ML19268B779

Tech Spec Change Request 69 Re Protective Instrumentation Requirements,Radioactive Effluents & Radiological Environ Monitoring Program

ML19268B779
Person / Time
Site:	Oyster Creek
Issue date:	06/01/1979
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:
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ML19268B778	List: ML19268B777 ML19268B779
References
NUDOCS 7906070262
Download: ML19268B779 (24)

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JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION Provisional Operating License No. DPR-16 Technical Specification Change Request No. 69 Docket No. 50-219 Applicant submits, by this Technical Specification Change Request No. 69 to the Oyster Creek Nuclear Generating Station Technical Specification, changing sections 3.1, 3.6, 4.1, 4.6 and 6 to incorporate the requirements of 10CFR50, Appendix I and associated regulations.

JERSEY CENTRAL POWER & LIGitT COMPANY BY - [47/ . g VlecpPresifent f STATE OF NEW JERSEY COUNTY OF MORRIS Sworn and subscribed to before me this / day of ' e< < . - ,1979.

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Notary Public MARION M. BREE5E NOTARY PUBUC OF NEW ffR$ty

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95005504 7906070 A6 A

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN Tile MATTER OF )

) DOCKET NO. 50-219 JERSEY CENTRAL POWER & LIGilT COMPANY)

CERTIFICATE OF SERVICE This is to certify : hat a copy of Technical Specification Change Request No. 69 for the Oyster Creek Nuclear Generating Station Technical Specifications, filed with the U. S. Nuclear Regulatory Commission on June 1, 1979, has this 1st day of June, 1979 been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail addressed as follows:

The Honorable Mary Lou Smith Mayor of Lacey Township P. O. Box 475 Forked River, New Jersey 08721 JERSEY CENTRAL POWER & LIGilT COMPANY BY

05) N VicePpide DATED: June 1, 1979 95005305

m 7% og v$-- - --- Jersey Central Power & Light Company g l( [j ,' h L. Madison Avenue at Punch Bow! Road w '.maisc . Mornstown New Jersey 07960 (201)455-8200 June 1, 1979 The lionorable Mary Lou Smith Mayor of Lacey Township P. O,. Box 475 Forked River, New Jersey 08731

Dear Mayor Smith:

Enclosed herewith is one copy of Technical. Specification Change Request No. 69 for the Oyster Creek Nuclear Generating Station Technical Specifications.

These documents were filed with the U. S. Nuclear Regulatory Commission on June 1,1979.

Very truly yours, h y Ivan R. Finfr k, Vice President la Enclosure

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95005306

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JERSEY CENTRAL POWER 6 LIC11T CO)fPANY OYSTER CREEK NUCLEAR GENERATING STATION (DOCKET No. 50-219)

PROVISIONAL OPERATING LICENSE NO. DPR-16 Applicant hereby requests the Commission to change Appendix A to the above captioned license as follows:

, 1. Sections to be changed:

3.1, 3.6, 4.1, 4.6, and 6.

2. Extent of Changes:

Incorporate the requirements of 10CFR50 Appendix 1 and associated regulations.

3. Chances requested:

See attached pages.

4. Discussion:

The reason for this change request is discussed in the t ransmitt.a1 let ter.

I 95005307 Technical Specification Change Request No. 69

! F li.

l ) (;h 3.1-10 .

TABLE 3.1.1 PmTELTIVE INSTRUMENTATItU REQUIREMENTS (ONTD) g  ? tin. No. of

, Reactor Modes flin. No. of Operable in Which Function Operable or Instrument

, fiust De Operable Operating Channels Per (Tripped)Trin Operable Action Function Trip Setting Shutdown Refuel Startup Run Systems Trip Systems Required

• See note h

2. Low-Low-Lou > 4' 8" above X X X X 2 2 Reactor Water top of I Level active fuel i 3. AC Voltage NA X X 7 2 Prevent auto depressurization

{~~' on loss of AC power. See note i

! II. Isolation Condenser Isolation Isolate Affected i 1. liigh Flow Steam < 20 psig A P X X X X 2 2 isolation con-Line denser, comply with Spec. 3.8 I

2. Iligh Flow Con- [27"O P 11 0 2

X X X ,

X 2 2 densate Line I- DELETED -

J. Reactor Building Isolation and Isolate Reactor Standby Gas Treatment System Bldg.& Initiate g Initiation Standby Gas Treat-

U 1 1. liigh Radiation < 100 Mr/llr X X X X 1 1 ment Systen,.or O Reactor Building Manual Surveill-O Operation Floor ance for not more

2. Reactor Bldg. X X X X 1 1 than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

-< 17 ffr/Nr (total for all in-Ventilation

![ Exhaust struments under g J) in any 30-day

3. High Drvwell -< 2 psig X X X X 1(k) 2(k)

- Pressure period.

4. I.ou Lou Reactor > 7 ' 2" ab ove X X X X 1 2 Water Level top of active fuel

MN 3.1-17 .

• a

.;

t  ;

0 TABLE 3.1.. ) (C013T'D.) ,

V .

• Action required when einioun conditions fer operation nre not satisfied. Also perniscible to trip inoperable trip spte n. k* hen necessaty to conduct teate and calibrations, one chv2c1 may,be made inoperobic for up to -

one hout per tionth withc.,yt trip? i ng'its trip systen. .

• • Fee Specification 2.3 for Liniting Safety Systen Settings.

?:otes:

a. Fernissibic to bypass, with control rod block, for reactor protection systen reset in refuct teode. .

b. Pernissible to bypass belov 40 psig in refuct and startup redes.

c. One (1) APRM in cach operable trjp system may be bypassed or inoperabic 'provided the requirements of' specification 3.1.C and 3.10 D are satisfied. Two APPJ1's in the same quadrant shall not be conc #rcatly bypassed except as noted below: .

Any one APRl! may be removed from service for up to one hour for test'or calibration without inserting trips in its trip system only if the remaining operable APPJi's meet the requirements of specification 3.1.15.1 and no control rods are moved outward during the calibratien or test. During this short period, the requirements of specifications 3.1.11.2, 3.1.C and 3.10 D need not be met. ~.

L~nen in the Refuel ?! ode, ts:o APRI!'s in the sanc quadrant may be m.ide 'inoperabic during replacement of an ,

i.PPJI ::sscmbly, provided that the Source Range Cha mel and both Internediate Range Channels in that quadrant arc operable and provided that the Renovabic Jutpers for nefucIJng tron-Coincidence have been removed.

The (1101) shell be inserted and operable ont ti the APici's . ire operat.le anil reading a* h ast 2/150 full secle. -

d.

e. DEIEfED ,

f. Unicss SR}i chonbers are fully inserted.

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1:ot applicabic when IlUI on louest range.

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h. One instrument channel in cach trip systcra etay be f riopernb}c provided tbc circuit which it operates in the

, t rip syste, is placed in a rioulated tripped condit ion. If, repairs cannot be completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> the If 'nore than one instrument. channe't in any trip o r ac trer -: ball be placed in the cold shutdo m condition.

C systen hecemes incperable the t eactor shall be pJcced in the' :old shutdem condit ien. Relief valve cont roll er e. shall not he bypasc._d for r ort- t: :.n 3 honr : (totala Linc tirc.

for all centtollers) In any 30-day

• p.:s ial .in.i coly rede relief valve contioller :ay I.c hys .m:c.! at

36 MDICACTIVE EFFLUENTS AoplicLLility: Applies t.o the radioactive ef fluents of the facility during all

r. odes of operation.

Cbject.ive: .To define the limits and conditions for controlled release of ranoi ct2ve r.ateritls in liquid and gaseous effluents to the ervirons to ensure that these releases tre as low as is reasonaoly achievable in conformance with 10 CFh Farts 50.34a and 50 35a, and to ensurc that these releases result in concentrations of radioactive materials in liquid and gtseous effluents released to unrest ricted areas that are in conformance with 10 CFR Part 20.

To ensure .that the releases of radioactive meterial above background to unrestricted nrecs are os lou cs is reasonably achievable, the followir.c desita objectives as dc rined in t.p;endix I to 10 CFP Part 50.36c apply:

a. h annual total quantity of L11 rMionetive mLterial above background that may L relened from the Oyster Cre"k Muc1 car Gencrcting Station to unrestricted crear should not result in an annucl dose er dose commitment fror liquid effluents for any individual in an unrestricted area from all pathways of e x ;.n s u r r- in excess of ? ~11111 rems to the total Lody er 10 mil] ire ~s t'.< any v'..

L. . nn s: 1 total quar.tity of cll rLdioactive ~.aterici above background th:t

':ay b. relenceJ from thc Oyster Creek MJclear GeneratinC CtClion to the Lt/t.or::.ere should nst result in :.n annuel air dose fran gaseous effluents at any locat.on near crc une levc1 wh'ich could be occupied by individucls iri ur.re;tricted crecs in excess of 10 millirads for ccm.a radiation or 20 uilliraJs for r t< rceiation, or tn:t this quantity should not result in en annual exh- 1 1ose f rom gasecus effluents to any individuc1 in unrestricted creas in exc. / ;f 5 n.illirems to Lne totL1 body cr 15 millirems to the at:f r..

c. Enqucl totrl qutntity of t.1} rtdioLetive iodine and radioactive :.nterir.1 in ;nruuula.te !crm ubove ba:mcround that n.cy b:. rc) cased from the Oyster Creek Nucle r Generatint Station in effluents to the atinosphere should not result in an annual dose or dose coa.T.itn ent from such radioactive iodine and radioactive material in particulate fonn for any individual in an unrestricted area from all potne ys of exposure in cxcess of 15 millirems to any organ.

Speci fiertions:

t A. CASE 003 WASTE EFFLUENTS

1. The concentration of radicar,1ve materials in gaseous effluents to unrestricted areas except iodines and 'ticulates with half lives longer than eight days shc11 not exceed the values specified in 10 CFR Part 20.106, as indu .tcd in thc fol'.owine, equation:

0 = 0.21 Curies /Sec.

E 95005310 3.6-1

'uere C is the sta:k reletse rate (Curies /fec) of gruss activity and T is the averLge gtntna energy per disintegration. (Mev/ dis).

The mr.xiwn release rcte of iodines and particulates with half lives longer tha eight acys shall not exceed 4 'nicro:uries/sec.

2. The design cbjective annual air dose from radioactive noble cases in gLseous effluents to unrestricted crecs in each direction sector is 10 mrad for cc~rna radiation F.nd 20 r. rad for betc radiation.

3 The design objective annual dose or dose commit nent frcrn radic-iodines, radicoctive ncterial in ptrticultte form :nd radio-nuclides other than noble ccses in gaseous effluents to unrestrictcd crecs in each direction sector is 15 nrem to the total body cr Eny cre,Ln.

4 Dases due to the release of radioactive materials in gaseous effluents shall be c lculrted for e:ch calendtr quarter of reactor op?rction and compared with these dose objectivcs.

5. ic.Jio;Lses releuca from the stc01: shall be continuously *t.cnitored except for t.a short per is of time d uring monitor filter changes, required surveillance testint . r.pl e system purgin ;, cnd following unanticipated sample p um;) trips. If this specification cannot be met, a reactor shutdown shall be inititet.J withir. 2 h;urs anc the ret: tor shall be placed in the isolttcd w 'it ic - ..ithin 20 ho r .

C. ... - y . ;. ..t instvilcJ c, the cast cus radionctiv e W't.ste systua shall be mu nteir.ej and snail N oporr.ted ns necessary to ,rct the design objectives of Epecifi_aticn 2.C.A.2 a.d 3

• / . If the act.ual relu.se of radioactive materials in geseous cffluants results in a lcLitted dose exc* din 3 one-hc1f th' design objectives of 3.6 A.2 cr 3

bwe , in .y

Lleniar quarter, the followinc action shall be tM:en:

.. r'- an investil;ttien t3 Identify the causes for such relensc rttes,

b. :ofine n. initiate a pro.; ram of action to reduce such re ,- to tpecif a .ier. 3. t .l. 2 ar.d 3. L. A. j, and

c. report these :tions to the 11RC within 3D days frcrn the ena of the quarter.

L. LIOU1 AACTE EFFLUE':TS i

1. Ine concentration of radioactive materials released in liquid effluents to unrestricted areas shcl1 not cxceed the values specified in 10 CFR Part 20.100.

2. The design objective annual dose from radioactive r.aterials in liquid effluants t.c unrestricted areas is 3 mrec to the totcl body and 10 mrem to any organ. Dases ale to the release of redioactive materials in liquid efflu?nts chall bt calcultted fcr cach cclendcr quarter of reactor op3rction and compcred with thest dose objectives.

95005311 3.6-2

the recc sbiner shall be li'r.ited to 4% by volur,e at all times except as specified in 3 6.F.2, 3.6.F. 3, and 3 6.F.4

2. If the con 0entration of hydrogen in the op3 rating recombiner train exceeds 47, the inlet vs1ve in that train shall be tripped closed cnd the system purgen with air. Augmented offgts system operation may continue through the other recombiner train.

3 If the concentration of hydrogen downstream can,ot be maintained at 4% or less, then the augmented offr,as system shall be bypassed.

4 Operation of a recombiner may continue with a hydrogen monitor out of service for up to 14 days if a grab sample for hydrogen is taken ano Srmlyzed ct tt Wst every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

G. V,cin Condenser Noble GLs Activity

1. The gross radioactivity rate of noble gases input to the augmented off-3as system cs.ct.lcuhted from samples taken at the air ejcetcrs shall be limited to

.21/L Uhere E is the Everrae gt=3 energy per disintegration.

2. .,ith

• ' the gross radioactivity rate of noble gcscs exceeding the above limit, restore the gross radioactivity rate to within its limit within 15 minutes or isoltte tha reactsr.

Enn : .Jome raciusetiv< uteritl is relerscd from the plcnt under controlled car.:.t..ns as part of the nmr.cl o;seration of the facility. Otner radioactive mrtcrial not ner:ully intended for release could be inadvcrtently released in the (vent of certain c:cident ecnditions within the facility. Tnerefore, limits have baen placca on the above types of radioactive materials to assure not exaceding the IJmits of 10 CFR 20 for the fonner type and the guideline limits of 10 CFi.100 for the letter typ2.

Tnc specifications in Gaseous n.ste Fffuents are provided to ensure that the dor: rLte at cny time at the exclusion area boe Jary from r,cseous effluents wil) be u @in thc ennual donc limits of 100FR Pcrt 20 for unrestrictei areas. The annwl dose limits are the dosas cssociated with the concentrations of 10 CFR ParL h , Appendix B, Table II. These limits provide reasonable assurance that radioactive mat: rial discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or cutside the exclusion croc boundary, to annual averago concentrations exceeding the limits specified in Appendix E, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)) .

The case restrictions on noble gases tre provided to insure the implementation of the guidelines provideJ by Sc0tions II.B III. A, and IV. A of Appendix I of 10 CFR Part 50. Tne dose restrictions on radiciodines, radioactive material in particulate forms and rodionuclides other than noble gases are provided to implement Sections IIc, IIIA and IVA of Appendix I of 40 CFR Part 50.

Continuous monitorinc of radiogases provides the means for obtaining information on Stock relecse rcte limits In the event continuous monitoring isnot availcble, the reactor is isolated fron the turbine condenser end, therefore, is isol:ted from the plant stack. 'Ihe isolatien would normally be expected to be comp'.mtet within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

95005312 3.6-4

f. . T.ie cquipunt installed in the liquid radioactive waste system shall be mainteined and shall be operated as necessLr meet the desi[;n objectives of Specifications 3.6.B.2.

4 If the actual release of radioactive materials in liquid effluent results in a calculated oose exceeding one-half the design objectivcs of 3 6.B.2 in any calendar quarter, the following action shall be taken:

a.  :.ake on investigation to identify the ccuses for such releases,

b. define and initiate a progrcm of action to reduce such releases to S;>ccifiction 3. 6.E.2 and ,

c. re crt these actions to the NRC within 30 days frcen the end of the quarter.

C. Ptdisactivc Linuid Stcrare Tn. neximum amount of radioactivity, exclujing tritiun, noble cases, and those is: tap 3s with nalf lives snorter than three days, contained in the radwaste sta r g;e tanks outside the radwLste building shtll not exceed 10.0 curies.

If tnis activity exceed 5.0 curies, then tne stored liquid will be recycled to tanks within the radwaste facility until the level is reduced below 5.0 curies.

'. c-ter C clnr.t - _in stivity

'1, . ncmtr t. n of t w tettl iodine in tnt et coolant shall not exceed 0 u i/ v . If L:.is specification cannot be act, the ret,ctor shc11 be placed in the 001: sh;tdo':n condition.

E. Se

1. me dos: ar dose ccm/.itment to a real indivijual in the unrestricted area n mil uranium fuel cyclc sources is limited to < 25 r.re9 to the total body cr en) organ ( c x ot pt, thu thyroid, which is limith to <75 mrcm) cver a period of

• ht ru-rtnt lenJnr year. Compliance with this specifica' ton shall be m uered to be met provided that the design objectives 01 Specificctions J . t . i. . E , ; . C . T. . : and 2.6.D.2 are not exceede-J by a factor of tw ,

2. rlith the calculated dose frcn: the release of radioactive materials in liquid or casects of fluents exceeding twice the design objectives of Specificator.3 3 6. A . 2, 3.'.t. 3 or 3.6.B.2 , prepare and submit a Special heport to the Comnission within 33 days and limit the subsequent releaes such that the dose or dose commitment

• o a r eal individual from all uranian fuel cycle sources is limited to <25 r. rem to the total body or any organ (except thyroid. wnich is limited to <75 mrem) over the current calendar year. Tnis Special heport shall include an analysis which demonstrates that radiction exposures to all real individuals froa all uranian fuel cycle sources are less than the 40 CFR 190 Star.dard. Cr hernse, obtain a variance from the Ccmmission to permit releases which exceeds the 40 CFR Part 190 Standard.

F. glosive Gas Eirure

1. Tne conn .tation of Hydrogen in the augmented offr,as systen. downstrearn of 95005;i3 3.6-3

It is reco;nized ? precise determinction f environmental dose fr:m a certain emissien .* a t he stack is only possible by direct mensurement. Such information will te provided by the environmental ,cnitoring program (Section 4.5) conducted at and oround the site. If the stack emission ever reaches a levtl such thtt it is measurenble in the environmcnt, such measurements will previde a basis for cdjusting tre proposed stack limit Icn3 before the effect in the environment is of any concern for permissible dose. In this regard , it is importr.nt to realize that not tvercging emission rate over a period of one caltnitr year as parmitted by to CFTt 20 represents a very large safety margin between conditions at any one instant (any minute, hour or day) snd the long term dose of interest.

'i h e radioactive liquid ef fluents f rom the Oyster Creek Station will be cor. trolled on t batch basis with each batch being processed by such method or meth:. s .ppropriate for the quality ,nd qu,ntity of .sterials determined to be prescnt. Those batches in which the radioactivity concentrations are suf f.cicntly 10.- to cllow reletse to the discharge canal are diluted with ccWnser circulcting water end/or dilution water. 'Ihe radioactive liquids will br c rr.pl e : ma an u yzec for radioactivity prior to release to the dis:hcrge 08nt., inus providin , ~.cnns for obtaining information on effluents to be rel m ed co th:t appropriate releste rates will be established.

Tne requirements of the specifications on Liquid Waste Ef fluents is to insure g li.n mit'. nppc ndix 1 of 1C CFil Part 50.

%.... rc mative 1.qJids on-site in or:er to pcrmit system:. tic and complete p ; _. .:' ., c o r s i s h r.t .cith maintaining rrd i oactive 11r^hargy to the env ir ; . nr.t = l o t, as ;)racticLble. Limiting the stored centents tc 10 0 curies of .ct.vity 'ccures th;t tven in the extrmly unlikely event of simultr.neous r t.p t ur ( af .11 thc tanks, the total cetivity discharged to the f.cy would be less than hvif the ctivity discharged to the Lay in one year if the plant were to disca.rr e ::nt.nuously wit h the effluent having a radiorctive concentration eq rl '- t: - l' :TR ? ? 7 for unidentified isotop:s.

Tne c.in p ai .,< ,/ t o m n for Lctivity deposited in the Day is tnrough the

- c .pt . x 30 qu; ir nicts since there are no drinking wnter supplies tahan fror L:w .u y . N conac ntrctions that could dev elo;) in the Ocncl tre reauced rapicly in tk bsy (We FDSAR Figure II.4.2). The peak concentrations exist for a relatively snort time in the Bay and this combined with the uptche time of the biotn could result in only minor increases in the equilibrium levels of radioisotopos in the biota. Isotopes with half lives less than three days are not of concern since there is sufficient delay between production in the plant, discharG by means of this postulLted accident and human consumption to preclude, their being biologically significant. Tritim nd noble gases are excluded also beccuse t w y Ln not biologically significant. ihe requirement to process the tank contents if the activity inventory exceeds 5.0 curies assures action is taken on a timely basis to avoid reaching or exceeding the limit.

The primary coolant radioactivity concentration limit of L.0 uCi total iodine per gra:: Of water was calculated based 7n a steamline break accident which is isolatea in 10.5 seconds. For this accident analycis, all the iodine in the mars of c:,olant released in this time period is assumed to be released to the atmosphere nt the to;) of the turbine building (30 meters) . f!y limitin:; the thyroid Jose tt th' site bound ar y to a max imuir of '0  ; Fem, the iodine 95005414 3.6-5

concentration in the primary coolant is bcck-calculated assuming funicaticn metccrology, Fasquill Type F at 1 m/sec. The iodine concentration in the prirr.ar'y coolant resulting from this analysis is 3.4 uCi/Gn.

Restricting the gross radioactivity ratc of noble gases to the augmented offgas system provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a sr.all fraction of the litnits of 13 CFR Part 100 in the cvent 'his effluent is inadvertently dischcracd directly to the envirorrnent without treatment. Tnis specification impirments the requirements of General Ecsign Criteria 50 and 64 of Appendix A to 10 CFR Part 50.

Tne specification on explosive gase mixtures is provided to ensure that the cenur.tration of ;20tentially cxplosivc gcs mixturer centained in tne weste ;cs treatment. system is mainteined below the fla= ability limits of hydrogen.

hut 0 r.atic cont rol featurer cre included in the systm to prevent th? hydrogen concentrations frcrr reachirc these flarn. ability limits. ~hese autcmatic control features include isolation of the source of hycrogen and, injection of dilutants to recucc the concentratior, below the flammability limits. "nintaining the

onn otration of hydrogen below their fla rr.cbility limits provides assurance that the rr. leases of radiact.ive r.aterisis will b2 controlled in conformance with the requirements of General Design Criterion 63 of Appendix A to 10 CFR Prt 50, ix. f, o .c. a (1) F

'u.F, Valace 1, Section VII-6.2.3 95005315 3.6-6

! . rt oir

( t Ins trement Channel Oieck. Cali b rat e Test Remarks (Applies to Test and Calibration)

APRM Scram Trips Note 2 1/wk 1/wk Using built-in calibration equipment during power operation 7

12. APRM Rod Blocks Note 2 1/3 mo 1/mo Upsca:1c and downscale

13. a. 111gh Radiation on Main 1/s 1/3 mo 1/wk Using built-in ca'tibration equipment Steamlice during power operation

b. Sensors for 13(a) NA Each Refueling NA Using external radiation source Outage

14. liigh Radiation in Reactor Building Operating Floor 1/s 1/3 mo. 1/wk. Using gamrna source for calibration Ventilation Exharst 1/s 1/3 mo. 1/uk Using gamma source for calibration e

15. li!!!J m iD ,

16. IRM Icve' NA Each NA During approach to shutdown only Shut down IRrf Scram * *

• Using built-in clalbration equipment

17. IPJf Blocks NA Prior to Prior to Upscale and downscale Startup and startup and Shutdown Shutdown

18. Condenser Iow Vacuum NA Each Refuel- Each Re f erel-Ing out age ing outage Ln O

o*

Cn Calfbrate prior to s t ar t up and normal shut d.n.ru and thercaf t e r chcrk I/s and tent 1/wk un t i l no longer required.

m Ir gen d: nae Not applicable; 1/s e Once per shi f t ; 1/d - Once per day: 1/3d = once per 3 days; 1/wk = onn- per week; l /3 no = on ce e ve ry 3 mon t hs .

CB

4.# RADIOACTIVE EFFLUE!JTS Ap:nicability: Applies to . onitoring of the gaseous and liquid rcdioactive ef fluents of the facility during Ell modes of operation.

Objective: To verify thtt discharge of radiocctivc ef fluents to the environment is kept to a practical minimum and, in any ever.t, within the liuits of 10 CFR 20.

Specificttion:

A. Goscous '..nstc Effluents

1. Station records of gross stack release rate of noble gase7us activity and mucorological conditions shall be .aintained on an hourly besis to assure that tr.e specified ratcs are not exceeded, to provide data for calculating offsite dca und to yield informction concernin; gtneral integrity of the fuel cladding.

2. .lithin ona month after issuance of these specifications and within one month following refuelings, an isotopic analysis will be made of a gaseous activity reise" sample which identifies ct leest 90 percent of the total activity. From t' i e m 'ple, a rrtio of lent-lived nr.d short-lived activity will be estcblished.

3 U :plet of of f :'nn will be taken at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and a gross ratio of long-lived and short-lived activity determined.

4 i.n isotopic nnelysis of off-gas will be performed monthly unless the ratio det.rmined in 3 above differs from the ratio established by the previous isotopic analysis by more than 20 percent. If this occurs, a new isotopic ene.ysis shall ne per form a .

5. Caseous release of tritiun shall be measured ct least quarterly.

6. Station records of stcek release of iodines and particulates with half-lives greater thar. eight days shall be maintained on the basis of all filter cartridges counted.

7. These eartridges shall be analyzed weekly for gross alpha, beta and gr.ma isotopic activity when the iodine or particulate release rate is less than 4 percent of the maximu~. release rate given in Specification 3.6. A.1. Ctherwise the cartridges shall be removed for analysis twice a week.

8. Knen the gross gaseous release rate exceeds 1% of the maximun release rate given in Specificatun 3.6. A.1 and the average daily gross activity release rate increased by 50I over the previous full operating day, the cartridges shall be analyzed to determine the release rate increase for iocines and particulates.

9 An isotopic analysis of iodines and particulate radionuclides shall be performed at least quarterly,

10. The stack gas radiation monitoring channels shall be checked daily, tested 95005617 4.6-1

monthly, and c:.liorated every 1. months.

B. Licuid 'r aste Effluer.ts

1. Station records shall be maintained of the radice:tive concentration and volute b: fore dilution of each batch of liquid effluent relecsed and of the avern7,e dilution flow and length of time over which each discharge occurred.

2. A m;.r,tnly proportional composite of samples of all batches discharged during the month shall be cnalynd for gross alpha and beta tritiun and Sr-90.

3 D.:ch batch of liquid efflwnt releesed shall be cnalyzed for gross alpha, betc and ga~ma activity and tne results recorded.

4 N %dion:tivity in liquid uastes shall be continuously ":enitored during release. If the e f fl uent rsdiation monitor on a batch release line is inopertble two independent sL .ples shall be taken nnd analyzed and two plant perr onnel shell indep'ndently cheth vclving prior to the release.

5. ~he liquid rciwaste effluent monitoring channel shall be checked daily, testo nonthly, nnJ calibrated every 3 months.

• A proportional composite is one in which the quantity of liquid added to the ecmposi+^ is proportioned to the quantity of liquid in caen batch that was rd e R.

C. n alcriccl Environnntal '<onitorinr Pro: ram

1. T: rouc1:cical environmental monitoring progrm shall be conducted as specu icJ in h ble 4.C-1,

2. .lith the -diclo;in1 environmental monitoring program not being conducted as qsifis in ' cle 4.0-1, prepare and submit to the Comission, in the /.nnual Rcalc1:.cien1 Operating Toport, a description of the recsons for not conducting the 1 'r m

• rr vired and the plans for preventing a recurrener . (Deviations are per".ittee f rom the required sampling schedule if specimens ar: unobtainable dw to mzardous conditions, seasonal unnvailability, or to malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling p riod).

3 '.lith the level of reiioactivity in an environmental samping mediut at one or more of thc lo:ations specified in Tab 1c 4.6-1 exceeding the limits of Tcble 6.9-1 when averaged over any calendar quarter prepare and submit to the Comission within 30 days from the end of the affected calendar quarter, a Specitl Report which includes an evaluation of any release conditions, environmentsl factors, er other aspects which caused the limits of Table 6.9-1 to be exceeded. This report is not required if the measured level of radioactivity wn not the result of plant effluents; however, in such an event, the condition shcIl be reported and described in the Annual Radiological Environmental Operating hepart.

4. bith broM lerf vegetation sar.ples unavailtble, prepare and suttnit to the Commission within 30 ctys, pursuant to Specification 6.9 3, a special Report 4.6-2 95005H8

which identifies locations for obtaining replacement samples.

5. Th'e results of analyses performed on the radiological environmental n.onitoring samples shall be samarized in the Annual Radiological Environmental Cperating heport, pursuant to Spacification 6.9.3

6. A land use census shc11 be conducted at least once Mr 12 months between the dates of June 1 and October 1, by door-to-door survey, serial survey, or by consulting local agriculture tuthorities and shall identify the location of the nearest residence and the nearest garden of greater than 500 square feet producing broad leef vegetation in each of the 16 meteorological sectors within t distance of five miles. (For elevated relecses as defincd in Regulatory Guide 1.111, March 1976. 'Ihe 1cnd use census shall also identify the locations of all gardens of greater than 500 square feet producing fresh leafy veget&bles in each of the 16 mcteorological sectors within c distance of three miles.) Ercod leaf vcgetntion sampling may be performed at the boundary in the direction sector with the htchest X/O i.) Ideu of the garden census.

7 With a led use census identifyirg a location (s) which yields a ecloulated dosn er dose commitment greater then values currently being calculated in Op;cifianton 3.6.A.4, preptre and submit to the Commission within 30 dr.ys, puraucmt to tpecification 6.9.3, o Special Report which identifies the new location ( s) .

.in - 19 use eencur identifying n loention(s) whier yields e calcoleted are w dose u om.i tm en t (vir. the same cxposure pathway) crester than r.t a 1catn- fron .3!ch s:mples nrc currently being obtained in accordcce with Ep;cification h.6.C.1, prepare and submit to the comission within 30 days ,

purtant to ipecifi er.ti on G . 9. 3, n Special Report which identifies the new locition. Inc new location sht.11 be added to the radiologicc1 new environmentc1 monitoring progrcm within 30 days. The sampling location having the lowest eticu bted dos; or dose commitment (v.a the same exposure pathway) may be dclctd from this monitorin; program after October 31 of the year in which this I r.n 1 z census was conju:ted,

o. Tw results of the land use census shall be included in the Annuai ladiolo ical Environmentcl Cperating Raport.

D. A sample of reactor coolant shall be analyzed at least every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to dctermine total radioactive iodine content.

F. The op:rnbility of systems installed for the treatment of liquid wastes shall be verified a; least once per quarter if the system is in use during the quarter to process water released to the environment. In systems having redundant equipment the equirnent in service shc11 be checked.

G. Die quantity of radioactive liquid contained in the total of all outside redwaste storage tanks shall be determined to be within the limit of Specification 3.6.C by analyzing a representative sample of the tank's contents at least once Mr 7 days when radioactive liquids are being added to the tank.

H. Die concentation of hydrogen in the augmented offgas treatment system shall be determined to be within the limits of Specification 3.6.F by continuously monitoring the waste cases in the cugmenttd offgas treatment system with the e

95005 H 9 4.6-3

hydrogen monitors, except as permitted in Specification 3.6.F.O I. Inc gross radioactivity rate of noble gases frcm the mein condenser air ejector shall bc determined to be within the limits of Specification 3 0.G at the following frequencies by perfoming an isotopic analyss of a representetive sample of gases taken at the discharge (prior to dilution and/or dischargd of the mt.in condenser air ejector:

1. At least once par 31 days.

2. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following an increase, as indicated by the Condenser Air Ejector Ioble Gas Activity Monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POVER level, in the nominal steady state fission gas release from the nuclear steam supply system.

BASES: The bases for the surveillance requirements of this section are to ensure the implementntion of Technical Specification 3.6, RADIOACTIVE EFFLUENTS.

The specific bascs for each requirement of this section is rJeta13 9') In Vect10n

3. 5.

t 95005320 4.6-4

N TAnf R 4.6-1 e LD RADIGII)GICAL UNIIOtt1 ENTAL FOllPIORItG PROGIW4 O O

LD Dcposure thunber Of SanplityJ and Type and Froguency &

and/or sanple Sanples Collection FroIuency of Analysis

1. ATRDORtE

a. Radiciodine and S Continuous operation of sanpler with Radiciodine canister. Analyze Particulates sanple collection as requirod lif at least once per 15 days for dust loadity, but at least once per I-131.

15 days.

Particulate sartple . Analyze for gross beta radioactivity >24 hours following filter chenge. -Perfona ganina isotopic azulysis on each sanple wlen gross beta activity is

> 10 tines the nean of control 4

sanple. Perfonn gannu isotopic analysis on canposite (by location) saiple at least once ter 92 days.

if an isotopic analysis is performed on each sample ath 92 day composite is not required.

2. DIRECT RADIATION 18 At least once per 92 days. Gamma dose by T1.D. At least (Read-out frequencies are determined once per 92 days.

by type of dosimeters selected).

-f

N

'rADIE 4. 6 . (Continued) u, RADIOliEICAL UNIIGHam(L f10tJI'IORItG PIOGI(Mt c, CD Exposure Pathway flunber of Sanplirvj ard Type ard Frequency Ln ard/or Sanple Sanples Collection Frequ2ncf of Arnlysis D

3. WNIERDatrE

a. Surface 5 Sanple collectal at least every Gannu isotopic arulysis of each 31 days, sample. Tritium analysis sanple at least once per 92 days.

b. Rain Water 5 At least orm per 92 days. Ganna isotopic ard tritiun analyses of each sanple

c. Well Water 5 Sanple collectal at least every I-131 arulysis of each sanple 31 days. and Gross beta and gannu isottpic

, azulysis of each sanple. Tritiun arulysis sanple at least oire per 92 days.

d. Silt arxl Sedinent 5 At least orm ter 184 days. Ganna isotopic arulysis of each sanple

• Corposite sanples shall be collectal ly mllectirvj an aliquot at intervals rot exceeding 2 leurs.

- e e

-7

a .. u- . . .. .. .

tn TABIE 4.6-1 (Contintn!) N

'n LD RADIOIOGICAL BT/1ROtME2 TIE for1110RIIG PIOGRM1 CD Exposure Pathway Number of SanplityJ arr3 Type arxl Frequency and/or Sanple Sanples Collection Frequeref of Arnlysis &

4. ItGESTICri

a. FirA and Inver- 3 One sanple in season, or at least Ganna isot@ic analysis on edible tebrates once tur 184 days if rudseasorul. portions.

Oru sanple of each of tie followinJ species:

1. C1.ims

b. Food Products 3 At tine of turvest. One sanple of Gannu isotwic arulysis on edible eacIn of tie followinj classes of portion.

food prcdtets:

1. Various Food Products in Season S At Line of turvest. One sanple 1-131 analysis. E of bnxid leaf vexjetation.

e 9

a

Cause reduction of degree of redundancy provided in reactor prottetion systems

,or engineered safety feature syster.s.

4 Abnormal degradation of systems other than those specified in Item 2.a(3) above designed to contain radioactive material resulting from the fission process.

NOTE: Sealed sources or calibration sources are not included under this ites Leckage of vtive packing or gaskets within the limits for identified leak ge set forth in technieni specifications need not be reported under this item.

5. An unplanned offsite release of 1) more than 1 curie of radica:tive material in liquid ef flents, 2) more than 150 curies of ncble gas in gaseous effluents, or 3) more th:.n 0.05 cu-ies of radiciodine in ;csecus effluents. ~nic report of an unplanntc offsite release of radioactive mr.teriti shell include the followins ir.f ormstion :

1. description of the event and equipnent inv0lved.

2. Ca use( s) for the unplanned release.

3 Actions tuken to prevent recurrence.

4 conr.equ.ncer, of the unp1r.nned release.

6. "c sure icvels of m.diocctivity in An environmentel sampling medium c". ermine te t xceed the reporting leve) values of Table C.0-1 when averaged ovir any colendar qucrter stmpling perion. '.l hen more th;n one of the rrdienu:litr in Table 6.9.1 nre detected in tne supling medium, this report d

sh:11 by s ubr.i t te if:

concentrction (1) + c:ncentrction (2) 4..>1.0 Limit Level (1) Lurat h v el (2) inc. radionu:1; des other than those in Table 6. 0-1 are detected and cre the rc; ult of pl cnt e f fl ue n ts , this report s h r.' 1 b 2 surr.itten if the potential cnnual dose tc an individual is equal to or gretter than the calender year li".its of specifications 3.6.A. 3 6,B and 3.0.E. nis report is not required if the measured level of radioactivity was not the result of plant effluents; however , in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

6.9.3 Jniqu

Reporting R quirer.ents Special reports shall b: submitted to the Director of Regulatory Operations Regi>3nl Office within the time period specified fer each report. These reports shall be submitted coverning the activities identified below pursuant to the requirements of the applictble reference specification.

a. Materials Radiation Surveillance Specimen Reports (4.3A)

b. Integrated Primary Containment Leakage Rate Tes:S (4.5)

c. Semiannual Radiocctive Effluent Release Report 95005324 6-23

1. . he utint radioactive effluent release re;crts covering the operating cf the unit during the previous 5 months of oparation shall te subt.itted within 63 days af ter January 1 and July 1 of each year.

2. The radioactive effluent release reports shall include a sar,ary of the quatities of radioactive liquid e a gescous eff1mnts and solid waste released frc~' the unit as outlined in Feyulatory Guide 1.21, "Feasuring, Evaluating, and Re;crting F.3dioactivity in folid Kastes and *-eleases of Radioactive Materials in Liquid and Casnous Effluents from Light-Water Cooled I:uclear Power Plants", with ditt smarized on a quarterly basis fo11 ewing the format of Appendix B thereof.

The radiocctive ef fluent release reports sh011 include a summary of the

~.eteorolog ic t ] conditions concurrent with the release of gaseous effluens during etc quarter as outlined in Regulatory cuide 1.21, with data stm.arized on c ge>rttrly basis following the format of Appandix P thereof.

Tre radiotetive efflucnt releas" reports shc11 include the following information f:r :.11 unp1tnned releases to unrestrictef : roos of rLdioactive materials in gr.sraus t nd liquia effluents:

a. a description of th; event and equipment inv ol v ed .

L. Lase:s) f:r the unp1Lnned relanse.

c. l.*' M DT.s 1 : Nr to pre vent recurrenre,

d. Consequta:cs of th? unplanned release.

In. rLJioactiv( ( ffl uent release reports shall include an assessmer.t of rPdiation doses frur, th0 roiioactive liquid and gaseous offluents releasec from the unit durin each c .lenacr quarter as outlined in Regulatory Guide 1.21. In r'11 tion, the unrestricted cret boundary .m:itr.n noble ;t s cam.a nir and bett air mses san 11 te (vnlu. ted. The meteorological con 11tions concurrent with t he re' res of effluents snall be used for determining the caseous pt.th* ay doses,

d.  ::.nprab1< fire protection equipment (3. ".2)

e. Core Spray Sparger Inservice Inspection (Table 4 31-9)

Prior to startup of each cycle, a special report presenting the results of t.he inservice inspection of the Core Spray Spargers during coch refueling outree shall be submitted to the Commission for review.

f. Annaul Mediolor,ical Environmental Operatine Report

1. Routine radiologic 61 environmental operating reports covering the operation of the unit cu-ing the previous calendar year shall be submitted prior to '%y 1 of eatn year.

2. Tne enr.uM rndiological environmental opercting reports sht11 include summaries, ir.terpretations , and statisticL1 evtlustion of the report period ,

oparntional centrols (cs oppropriate), and previous environmental surveillince reports and an assessment of the observed impacts of the plant op3raticn on the 95005325 6-24

environment. he reports shall also include the results of the 1rnd use ernsus required by Specification 3 6.D if hermful effects or evidence of irreversible dar,acc tre dete:ted by the monitoring, the rep;rt shall provide an Enclysis of the problem and a planned course of cation to alleviate the problem.

Inc nnual radiological environmentEl opertting reports shcll i r.:l ud e d summarized and tabulated results in the format of T:ble 6.9-2 of all radiological environmental samples tsken du-in; the rep;rt period. In the event that some results cre not tvailsble for inclusion with the report, the report sh::ll be submitted noting and expleining the reasons for the missing results.

The missing data shall be sub-itted as soon as possible in a. sup;'le .entary rep;rt .

The reports shall also include the following: " stmary description of the radiclogical environmenttl "onitoring pr02rt m inclu11rm stmpling .cthods for eDeh 3 ample type, si o ani physical charseteristics of each s=ple type, ser.ple pr:p;rr tion mctbods, EnElytical methods, and me:suring eculpoent used; a map of Lll sinpling locations keyed to a trble giving distances an: directi:ns fr:r. the rc te:cr; the resu' t of IEnd use censuses required by the Specification 4.C.C.

95005126 6-25

CN TAluE 6.9-1 g O

_ItE10lfrItG ILVFIS FOlt ItADIGACPIVrlY GMCF2THIATIOtG 113 UNII0tN11TTAI, SN4PIJ23 o u7 Ik4ottinJ IcVels Water Airbonym Partiglate Invertebrates Ebod Pnxiucts Analysis (pCi/1) or Gases (ICi/m ) ([Ci/Kg, wt) (ICi/K(J, wl)

!!-3 3x10 3 4 Mi-54 1 x 10 3 x 10 Eb-59 4 x 10 1 x 10 0>-58 1 x 10 3 x 10 2 4 03-60 3 x 10 1 x 10 .

.o 2 4 h45 3 x 10 2 x 10 i 2

Zr-Ib-95 4 x 10 I-131 2 0.9 1 x 10 Cs-134 30 10 1 x 10 1 x 10 Cs-137 50 20 2 x 10 2 x 10 Ba-Ia-140 2 x 10 9

O a

TAntE 6.9-2 e

12#11(ittt2TIRL IttO!O1161CP.1, it011tXtira; 11tCIVN 9ttEf4 IOrras of Focility Ekdet th. m '

N PqortissJI Win! , #

Iccistitui of Facility (Ommty, State) C O-O Incatican widt liig!r.st tender of m Tyge aral Im er Limit. Omtrol Incatisms 143utrMitE &

All Irulicator IAcatlosus Assasil n'an nulitse of Patimaay 1 bid landme of tasse hn thwi (OL1su2am; Sasipled of hlyses Detection than msyp (flDO merp Distasnoe & Raup intit of R:amisaierat l'erformux! tsli(ct toen

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