ML20024G632

Proposed Tech Specs,Correcting Discrepancies Found in Change 2

ML20024G632
Person / Time
Site:	Monticello
Issue date:	10/31/1973
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20024G629	List: ML20024G628 ML20024G630 ML20024G632
References
NUDOCS 9102130519
Download: ML20024G632 (17)

Text

.

3.0 LIMITING CONntTIOT: FOR OPERATION 4.0 Sl*RVEILIANCE REQUIREMENTS B. Emergency Core Cooling Subrystens Actuation When irradiated fuel is in the reactor vessel ' -

and the reactor water temperature is above 212 F, the limiting conditions for eperation for the instrumentation which initiates the emergency core cooling sybsysters are given in Table 3.2.2.

C. Control Rod Block Actuation The limiting conditions of operation fer the instrumentation that initintes control rod block are given in Table 3.2.3.

D. Air Ejector Of f-Gas System

1. Except as specified in 3.2.D.2 and 3.2.D.3, both steam jet nir ejector off-gas radiation monitors shall be ,

l operable during reactor power operation.

i The trip settings for the air ejector

=

monitors, except as specified in 3.2.D.4, shall be set to close within 30 minutes the recombiner train inlet valve (s) at 1 a Icvel not to exceed the equivalent of ,

1 270,000 microcuries per second after a

decay time of 30 minutes.

I  !

i f

9102130519 DR 731031 '

AEKJCK 05{N}0263 PDR t 32/h.2 kB rr" _

3.0 LIMITI!:G CO':7 tTIONJ FOR OPERATION 4.0 SURVEILIA' CE REQUIREMENTS

2. Fro: and after the date that one of the two stea7: Jet air ejector off-gas radiation monitors is -nade or found to be Inoperable, continued '

reactor power operation is permissible provided the inoperable radiation monitor instrument channel is tripped.

3. Upon lost- of both steam jet air ejector eff-gas radiation monitors, an orderly shut-down shall be initiated and the reactor shaII be in cold shutdown withir 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4 If operation is necessary with the Of f-Gas lioldup System recombiners hypassed, the steam jet air < Jector radiation monitors shall be set to close the off-gas isolation valve instead of the recombiner intet valves with a delay time not to exceed 15 minutes.

l l

l 1

48A 302./4.2 REV

m 3.0 LIMITiMG CONrtIfl0NP. FOR OPEPA TIOS 4.0 Si'RVEILIWICE REQUIREMENTS E. Reactor Building Ventilatiote I sola t. ion and Standby Gas Treatment Syrtera Initiation

1. a. Except as specified in 3.2.E.1.b below, four radiation monitors shall rs be operable at all tines.

b. One of the two monitors in the venti-lation plenum and one of the two radia-tion monitors on the refueling floer nay be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the inoperable monitors are not restored to service in this time, the reactor build - .

i Ing ventilation system shall be iso-lated and the standby gas treatment system opereted until repars are complete.

2. The radiation monitors shall be set to trip as follows:

(a) ventilation plenum i 3 mr/hr (b) refueling floor 6100 mr/hr

3. When irradiated fuel is in the reactor vessel and the reactor water temperatore is above 212 F, the limiting conditions for operation for the instrt mentation listed in Table 3.2.4 shall be iaet, 3.2./4.2 49 REV

. - _ . . _ _ _ m . _ . _ . . _

Table 4.2.1 - Continued l'inimum Test and Calibration Frequency For Core Cooling.

Rod Block and Isolation Instrumentation Instrument Channel Test (3) Calibration (3) Sensor Check (3) f

3. Stean Line low Pressure Note 1 Once/3 months None

4. Steam Line Ilir,h Radiation Once/ week (5) Note 6 Once/ shift ilPCI IS_0_LATION

1. Steam Line Iligh Flow Note 1 Once/3 months None

2. Steam Line liigh Tenperature Note 1 Once/3 months None RCIC ISOIATION

1. Steam Line Iligh Flow Note 1 Once/3 months None

2. Steam Line liinh Temperature Note 1 Once 3/ months None l

REACTOR BUIIBING VFNTIIATION

1. Radiation Monitors (Plenum) Note 1 Once/3 months once/ shift

2. Radiation Monitors (Refueling Floor) Note 1 Once/3 months (4) 0FF-GAS ISOIATION

1. Radiation Monirors (Air Ejectors) Notes (1,5) Note 6 Once/ shift

=

WOTES:

(1) Initially once per month until exposure hours (M as defined on Figures 4.1.1) is 2 0 x 10 , thereafter according to Figure 4.1.1, with an interval not greater than three months.

32/h.2 62 ia

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

faser Continued:

3.2 ror effective er,rgency core cooling for the smali pipe break die HPCI or Automatic Pressure Relief system must function since for those breaks, reactor pressure does not decrease rapidly enough to allow either core spray or LPCI to operate in time. The arrangement of the tripping contacts is such as to provide this function when necessary and minimize spurious operation. The trip settings given in the specification are adequate to assure the above criteria is met. Reference Section 6.2.4 and 6.2.6 FSAR. The specification preserves the effectiveness of the system during periods of main-tenance, resting, or calibration. and also minimizes the risk of inadvertent operation; i.e., only one instrument channel out of service.

Two air ejector off-gas monitors are provided and when their trip point is reached, cause an isolation of the air ejector off-gas line. Isolation is initiated when both instruments reach their high trip point or one has an ut scale trip and the other a downscale trip or two downscale. There is a 30-minute delay before recombiner train inlet valve closure when the recombiners are in use and a 15-minute delay before off-gas is; stion valve closure when the recombiners are bypassed in which the ,

reactor operator may take corrective action. Both instruments are required for trip. The trip settings of the instruments are set so that the maximun stack release rate limit n11 owed by Specification 3.8. A.1 is not exceeded. ,

Four radiation monitors are provided which initiate isolation of die reactor building and operation of the standby gas treatment system. The nonitors are located in the reactor building ventilation

, plenum and on the refueling floor. Any one upscale trip will cause the desired action. Trip settings of 3 mr/hr for the monitors in the ventilation duct are based upon initiating not- al ventilation isolation and Standby Cas Treatment System operation so as not to exceed the maximum release rate limit allowed by Specification 3.8.A.1 for the reactor building vent of 21,000 mic.~ss a *"- per second of gross radioactivity.

Trip settings of 100 mR/hr for the monitors on the refueling floor are based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident Icaves the reactor building via the normal ventilation stack bet that all rhe activity is processed by the standby gas treatment system.

Although the operator will set the set points with.n the trip settings specified in Tables 3.2.1, 3.2.2, 3.2.3 and 3.2.4, the actual values of the various set points can differ appreciably from the value the operator is attempting to set. The deviations could be caused by inherent instrument error, operator setting error, drift of the set point, etc. Therefore, these deviations have been accounted for in the various transient analyses and the actual trip settings may vary by the following amounts.

3.2 P.ASES 68 REV

3.0 LIMITING CO mITIO::S FOR OPERATIO!! 4.0 SUR'IEILLA;;CE REQUIRDtENTS 3.8 RADIOACTIVE !TFLUE?!TS 4.8 RADIOACTIVE ESTLUE' TS Applicability: Applicability: r Applies to the gaseous and liquid radioactive Applies to the pcriodic monitoring and record-  ;

cffluents from the plant. ing of radioactive effluents. '

oblective: Objective:

To assure thet radioactive material is not released To ascertain that radioactive releases are to the environment in an uncontrolled manner and to being kept as low as practicable and within assure that any material released is kept as low as allowable values.

practicable and, in any event, is within the 11rits of 10CFR Part 20. Specification:

Specification:

A. Airborne Effluents A. Airborne Effluents A set of equations are given to express the airborne effinent limits. The symbols stand for the folicwing:

Q1 = release rate from the off-gas stack QRS = release rate from the reactor building vent 3.8/h.8 168 REI

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

i r

i 3.0 LIMITING CONI'ITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS l

1. The maximum release rates of cross radioactivity 1. Station records of gross stack computed oh n 15-minute avernre bocin chall not, release rate of gaseous activity exceed a rate 9, in curlec/ cec: shall be maintained on an hourly basis to assure that the specified Q1 + QRS f, 1 rates are not being exceeded, and ,

0.27 0.021 to yield information concerning general integrity of the fuel cladding.

2. Die release rntes of gross radioactivity Records of isotopic analysis shall shall not exceed 16 percent of the limit be maintained. Die off-gas stack in Specification 3.8.A.1 averaged over and reactor building vent monitoring any calendar quarter. system shall be functionally tested monthly and calibrated quarterly with

3. V - r_ylmum release rate of radioiodine- an appropriate standard radiation source. .

131 (I-131) shall not exceed a rate Q, in Each monitor, 'as described, shall 'save microcurfes/sec: a sensor check at least daily. r g + QRS f.1 2. An air e.jector off-gas sample 25 1.2 isotopic analysis for at least six firnion product Caces; Xe-138, Se-135, Ge-133, Kr-88,

4. The release rate of I-131 shall not exceed Kr-85m, Kr-87 shall be made at least 4 percent of the limit in Specification weekly and following each refueling or 3.8.A.3 averaged over any calender quarter. other occurrence which could alter significantly the mixture of radio-

5. Eie maximum release rates of radioactive nuclides.

particulates with half-lives greater than 8 days shall not exceed a rate Q, in micro-curies /sec:

01 + QRS /_

~1 9.5X107 ret!a 1.1X100 FII'Ca where RFCd is the composite maximum per-missibic concentration in air in uCL/ml determined using Appendix B, Tnble II, Column 1 and Notes of 30 CFR 20.

3 8/h.8 169 e m--

N

~

3.0

__ LI!!ITI :G CO:mIT10 :'; FOR OPSPATIO?:_ _.____ _3_ __ __ _

6 The rele se rates of radioactiv

_ _ _ _ e

'.0

+

StTVEI LIA!;CE P10UIREME::TS -

than 8 d,ys shall notparticulates with half-11 es greater  !

3. -

of the limit in Specification 3 3 A 5 exceed 8 percent Caseous release of tritium calculated on a quarterly basis fr a be sh ll averaged over ,ny calendar curr.er, . .

om

7. tritlam concentration ifications 3.8.A.1,. .3.8 A 3If the pec-mutmum releasefrom a reprasentative rate limits of S sampleVapor f

u ated not met , sum of these .

The following a routine survalliaor 3.8.A.5 are an orderly shutdown shall be initiat dnce check. ported as the total tritium releatwo se.

values s e and the 4.

reactor within sitall 2i hours. be in the cold shutd vm c ondition Station records of release radio-of 8.

If the limite lives greater than a8 adays f-be sh lllodine 3.8.A.4 or 3.8.A.6 are exceedadof Specifications 3.8. A.2, maintained on the basis stack of all appropriate corrective action such and vent cartridges counted .

The as an charcoal cartridges shall be co initiated to bring the releaseorderly reduction of power weekly when theshall be releaseunted measured rate these limits. s within of radiolodine-131 activity is l ess 9 '

than the rate of Specificati on k 3.8.A.4; otherwise the cartrid k If the release rates exceeds four p shall be counted d911y. ges

{

of the 1imits in Specificatien 3. .8ercent .

A1 I The

( percent of the limits in Specificationaveraged wo weekly over when any the c'easured calendarase ne releparticul quarter or t 1 s

\

3.8.A.3 or 3.8.A.5 averaged over any with half-lives greater ythan 8 rate of par quarter, the following actions shall be taken: calendar 1

days is less than the rate of

\ \

Specification 3.8.A.6; otherwise t

the activity shall be counted daily, 6 ann f.kinthly the principal parti

\ culate i radionuclides shall be detemired .

3.8/h.8 170 REV

~.

l 3.0 LIf11TI IG CONDITIO!N FOR OPEPATIO!! 4.0 SURVEILU0 ICE REQUIRDIE?iTS

6. The release rates of radioactive 3. Caseous release of tritium shall be particulates with half-lives greater calculated on a quarterly basis from tritium concentration of the syndensate.

than 8 d,ys shall not exceed 8 percent f.

of the Ilmit in Specification 3.8.A.5 vaporous tritium shall be calculated averaged over any calendar quarter. from a representative sample. The sum of these two values shall be re-

7. If the maximum release rate limits of Spec- ported as the total tritium release.

ifications 3.8. A.1, 3.8. A.3, or 3.8. A.5 are not met following a routine surveillance check, 4. Station records of release of radio-an orderly shutdown shall be initiated and the lodines and particulates with half-reactor shall be in the cold shutdown condition lives greater than 8 days shall be within 2'+ hours. maintained on the basis of all stack and vent :artridges counted. The

8. If the If mits of Specifications 3.8.A.2, charcoal cartridges shall be counted 3.8.A.4 or 3.8.A.6 are exceeded, weekly when the measured release rate appropriate corrective action such as an of radiciodine-131 activity is less orderly reduction of power shall be than the rate of Specification initiated to bring the releases within 3.8.A.4; otherwise the cartridges these limits. shall be counted daily. The particulate filters shall be counted

9. If the release rates exceeds four percent weekly when the measured release of the limits in Specification 3.8.A.1 rate of particulate radioactivity averaged over any calendar quarter or two with half-lives greater than 8 percent of the limits in Specifications days is less than the rate of 3.8.A.3 or 3.8.A.5 averaged over any calendar Specification 3.8.A.6; otherwise quarter, the following actions shall be the activity shall be counted taken: daily. Monthly the principal particulate gamma radionuclides shall be detemined.

3.8/h.8 170 PEi

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

s t

3.0 LIMITI::G C0!mtTIOf 7 FOR OPERATIO" 4.0 SURVEILUJ CE REQUIREME! TIS

a. Investigate to identify the causes for such release rates.

b. Define and initiate a program to teduce such release rates to the design level

c. Provide a report describing these actions within 30 days as an unusual event (See Specification 6.7.B.2). .

10. At least one of the two stack manitcrs, in-cluding the charcoal cartridge and particula +c filter, shall be operable at all times that the stack is releasing effluents to the environs.

11. If both stack monitors are made or found in-operabic, the reactor shall be placed in the hot standby condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

12. Except as specified in 3.8. A.13, the off-gas stack and reactor building vent monitors shall have automatic isointion setpoints consistent with Specification 3.8. A.1 and alnrm cetpoints consintent with Speelfication 3.8.A.2.

13. If operation is necessary with the Off-gas lloldup System recombiners bypassed, the off-gas stack monitors shall serve ont f an alarm function.

3.8/h.8 170A RE7

. _. - .. . . . ~.

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

4 4

3.0 LIMITU!G ConITIO :S FOR OPERATIO:: 4.0 SURVEILIMJE REQUIREMEITIS B. Mechanical Cor: denser Vacuum Pu7 B. Mechanical Condenser Vacuum Pump

1. The mechanient condenser vacuum pump 1. At least once during each operatinge shall be capable of being isolated and cycle, verify automatic isolation secured on a signal of high radioactivity of the mechanical condenser vacuum whetiever the main steam IIne isolation pump.

valves are open.

2. If the limits of 3.8.B.1 are net met  :

following a routine surveillance check, '

the nechanical condenser vacuum pump ,

shalI be kept in an isolated condition

, untii repairs are made.

i j 3.8/h.8 170B ret t

._. . _ _ _ _ _ _ _ _ _ . _ . . . _ . . _ _ _ _ . . - . . . _ .. __ _____ _ _ _._ _._..__ ___. . . . _ - -_ _m.

l 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

3. Two 11 dependent samples of each tank shall 3. The performance and results of independent be taken and analyzed for gross beta-ganna samples and valve checks shall be logged.

activity and the valve line-up checked prior to discharge of liquid effluents. / %

4. If the limits of 3.8.C cannot be met, radio-active liquid effluents shall not be released.

D. Radioactive Waste Storage D. Radioactive Waste Storage i

A sample from each of a Waste Sample, Floor The maximum amount of radioactivity in liquid Drain, Condensate Stc** age and Waste Surge storage in the Waste Sample Tanks, Floor Drain Tanks shall be taken, a .syzed and recorded

Sample Tanks, Waste Surge Tanks and the conden- every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If no additions to one of the 4

sate storage tanks shall not exceed 2 curies. above tanks has occurred since the last sample, If this condition cannot be met, the liquids in that tank need not be sampled until the next these tanks shall be recycled to tanks within addition.

]

the radwaste facility until the specification is met. E. Augmented Off-Gas System 4

E. Augmented Off-Gas System 1. The hydrogen monitors shall be functionally j tested monthly and calibrated quarterly

1. If the hydrogen concentration in the off- with an appropriate gas mixture source.

gas downstream of the recombiners reaches Each monitor shall have a sensor check at i four percent, the recombiner off-gac flow shall least- daily.

j be stoppel automatienlly by closing the vn1ves

< upstream of the recombiners. 2. Tank radiation monitors shall be calibrated

]

quarterly by correlation with tank sample i 2. Except as specified in Specification analyses. Monitor readings shall be recorded 3.8.E.3 below, at least one hydrogen monitor every eight hours to determine that the limit  !

j upstream and one hydrogen monitor downstream of Specification 3.8.E.4 is not exceeded.  ;

j of each operating recombiner shall be t operabic during power operation.

i i

i k

3.8/h.8 173

! RE7

_ _ _ _ _ _ _ ._ ._ _ _ .m _

4 3.0 LIMITING COMA [ Tion FOR OPERATIO?:3 4.0 St*WE11Lt* ICE REQUIREMENTS t

3. If the a' ove specified upstreart hydrogen 3. If a tank radiation muitor is monitors are not operable, continued inoperable, a sarple from the gas operation of a recombiner is permissible decay tank shall be taken, analyzed, if the flydrogen Inventory Processor is and recorded every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I f no ,

set to provide a constant signal rep- additions to a tank have occurred resentative of the worse case hydrogen since the last sample, the tank need concentr, tion. If the above specified not be sampled until the next addition.

downstre.mt hydrogen monitors are not operable. an orderly reactor shutdewn shall be initintad to transfer the Off-gas System to the recombiner bypass mode. -

4. The maxir*rm gross radioactivity contained in one g,s decay tank after 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> hold-up that can be discharged directly to the environs shall be less than 22,000 curies of Xe-133 dose equivalent. If these conditions cannot be met, the stored radioact Eve gas shall be recycled within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to other gas decay tanks until the condition is met.

F. Environmental Nnitorin;; Program The environmutal r:onitoring pmcrna given in Table h.8.1 chnll le cond etul.

3.8/h.8 173A Frl

FiiI,r 11tj[!{;}ji 1!l ,;f[! , I;i[ ef! it tt it!, ,! !!!i ,!I:l

m. -

r

. cs m e 1 d t-cl n ev oa u h B -

n i n

yt h

e h

e d cs mti'eua sn n t ee masb

- xo ] et oieo en _

a t e rf c B rsue el a i

d m7ll eoee mcnnt mec ar 7I 7S

_ n eiac m 2. s oub ppgOen po- r t

rtI o nn'

- e hv ba 0ect s 0hi n -

5tl of eii s

eet l e s 1P a qc . cf h v s

_. At 1 me n ro 'ea 'o on t re , o _ Tea l v

,et y aoh a iI bt no ep-s l rt n n l re nf .i . d e dd c ol d bh v o ms Bnt ua a sont

_ b i

enccl e a m =>wn ic ct ct i anc ei d crol eafi u x

iml u r .g b ea cr t c d gc

_ n

- cnl t i ec c ' h ne et a ner p

b n e,) Ql ae eat _

._ eiot er ror ar e/u p r pt.a

._ dt va pi shZ et A ap sen scu ,

t m it( l o n n h eit i cs nt e m r r nt i aam8i d gre n

a <. m ,i one d i t r

. t cd n r vexd hit el dpo0 d eeyl1 evan t mecu eeb2

._ nmad a

ae r ai1 u

b e l i ma rae2 t mumeocah w nrt rcrE exiF eh] 8 r agh eoa k . v eaC re it f h cpncm o 0 d c a

my mnob atI ot t sr o T yn on e tF ctd1 nn cehc' eos r .l sie odsm t eaf ov o

_ nnrt a e v aaa e . t nt o f uccs0 n gusn

_ eyrrr0 nint faufouaa0 b oee 2 e ec E g5 miai not uv ge umrf ca t nf - 1

_. eL anhH m; . l l otC l

fi e sii td f

.ff ad cm

) i gl l ai 0 f upe C n 3 oc h ya m1 eq r 2oin , S u rusm Ebf e eono t l nffi n

u cr1 e6 a d

1 cn/eO evnetH ch2 Q

(' r oh t

odt n h onc F od

's- oai ron ldd ne el aa cu t ca 8 o0 m'; et nd t coe

_. r e *t r oi r

+

oe .nei n

mch cc r

i

] c?

/a i

nht m i cci one rwotii yk m-bli u0f emt xei dt

=1 x7 e r1 n

mace e /e cee eer rrx eoh cp i al r gs sd nhit

_ i t er sh r nm1/e I i et ro im.itit t ewnO r

i l un t cawrt c nt esCf

_ t l ui ndi o2 eshi pi N e. C < 7 1

'c oece ruscm i eetH lhaC eiT b x e5e c

tl 2a y1 n e nn0 . t

_ ec- O J d1 t1l c2p -

i 1 aP . ri p" J t

e . n n en

] - l l vn) ef ~ a0 n

_ a -

roecOt /

t.

C. ie ~- yb ow t . a o h annl oe ee t got v .o ml rt,i nt a ecri v

ech r oop et rfC 1 itdl vnee i et b coi nr mk ui nm i ddt n hg cnt a t c of col l e i

_ o pk sD cniy i 5um i s wd rin cc- aerl tk . t ae uuol hi

_ et odae0 oett s l 1 s

- h b rrecu b r a nt c1 ib c n li et -

l dasxx d ea umt eh -

_ cue e3 aere c ahtf oes

_ nc r s1 ns rv l l e t n

o t wnr c oo ol an adf ah cr -

i aB etii ch ni o, oric aBit t -

n i e gi o r. cC

.lU eP c

ec reei anr

- ne f1 e 3c.

c mxaa t c i l e e urt a tM gtt c oar a1 x ed ur _

enh mo aa . d r t - e h ne

_ t n

e 1

- ho t ede r r t

i r r mco -

dt r d

-sI n

t el a pnh meeav e rprl o it e ri rpet

_ u r e ah i cc i oA l e' lnact mhhaavl o.s f em f

f c'.ecduw aR eeone xnn eeec ol l t e yt t cee h rit c siTm nh E d l- h t a r t e e a }, td orno e r

_ e dEt yret ,e u r rrb l nord sd n

r o di( l ae . d r e l aoicii rt/t x eeme d gusn eh l crr si oed bbd e i ec 8

_. o l h s ecm ramag i ooao erma h b af t ii - ori ei aat eer h eue /

r ' nt rf n exl s t ct l y Tc sl 8 i

- : e uf o nv n ee woee eh ese -

e t

A f* ot mcoc I aard I t cmrt

• d ar 3 -

?h 1 -

~

i. 1 li  :? .ii]jjjj j j4 !l{ ii t4i .j< j i ,4jii1; i lljj3' il! 1!,ji

Bases Continued:

The AEC staff performed an analysis similar to that used to determine the naximum release rate for I-131 for radioactive particulates. A reduction factor of 700 on the MPCa to allow for possibic ecological chain effects similar to those associated with radioiodine was used. The annual average diffusion parameter value of 1.5 X 10-7 sec/m3 was used as determined for the most critical sector for an elevated release at 600 n in the SSE sector. Based on these calculations, a continuous release rate of radioactive particulates with half-lives greater than 8 days in the amount of 9.5 X 10 9 MPCa pCi/sec from the off-g'as stack would not result in of f site annual organ doses in excess of the limits specified in 10 CFR 20. The resultant organ doses are not additise to those caused by the rndiolodine or gross radioactivity releases.

The staff performed similar analysis for the reactor building vent release as for the off-gas stack releases except the releases were considered to be at or near ground level. The maximum annual average diffusion parameter (X/Q) from the particulates is 1.3 X 10 gicenseg's sec/m . met,eorolerical d9 6 for the ground levbl r"Jmce an used for rnMoactive as used for radiolodine is 3.5 X 10-}hesec/m anngal. Based average ondiffusion parameter aatcontinuous these calculations, the nearestground existing milk cow level release rate of 1-131 in the amount of 1.2 uCi/sec would not result in offsite annual thyroid doses in excess of the limits specified in 10 CFR 20 of 1500 mrem. A continuous ground legel release rate of radioactive particulates with half lives greater than 8 days in the amount of 1.1 X 10~ MPCa pCi/see would not result in offsite annual organ doses in excess of die limits specified in 10 CFR 20.

In order to limit radiolodine releases in gaseous releases to as low as practicable, quarterly average release rates have been established which would require investigative actions at 2 percent of the maximum release rate and restricted operation action at 4 percent of the maximum release rate. These release rates are significantly below 10 CFR 20 linits and are factors of 2 and 4, respectively, above t'ie design objectives as defined in Regulatory Guide 1.42.

In order to limit radioactive particulate releases in gaseous effluents to as low as practicable, quarterly average release rates have been established which would require investigative actions at 2 percent of the maximum release rate and restricted operation action at 8 percent of the maximum release rate. These release rates are significantly below 10 CFR 20 limits and are factors of 2 and 8, respectively, above the design objectives.

3.8/h.8 BASFS 178 REV

. .- - - ___ _ _ ~ - .- . .. . _ .- . - _ _ . - .- .- ~ _. ____ _. -

~

Bases Continued:

Measurenents of the gross radioactivity from the off-gas stack r,ust be continuously monitored for possibic changes in the release rates from the augmented off-gas system. Additional measurements are made continuously at the steam jet air ejector to evaluate the core condition and the quantity of radioactivity being added to the augmented off-gas system. The measurements obtained by sampling and isotopic analysis define the releases to the environs. Quarterly analysis for tritium is adequate to define such releases to the environs.

Isotopic analysis will be performed on samples taken fron the steam jet air ejector. These sampics will be used in an inotopic analysis for Xe-138, Xe-135, Xe-133, Kr-88, Kr-87, and Kr-85m, which is calculated to be approximately 90 percent of the noble gas emission. The renaining noble gases will be calculated from empirical ratios with the measured cases. Such calculations will be made for the various gases down to a release rate of 100 uCi/sec. Argon 41 will not be nensured routinely since. It cannot be measured in the presence .of t he other noble gases.

The measurements and methods used for releases from the reactor building vent are similar to those described for releases from the off-gas stack. It may be necessary to use of f-gas stack data to evaluate the predicted lou levels of release frou the reactor building vent. Batch releases may be made during drywell purging or other special conditions when continuous monitoring is not avialabic. For such conditions, sampling and analysis are required before releases are made and meterological corditions rny 1,e uced. i r practical, to reduce possible environmental ispact for such releases. If the samples indicate high concentrations of either radioiodines and/or radioactive particulates, the releases shall be filtered by the Standby Gas Treatment System.

Concentrations of gross radioactivity in the reactor building vant are expected to be below the minimum detectable levels with the existing analytical equipment. Therefore, isotopic analyses of samples from the

vent will not normally be performed.

Measurement of the gross radioactivity from the duct to the vent is based upon an equivalent dose rate for the release rate in curies per second, i.e., analysis of a typical vent gas release resulted in a gamma dose rate of 3 mr/hr being equivalent to 21,000 microcuries/second release rate. Since an isotopic analysis cannot be made routinely.of the vent effluent, the assumption is made that the isotopic composition in the vent will be the same as determined in the off-gas stack.

3.8/h.8 BASEC 179 REV

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

i I

. t i

i Bases Continued:  ;

The release of radioiodine from the reactor is monitored by the use of charcoal cartridges which integrate i

' the releases over the sampling period of one to neven days. Frequency of removal is dependent upon the release level measured on the previously removed charcoal cartridge. The relationship between coolant , .s.  !

]

1 activity levels for radioiodine and effluent releases during possible iodine' spiking conditions has not '

been determined. Measurements required for such possible operating conditions that may result in iodine spiking should provide necessary effluent data to the operator to evaluate plant conditions during such periods. The analysis performed for I-133 and I-135 indicates the contribution of these ridioiodines to  ;

the possible inhalation dosca. ,

i The release of radioactive particulates with half lives greater than 8 days from the off-gas stack is ,

, monitored by the use of particulate filters which integrate the releases over the sampling period of one to seven days. All other aspects of particulate release measurements are similar to 'those discussed for j radioiodine release measurements except for the relationship of iodine spiking to reactor opertting q '

4 conditions.

l B. Mechanical Vacuum Pump Mut purpose of isolating the mechanical vacuum pump line is to limit release of activity from the main .  !

condenser during a control rod drop accident. During the accident, fission products would be transported >

from the reactor through the main steamlines to the main condenser. The fission product radioactivity would be sensed by the main steamline radioactivity monitors and initiate isolation, j C. -Liquid Effluents i i  !

! The radioactive liquid effluents from the tbnticello plant will be controlled on a batch basis with each i t

i batch being ;rocessed' by such method or methods appropriate for the quality of materials determined to be

]' present. Those batches in which the radioactivity. concentra" ions are sufficently low to allow release to

~

the discharge canal are diluted with condenser circulating water in order to achieve the allowable concentrations set forth in 10 CFR 20. The radioactive liquid will be sampled and analyzed for gross 5

radioactivity prior to release to the discharge. canal, thus providing n means of obtaining information on

! effluents to be released so that appropriate release rates will be established.

! , i 38/h.8 BASES 179A PDT t t

Bases Continued:

Liquid effluer t release will be controlled in terms of the concentrations in the discharge canpl. In the case of unidentified mixtures, such concentration limits is based on the assumption that the entire content is made up of the most restrictive isotope in accordance with 10 CFR 20. Such a limit assures that even if a i

person obtained all of his daily water intake from such a source, the resultant dose would not exceed that specified in 10 CFR 20. Since no such use of the discharr,e canal is made and considerable natural dilution ,y occurs prior to any locations where such usage could occur, this assures that off-site doses from this source will be far less than the limits specified in 10 CFR 20.

If radioactive effluents are released to unrestricted areas on a radionuclide basis, the MPC shall be determined and controlled in the cooling water discharge canal in accordance with Appendix B Table II Column ,

2 of 10 CFR 20 and Note 1 thereto.

Ihch batch to be released will contbrm to 10CFIPO relence limits on an instant intous basic, i.e., anntal averaging will not be uced as pemitted by lOCFICO. See Section 9 2 3 or the ICAR. The radioactivity level in the discharge canal for a given releare of vaste will be the highest when the dischar6e canal flow is lowect. 'Ihis occurs during " closed cycle" cooling tower operation at which time the cooling tower blowdown of approximately 36 cubic feet per second is the ma,)or flow in the discharge canal. 'Ihe rate of pumping the mdwiste effluent into the discharge canal is variable and can, therefore, be controlled to maintain the concentration within the specified limit. Tnis type of operation will be employed only when the river flow is very low and will result in further dilution between discharge canal effluent and the river.

D. Radioactive Waste Storage The waste sample, floor drain, vaste surge and condensate storage tanks are not contained in a Class I structure. A postulated catastrophic failure of these tanks could cause release of the contained radioactive liquids to the river. To assure that such a postulated release from all the tanks vould not I raise radioactivity levels in the river at the public water intakes to values greater than 10 CFR 20 limits, the maximum amount of radioactivity that can be contained in these tanks is established, i

3.8./4.8 BASES 179B REv

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

f Ba,ses Continued:

l E. Au :mented Of f-Gas Gystem e

The hydrogen monitors are used to detect possible hydrogen buildups which could result in a possible ,%

hydrogen explosion. Isolation of the off-gas flow would prevent the hydrogen explos'$n and possible danage to the augmented off-gas system.

Experience has shown that a daily check with month 1v testing and cuarterly calibration assures proper operation of the hydrogen monitors nnd quarterly calibratL'n assures proper operation of the radiation monitors.

The maximum gross radioactivity in one gas decay tank has been limited on the basis that accidental release of its contents to the environs by operator error af ter 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> decay e5ould not result in exceedin6 the dose equivalent to the maximum quarterly release rate specified in Specification 3.8.A.2. Staff analysis of an elevated reIcase under accident reteomlo: f for a minimun mlence .perievi of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> indicated a relcase of 22,000 curies of Xe-133 or the dose equivalent would result in a whole body dose of 20 mRen at the nearest site boundary.

The frequency for monitoring or sampling has been established so that if the maximum amount of gross radioactivity is exceeded, action can be taken to reduce the radioactivity to a level below the specified limit.

4

p. Environmental Monitoring Program It is recognized that a precise determination of .environmentaldose from a certain emission from the stack is only possible by direct measurement. Such information will be provided by the environmental monitoring program conducted at and around the site. If the stock emission ever reaches a level such that it is measurcable in the environment, such neasurements will provide a basis for adjusting the proposed stack limit long before the effect in the enviro ment is of any concern for permissible dose. In this regard, it is important to realize that averaging emission rate over a period of one calendar year as permitted by 10 CFR 20 represcnts a very large safety margin between conditions at any one instant (anv minute, hour or day) and the long-term dose of interest.

3.8/h.8 BASES 179C BEV

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

. AEC CTRIBUTION FOR PART 50 DOCEET M'* SRI AL 7971

• (TDiPORARY FORM) CONTROL Nos

- FILE:

1 1 FROM: DATE OF DOC DATE REC'D LTR MEMO RPT OTHER

! Northern States Power Company

} 'finnenpolis, Minn. 55401 Mr. L.O. Mayer 10-31-73 11-2-73 X l

l TO: ORIG CC OTHER SENT AEC PDR vrx I 3 signed SENT LOCAL PDR xxx J.T. O' Leary ,

l CLASS UNCLASS PROP INFO IhTUT NO CTS REC'D DOCKET NO:

I j XXX XXX 40 50-263 i DESCRIPTION: ENCLOSURES:

Ltr requesting a chance in tcch specs... .trans Request for chance in tech speg. , notarize ;

the following........ 10-31-73, consist of revisioe to replace

[ change #2 in its entirety.

- - ~ -

(40 cvs enc 1 rec'd)

PLANT NAME

Monticello ygy , ,

[,3 1

FOR ACTION /IhTORMATION 11-2-73 Jb BUTLER (L) SCINENCER(L) /ZID1 ANN (L) REGAN(E) 1 W/ Copies W/ Copies W/1 Copies W/ Copies CLARK (L) STOLZ(L) DICKER (E) .

W/ Copics W/ Copies W/ Copies W/ Copies i GOLLER(L) VASSALLO(L) KNIGHION(E) i W/ Copies W/ Copies W/ Copies W/ Copies 4

KNIEL(L) SCHD1EL(L) YOUNGBLOOD(E)

W/ Copies W/ Copies W/ Copies W/ Copies

! ~ INTERNAL DISTRIBUTION j kREGFILEd TECH REVIEW DENTON LIC ASST A/T IND j /AECIDR HENDRIE GRIMES BRAI'DiAN 4

YOGC, ROOM P-506A SCHROEDER GAMMILL /DIGGS (L) SAL'IZMAN 4

/MUNI21NG/ STAFF MACCARY KASTNER GEARIN (L) B. HURT CASE KNIGHT BALLARD GOULBOURNE (L) l PMNS

GIAMBUSSO PAWLICKI SPANGLER LEE (L) MCDONALD BOYD SHA0 MAIGRET (L) /bUBE MOORE (L)(LWR) STELLO ENVIRO SERVICE (L)

DEYOUNG(L)(IVR) HOUSTON MULLER SHEPPARD (E) IhTO r SKOVHOLT (L) NOVAK DICKER SMITH (L) C. MILES Pa COLLINS ROSS KNIGHTON TEETS (L) / iCABELL IPPOLITO YOUNGBLOOD WADE (E)

/ REG OPR TEDESCO REGAN WILLIAMS (E) I FILE 6 REGION (3) LONG PROJECT LDR WILSON (L) l MORRIS LAINAS

. STEELE BENAROYA HARLESS VOLIMER /

EXTERNAL DISTRIBUTION M j V1 - LOCAL PDR m.,nnnnnlic. m ., n .

/ / l VI - DTIE(ABER';ATHY) (1)(2)(10)-NATIONAL LAB'S 1-PDR-SAN /LA/NY /

/1 - NSIC(BUCIW;AN) 1-ASLBP(E/W Bldg.Rm 529) 1-CERALD LELLOUCHE i

1 - ASLB(YORE /SAYRE/ 1-U. PENNINGTON, Tc E-201 GT BROOKHAVEN NAT. LAB f

WOODARD/"H" ST. 1-CONSULTANT' S 1-AGMED(Ruta Gussman)!

/16 - CYS ACRS C-+w Sent to Dinen NEWMARK/BLUME/AGBABIAN RM- B-12 7. GT.

l 11-I-73 1-CERALD ULRIKSCN. . . ORNL 1-ED. . MULLER. .F-309 S ;

- _ . - . - . . . . . . , . - - - - . - . _ . -