrete hatches with offset gaps to reduce radiation streaming are provided for replacement of ion exchangers, and heat exchangers.
12.3.2.2.4 Fuel Building Shielding Design Concrete shield walls surrounding the spent fuel cask loading and storage
- area, fuel transfer and storage pools, and fuel transfer tube between the containment and fuel transfer pool are sufficiently thick to limit radiation levels outside the shield walls in accessible areas to design radiation Zone 2.
Access to the fuel transfer tube through the concrete radiation shield's provided by a heavy concrete, hatch through the roof of the shield as shown in figure 12.3-23.
The hatch is labeled to caution maintenance personnel that there are potentially lethal radiation fields during fuel transfer.
Water in the spent fuel pool provides shielding above the spent fuel transfer and storage areas.
The relationship between dose rate over spent fuel during transfer and 'depth of cover-ing water is shown in figure 12.3-24.
Radiation levels at the fuel handling equipment are not expected to exceed 2.S mrem/h.
The spent fuel pool cooling'and cleanup (SFPCC) system (section 9.1) shielding is based on the maximum activity discussed in section 12.2 and the access and design zoning requirements of adjacent areas.
Equipment in the SFPCC system to be shielded includes the SFPCC heat exchangers, pumps and piping.
(SFPCC filters and ion exchangers are located in the auxiliary building.)
12.3.2.2.5 Radwaste Building Shielding Design Radwaste systems are principally located in the radwaste building.
Additionally, the boric acid concentrator and the Amendment 12 12.3-18 Tahar oi o vier
t PVNGS FSAR PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS F.
Functional Group Display The functional group display is a multi-page, tabular display listing all of the monitor channels of a specified channel type.
The desired channel type is a display parameter and is specified along with the display request.
The information on the display is presented as one line for each channel.
11.5.2.1.1.5.4 Automatic Controls.
Provides automatic control of each channel by the associated field unit micro-computer.
Automatic control includes the following, as appli-cable to the particular channel type:
A.
Automatic activation of the check source and monitor-ing for a proper response at regular intervals specified in the channel critical parameter file.
B.
Automatic stepping of a particulate channel moving paper filter at regular intervals specified in the channel critical parameter file.
11.5.2.1.1.5.5 Remote Manual Controls.
Provides remote manual control of each channel through operation of DCU
~ ~md-4 ~ ~
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+0 La. wert~~<
February 1984 11.5-22A Amendment 12
~ ~ ~
~ ~
~ s PVNGS FSAR PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS iodine channels, the sampler is a lead-shielded filter assembly.
Four Q shielding is furnished for all process and effluent detectors.
12 Particulate collection efficiency is greater than 90% for 0.3m particulates.
Volatile iodine adsorption efficiency is greater than 90%.
Airborne particulate and iodine monitors. and samplers,-
g g-(Ltg (XJ-SQN-RU-OS,
-RU-14,
-RU-141,
-RU-142,
-RU-143,
-RU-144(and XJ-SQB-RU-146) sample isokinetically in accordance with the principles and methods of ANSI N13.1-1969, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities.
The particulate and iodine sample flow is maintained constant over the normal expected range of filter paper and/or charcoal car-tridge differential pressure by an automatic control system.
64Ifn Pl ~
Local flow indication and high-and lowqflow alarm signals are provided.
These signals actuate local alarms and the channel T
o8 failure alarm. g3 articulate
(~c
- XJ-SQN-RU-~~
I+
d
-Q- -~)
'WPI f'1 type and incorporate microcomputer-controlled step
- advance, and feed failure channel failure alarm.
Sampling assembly fittings are provided which allow grab sampling of the moni-
~ ~A~ AVp~ hnOinkW5 ~>44ukC
~~44 tored airstreams.
"ee <~en ep s~>5. peuY(
RVj4~ 4lmu. 1R RIgc~giaz i fey e~rkm 6k mtmMaIg~ KJ'-saswu-oe Q-Ru-Ia ~~gmdiodIq4ot IcT-sgi4;Ru-Ial iI,~u-Ru A Ia A flow-integrating elapsed sample volume indicator"is piovided downstream of each particulate and/or iodine channel.
It has a local digital readout and is resettable to zero.
11.5.2.1.1.7.3 Detector Assembly.
The detector assembly is a completely weatherproofed
- assembly, housing a detector, preamplifier, and radiation check source.
The assembly is capable of withstanding the design pressure and temperature of the piping system of which it is a part, without leakage, collapse of the tube walls, or damage to the detector.
The detector assembly is incorporated in the sampler assembly.
Amendment 12 11.5-26 February 1984
I
PVNGS F SAR PROCESS AND EFFLU T RADIOLOGICAL.
MONITORING AND SAMPLING SYSTEMS 11.5.2.1.4.2 Plant Vent XJ-S N-RU-143 and XJ-S N-RU-144
- PVLR, PVHR Monitor.
The plant vent exhaust is continuously and isokinetically monitored for particulate, I-131, and gaseous activity.
A low and a high range monitor is used to 'cover a range of decades. with ~ decadep'f overlap.
Shielded particulate and iodine samples exist in the high monitor and are removed for analysis.
The low range iodine and particulate samples have a
5 decade detection range.
11.5.2.1.4.3 Fuel Buildin Ventilation Exhaust Monitor,
- FBLR, FBHR Channel "B"
XJ-S B-RU-145 and XJ-S B-RU-146 0
'gaseous-channe
+monitors the fuel building ventilation.'
.,exhaust for release of-activit due to, a fuel handlin acct,dent.
s
~~~ c
~ Cecnlmeeea.
hPm'onrtor erforms the safet function of isola in Me normal ventilation system and activating the essential ventila-tion system (initiates a
FBEVAS signal) on a HIGH-HIGH activity alarm.
Redundancy and diversity are provided by the fuel pool area monitor (JSQARU31) that also actuates the essential ventilation system.
Refer to section 7.3 for a discussion of the safety function of the Fuel Building Ventilation Exhaust monitor.
During normal operation the only significantly abundant isotope which would be rele sed from the fuel build-s~~
g
'; th f,Ap
~
-1
$~o capability is provide A low and a high range monitor is used to cover a range of
~~- decades with~ decade@'f overlap.
Particulate/iodine cartridge samples exist in the low and high range monitor and are removed for analysis.
High range cartridge samplers are shielded.
Both monitors share the same sample ll.ne from the fue building HVAC.
When a
FBEVAS signal is generated, a
class lE HEPA filter system is placed into operation upstream of the monitors'ample point.
Thus filtration will be in operation for the upper range of detection for the low range As,4!Alat ~
COr4I~~
~cuJl akt
) X-l31 aux' o-&~i+)
~
February 1984 11.5-41 Amendment 12
~ I
i t I
~
)
PVNGS FSAR PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS onitor and throughout the range of etection for the hig range monitor.
Because the fuel building HEPA filters operate at 6000 cfm and remove particulates greater than 0.3 microns (see FSAR section 9.4.5.2) the high range monitor is sampling isokinetically within the guidelines of ANSI N13.1-1969.
11Property "ANSI code" (as page type) with input value "ANSI N13.1-1969.</br></br>11" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..5.2.1.5 Area Radiation Monitoring One function of area radiation monitors (except for XJ-SQA-RU-37 and XJ-SQB-RU-38) listed in table 11.5-1 is to indicate and alarm locally and remotely the area dose rate to ensure proper personnel radiation protection.
Several of the area monitors also perform other additional functions or have unique characteristics:
11.5.2.1.5.1 Central Calibration Facilit Area XJ-S N-RU-24 CFA Monitor.
The CFA monitor is located in a small outbuild-ing in the yard of Unit l which is shared by all three Units as a central calibration facility.
11.5.2.1:5.2 Waste Solidification S stem Process Control Area PCA XJ-S N-RU-27 and J-S N-RU-28 Monitors.
These two moni-tors are not connected to any of the communications loops of the RMS.
They are permanently in LOCAL control and are integral parts of the control system for the Waste Solidifica-tion System.
Refer to section 11.4.2.3.1 for a description of their functions.
11.5.2.1.5.3 Deleted 11.5.2.1.5.4 Fuel Pool Area Monitor, Channel "A"
FPAA XJ-S A-RU-31 The monitor is located on a wall overlooking the fuel pool where it monitors for a release of activity due to a fuel handling accident in the fuel building.
The monitor performs the safety function of isolating the normal ventila-tion system and activating the essential ventilation system on Amendment 12 11.5-42 February 1984
~ ~
PVNGS FSAR LIQUID WASTE MANAGEMENT SYSTEMS Table 11.2-1 LIQUID RADWASTE SYSTEM (LRS)
EQUIPMENT DESCRIPTIONS (Sheet 4 of 7)
Pumps (Continued)
Anti-Foam Pump (P-07)
Quantity/unit Type Capacity Design pressure/temp Material Motor rpm/bhp Positive displacement 54 gal/h 93 psig/175F 316 SS 1725/0.5 Recycle Monitor Pump (P-03)
Quantity/unit Type Capacity Design pressure/temp Material Motor rpm/bhp Centrifugal 150 gal/min 275 psig/100F 316L SS 3600/10 LRS Evaporator Main Recycle Pump (P-08)
Quantity/unit 1
Type Capacity Design pressure/temp Material
-Medor rpm/bhp n7A'~ bhp LRS Evaporator Distillate Quantity/unit Type Capacity Design pressure/temp Material Motor rpm/bhp Pumps In-line propeller 10,500 gal/min Xpslg/ CZo e AO-ps~~OF" Carpenter 20 Cb-3
/jd 756/~
(P-09 A,B) 2 Centrifugal 30 gal/min
,5S'>~ i~/ gpss ~
Mp8lg/250F 316 SS 3500/5 Amendment 11 ll~ 2-6 April 1983
PVNGS FSAR LIQUID WASTE MANAGEMENT SYSTEMS Table 11.2-1 LIQUID RADWASTE SYSTEM (LRS)
EQUIPMENT DESCRIPTIONS (Sheet 5 of 7)
Pumps (Continued)
LRS Evaporator Concentrate Quantity/unit Type Capacity Design pressure/temp Material Motor rpm/bhp Pumps (P-10 A,B) 2 Centrifugal 50 gal/min
/$ ~g rye/ Qg5 ~
W'ps-ig+24F-Gould-a-loy 20 1750/2 LRS Steam Condensate Pump Quantity/unit Type Capacity Design pressure/temp Material Motor rpm/bhp (P-11)
Centrifugal 40 gal/min gt ~.-i~~/ a/o/-
-&ps-z:g/-2 8 1P 316 SS 3505/5 Concentrate Monitor Tank Pumps Quantity/unit Type Capacity Design pressure/temp Material Motor rpm/bhp (P-04 A,B) 2 Centrifugal 130 gal/min 275 psig/100F W20 1770/30 Filters LRS Ion Exchanger Prefilters Quantity/unit Size Capacity Design pressure/temp (F-Ol A,B) 5 pm 98%,
25 um 100%
150 gal/min 200 psig/250F April 1983 11.2-7 Amendment 11
PVNGS FSAR GASEOUS WASTE MANAGEMENT SYSTEMS annunciated in the main control room and in the radwaste'ontrol room.
Operating personnel can be dispatched to mitigate-the situation via nitrogen dilution, purge, etc.
An alarm on high-high oxygen (4%), from any of these sources is annunciated in the main control room and, in the radwaste control room.
Under these conditions the waste gas compressors will automatically trip, and nitrogen will be automatically injected into the GRS surge tank.
Automatic nitrogen dilution will mitigate the situation.
In addition, low surge tank pressure automatically initiates an alarm to alert operating personnel of a tank leak which could potentially result in oxygen inleakage to the system.
Thus, it is not necessary for the waste gas surge
- header, surge tank, decay tanks, valves, piping, and compres-sors to be designed to withstand an internal hydrogen explosion.
The air-flow,rate through the.vent is 25,500.standard ft /min, which results in a hydrogen concentration of less than 1%, well below the combustion limit of hydrogen in air.
The gaseous discharge isolation valves will automatically shut on high discharge flow rate, low radwaste building exhaust or hign radiation level in the discharge line.
Potential buildup of hydrogen in the ventilation exhaust sys-tems can come from storage tanks that contain liquids previously processed through the gas stripper.
Consequently, with a gas stripper efficiency of 99.9% and a maximum hydrogen pressure of 50 psig (administrative limit) in the volume control tank, the maximum hydrogen concentration that can exist in the gas space above a liquid surface downstream of the gas stripper is 0.44%,
well below the combustion limit of hydrogen in air.
Another potential source of hydrogen is liquids fed to the equipment drain tank and chemical drain tanks, but'hese will contain only small quantities of, dissolved hydrogen.
The Amendment 6
11.3-8 October 1981
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ea
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(
p~
'l'I 8-8 A g~
1 ra.cLwo ~
pur~, ~ ~a r
~4AA~
~ ~ ~cuX i munch~
4G Mom.hcurd 4+~/mu~. M~~~d~
v~~
pR E 0 ~~ckOJld 4p/~
4 t
I f
N J
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~
0
=
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t 1
PVNGS FSAR GASEOUS WASTE MANAGEMENT SYSTEMS 11.3.1.1.5 Instrumentation The GRS instrumentation is shown in figure 11.3-2.
The, hydro-gen and oxygen analyzers are discussed in section 9.3.2.
The GRS radiation monitors are discussed in section 11.5.
Com-pressor instrumentation necessary for operation can be read at a local panel outside the compressor room.
Remote indication and alarms are provided in the radwaste system control panel area in the radwaste building.
GRS alarm conditions are retransmitted to the main control room.
The automatic isolation valves in the decay tank discharge header are interlocked to close on high radiation signals from the waste gas header monitor, high discharge. flow, or low radwaste building exhaust flow.
Therefore, even during the improbable instance where th'e discharge valve from the wrong decay tank is inadvertantly
- opened, the release would be automatically terminated when the radiation setpoint is exceeded.
The resultant activity released to the environment
.yk n>
would be within technical specifications limits for radio-active gaseous
- releases, 11.3.1.1.6 Hydrogen Control The major sources of hydrogen in the GRS are the off-gas from the gas stripper, the volume control tank, and the reactor drain tank.
These sources will produce a gas consisting pri-marily of hydrogen and nitrogen with trace quantities of oxygen and fission gases.
These sources are piped to the waste gas surge tank from which gas is compressed into decay tanks.
The GRS and its input sources are initially purged at plant startup with nitrogen.
The surge tank (gas surge header),
decay
- tanks, and various input sources are monitored for oxygen and hydrogen as described in section 9.3.2.
The hydrogen and oxygen analyzer sequentially samples the major GRS inputs and on-line decay tank, and continuously samples the gas surge tank.
An alarm on high oxygen (2%) from any of these sources is October 1981 11.3-7 Amendment 6
~ JE tp
~
eg J'
PVNGS FSAR GASEOUS WASTE MANAGEMENT SYSTEMS Sources for the GRS include the gases from:
~
Reactor drain tank
~
Volume control tank
~
Refueling failed fuel detectors o
Gas stripper
~
Reactor vessel vent The high-activity gases accumulate in the waste gas surge tank and are compressed and stored in the waste gas decay tanks.
When the surge tank pressure reaches 3 psig, the compressor selected for operation starts automatically and starts charging the online decay tank. If the surge tank pressure reaches 3.5 psig the standby compressor will automatically start.
Operation of either compressor automatically stops when the surge tank pressure decreases to 0.5 psig.
When decay tank pressure reaches 350 psig, an alarm is actuated, and compressor operation is terminated manually.
Identical compressors are provided to minimize system down time.
Each decay tank is sampled prior to discharge.
No special mixing is considered necessary for the gas.
Each sample is analyzed for radioactivity and the concentration,
- volume, and total radioactivity are recorded.
Isotopic content of the waste gases is determined and recorded as specified in the station manual procedures.
The maximum rates and quantities of radionuclides released from the gaseous waste decav tanks will be in accordance with Wan+
the limits imposed by the~Technical Specifications, The rate of release from the decay tanks into the ventilation exhaust is limited so as not to exceed the release limits of 10CFR20.
Releases are conducted to meet the "as low as is reasonably achievable" objectives of 10CFR50 Appendix I.
11.3-10
~
o
MAINSTEAM SUPPORT STRUCTURE CONTAINMENTBLDG AUXILIARYBLDG FUEL BUILDING EXIIAUSTPOINT PLANTVENT EXHAUST POINT VACUUMPUMP EXHAUST TURBINE BUILDING FUEL BI.OG CONTROL BUILDING AIR IN TAKES RADIYASTEBUILDING DIESEI. GEN BUILDING CONTROL BUILDING LAUNDRY6 DECONTAMINATION FACILITY(UNIT I ONLYI eL CONT PLANT NORTH 57 -0 6+5 ILCONT 153'-6" 124'-0" e'
II L
EXHAUSTPOINTS KEV PLAN Psln Venle Nuclesr Genersling Slslinn I'!IAR PLANT LAYOUI'IR IIITAXE AIID POTENTIAL RELEASE POIIITS Figuto 6.4-l
I