ML20118B960

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Proposed TS 2.9 Re Radwaste Disposal Sys,Deleting 2.9.1 Re Liquid & Gaseous Effluents & 2.9.2 Re Solid Radwaste
ML20118B960
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 09/24/1992
From:
OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20118B958 List:
References
NUDOCS 9210080180
Download: ML20118B960 (52)
v • d • e


Text

g 9 TECIINICAL SPECII1 CATIONS TABl,E Ol' CONTESTS PAGE DEITNITIONS 1 1.0 SAFETY L1h11TS AND LIMITING SAIT:TY SYSTEM SETTINGS 1-1 1.1 Safety Limits Reactor Core 11 1.2 Safety Limit Reactor Coolrat System Pressure 14 1.3 Limiting Safety System Settings. Reactor Protective System 1-6 2.0 LIMITING CONDITIONS FOR OPERATION 24 2.0.1 Ct.oeral Requirements 20 2.1 Reactor Coolant System 21 2.1.1 Operable Components 21 2.1.2 lleatup and Cooldon Rate 23 2.1.3 Reactor Coolant Radioactivity 28 2.1.4 Reactor Coolant System Leakage Limits 2 11 2.1.5 Maximum Reactor Coolant Oxygen and IIslogens Concentrations 2 13 2.1.6 Pressurizer and Main Steam Safety Valves 2 15 2.1.7 Press.arizer Operability 2 16s l

2.1.8 Reactor Coolant System Vents 2-16b 2.2 Chemical and Volume Control System 2 17 2.3 Ecnergency Core Cooling System 2 20 2.4 Containment Cooling 2-24 2.5 Steam and Feedwater Systems 2-28 2.6 Containment System 2 30 2.7 Electrical Systems 2 32 2.8 Refueling Opentions 2 37 2.9 Radioactive-Effluents- \AbTe D type M { ,te m 2-40

-2.9.1-Liquid and Gaseous Effluents -240~

-2.9 2-Solid RadioactiveAVasta 47a-2.10 Reactor Core 2-46 2.10.1 Minimum Conditions for CriticAty 2-48 2.10.2 Reactivity Control Systems and Core Physics Parameter 1.imits 2 50 2.10.3 In-Core Instrumentation 2-54 2.10.4 Power Distribution Limits 2 56 2.11 Containment Building and Fuel Storage Building Crane 2-58 i Amendment No. 32,18,62,54,67,67rl4 fr--

9210080180 920904 PDR ADOCK 05000285 P PDR 1

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'ITERNICAL SPECIFICATIONS .TAntM l

TABLE OF COYrEvrS (ALPHABETICAL ORDER) ,

Cootmund  !

TABLE DESCRIFFION i

Eg g i 35 Minimum Frequencies for Equipment Tests . . . . . . . . . . . . . . . . . . . . . . . . . . 3 20

................................320s

.......,........................320b  !

............................ . . . 3 20c

................................320d 3-4 Minimum Frequencies for Sampling Tests . . . . . . . . . . . . . . . . . . . . . , . . . . . 318

.................................319 5.2 1 Minimum ShiA Crew Composition ................................52 2 10 Post. Accident Monitoring Instrumentation Operating 1.imits . . . . . . . . . . . . . . . . 2 98 -

. . . . . . . . . . . . . . . . . . . . . 2 -9 8a

. . . . . . . . . . . . . . . . . . . . . 2-9 8b -

- 3 12 - -Radioactrve Geneous.Wasse Samplint and-Analysis . . . . . . . . . . , . . . . . . . . . . .--3 . crer.-. ,, . . . . . . . . . . . . . . . . rM S- i r

-3 11- ~Ridio~~a~ctive DijuisWaste~51mpting nad Analysi. . . . . . . . . . . . . . . . . . . . . . , . 3 i

. . . ~~._. u_. -. -~mr3 *73 -

-3 9 Radiological Environment Monitoring Prorrum rwm . - . ,_ ,,- -.,,,,-et-3 46 -

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2-9 RCS Pressure Isolation Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2d 36 Reactor Coolant Pump Surveillance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 27 11 RPS LS S S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 10

................................................110s 1 14 Snubber Visual inspectiors !sterval . . , , . - . . . .

. . . . . . . . . . . . . . . . . . . . 3 79b l 3 13 Steam Generator Tube laspection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .' 3 90 2 11 d

Toxic Gas Monitoring Operating Linuts . . . . . . . . . . . . . . . . . . , , . . . . . . . . 2 100 t

l i-I F

vii .a ==d===# No. 46 -14 5' I

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TABLE 2-4 (Continueo) . .{_g e, r'

d A and B circuits are both actuated by-any one of the fivefVIAS initiating channels /RM-0EO, RM-051, RM-060,-P,M-06),-or-RM-062;-however,anly-RM-050-a nd - RM-051-a re- requ i red - fo r- con ta i runen t- v en t i l a t i on -i so l a t i o/ .

e If minimum operable channel conditions are reached, one inoperable channel must be placed in the tripped condition within eight hours from the time of discovery of loss of operability. The remaining inoperable channel may be bypassed for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from the time of discovery of loss of operability and, if an inoperable channel is not returned to operable status within this time frame, a unit shutdown must be initiated (see Specification 2.15(2)). l 7 f If one channel becomes inoperable, that channel must be placed in the tripped or bypassed condition within eight hours from the time of discovery of loss of operability. If bypassed and that channel is not returned to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> fram the time of discovery of loss of operability, that channel must be placed in the tripped condition within the following eight hours. (See Specification 2.15(1) and exception l associatedwithmaintenance.)

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2-69a knendment No. 88. 446-n yn,i-- $- y ar -- w w r r-v. e va. w ++.m,--v--+e-.a toe,-v-ae er v- "-m- e - - - - , .vo-+ + -s -e' ==.r--.--es =r-* s *n= -w- - - - * - * - ~- - * -m--'-s- ---

-- . . - - - . - - _- - . . . - - - _ - - ----- ~ - . . - .

5.9.3 Soccaal Recons t Special tr.ans shall be submitted to the Regional Administrator of the appropriate NRC Regional (Jfice within the time period specified for each repon. These repons shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification where appropriate:

a. In service inspection repon, re'erence 3.3.
b. Tendon surveillance, reference 3.5.
c. Containment structural teats, reference 3.5.
d. Special maintenance reports.
e. Containment leak rate tests, reference 3.5.
f. Radioactive.cfnuent releases,-reference 2.9, DELETt2D
g. Materials radiation surveillance specimens reports, reference 3.3.
h. Fire protection equipment outage, reference 2.19.
i. Post-acrident monitoring instrumentation, reference 2.21
j. Elecu . t tstems, reference 2.7(2).

l 5.9.4 Unique Reoortine Recuirements a.\ Radioactive Effluent Release Recon

'\ p/

A report covering the operttion of the Fort Calhoun Station during the previous six months'shall be submitted within 60 days after January I and July,l'6f each year per the requirements of 10 CFR 50.36a.

N /

N The radioactive effluent release report shall include a summa /./

ry of the quantities

/b_UdmeJTof radioactive liquid N and ga'seous effluents and solid wastfrele

[3 as outlined in Regulatory Guide l 21, Revision V N

The radioactive effluent release rep ort \ shall include a summary of the meteorological conditions concurrenywith t e release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21',sRevision 1.

/ \

The radioactive efflucrit-release report shall include an a'ssessment of radiation doses from the radioictive liquid and gaseous effluents released from the unit s

during each caler(dar quarter as outlined in Regulatory Guide 1.21} Revision 1.

In additiopthe unrestricted area boundary maximum noble gas gamms' air and beta air dons shall be evaluated. The meteorological conditions concurrent'with the/ '

/

/

5-15 Amendment No. 9,'t'4,33,46,86,

+40,4+3,+33 , 91

. '. Nftachmen 8

a. Semiannual Radioactive Effluent Release Report The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be 1) consistent with the objectives outlines in the ODCM and PCP, and 2) in conformance with 10 CFR 50.36a. and Section IV.B.1 of Appendix 1 to 10 CFR 50.
b. Annual Radiolocical Environmental Operatine Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. De report shall include summaries, interpre*.ations, and analysis of trends of the results of the R ::liological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2)Section IV.B.2, IV.B.3, and IV.C of Appendix 1 to 10 CFR 50.

1 1

IliCilNICAL SPECillCATIONS TAill.E Ol' CONTENTS l'au DEFINITIONS . . . . . . . . . . . . . . . ........ .................................I 1.0 SAITTY LIMITS AND LIMITING SAFETY SYSTEM SPTTINGS . . . . . . . . . . . . . . . . 1 1 1.1 Safety Limits . Reactor Core .... ... .... .............. ........11 1.2 Safety Limit. Reactor Coolant System Pressure ..........................1-4 1.3 Limiting Safety Sy6 tem Settings. Reactor Protective System .. .......... . . . . 1 -6 2.0 1.lMITING CONDITIONS I"OR Ol'ERATION 2-0 2.0.1 General Rtxtu;rements .............. ............... . .. . 2-0 2.1 Reactor Coolant System . ... . .. . ...... ....... ...........21 -

2.1.1 Operable Co.nponents ................. ,.................21 2.1.2 lleatup and Cooldown Rate . . . . ... ........... ... ....... 2-3 2.' 3 Reactor Coolant Radioactivity .. ..... ....... ..............28 2.1.4 Reactor Coolant System Leakage Limits . . . . . . . . . . . . . . . . . . . . . . . . 2 11 2.1.5 Maximum Reactor Coolant Oxygen and llalogens Concentrations . . . . . . . . . 213 2.1.6 Pressurizer and Main Steam Safety Valves . . . ..................215 2.1.7 Pressurizer Operability . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-16a 2.1.8 Reactor Coolant System Vents . ....... .. . . . . . . . . . . . . . . . 2 16 b -

2.2 Chemical and Volume Control system . . ....... ... ...............217 2.3 Emergency Core Cooling System ......... .......... ..... ... . 2-20 2.4 Containment Cooling . . . . .... .. . . .... . . . . . . . . . . . . . . 2 24 2.5 Steam and Feedwater Systetta . . . . . . . . ..... ..... . . . . . . . . . . . . . . 2-2 8 2.6 Containment System . . . . . . . . . . . . . . ...... .................. . 2-30 2.7 Elutrical Systems . . . . . . . . .... .... . . . ... ....... . . . . 2-3 2 2.8 Refueling Operations ......... ..... .... .. .. ....... .... . .... 2-37 2.9 Radioactive Waste Disposal System

................................2-40l 2.10 R eac tor Core . . . . . . . . . . . . . . . . . . . . . . . . . . .. ..... . . . . . . . . . . 2 -4 8 -

2.10.1 Minimum Conditio ts for Criticality . . . . . . . . . . . . . . . . . . . . . . . . . 2 -4 8 2.10.2 Reactivity Control Systems and Core Physics Parameter Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-5 0 2.10.3 in-Core Instrumentation . . . . . . . . . . .... . .. . .... ........ 2-S4 2.10.4 Power Distribution Limits , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 56 4

2.11 Containment Building and Fuel Storage Building Crane .. ......... . . . . . . . 2-5 8 i Amendment No. 32.48,&2.54.H ,M ,

80,84, 4 ,446,

, a TECilNICAL SPECII1 CATIONS. TABl.13 TAftl.E Ol' CONTENTS (Al.PIIABETICAL ORDI:R)

Continued (

IAluI DEscultiiON 1%SE 3-5 Minimum Frequencies for Equipment Tests ........................... 3 20

. ..............................320s

................................3-20b

..... . . . . . . . . . . . . . . . . . . . . . . . . 3 20e

...............................320d 34 Minimum Frequencies for Sampling Tests . .......................... 3 18

...............................319 5.2-1 Minimum Shift Crew Composition . ................. .............52 2 10 Post A.cident Monitoring it trumentation Operating Limits ................298

. . . . . . . . . . . . . . . . . . . . . . 2 -9 8a

. . . . . . . . . . . . . . . . . . . . . 2-9 8 b 29 RCS Pressure Isolation Valves ................. . . . . . . . . . . . . . . . . 2 24 3-6 Reactor Coolant Pump Surveillance .... ............ . . . . . . . . . . . . . 3 -2 7 1-1 RPS LSSS . . . . . . . . ....... ............................... 1 10

....................... ............... . . . . . . . . 1 10s 3 14 Snubber Visualinspection Interval ...............................3-79b 3 13 Steam Generator Tube Inspection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-90 2-11 Toxic Gas Monitoring Operating Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-100 vii Ameulment No. 4M,445,

5.9.3 Special Repens Special reports shall be submitted to the Regiot.L Administrator of the appropriate NRC Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification where appropriate:

a. In-service inspection report, reference 3.3.
b. Tendon surveillance, reference 3.5.
c. Containment structural tests, reference 3.5.
d. Special maintenance reports,
e. Containment leak rate tests, reference 3.5.
f. DELETED l
g. hiaterials radiation surveillance specimens reports, reference 3.3.
h. Fire protection equipment outage, reference 2.19.
i. Post accident monitoring instrumentation, reference 2.21
j. Electrical systems, reference 2.7(2).

3.9.4 Unique Reportine Requirerrents

a. S.cmiannual Radicactive Ef0 tent Release Report The Semin.nual Radioactive Efnuent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January I and July I of each year. The report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be 1) consistent with the objectives outlines in the ODChi and PCP, and 2) in conformance with 10 CFR 50.36a. atid hetion IV.B.1 of Appendix 1 to 10 CFR 50.
b. Annual Radiological Environmental Operatine RepgIl The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before hiay 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the repoiting period. The material provided shall be consistent with the objectives outlined in (1) the ODChi and (2)Section IV.B.2, IV.B.3, and IV.C of Appendix ! to 10 CFR 50, 5-15 Amendment No. 9,24,38,46,86, 440,443,4M 447,

I U.S. Nuclear Regulatcry Commission LIC-92-303A ATTACHMENT B i

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t DISCUSSION JUSTIFICATION, AND NO SIGNIFICANT HAZARDS CONSIDERATIONS DISCUS $10N AND JUSTIFICATION The Omaha Public Power District (0 PPD) proposes to revise the fort Calhoun Station Unit No.1 Technical Specifications to implement Generic letter 89-01 concerning the Radiological Effluent Technical Specifications (RETS), and to revise the requirements for the Containment Radiation High Signal follouing the guidance of NtlREG-0133.

PIppaigd changes to RETS As specified in Generic letter 89-01, it is proposed to relocate RETS from the Technical Specifict.tions to the Offsite Dose Calculation Manual (0DCM). The following is a description of the proposed changes:

1. The definitions for the ODCM and Process Control Program (PCP) were revised to agree with the definitions in Generic Letter 89-01.

Definitions for purge-purging and venting were moved to the ODCM.

2. Technical Specifications 2.9 under Limiting Condition for Operations Section and 3.11 and 3.12 under Surveillance Requirements Section were relocated from the Technical Specifications and incorporated into the CJCH.
3. Tables 3-2, 3-3, and 3-4 were revised to ensure that LC0 requirements, which are currently controlled by Specification 3.12, were retained. The surveillance function and frequency for Containment Radiation High Signal, Area and Post Accident Radiation Monitors, and Primary-to-Secondary leak rate detection radiation monitors in Table 3.2 are updated for consistency. Sampling requirements for steam generator blowdown are being relocated from Table 3-11, which is being deleted, tc Table 3-4. Operating modes are being added to the sampling of steam generator blowdown

! consistent with the actions required by Specification 2.20.

4. Tables 3-9, 3-11 and 3-12 were relocated from the Technical SpecificationsandincorporatedintotheODCM.
5. S)ecifications 2.9 and 3.12 are proposed to retain requirements in tie Technical Specifications that are related to explosive gases.

This was a specific requirement of the Generic Letter. The grab i

sample 2.9.l(2)p~ d.rovisions A 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> are in agreement Limiting with for Condition theOperation present Specification has been l added for the time allowed for hydrogen and oxygen concentrations to be out of ::pecification. This is consistent with the Standard RETS.

i 6. Reporting and records requirements were revised in Section 5.9.4 and l

Sections 5.16, 5.D, and 5.18 under Administrative Controls were added to the Technical Specifications to define administrative details of the ODCM and PCP. Records retention for RETS will be covered under existing Technical Specification 5.10 2.

1

t a .-

1 Administrative chanant j

a. The Table of Contents is being revised to reflect proposed changes.

b, Pape 2-0 is being revised to currect a reference that was changed as a result of the Generic Letter changes.

l

c. Page 2-38 is being revised to delete a reference to the specific  !

arr.cedure %ich implements the independent verification of fuel i burc.up whid is required to move feel directly to Region 2 of the I spent fuel cool. The requirements remain, only the name of the procedure is being deleted. Additionally, wording whit.h reflects the CE Sundard Technical Specifications is being added to clarify movement of irradiated fuel.

d. Roiarence 2 on Pa e 2-63 is being revisej to reflect a Section of the Updrited Safet Analysis Report Containment Radi tion High Signal.(USAR) which better describes the Table 2-4, Item 3B on page 2-69 is being revised to reflect the e.

requirements of CE Standard Technical Specifications. As descr Ged in USAR Section 7.3.2.6 and Specification 2.8(2), the Contatnment Radiation High Signal (CRHS isolates the containment p. essure relief, air sample and purge) system valves. As currently written, it could be implied that all valves which receive a /IAS are required to be closed in order to place the CRHS channels ,n bypass.-

This change clarifies the requirements that only the containment vent and purge valves are required to be closed. A description of these valves is being added to the basis of Specification 2.15 on page 2-66a. A change is also proposed for page 2-66a to revised the term FSAR to the present nomenclature for this document which is the USAR (Updated Safety Analysis Report).

. f. Page 3-Ob is being revised to delete an example of a surveillance test table that will be relocated to the ODCH. Additionally, a typographical error " Code of Federal Requirements," is being corrected to read " Code of Federal Regulations.*

g. Page .1-63b is being revised to include a statement on the bottom of the page indicating that the next page will be page 3 69.
h. Page 5-19 is being revised to add records retention requirements-for  ;

the ODCH and PCP

1. Page 5-196 is beinn revised t) change the references to Sections of 4 10 CFR Part 20 which reflect chan es to 10 CFR Part 20 and to revised the definition of a Very Hi h Radiation Area so that this definition does not conflict with he definition which has been added to 10 CFR Part 20.

3

- = _ -. . --. -. . - - -

, e d.S. Nuc', ear Regulatory Connission ,

LIC-92-303A ATTACHMENT C f

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. _ _ _ _ _ _ _ .. _ _ _ . , _ . . _ . _ _ . . _ _ _ . _ _ _ . - _ . _ . . = . _ . _ . . . _ m f

COMPARISON OF PARAGRAPH NUMBERS FROM TECH. SPECS TO ODCM Tech. Sneh ODCM 2.9.1 Objective 1.0

2. 9.1. A. (1) 1.1.2 2.9.1.A.(2) 1.1.3
2. 9.1. B . (1) 1.2.2 2.9.1.B.(2) 1.2.3 -'

2.9.1.B.(3) 1.2.4

2. 9.1. (1) a. (i) 1.1.1
2. 9.1. (1) a . (ii) 1.1
2. 9.1. (1) b. 4.1.1
2. 9.1. (1) b. (1) 4.1.1.A
2. 9.1. (1) b. (ii) 4.1.1.8
2. 9.1. (1) b. (iii) 4.1.1.C '

2.9.1.(1)c. 4.2.1

2. 9.1. (1) c. (i) 4.2.1.A 2.9.1.(1)c.(ii) 4.2.1.B 2.9.1 (1)c.(iii) 4.2.1.C '

2.9.1 (1)d. 2.1.1

2. 9.1. (1) d. (1) 2.1.1.1
2. 9.1. (1) d. (ii) 2.1.1.2
2. 9.1. (1) d. (iii) 2.1.1.3 2.'9.1. (1) d. (111) 1. 2.1.1.3.A 2.9.1.(1)d.(111)2. 2.1.1'3.B .
2. 9.1. (1) d. (iii) (Notes) 2.1.1.4 2.1.1.5--

2.9.1. (110.1) 2.1.2.2

2. 9.1. (1) e. 2 ) 2.1.2.3 2.9.1.(1)e. 2.12 7.3.A 2.1.L.2.B 2.1.4.4
2. 9.1.- ( 2) a. (i) 1.2.1-2.9.1.(2)a.(ii)

_ _ 1.2 ,

2.9.1.(2)b. 4.2.1 '

2. 9.1~. ( 2) b. (i) 4.2.1.A 2.9.1.(2)b.(ii) 4.2.1.B 2.9.1.(2)b.(iii) 4.2.1.C 2.9.1.(2)c. 4.2.2
2. 9.1. (2) c. (i) _ 4.2.2.A-

?. 9.1. ( 2 ) c. (ii) 4.2.2.B

2. 9.1. (2 ) c. (iii) ~- 4 . 2 . 2 . C __

2.9.1.(2)d. Retained in Tech. Specs.

2.9.1.(2)L. .2.2.1.4 2.9.1.(2)e.1)_ 2.2.1.4.A t

- 2. 9.1. ' 2 ) s . 2 ) 2.2.1.4.B 2.9.1.(2)f. 2".2.2.1 >

2.9.1.(2)g. . _ 2.2.1.1

2. 9.1. ( 2 ) g . (1) . 2.2.1.1.A-

- 2. 9.1. (2 ) g. (ii) 2.2.1.1.C_

2.9.1 (2)g.(iii) 2.2.1.1.B

-2.9.1.(2)g.(iv) 2.2.1.1.D 2.2.1.1.E.

1

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COMPARISO!1 OF PARAGRAPH NUMBERS FROM TECH. SPECS TO ODCM Page Two Tech. Soec. OACli

2. 9.1. (2 ) g. (v) 2.2.:.2.A/B
2. 9.1. ( 2 ) h . (1) 2.2.3.1
2. 9.1. ( 2) h. (i) 2.2.3.1.A 2.2.3.1.B 2.9.1.(2)h.(11) 2.2.3.1.C

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3.11 Objective 5.0 3.11(1) 5.1.1 3.11(2) 5.1.3 3.11(3) 5.1.4 3.11(3)a. 5.1.4.A 3.11(3)b. 5.1.4.B

-3.11(3)b.(Note) 5.1.4.B ,

3.11(4) 5.1.5 3.12.1 Objective 3.0 3.12.1 (1) a . . 1.1.1 3 .12 .1 ( 1) b. 3.1.2 3 .1. 2 . *_

3.1.2.2 3.12.1 ( 1) c .'( i) ( ii) ( iii) Table 3, Part A 3.12.1(1) d. ( i) (ii) (iii) (iv) Table 3, Part A 3.12.1(1)o. Table 3, Noto #4 3.12.1 ( 1) f . 3.1.3 3 .12 .1 ( 2 ) a . .

3.2.1 3.12.1(2) b. (i) (ii) (iii) (iv) Table 3, Part D '

3.12.1( 2) b. (v) Tabic 3, Part B "

3.12.1(2) c. (i) (11) Table 3, Part B Table 3-11, Note (4) 3.3 Table 3-12, Noto (4) 3.3 5.9.4.a. 4.3 5.9.4.b.1. 4.4

-5.9.4.b.1.a. 4.4.1 5.9.4.b.1.b. 4.4.2 5.9.4.b.1.c. 4.4.3 5.9.4.b.1.d. 4.4.4 <

5.9.4.b.1.e. 4.4.5 5.9.4.b.1.e.(1) 4.4.5.1 5.9.4.b.1.(2) 4 4.5.1.A 5.9.4.b.1.(3) 4.4.5.1.B 5.9.4.b.1.(4) 4.4.5.1.C 5.9.4.b.1.(5) 4.4.5.1.D 5.9.4.b.2. 4.5

)

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  • - FORT CALL!OUN STATIO!1 PAGE 1 OF 35 CllEMISTRY MANUAL PROCEDURE q

, CMP-6 kJ PART III RADIOLOGICAL EFFLUENT RADIATION MONITOR CALCULATIONS FC/ CMP /01 082792

a.

t 1 FORT CALHOUN STATION PAGE 3 OF 25 CHEMISTRY MANUAL PROCEDURE f l" aM fi CMP-6 l l

1,0 EFFLUENT MONITOR SETPOINTS .

l 1.1 Liould Effluents l l

There are two liquid discharge pathways to the ,

Missouri River. These pathways originate with the H radioactive liquid waste processing system (monitor or '

hotel tanks) and the steam generator blowdown system.

Both of these pathways empty into the circulating water system which discharges to the Missouri River (see Figure 1). Figure 2 depicts the liquid discharge pathways and associated radiation monitors. Figure 3 depicts the methods of liquid effluent treatment. A detailed discussion of the liquid effluent treatment system is presented in Section 2.1.

The flowrate for dilution water varies with the number [

of circulating water pumps in service and with the operation of the warm water recirculation. Some warm water from the condenser outlet is diverted from the circulating water discharge to upstream of the intake structure to help prevent ice from forming on the circulating water pump intakes during winter months.

The varying dilution flowrate'is accounted for in the dilution calculations for monitor tank and stream generation releases.

Alarm setpoints shall be established-for the liquid offluent monitoring instrumentation to ensure that the concentration of radioactive material released in liquid effluents to unrestricted areas shall be less than the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2.

Cs-137 is the most abundant radionuclide in liquid effluent streams and is used to calibrate the liquid effluent monitors.

FC/ CMP /01 082792'

l I

' FORT CALHotT!1 STATIOft i PAGE ~ OF 21 CHEMISTRY MANUAL PROCEDURE CMP-6 2.1.2 Steam Generator (Continued) 2.1.2.3 to 0.01 uCi/ gram uJs luiva-lent I-131 and at lenot C. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 uCi/ gram dose equivalent I-131.

2.1.2.4 The radioactivity for each blowdown line chall be continuously re-corded. If the process radiation monitor chart recorder is not oper-ational, Steam Generator releases may continue provided that the radioactivity level is recorded manually at least once per four hours during actual release.

2.2 Gaseous Effluent Peleases 2.2.1 Gaseous Auxiliary Buildina Exhaust Stach 2.2.1.1 During release of gaseous radioac-tive effluents from containment pressure relief line to the Auxiliary Building Exhaust Stack, the following conditions shall be met:

A. The Auxiliary Building Exhaust Stack noble gas monitor, iodine campler and particulate sampler shall be operational.

B. The Auxiliary Building Exhaust Stack noble gas radiation mon-itor shall be set in accor-dance with Part III to alarm and automatically terminate the relaase prior to exceeding 10 CFR 20 limits at site boundary (see Figure 1).

C. At least one Auxiliary Build-ing exhaust fan shall be in operation.

FC/ CMP /01 060592

' FORT CALHOUN STATION PAGE E OF 13 <

CHEMISTRY MANUAL PROCEDURE t CMP-6 PART III 1.0 CFFLUENT MONITOR SLTPOINTS . . . . . . . . . . . . . . . 2 1.1 Liquid Effluents . . . . . . . . . . . . . . . . 2 1.2 Liquid Effluent Radiation Monitors . . . . . . . . 3 1.2.1 Steam Generator Blowdown Monitors . . . . . 3 1.2.2 Overboard Discharge Header Monitor . . . . 4 1.3 Gaseous Effluents . . . . . . . . . . . . . . . 7 1.4 Gaseous Effluent Radiation Monitors . . . . . . 8 1.4.1 Auxiliary Effluent Radiation Monitors . . . 8 1.4.2 Auxiliary Building Exhaust Stack Gaseous Activity Monitors . . . . . . . . . . . . . 10 1.4.3 Auxiliary Building Exhaust Stack Iodine Monitor . . . . . . . . . . . . . . . . . 12 1.4.4 Condenser Air Ejector Monitor . . . . . . . 14 1.4.5 Laboratory and Radioactive Waste Processing Building (LRWPB) Exhaust Stack Particulate Monitor (RM-041) . . . . . . . . . . . . . 16 1.4.6 Laboratory and Radioactive Waste Processing Building Exhaust Stack Iodine Monitor ( RM-04 2 )18 1.4.7 Laboratory and Radioactive Wasto Processing Building Exhaust Stack Noble Gas Monitor (RM-043) . . . . . . . . . . . . . . . . . 20 1.5 Simultaneous Release Pathways . . . . . . . . . 22 1.5.1 Liquid Release Pathways . . . . . . . . . . 22 1.5.2 Gaseous Release Pathways . . . . . . . . . 24 2.0 RADIOACTIVE WASTE TREATMENT SYSTEM . . . . . . . . . . . 28 2.1 Liquid Radwaste Treatment System . . . . . . . . 28 2.2 Gaseous Radwaste Treatment System . . . . . . . 29 FC/ CMP /01 081092

FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE f )ffjh(f5 '

PAGE 3 OF 35 CMP-6 4 1.2 Idauld Ef flun.t;_ Radiation _lionitors 1.2.1 Steam Generator Blowdown Monitors (RM-054A and B) 1 These process radiation detectors monitor the flow through the steam generator blowdown ,

lines and automatically close the blowdown l isolation valves t' the monitor high alarm l setpoint is reached. The high alarm  ;

actpoint calculations are based on controlling the discharge at 10 CFR 20 limits of 1.0E-07 pCi/ml for unrestricted areas.  !

The following calculations for maximum concentration and alarm setpoints are valid when steam generator blowdown is the only liquid release pathway. For simultaneous radioactive liquid releases of steam generator blowdown and monitor tank discharge, refer to Section 1.5.1.

The maximum allowable concentration in the blowdown line is calculated as follows:

(1.0E-07 pCl/ml) (X o)

Ya Where:

1.0E-07 pCi/ml = 10 CFR 20 Limit for unidentified radior.uclides at site discharge (I-129, Ra-226 and Ra-228 are not present).

X, = Total dilution flow in the discharge tunnel (gpm). . (Normal flow is based on 1 circulating water pump at 120,000 gpm.

Other flowrates may be used, as required.)

Y, = Blowdown flow ratt (gpm).

(Normal blowdown flow rate is based on 2 transfer pumps with a design flow of 135 gpm each, _

270 gpm total. Other flow rates may be used, as required.)

A, = Maximum allowable blowdown concentration (pci/ml).

FC/ CMP /01 082792

s -- i FORT CALHOUN STATION -PAGE 4.OF 35 CHEMISTRY MANUAL PROCEDURE CMP-6 ,

1.2.1 Steam Generator Blowdown Monitors (RM-054A and B) (Contin ed)

The high alarm setpoint (CPM) =

.85 ( (Sf ) (A,) +B]

Whcre:

.85 = Correction factor for instrument meter error.

Sr = Detector sensitivity factor (CPM /pCi/ml). (Sensitivity based on Cs-137).

A, = Maximum allowable tlowdown line activity (pCi/ml).

D = Background (CPM).

Setpoints may be recalculated based on adjusted dilution-flow and adjusted-blowdown flow.

An alert setpoint will be chosen at a value below the alarm setpoint so that significant increases in activity will be identified prior to automatic actuation of the blowdown isolation valves.

1.2.2 overboard Discharge Header Monitor (RM-055 or RM-055A)

This process radiation monitor provides control of the waste monitor tank effluent by monitoring the overboard header prior to_its discharge into the circulating water discharge tunnel. The concentratier of_ activity at s

discharge is controlled below the 10 CFR 20 limit of 1.0E-07 pCi/ml for unrestricted areas for unidentified isotopes by the high. alarm setpoint which closes the overboard flow ,

control valve.

The following calculatioris for maximum concentration and alarm setpoints are valid when Mon' tor Tank discharge is the only liquid release pathway. For simultaneous radioactive liquid releases of monitor tank discharge ~and steam generator blowdown, refer to Section 1.5.1.

FC/ CMP /01 082792

FORT CALHOUN STATION , PAGE 5 OF 35 CHEMISTRY MANUAL PROCEDURE CMP-6 1.2.2 Overboard Discharge Header Monitor

-(RM-055 or RM-055A) (Continued)

The maximum allowable concentration in the overboard discharge header is:

(1. 0E-07 pCl/ml) (X,)

A, = ,

O Where:

1.0E-07 pC1/ml = 10 CFR 20 Limit for unidentified radionuclides at site discharge (I-129, Ra-226 and Ra-228 are not present).

X, = Total dilution flow in the discharge tunnel (gpm). (Normal flow is based on 1 circulating-water pump at 120,000 gpm.

Other flowrates may be used, as required.)

Yo = Maximum monitor tank discharge flow rate (gpn). (Normal monitor tank maximum flow is 50 gpm. Other flow rates may_be used, as required.)

A, = Maximum allowable activity in discharge header (pCi/ml).

ll FC/ CMP /01 082792

s s' 4

  • - -FORT CALilOUN STATION PAGE 6 OF 35 CHEMISTRY MANUAL PROCEDURE CMP-6 1.2.2 Overboard Discharge Header Monitor (RM-055 or.RM-OSSA) (Continued)

The high alarm setpoint (CPM) =

.85 ( (Sr ) (A o) +B3 Where:

.65 = Correction factor for instrument meter error.

S, = Detector sensitivity factor (CPM /yCi/ml) . (Sensitivity based on Cs-137). '

A, =

Maximum allowable concentration in discharge header (pci/ml).

E = Background (CPM).

An alert setpoint will be chosen-at a value below the alarm setpoint so that significant increases in activity will be identified, prior to. automatic. actuation of the overboard flow control valve.

FC/ CMP /01 082792

,-~_---.r.- - - - - - . - ..

- .c

.gJ 4

- C 2 FORT CALHOUM STATION M D A~ga PAGE:7~OF 35-  :

CHEMISTRY-MANUAL PROCEDURE- wf4MB: -

CMP-6

-1. 3 L Gaceous Effluent;g The gaseous effluent monitoringfinstrumentation for-controlling and monitoring normal radioactive material releases in;accordance with 10 CFR.20, appendix.B,

-Table 2,-Column 1 limits for unrestricted areas (see Figure 1), are summarized as follows:

A. Auxiliary Buildina - The Auxiliary.

Building ExhaustLStack receives discharges ,

from the vaste gas decay tanks, contain-ment purge, containment' vent systems and -

the auxiliary building ventilation. system.

Effluents are monitored by RM-062, a noble gas. activity monitor. Additionally, noble gas activity monitor,_RM-051, provides redundant back-up monitoringfcapabilities to the RM-062 monitor. Iodine monitoring-and sampling capabilitiesLare provided-by-RM-060. Particulate monitoring is

_provided by RM-061. Redundant particulate monitoring is-provided by RM-050.~ Ven-I tilation Isolation Actuation Signal (VIAS)L is actuated by exceeding a monitor's alarm setpoint. -Actuation of-VIAS will' isolate' '

releases from containment.and waste gas decay _ tanks. The Auxiliary Building

' Exhaust fans will remain in operation.

B. Laboratory and Radioactive Waste Process-ino Buildinc~(LRWPB) - Noble gas, iodine,-

and particulate monitoring is provided.by-t Radiation _ Monitors RM-043, RM-042, and RM-041, respectively. These radiation monitors do-not serve a control function.

C. Condenser Off-Gas Monitors - Noble-gas activity is monitored-by RM-057. .The condenser of f-gas Dbs discharged directly to the: environment. Exceeding the high alarm setpointfon RM-057=will activate.

~

isolation of main' steam to the1 Auxiliary.

  • Steam System.

A' gaseous' radioactive waste flow diagram with the applicable, associated radiation monitoring instru-mentation ard controls is presented as Figure'4. --The gaseous waste disposal system is presented'in Figure

5. -A' detailed discussion!of the gaseous effluent

{ treatment system is'presentednin Section-2.2.'

j h

i FC/ CMP /01 082792

FORT CALHOUN STATION .. PAGE 8 OF 35 CHEMISTRY MANUAL PROCEDURE

' k CMP-6 l

1.4 Gaseous Effluent Radiation Monitors 1.4.1 Auxiliary Building Exhaust Stack Particulate Monitors (RM-061/RM-050)

Either of these monitors may be used to measure airborne particulate activity in the exhaust stack. The detector is located adjacent to a section of moveable filter paper on a capstan drive. The monitor alarm setpoint is based on 10 CFR 20 limits of 1.0 E-10 pCi/cc at the site boundary.

The following calculations for maximum release rate and alarm setpoint are valid when the Auxiliary Building Exhaust Stack is the only gaseous release pathway. For simultaneous gaseous releases from Auxiliary Buildin, Exhaust Stack, condenser off-gas, and the LRWPB Exhaust Stack, refer to Section 1.5.2.

The maximum allowable release rate for stack particulates is calculated as follows:

(1. 0E-10 pCi/cc) x (1.0E+06cc/m3) = 2.vd+0' /Ci/sec (5. 0E-06 sec/m )

3 Where:

1.0E-10 4Ci/cc = 10 CFR 20 Limit at site boundary for unidentified isotopes.

5.0E-06 sec/m3 = Annual average dispersion =

factor at the site boundary.

1.0E+06 cc/m3 = Constant of unit conversion.

The high alarm setpoint (CPM):

( 2 . 0 E+ 01) (S,.) ( F,) ( T)

Setpoinc = .85 [ +B3 (Fy)

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_. =

FORT CALHOUN STATION PAGE 9 OF 35-CHEMISTRY MANUAL PROCEDURE CMP-6 1.4.1 Auxiliary Building Exhaust Stack Particulate Monitors (RM-061/RM-050) (Continued)

Where:

.85 = Correction for-instrument meter error, sr = Detector sensitivity factor (CPM /yCi). (Sensitivity based on Cs-137).-

F, = Monitor sample flow rate (SCFM).

T = Effective monitor responseftime (sec).-

F, = Auxiliary Building Exhaust stack-flow rate (SCFM). (Default maximum flow rate is 122500 cfm for 3 Auxiliary Building exhaust-fans and 2 containment purge fans in operation. Other_ flow rates may be used, as required.)

B = Background (CPM).

An alert setpoint'will be chosen at a value below the alarm setpoint so that significant increases in activity will be identified, prior to exceeding the alarm setpoint.

FC/ CMP /01 082792

h"f FORT CALHOUN STATION ',

PAGE 10 OF 35 CHEMISTRY MANUAL PROCEDURE e i CMP-6 1.4.2 Auxiliary Building Exhaust Stack Gaseous Activity Monitors (RM-062/RM-051)

Either of these monitors may be used to measure gaseous activity in the exhaust stack.-

The gas is monitored after. passing through a particulate filter. The monitor controls gaseous activity releases so that the 10 CFR 20 limit for the unrestricted areas of 3.0E-07 pCi/cc, based upon Xe-133, is not exceeded. The Ventilation Isolation Actuation Signal is initiated when the high alarm setpoint is reached.

The following calculations for maximum release rate and alarm setpoint_are valid when Auxiliary Building Exhaust Stack is the only gaseous release pathway. For simultaneous gaseous releases from Auxiliary Building Exhaust Stack,-condenser off-gas and the LRWPB Exhaust Stack, refer to Section 1.5.2.

The maximum allowable release rate for stack gaseous activity is calculated as follows:

(3. 0E-07 pCi/cc) x (1.0E4 06 cc/m ) = 6 . 0 E+ 0 4 p Ci/sec 3

(5. 0E-06 sec/m )3 Where:

3.0E-07 pCi/cc = 10 CFR 20 Limit at site boundary (based upon Xe-133).

5.0E-06 sec/m3 = Annual average dispersion factor-at the site boundary.

1.0E+06 cc/m3 = Constant of unit conversion.

The high alarm setpoint (CPM):

(6 . 0 0E+ 04 ) ( S,) (60)

Setpoint = .85 [

(Fy ) (28317)

FC/ CMP /01 082792

, '4 FORT CALh0UN STATION PAGE 11 OF 35 CHEMISTRY MANUAL PROCEDURE CMP-6 1.4.2 Auxiliary Building Exhaust Stack Gaseous Activity Monitors (RM-062/RM-051) (Continued)

Where:

.85 = Correction for instrument meter error.

Sr = Detector sensitivity factor (CPM / pCi/cc). (Sensitivity based on Xe-133) 60 = Conversion (seconds to minutes).

28317 = Conversion factor (ft2 to cc).

4 Fy = Auxiliary Building Exhaust stack flow rate (SCFM). (Default maximum flow rate is 122500 cfm for 3 Auxiliary Building exhaust fans and 2 containment purge fans in operation. Other flow rates may be used, as required.)

B= Background (CPM).

An alarm setpoint will be chosen at a value below the alarm setpoint so that significant increases in activity will be identified, prior to actuation of VIAS.

FC/ CMP /01 082792

FORT CALHOUN STATION PAGE 12 OF 35 CHEMISTRY MANUAL PROCEDURE ' 'f CMP-6

1. 4 . 3 - Auxiliary Building Exhaust Stack Iodine Monitor (RM-060)

RM-050 monitors the gaseous waste discharged from the exhaust stack for Iodine-131 activity by continuously counting a charcoal-cartridge and pre-filter through which a sample of exhaust stack air is passing at a known rate.

The monitor alarm setpoint is based on t ae ' 10 CFR 20 limit for Iodine-131 at the site boundary.

The following calculations for maximum release rate and alarm setpoint are valid when Auxiliary Building Exhaust Stack is the only gaseous release pathway. For simultaneous gaseous releases from Auxiliary Building Exhaust Stack, condenser off-gas and the LRWPB Exhaust Stack, refer to Section 1.5.2.

The maximum allowable release rate for stack iodine is calculated as follows:

(1. 0E-10 pCi/cc) x (1. 0E+06 cc/m 3) = 2 . 0 E4 01 p Cl/sec (5.0E-06 sec/m ) 3 Where:

1.0E-10 pCi/cc = 10 CFR 20 Limit at site boundary (based upon I-131).

5.0E-06 sec/m3 = Annual average dispersion factor at-site boundary.

1.0E+06 cc/m3 = Constant of unit conversion.

The high alarm setpoint (CPM):

. ( 2 . 0 E+ 01) (S,.) (F y ) ( T) (E)

Setpoin t = . 85 [ +B]

(Fy)

FC/ CMP /01 082792

FORT CALHOUN. STATION f PAGE 13 OF 35 CilEMISTRY MANUAL PROCEDURE CMP-6  !

i 1.4.3 Auxiliary Building Exhaust Stack Iodine Monitor (RM-060) (Continued)

Where:

.85 = Correction for instrument meter error.

Sr = Detector sensitivity factor (CPM /pCi), (Sensitivity based on I-131)

F, = Monitor sample flow rate (SCFM).

T = Effective monitor response time (sec).

F, = Auxiliary Building Exhaust stack flow rate (SCFM). (Default maximum flow rate is 122500 cfm for 3 Auxiliary Building exhaust fans and 2 containment purge fans in operation. Other flow rates may be used, as required.)

=

E Charcoal filter collection efficiency.

B = Background (CPM).

An alert setpoint will be chosen at a value below the alarm setpoint so that significant increases in activity will be identified.

4 FC/ CMP /01 082792

  • ( .

FORT CALHOUN STATION PAGE 14 OF 35 CHEMISTRY MANUAL PROCEDURE CMP-6 1.4.4 Condenser Air Ejector Monitor (RM-057)

This monitor is located in the turbine.

building and monitors the condenser off-gas.

The purpose of this monitor is to monitor the condenser off-gas discharges so that the 10 CFR 20 limit for unrestricted areas of 3.0E-07 nCi/cc, based upon Xe-133, is not exceeded.

The following calculations for maximum release rate and alarm setpoint are valid when conaenser off-gas is the only gaseous release pathway. For simultaneous gaseous releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack, refer to Section 1.5.2.

The maximum allowable release rate for condenser air ejector monitor is as follows:

(3. 0E-07 pCl/cc) x (1.0E+06 cc/m 3) = 6 . 0E+ 04 p Cl/sec (5.0E-06 sec/m ) 3 Where:

3.0E-07 4Ci/cc = 10 CFR 20 Limit at site boundary (based upon Xe-133).

5.0E-06 sec/m8 = Annual average dispersion factor at the site boundary.

1.0E+06 cc/m3 = Constant of unit conversion.

The high alarm setpoint (CPM):

. (6 . 00 E+04 ) ( S,,) (60)

Se cpo2n c = . 85 [

(Fy) (28317) l' l

l 082792

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  • PAGE 15 OF 35 FORT CALHOUN STATION "

CHEMISTRY MANUAL PROCEDURE CMP-6 1.4.4 Condenser Air Ejector Monitor (RM-057)

-(Continued)

Where:

.85 = Correction for instrument meter error.

Sr = Detector sensitivity factor (CPM /gCi/cc). (Sensitivity based on Xe-133) 60 = Conversion (seconds to minutes).

28317 = Conversion factor (ft3 to cc).

F, =

Vent stack flow rate (SCFM) .

Default maximum flow rate is-4755 scfm (3 vacuum pumps in hogging mode.- Other flow rates may be used, as required.)

B = Background (CPM).

An alert setpoint will be chcsen at a value below the alarm setpoint so that_-significant increases in activity will be identified, allowing time for corrective actions prior to exceeding the alarm setpoi7t and tripping of the auxiliary steam supply calve, RCV-978.

FC/ CMP /01 082792 L

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FORT CALHOUN STATION

  • d PAGE 16 OF 35 CMEMISTRY MANUAL PROCEDURE CMP-6 1.4.5 Laboratory and Radioactive Waste Processing Building (LRWPB) Exhaust Stack Particulate Monitor (RM-041)

This monitor is used to measure airborne particulate activity in the LRWPB exhaust stack. The detector is located adjacent to a removable filter paper. The monitor alarm setpoint is based on 10 CFR 20 limits of 1.0E-10 #Ci/cc at the site boundary.

-The following calculations for maximum release rate and alarm setpoint-are valid when LRWPB Exhaust Stack is the only gaseous release pathway. For simultaneous gaseous releases from Auxiliary Building Exhaust Stack, condenner off-gas, and the LRWPB Exhaust Stack, refer to Section 1.5.2.

The maximum allowable release rate for-stack-particulates is calculated as follows:

(1. 0E-10 p Ci / cc) x (1. 0E+06 cc/m ) 3 = 2. 0E+01 pci/sec (5.0E-06 sec/m ) 3 Where:

1.0E-10 pCi/cc = 10 CFR 20 Limits at site boundary for unidentified isotopes.

5.0E-06 sec/m3 = Annual average dispersion factor at the site boundary.-

1.0E+06 cc/m2 = Constant of unit conversion.

The high alarm setpoint (CPM):

. ( 2 . 0 E+ 01 ) - ( S,.) (F) ( T) -

l +B1 Setpoint = .85 (Fy) l FC/ CMP /01 082792

, =.a FORT CALHOUN STATION PAGE 17 OF 35 CHEMISTRY MANUAL PROCEDURE ~*h*'.fIk*"'

b '

CMP-6 1.4.5 Laboratory and Radioactive Waste Processing Building (LRWPB) Exhaust Stack Particulate Monitor (RM-041) (Continued)

Where:

.85 = Correction for instrument meter error.

Sr = Detector' sensitivity factor (CPM /pci). (Sensitivity based on Cs-137),

F, = Monitor sample flow rate (SCFM).

T = Effective monitor response time (sec).

F., = LRWPB Exhaust stack flow rate (SCFM). (Default maximum flow rate is 28700 cfm. Other flow rates may be used, if required.)

B = Background (CPM).

An alert setpoint will be chosen at a value below the alarm setpoint so that significant increases in activity will be identified, prior to exceeding the alarm setpoint.

This monitor alarms in the Control Room.

There are no automatic control functions associated with the actuation of the alarm.

FC/ CMP /01 082792

FORT CALHOUN STATZON CHEMISTRY HANUAL PROCEDURE h 'f PAGE 18 OF 35 CMP-6 1.4.6 Laboratory and Radioactive Waste Processing Building Exhaust Stack Iodine Monitor (RM-042)

RM-042 tronitors the gaseous waste discharged from the LRWPB for Iodine-131 activity by continuously counting a charcoal filter cartridge through which a-sample of LRWPB exhaust air is passing at a known rate.

The monitor alarm setpoint is based on the 10 CFR 20 limit for Iodine-131 at the site boundary.

The following calculations for maximum release rate and alarm setpoint are valid when LRWPB Exhaust Stack is the only gaseous release pathway. For simultaneous gaseous releases from Auxiliary Building Exhaust Stack, condenser off-gas, and the LRWPB Exhaust Stack, refer to Section 1.5.2.

The maxirum allowable release rate for stack iodine is calculated as follows:

(1. 0E-10 pCi/cc) x (1. 0E+06 cc/m3 ) = 2. 0E+01 p Ci/sec (5.0E-06 sec/m ) 3 Where:

1.0E-10 4Ci/cc = 10 CFR 20 Limit at site boundary (based upon I-131).

5.0E-06 sec/m 3 = Annual average dispersion factor at the site boundary.

1.0E+06 cc/m' = Constant of unit conversien.

The high alarm setpoint (CPM):

Se tpoin c = . 85 ( 2 . 0 E+ 01) (S r ) (F) ( T) (E)

[ +B]

(Fy)

\

FC/ CMP /01 082792 )

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,. N.

FORT CALHOUN STATION PAGE 19 OF 35- ,

CMP-6 CHEMISTRY MANUAL PROCEDURE 1.4.6 Laboratory and Radioactive Waste Processing Building Exhaust Stack Iodine Monitor-(RM-042)

(Continued)

Where:

.85 = Correction for instrument meter error.

Sr = Detector sensitivity factor (CPM /pC1). (Sensitivity based on I-131)

F,

  • Monitor sample flow rate (SCFM).

T = Effective monitor response time (sec).

F, = LRWPB Exhaust stack flow rate-(SCFM). (Default flow rate is 28700 cfm. Other flow rates may be used, if required.)

E = Charcoal filter collection efficiency.

B = Background (CPM).

An alert setpoint will be chosen at a value below the alarm setpoint so that significant increases in activity will be identified.

This monitor alarms in tho' Control Room.

There are no automatic control functions associated with the actuation of the alarm.

FC/ CMP /01 082792

,- s.

FORT CALHOUN STATION TJ 4 PAGE 30 OF 35 CHEMISTRY MANUAL PROCEDURE .

J%.1[%p- . CMP-6 1.4.7 Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Monitor (RM-043)

RM-043 is located in the Radwaste Building and samples the LRWPB Exhaust Stack. The monitor alarm setpoint is based on the 10 CFR 20 limit for Xe-133 at the site boundary.

The following calculations for maximum release rate and alarm setpoint.are valid when the LRWPB Exhaust Stack is the only gsseous release pathway. For simultaneous gaseous releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack, refer to Section 1.5.2.

The maximum allowable release rate for RM-043 is as follows:

(3. 0E-07 pCi/cc) x (1. 0E+06 cc/m ) = 6. 0E+04 p Ci/sec 3

(5.0E-06 sec/m ) 3 Where:

3.0E-07 pCi/cc = 10 CFR 20 Limit at site boundary (based upon Xe-133).

5.0E-06 sec/m3 = Annual average dispersion factor at the site boundary.

1.0E+06 cc/m3 = Constant of unit conversien.

The high alarm setpoint (CPM):

( 6 . 0 0 E+ 0 4 ) ' ( S,.) (60)

Se tpoin c = . 85 ( +B]

(Fv) (28317)

FC/ CMP /01 082792

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FORT CALHOUN STATION d e 2-A PAGE 21 OF 35 CHEMISTRY MANUAL .DROCEDURE k i**'tIl C T r

CMP-6 1.4.7 Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Monitor (RM-043) (Continued)

Where:

.85 = Correction for instrument meter error.

Sr = Detector sensitivity factor (CPM /pCi/cc). (Sensitivity based on XE-133) 60 =

Conversion (seconds to minutes).

28317 = Conversion factor (ft8 to cc).

F, = LRWPB Exhaust stack flow rate (ECFM). (Default flow rate is 28700 cfm. Other flow rates may be used if required.

B = Background (CPM).

This monitor alarms in the Control Room.

There are no automatic control functions associated with the actuation of the alarm.

l l

l FC/ CMP /01 082792 l

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= FORT CALHOUN STATION A]8*N['[i7;

$7/ PAGE 22 OF 35 CHEMISTRY MANUAL PROCEDURE 5 CMP-6 1.5 Simultaneous Release Pathways 1.5.1 Liquid Release Pathways >

The liquid radiation monitors (RM054A and B.-

RM055, and RM055A) control liquid release 6'so-that 10 CFR 20 limits of 1.0E-07 pCi/ml for unidentified isotopes in unrestricted areas are not exceeded. There are two liquid release pathways that contribute to the con ~

centration at discharge to unrestricted Creas.

These are Steam Generator Blowdown and Monitor Tank Overboard Discharge-Header. When mont-than one pathway is Utilized for radioactive-releases, it is necessary to adjust the alarm -

setpoints given in Section 1.2 so that unre-stricted area concentration limits are not exceeded.

The calculations for the alarm setpoints for the liquid effluent monitors will be adjusted as follows:

A, = K, A, + Kg 1A K, (1,0E-07 Cd/ml) (X,) K (1. 0E-07 pCl/ml) (X,)

A' = Yo

+ 3 Y1 Where:

A, = Sum of individual maximum allowable concentrations for Steam-Generator and Monitor Tank prior.to dilution for simultaneous liquid releases (pci/ml)

Ao =

Maximum allowable concentration in Steam Generator t?.owdown Line (pCi/ml)

A1 =

Maximum allowable concentration in Monitor Tank-Discharge Line (pci/ml)

K, = Proportionality constantLfor Steam m

Generator (See Table 1)

'K 1 = Proportionality constant for Monitor Tank (See Table 1)

X, u Total dilution flow in Discharge Tunnel (GPFi)

FC/ CMP /01 082792

-- FORT CALHOUN STATION '

PAGE 23uOF 35 CHEMISTRY MANUAL PROCEDURE CMP-6 1.5.1 Liquid Release Pathw'ys a (Continued; Where:

Yo = Steam Generates Blowdown flowrate (GPM)-

Y3 = Monitor Tank Discharge flowrate (GPM)

The High Alarm Setpoint for Steam Generator Blowdown monitors, RM054A and B, will then be: '

Alarm Setpoint (CPM) =.85 (K, S r, A, + B,)

The High Alarm Setpoint for Monitor Tank Discharge monitors, RM055 and SSA, will then be:

Alarm Setpoint (CPM) = .85 (K Sr ,A +B]

1 1 1 Where:

Sr = Detector Sensitivity factor for RM054A/B, CPM / (pCi/ml) , based on Cs-137.

Sri = Detector Sensitivity factor for RM055/55A, CPM / (gCi/ml) , based on Cs-137.

A, = Maximum allowable concentration in SG Blowdown line. (#Ci/ml)

A1 = Maximum allowable concentration in-MT Discharge line. (gCi/ml)

= RM054 A or B background B.

countrate. (CPM)

Bi = RM055 or 55A background countrate. (CPM)

C FC/ CMP /01 -082792

I

. . FORT CALHOUN STATION D '

PAGE 24 OF 35 CHEMISTRY MANUAL PROCEDURE D L% CMP-6 1.5.1 Liquid Release Pathways (Contlnued)

Where:

K., Kt = Proportionality constants.

See Table I.

1.5.2 Gaseous Release Pathway The gaseous radiation monitors (RM041, RM042, RM043, RM057, RM060, RM061, and RM062) control gaseous releases so that 10 CFR 20 limits of 3.0E-07 pCi/cc for gases and 1.0E-10 #C1/cc for iodines and particulates in unrestricted areas are not exceeded. There are three pathways that contribute to the concentration at site boundary. These are the Auxiliary Building Exhaust Stack, Condenser Off-gas, and the LRWPB Exhaust Stack. When more than one pathway is utilized for radioactive releases, it is necessary to adjust the alarm setpoints given in Section 1.4 to ensure that unre-stricted area concentration limits are not exceeded.

The calculations for the alarm setpoints for the gaseous effluent monitors will be adjusted as follows:

The maximum allowable release rates for simultaneous releases is:

Conci Max. Release Race = XRii=[K 1 [o oo i

Xl0 Where:

R= RM061/RM050 release rate (pCi/sec)

R t

= RM062/RM051 release rate-(pCi/sec)

R2 = RM060 release rate (pCi/sec)

R3 = RM057 release rate (pCi/sec)

R= RM041 release rate (pCi/sec)

R3 = RM042 release rate (pCi/sec)

R6 = RM043 release rate (pCi/sec)

K, - K, = Proportionality constants. See Table 1.

Conct = Radionuclide concentration for the monitor of interest.

FC/ CMP /01 082792

,. . FORT CAIllOUN STATION- 'PAGE 35 OF 35 CHEMISTRY. MANUAL PROCEDURE - -

CMP ' '

1.5.2 Gaseous Release' Pathway (Continued)

The maximum release rate is then:.

Ko (1.0E-10 pCi/ cc) K 1 (3.0E-07 pCl/cc) K2 (1. 0E-10 CJ/ce)

[ '

5. 0E-06 sec/m3 5.0E-06 sec/m' 5.0E-06 sec/m3 K 3 (3.0E-07 pCl/cc) K4 (1. 0E-10 pCf /ce) K,(1,c3 10 pcj/ce)
5. 0E-06 sec/m3 5.0E-06 sec/m3 5. 0E-06 sec/m 3 Ks (3.OE-07 pCl/cc) cc 5.0E-06 sec/ms g* X. Re e e Ra te The alarm setpoints for the gaseous affluent -

monitors will then be:

( .0 E+01) (Sr) (Fg) (W + B 1 RM061/5 0 = . 8 5 ( K, Fy RN062/51 = . 85 [ K, 'O WI I F) (6 0) *B]

Fv (28317)

+

RM060 = , 8 5 [K2

) ( e) (Fs) ( T) (E)

-Fy

. E+04) ,'Sy) ( 6 0 )

RM057 = . 85 [K3 (Fv) I'.8317)

(2. 0 E+01) - (Sr ) (F,) ( T)

RM041 = . 85 [K4 +B]

(Fy)

(2. 0 E+01) (S,) (F 3) (T) (E)

RM042 = . 8 5 (K3 (Fy)

RM043 = . 8 5 [ K,

.0 DOC (S p) (60) +B1 (Fv) (28317)

Where:

FC/ CMP /01 082792

i l FORT CALHOUN STATION PAGE 25 OF 21 CHEMISTRY MANUAL PROCEDURE I CMP-6

?ABLE 3 Eadiation and Enytromentat wonitors Soer eilitv #MJi r Wn t s Catly "onthly Latterly Source Checti' i

' Charneg I tourcq Chamen Refveting IA. Li4Jtd Mmitors thectl Chect(') W . Test (3) CalibrattonO) Priortg3 Releasel ,

RM 054 A/B x0)

  • x x x I:M-055 /55 A 59) x x x l

Daily Monthly Juarterty Chame Source Chect

' Sourcq Channet Refueling Prior t B. Caseous Manitors thectl) Cneckl ') Fmc. Test (3) CalibraticM 'I ReleaselgI a4 043 x x x x -

l RM 057 4 4 x x -

l l 94 062/51(6) x g x x x Monthly Annual j

Operatigns Airflow C. Envitnanti. Manitors i Checkl') Calibration (0) i

{ RM 035 - 039  ; x x I, I

toGTIS:

(1) Docunentation is provided by signof f en 09-ST-SHIFT-0001.

(2) cocumentation is provided by signoff on IC-st RM 0050.

-(3) Docunentation is provided by signof f on IC+St-RM-0050.

(4) Docunentation is provided by conotetton of acproortete calibration procedure.

Air or liquid flowrote calibrations nust be incitoed for RM-054 A/8 and RM 043, RM 057, and RM-062/51.

(5) Occunentation is provided by signof f on appticable Release Permit Form (6) RM 051 will be substituted for RM-062 when it is sancting the Auxiliary Building ventitation Stack.

l (7) Docunentation is provided by signof f on IC-ST RM 0100.

{ (8) Docuwntation is provided by cocoletion et calibration proceours I

(9) Visual flowcheck daily FC/ CMP /01 080592

. *c

.- . FORT CALHOUN STATION PAGE 26 OF 35 CHEMISTRY MANUAL PROCEDURE CMP-6 1.5.2 ' Gaseous Release Pathwa'y (Continued)

.85 = Correction factor for instrument meter error.

K,

  • Ks = Proportionality contents. See Table 1.

=

Sr Detector sensitivity factor.

Fs = Monitor sample flow rate.

T =

Effective monitor response time.

E =

Charcoal filter collection efficiency.

Fy =

Vant stack flowrate. (Coindenser off-gas flowrate for RM057, LRWPB Exhaust stack flow rate for RM041/42/43, Auxiliary Building Exhaust Stack flow rate.

for RM061/50, 62/51 and 60).

B = Monitor background count rate.

60 =

Constant of unit conversion.

(60 sec/ min).

FC/ CMP /01 082792

=;

  • * . FORT CALHOUN STATION PAGE 27 OF~35 CHEMISTRY MANUAL PROCEDURE CMP-6 TABLE 1 Proportionally Constants for Simultaneous Release Pathways
a. Liquid Effluents Ko +K 51 1

Ko = .30 RM054A/B Ki = .70 RM055/55A

b. Gaseous Effluents E K $1 i

Ko = .05 RM061/50 Ki = .40 RM062/51 K2 = .35 RM060 K3 = .05 RM057 K. = .05_ RM041 K3 = .05 RM042 K3 = .05 RM043 NOTE The constants are based on prior knowledge-and may be updated as necessary to provide for plant operations.

FC/ CMP /01 082792 a

~..

, (

. *

  • FORT CALHOUN STATION PAGE 28 OF 35 CHEMISTPY MANUAL PROCEDURE i- -

CMP-6 2.0 RADIOACTIVE WASTE TREATMENT SYSTEM 2.1 Licuid Radwaste Treatment System The major equipment or subsystem (s) of the liquid radweste treatment system are comprised of the waste filters, monitor tanks, and evaporator. This equip-ment, including associated pumps, valves and piping, is used in different combinations on an as-needed basis to process the liquid effluent to provide complience with the as low as is reasonably achievable philosophy and the applicable section of 10 CFR Part

20. The liquid radwaste treatment system is oescribed in Section 11.1.2 of the USAR. For effluent release points and monitor locations refer to P&ID's 11405-M-100, M-9 and M-8.

A filtration / ion exchange (FIX) system may be utilized for processing liquid radwaste in the event the waste:

evaporator is not in service.- The system consists _ofa a booster pump, charcoal"pretreatment-filter, and= ~ ~ ~ ~ ~ ~ ' ~

pressure vessels containing organic / inorganic resins, which can be configured for optimum performance. The effluent from the FIX system is directed to the monitor tanks for release.

Waste filters (WD-17A and WD-17B) are used only on those occasions when considered necessary, otherwise the flows from the 1;r activity fluids may bypass the filters. No credit ior decontamination factors 4

(iodines, Cs, Rb, others) was taken for these filters during the Appendix I dose design objective evalua-tion; therefore, the inoperability of these filters does not affect the dose contributions to any indivi-dual in the unrestricted areas via liquid pathways.

~,

The inoperability of waste filters will not be considered a reportable event in accordance with 4 Specification 2.9.1(1)c.

Every effort will be made to process all liquid waste, except from the hotel waste tanks, through the evaporator or FIX before entering the monitor tanks.

If the radioactive liquid waste is discharged without processing and it appears that 1/2 of the annual objective will be exceeded during the calendar quarter, a special report shall be' submitted to the commission pursuant to Specification 2.9.1(1)c within 30 days.

The quantity of radioactive material contained in each

, unprotected outdoor liquid holdup tank shall not 2xceed 10 curies, excluding tritium and dissolved or entrained noble gases.

FC/ CMP /01 082792 1

. i

'a

  • a- FORT CALHOUN STATION M

(I 'i ""[i PAGE 29 OF 35 CHEMISTRY MANUAL PROCEDURE CMP-6 2.2 Gaseous Radwaste Treatment Systsm The waste gases at Fort ralhoun Station are collected in the vent header where the gas comprocsors take suction, compress the gas and deliver it to one of the four gas decay tanks. The waste gases are treated in these gas decay tanks by holding the gases for radioactive decay prior to final controlled release to the environs. In order to provide conforme.nce with the dose design objectives, gas decay tanks are nor-mally stored for approximately 30 days, with earlier release allowed to support plant operation only, and thus achieve decay of short half-life radioactive materials, e.g., I-131, Xe-133. If the radioactive gaseous wastes from the gas decay tanks are discharged without processing in accordance with the above condi-tions, a special report shall be submitted to the Commission pursuant to Specification 2.9.1(2)c.

The radioactive effluents from the controlled access.,

area of the auxiliary building are' filtered by the-HEPA filters in the auxiliary building ventilation syste.n . If the radioactive gaseous wastes are dis-charged without the-HEPA filters, a special report skall be submittee to the NRC pursuant to Specifi-cation 2.9.1(2)c.

The discharge from the gas decay tanks is routed through charcoal and HEPA filter unit VA-82. No credit was taken for the operation of hydrogen purge filters during the Appendix I dose design evaluation and doses through the gaseous pathways were well below the design objectives. The unavailability of hydrogen purge filters will not be considered a reportable event as per Specification 2.9.1(IJc.

The containment air is processed through at least one of the redundant. containment HEPA and charcoal filters in the Conteinment air Cooling and Filtering Units prior to purging. 'If the containment purges.are made without processing through one of the Containment Air Cooling and Filtering Units, a special report shall be submitted to the Commission pursuant to Specification 2.9.1(2)c.

The gaseous radwaste-treatment system is described in Section 11.1.3 of the USAR. For effluent release points and monitor locations refer to P&ID's li405-M-1 and M-261.

FC/ CMP /01 082792

FORT CALHOUN STATION '

PAGE 30 OF 35-CHEMISTRY MANUAL-PROCEDURE CMP-6

\ N N

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BLAIR ~

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TRAINING CENTER

\{si s

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LIQUID EFFLUENTS DISCHARGE

('2) GASEQUS EFFLUENTS DISCHARGE 's TO OMAHA

?- 'l2 l SCALE IN )ULES EXCLUSION 4-D SITE "nUNDARY MAP FC/ CMP /01 082793

c

. * . FORT CAL 110Uli STATIOli CllEMISTRY MANUAL PROCEDURE ' /k*h f.T "' '

PAGE 31 0F 35 CMP-6

- . _ > . - . . _ _ . - . - - . . . . . _ _ , , . . , _ . _ . . . ~ . _ , p.,_....__ _

i HOTEL S/G  ! S/G RAW j TANKS ! A B WATEF i- -

J BLOWDOWN BLOWDOWN _.

i h MON \ TOR jA (f> ([]

TANKS l

~

J' w -

e (4[)

( 5_)

C1 1f V OU l f Al.L 7~~~~~--~~~"~ A

/ CIRCULATING / *h 7

WAT ER

-~

N -

\)

f

~ . ~ ./ .

WARM WATER RECIRCULATIC:1 _a ;g n RIVER V rWE R

, ,;. . . . . . , , . ,,, ,.;.,, .,n.. n a ,%vevv A + Nvv NN NNs/sv.AAVA%w NN*v%^NV%^ %%%%%d

. ,,,,.n =.,.n-n-,..,,,,,n, ,na-,n. (n%n e #@/ #NN*NVV A V

4

--N */N, f .NAA%.NS/N N^NA%A.avv y%*. N%N s% ^ rN-W%e/W4*v%YsA.rN%A,N"'vVvNW*AWNNW%

%^ vv/wwSvNwANv/% AWN %r#-ANN Nv^##A%.*J/Nyv N W ANN W %VNV N ' N A%

- . vNw%%* .%w-M,a N%Nvvv..a ANv /vs*NNvA%%%%%%%%*vN^.NA./v%^ NWWN$ %

p a A%%vA %^./ #NArN% #A vNNN#/#vwW%N%*# #v%AMN^#%%A%%^Nv%%^N=A^NwN% %%%%NS

{ +A A,%% %d A%NW* -A 'b%"VvN / - + ** AN%^M A.%%.%%* /Nw%AMA/N%%Aew N%'v%ArVu%VvN (D RM-054A

0) RM-054B (J) RM-056B (D RM-056A (s) RM-055 AND RM -055A MOULD RADLOliCTJVE_ DISCHARGE PATHWAYS i

FC/ CMP /01 082792

...m. --w . . . . . .d

i *

. < . FORT CAL 110UN STATIOli CllEMISTRY MANUAL PROCEDURE 4* ' b k 9  %

ET' d

v^ce n or 35 CMP-6 AU),'!!,l AlO_ _MYS.TEMS R F' A UTolt_f 001.A NT ll0Tl'l, WAST!'

PROCl? .W ASTE WASTE Iloor Dr ains rVCS liltedof f 1,n u nd t y W n s t e

!:uinp I tow s l'quipinent Druins rh ver De ains l(C 1.oop Dr nuns -

II )I II e

pent  !

I 'i #~'"l'~ waste Iteceur t nni ..

b _; l lloldup Tank"

~

rants ,t" {

1200 Gal ^

b5:10 Gul 'I l} i 4's.600 Gal L- J I. , , - - s e ~ zy , :::J C

)[, )f, -- .

)f Wnste l' alter s l\ f! 'l 60 Microns l.*d i./s AI t ...,,a Dernineralizer Y t'$ N f'l8

10 GPM u_,

Charcor.1 l'ilt e r 69 Cu. I't .

(optional) )f

-=,<=2 3

Motutor Tai.hs 0770 Gal a=

+

Overboard llender (To River) hiQUID HADIDACTIVE WASTE DISPOSAL SYSTEhi FC/ CMP /01 082792

- * * - FORT CALL!OUli STATIOli CllEMISTRY MANUAL PROCEDURE a.,

N-u\ n{A.T k

PAGE 33 OF 35 CMP-6

)(

Particulate Ilhl-042 lodine O Ilht r 11 Ithi-043 Noble Gas LitWPB laboratory LABDRATOBY AND RAQi_0 ACTIVE WASTE PROR1S.JJNG 13UlLDING c-

)(

Ithi- 000 lodine hionitor and Sampler C ithi-061,050' Particulate hionitor and Sampler (htoving)

Ithi- 002.051 ' Noble Gas hionator

)k

=

Rhi-057 Noble Gas fDND/,NSERJEFGAS AUXILIARY _BMILDibTt_EXUAUST STAG Condenser Auxiliary Building Containment Ventilation Building Ventilation

  • Can tie used for either containtnent or plant inonitoring.

. GASEOUS RADICACTIVE DISCllARGE PATlHVAYS FC/ CMP /01 082792

e-

= ** - FORT CALilOUN STATION ,h, PAGE 34 OF 35 CllEMISTRY MANUAL PROCEDURE CMP-6 *

! 1 i Turbine F Auxiliary

  • Dullding y Ventilation i

,- , Condenser To h o here 1 2500 S C. j(

.a aa Condenser

)( To floo! Vacuurn --)m Vent Purnps Charcoal Absorber 4 y ,,

d .;

  1. ',[3,{ " w 3

Cas lloidup Tanks (4) > @<";; '

Tani' T l~ CD SCFM r

( 400 CuFt (each) j - v5' IIEPA Filter WASTE GAS AND CONDENSER OFF-GAS SYSTEMS .

t Inlet ,,, Roll Fans, g3 Filters Containtnent Nortnally g-} gj vc

'?losed' y ' )fN w M43 rge ge(

j rContaintnentK w '

IILPA-Wi Filter

(

Cooling and m

internal cA '

.y. r' $ 50,000 SCFM ^

N%;

Itecirculation b Purge Systern-IIEPA Outlet Charcoat ' Filters .

_ CONTAINMENT Bull DING VENTILATION CONTROL 2

Charcoal.

Filters il -

Fuel llandling *

l. 4 liEPA Arena w- Filter W Fans Safety I l gall (74 F' > Injection r

$ld V D Filters i f([> Areas V( s CM other :2 p2,500 sem -

Areas Ground ,

.0ASEOUS RADIDACTlVE WASTE DISPOSAL SYSTEM page 1 of 2 FC/ CMP /01 082792 P

O' ^t

  • * * - FORT CALilOUN STATION PAGE 35 OF 35 CilEMISTRY MANUAL PROCEDURE CMP-6 i

20,000 cfin (max) 20,000 cfm (inax)

En ficof Vent fans (14)-q_,_;

'C O 2 i'.51.

vvv C N,! Fans

}{oll ',(=;*'f}

,, > Turbine flullding filtet a ,a,*x ( ,

cm

.__ v_

lllElllNJLILUlU?JNG VEKillAILON CONIROL XYEIDj

. GASEOUS RADICACTIVE WASTE _DJSPOSAL_FlYSTEM page 2 of 2 FC/ CMP /01 082792

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