Text

Proposed Tech Specs Reflecting Relocation of Rets,Per GL 89-01
	ML20035B868
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/01/1993
From:	; PORTLAND GENERAL ELECTRIC CO.
To:	;
Shared Package
ML20035B860	List: ML20035B859; ML20035B865; ML20035B868; ML20035B872;
References
	GL-89-01, GL-89-1, NUDOCS 9304050218
	Download: ML20035B868 (75)
	v • d • e

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INDEX s_

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DEFINITIONS P

SECTION PAGE j

1.0 DEFINITIONS Source Check.....................................................

1-Sa l

Process Control Program..........................................

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Offsite Dose Calculation Manual (0DCM)...........................

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Core Operating Limits Report (C0LR)..............................

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TROJAN-UNIT 1 Ia Amendment No. ff I72, tB7-G Augus:167-1952 L

9304050218 930401 PDR ADOCK 05000344 p

PDR

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

-m SECTION Page 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Difference................... 3/4 2-1 3/4.2.2 Heat Flux Hot Channel Factor............... 3/4 2-3

-(

3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor......

.. 3/4 2-7

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3/4.2.4 Quadrant Power Tilt Ratio................. 3)42-11

.7 3/4.2.5 DNB Parameters.....

3/4 2-14 4 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION............ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION..................... 3/4 3-13 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation........... 3/4 3-33

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Movable Incore Detectors................. 3/4 3-37 1

Seismic Instrumentation.................. 3/4 3-38 Meteorological Instrumentation.............. 3/4 3-41 Remote Shutdown Instrumentation.............. 3/4 3-44 Chlorine Detection Systems................ 3/4 3-47 Fire Detection Instrumentation.............. 3/4 3-48 Decouple Switches..................... 3/4 3-50 Acc kent Monitoring Instrumentation............ 3/4 3-51

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Radicactive Gaseous Process and CTTh.i..t ExplosinClas Monitoring Instrumentation................ 3/4 3-59 50 Detection Systems................... 3/4 3-58 2

3/4.4 REACTOR COOLANT SYSTEM s

3/4.4.1 REACTOR COOLANT LOOPS................... 3/44-1

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TROJAN-UNIT 1 IV Amendment No. KB, 55, 78, if, Illi, 727 M2 Septembee-30--4991

n INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Page 3/4.9 REFUELING OPERATIONS 3/4.9.1 SORON CONCENTRATION.................. 3/4 9-1 3/4.9.2 INSTRUMENTATION.................... 3/4 9-2 3/4.9.3 DECAY TIME...................... 3/4 9-3 3/4.9.4 CONTAINMEhT BUILDING PENETRATIONS........... 3/49-4 3/4.9.5 - COMMUNICATIONS.................... 3/4 9-5 3/4.9.6 MANIPULATOR CRANE OPERABILITY. ~............ 3/4 9-6 3/4.9.7 CRANE TRAVEL - FUEL BUILDING............. 3/4 9-7 3/4.9.8 COOLANT CIRCULATION AND LOW WATER LEVEL 3/4 9-8,

3/4.9.9 CONTAINMENT YENTILATION ISCLATION SYSTEM....... 3/49-9 3/4.9.10 WATER LEVEL-REACTOR YESSEL.............. 3/4 9-10

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3/4.9.11 STORAGE POOL WATER LEYEL................ 3/4 9-11 3/4.9.12 SPENT FUEL POOL EXHAUST SYSTEM............ 3/4 9-12 3/4 9.13 CONTAINMENT PURGE EXHAUST SYSTEM CPERATION...... 3/4 9-15 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.................... 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS. 3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION-REACTOR CRITICALITY.. 3/4 10-3 3/4.10.4 PHYSICS TESTS..................... 3/4 10-5 3/4.10.5 XATURAL CIRCULATION TESTS............... 3 /4 10-6 3/A.11 RADICACTIVE EFFLUENTS 3/4.11.1 LIOU*D TJrLUENTS...................

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SECTION PAGE 3/4.9.6 MANINLATOR CRANE OP ERABI LITY...................,......... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - FUEL BUILDING.............................. B 3/4 9-2 3/4.9.8 COO LANT CI RCULATI ON....................................... R 3/4 9-2 3/4.9.9 C0hTAINMENT VENTI LATION ISO LATION SYSTEM.................. B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND r

STORAGE P00L............................................

B 3/4 9-2

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3/4. 9.12 S PENT FUE L POO L EXHAUST SYSTEM............................ B 3/4 9-3 3/4.9.13 CONTAINMENT PURGE / EXHAUST SYSTEM..........................

B 3/4 9-3 g

C 3/4.10 SPECIAL TEST EXCEPTICNS 3/4.10.1 SHUTDOWN MARGINS..........................................

B 3/4 10-1 j

3/4.10.2 GROUP HEIGHT, INSERTION AND F0VER DISTRIBtITION LIMITS.....

B 3/4 10-1

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3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS-REACTOR CRITICALITY...... B 3/4 10-1 C 3/4.10.4 PHYSICS TESTS.............................................

B 3/4 10-1 3/4.10. 5 NATURAL CIRCULATION TESTS................................. B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS

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ADMINISTRATIVE CONTROLS SECTION PAGE Consultants...................................................

6-9 heeting Frequency.............................................

6-9 i

Quorum........................................................

6-9 Review........................................................

6-10 Audits........................................................

6-11 Authority..................................*...................

6-11 Records.......................................................

6-12 6.5.3 TECHNICAL REVIEW AND CONTROL L

Activities..................................................

6-12 7

L 6.6 REPORTABLE EVENT ACTI0N.......................................

6-12a 6.7 SAFETY LIMIT VIOLATION........................................

6-13 6.8 PROCEDURES AND PROGRAM 5........................................

6-13

,m 6.9 REPORTING REOUIREMENTS.

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6.9.1 ROUTINE REPORT 5.............................................

--6-14a-l-- VLc, 6.9.2 SPECIAL REPORT5.............................................

6-17 6.10 RECORD RETENTION.............................................

6-18 6.11 RADIATION PROTECTION PR0 GRAM.................................

6-10 6.12 HIGH RADIATION AREA..........................................

6-19 6.13 ENVIRC?: MENTAL 00ALIFICATION..................................

6-20 6.14 PROCESS CONTROL PR0 GRAM......................................

6-21 i

6.15 0FFSITE DOSE CALCULATION MANUAL..............................

6-22 6-16-MAJOR-CHANGES-TO RADI0 ACTIVE-WASTE-TREATMENT-$YSTEMS.........

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i TROJAN-UNIT 1 XVII Amendment No. 11, 75, 57, if, Ifi, 467-Auguet-36-r-MM

I h.D DUlfCTIONS (Centinued i

m 50U8.!! CHECK 1.27 A SOURCE CHECK shall be the cualitative assessment of channel respense when the channel senser is exposed to either an installed detecter check source er te a be:kground radiatien level if background exceeds the installed the:k seur:e stren;*t..

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1.0 DEFINITIONS (Continued) m PURGE - PURGING 1.33 PURGE or PURGING is the process of discharging air from the Con-tair=ent utilizing the Containment Purge Supply and Purge Exhaust Systems.

-LIOUID FADVAST~ TT.EA~ MENT SYSTE" D E LtTED 1.34 T6 LIQUIO Ta0*dASTE TREAT"Eh7 SYSTEM i: th: :y:te u::d te re^'ce -

ridice;tise E.Eteriel in liquid ffluents by filtering, d::ineraMa4eth gg and pr viding heldup er &c4y Of the r:dicac44ve-waste: for th: pu p:::-

of redcig the tot:1 radioac44444y-pv4er-t: 7:1:::: to-th: :nuir:=:nt.

CORE OPERATING LIMITS REPORT - COLR 1.35 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides ccre operating limits for the current reload cycle.

These cycle-specific core operating limits shall be determined for each reload cycle in occordance with Specification 6.9.

Plant operation within these core

. operating limits is addressed in individual specifications.

MEMEER(5) 0F THE PUBLIC 1.25 MEMEER(5) 0F THE PUBLIC shall include all persons who are not occupa-g tionally associated with the plant. This category does not include employees j

of the licensee, its_ contractors, or vendors. Also excluded from this cate

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are persons who enter the site to service equipment or to sake deliveries. gory v

This category does include persons who use portions of the site for recre-ational, occupational, or other purposes not associated with the plant.

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TROJAN - UNIT 1 1-5b Amendment No. N;t-172-187-Aucutt-26,-1992 j

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1.28 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to l

ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes i

will be accomplished in such a way as to assure compliance with 10 CFR

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Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive

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waste.

r INSERT B 1.30 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the I

methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the i

calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

The ODCM shall also contain (1) the Radioactive

)

Effluent Controls and Radiological Environmental idonitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the annual Radiological Environmental Monitoring f

'T and annual Radioactive Effluent Release Reports required by i

('jiSpecifications6.9.1.5.1and6.9.1.5.2.

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i 1.37 The SITE BOUNDARY shall-be that line beyond which the land is neither owned, not laased, nor otherwise controlled by the licensee.

UNRESTRICTED AREA I

1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for l

purposes of protection of individuals from exposure to radiation end radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

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,7 Tac 3 IrJTRinGTAMON IUL\\D 0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION i

LIMITINE CONDITICW FOR OPERATION 3.3.3.10 Thg radioactive liquid effluent acnitoring instrumen+ ion channels in Table 3.3-12 shall be OPERABLE with their al/rs/ trip setpoints set ensure that the limits of Specification 3.1.1.1 are not exceeded.

APPLICABILITY: As wn in Table 3.3-12.

ACTION:

a.

With a radioact.ve liquid effluent monito ng instru:nen-tation channel al'ars/ trip setpefat less enservative than a value which wil15sure that ce liajts of 3.11.1.1 are met, facediately suspend the release /f radioactive liquid th hannel or declare the effluents monttcred b'y\\ e affected channel inoperable.

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With less than the sinfaun number of radioactive liquid effluent senitoring instr.nnentaticahh&(mels cperable, t4e the ACTION shown in Table 3.3-12. WithXthe incperable instrumentation channels not returned to op4rable status within 30 days, iden-tify the cause of the inoperab1'a channels in the Semiannual k

Radiological Environmenta'l Repor in lieu of any other report.

c. The provisicns of Spec fications

.3 and 3.0.4 are not appitcable.

SURVEILLANCE REQUIRDC 5

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4.3.3.10.1 The cints shall be detersined in accordance with pro-cadures as desc bed in the CDCM and shall be recorded.

4.3.3.10.2 Each radioactive licuid effluent acnf tering instrumentation channel sham be descastrated CPERAELE by performance of the CMANMEL CHECK, SOU)tCE CHECK, CHAEXEL CALIBRATION, and CHANNEL FUNCTICKAL TEST

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- R A D I D A C T ! Y E-L iggl D -[ F F L UE N T-MON I T OR I NG-I N ST R UME N T AT I ON -

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MINIMUM H

CHANNELS JMS RUME_N_I OPERABLE APPLICABILITY ACTION Gr\\ossRgdloactivityMonitors 1.

Providinb utomatic Termination of Release a.

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TABLE NOTATION ION 23 With the number of channels OPERABLE less than required by the Minimum Channels CPERABLE requirement, effluent releases r.ay continue provided that prior to initiating a release:

1.

At least two independent samples are analyzed in accordance

)

with Table 4.11-1, and; l

At least two technically qualified members of the F cility l

\\ Staff independently verify the release rate calcui tions nd discharge valving, and; 3.

In $1 ate corrective action to return the che. els to OPERAELE status; or Otherwise pend release of radioactive eff uents via this l

pathway.

ACTION 24 With the number f channels OPERABLE less than required by s

the Minimum Channe(s OPERAELE requirement, effluent releases via this pathway may continue provide'd grab samples are g

(beta or.gamca) at a limit

- analyzed for gross radioactivity / gram; of detection of at lea's 10 7 pC 1.

At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months en release is discharged into

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the Columbia River.

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ACTION 25 Vith the number of channels OPERABLE 1ess than required by l

l RABLE iequirements, collect and analyze the Minimum Channels OP/ radioactivity (beta or gama) at a lower grab samples for gross limit of detection cf at least 10 7 pCi/ml as defined in Table 4.11-1; 1.

At least once per 7 days when CCWS 4dioactivity is less than 10.s/Ci/ml and no indication of leakage from the g

radioactive systems to the CCWS is obs ved.

Otherw/

ise, at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

2.

ACTION 26 With number of channels OPERABLE less than reguired by the Minjeum Channels OPERABLE requirement, effluent releases via i

this pathway may continue provided the flow rate is stimated

4. least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

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RADIDACTIVE L100iD EFFLtlENT MONITORING TNSTRtiMENTATION SilRVEILLANCE REQUIREMENTS 1

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I 8

CH NEL l

g CllANNEL SOURCE CHANNEL F CTIONAL tiSTRtiMENT

_GLE C,K_,

CllECK cal!DRATION TEST 5

NGrbts Beta or Gama Radioactivity Monits(s Providing Alarm and Automati isolatior!

i a.

Liquid aste Effluents Line D*

P.

R(1)

Q(1)

.(PRM-9) y i

b.

Steam Generator lowdown Effluent D*

H R(1)

Q(1)

O Line (PRM-10),

- Y (#

l c.

Steam Generator Blowdown ion D*

H R(1)

Q(1)'

'C Exchanger Ef fluent (PRH-17)

(

)

[ k' P.

Gross Bets or Game Radioactivity uh Monitors ProV.lding Alarm But Not p

providing Automatic Isolation G

w Component Cooling System (PRM-7, -8)

D M

R(1)

Q(1)

U E

l O

3.

Flow Rate Monitors E

l a.

Liquid Radwaste Effluent Ine D*

/

R**

N/A 7

i (FT-4044/FIY-4098)

J b.

Discharge Structu- (FR-3495)

D*

N/A R**

N/A i

ff,k, c.

Steam Genera of Blowdown Line

.D*

N/A

'N/A 4

_ /\\

g (FI-6715 or I-4921) 4' M

3 m

(1 - \\

i n,

g,

During r leases via this pathway.

EP

- Applie only to flow indication. loop.

(1) Th6 hannel Functional Test shall, where appilcable, include verification that autom Ic l olation of the effected pathway and/or control room annunciator occurs if:

1

'11 instrument indicates above alarm trip setpoint f;

2h Instrument indicates a downscale failure-3Montrois-met-in-OPERATE-mode -or-instrument-d..... sl-zed.

4 r

\\

i INSTRUMENTATION EkPl451VE 6A5

{I.,'

RADIOACTIVE GASEOUS PROCESS AND UTIENT MONITORING INSTRUNENTATION LIMITING CONDITION FOR OPERATION and opleswe ga6 3.3.3.11 The radioactive gaseous process and Ef ficcat monitoring instrumen-tation channels shown in Table 3.3-13 shall be OPERABLE with their alarm /

trip setpoints set.t; en;ur: th:: the limits of Spc;ificatien-0.ll..1 are act ;;;ccdcd cad to comply with the requirements of Specifications 3.3.2, 46 3.4.6.1 and 3.9.9. as applicable.

- -.h.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

or cAplo m e W a.

With a radioactive gaseous process er f'hent monitoring instrumentation channel alarm / trip setpoint less conservative than the value shown in Table 3.3-13, adjust the setpo$nt to within the limit without delay or declare the channel in-ope rable.

b.

With lesg phggrgiq1pm number of radioactive gaseous process cr u r,ccat monitoring instrumentation channels i

OPERABLE With theexpbe 33 nen de p ep= = *. take the ACTION shown in Table 3.3-13.

instrumentaticn channels identified in Table 3.3-13 tt:m: 1, 2, R. " :nd -5 not returned to OPERABLE status within 30 days, identify the cause of the inoperable channels in the-a Sedd i

~

Samizanval Radiological Envir:>nment:1 hpor+ in lieu of an" 4*S E*fkdim b.94.

eher-report.gte h Cm missica P*S**^

P Su W Hed {c c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.0.0.11.1 The 5etpcints ihEli Le detes. wined in 4Q.eid4nse with p,vcedwiss E3 described in the GCCM &nd shall be reccided.

(

explosWe, cjt5 4.3.3.11.% Each radioactive gaseous process or ef fk:n m5nitoring i

instrumentation channel steall be demonstrated OPERABLE by performance of the CHANNEL CHECX, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FlJNCTIONAL TEST operation at the frequencies shown in Table 4.3-9.

TROJAN-UNIT 1 3/4 3-59

/mendment No. if, W j

gee-.cer 13. 155G-l l

s k;

(

)

1 d

^

~

E*z TABL y

~/,E 3.3-13 mN ILADTDAC,TlyJE ASlalls PROCE P AND-EFFillENT HONITORING INSTRilHENTATIO At4D E PIOS tvE (oAS A

MINIHilH ISSlElJ!! Oil CllANNELS APPt.ICABLE AtARM TRIP DeleAed DPERADLE hones Wette-Ga2-ffaldttp-Sys tem SETPOINT ACTION 1.

Holde-G4s-As44vi t y-Hontter Pr*wid4ag41erm-end-Autema t-4c 1

Vertelnat4en-e F-Rel eete-( PRM-4 A )

31 2.

2 Waste Gas lloidup System Explosive w

Gas Honitoring System 0xygen Monitor (a) p(a) 3a. Containment Ventilation isolation ufg pg Particulate Activity Honitor a.

(PRM-IA) 1 1, 2, 3. 4

< 2 Times 33 and 6 Dackground b.

Iodine Activity Monitor (PRH-10) 1 1,2,3,4, s 2 Times "N

and 6 33 low level Noble Gas Honitor

Background

a c,

gg (PRM-IC) 1 1,2,3,4, 5 2 Times

==

33

[N d.

Illgh Level Noble Gas Monitor

Background

and 6

, mg (PRM-ID) 1****

1,2,3,4, S 2 Tfmes 33 a'::::

and 4.

Dackground O.

}a) for purposes of oxygen monitor requirements, two channels shall be operabl

-o C.

t remote indicator on panel C-151.

s.it isf y the requirement of SpecificationA single alarm shall be operable in the control room in order te 4.11.2.6.1 for cont inuous monitoring.

6 o

)

d TARI T _3.3-13 (Continued) 8 E

EffT H0H I T OR i N_fG,lHST RilME N T AT I ON P

RAD 10 ACTIVE GASfulls PROCESS AND-Eq ALARH TRIP HINIMUM APPLICADLE ACTION

~

CllANNELS SETP01HT

. MODES OPERARLE INSTRilMENT 32 3h. RCS Leakage Detection 1,2.3 N/A 1

and 4 Particulate Activity Honitor 32 a.

N/A (PRM-1A) 1,2,3 1

and 4 Low Level Noble Gas Honitor 32 L.

D (PRM-1C)

~

N/A w

1, 2, 3, 1****

and 4 liigh Level Hohle Gas Honitor u

(PHH-10) c.

'D e.\\ e.l e).

?B 3c. Eont+4nment-Purge-Effluent-Henitoring

- #/A---

1 1

(

l.;.:-Level-Hottle-Gas-Honitor

-28 g

.e.

(-PRM-lC)

-N/A

/

- 1 *** * --

' h,--High-Leve-1-Not>1e-Gas-Monttor --

--30 (PRM-10)

- N/A,'

^

mg -

30

[

lt.

Site-Sa mler

/A h

-c---led ins - Ce;p

^

2'i

}

1 l

tf--Part-lculate-Gempestte-Say er N/A I

e----ff f-ittent-Sys ts. Pisw-Rate- -

mx 27

)

'[

Measuring-Device-(FR-5600)

- H/A-l

^

gg 1

f---S eerri er-Fl ow-R a t e-Mea s u t'i ng --

o.

g 9eytec-for-Composite-Sa mler gS

-r

~

(v-v' o.

4m8 E

E

,T_ADIC 3,3-13 Go $ n erl)

=

e-e*

_R.A..D..IDACTIVE GA.S.E.0ll! P.R.O._C_E_S_S

...D__f_ ff t-ttf MT._ MON I.G..R I.N.G I.N..S.IR.l.l.M._ENIA T I ON.

MINIMUM ALARM CilAN#LS APPLICADIE TRIP

]NSTilllHE)lcJ ~

T OPERAOLE MODES SETPO M ACTI(IN l

De(e 4

Awrt+tery-9wtiding-Venttletien Montterir.;; System e,--4fohl e-Sa s-Ast-l v i t y-Mon i t o r-( PRM-2 C) 1

^*^

73 5

in-le6 Hie-Gempetite-sampler 1

N/A so-Terticsiete composite-Sampler 1

M/A 30

~

-d.

2--..ler FIw Reta X;;suring-De,1ce -

1

/A 27-

^

fer Occ g-;!t: S: pler pelgM -

5.

....;r,:cr Alf-E-Jeetee-Meniterleg Syst =

i

. tile-Ges-AetiVity-Menitor 1

g

-tPRM-6A-or-68).

N/A 28

(

i ;R in-ledine-Competite-Sampler 1

N/A 30-(

' /j'd j\\

IR

' 'S

-c.

Per14eelste-Compesf te-Sampler 1

N/A 3G

^

M

(

=

P 4r--EH-leent-Sys tem-Flow-Re t:

1 N/A 27 L

Measuring-Devlee-(FR-3100).

e n"".

e--Sampler-Flow-Rate-Meeserte:g 1

,l, m

.ee,ue-N/A 27-h.

s I

i L

... ~

.hg.U

\\m)

).

~

p..

s m

Y O

TAntE 3.3-13 (Continued) u

[DfffHJENTMO)NI

(

~

h RAD _IOA.CJIVE GASEntlSJ ROCESS RING INSTRtlMENTATION q

EXPLCSLNE 6N.

1

~

MINIMUM ALARM CllANNEl.S APPL.ICADI.E TRIP IN51Hl!MENE UPt:RanLt.

Monts SETPOINT_

ACTION 6.

Post-Accident Monitoring Systems

}

l a.

Containment Noble Gas Effluent 1

1,2,3,4 34 i

Monitor (PRM-1E)

{

Containment Effluent 1

1,2,3,4 N/A 34 h.

Sampler.(High Range) {odine t

u u-c.

Aux 111ary Building Noble Gas 1

1,2,3,4 34'

(

E.

Effluent Monitor (PRM-2D).

i o

)

d.

Auxillary Building Effluent 1

1,2,3,4 N/A 34 Iodine ~ Sampler (Illgh Range)-

/

e.

Condenser-Air Ejector Noble Gas 1

1,2,3,4#

34

{

Effluent Monitor (PRM-6C) f f.

Condenser Air Ejector Effluent l'

1,2,3,4#

N/A 34 Iodine Sampler (lligh Range)

\\

! 2E g..

Main 15 team Line Noble Gas Activity 1/ steam 1,2,3,4 N/A 34

}

Mon t tors ( PRM-16 A.. -168,. -16C, -160)

Ilne t

a

..,=

MP A

is i

1-(

i i

TABLE 3.3-13 (Continued)

TABLE NOTATION s

__a

,_u.

m...

e m.

../.

m u n, 4c csaca Ouring waste gas compressor operation.

.a c 5 w as2. c __ __.. -

,,_m...

s....,.

o, e-.ce..

.....um

. ou o

Minimum channels operable recuirement does not apply if PRM-lt is on scale and operable.

Setpoint calculated in accordance wita -4.3.~.ll.i.fhc. oDc.%,

(

~

/

J Only applicable in Modes 3 and 4 if the condenser has a vacuum.

m,,.., _ __ _ _.. 3. tLS..T..e.q., n e e,, ABu. e A,.,m

, -. su um... ~ _

~ _ _ _

n

___.2_

....han-require 6 by-tee-me.

M 2. u_,.._...._u s. mum.3.. m r,A m u. r.. c...... mus,.r.....__...teses-vie n

.u.

t.a.. _. _..m.,..

___.w

m. u.

1.

o..... _ d g.

......m.

r...mu 4

3......,..,.,

u.....es.

r,., m,,

m u_

_1. b_ @ _ W-

,., w. m

.h. to n e r, Am.. ___

n o_ u_

__m m

.m o..~.

.m.m..

w,. m.o r_

n ne u.m,.e

_ _ _ _m,n_____.

. r.e,.. _ _.

u

.mu

__6 %, _,..-___

1....u..,

-2_2_

_ ~____,_

e n.u.a.....

..mmm.

.,...m,

.mm.

., m.m.,

y.w...

. ~g.

.. k 4..... y ~ o...a.

g. euu _.. - a.

_..Eu

.,.Dek""enee

...-y

..my 6..

6

.a..

...s..,

.~,,u 3.

u u

,u--

u....

...,...a.

....y

__a y..

.a. u...

.a

_____m_

, _ _ ~ _ - >_- - --

. e%...,... _- m s u m..,..cuor

.uu ss2es

......- mm

..m r

me__

.m..

, n.

_ a.

. m.. geev4eu_,r, m.._ u...,,.1__

s.._,..

um..

3,.

m.

m__

uw...

. u.,

t M.. z. w_ _i.. eM e.. a.

z...._

n... u.u.__y_ _..u....

>______a J

_w a....

,, u T

w.

.....s

__s., wou ___

.n u.._.

owa,.

ACTION 29 With the num:er of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the wasti gas compressors may continue provided grab samples are taken and analyzed once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . With both channels inoperable, opera-tion of the waste gas compressors may continue provided grab samples are taken and analyzed once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

_, D_E L_.E_ _TE_ D,,

.,.,m.

..m.. n

_._..._.m_._

m.

m.. -

w

.om w.

..muus..

m.m.

.u

.ooo m m _

..,e... w,.se. 4.

.*4.,

.s m --

Mb-4.._....

..'.c a m s. a -e,ni.

.:___ent,

. t. r 9.. -..

. - _ _ _ m e.

n.

...a..

mm.

._.w

. _. ~,. um. o m

--o,.

___a-g.... a ded--gra b __...a, >..

...sk..

..J

.a.ys+4 m..__

.1..m__.

,3.

3..ese-ret

.a._.e._m

.- u

,m.

r mm.,

m.

.. e ou u

.u.

.w w-

.a. w,_ _...

,s

.._,,,<..+

s.

a.c.

.. nt4 e4eet._s

_ ef 1. m :. s. o.

nemoe.,

,e4.

4..a..

a.

.;3,

-..r

.m.

..t...

.., weeument.__.... _..es.

s S...@...., n,n eAA.c,., e

1..s - t.k.m..

_..z.._._..s.

6,..

.6._.. Ani--

,n, em..u.

93

u. t. +.;.w.

-f

+w.

e w

V m

.o mem-Channels 0"""ABLE r:m;4eement, th: conte.ts-of-the-tank (s).rj

u..

s...,e %.e-.A.....<-.......,.,..u.,.a.

.u..

s. a. a.. a.. m- -a...s-v

..-.........y.

..m.

g.

m.

u 3

+:l e.n e :

e--At4eeet two indt;;c. cent--semples of the-tenk 's :sntsnts erE On.a. g~

a uv A.

A.. i..,.

b..... k.m 2.

4 3,,...... i t r 2.

2.....m.__

. f.

r 2,,1. &./

m

.L_

a m.

.__:,o..

.m u.

._r, a....,..;... ed

....ew_.. u o.,.

.m..

m.

s2__

.___...,..,4....m.,

.,4 w.a.m,n

. a. a. ~...

...-_u..~.. a.

m z.......,.

a...

m-c.

m_..-

a.. m..., r,.,,.,. em.,,

..A4s--patha y.

___ m _

m..g.a

, e.. m.

m TROJAN-UNIT 1 3/4 3-53 Amendment No. 39,105. -tte-

.n-r m..-

_.. - -.~,

e*

s

.I J.

d d

l

^

@\\-

v v

v i

f

.1

.I:

uJ

=u

.s so 5

C 2C 4/5

$ aC w g*

T slll:

O a-ig --

a oc

< n u

2 2 J *-

4*3 @

f*2. @

t,. a:>. u y

be a.====

3 g

l E

L.J Q

<C 4 N2 ed 't3

<C

<C gC et

<st g

3 y

w m>w s

N

-C

C

's piy m

i ac 6a cc cic

E 2

c= so== c

t

E t: t ;t

t

.i::

=

C=

I g ee=

se

=

Cm 93 C

E ain h

i s.a o

e-

<J cc u1

.i sa w

J

= 13 u

J<

g1.-

e g

- au qu' 4' 4* .,,J 2 e-m s "e .a aw== n,,- s.e -w w me: >. w e 1e. .a%. = u p-y a.C N N f%' ed

C aC C

<C a =- en ta.s u2 = N* w- =* %~% s c = 4 ll" Z X X C

C E

E :E

E

.pll '.C E se. ,a m J 2 e,u .D i 2 2 .C 3 C s.C.- e-e., u-i.J >-1 O C aiC 2 at; we f ln C.

e ar-e 2 =c e

E =.cc as: aC <:: aC dl: w E uJ tc C' CE C: EC IC -:C :Etc

E i=

- as - = .C l ac u >= .u v. m a 2 L >= 43 - '.O ^ ' gn n.J l 3 ((- f".) Z cr ut s0 as:

C

sll

<C

e aC

C ip C

4 C U Mi e. 93.C3 ' **= Q

3 wl

%.e N

s N

e E a l:. ac c =. a. 2 2 2

c se at sc C

ui .v,- e W ow u C h J W L e) 2 e 2 g lf:p. ci C E D 4.- M ) o e= sa% IJ. M 2u 5 f") r1 lJ l e U 4.- Z 6s tr 4 4 w ==* 4 4

1..at 2 1 et =1 S.

C m M C': d '. 'E 2 E'. - 2 w w n '= ut <uo..c ' f. :": a W 4 _ $.c .d .es 3 5 i W w f L E v. O o ne,a y art = c I-b' D 6 - C so. g i 85 c 13-e e i 3 i

.e.

re a n o. 2

l. e i:.

i => 1 w c m n o .i.$'- n%. + o-<,. -i .c i .a e E.8=- laJ 4 : .EC m cc .e - e m si <s.e !.l. .s. m o- = o sa mm i a 2T* Emo I *4B

.1 e,

B 1B s.* e'* I i u - a o m - r c >E E e

i s's is s -- lbw 1 a C c a, se l

E4 cc o is up 47 n a- .t (l I u c-I'. a. 1., a. . e. <m u I L .s: o o e, o 4. a- -w _ o <.'1 :. I e ew w =- 'I'., i .4..<o. a m .o t m. i --u si - er -i e i e u s i -a o<l - c.lil

1..e. c

+ <3 st w n

Do n 3

.c u = o ei e i. ca ..e <> e<i.e 23~ ...e u e w -.E e :: g. -cE: a c. .In6 o ,- n. o-o o $ w *a m oo. ou4 .-l, E,<. .o. c z s. um t -l su oa .u s E - a oe . :n. e e-J- -m 2 hr o-a E a J e e c u.$< -e o es =

o l

a:.. - - ei .<A.: zatz-n. -.S *. oe ee

3..-

.c u.c gLvi Ie:. - - < E.-I p - oe sia I ha e ~. E - C M --.- - c. e e acas u> .J

=

i-s. o e - 4 ..ae o ~ >- -s- ~z zu s. ma e wi e w e== m e: - e -i o.9. E u - 2 p;6a c :l-v :l-ti .o es t .: p 2c so u - :::, o <s' A s 3: o =: c c- } n 'F t - u ~ ' j'% ..c.: o em a, i .=. c. n f e> TROJAN-UNIT 1 3/4,3-65 A.mendmen'l-,N,o.,99 1Hirt-A FE o a sew g,,,,,, g.f ,4 ,.c, ,,-9 =w., w re - -*-iea-e*- ^ ~ ' '^' d-( ) s l y B0i.E 4.3-9 (coniimInt) y it. I IDACTIVLGASEntlS PROCESS AND EffllffNL HONITORING INSTRilMENTATION SilRVEILI ANCE RigtJMEp S = H Db IN WillCI' CllANNEL Cll ANNI L SullRCE CllANNEL FilHCTION AL SURVEILLANCL ~ 10STRtlME NT CllECK CilECK C Al. lull ATION TEST R[jlflRED 4 Auxillary Building entilation Honitoring System a. Noble Gas Activity Ho i or D* H R QI4) N/A (PRM-2C) b. Iodine Composite Sampler WI3) N/A 8 N/A N/A g. c. Particulate Composite Sampler (3) N/A N/A N/A N/A p d. Sampler flow Rate Hessuring W* N N/A N/A N/A Device for Composite Sampler p f S Condenser Air Ejector Honitoring y System ')( 4 ) N/A a. Noble Gas Activity Monitor D* H h (PRM-6A and 68) [ / h. Iodine Composite Samp1 f W(3) N/A N/A N/A N/A g ($ c. Particulate Comon te Sampler W(3) N/A N/A A N/A y ?, d. System Effit t Flow Rate 0* N/A R N/A N/A oh ia Heasurin evice (FR-3100) g g Samp) r Flow Rate Measuring W* N/A N/A N/A N/A

%w e.

8"' O vice for Composite Sampler J. =. =w-- v -r /% ((1 )). Y l. \\ ) c8 J Qlf 4.3-9 (continued) E Y h E lM!!10 ACTIVE GASE0liS PROCESS AND EFFillENT HnNIT RING INSTRilHENTATION SilRVEll.l ANCLRGillREMENTS .Y. ( Ep,rtoStW GAS CllANNEL HnDES IN WIIICil ~~' CllANNEL SOURCE CllANNEL FUNCTIONAL SURVEILLANCE ]NSil!!!HElg CllECK CilECK CALIRRATION TEST RGUIRED 6. l'os t-Accident Monitoring Systems a. Containment Noble Gas S N/A R M(5) 1, 2, 3, 4 Cffluent HonItor (PRM-1E) b. Containment Effluent fodine N/A N/A N/A H(3) 1, 2, 3, 4 Sampler (Illgh Range) c. Auxillary Building Noble Gas S N/A R H(5) 1, 2, 3, 4 y Effluent Monitor (PRM-20) h d. Auxillary Building Effluent N/A N/A N/A M(3) 1, 2, 3, 4 Iodine Sampler (Illgh Range) e. Condenser Air Ejector Noble S N/A R H(5) 1, 2, 3, 4 Gas Ef fluent Monitor (PRM-6C) f. Condenser Air Ejector Effluent N/A N/A N/A M(3) 1, 2, 3, 4 lodine Sampler (lligh Range) g. Main Steam line Noble Gas S N/A R H 1, 2, 3, 4 !1 R Activity Monitors (PRM-16A, {!! -168 -16C, -160) 8 L ?? $y 6 n e-v TABLE 4.3-9 (Continued) TABLE NOTATION

C m iny wr privr i.v TElEsses via thh pathu:y.

- During waste gas compressor operation.

(1) The CHANNEL CALIBRATION shall include the use of standard calibration gas samples. Each monitor shall. be calibrated on a staggered test l basis, with each channel being calibrated at least once per 92 days. (2) CHANNEL FUNCTIONAL TEST does not include testing for containment purge supply and exhaust valve closure in Modes 1-4. (3) CHANNEL FUNCTIONAL TEST consists of verification of sampler flew through the sampler. ( (4) The CHANNEL FUNCTIONAL TEST shall, where applicable, include P verification that automatic isolation of the affected pathway and/or control room annunciator occurs if: a), Instrument indicates above the alarm trip setpoint 7 b) Instrument indicates downstale failure ~ c) Controls not in OPERATE mode (') v NOTE: The alarm trip setpoint' verification for the vaste gas holdup system, noble gas activity monitor (PRM-4A), and Con?ainment purge effluent noble gas monitor (PRM-lD) will be accomplished by reducing the alarm trip setpoint below the level of the ( keep-alive source. (5) CMANNEL FUNCTIONAL TEST includes verifying that the PRM shifts into the accident mode as required. i i i f 3 V TROJAN-UNIT 1 3/4 3-67 Amendment No. 57, ' 705. Ett-t I Oc:: macr 18, 1000- hi'> P M e h il f D M cJ 7 O b.ii sulUAUlvi irrtutm 3. 1 LIOUID EFFLUENTS h0NCE TION LIMITING \\0NDITIONFOROPERATION 1 \\ 3.11.1.1 The concentration of radioactive material released fro the site s no unrestricte areas (see Figure 5.1-1) shall be limited to concentra-tions specifie n 10 CFR Part 20, Appendix B. Table II, Colunr$ 2 for radionuclides o er than dissolved or entrained noble gases. For disso 6r entrained noble \\ gases, the concentration shall be limit to2x10-}ved 1 C1/ml total activity. \\ mes. APPLICABILITY: At all i ACTION: a. With the concentra jon of radioactive terial released from the site to unrestrieted areas exceed ng the above limits, s imediately restore centration w k in the above limits. b. With the concentration o radicap ive material released from the site to unrestricted areas xceeding twice the above limits averaged over one hour, progi imediate notification to the 'd' Corr:tission per 10 CFR 50.72 submit a licensee event report within 30 days after disco f the event per 10 CFR 50.73. c. The provisions of Specif cations 3.0.3 and 3.0.4 are not applicable unless Specffications 3%s. 3 and 3.0.4 result in reduction of radioactivity release SURVEILLANCE RE00!RO4ENTS 4hl1.1.1.1Radioactive iquid wastes shall be sample and analyzed according to the sampling and an'alysis program of Table 4.11-1. 4.11.1.1.2 The res ts of radioactive analysis shall be used with the calculational methods in the ODCM to assure that the concent ation at the t point of release'is limited to the values in Specification 3.11.1.1. TROJAN-UNIT 1 3/4 11-1 Amendment No.95}- \\ aj h 6 r, 1904 y t-Thi$ P, Wbw jyDdek). y .i e TABLE 4.11-1 RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM- / \\ Minimum L6wer Limit of Liquid Rglease Sampling Analysis Type of Activity ,/tetection (LLD) Type \\ Frequency Frequency Analysis j (WCi/ml)a l 5 x 10 7b A. Batch P P Principal 6 a Waste Emittersf Release Tanksd 1 131 1 x 10-6 M* Dissolyed and One Bhtch/M M Entrafned Gases 1 x 10-5 \\ / P H-f' 1 x 10-5 j M ~ 4ross alpha 1 x 10-1 positeC f c P Sr-89, Sr-90 5 x 10-6 Compo teC Fe-55 1 x 10-0 (.;; ,-] ~ 5. Plant Continuous Principal Gamma E f 5 x 10-7b i '\\mitters Releases D W Grab Sa=ple Composite 1. Steam 1 131 1 x lo-o Generator y B1cwdown'.9 M Dissolved and Grab Sample Entrained ases 1 x 10-5 / / D M H-3 1 x 10-5 i Erab Sample Composite i Gross alpha \\ 1 x 10-1 } \\ D Q Sr-89, Sr-90 $ x 10-8 Grab Sample Composite \\ Fe-55 1 x 10-0 \\ i / s \\. TROJAN-UNIT 1 3/4 11-2 Amendment No. 99-Deced er-20,-1964 Ek T h(3 p nkn och ex TABLE a.11-1 (Continued) RADIDACTIVE LIDUID WASTE SAMPLING AND ANAL.YSIS PROGRAM/ Minimum . tower Limit of . Liquid Relea e Sampling Analysis Type of Activit Detection (gtD) Type Frecuency Frecuency Analysis (vCi/ml) _\\ / b ~7 2. Oily Wast.t W W Principal mma 5 x 10 Separator ab Sample Emittery d Discharge * / ~ 3. Service W P ncipal Ganma 5 x 10 Water Grab Sarcole ittersf d System ** \\ / l

Grab samples shall be taken afly and composited for weekly, monthly, and quarterly analyses as t clease Type B.1 steam generator blowdown analyses wheneve vity exceeds 10-5 vCi/ml (excluding A

dissolved and -entrained ases). / r(

Grab samples shal e taken daily an composited for weekly, monthly, and quarterly a lyses as the release ype B.1 steam generator bicw-down analyses enever Component Cooli Water System activity exceeds 10-5 vCi/ml excluding dissolved and entrained gases).

g

- - If no patch release is made in a month, samp does not need to be takeVand analyzed for that month.

'/ \\ i d TROJAN-UNIT 1 3/4 11-3 Amendment No. if,167- -Cecember-18 r1990- %b Ind Cn bo 3 )r c. e. TABLE 4.11-1 (Continued) TABLE NOTATION l a. T lower limit of detection (LLD) is defined in Table Notat)on a. of 'h Ta e 4.12-1 of Specification 4.12.1.1 with exception of aT/ AT in this ase is the elapsed time between midpoint of sample llection / i and tire of counting. ( b. For certa n radionuclides with low ganna yield or low energies, or ~ ) for certai radionuclidemixtures,itmaynotbepofsibletomeasure radionuclide in concentrations near the LLD. Under these circum-stances, the ' D may be increased provided thatfuch an increase will not result in a discharge of that radionuclidephich is greater than s 10 percent of th MPC value specified in 10 CFR 20, Appendix B. Table II, Column 2 in the diluted stream. c. A composite sample isMne in which the quantity of liquid samp1.ad is proportional to the quagtity of liquid y/aste discharged and in which themethodofsamplingemployedresulpsinaspecimenwhichis representative of the liquids released. at A batch release is the disc \\ / har e of liquid wastes of a discrete d. volume. Prior to sampling for n'alysis, each batch shall be isolated, and then thoroughly mixed to aisttre representative sampling. (p / \\ /_. A continuous release is the, discharge of liquid wastes of a non-e. a discrete volume; e.g., from a volume r system that has an input [ flow during the continuous release. / \\ / f. The principal ga::na emitters for which the LLD specification will s apply are exclusive}y the following radionuclides: Mn-54, Fe-59, i Co-58, Co-60, In-65, Mo-99, Cs-134, Cs-137, he-141 and Ce-144 This list does not mearf that only these nuclides a%to be detected and Othf' peaks which are measurable and dentifiable, together reported. e with the above nuclides, shall also be identifie and reported. ib bould not be Nuclides whf are below the LLD for the analyses reported as being present at the LLD level. When un' usual circum-j stances ry'sult in LLDs higher than required, the reaso'gs shall be documen (d in the Semiannual Radioactive Ef fluent Relea$c Report. g. Samp ng and analysis only required during periods of ble wn to iver. thej l L 1 TROJAN-UNIT 1 3/4 11-4 Amendment No. 99-Des cgic 20 - 1984 ~ i %3 {nkedond De\\c ed '/ Q uuiva uvi--EFFtttENT5 D0 l LIMITIN CONDITION FOR OPERATION \\Th dose or dose comitment to an individual from r fonctive \\ 3.11.1.2 guid effluents released to unrestricted areas (see ) materials in Figure 5.1-1) sh 11 be limited: / During any ca e / 12.5 mrem to,ndar quarter to 11.5 mrem to the to 1 body and to organ. APPLICABILITY: At all imes. ACTION: a. With the calculated se from the re) ease of radioactive material in liquid effluents exceeding any of the above limits, prepare and submit to the Cormnissfon within 30 days upon deter-mination, pursuant to Sphificapon 6.9.2, a Special Report in i lieu of any other report, Micy identifies the cause(s) for exceeding the limit (s) and ' fines the corrective actions to { ~} be taken to prevent recurre and to reduce releases to below the design objectives. T) sS ial Report shall also include (1) the results of radioJo)gicalNnalyses of the drinking water source, and (2) the radfological b act on finished drinking water supplies with rpgard to the requirements of 40 CFR 141, Safe Drinking Water t. b. The provisions of Specifications 3.0.3 and 3.0.4 are r:ot applicable. _ SURVEILLANCE REOUIREMENTS* / \\ 4.11.1.2.1 Dose /talculations. Cumulative doses due to itquid releases to unrestricteo' areas snail be eterzined in accordance witN the Offsite Dose Calculatf'on Manual (00CM) at least once per 31 days when$e cumula-th , tive liquid fetivity release, excluding tritium and dissolved

ses, f

exceeds 2.5 C1/qtr. The cumulative liquid activity release will be detarsined at least once per 31 days. 4.11. .2 When the cumulative liquid activity release, excluding tri um and dissolved gases, exceeds 2.5 C1/qtr, sample and analyze d king water for I-131 per 3.12.1. / } .J V TROJAN-UNIT 1 3/4 11-5 Amendment No. 49 Dece:nber -20,-1-984 J i O TW5 by \\Medondl 'l)e\\eled 3 RADT0XtnvE UPLULMIb I LIO O WASTE TREATMENT _ LIMITING ONDITION FOR OPERATION / 3.11.1.3 The iquid radwaste treatment system shall be mainta e and t sed to reduce e radioactive materials in liquid wastes p to their dscharge when t. Ifquid activity release excluding tritiu nd dissolved 5 ases to unrestric ed areas (see Figure 5.1-1) when avera e'd over a c.alendar quarter woh d exceed 1.25 C1/qtr. ( JSPLICABILITY: At all imes. dCTION:

a. hith radioactive liquid waste bejng scharged without treatment A

and in excess of the bove Ifmits, following information ,b /,g i shall be provided in e Semiannua Radioactive Effluent Release ( Report: 1. Identification of equi n not OPERABLE and the reason for inoperability. 4 i \\ v 2. Action (s) taken to store e inoperable equipment to OPERABLE status, t 3. Summary descript on of action (s taken to prevent a recurrence. / b. The provisions /of Specification 3.0.3 and 3.0.4 are not applicable. $URYEILLANCE REQ REMENTS Cumulative liquid activity releases excluding \\ J.11.1.3.1 tium and pissolved gases to unrestricted areas shall be determined at east once wr 31 gays. .,f TROJAN-UNIT 1 3/4 11-6 Amendment No.99 Dece=ber-20;;-1984 mR Mehuge Ad ~ 7 c. MDICACIVE-EWWEhTS 3 11.2 M5E005 EFFLUENTS ( DOSE TE LIMITING \\0DITIONFOROPERATION 3.11.2.1 Th dose rate in the unrestricted areas (see Figure 5. )dueto radioactive m erials released in gaseous effluents from the si shall be ~ limited to the 11owing values: a. The dose ate limit for noble gases shall be 1 p0 mrem /yr to j S the total dy and 1 3000 mrem /yr to the skin, nd b. The dose rate imit for Iodine-131, tritium nd radionuclides in particulate orm with half-lives greate than 8 days shall be 5 1500 mrem /y to any organ. APPLICABILITY: At all times. ACTION: With dose rate (s) exceeding the,above limits, icraediately a. decrease the release rate t comply with the limit (s) given in Specification 3.11.2.1. (, b. With dose rate (s) exceedipg two ines the above limits averaged l over one hour, provide iprediate nqtification to the Comission ( per 10 CFR 50.72 and su$mit a licensee event report within 30 s days after discovery 'f the event pe' 10 CFR 50.73. c. The provisions of Jpecifications 3.0.3 d 3.0.4 are not applicable unless' Specifications 3.0.3 a 3.0.4 result in f reduction of radioactivity releases. SURVEILLANCE REOUIR._ m 5 4.11.2.1.1 The 7e ease rate of noble gases in seous efflu ts shall be such that 2.0 %v Tv i 1 and 0.33 h y (Ey + 1.1 Kv i 1. 4.11.2.1.2. e release of Iodine-131, tritium and radionuclides n partic- [ ulate form, ith half-lives greater than 8 days in gaseous effluents hall be i such tha[spe.67 Qy K < 1 by using the results of the sampling and ana' 0 i sis ( cified in7able 4.11,2. prog 4.1 .1.3. The above release rates are detemined in accordance with th me dology and parameters in the 00CM. \\ e s TROJAN-UNIT 1 3/4 11-0 Amendment No. 99~ 7eedu R, 1954 h I.O d==# h m4.h E s 1 ll ' j N ' j, / k \\ ) / \\ s .N i f lt_ oi i 2 f j I tf n 4 4 I I i ) .0 0' 0 0 0 '0 _ 0 0 0 b 6 ~ mnl inm 1 1 1 1 1 li/ 1 1 1 1 L. l x x x rt C _ x x x _. x x eai 1 l 1 1 1 1 1 1 wL( oa t D_ A e e ~ s s r r e e N t t A t l R i l G m m O s F) I) R i y "s "s y P s al r al r y nn e nn e S nn no l t l I f a a t a S on Gs l Gs i lY. - A e m a m i e ss i st e r A py a ua N yt tog a on A li c n e ) h.o s v s e n so r D i al n al N Gb G Gb Gh a 9 s 0 t A c o n l e e A N l l l N l O lp r s ?G a( a a( N a p p p S a p. a G I i i i 1 iI 1_L c c c 1 c3 s 9 e P n n n 3 n1 s 0 l t,_ A M i i i n 3 b 1 i r r r [r 1 r r o S P P P E l ( G S N 1 E \\ 1 L D I W y '\\ [ A S T A e j t e af e ea s E sc S nin g l 1 tl asI d l J s rc 1 I u Gr e t0 my+ P P M nrl if ol oI l et p6 e i e ce se sce otC t E i l q S aae Wl t p Wt p Npp )I pt p li e nr d rm rm mm mrm bnc A l naa aa oa oaa oox0 G Af I CS PS CS CPS NMe2 i f E V s s u y s s s I u u T gc u u o n n n o C %n u u u u u A e e c e n n n n n 0 t u P l P i l i i I pq hp h p d hp t t t t t 1 i I D se am am am n n n n n A nr ra ra ra o o o o n R $f GS GS HGS C C C C C e t r s p g 1 s e e h y y 1 g ru p l ~ t a xn a l i y1 1 P r \\ uin Aht e T e e Al o xnR n. e nN s t l i rE e ei e a n dl t. e ( e me s v e nuaI srnr al n l = m an1 s noiu eeh e \\n e n 1 uet as l t a R i t yt at ct s es ( s e a crnh nene RiC tk l uaex ojor l n sn n rl YECECP l d ysn~ aa n l sn e Wl P Aaa I 7 3 h' Ga'A. 1 C .0 1 s / "c%fE ". 2 >t N,,* o2E$3z'g,*Sc, m$ 7, *k, g his nken @o De.lcded, TABLE 4.11-2 (Continued) ,r^ TABLE NOTATION a. The lower limit of detection (LLD) is defined in Table Nota on a. of Table 4. 2-1 of Specification 4.12.1.1 with exception of a. AT in t this case is the elapsed time between midpoint of sample ollection and time o counting. b. For certain raqionuclides with low gama yield or low nergies, or i for certain rad onuclide mixtures, it may not be posfible to measure radionuclides in oncentrations near the LLD. Und f these circum-stances, the LLD y be increased provided that s h an increase will lot result in a dis arge of that radionuclide w ch is greater than j 10 percent of the MP value specified in 10 CF 20, Appendix B, 4 'rable II, Column 1, in lant effluents. \\ Analysis shall also be pe formed following hutdown, startup, or c. nimilar operational occurr ces which cou alter the mixture of radionuclides. d. Grab =mple shall be taken mont ly wh there is a discharge through each release point. e. l he principal camma emitters for w h the LLD specification will q a pply are exclusively the follo 6g dionuclides: Kr-87, Kr-88, ) Ke-133, Xe-133m, Xe-135, and X 38 fo gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, 2n-6s', Mo 99, Cs-1 , Cs-137, Ce-141 and Ce-144 or particulate emissions. bis list doe not mean that only these nuclides are to be detected and reported. ther peaks which are m'easurable and identifiab), together with t above nuclides, shall i allso be identified and rp orted. Nuclides wh h are below the LLD f'or the analyses should/not be reported as bein present at the LLD 1p' vel for that nuclid I When unusual circumstan s result in LLDs higher than require the reasons shall be documen ed in the semi-ainual effluent re rt. J id g s TROJAN-UNIT 1 3/4 11-10 Amendment No. 49- -Dec embe r-20;--M84 }& W / ~ ') k._______ -i AAulvAL.41f t LPPL*ItN15 10, NOBLE GASES \\ LIMITINE CONDITION FOR OPERATION 0.11.2.2 T e air dose in unrestricted areas (see Figure 5.1-1) ue to i s oble gases re eased in gaseous effluents shall be Itaited to i illowing: During any ca ndar quarter to < 5 mrad for gamma rad ation and < 10 arad r beta radiation. ~ hPPLICABILITY: At al times. ~ hCTION: a. With the calculate s ir dose frca radjeactive noble gases in a gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 s upon detemination. pursuant to Specification 6.9.2, Special Report which identifies the cause(s) for exceeding the } mit(s) and defines the corrective actions to be taken to prevent /rveurrence and to reduce releases $. ~ to below the design objectives. U The provisions of Specifica/\\ b. ti s 3.0.3 and 3.0.4 are not applicable. _$URYEILLANCE REOUIREENTS ReleaseRate/ Calculations The aver \\ 4.11.2.2.1 age release rate of noble pses from the site curing any calencar quartar sha 1 be such that 50 h y Ty < 1-or 25 Ory Ny < 1 4.11.2.2.2 Jhe above release rates are detemined in accordance with the atthodology/and parameters in the 00CM at least once per 31 hays. i / \\ i TR!k1AN-UNIT 1 3/4 11-11 Amendment NoS-E rt u r, M"4 - Thi3 Py h b4. J3 belAd c q RADI0 ACTIVE EFFLUENTS \\ DOSE - 10 DINE-131, TRITIUM AND RADIONUCLIDES IN PARTICULATE F0F,M LIMITIN CONDITION FOR OPERATION / l l 3.11.2.3 The dose to an individual from iodine-131, tritic and radio-ruclides in par 41culate form with half-live's greater than y days in gaseous effluen released to unrestricted areas (see F1 dre 5.1-1) shall be limited to the o11 ewing: i \\. During any cale ar quarter to < 2.5 arem to an organ. APPLICABILITY: At all c>e s. ACTION:

a. With the calculated se from the re ease of iodine-131, radioactive materials g particulate form, or radionuclides 9

other than noble gases f gaseous' effluents exceeding the above limit, prepare and bei+/to the Comission within , ) 30 days upon determination, ursuant to Specification 6.9.2, I a Special Report which idenj;1(f es the cause(s) for exceeding u ~ the limit and defines the Sorrective actions to be taken to prevent recurrence and ta/ reduc' releases to below the design objectives. b. The provisions of Specifications 3. 3 and 3.0.4 are not applicable. . SURVEILLANCE REOUIREMENTS Release / ate Calculations. 4.11.2.3.1 R The average rele rate of iodine-131, tritum ano racionuca toes in particulate formXith half-lives greater than 8 pays in gaseous effluents released to unrestr eted areas during any calendar quarter shall be such thet 100 Qy Tg < 1 f.11.2.3. The above release rates are determined in accordance the ythodotogy and parameters outlined in the ODCM at least once per 31 ys. s, ~ TROJAN-UNIT 1 3/4 11-12 Amendment No.W December 20,-1984 b5' $hn on Qs hDI0ACTIVEEFFLUENTS j i.- ) N / ~ GASEDUS RADWASTE TREATMENT \\ / LIMITING CONDITION FOR OPERATION / 3.11.2.4

1) The GASEOUS RADWASTE TREATMEhT SYSTEM shell be saintain O

l and used to duce radioactive materials in gaseous waste prior to their discharge wh the gaseous effluent air doses due to gaseous effl t releases to un estricted areas (see Figure 5.1-1) when averaged er a calendar quarte would exceed 2.5 mrad for gama radiation and .0 mrad for beta radiatic. (2) The VENTILATION EXHAUST TREATMENT SY EM shall k_ be maintained and_ ed to reduce radioactive materials in g ecus waste prior to their disc rge when the doses due to iodine-131, ritium and radionuclides in part ulate form with half-lives greate than 8 days in gaseous effluent te asas to unrestricted areas (se igure 5.1-1) when averaged over a cal idar quarter would exceed 1. aram to any organ. APFLICABILITY: At all time. I ACTION: a. With gaseous waste bei discharp for more than 31 days r without treatment and i xcess 'f the above limits, discuss l in the Sesiannual Radioac ve fluent Release Report the following information: [i 1. Identification of a pae t not OPERABLE and the reason fer inoperability. 2. Action (s) taken o restore th inoperable equipment to OPERABLE stat I Summary desc/ 3. riptionofaction(s) ken to prevent a recurre ti. b. The provisjons of Specifications 3.0.3 and .0.4 are not i applicab SURVEILLANCE RE IREMENTS / i .11.2.4.1 he average release rate of noble gas 2s from the ite during l any cal dar quarter shall be such that 100 Q 'N < 1 or 50 Q R < l' TV v T v \\ [ TROJAN - UNIT I 3/4 11-13 Amendment No, if 187 August-267-1992-i ThiS m 'N b &E8 Tn vidsAi.iivi-E F FtVEKi5 SURVEILL.A EQUIREMENTS (Continued) y i t, ~ 4.11.2.4.2 The average reles te of Iodine-1 ritium and radionuclides ( in particulate form with half-live gater n 8 days in gaseous effluents released to unrestricted areas during alendar quarter shall be such that 7' 200 Qy It 5.1.,,,,., ...,.,.,,.,,.,.,m.. __, _. 4.11.2.4.3 The above ase rates are dtiemined in rdance with the methodolo;y and ters outlined in the ODCM at least on r 31 days. x i l l ,%() (- 4 i l l i .I i T W AN-UNIT 1 3/4 11-14 Amen &ent No. u_ ~ l ,j Dece=he:Mto;-1%4 /C l j a Y nhenkondkU k kB M i5 O / 'O ~ \\___. / / D u m CTIVU tPFLUUUd \\ TOTAL DOSE I \\ LIMITING CONDITION FOR OPERATION The\\ nual (calendar year) dose or dose commitment 3.11.2.5 any MEMBER OF piEPUBLICdue o releases of radioactivity and to radiation / rom uranium ) fuel cycle sourcehshall be limited to less than or equal Jo 25 mrec:s to the total body or any o'rgan, except the thyroid, which shall be limited to less than or equal to 75 mr ms. ) APPLICABILITY: At all t s. ACTION: a. With the calculated ases from the rA ease of radioactive materials in liquid or\\aseous eff)6ents exceeding twice the limits of Specificatt 3.11.7.2, 3.11.2.2, or 3.11.2.3, calculations should be ma ine)sding direct radiation contri-butions from the reactor un tjnd from outside storage tanks to determine whether the abo limits of Specification / 3.11.2.5 have been exceeded an repare and submit to the Comission within 30 days,4 Special Report pursuant to 10 CFR ] 20.405(c)(1) and Specif) cation 6.9.. b. The provisions of Specifications 3.0. and 3.0.4 are not applicable. SURVEILLANCE REOUIREw.ENTS I4 11.2.5.1 Cumulative / \\ dose contributions from liquid and gaseous effluents shall be determined /in.accordance with Specifications 4.11.112, 4.11.2.2, and 4.11.2.3, and,in accordance with the methodology and parameters in the ODCM. t l 4.11.2.5.2 Cumulative dose contributions from direct radiation from the hactor unij;[and from outside storage tanks shall be detennined in a'ecordance with the methodology and parameters in the ODCM. This requirement is pli-cable on y under conditions set forth in Specification 3.11.2.5.a. ~ l TROJAN-UNIT 1 3/4 11-15 Amendment No ' ij Occ d a 20 r1984 f n I TLs P,i,A a.omu,pejeteL .,RADIDACU Vt t m utni5 g 3/4 3 SOLID RADIOACTIVE WASTE LIMITING DITION FOR OPERATION 3.11.3.1 The radwaste system shall be used in as dance with a PROCESS CONTROL PRO AM to process wet radioactive (stes to meet shipping and burial ground req ements. APPLICABILITY: At all time ACTION: With the provisions of thyt ESS CONTROL PROGRAM not satisfied, a. suspend shipments of d f rocessed or defectively packaged solid radio (3 tetivel tive wastes om the site. b. The provisions Specifications 3.0.3 d 3.0.4 are not (' applicable. f 1,URVEfttANCE REQUIREMENTS 4.11.3 PROCESS CONTROL PROGRAM, as defined in the ODCM all be used tovejr y t!.at processed wet radioactive wastes (e.g., filter

ges, fi l spept' resins, evaarator bottoms, and boric acid solutions) meet t shipping Q)

-e6-bur 4al-ground-reqctrements-with-regard to solidification.and dew _ ar;ing. / y 5 ) TROJAN-UNIT 1 3/4 11-17 Amendment No. If t36- ~ Noveccr 0, 1037 ,y, I i %I )c d Nib y ^ ME 1? vt01DLCSitu-En EONY. ENTAL 2hN11BR1M /

!/ 17.1 MONITORING PROGRAM LIMIT CONDITION FOR OPERATION

,.12.1 A adiological environmental monitoring program as specifi in Table.3.12-1 shall be conducted in accordance with written proced res.

/ JPPLICABILITY: At all times. I ACTTON: a. With the ragiological environmental monitori program not being conducttd as specified in Table 3.12-nd the ODCM, prept re and sdtmit to the Co:xnissien, in 14 annual Radio-logical Eavironkntal Monitoring Report./ description of the reasons for nat conducting the procr'am as required and the plans for preve ting a recurrence With milk or fresh leafy vegetables samples unavailable from any of the sample locatigns requi/ed by the ODCM, identify the-causeoftheunavailahilitypfsamplesandthelocations for obtaining replacement f moles in the next Semiannual-g' Radiological Effluent Reless (Report. The locations from which t samples were unavailable ma tten be deleted from the ODCM provided the locations frpIn whik the replacement samples were obtained are added to the environrental monitoring program as g replacement locations, f available (Deviations are perpitted from the uired sampling schedule i if specimens are unoctainable due to hahrdous conditions, seasonal unavaila'bility, or to malfunctik of automatic sampling equipment. If the latter, every effort shall be made to f complete corr ctive action prior to the end\\f the next sampling period.) b. With the/ level of radioactivity in an environmen 1 sampling mediumfit one or more of the locations specified ih Table 3.12-1 s exceeding the limits of Table 3.12-2 when averaged eger any cal dar quarter, prepare and submit to the CornissinNwithin 30 days from receipt of analysis results for the affectad flendar quarter, a Special Report which includes an eva ation of any release conditions, environmental factors or other aspects which caused the limits of Table 3.12-2 to be excee d. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitte g if: \\ / J TRC.1AN-UNIT 1 3/4 12-1 Amendment No. 99, 4 M-Decembe r-46-1990- 34 e, k nkn~i ru D CE ,/ ,. i h,Wu L UN U l l I UN PUE UP[AdiiCN (COnLinueGi ~. \\ ~ Concentration (1)

Concentration (2) * * **#

Limit Level (1) Limit Level (2) 'l l This repo is not required if the measured level radio-activity was et the result of plant effluents

owever, in such an event, e condition shall be repor+

and dercribed in the annual Radt ogical Environmental .nitoring R4 port. When radionuc'lides othe than those n Table 3.12-2 are detected and are the resul of p nt ef fluents, this report shall be submitted if the pot ial for annual dose to an individual is equal to or ate Nthan the calendar year j limits of Specification .11.1.2, 3 1.2.2 and 3.11.2.3. j i c. The provisions of ecifications 3.0.3 a 3.0.4 are not I applicable. / SURVEILLANCE REOUI EMENTS N 4.12.1 radioiogical environmental monitoring srmples shall

ellect pursuant to Table 3.12-1 from the locations shown in the i

DDCM nd shall be analyzed pursuant to the requirements of Tables 3. 1 k_.. B, 4.12-1. 8 [ v ( TROJAN-UNIT 1 3/a 12-2 Amendment No. m.m. =. = m m ]' d TABLL J.12-1 /

g RADIOLOGICAL. ENVIRONMENTAL MONITORING PROGRAM C

Minfan* E' Number N Esposure Pathway of Sample Sampling and Type and Freque y and/or Sample locations Collection Frequency of Ana]ytis 1. AIRBORNE Radiofodine and 6 Continuous operatfon of sampler Radtd odine canister, u Particulates with sample collection as required rfalyre at least once ( g by' dust loading but at least once per 7 days for !-131. per 7' days. Particulate sampler. ) Analyze for gross beta /% 3 M radf onctivtty > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months I L99h -+- following filter change. yy Perforis gaussa isotopic j -y' analysis on composite o w (by location) san 9 e at 3 1 I Icast once per 92 days. 2. DIRECT RADIATION 40 At I ast once per 92 days. > 2 dostmeters at each ) BCatton. Gapena dose. d At le st once per 92 days. j Q i T{ 6~ h t' 7 la ( ox 'l-t 33 le locations are shown in the 00CH. i ~ N I 5 s, -s L-N \\ TABLE _3.12-1_(Contintied) ) U RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM E 1 E Mfnfmum* E Number Es posure Pathway of Sample SampIfng and. Type and Frequ3n y _and/or Sample Loca tions Collection Frequency of Analysis y 3. WATER 50RNE a. Ground Water 2 At least once rer 92 days. Ganeta isotopic and trf tfum [ ~ analyses of each sample. \\ Co\\ h b. Surface 2 mpostte samples over Gross beta and gamma Water 31-day ' River (period from Columb a isotopic analysis of each 1 d stream and-l' sampl e. Tritium analysis [ including Drfnking downstream.N!f pl31 of composite sample at w D Water analysts is regsfred, least once per 92 days. )[ g compost te over 15 ' day I-131 analyst s on 15-day J,, period. compost te when the cumula-tive 11guld activity 7 ralease, excluding trftfum and dissolved gases, ex-54 eed 2.5 Ci for the cur-6- rentsquarter. O c. Sediment At least once per 184 days. Gamma to ic analysis d" of each samhle. 'T d I a-from o d, Shoreltne f g @r ( gIImple locations are shown in the ODCM. (': O 3 O ) \\ TABLE 3.12-1 (Continued) \\ RA DIOLOG I CAL-ENVI RONMENTAL-MON ! TOR ING' PROGRAM

f flinimum*

I 2 Nunber I E Exposure Pathw of Sample Sampling and Type and Frequency N and/or Sample Locations Collection Frequency of A6alysis ! } 4. INGESTION a. Milk 4 At least once per 31 days during Gama isotopic and I-131 December, January and February. analysis of each sample 7 At least once per 15 days duri ~ ' ther months of. the year. ( o N J9s b. Fish and/or 2 Samle in season, or at least once Gama isotopic analysis V Inverte-per 104 days if not' seasonal, on edible portions. brates Sample from eacVlocation two 4 R species of fish 'and/or inverte-brates reffecting cbrrent sporting 5 and/orcomercial inteh ts in the 0, vicinity.

. Food 1

At time of harvest. One sample Gama isotopic analysis o Products of fruits and vegetables on edible portions. 'S (including root types). P, (( 1 At time of harvest. One sample I-1 1 sand gama isotopic [ ga of broad leaf vegetation during analysi hon edibic portions, gg the months of June, July and g August. g [qa le:e o-g j5fmlelocationsareshownintheODCM. j l i' n ( \\ ) s TABLE-3.12=2 / REPORTING LEVELS FOR RADIDACTIVITY CONCENTRATIONS IN ENVIRONENTAL SAMPLES E h Reporting levels Q \\ Fish / /roadLeaf I ~ Water 'Af rborne Particulate invertebrates Milk / Vegetaticn Analysis (pct /1) os' Gases (pC1/m3) (pC1/Kg, wet) (pC1/1)/ (pC1/Kg, wet) ( .H-3 5 x 104 ) (2 x 10 )(a) q 4 Mn-54 5 x 102 2 x 104 ( Fe-59 2 x 102 hx10 g I Co-58 5 x 102 ? ~ lC Co-60 2 x 102 6 x 103 [ W Zn-65 2 x 102 2 x 104 Zr-Nb-95 2 x 102 3 Ek 1-131 (1)I"I 0.3 1 30 / Cs-134 4 1 x 103 20 102 l(" Cs-137 20 6 2 x 103 20 5x1 I t 1 x 102 90 /(a) For drink,4-- water samples. N t This is 40 CFR Part 141 value. ( 4 e m ) TABLC 4.12-1 \\ U H4XIHilH VAltlES FOR Tilt LOWER LlHITS OF DETECTION (LLD)d 8 h ( \\. Airborne Particulate Analysf s Water or Gag F1sh Hlik Food Products-Sediment \\ ~ (pCl/1) (pct /C) (pC1/kg, wet) (ptt/1) (pC f /kg,wgt)' (pC1/kg. dry) \\ / \\ b gross beta 4 (I ) 1 x,10-2 y, b 3:g 2000 (1000 ) 54 n 15 130 H 59, 30 N0 R 7 7,9 + 58,60 o 15 130 C 65Zn 30 260 3 95Zr 30 9 95Hb 15 \\ 'LC t2{ 131g (1)b 7 x 10-2 1 \\ 25 pl g h 134cs 15 5 x 10-2 130 15 0 150 7 5 g 137 s 10 6 x 10-2 150 ja 80 180 f C 8 Q-14DDa 60 60 gg y a'. 15 15 i F .j v TlasPyiJeJondg bddd ] h x + \\ TABLE 4.12-1 (Continued) -l t l TABLE NOTATION 11est concentration of radioactive material.in a le that l The LLD is ~ defined, for purposes of these specificatio. as the a j 1 yield a net count, above system background, th will be s i de ted with 951 probability with only 51 probabi ity of falsely i j - conc eding that a blank observation represents a real" signal. - j For a ticular measurement system (which na. include radio-- chemical paration): \\ 4.66 sb " E Y z.ZZ T exp(-Aat) / i where { j LLD is the "a pr ori" lower limit of detection as defined j . above (as pCf per knit mass o volume) i sb is the standafd atto of the background counting rate or of the countin r te of a blank sample as appropriate 1 (as counts per minute) j ( 3 s u' E is the counting of ciene (as counts per disintegration) L t Y is the sample siz (in units f mass or volume) I 2.22 is the numb r of transformati n per minute per picoeurie / Y is the frac'tional radiochemical y d (when applicable)- A is the r/ 1 adioactive decay constant fo the particular radionuclide. at is the elapsed time between sample call on (or end of sample. collection period) and time of anting i i It 1d be recognized that the LLD is defined as a priori l (before the fact) limit representing the capability a measure-a ~ .almt system and not as an a posteriori (after the fac limit for i a particular measurement. ~ b LLD for drinking water. ? t \\ ( a v u TRalAN-UNIT 1 3/4 12-7 Amendment No.99 December-20,-1984-i f e iotna. C. ,. m -40!OLOO!O AL CWI?OtMNTE "0NITORING /

/ 12.2 LAND USE CENSUS LIMIT G CONDITION FOR OPERATION

.12.2 A land use census shall be conducted and shall identify the location o the nearest milk animal, the nearest residence and th earest ga en* of greater than 500 square feet producing fresh enfy egetables in\\ ach of the 16 meteorological sectors within a d stance of I ive miles. APPLICABILITY: A all times. l ACTION: a. With a land use ensus identifying a location (s) which yields a calculated dose or dose comitment greatef than the values currently being ca \\ulated in Specificatic'nn the next Semiannuf1 Ra ,h 4.11.2.3.1, identify the new location (s) Effluent Release Repor+. b. With a land use census id ntifying location (s) which yields a calculated dose or dose omitment (via the same exposure i l h( pathway) 20 percent greater than/at a location from which samples are currently being o ained in accordance with Specification 3.12.1, identif the new location to the Comission in the Semiannual Radiological new location shall be added to t(hfluent Release Report. The radiological environmental monitoring program withip'30 days, f possible. The sampling l location having the lowest calculat d dose or dose comitment (via the same exposurp/ pathway) may b'e deleted from this monitoring program after (October 31) 'of the year in which this land use census was' conducted. c. The provisions o Specifications 3.0.3 and .0.4 are not appli-cable. SURVEILLANCE REOUIREMENTS The lan/use census shall be conducted at least onegper \\ 4 12.2 1 months between the dates of June 1 and October 1, by door-o-door survey, groun'd survey, aerial survey, or by consulting local (griculture a authoritie f

Broad,/ leaf vegetation sampling may be performed at the site bounda in t,he direction sector with the highest 0/0 in lieu of the garden yeyus.

j / / / ~ TROJAN-UNIT 1 3/4 12-8 Amendment No. 19, 167-December la. 1990 1 J Cs hM E. C, C, {$ p [ADIOLOGICAL ENVIRONP'tMI AL m0Niiukimb ~-) J K 3 /4.M. 3 INTERLABORATORY COMPARISON PROGRAM ( LIMITIN DITION FOR OPERATION / 3.12.3 Analyses hall be performed on radioactive mater s supplied ts part of an Inte. boratory Comparison Program whic as been approved s sy NRC. LPPt.ICABIt.ITY: At all time LCTION: I a. Withanalysesnotbeingpefo d as required above, report the corrective actions Jaten to event a recurrence to the Consnission in the an 81 Radiologic Environmental Monitoring Report. / b. The provisico of Specifications 3.0.3 and 0.4 are not applicable /- $URVEILLANCE-IREMENTS 4.12.3 e results of analyses performed as part of the above Qred [nt/aboratory Comparison Program shall be included in the annual Radio-e_h bl. meical rnviraament=1 Menitaring 8*nnet nii">>>nt ta Sa=rifie=tica L \\ d f .s TROJAN-UNIT 1 3/4 12-9 Amendment No. 49-b emue. 20, 1:04 1-' INSTRUMENTATION 7 BASES I 3/4.3.3.8 DECOUPLE SVITCHES OPERABILITY of the decouple switches in the cable spreading room (CSR) r ensures that the control cables passing through the CSR to certain equipment required for safe shutdown of the Plant will be isolated and local operation In the event that a portion of the of the equipment can be achieved. decouple switches becomes inoperable, a fire watch will be established in the CSR until the inoperable equipment is restored to OPERABILITY. 3/4.3.3.9 ACCIDENT MONITORING INSTRUMENTATION The OPE?dBILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. This capabil-ity is consistent with the recomendation of NUREG-0578, "THI-2 Lessons Learned Task Force Status Report and Short-Term Recomendations" and NUREG-0737, " Clarification of TMI Action Plan Requirements." 3/4.3.3.10 RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATION The-radioactive 44 qui e t-instrumentation 4s-provided-to manitor and-controh-asrapplicablerthe-releases-of-radioactive-materiais in liquid - ( ) eH4 vents-during-actual-oe-potentfal-releas es. The-alarm / trip-setpa4ats-44r ^ these instr usents-thalMe-calculated in accordance-with-the-0CG-tc nsure thit the elem/ trip will e; cur prier te i cieding the4imits-of40-CfR Pirt 20. The OP:Ta:ILITY and u;e cf this instrumentation is consi; tent ith the re;uirixats of Ocntr:10: sign Criteri; 50, 53, and 54 sf Appendix A ts 10 CFR-Part-50. EiptOSlEGAS 3/4.3.3.11 RADIDACTIVE GASEOUS PROCESS AND EFFLUENT INSTRUMENTAT exP tos sec. p The radioactive gaseous process and efficent instrumentation is provided b -te (1) c; niter end c;ntrci, es applicabit, the reic;ses ;f radice:tive saterials4n-gaseous-+M4 vents-during-ac+ael er petentiel ieirases, (2) gru-0T discherges prier te exceeding the lisit: v4de-automat 4e-4so1*tieHf t': of 10 CT2 Pert 20, (2) ta prsvide automatic isolation of Containment ventilation at two times Containment background readings in Modes 1, 2, 3, 4 and 6; however, in no case will the limits of 10 CFR Pa'rt 20 be exceeded T6 to provide Containment activity levels for RCS leakage detection, d to monitor potentially explosive sixtures in the Gaseous Radwaste System, and (Q to sonitor post-accident release levels. Th: :1 = / trip :The OPEPlaltITYetpcint: f:- thes Ntruments-s hall-be-c alculat ed-4 n-accordance-with-the-0&CM. irud sie ei this in ir m uietiuu i. w uii tent wiU Lhe rew i s ents of General Design Criterie 00 end O' ef Appendix A te 10 Ci; Pest 00. TROJAN-UNIT 1 B 3/4 3-4 Amendment No. 50, if, JJ 59,125, %" Agust 5, 2 INSTRUMENTATION BASES (Continued) The process and effluent radiological monitors for the Containment, Auxiliary Building and condenser air ejector effluents are equipped with an extended range designed to function during accident conditions. Additionally, noble gas activity monitors have been installed on the main steam lines to monitor potential releases of activity through the sain steam relief valves. These monitoring capabilities are consistent with the requirements in NUREG-0737, " Clarification of TMI Action Plan Requirements." 3/4.3.3.12 50 DETECTION SYSTEMS 2 The OPERABILITY of the sulfur dioxide detection system ensures that sufficient capability is available to promptly detect and initiate protective actica in the event of an accidental sulfur dioxide release. This capability is required to protect control room personnel in accordance with Regulatory Guide 1.78, " Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release," June 1974, and is consistent with the requirements of General Design Criterion 19 of Appendix A to 10 CFR Part 50. The recirculation mode of operation is defined as stopping the control room normal ventilation system and maintaining the emergency control room ventilation system in a lineup capable of responding to a safety injection signal. This does not preclude operating the CB-1 fans with the outside air makeup dampers closed and/or performing the other required actions in the u event of an actual sulfur dioxide release. 1 I TROJAN-UNIT 1 B 3/4 3-5 Amendment No. If, 125, 75; l August 26, 1992 M is i/4.u uDICACT-IVE-EFFEUENTS \\ / BASES l \\ 3/4.11.1\\ LIQUID EFFLUENTS \\ 3/4.11.1.1 \\ CONCENTRATION This spect ication is provided to ensure that the concentrat on l of radioactive a(gterials released in liquid waste effluents fr the site to unrestricted areas will be less than the concentration leve) specified / in 10 CFR Part 20.106 and Appendix B, Table II. This limitation provides additional assurance \\(hat the levels of radioactive materials in bodies f water outside the ::ite will result in exposures within 11) the etion II.A design objhetives of Appendix I,10 CFR Part 50, to an / ^ iindividual and (2) the li'mits of 10 CFR Part 20.106(e),to the population. t he concentration limit forgnoble gases is based upon/the assumption that -135 is the controlling radioisotope and its MPC ja air (submersion) was converted to an equivalentsconcentration in water using the methods described in International Cocrnission on Radiol feal Protection (ICRP) Publication 2. i 3/4.11.1.2 DOSE [I This specification is provided to splement the requirements of Section II.A and III.A and IV.A of Appendix I,10 CFR Part 50.Section II.A of Appendix I,10 CFR 50, specifies de ign objective dose to an Individual from radioactive materials'in li uid effluents released to I ianrestricted areas will be Ifmited during anyNalendar year to ( 3 mrem to the total body. The design objective for an'y organ will be Timited to < 5 arem during any calendar year in accordance with PGE Agreement with Tnterveners dated May 1972. section IV.A to 10 CFR Part 50 specifies the limiting condition for operation as one-half the. design objective annual exposure in one calendar quarter. \\ / The ACTION statements provide the required operating f1 ibility and at the same time implement the guides set forth in Section Ilf.A of Appendix I to assure that thejeleases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for sfresh water sites with drinkin plant operations ( g water supplies which can be potentially affected by there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141K The dose calculations in the ODCM implement the requirements in Section III.A of Appendix' I that conformance with the guides of Appendix I is to be I. TROJAN-UNIT 1 B 3/4 11-1 AmendmentNo89-f L6; Z,1%!. h iS \\nNnkCnb e\\eY StD10AcliVL EFFLUENTS b ~ /4.11.1.2 D0 ontinued) s hown by calculational p G res based on" rode 1 nd data su'ch that the ~ ~ (ctual exposure of an indiv ual through ap. - riate pathways is unlikely to be substantially underestimate Th untions specifidd in the ODCM for calculating the doses due to th ual release rates of radioactive ~ iiaterials in liquid effluents w e coististent with the methodology.....m._ provided in Regulatory Guid .109 (Rev.1)q1 1.113 (Rev.1). The intermediate surveillan alue of 2.5 Ct/qtr exc ng tritium and noble sases is a release rate which has been shown during 7 rs of Trojan operation to b gegnificantly below the LCO.value of 1.5 qtr total body and 2.5 4 rem /qtr to any organ. Refer to PGE-1015, Annua perating Reporjtf' Trojan Nuclear Power Plant for 1977, 1978, 1979, 1980, 19 ( s 1 . ire. m. ~ TROJAN-UNIT 1 B 3/4 11-2 Amendment No.- W m : a r 20, 1934 \\ RADTDAf.TIVE EFiuiEuTS f BASES " ] 2/4.11,1.3-EIOU10-WASTE--TRE ATENT I \\ T cAMeck This specification ensures that this system will be available Jof' s use whenever\\ quid effluents require treatment prior to release to the li environment. The requirements that the appropriate portions of this system be used when specified provides assurance that the re'1 eases of radioactive materialsqn liquid effluents will be kept "as low as is reasonable achievable. NThis specification implements the requirements of 10 CFR Part 50.36a, Gene (al Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR Part 50. The specified h portions of the liquid radwaste t(reatment system were specified as onets govern quarter of the annual design objectivNe set forth in Section II.A of Appendix I,10 CFR Part 50, for' liquid el' ents (3 mrem /yr whole body; 5 arem/yr maximum organ per PGE Agreement Intervenors dated May 1972). The dose calculational procedures spec fled in the ODCM include sufficient factors of conservatism to ensure thathty sum of both treated and untreated releases will not result in doses exceedQg the design l objectives., -The surveillance value of 1.25 C1/qtr exclud g tritium and noble gases is a release rate which has been shown during first 7 years of Trojan operation to be significantly below the LCO v ue cV.75 mre=/qtr to the total body and 1.25 arem/qtr to any organN 3/4.11.1.4 TEMPORARY RADWASTE STORAGE TANKS This specification assures that outside temporary radwaste storage tanks will contain less than the number of curies which could result in excess of the limits of 10 CFR Part 20, Appendix B. Table II, Column 2, at the nearest potable water supply in an unrestricted area. For tanks of unknown size, the NRC staff has accepted 10 curies as a default value in cases where substantial dilution would occur before the spill could reach a potable water supply. ~ S/hih2-4ASE005-Er*7EtFENTS I N I 3/4.11.21 DOSE RATE )eMEd This spec cation is provided to ensure that the ose rate at anytime at the exclusion-area boundary from gaseous' effluents from all units on the site will be iithin the annual.dese Ifmits of 10 CFR Part 20 7 for unrestricted areas. The asnual dose-11mits are the doses associated with the concentrations of 10 CFR Part20.106 and Appendix B, Table II. These limits provide reasonabJa-a,ssurance'that radioactive material discharged in gaseous ef,fluehts will not ress1(in or outside the exclu-in the exposure of an individual in an unrestricted area, either with s kion area boundasta annual average concentrations exceeding the limits specified pvAppendix B, Table II of 10 CFR Part 20 (10 CFR'Part 20.IO6(t )). i for individuals who may at times be within the exclusion area boundary, ~ b Jhe-6ccupancy of the iridividual will be sufficiently low to compens'atQc r TROJAN-UNIT 1 B 3/4 11-3 Amendment No.,-9g --..~,w. R4010ACTMETFFLUENTS p Tni5 bc.nkernc%ll be ctec BASE y as e-in-th e-a tros ph e rie-di f fus ion-fa c to r-a bo ve-tha t-for-the-excl usD irea boun cified release rate limits restrict theyrrespohTing gama and beta dose ra 'es ebov background to an i Jnddual hT or beyond the ( exclusion area boundary to < (5 o~Ee total body or to < (3000) nirem/ year to the skin. These ea te 11 1s strict the corre- .I sponding thyroid doie-ra a ove background to an infant v e e -milk-infan y thway' 6 1.he controlling exposure location as determined in t BCF / LO3..r00 dyear-for-the nearc5L cvw i.u Lhe planL. 3!4.11.2.2 00SE M BLE 645E5 is specification is provided to implement the requirements of Sectic'n'; ll.B. II.A and IV.A of Appendix I,10 CFR Part 50. As outlined in Sect;io'n TI.B of ' Appendix I to 10 CFR Part 50, the design objective air dose irg" unrestricted areas due to noble gases released in gaseous effluents /ill be limited during any calendar year to < 10 mrad for gamma radiation,gnd < 20-( mrad for beta radiation. As outlinel in Section IV.A to Appendix I to 10 CFR Part 50,The limiting condition for operation is speci,ff'ed as one-half ) the design objective annual exposure in one calendar quarter. The ACTION statements provide the required operating flexibility and st the same time / tmplement the guides set forth in Section IV.A of Appendfx I to assure that \\ k the releases of radioactive material in gaseous effluents will be kept "as [ 1 ow as is reasonably achievable". The Surveillance Requirements implement ( ) the requirements in Section'III.A of Appendix I, which requires that calcula w tional pror adures be based onNodels and data su,ch that the actual exposure of an individual through the appropriate pathw'ays is unlikely to be substantially underestimated. The dose cale'ulations established in the ODCM s for calculating the doses due to thesactual release rates of radioactive ( noble gases in gaseous effluents will'be consistent with the methodology prtvided in Regulatory Guides 1.109,(Re'.1) and 1.111 (Rev.1). The ODCM v. equations provided for determiningthe airsdoses at the site boundary will / be based upon the histor,ical average atmosp'heric ccnditions. \\ l / \\ "\\ 3/4.11.2.3 DOSE - 10 DINE-131, TRITIUM AND RADIONUCLIDES IN PARTICULATE / FORM N This specificati is provided to implement the\\ ( Sections II.C. III.Xand IV.A of Appendix I,10 CFR Par \\quirements of re

50. As outlined in Section II.C of Appendix I,10 CFR Part 50, the d2 sign' objective dose to an individual'from Iodine-131, trithsn and radionuclidesMn particulate

/ form with half-lives greater than 8 days in gaseous effluentsyleased to unrestricted areas will be limited during any calendar year to (15 mrem to any organ. This value is further reduced to 5 mrem / year maximum organ dose per PGE Agreement with Intervenors, dated May 1972. As outlined in Section IV.A of Appendix I,10 CFR Part 50, the limiting condition for s opefation is specified as one-half the design objective annual exposureg jn euewetendarquarter. TROJAN-UNIT 1 C 3/4 11-4 Amendment No, .F Decembu r, 1964 C 9 JekenaH@ceQ 5 n ltAtr10ACT!YEMFFtt!ENTS y \\ BASESs i \\ / The ACTIOl(ime implement the guides set forth in Section IV.A of Appeni statements provide the required operating flexibility and at @e same t yfx I to assure that the releases of radioactive materials-.in gaseou's ffluents willgbe kept "as low as is reasonably achievable." The ODCM alculational methods specified in the surveillance requirements'imple-nt the requirements in Section III.A of Appendix I that conformance kith the guides of%ppendix I be shown by calculational procedures based in models and data such that the actual exposure of an indiv'idual through <tppropriate pathways 'Is unlikely to be substantially underestimated. Jhe dose calculations established in the ODCM for calculating the doses due to the actual release rates of radiofodine and par,ticulates in s gaseous effluents will be consistent with the methodology provided in legulatory Guides 1.109 (Ret.1) and 1.111 (Rev.1).' The ODCM equations s provided for determining these oses will be based upon the historical tverage atmospheric conditions The release rate' specifications for Jodine-131, tritium and rationue des in particillate form with half-lives greater than 8 days are dependent (on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the developmen,t of these calculations are':s (1) individual inhalation of ] lirborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption 'bysman, (3) deposition rto grassy 'g areas where milk animals and meat producing animals graze with consump-tion of the milk and meat by man, and (4) deposition on the ground with bsequent exposure of man. \\ 3/4.11.2.4, GASEOUS WASTE TREATMENT This specification ensches that the gaseous radwaste treatment system and ventilation exhaust treatment systems will'be used whenever gaseous effluents requirti treatment prior to release to'N e environment. th The requirement that ther appropriate portions of these systems be used shen specified provides reasonable assurance that the releases of radio-4ctive materials in' gaseous effluents will be kept "as icw as is rea-sonably achievable'." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix 'A, to 10 CFR Part 50f and design objective Section IID of Appendix I to s 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as one quarter of the annual design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents (20 mrad /yr beta air dose; 10 arad/yr gama air dose; 5 ares /yr maximum organ dose per PGE Agreement with Intervenors, dated May 1972). The dose calculational procedures of the ODCM include sufficient factors of conservatism to ensure that the sum of both treated and untreated releases will not pesul t-in-doses-exc eedi ng-the-desi gn-obj ec ti ve s. s TROJAN-UNIT 1 B 3/4 11-5 Amendment No T D s _Lc 20, M 04 t 1 i 1 i ,m O \\ t 'I RAD 10ACMYE-EFFttT4TS-- i BASES ( t i 3/4.11.2.5 LG5E-- gQ Tht: ;;;;;i'f::ti. i: pre;id;d te ;;;t 04 reye i;ng req.ii_LG gggy 3/k.11.2.6 EXPLOSIYE GAS MIXTURE This specification is provided to ensure that the concentration. of potentially explosive gas mixtures contained in the waste gas treat-ment system is maintained below the flammability limits of hydrogen / i and oxygen sixture. Maintaining the concentration of hydrogen and oxy. \\ gen below their flassability limits provides assurance that the releases ) of radioactive materials will be controlled in conformance with the / requirements of General Design Criterion JO of Appendix A to 10 CFR Part 50. l 2 314-tht-50L-!D-RADISAGTIVECS~E DdckCd ( ) This-speef fication-ensures-that-radioactive-wastes-that-are-trans- \\ (,s.,.h ^ ported - frid the-site-shah-meet ce salidificatics equi.. i.G.y.cified A./. s..s by-the-burial v.or.d-license-of the respective-states-to-which-the-radioactive-materiel d11 l4 dipped.- A 6 i i v { TROJAN-UNIT 1 B 3/4 11-6 Amendment No. b~ M " :: 20, 19S4 i 9 s ~ q nus P \\ 9 m6JAAW j -3f*.u -- nAututuGICAL Enrix0xnExiAL FION1~lVKINb \\ 4ASES [ 3/4.12.1 MONITORING PROGRAM The ra iological monitoring program required by this s'pecif cation 'provides measugments of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiatfor. exposures of individuals resulting from the station operation. This mo'nitoring program thereby supplements the radiological - effluent monitoring program by verifying that the measurable concentra-tions of radioactive materials and levels of radiation are not higher than expected on the ba's{s of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring

rogram will be effective for at least the first three years of comercial lcperation. Following this period, program changes may be initiated based -

'on operational experience. I' The detection capabilities reguired by Table 4.12-1 are state-of-the-art for routine environmental measurements in industrial laboratories. m The LLD's for drinking water meet th'e requirements of 40 CFR 141. 3/4.12.2 LAND USE CENSUS This specification is provided to ensury that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results ofsthis census. This census i satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of gre(iter than 500 square , feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy i vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To detensine this minimum garden size, the following assumptions were used,1) that 207. cf the garden was used for growing broad '1.eaf vegeta-tion (ie, similar to lettuce and cabbage), and 2) e vegetation yield of 2 kg/ square meter. 3/4.12.3 INTERLABORATORY COMFARISON PROGRAM The' requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision jand, accuracy of the measurements of radioactive material in environmen\\ ta , sample matrices are performed as part of a quality assurance program for

environmental-monitoring-f a-order-to-desonstrate-that-the-result: are reasonably valid.

w

.j TROJAN-UNIT 1 B 3/412-1 Amendment No. WW 20, 55'. ~ i \\ ADMINISTRATIVE CONTROLS I (iii) Identification of the various sampling points. (iv) Procedures for recording and management of data. (v) Procedures defining corrective actions for off control point chemistry conditions. (vi) A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of the administrative events required to initiate corrective action. d. Post-Accident Samplino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and Containment atmosphere samples under accident conditions. The program shall include the following: (i) Training of personnel, i INSE.Ri' (ii) Procedures for sampling and analysis, [ (iii) Provisions for maintenance of sampling and analysis equipment. f 6.8.5 Procedures for radiological environmental monitoring shall be approved f and implemented in accordance with the PGE Nuclear Quality Assurance Program. 6.9 REPORTING REOUIREMENTS (1 ROUTINE REPORTS G.. 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, signed originals of the following reports shall be submitted to the U.S. Nuclear Regulatory Commission, ATTN: /\\ Document Control a3L Desk, Washington DC 20555, with copies sent to the Regional Administrator, el USNRC, Regicn V, and the USNRC Resident Inspector. STARTUP REPORT ytJ A s _,,..o,t o, plant sta m p and p _. scala,,on testing shall be submitted following (1) receipt of an operating license, (2) ~2 7 amendment to the license involving a planned increase in power level, bo I (3) installation of fuel that has a different design or has been manu-S factured by a different fuel supplier, and (4) modifications that may W have significantly altered the nuclear, thermal, or hydraulic perfor- { mance of the plant. S_' 6.9.1.2 The Startup Report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactory TRO,lAN-UNIT 1 6-14a Amendment No. 77, 77, 97, 706 1i 728, 4 43- -May44 i988 T j m INSERT G i e. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements: i 1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR 20, Appendix B, Table II, Column 2, + 3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters of the {

ODCM, 4)

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5) Determination of cumulative and projected dose contributions from radioactive effluents of the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 4 l 6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, j 7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, ~s l i l 8) Limitations on the annual and quarterly air doses s resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9) Limitations on the annual and quarterly doses to a MEMBER OF.THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents i released to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and i 10) Limitations on the annual dose or dose commitment to i any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190. l f. Fadiolocical Environmental Monitorina Procram l t A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent [ monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, ~ (2) conform to the guidance of Appendix I to 10 CFR Part 50, j and (3) include the following: 1) Monitoring, sampling, analysis, and reporting of j radiation and radionuclides in the environment in accordance with the methodology and parameters in the

ODCM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental-1 monitoring. i r t ADMINISTRATIVE CONTROLS which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit. ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT nouune nelt p%E M IT H (Q l m _.. R FP $q.A.s.1 lugica s c.nvaranraerLas rion1Loring neporu covermg Ann oper(tion of the unit during the previous calendar year shall be submit e'd prior 4o May 1 of each year. ii. 9.1. 5 he Annual Radiological Environmental Monitoring Reports shall include su=a fes, interpretations, and statistical evaluatiorv6f the results of the radiol ical environmental surveillance activities for'the report period, includ nia comparison with preoperational studies {illance reports ar operational controls (as approp'r(ate), and previous environmental po'rve .d an assessment of the observed impacts of the plant operation on the environ-The reports shalTNLso include the results,of the land use censuses P i sent. requiredbySpecification3.12.2. If harmful effects or evidence of irrever, sible damage are detected by4h,e monitoring,,the report shall provide an analy-sis of the problem and a planned ourse o action to alleviate the problem. i The Annual Radiological Environment 1 M nitoring Reports shall include x summarized and tabulated results in thegormat of Table 6.9-1 of all f padiologicalenvironmentalsamples'takendurinothereportperiod. In the ~ event that some results are no Vavailable for, inclusion with the report, the report shall be submitted noting and explainihg the reasons for the missing j tesults. The missing data'shall be submitted as'soon as possible in a upplementary report The reports shall,also include the following: a summary sdescripticn of the Radiological Environmental Monitoring Program including sampling methods for each sample tyie, size and physical characteristics of each' sample type, sample preparatioVme;thods, analytical methods, and measuring equipme'nt< used; a map of all sampling locations keyed to a table giving distances and directions from on'e reactor; the result of land use censuses required by the $pecification 3.12'2; and the results of licensee participation in the Interlaboratory l s -Cispsrisons Fregros required-by-Specification-3r12.3 N SEM ANNUAL RADI0 ACTIVE EFFLUENI RELEASE REPORT Rye we with t Di avane Radke th' -Effhent-Rehase Repsrts-covering the eperution Sa.1.5.3c4-the unit during-the-prev 4+us-6-eenth; of operat4on-shall bc :ubmi-tted witMn-60-days-afte4nua y 1 :nd Aly I cf c:ch yt:ri 3 . 2. TROJAN-UNIT 1 6-15a Amendment No.19, IIE, IZE, IJ5, IEI, it+- August.26. 1992 i i -s INSERT C ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 6.9.1.5.1 The annual Radiological Environmental Monitoring Report l covering the operation of the unit during the previous calendar year shall be submitted before May 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 reporting period. The material provided shall be consistent with the l objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.E.3, t and IV.C of Appendix I to 10 CFR Part 50. t i INSERT D f ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.5.2 The annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within 60 days after January 1 of each year. The report i shall include a summary of the quantities of radioactive liquid and f gaseous effluents and solid waste released from the unit. The [ I ~ material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50. [ ~ t i I r i i e t fABl%9-l- -4' Lun_JoionicAt-y#tinnunelviat-Mnellionliso-rpionaAM-sismant-o I '7 fro.e towelee M hat, Colidle-Countyr regon,-Docket-##e-50-344rRePorting-Period / E s - / i M Type and Lower timit All location IJ1th liighest _ Annual Mean Control locatio )' m Neillum or Pathway Total meer of Inclicator locations mwher of Mean(f)b Name Mean(f)b Me ) Reportab1 [ Sampled Analyses Detectiona b b h (linl t of Measurement) Pe twed (I.10) Range Distance and Direction Range c Events I i ~~ e = P 3 3+- o 1 + -o, b I O,,. LC .f. u A \\ 1E 05 -a samt tower Limit of Detection (Ltc) as defined in table notation a. of Table 4.12-1 of Specification 4.12.1.1. I n and range based upon detectable seasurements'only. The fraction of detectable measurements at specified locations is Indic kl bt In parentheses (f). l G b ....n-<.

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aa-mw'*+-*--+w e +.y<w--=- --w--- e we w- .,,--e-n* rs EnbnA heere2 kg o 9 ADfhNTSTRAMTE-00NTROi.3 [ l 0.9.1.5.4 The Radioactive Effluent Release Reports sha]l include a / [ iummary ( the quantities of radioactive liquid and gaseous ef fluents and solid haste released from the unit as outlined in Regulatory Guj e' l.21 (Rev. Q, ' Measuring. Evaluating, and Reporting Radioactivity /in Solid Wastes lLnd Releases of Radioactive Materials in Liquid and4aseous %ffluents from\\ight-Water-Cooled Nuclear Power Plant *, with dafa summarized on a ' quarterly basis following the format of Appe dix B hereof. _.m. Se Radicactive Effluent Release Reports may include a ummary of the meteorological conditions concurrent with the release f gaseous effluents during each quarter as o'utlined in Wegulatory Guide.21 (Rev. 1), with data sunrnarized on a quarterly basis following the fonnat of Appendix a t! hereof. If the surrary of'the meteorological da'ta is not included in the radioactive ef fluent rele'ase reports, it wt11 be available for review at PGE's Corporate Office. The Radioactive Effluent Release Reports A all include an assessment of the radiation doses from radioactive effluents to individuals due to their activities inside the unrestricted area boundary (Figure 5.1-1) dluring the report period. All assum;itions used in making these assess- [ _ ments (e.g., specific activity, exposure time and location) shall be i ncluded in these reports. .i v The Radioactive Effluent Release Reports shallinclude a copy of all licensee event reports required by Specification 3.11.1.1 and 3.11.2.1. The Radioactive Effluent Release Reports shall inciude an assessment s of radiation doses f rom the radioactive liquid and gaseous effluents rhleased from the unit during each calendar quarter as outlined in s maximum noble gas gar:ma air and beta air doses shall be,ea boundary Regulatory Guide ).21. In addition, the unrestricted ar evaluated. T1e meteorological conditions concurrent with the releasesief effluents s tall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the Offsite Oose Calculation Manual (00CM). The Radioactive Effluent Release Reports shall include any changesxto thePROCESSCONTROLPROGRAMortotheOffsiteDoseCalculationManuh{ (pDCM) made during the reporting period, as provided in Specifications, 61 A mM A " g TROJAN-UNIT 1 6-15c Amendment No. ii. %7-Decent >er 18. '990 ADMINISTRATIVE CONTR0tS p.

edisective Ef fiacnt;. Sp"ci'ic:ti:n: 3.1'.1.2, 0.11.:., 0.;;.2.3 l

end 0.11.2.5..hje%cd Redielegicei Envir;n;;nt:1 M: nit:-ing. Sp::!!i::tien 3.12.1.'bddeJ_ 4 E ylosaw-G.,s f f Radioactive Gaseous Process and lifiewnt Monitoring Instrumentation. - Specification 3.3.3.11. i Radiation Monitoring Instrumentation, Specification 3.3.3.1. g y. I 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years: a. Records and logs of facility operation covering time interval at each pcwer level. ) b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety. c. All REPORTABLE EVENTS submitted to the Commission. + d. Records of surveillance activities, inspections and calibrations ( required by these Technical Specifications. ~ e. Records of reactor tests and experiments. f. Records of changes made to Operating Procedures. g. Records of radioactive shipments. h. Records of sealed source leak tests and results.

i. Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Facility Operating License: [ Records and drawing changes reflecting facility design modifi-a. + cations made to systems and equipment described in the Final Safety Analysis Report. b. Records of new and irradiated fuel inventory, fuel transfers ~ and assembly burnup histories. c. Records of facility radiation and contamination surveys. TROJAN-UNlt 1 6-18 Amendment No. 77, f7, 95, T95, ' 787, t?t Swsn.ew. 30, 13;1 f f l i t ~. 5 ADMINISTRATIVE CONTROLS i d. Records of radiation exposure for all individuals entering radiation control areas. l e. Records of gaseous and liquid radioactive material. released to the environs. l f. Records of transient or operational cycles for those facility l components identified in Table 5.9-1. l g. Records of training and qualification for current members of the i plant staff. l h. Records of in-service inspections performed pursuant to these Technical Specifications. i i. Records of Quality Assurance activities required by the PGE Nuclear & a Quality Assurance Program. j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59. i r ~' / k. Records of meetings of the PRB and the TNOB. l ) 1. Records of Environmental Qualification which are covered under the i provisions of paragraph 6.13. i Records of analyses results required by the Radiological m. Environmental Monitoring Program. 'I kgf n. Records of the service lives of hydraulic and mechanical snubbers i including the date at which the service life commences and associated installation and maintenance records. I w t 6.11' RADIATION PROTECTION PROGRAM Procedures for personnel radiaticn protection shall be prepared consistent I with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. [ 6.12 HIGH RADIATION AREA l 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20-a. Each High Radiation Area in which the intensity of radiation is [ greater than 100 arem/hr but less than 1000 arem/hr shall be l barricaded and conspicuously posted as a High Radiation Area and i d i TROJAN-UNIT 1 6-19 Amendment No. 77, if, 252, W/,.et m ;__;y 20, m 2 1 1 INSERT H l o. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. { P I o s s 9 f ? ? P- @ CC Y tTd puninri:,ikAi n vt ~ wnik0t 5 /, m 6. PROCESS CONTROL PROGRAM (PCP) I FUNCT 6.14.1 PCP shall be a progr'am defined in the ODCM detaili how solidifica on of wet radioactive wastes is assured, consist t with-Specificatic 3.11.3.1 and the surveillance requirements of hese l 4 echnical Spe fications. j T Since [utside contractors provide so'lidification serythes"a't Trojan, a copy of the contractor %P and/or contractor implementing, procedures will be integrated into a Tro an procedure to constitute t ' Trojan PCP. l 6.14.2 Licensee initia ed changes to the porti of the PCP contained 1n ~ the ODCM: a. Shall be submitted c the Commissip by inclusion in the Semi- [ annual Radioactive Ef tRelepeReportfortheperiodin which the change (s) was de and shall contain: } \\ (1) information summarizitt and supporting the rationale of the change without be e it of additional or supplemental information; (2) a determination at the chaqge did not reduce the overall ^ 3 conformance of he solidifiedyaste product to existing - f.). criteria for urial ground regtt ments; and O ~ (3) documenta,t on of the fact that the change has been reviewed g { by the Plant Review Board. / Shall become ef fective upon review by the Plant Review Board and b. approvaVby the Plant General Manager. L j i I l l -l 1 ~ TRDJAN-UNIT 1 6-21 Amendment No. If, tit-j ~.n.. J' Y l l a V l INSERT E 6.14 PROCESS CONTROL PROGRAM (PCP) Changes to the PCP: a. Shall be documented and records of reviews performed shall be retained as required by Specification-6.10.2.o. This l documentation shall contain: 1 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2) A determination that the change will maintain the overall conformance of the solidified vaste product to existing requirements of Federal, State, or other applicable regulations. i b. Shall become effective after review and acceptance by the Plant Review Board and the approval of the Plant General Manager. l i i j l i Aphce u> i+h @ ) bl l' ini5itAti n iv= Trots 5 0FFSITE DOSE CALCULATION MANUAL (00CM) FUNCT l }6.15.1 00CM shall describe the methodology and parameters to be a ed in I the calcula ton of offsite doses due to radioactive gaseous and liquid [ ' effluents an in the calculation of gaseous and liquid effluent monitoring \\ l hastrumentati alarm / trip setpoints consistent with the applicable LCDs i tentained.in Technical Specifications. ) p.15 N Any change tu the ODCM shall be made by either of e following j methods. t I A. Licensee init ated changes-1. Shall be su tied to the Commission by inclusion in the Semiannua1\\{ffluent Release Repor 'for the period in which the cha a(s) was mad,e and all contain: a. sufficiently detailed information to totally support the rationale for ths change without I I benefit of additi'onal or su'pplemental informa- ^ tion. Information h ubmitfed should consist of f. a package of those A ges'of the 00CR to be changed -), l G with each page numbered and provided with an /, i approval and date bo4 'together with appropriate I analyses or evaluations justifying the change (s): ( ,a i b. a determinationfthat the change will not reduce ) l i dose calculations the accuracy or reliability of,d / l er setpoint diterminations; an / \\ \\ c. documentation of the fact that the, change has been reviewed 'and found acceptable by the PRB. i i shall beco/me effective upon review and a\\ the PR8/ ./ cceptance by i 2. i 8. Commission initiated chantes: 1. Ska 1 be determined by the PRB to be applica'ble to the acility af ter consideration of facility design. The licensee shall provide the Commission with writte \\ l motification of their determination of applicability )' including any necessary revisions to reflect facility l design. Y l ~~' TRO.1AN-intIT 1 6-22 Amendment No.99-D::si n 20, 1984- ) i l l INSERT F 6.15 OFFSITE DOSE CALCU{ATION MANUAL (ODCM) Changes to the ODCM: a. Shall be documented and records of reviews performed shall i be retained as required by Specification 6.10.2.o. This documentation shall contain: 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2) A determination that the change will maintain the level i of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. b. Shall become effective after review and acceptance by the Plant Review Board and the approval of the Plant General Manager. c. Shall be submitted to the Commission in the form of a complete legible copy of the entire ODCM as part of or concurrent with the annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages,1 clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented. P h4f \\nhewicmcbfC 6 / ~ (- m I 4CMINISTRATivE COnTR0i.5 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SY G.16 nd Solid) 6.16.1 fliquid, g(censee initiated major changes

to the radioactive waste systems aseous and solid):

1. dA ary description of the change including discussion of the J

~ c equigent, components and processes involved shall be,r'eported to the Commission in the next update of the FSAR, implemented in accordahce with 10 CFR 50.71(e), for the year the change is ~ ' completek The change shall be reviewed and approved by the Plant Review Boa 2. The following nformation shall be available.for review: [ A summary o gthe evaluation that led,tb the determination that a. i the change could be made in accordance with 10 CFR 50.59; i \\ b. Sufficient information to totally, support the reason for the change; / l c. A description of the quipmen't, components and processes f3 involved and the interfaces'w.ith other plant systems; (' \\' 4/ d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or s quantity of solid waste that(lication and amendments thereto; differ from those previously estimated in the lic'ense app 1 \\ j-An evaluation of.the change which shows the expected maximum e. exposures to an individual in the\\nrestricted area and to the general population tha'. differ from\\ hose previously estimated in the license application and amendme s thereto; f. An estimate of the exposure to plant operating personnel as a result of the change; and g. Documentation of the fact that the change was eviewed and found acceptable by the Plant Review Board.

djor' changes to the radioactive waste treatment systems are permanent changes which would alter the capacity of handling radioactive wastes or differ in

.1 i.De meund ui ve wutn* / TROJAN-UNIT 1 6-23 Amendment No. SS.*iB P ~ =. = r 4 Trojan Nuclear Plant Document Control' Desk Docket 50-344 April 1, 1993 License NPF-1 Attactnent III: 154 Pages f _

ML20035B868

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