ML20024G703

Proposed Tech Specs Clarifying Certain Sections of Interim Radioactive Effluent Tech Specs

ML20024G703
Person / Time
Site:	Monticello
Issue date:	03/20/1978
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20024G392	List: ML20024G391 ML20024G393 ML20024G703
References
NUDOCS 9104250410
Download: ML20024G703 (9)

Text

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EXHIBIT B i

LICENSE kiENDMEhT REQUEST DATED RARCH 20, 1978 This Exhibit consists of the following pages revised to incorporate all of the proposed Technical Specification changes:

TS B.2.4-4 TS B.2.4-8 TS B.2.4-13 TS B.2.4-17 TABLE TS B.2.4-2 (page 1 of 2)

TABLE TS B.2.4-2 (page 2 of 2)

TABLE TS B.2.4-3 TABLE TS B.2.4-1 FIGURE TS B.2.4-1 1

9104250410 780320 I DR ADOCK 050 g3

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

1 1

i l .

e. The flow rate of liquid radioactive vaste shall be continuously measured and recorded during release.

f. The continuous effluent monitors listed in Table 2.4. 3 shall De calibrated at least quarterly by means of a liquid er solid radioactive source wqich has beet. calibrated to a National Bureau of Stardardt source. Each tenitor shall also have a functional test renthly and an inatrument check prior to makinc a release.

g. During each release cf liquid radioactive vaste, the liquid radvsste dischstge =onitor res. dings etall be correlated with the resulte of analyses performed prior to release.

Bases: These Specifications are applicable until Specifications prepared in accc dcnce - ith Arpendix I tc- 10 CTR Part 50 are issued by the Cocnission. In sete cases these Specifice-ions may be core restrictive than required by Appendix I. In the event that plant availability is adversely

~

affected by these Specifications, the licensee may apply to the Cocnission for appropriate Technical Specification changes on a case by case basis.

Specificatien 2.4.1.e requires the licensee to limit the concentration of radioactive materials in tiquid waste effluents released from the site to levels specified in 10 CTR Part 20, Appendix D, Table II, Colu=n 2, f or unrestricted areas. This specification provides assurance that no me~ber of the Feneral public will be exposed to liquid containing rad'.ce:tive caterials in excess of limits considered permissible under the Coc: mission's Regu la t i ens .

IS B. 2.4-4

l l

vhere the values of K g, L t , Mg and Ng are provided in Table 2.4-5, and are site Jependent gamma and beta dose f actors.  !

Q = the ocasured release rate (Ci/sec) of the radiciodines l and radioactive materials in particulate forms with half- -

lives greater than eight days.

1.1 = average ratio of tiseue to air energy absorption coefficients.

a. Should any of the conditior.c of 2.4.3.n(1) or (2) be exceeded, the licensee chall take appropriate corrective action to bring the relences within therie limitt.

(1) Ihe release rate Ibtit of noble gases from the site shell be such that 2.0 ( QTv_v E Is s IE I a:d 0.33 7y(Iy 4 1.lEy) + QTsI e + 1'1  : Ib l (2) Tht relcare rate iteit cf all radiciodines and radioactive materials in particulate form with half-lives greater than eight days, released to the environs si part of the gaseous wastes from the site shall be such that 3.7 x 10 Qy + 2.5 x 10' Q ji 1 TEB.2.L-c

4 TABLE IS B.2.4-2

.'RLICAC"'!VE GASSTS WAETE f.AMIfC A?O Analysis Gaseous Sa=pling Type of Detectable  !

Source frequency Activity Analysis Concentraticns!

(uCi/ml)*

h A. Contain:ent Nrces Each Parge Principal Noble Gas Garra 10L b Emitters [

I PrincipalpobleGasGarna L t ,:

E. Envirer.nented Felease Monthly .

Enitters Pointo (GasSamples) 11 - 3 lo-6 Weekly I-131 10 12 d l I ( ~.stircot.1 fx:ple o )

Monthly I.133, I.135 10-10

( Charecal Sa=plec)

. Weekly Principal Particulate Ganoa 10-11 d (Im rticulates ) Emitters (a t least for Ba-La-140 and I-131

.tnthly Co= posit e* Fr-80 3C~11

hrticulates) j Grecs Alpha 1 1C-L f G rly Cc=posite*

( Pr.rti culates ) Sr-90 10-21

• ?;-e ateve detectatility lindte for activity aulysis are based on technien1 feasibility tri en the potentie.1 cicnifican:e in the envirorsent of the quantities released. Fcr scce nu:lider, lover detection 11=its ray be readily achievable, e.nd when nue11 der are meesurad below the stated litite, they thould race te reported.

b Analyses shall alre be perfomed followinc ea:t refueling, startup, or cicilar operatienta oe:urrence whi:t c uld elter the cirture cf radionuclides.

U Icr certain tix+.ures of gn==a emitters, it may not be possible to measure mdionuclides at levels near thcir tensitivity limits vter other nuclidec are present in the ca:Ple at much higner levels. Under these circumstances, it vill be more appropriate to calculate the levels of such mdionuclides usirg observed ration with those radionuelidee which are censarable.

IAELE TS L.I.l.-2 (Page 1 of 2)

9 IABLE T5 B.2.4-2 Notes (continued)

J When the average daily gross radioactivity release rate exceeds that given in 2.4.3.c(1) or where the steady-state gross radioactivity release rate increases by $00. over the previous corresponding power level steady state release rate, the iodine and particulate collection devicosfor the release point whose contribution exceeds 50% of these rates shall be removed and analyzed to determine the change in iodine-131 and particulate release rate.

The analyses for this release point shall be done daily following such change until it is shown that a pattern exists which can be used to predict the release rate after which it may revert to_ weekly sampling.

• To be representative of the average quantities and concentrations of radioactive materialt in particulate fonn released in gaseous effluents, samples should be collected in proportion to the rate of flow of the effluent streams.

t Concentrations rm' be of individati ramma enittert in the Beactor Eatidine vent  !

belm. the minimum dc tcctable levels with the exis ting ana'lytici. .

equipment. Therefore when isotopic analyst s of samples from the vent cennet be perfermed, the isotopic content vill- be assumed to be thet existing at the steam jet air ejector.

g Containment purges are always made via the standby gas treatment system and the plant stack.

The plant stack continuous gross gaseous, particulate, iodine , and tritium raonitoring systems respond to these releases. An analysis for individual noble gas gamma emitters is made to permit the quantities of individual isotope to be quantified. Normally, noble gas releases due to egntainment purges are neg11 gable compared to releases from the main condenser offgas system.

IABLI TS B.2.4-2 (Page 2 of 2)

c. An isotopic analysis shall b< nede of a representative sa=ple of gaseoua 1

activity at the discharge of tFt steam jet air ejector $ nat nt the pinut stack:

(1) at least monthly, and (2' f ollowing each refueline *utage, and (3) if the stet: .'et nir eje-tor conitors indicate an increa.se of greater than 50% in the steady state fission gas release af ter f actoring out increases due to power changes. l Following en:h tnalysis, steam jet air ejector monitor and sta:h monitor readings shall be correlated with the r* salts ci the analysis,

d. Tne rnti:.nar e:Tluent monitore listed in Table 2.h.h chn11

-cd r- I v rt qurr e 2: t:, tennr of r Mor. -erem:r or rol t6 rnd?.ot":P - cource unich hnc been enlibrated to e t- nni iuretu of Ctandardt t o tree. Ihch monitor rht.11 heve n

..i 11onnl tert at leer monthly trid an instr =er.t cheri. nt l o c '- inily.

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e. Serpling and analysis of radioactive material in gaseous vaste, including par:iculate forms and radiciod!nes shall be performed in accordance with lable 2.4-2.

f. The hydrogen conitors shall be functionally tested monthly and estibrate?

quarterly with an appropriate gas mixture source. Each moniter shall have a sensor check at 1 cast daily.

p. Condenser air inleakage shal A be evaluated weekly and used in conjunctien with ster: jet air ejector c2fges isotopic analyses and Fi;ure 2.4-1 to en determine that the limit cf Specification 2.4.3.j is not exceeded.

Y; .2.h-13

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

Spscification 2.4 .i is intendsd to monitcr the pe. 3rmance of the ecre. An-increase _ in the activity levels of gaseous releases may be the result of defectivt iuti. Since core performance is of utmost importance in the result-ing doses from accidents, a report must be filed within 10 days following the specified increase in activit/ level at the steam jet air ejector.

Specification 2.4.3 3 requires that tne drywell atmosphere receive treatment for the removal of gaseous iodine and parti:ulates during purgint. When containment integ.rity is not required, ventilation air is not treated but le released through the monitored reactor building vents.

Specifiention 2.k.3.h requires that hydrogen concentration upstream of the ec=prersed mdioactive gaseous stomge tanks chall be monitored whenever

- the ccepressed stomge subsystem is in use.

Epecification 2.1. 31 requires offgas flow to the ec= pressed storage tanks to be te:sinated in the event that the hydrogen monitors downstream of the recombinere ut inope mble. 31c prevents the possible accumulation of an

, explccive mixturt in podionc of the offgas system which are net designed to fully withstand a hydrogen detonation.

Specification 2.4.3.j limits the maxie.an gross activity in one decay tank 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 should not result in exceeding the dose equivalent to the maximum quarterly release rate specified in Specification 2.4.3.c.1. Staff analysis of an elevated release under accident meteorology for a minimum release period of E heurs indicated a release of 22,000 curies of Ae-133 or the dose equivslent would result in a whole body dose of 20 mrem from noble pases at the site beundary.

Calculations have been performed to determine the relationship between stea=

jet air ejector offgas activity and composition and condenser air inleakage.

Ihese calculations were used to determine the curves presented in Figure 2.4-1.

Ihe results of the measurement of condenser air inleakage and the average air ejector offgas release rate are used in conjunction with the TSB.2.4-17

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

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TABLE 15 B-2.4-3 LOGTIO!! OF LIQUID EFTIJTNT ?tmITfmS AND SAMPLERS Hir.h t;rsh h- inrement Liquid Praross St,1*nn Auto Control Continuous J n71 e Gro*= Dissolved Inutopic I# vel or R m!! s t i en to Isolation Station Activity I Cases Alphs l 11-3 Analysis Alarm Felent:e Ibint A l arrt Valve Montter X X X X X X X Fleer Drain Secrple Tank X X X X X X Laundry Drain X Tank X X Primasry (bolant  ;

Systen " i X X X Liquid Pndynr*e Di e-hn rga Pipa X X X Service Water Disetnrge Pip *=

Closed Cooling X X X Water Fystem 3 Dieeharge thnal X X X S m ler I

a Sot in effluent release point.

TABLE TS R.2.4-4 IOCATION OF GASEOtf3 PROCESS Ann rrFLU'N r Mc'tI TORS AND SA.

M PIIRS Grab Radiation Auto Control to C(mt i mic r e Semple Measurment Process Stream or Pelense Point Alem I*olation Valve F' miter Station Noble Gas I Particulate H-3 Alpha Condenser /Afr Ejector (before X X X T X is, treatment systm) 3f fqcs Treatment Syntese 1,a ro m X X d i lut t on anr1 d ischa rge ) '

Hain Stack X X X X X X X X X Reactor !ksilding X X X X X X X X X Ventilation Systm Ibrbine th:11 ding X X X X Jeerating Floor

&chantcal Vacuum " X l

• b Isolation on mnin stena line high radiation.

I;ot an effluent release point. Monitor surveillance requireactits a re speciflod in the Appendix A Technical Specifications.

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. 30% NO O 10 20 30 40 50 60 70 80 90 100 LIMIT

. OFF-GAS DISTRIBUTION - % DQUILIBRIUM

. , , , i i i . . i 100 - 90 80 70 60 50 40 30 20 10 0 OFF-GAS DISTRIBUTION - % RECOIL + % DIFFUSION Figure TS B-2,4-1.

. Off-Gas Storage Tank Gross Activity Limits y.w.e-..,-..w ,.r.-