ML20138R213

Amend 106 to License DPR-21,deleting App B in Entirety & Providing New Tech Spec Sections to Define Limiting Conditions for Operation & Surveillance Requirements for Radioactive Liquid

ML20138R213
Person / Time
Site:	Millstone
Issue date:	10/01/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20136G192	List: ML20136G188 ML20138R188 ML20138R213 ML20138R226
References
NUDOCS 8511180493
Download: ML20138R213 (45)

Text

{{#Wiki_filter:/ \\;. UNITED STATES 8 NUCLEAR REGULATORY COMMISSION o h s WASHINGTON, D. C. 20655 %,...../ THE CONNECTICUT LIGHT AND POWER COMPANY WESTERN MASSACHUSETTS ELECTRIC COMPANY AND i NORTHEAST NUCLEAR ENERGY COMPANY MILLST0hE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NO. 50-245 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.106 License No. DPR-21 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by the Connecticut Light and Power Company, Western Massachusetts Electric Company, and Northeast Nuclear Energy Company, (the licer. sees) dated May 29, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied. PDR

-2, 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendnent and Paragraph 2.C.(P) of Provisional Operating License No. DPR-21 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 106, are hereby incorporated in the license. The Northeast Nuclear Energy Company shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective on January 1, 1986. FOR THE NUCLEAR REGULATO Y COMMISSION w John. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing

Attachment:

Chanoes to License No. DPR-21 and to the Technical Specifications Date of Issuance: October 1,1985 l l l

ATTACHMENT TO LICENSE AMENDMENT NO.106 PROVISI0t!AL OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 1. Revise License DPR-21 by removing page 4 and inserting the enclosed page 4. 2. Replace the following pages of the Appendix A Technical Sne-ifications with the enclosed pages as indicated. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change. Overleaf pages have been provided to maintain document completeness. REMOVE INSERT iii 111 iv iv 1-8 1-9 3/4 6-19 3/4 6-19 4 3/4 7-12a 3/4 7-12a 3/4 7-12b 3/4 7-12b 3/4 8-1 3/4 8-1 3/4 8-2 3/4 8-2 3/4 8-3 3/4 8-3 3/4 8-4 3/4 8-4 3/4 8-5 3/4 8-5 3/4 8-6 3/4 8-6 3/4 8-7 3/4 8-8 3/4 8-9 l 3/4 8-10 3/4 8-11 3/4 8-12 3/4 8-13 3/4 8-14 3/4 8-15 3/4 8-16 3/4 8-17 3/4 8-18 3/4 8-19 3/4 8-20 B3/4 6-12 P3/A 6-12 B3/4 8-1 B3/4 8-1 83/4 8-2 B3/4 8-2 B3/4 8-3 83/4 8-4 B3/4 8-5 6-14a 6-16 6-16 6-17 6-17 6-21 6-21 6-21a 6-26 3. Delete Appendix B in its entirety. I

1 4.. i (1) Maximum Power Level NNECO is authorized to operate the facility at stea$ state ' reactor core power levels not in excess of 2011 megawatts thermal. (2) Technical Specifications The Technical Specifications contained in Appendix-A as revised through Amendment No.106are hereby incorporated in this amended licuse. NNEC0 shall operate the facility in accordance with the Technical Specifications. ~ (3) Re> orts kk ECO shall make certain reports in accordance with requirements of the Technical Specifications. 1 l (4) Operating Records kNECO shall keep facility operating records in accordance with the requirements of the Technical Specifications. t (S) (Previously Paragraph 3.E. " Restriction," relating to 1 j Cycle 4, issued by License Amendment No. 26, April 2,1976 -- DELETED) (6) Fire Protection kNECO may proceed with and is required to couplete the modifications identified in Paragraphs 3.1.1 through j _~ 3.1.18 of the NRC's Fire Protection Safety Evaluation (SE), dated September 26, 1978 and Supplement No. I to the SE dated November 19, 1980 for the facility. These modifications j will be completed prior to returning to power operation following the 1980 refueling outage. NHECO is required to implement the administrative controls identified in Section 6 of the SE. The aministrative controls shall be in effect by December 31, 1978. 1 l (7) Physical Protection NNECO shall fully. implement and maintain in effect all provisions of the following Cosmission-approved documents, including ameneents and changes made pursuant to the authority of 10 CFR 50.54(p). These approved documents con-4 sist of information which is required to be protected from public disclosure pursuant to 10 CFR 73.21: i 4 (a) " Millstone Nuclear Power Station, Units No.1 and 2 16, 1978 as Physical Security Plan," dated June 20,1979 (orihinally l revised August 4,1978 and February approved by License Amendment No. 59, February 23,1979). l Amendment No.106 m..._

Surveillance Pane No. 2 J r-E, C. Secondary Centainment...................................C.................... 3/4 7-13 d D. Primary Centainment Isolation Valves ....................D.................... 3/4 7-14 2 m l e 3.8 RADISACftVE MATERIALS 4.8 c-5 A. Radteactive Liquid Effluent i Instrumentation............................... A..................... 3/4 3-1 ~ 3. Radiometive Geseous Efflueet Instrumentaties............................... B..................... 3/4 S-4 C. Rediedetive Ligold Et fleeste.................. C..................... 3/4 8-12 3. Radioactive Goosess Effluents.......,......... D..................... 3/4 8 -14 ) 3.9 ABRILIARY EI2CTRICAL SYSTEMS 4.9 - 3/4 9-I I 3.10 REFWELING 4.10 A. Refuelles Interlocks....................................A.................... 3/4 10-1 l B. Core Monitoring.........................................B.................... 3/4 10-2 l ^ l C. Feet Storage Poel Water Invel...........................C.................... 3/4 10-2 l 3. Crane Operability.......................................D.................... 3/4 10-2 1 E. Crane Travel - Interlocks and Suitches..................E.................... 3/4 10-2 t i 3.11 REACTOR FM L ASSEfmLY 4.11 1 i j A. Average Planar Linear Neat Ceneraties Rate..............A.................... 3/4 11-1 B. Linear Best Generaties Rate.............................B.................... 3/4 11-8 C. Misiano Critical Power Ratie............................C.................... 3/4 11-9 [ 3.12 FIM PROTECTION SYSTEMS 3/4 12-1 i = 1 CL 3 3.13 ISBERTICE INSPECTION 4.13 3/4 y -1 j = ft 3.14 PEANT STSftNB 4.14 3/4 14-1 l 2 i j O I 5.9 SESIGN TEATINtES .1 l W = l 15En ?

• a

? om

Pago Ilo. 3 ARNtWISTRATITE G1Hfmot.5 r-r-$ 6.1 heepomelbility...................................e.............. 6-1 9 6.2 Organisatten.......................-............................ 6-1 6.3 Facility Staff gene 11ticattene................................... 6-1 l e c 6.4 Trafalog............................................................ 5-5 z 6.5 sevIew and AodIt.................................................... 65 Z 6.6 Repor table Occurrence Ac t ica........................................ 6-15 6.7 sa f e t y L Im i t V I s l a t l en.............................................. 5-15 6.9 Procedures.......................................................... 6-16 6.9 Repor t i ng Rege l rements.............................................. 6-17 6.14 secord Retentlen......................................:............. 6-22 6.11 Radiatlen Protectlen Program........................................ 6-23 1 6.12 01191: RadiatIan Area................................................. 6-23 6.13 Sys tems I n tegr.i ty.................................................. ' 6-25 6.14 lodine Monitoring.................................................. 6-25 ) 6.15 Radiological Effluent Monitoring and 1 Offsite Dose Calculation Manua1.................................. 6-26 7 6.16 Radioactive Waste Treatment Systems................................ 6-26 l i i 1

3 Q.

= u 2 O. Its N h Ica its e o m

N I, '.jh ) jl ~ I Perforsmace of a servel11ance regelrement within the specified time laterval shall cosistitete cog 11ance witli t sperability requirements for a Limiting Condition for Operation. 5erveillance heguirements shall be appilcable during the OPCRAil0NAl. MDOCS associated *with Limiting Condittens for Operation. Serveillance need not be performed if the system or component to be tested is not required to he operational as spec.lfled by the Limiting Conditions for Operation. However, the required serveillance ~. shall be performed prior to returning the compownt to an operational status as regelred by the limiting. i canditions for operatten. ~ AA. Transtilen teillag Tr'ansttlen belling means the belling regloe betw'een nucleate and flim betilng. Transtilon bolling is the l regime in which both necleate and film belling occur intermittently with neither type being completely stable. i

35. Emergency Power Sources f

taergency power secrees the on-site gas turbine generator and diesel generator. ~ CC. St a ; M Test tests A. Staggered Test Basis shall consist of: a) A test schedule for a systems, subsystems, trains or other designated components obtained t by dividing the'specified' test interval into n equal subintervals, and 1 ~ b) The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval. [ i De. anst Instv& Leser 1-131 i DOSERoutTAthWT1-13lshallbethatconcentrationof1-131(act/ gram)whichalonewould pro'dece the some thyroid d'oe as the quantity and isotopic misture' of I-131, 1-132, 1-133, { I-834 and 1-135 octeetly present. The thyroid dose conversion factors used for this calculation.. j nhall be t$ose listed on Table E-7 of Regulatory cuide 1.109 Revision 1. EE." i-Avr.Ract Dis 1NTECRATinN EnERCY [ E shall'be the average sua ef.the.heta, sed gamme energi~es per disintegration (in MEV) for inntepen. other then ledines,,with half. lives greater than 15 minutes, making up at.least 95% of the total ase-ledine activity'in the codiset. l l-7 j .A=cadment no. H. di gy ,l I i _ - _... - _ _ _ _ -. _.. = - _ _-.m-.__,.

. = _. - ) DEFWatTMNts . s: i e t ' * ~ . 0; F.F. RADIOACTIVE WASTE TREATMENT SYSTEMS ~E i i E RADIOACTIVE WASTE TREATMENT SYSTEMS are those liquid, gaseous, and solid waste systems which are required to maintain l control over r=d==ctive materials in order to meet the LCO's set forth in the Specifications. [ i e G.G. RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) l ~ A RADIOLOGICAL EFFLUENT MONITORING MANUAL shall be a manual containing the site and environmental sampling and f analysis progranes for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides 1 l which lead to the higliest potential radiation exposures to individuals from station operation. An OFFSITE DOSE CALCULATION MANUAL shall be a meanual containing the methodology and parameters to be used in the calculation of offsite doses due to i radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip j setpoints. Requirements of the REMOOCM are provided in Specification 615 I H.H. PURGE - PURGW8G i j PURGE OR PURGING is the controlled process of discharging air or gas from a confinem6nt to maintain temperature, pressure, f i g, husnieEty, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the i continement. IJ VENT 94G I VENTWIG is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition,in such a manner that rgh..a..t air or gas is not provided or required during venting. i Vent, used in systens names, does not imply a VENTING process. 1 JJ J. IMllER(5)OF THE PUBUC i I g MEnanFR(5) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not i inch c ;t,u-of the utility,its contractors or its vendors. Also escluded from this category are persons who enter the site to i 3 ) 'g service equipment or to analse deliveries. This category does include persons who use portions of the site. for recreational, occupational or p purp was not associated with the plant. s -f The term "REAL MEMBER OF TIE PUBLIC" means an individual who is exposed to existing dose pathways at one particular location. .f [ 42 ] i I i i l

ib sm4G g p K.K. 55TE BOUNDARY O The SITE BOUNDARY shall be t;mt line beyond which the land is not owned, leased or otherwise controlled by the licensee. S r L.L. SOURCE CHECK E A SOURCE CNECK shall be the qualitative assemenient of chasmet response when the charmet sensor is esposed to redation. 4 ~ An IJNItESTRICTED AREA shall be any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of r_= ? -_ of individuals fresa esposure to radiation and radioactive materials or any area within the site boundary used n1;-:' ; institutional and/or recreational purposes. =' for r==Ms=elet quarters or Industrial, -1_ W i l i 3 i.f M 8 o

l Llulits ta stTim f5 GPERATIN. SWWEILLARK REqWIADIENf d. N ata Osmeserettaers J.. f==d=== ate testeerettaers 3 r ( i-G

1.. hogenerettee of a condensate desteerellates 1.

The pertest of the remeistag fee }g capacity of the reste reaches a statsee shall be calcolated and legged: reste change shell accer hetsre the onesed , escheese capacity of the antes restes. m sales of 30 pseeds as chlerlee fees. 'le. [ e. Hook 1r uhes the lofloset eso. t i5 2. Antes restes to the condensate desteeretta-esctivity is heteese 0.055 and l t systes shall have a eletese salt-8.3ad e/ent Itates cepecity of e.75 milliewtseleets t per et19110ter to the met chlerfde fans. h. Betty seen the lofloset ces. j Antes restos ehleh es met'have a cepecity dactivity is eges) to er greater i i et e.75 meiste ptueleste per a011 titter than 0.3 ashe/as. l 1 m011 he repleted se e ese meste as well the { cettee reste ettch esemples the seen bed. 2. Antes restes to all condensate. esoleoretsaar charges small be 3. At least see===d====*= douteerettaer. - analyzed quarterly for salt.spItttles

• tefloset sendestivity testrument shall he cagacity,.

k W ** ' ~u E. h4==sent - -~ seeman yese 4. Mosesor e desteere19aer to en-lies, the ? esadettivity of either Ste effleest er the G ter M W shall be At least sees deries each operettas eyete emetteesesty meettered. verify==*=== tic securies and feelettee of the m acet A incessi pesy, 5. Fles ' rete ae#sr letogrottag flew testro-seatetten shell be aparable and recorded for each desteerettaar. 1 E. r - s d condenser seeman puse -f,. 1.' me m n h secessipesy ~e o c.y.h e., h. e._.= a e.d g moeured en a staaet of hidr rettemetivity f " '-___ the este steen line tooletfes ~ g selves are spee. i M ( M 1 a l I i

~ LMTles CEustTIS fER OPERATIGE,- - __ L $NRVEIttANCE REQUIRGIENT j 5. Stase r Ds 1 H e hest System { ~ 3 S. Stan &y Ces Treeteent Systes l 4 j F 1. Estopt as spectffed le Specificettent 1. At least once per operettag cycle. the l { 3.7J.3 and 3.7.B.4 beles, both circutts following condttiens shall be 9~ of the stener gas treatment system and the demonstrated: { 4 l 7 emergency power searces regelred for opera-ties of such circelts shall be operable at a. pressere drop screts the es efned c3 all times when secondary contalsment EPA filters and charcoal edsorber ~ fotogrity is regelred. a bents is less then 7 inches of l 2. a. D e results of' the fe-place cold enter at the systes design flee U ) BOP and helegensted hydrocarbon rete (liceSCfM). tests, et ofnimes flew rete of' 50s.3CRI. en IEEPA. ffiters and b. Inlet heeter setput' is et leest 5tu. chercoal adsorber banks shall show > 995 30P removal and > pgs hele-c. Air distribetten is entfore with Mted lydrocortes reisevel.

f. 29E of the averaged flow per

( unit across the NEPA filters and chercosi adsorbers. t' b. He.reselts of t"_: M=, cartes saspie analysts shall shou o get 2.

a. ' The tests and sample snelysts of

? i eedlesettee sathyl ledede removal at y a selecity wittle fez et acteel system Spectficetten 3.7.8.2 shell be i design. 0.5 to 1.5 me M inlet methyl perfeemed inttla11y and at least leefde concestretten. 995 a.N. and once per year for standby service er after no hears of system opere. l

• 19e*F.

tien and following pelating, fire l ~ c. fene shell be shoue to aperate withfe er chemical release in any wenti-e ISE design flew. latten rene connunicating with g the system that could contentnote ~ the leEPA filters er charcoal ( adsorbers. R y b. Cold per testing sliell be per- ~ g I formed after each cenplete or E partial replacement of the NEPA filter bank or after any strec- ~ teral metatenance en the systen housing. i i

LIMITING 6 FW M 3 .l I SERTtfRANK AEqW19t3ENt 1 From and cfter the dote that ese etreef t of the staae get treelmeet systes is me Helegenoted hydrocartes testfag ( r t. or fasad to be temperable:for any ressen,d shell be perfeemed after sect e 1 3 reacter operetten and feel handleep is complete er portial replacement I p-poselssible only darlag the succeeefag of the cherceal adsorter beak er l t*, seven days unless such efecult is scener efter any structural meistenance g mode operable. provided that darlag such se the system heeslag, i seven days all active compensets of the ether staany ges treegment eleceit shall E . te operable. 4 ( Berleg fhet hoodiles both efetetts of the stamar ses treatneet system siell ne operable, essert as stated le peregraph 3.FJ.3. le additles. there shall be ~ i operable etther (e) tuo seerees of offsite I 345ET)(and one emergency po. GNU and one poner tes 385Et er one 27 { ner searce, or (b) ene soorte of offstte poser 305KV or FF.$ty) and tuo emergsary pesar e(serces to i eperste taugmoests reptred to peregrept i ~ y 3.7.s.3. t y 5. If the atese comoet be met. ~ h ~ shell be lettleted tamedle to estab I e fish the esmettless 19sted le 3.F.C.la through 4 and es ylfante shall be esp. l Pieted elete M hears thergefter. i I 6. Prtemey W M1 he purged i ( theems the standby see treatment speese se att tasse itse pesamey i h - 1stegrity is required. ~ = t i 4 3 E M e l 3 l 8 l

i LNWTim ( M TIM pm M Tim E-SKILLWCE K0utRDENT 1 -{e 18 RADIO 4 CME RAATERSALS 4.LA RADIOACTIVE LIQUID EFFLUENT MSTRUMENTATION ll LLA ME M EFFLM I DE5TRUeENTAssON 4.LA.I Eade radoactive ligdd efflesent seenitoring instrusiesitation e channel shaN be desmonstrated OPERABLE by periersnance g 18.A.I The N ligdd einuent smanitoring of the INSTRUAENT CHECK, pt5TRUMENT CALBRA-W =as== h shevse in Tame 18-l shen be TION, and INSTRUAENT FtmCTIONAL TEST operations at OPERASLE witte appikmMe alarse/ trip setpeises set to enmare the fregsencies shown in Tame 4.5-1. that the Nashe of SpecNicatissa 3.8.C.I are not encoeded. The o seepsises shsII he deterunined in accordnice witte sinethods and paraenseess as descrthed in the OOCM. Aesthahtity: As sheenin Tame 18-l. l Aceses i i 1. he die event a Ibadting condelsse for aparation andfar 2* h action regdr====* cannot he satisfied, this shalt not regdre aseit sheedesse er present a clienge in operathenal smedes. 2. When a radeactive ligdd effluent - smanitoring i Wh n*====a setpoint less censarvethe then required by stie above spedfication, sitteest detsy sempend stie c.a=== ef radmactive liged esmeents nianitored by the assected channes, er decsare the n*====a inoperaMe, er climage the setpoint so it is acceptaMy conservative. 1 Wish the sesaker et diennels less than the seinisnessi g-ch==asan opereMe regdresnent, tehe stie ACTION shown is TeMe 111. Emert best efforts to restore the 4~- InsparaMe beenlear to CPERABLE states witInin 30 days y med, it==&are===8ed, egaaisi he stie nest Sensi-annesol Ellbuent Report weiy the inoperaMIity was not correcsed i- )g he a tienely . Reteeses need not he eersnineted 4 - aster 30 sys pr.asded the specisied actamm are C continised. R 1 1 )

I TABLE 3.8-1 RADI0 ACTIVE LTOUID EFFLUENT MONITORING Alarm Minimum # 5etpoints Instrument Ooerable Recuired Applicability Action 1. Gross Radioactivity Monitors Providing Automatic Termination of Release

a. Liquid Radwaste Yes Effluent Line A

2. Gross Radioactivity Monitors Not Providing Automatic Termination of Release a. Service Water Yes i Effluent Line B 3. Flow Rate Measurement Devices a. Liquid Radwaste 1 No C b. Dilution Water No Flow NA - At all times - which means that channels be OPERABLE an continuous, uninterrupted basis, except that outages are permitted within the time frame of the specified ACTION statement, for the purpos,e of maintenance and performance of required tests, checks and calibrations. Dilution water flow is determined by the use of condenser cooling water the quarry at the time of the release are included I reviewed for purposes of determining flows. ) l NA. Not Applicable. f l l l i 1 MILLSTONE - UNIT 1 I 3/4 8-2 i Amendment No.106 f

TABLE 3.8-1 (Continued) ACTIONS STATEMENTS Action A i ~ With the number of channels OPERABLE less than required by the' Minimum Channels OPERABLE requirement, effluent releases may continue provided that best efforts are made to repair the instrument and that prior to initiating a release: 1. At least two independent aamples of the tank are analyzed in accordance with Specification 4.8.C.1.1 and; i j 2. The original release rate amiculations and discharge valving are independently verified by a second individual Action B With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases via this pathway may continue provided that best efforts are made to repair the instrumentation and that once per 12 hours grab samples are collected and enalyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 3X10-7 uCl/gm. Action C l With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours during actual releases. Pump performance eurves may be used to estimate flow. s i l ) 5 i MILL 5 TONE - UNIT 1 3/4 8-3 Amendment No.106 n

TABLE 4J-l I RADI0 ACTIVE LIQUlO EFFLUENT. MONITORING IN5TRUMENTATlON 5URVEILLANCE REQUIREMENTS hstrument Instrument Instrument Functional Source Instrument Check Calibration Test Check 1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release a. Liquid Radwaste D(1) R(2) Q(3) P Effluent Line 2. Gross Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a. Service Water D(1) R(2) Q(3) M Effluent Line 3. Flow Rate Measurement Devices a. Liquid Radwaste D(1) R Q(3) NA Effluent Line b. Dilution Water Flow D(4) NA NA NA 8 D = Daily M = Monthly ~ P = Prior to each batch release R = Once every 18 months Q = Once every 3 months . NA = Not Applicable MILLSTONE - UNIT 1 3f,3.g Amendment No.106

N TABLE 4.8-i (Continued) TABLE NOTATION t (1) Instrument check shall consist of verifying indication of radiation or flow ~ readings during periods of discharge. Instrument check need only be performed daily when discharges are made from this pathway. a (2) Calibration shall include the use of a radioactive solid source, the activity of which can be traced to an NBS source. The radioactive source shall be in a known, reproductible geometry. l (3) The INSTRUMENT FUNCTIONAL TEST shall also demonstrate that control { room alarm annunciation occurs if any of the following conditions exist: i 1. Instrument indicates measured levels above the alarm / trip setpoint'. 2. Instrument indicates a downscale failure or circuit failure. 3. Instrument controls not set in operate mode. Automatie isolation shall also be demonstrated for the liquid 4 radwaste effluent line. .(4) Pump status shall be checked daily. (5) The quarterly functional test for the liquid redwaste flow monitor shall consist only of a comparison of the calculated volumes discharged by using the measured flow rate versus the tank level decrease. This surveillance is not required if no waste was discharged during the quarter. i s I ~ l ~ i Amendment No.106 MILLSTONE - UNIT 1 3/48-5 2 i

i, , IIIRTIM MI] fM WEMTIm ^

5 SWWILLME MORMIST F

4

-M

> 3.8.B r-Radometive Geseous Effluent Monitorint 4.8.B Instruenentation Radiometive Geseous Effluent Instrumentation '3.8.B.1 'Ihe radfoactive i 4.8.B.1 Each radiometive gaseous effluent monitoring gaseous efnuent 'E instrusinentation channels shown in Table 3.5-2 sheH bemonitoring lastrumentation channel shnu be demonstrated OPE ! 'Q OPERABLE with appliemble alarm / trip setpoints set to ensure performenee of the INSTRUMENT CHECK, INSTRUMENT CALIBRA-that this Malts of Specification 3.8.D.1 are not ezeeeded. 'the TSON, and INSTRUMENT FUNCTIONAL TEST' operations at the I setp~oints sheH be determined in accordance with seethods andfrequencies shown in Table 4.8-2. parameters as deseribed in the ODCM. Applieebility: As shown in 'tisbie 3.8-2. Action: 1. In the event of a limiting condition for operation and/or asooeleted action requirement eennot be satisfied, this 3 g shan not require unit shutdown or prevent a ehenge in operational modes, eseept for Table 3.8.2 metion B 4

30 statement for SJAE off-ges nionitor.

i a. With a redlemetive gaeaan= effluent suonitoring j instrussentation channel alarm / trip setpoint less conservative then required by the above Specification, i without delay suspend the release of radiometive gaseous efnuents peonitored by the affected channel, or deelete the channel inoperable, or change the setpoint { so it is acceptably conservative. k b. With the number of channels less then the minimum "jk channels operable w; ' ;.w.ts, take the ACTION j" shown in Table 3.8-2. Esert best efforts to restore the j inoperable monitor to OPERABLE status within 30 days i 'e and, if unmuecessful, explain in the next Semi-annual P Efnuent Report why the inoperability was not corrected in a timely menner. Release need not be i-!R terminated after 30 days provided the specified actions are continued. t j i l l i

i YABIZ 3.8-2 RADf0ACTf7E GASIOUS EFFLUENT MONITORING INSTRUMDITATION Nimimum i Alarm fastrument Operable Setpoints Applicability Action 1. Main Condenser Augmented Ofiges Yreatment Systen Erplosive Gas Bonitor (Tor System Designed to Withstand Effects of a Bydrogen Explosion) (a) Bydrogen Manitor 1 Yes A 2. Condenser Air Ejector Noble Gas Activity Monitor i. (a) SJAE Off-Gas Monitor 2* Yes 3 3. MP1 Main Stack (a) Noble Gas Activity 1 Yes C Noaitor (b) Jedine Sampler 1 No 2 (c) Farticalate Sampler 3 No D (d) Stack Flev Rate Monster 1 No I (e) Sampler Flev Rate .1 Yes E Neatter l l

• - At all times which means that chamaels shall be OPERABLE and la I

service sa a restiavous, mainterrupted basis, except that eutages are permitted, withis the time, frame of the specified action statenest, for the purpose of maintenance and performance of required tests, checks and calibrations.

• • = Buring augmented off-gas treatment system (recsabiner) operation.

I 1 l i l MILLSTONE - UNIT 1 3/4 8-7 Amendment No.106 ---m ,._-wa.- __,,nn,.,,,_,

r TABLE 3.8-2 (Continued) i ACTION STATEMENTS Actiori A With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser ' augmented offgas treatment system may continue provided that best efforts are made to i repair the instrument and that gas samples are collected once per 4 hours and l analyzed for hydrogen within the ensuing 4 hours. Action B i With one monitor inoperable, releases via this pathway may continue provided the inoperable monitor is placed in the tripped position. With both monitors inoperable, releases may continue for up m 72 hours provided the augment system is not bypassed and the main stack monitor is operable, otherwise, be in I at least HOT STANDBY within 12 hours. i Action C j-With the number of channels OPERABLE less than required by the Minimum i.' Channels OPERABLE requirement, effluent releases via this pathway may i continue provided that best efforts are made to repair the instrument and that grab samples are taken once per 12 hours and these samples are analyzed for grou activity within 24 hours. Action D With the number of samplers OPERABLE less than required by the Minimum number OPERABLE requirement, effluent releases via this pathway may i continue provided that best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment for periods of seven (7) days and analyzed for principal gamma emitters with half lives i greater than 8 days within 48 hours after the end of the sampling period. i Action E With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours. MILLSTONE - UNIT 1 i 3/4g.3 Amendment No.106 I r

---

,n,

-,-,,-e-----,,-,,,---.-- m e -- m a - - - -, - -m m-wmmm, a,, -mm s,, v m e e m w- -- _ _,,v_ ,c,,-,w-,-m ,~,,m-e,_ n.,

TABLE 4.8-2 It ADIOACTIVE GASEOUS EFFLUENT MONITORING lb 5TRUMENTATION 5URVEILLANCE REQUIREMENTS ' Instrument. Instrument Instrument Functional Source Instrument Check Calibration Test Check 1. Main Condenser Augmented Off-Gas Treatment System i Explosive Gas Monitor l (a) Hydrogen Monitor D(1) Q(2) M NA 2. Condenser Air Ejector Noble Gas Activity Monitor (a) 53AE Off-Gas Monitor D(3) R(4) Q(5) M 1' 3. MI Main Stack (a) Noble Gas Activity D(3) R(6) Q(7) M Monitor (b) Iodne Sampler W NA NA NA (c) Particulate Sampler W NA NA NA (d) Stack Flow Rate Monitor D(3) R Q(7) NA (e) Sampler Flow Rate D R NA NA l D e Daily Q = Once every 3 months M = Once every month R = Once every 18 months W = Weekly NA - Not Applicable l l MILLSTONE - UNIT 1 3/439 Amendment No. 106 1 y,_, ,7 ..,-_...__,.,y

TARI2 4.8-2 (Castianad) TABIZ NOTATION l i (1) Instrument check daily caly when the aussented off-gas treatme i system is la operaties. (2) samples eestalaims a aaminal:The INSTRLMDf7 CALIBRATIO i 1. One volume percent hydrogen, balanes altregen; and 2. Four volume percent hydrogen, balance altregen. 1 (3) Instrument check daily only whom there esist releases via this pathway. l (4) Calibraties shall include the use of a known source whose stren has been determined through the use of a esadenser R meter trac i to the N35. The seures and detector shall be la a kneva reproducible geometry. (5) The lastrument fumetional test shall aise demonstrate the follow 1. Automatie isolaties of the off gas line occurs withia 15 i minutes if any of the following eenditions maist: 1 Both monitors fadicate measured levels above the trip set-a. pelat. i b. One mesitor ladicates measured levels above the trip set-pelat, and the other ladicates a dowascale trip. 2. Centrol room alors assumeistion occurs if any of the following i esaditions aalst i i 1 Either mesitor ladicates asasured levels above the a a. trip setpoint. I i 3 b. Either maatter ladicates a devescale failure. Jastrunest restrels are met set la the operate mode. c. (4) is determined by a detector which has been calibra soares. These sonrees shall be la a knova reproducible geometry. (7) The 2257RIMDIT FUNCTIONAL TEST shall also demons j rose alarm ensanciaties occurs if any of the following conditians esists i i MILLSTONE - UNIT 1 3/4 6-10 i Amendment No.106 ---+-see-- re.

---

,-,-.=w--w--.-

es---ew----*--se.- w---------

---

w-

TABI2 4.8-2. (Contissed) i TABI.I NOTATION 1. InstrumentLadicatesmeasuredlevelsabovetheshare/ trip setpolat.* 2. Instrument indicates a devascale failure. 3. Instrument teatrols met set ta operate mode. Not applicable for stack'ilow rate matter. I l e 4 i s l i 3 MILLSTONE - UNIT 1 3/4 4-21 Amendment No.106 ....y cm-__.,. _.. , ~ _ _ _., _ _ _ _ -. _ - _

4 - x , F LIIIITIIIE CONBilleII FnR ertR4TIgII G- ~ SIISTEILLAntt etsplatMtuf5 -e E.' 3.8.C Redioective Liquid Effimeets 4.R.C Radiesetive Liquid Effluents ~~- ! E 3.8.C.I' Lignid Effluents Cescentration 4.8.C.I Liamid Efflecets Concentreties i ' 4 I 3.8.C.I.1-The reecentraties of radiesetive esterial 4.8.C.1.1 Radioactive liquid moetes shall be released from the site (see Figure 3.5-1) sheII met sempled and emelysed secording to the eseyttes and enceed the teorestrattene specified la le CFR Part. 29 emelyste progree specified to sectise 1 of the Appendia S. Table II. Celmes 2 for radiosectides other gggmeC38. thee dissolved er estrained emble gases. For dissolved or entreteed e,ghte gases, the concentraties shell met 4.3.c.1.2 j The reemite of radiesetive smalyste } esteed 2 m It pCA/e! total actielty.. eine11 he mood le secordance with the methode of Section 11 of the 3E39004 to ensure that the ese-APPLICABILITY: At all times. eentretiene et the point of rolesse are meisteamed R ACTleN: within the limits of specificetten 3.8.C.1.1. { ? With the concentreties of radioective esterial releeeed M free the site exceeding the above limits, restore the l concentrattee within the above liette within 15 mimetes. t l t a i 3 t O r e lE f 5 ~ } i i ( i

9 1 y E NE N NE .m SINittiLLAuct arquietntats r-4/5 el I g 3.8.C.2 - Lignid Efflorets - Bene - .m 4.s.C.2 Ll_ geld Efflecet _Dese 3.8.C.2.1 The dose or dose comiteret to any REAL l je I M OF T M PW LIC from radiesetive meterials le 4.8.C.2.1 Bose Celeelettees. Canelattwo dose ese-i 5 lignid effleemts from Welt I released from the site. trihettone from Itgeld effluents shall be determined j [ (See Figure 3.5-1) shell be limited: Se secordance with Section II of the EEMoDos esce i per 31 days. } Duriesanyceleederquarterte{1.5areatothe a. total body and to i 5 meen to any orges; and, 4.8.C.2.2 Relettwe accuracy or cesservatism of the calculations shall be confirmed by perternance of j b. During any e'elander peer to the Radielenical Eeviressental Nemitories Program as bodyandtoileeramteser{erses.3 ores to the total detailed le the RENDDOI. AffLICABILITT: Atalltimes. ACfteN: N j a. With the calentated dose free the release of J redtemetive meterials la I4 geld effluents esceeding 4 I' w any of the abese liedta, le ties of any other report required by Specificaties 6.9.I. prepare 4 1 and sohmit to the Commissies within 30 deye, perseest to Specification 6.9.2, a Special Report which identifies the conee(s) for esceeding the limit (s) and defines the corrective actions to be j tahee to redere the releases of radiometive p meteriale is lignid effleemts during the reeninder d { et the corrent calender guerter and the calender J = year se that the cumulative dose er dose commit- [ g meet to any RAL SEMBER OF THE PUBLIC from such releases during the calendar a to the. tai bed, and i. year is within 3 mren to any er.aa. O I d j j \\ i l l l t

4 M NIE fM Mb 4 g g m g ggggy r-g 18.D Radoective Gaseous Effluents 8 4.g.D Radioactive Gaseous Efthsents t 18.D.1 Gaseous Elfluents - Dose Rate m 4.3.D.1 _ Gaseous Effluents - Dose Rate g 18.D.l.1 The h:^1 ^r: 2: dose rate offsite (see Figure 3.5-

1) due to radeactive sneeerials released in gaseous etfluents 4.8.D.I.I The instantaneous release rate correv:--34 to the j

q from the site shall be limited to st;a 1:"1 1 dose rate shall be determined in accordance with the methodology 4 values: Section It of the REMODCM. j a. The dose rate Malt for noble gases shall be 5 300 serem/yr to the total body and f 3000 sarem/yr to the 4.8.D.I.2 The instantaneous release rate shall be monitored stdne and, accordance with the requirements of Table 3.8-2. l j h. The done rate M ler lodne-131, Bodne-133. Tritkam 4.8.D.I.3 Sampling and analysis shall be performed in accordanc and ler all radeactive neaterials in particulate form with with Section I of the REMODCM to assure that the limits c half Eves greater than 8 days shall be d 1300 nerem/yr to specification 3.8.D.l.1 are met. any argen. c j :) APPUCAnit. TTY: At all tinies. i } }.a ACTION: l ) With the dose rate (s) enceedag the above limits, decrease the release rate to comply with the limit (s) given in Specification 3.8.D.I.I within 13 niinutes. 1 3, i i l l l l o g t i 3 E t , go } f a i l j =

~ e j M M fW M SNKI M W WIENT l h 3.10.2 Gaseous Effhants Dese. Nehle Cases 4.10.2 Caseois Etthsents - Dese. Nolde Cases I G e- ~ g un.11 The air dose offsite lose Figure 3,S-1) due to 4.LD.2.1 Dese Calculations - Cisnulative dose contrilmselens for noble gases released in gaseous etahsents froen Unit I shall be the cwrent calendar quarter and cwrent calendar year shall be Ihmited to the letteedngs determined in arrardance with Section It d REMOOCM once every 31 days. During any calender War, to I 3 snrad for gennna a. -i radation and f10 sarad for beta redations 4.LD.2.2 Relative acewacy or conservation d the calculations l shall be confirsned by perforsmance of the Madological Environneental b. Dwing any calender year, to $10 snrad far gasnma Monitoring Proyant as detailed in the REMODCM. ] radation and d 29 sared for beta redations j APPUCASEJTY: At all sinnes. J N l j g Winie see emandseed air daee frene radeactive nolde gases in gaseous offiumats eaceedag any of the above lisaits, in lieu of j any etsier report regstred by Specification 69.I, prepare and es l g subenit to the f*h within 30 days, pwsesent to l Specification 69.2, a 5pecial Report whide identified the caseels) for eaceedag the limitis) and defines the corrective actions to be tal=se to reduce the releases of radeactive nome gases in gaseous effhsents during the rennainder of the cwrent I calender gsorter and the calender year so that the cisnelative t duee during the calender year is within 10 enrad for gennna j radation and 20 snrad for beta radation. .F

• t g

E ) .a l j 1 i

{ M M IE N., SM N W EMW z f > 3.8.D.3 Caseons Effluents Dese Radoiodnes. 4.8.D.3 !y Radeactive Material in Particdate Form. and Caseaus Effluents - Dese. Radicionnes, Radianctive g R '- ,m "te Other Th._. Noble Gases Material in Partecdate Form, and Radeonuttedes Other Than Notde Gases

a 3.1 0.3.1 The dame to any REAL REMBER OF TIE I

PUBLIC froen lodne-131 ledne-133, Trithan and radoective g 4.8.D.3.1 Dose Caledations - Cisadative dose contributions for neaterials ist partiadmee fann with half lives yeeter than eigPetthe cwrent calendar quarter and cwrent calendar year shall be q days in gaseous effuents released offsite troen Unit detennined in accordance with Section it d the -REMODCM I (See Figure 3.3.1) shall be lismiled to the fo44 ewing: every 31 days. Dwing any calender geerter to f:7.3 parenal 4.8.D.3.2 a. Relative acewacy or conservatisne of the calculations shall be confitnied by perfonnance of the R9"_W Environneental b. Dwing any calender year to 413 nerenig Monitoring Proyant as detailed in the REMOOCM. APPLICABR.ITY: At all sinies. ACTION: w (2 a. With the calendated done fresa the release of ,;a r-fi" x, radeactive sumaterials in particidater fonn, ar rada===-lides other than noble gases in gaseois 4 ef8ments eaceedng any of the above lisaits, in lieu of any ottier report regsired by Specification 69.1, prepare and Mt to time C 'rn within 30 days, pursuant to i Specification 09.2, a Special Report whide identities the i causeis) for eaceedag the liwait and defines the corrective actions to be taken to reduce the releases dwing the resnainder of tese cwrent calendar gaarter and g the calender year so that the cumdative dose or dose I comuniennent to assy REAL MEMBER OF THE PUBLIC s. ]y, Irene such r a.m a dwing the calendar year is within s weresse to assy organ. i 3 2 4 t

M M IM N 3mKm gg, x ~ 1.8.D.4 Radeactive Effluents - Total Dese 4.LD.4 Radonctive Effluents - Total Dese C; U 3.S.D.4.1 The dose or dose caansmitsnent to any REAL 4.8.D.4.1 Cisnidative dose contritnations' fresa -liquid anc .N ngnanFR OF Tm PUBLIC fross the Millstone Site is lisaised gaseous elfluents and direct radiation frcen the Millstone site shall be to 4 25 snreen to stie total body or any organ (emcept the determined in accordance with Section li of the REMODCA4 once pes e s thyrohl, whicts is Manited to f. 75 seresn) over a period of 12 31 days. consecutive sneaths. APPLICABE.fTY: At au h. ACTION: a. With the calcidated deee fresa the release of raamartive snaterials in @ ar gaseous etfluents enceeeng twice tese lineits of Specifications 3.8.C.2, 3.8.D.2 er 3.S.D.3,in lieu af any other report required R by Specification 09.1, prepare and subsseit a Special Report to the Comunismien within 30 days pursuant to ? 5pedfication 09.2 and lisait the :t:7-4 releases .O such that the dame er done comunitsment to any REAL EtBER OF TE PtBLIC fresa the. Maistone Site is lismieed to n 25 anreen to the total body er any organ lencept tesyreid, whide is lineited tof73 sereni) over 12 consecutive susentis. This Special Report shall include asi analysis whicto dessionstrates that radation eigiosures to any REAL MEASER OF THE PUBLIC froen the MNissene Site Gactueng all etfluent pathways and y drect radadam) are less than the 40 CFR Part 190 3 Standard. k N shir estlaneted h enceed the above lineits, the 5 Special Report shaN include a regnest for a variance in accordance with the provisions of 40 CFR Part 190. 2 Subanittal of the report is considered a timely request -'g and a worlance is panted intil stafI action on the rept is cannplete. ~

e MN mmgm 3 r-0; 3.SA3 F _ "n* Gas Misture 4.8.D.5 Emplosive Gas Mixture U= 34.n.5.1 The eenceneration et hydrogen in the main condenser efigas tr==*==* s.a.o.5.1 The concentration et hydrogen shalt be determined to s.

system, 1 =asa ei the 5

'-1., shen be lineited es d 4% by vehnne. be within the above limits by neonitoring the waste gases with the s+: c-hydrogen neonitor required OPERABE by Table 3.5-2 er by ] APPUCASIUTY: At all times.

==- 2 with Action A of Table 3h2 if the Manitor is inoperable. ~ whh the e--r==* ation ei hydrogen areaser than es hist n. < i less then er e,ses se as, ressere the concentration to widnin Wee Manit wiWein 4: lesiers Wille Wee concentration of hydrogen greater tenen 3%, eerh une of the augmenced OFF-GAS SYSTEM. z. E a E = 3 ',,a 9

3 F LIstiflNE Cselfl011 FWR SPtR4flWII M Sultvtill.ANCE Stgt#1REMENf5 E ~~ 3.8.9.6 Steam Jet Air Ejectee Hable ces Activity 4.8.8.6 Stese Jet Air Ejector Noble ces A ivi,ty G 3.3.3.6.1 In the meia condeneer OFF-CAS STSTEN, 4.8.D.6.I the noblegges la process activity rate shelt met esceed The noble ass in process activity rate 1.47 x le pCi/see averaged ever 15 mimetes as measured shall be contimesesty moeitered by the steam Jet air at the off ges maalter. ejector ef t sas mealter rewired OPERAtti in Table 3.8-2. APPLICABILITY: At all times 4.8.9.6.2 The noble gas in-process activity rate shall be determined to be within the above tielt by ACTIW : Performance of the steam Jet air ejector saenting With the mehle ses actietty esceeding the aheve limit, required in Secties I of the Renosoi. redece the activity rate to withis the limit withis 72 R hours or be in at least IPyr STAlmsf withis the sent 12 beers. ? ~ ~ e

• 7 Y

-?

- - ~ _ _ "~w e e! ,t enum 1-g. ~4 5 1 5 i i N. 5 I l5 = l \\

l

~ 1 1 e. at '< l = I t y:8 5 i I sy j y! s ~ - 4, I C I N y j t f ,..Gp:37...:+ -m d }$ ';' l b r h c; g g, . e.w.a.. [ j' o i ~.

• N.

a k i \\.. I 2 \\ \\\\ I R. y 8 R. a J b' i ? g 1 IllLLSTONE. UNIT 1 3/4 8-20 kendment no,y y

4 1Anom a emubber is found lamperable, an engineering evelaation is perfonned, in ~ 0; addities to the deteaminat1em of tree snubber mode of failure, in order to determine [ ~ i g if any safety related congsonant or systemi has been adoersely affacted by the M inoperability of the enehtser. t [ { g ggio engineering eselection aball deteanime whether or not the snubber mode of i falleee has laparted a significant effect or degradation on the supported com-l i ] ponent or system. 14 peeride assurance of snubiner reliability, a representative samenle of the installed memhbers will tse tested during plant minutdouns at eighteen (10) month intervals. served falleres of timese sample amubbers shall regsire testing of additional units. 0 03 - j sydres11e ammbbers and nochenleal snubbers may each he treated as a different entity for the alsove surveillance programs. i j I J. randa= sate Samleeraltrees " [ 1he criteria of the reste mentterlag program and the resta replacement program have been established te } protect the reacter from high chlertde level should a seamater leek occur in the nata condenser. ( crtterla wt11 provide for a etetsum unused capactty af 30 pounds of chleride ien (50 percent depletien 1m a These reste uhtch is approachlag the llett of 0.75 megAn1) hefere a planned regenerattee of a resta. ,=, seamster leek accer when a reste has 30 pounds of capacity renntning, this criteria util allow a sufflctent Should a hoffor for an orderly plant s8ustdema. { i l The reste depletten can be calculated asteg the measured salt-splittles capacity. the flew through the bed, and the average lofluent conductivity. Based en this result, a depletten can he calculated utitch will assure j a 5. pound chlerfde ten enchange reserve. Regeneretten prior to this level of depletten will assure a i soffitteet les enchange reserve for removal of chierlde from the condensate system. j t These facters fore the hasIs for the fregsency ef sampitog. analyriog, calculatien and legging survei11ance i I fras dts initial value of 1.2 meg. A guerterly sampitag fregnency will he suffletent to detect the slow. regatrements. Stace startup of Delt 1. the salt-spitttlag capacity of the restas has degraded about 151 d . g leeg-term degradotten of the resta. As conductivity tacreases, the calculatten and legglag ulli he increased P to a weekly has15 and uitlestely on a daily hasis when and if 1afluent conductiwIty reaches 0.3 imho/cm er greater. i m i q w 4 w----- m- ,-~r--- ,,i-,e--- w- - - -- - -,-m --+-. -~ w ,.m--,-s e+:- e-'m -m-e ---e-----i----v-- ,e-- -- + - --- e'---- 9

~ 5 F $ K. N =1 Comesmeed Verses puey E 7 The perpeee of==Immetas the mecheetcal'essereser seemme peep line is to Ilmit the release of set condesser le the malibely event of a centrol red drop eccident. c male weeld be treespotted from the reacter to the este steemitees to the este conhecer. Series the postulated accident, flesl z ectivity weeld be

=====d by the sete steam 11me rediesetivity eseitere and feetettee would he initiated. The fiestem prodmet radio- ~ e e (It I i 1-t l i g 5 l t I ~

3.8 BASES O_ Radioactive Lieule Effisent feetrumentation j 3: l P h redieettive Ily id efflecet instrumentation is provided to mesiter and centret, as applicable, the C releases of radioactive meterials in lipid eff1 meets during actual er potential releases. The stare / trip N setreints for these feetruments shall be esiculated is accordz:-e with approved methode le the 000t to j Fi ensure that the alare/ trip will occur prior to esceeding the limits of 10 CFR Part 20. The OPERASILITY 's med use of LS8s feetrumentottee is coastetest with the repirements of General Design Criteria 60, 63 med, q 64 of Appeedia A to le CFR Fort 54. l [ B. Radioactive Geseems Effluent Testrumentaties The radioactive saeceos effluent imetrumentaties is provided to moeiter and costrel, as app 611chble, the reless,es of radioective meterials le gaseems effimeets during actual or poteettal releases. The alare/ trip setpoints for these feetruments shall be calculated in accordance with approved methods le the 0001 to i esaure that the alare/ trip w!!! occur prior to esceeding the limits of le CFR Fort 20. This instrumentattee j slee includes previelsee for moeitering (and contre 11 tag) the concestratione of potentially empleelve gas mistures le the weste gas heldup system. The OPERABILITY and use of this seatrumentaties is consistent with the re p irements of General Design Criter. 60, 63 and 64 et Appendia A to le CFR Fort 50. 3 l m C. Radioactive Liquid Eff1 meets s., 2 1. This specificaties is provided to ensure that the concentraties of radioactive meterials released is lipid weste effluents from the site will be less than the concentration levels specified la 10 CIR caL Part 20 Appendia 3. Table II. This imetantseeems Ilmitatlee provides additiemal assurance that the levels of radioactive meterials is hedles of water outside the ette will result la espesures withis f (1) the Secties II.A desige objectives of Appendia 1,10 CFR Fort 50, to an individual and (2) the limits of 10 CFR Fort 20.196(e) to the pepelattee. The concestrattee limit for dissolved er entrained mehle gases is based spea the assumptise that Ie-135 is the controllies radioteetepe and its MFC la air (embeersion) was coeverted to an e pivalent concentraties le water maing the methods described is laternational Commission se Radiological Fratecties (ICRP) Fuhlication 2. N 3 t g 1 n ? 8 I l ~ I

e 2. ~ This specificatiee 13 proeided to leptement the repiremente of Sectione II.A, III.A med IV.A of Appeedia 1, 10 CFR port St. The Limities Ceedittee for Operettee implemente the guideo set forth le } Secties II.A of Appendia 1. The ACTION statemente provide the regelred operating fleethility med at j the same time Iglement the guides set forth in secties AY.A of Appeedia I to essere that the ] g releaseo of radioective meterial in Ilyid ef fleeste will be kept "es les as le ressemehty ochleeable." 'The doee calcolotteen la the 0308 !aplement the regelresente le Secties III.A of Appendia I thet p l g confesseece with the seidee of Appeedia I le to be shown by calculatiesel precedures beoed en modele l e he embeteettelly enderestimated.med data each that the actual espeewre of as ledteideal threegh appropriate po A The egnettees specified le the 0001 for calcoleting the desee des i = to the actest relesee retee of radioective esterlste le lignid efilmente will be comeisteet with the g methodelegy proeided le Beseletery Gelde 1.189 "Calcolettee of aessel Deeee to Mme fr.am Resties i Deleases of Beector Effluente for the h,x: q "Seelelen 1, October 1977, med Segelstery Seide 1.113, "Estimeties Agostic Dieperates of Effluents free Accidestet med Beettee Reacter Relesees fee the perpeee of lapleasettag Appendia I," A$til 1977. \\ 4 1 != e. i ~ l N i a R 3 [ ] l h ,1 ~ I W 3 I 4

B. Radleective Caseems Effleemts t XP l. This specificaties is provided to G ~ all emits en the site will be withi y. eneere that the dose rate at any tis the aemme h sammel deee lloits are the doses a m

3. Table II.

me free gaseems efflecats frne e gaseems efflerets will set result in thThese limits provide reaseeable ssociated with the concentratfees of 50 g art 26 for all areas allsite. O reecentrations esceeding the limits sp e espesare of an individsel offsite tassurance th ,[ 29.le6(b)). individest will he sofficiently lFor individuals she soy at times h ecified in Appendia 8. Table II of le CFo asemel aserate scharmed in facter above that for the site bound es to compensate for any increase le the within the site bo the correspeeding gamme med bet ary. peery of the heemdery to a dose rates above hochgreemd to se i diThe speci ratelimitsa{lesrestrict,atalltim 5ee areevyear to the total body or t restrict, at all times, infant via the reemailk-infant. pothesy t n vidual at er beyond the site es, the corresponding thyroid dose r to f 3000 oren/ y 2. N ec release Appendia I, IS CFR Part 58This specificaties is proeided to im l o f 1500 meee/ year for the searest ces ta e above backg o the plmet. The Limiting Candition for operatiep ement the requiruerats Section II.B of Appendia I. the same time implement the guid The ACTION statements provide the req i .. III.A and IF.A ef o releases of radioective esterial is geo s implements the guides set ferth in 1 es set forth in Secties IV.A of Appeedi achievable". u red operating flesibility and at I that comfeemence with the guides of AThe Serveillance Segoirements impl eems effluents will be kept "as law a J, a I to assere that the 1 models and data such that the actual e ppendia I is to be shoue by calculatiement the require enlikely te he substantially enderesti speeere of an individeal threech th calculating the doses due to the actuel et Appendia esel precedures based on ested. will be consisteet. with the methodol release rates of radioactive noble gaThe dos Roses to Ilse free Beetime Releases ogy provided in Segulatory Guide 1 n the 000t for with le CFR Part 58, Appendia 1" of Beacter Effleemts for the purpose.199 " Calculation of Ames le gem Eatienting Atmospheric, Trans, Sevision I Light-Meter-Cooled Beacters", port and Dispers, ion of CeseeOctober 1977 and Resolatory Guidof semat Revision I, July 1977. ms Effluents la Reetime Releases fe 1.1 a The mot egnations provided for determi i y

stillaims soccessively more realistic d ree a

ose calculational methodelegiesn ng the air deoes porties of the regulatory limits.atisest methods are used 34enever sle lifi E are beoed open p The methods need, in order areed calculations indicate a do per released activity ratie, historical real time seteorology and actual radi i R , previessly determined air doseaching a omerlides released.meteorelegical date and actual radie neetide ein released, or S l'

~ 3. This specificction to provided to implement the regesir A r PP'*dic I.13 CFR Part 58. ) h Limiting Canditions for Gycration are the guides set ea th iem G Secties ll.C of ?;;; Jim 1. h ACTION statements provide the required operating flexibilit the same time implement the.gmides set forth in S g r n releases of radioactive meterials le gaseeens effimeets will bection IV.A ef ?;;; ;is I to asser i M y and at { achiewahle". I the regesirements la Section Ill.A of ?;;: Jim I thatThe 0308 calcolatiemal me l c-shone by calcolatiemmi precedures based ese models med dataconfermance with the guides ance regeeirements im 'l fi individual threegh appropriate pathways is enlikely to b serb that the actual esposeste of an ix 3 he meterials will to be consistest with the methodelegy provided i

• ~

j W 0001 release rates of the subject a lating of Aeneal Deses to Non free Beatise Releases of Rea t n Regulatory Caside I.It9, "Calce-j Evaluating Ceepliance with 18 CFR Part 54 Appendix 1 4 c or Effleemts for the Pierpes,e of Gelde 1.111, "Itethods for Estimeting Aa . " Revision 1, Octeher 1977 and Regulatory Reetime Releases free Light-Water-Cooled Reacters" r ; 2 ric Transport and Rispersies of Gemeems Elfliseets la for detereieing the doses based apen either conserv,ative at Revision I, July 1977. N oe egenetions provide critical nuclide ein oc estes real time meteorelegy and specificasepheric dispersion med se rate specifications for radioledines, radioactive esterial is meclides released. The release othee than emble geoes are dependent en the existing radieneclidparticolate fore and ra which are esselmed in the development of these calcolations e pat,hesays to mee. sicherme radieneclides, 2) deposities of radiomoclides este g { g W pathesays

1) individual ishalaties of are:

consesyttee by men graze with censum. 3) depeetties este grassy areas obere milk animals and m esposere of mee. pties of the olik and meat by mee, and 4) deposities se j \\ j 4. This specificaties is provided to acet the reporting regseirem the Special Report, it may be assumed that the dose c ents of 40 CFR 198. For the purpose of \\ meeleer feel cycle facilities at the same site er withis a radiether f i 1 ose centributiees free other i 5 This specificaties is provided to cesore that the concentratieses of 5 miles most be !g* contained in the meste gas treatment system is esistained below thof potentially emples;ve gas i i 2 and saygen.

provides asserance that the releases of radioactive materials will be j R l

the requireacets of General Resign Criteries 6e of "; e r flammability limits i ,; Jim A to 10 CFR Part 50.ostrelled in comformance with. \\5 l l i.8 i l I i

-:r 6 Restricting th.s gross radioactiwity rate of emble gases free the meio condenser provides resseeable

P esserence that the total hedy esposere to an individual at the esclosies area hemedary will not

'G esceed a small fracties of the limits er la Cf3 Part les se the event this effluent is inadvertently"

y discharged directly to the envireement withmet treateret. This specificaties implements the rey irr-erets of General Design Criteria 64 and 64 of Appendis A to le G1 Part SS.

m b em e u. l .e ~ y lll3 2 2 ,o M

I ADMINISTRATIVE CONTROLS l 1 f. m performance of activities in seeordance with the RADIOLOGICAL IFFLUENT MONITORING AND OFFSITE DOSE l CALCULATION MANUAL at least once per 24 months. g. h performance of activities required by the quan'tity Controls Section of R tory Ouldeg 1.11 Rev.1 June 1974 and 4.1, Rev.1 April 1978 at t once per 12 months. s. ig MILIATONE - UNIT 1 6-14a Amondment No.106 G 4

ADMINISTR ATIVE CONTROLS SAFETY LIMIT VIOL ATION (Continued) E. i b. The NRC Operations Center shall be notified by telephone as soon as l~ slble and in all cases within one hour. The Vice President Nuclear rations and the NRB shall be notified within 24 hours. A Safety Limit Violation Report shall be prepared. The report shall c. be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence. L d. The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Vice President Nuclear Operations within 14 days of the vlotations. 6,8 PROCEDURE 5 s s. i 6.8.1 Written procedures shall be established, implemented and malntained covering the activitj es referenced below, s s. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, February,1978, b. Refveling operations. Surveillance activities of safety related equipment. c. d. Security Plan implementation. e. Emergency Plan Implementatlon f. Flre Prelection Pragram implementation. 3 Quality Control for effluent monitoring using the guidance in Regulatory Guide 1.21 Rev.1, June 1974. h. Radiological Effluent Monitoring and offsite Dose Calculation Manual (REMODCM) Implementation, except for Section I.E., Radiological Environmental Monitoring. 6.8.2 Each procedure and administrative policy of 4.8.1 above, and changes thereto shall be reviewed by the PORC/SORC, as applicable, and approved by the Un,it Sowrintendent/ Station Superintendent prior to implementation and reviewed peroodically as set forth in each document. MILLSTONE - UNIT 1 d,16 Amendment No. 85. 75 106

ADMINISTRATIVE CONTROLS 2 l 8.8.3 i Temporary changes to procedures of 8.8.1 above may be made provided: I s. The intent of original procedure is not altered. i i b. The eh9nge is approved by two members of the plant management staff, at least one of whom hands a Senior Rosetor Operator's License i en the unit affected. 1 e. The charge is documented, reviewed by the PORC/SORC, as 4 appliesble, and approved by the Unit Superintendent / Station ) . Superintendent with a 14 days of implementation. 3 4.8.4 Written procedures shan be estabHahed, implemented and maintained j eevering Beetion LE, Radiolorleal Invironmental Monitoring, of the REMODCM. I 8.8.8 All procedures and proeodure changes required for the Radiologloal Environmental Monitoring program of 4.8.4 above shan be reviewed by 'an ( individual (other than the author) from the Radiolo supervision. peration Servlee laboratory (pOSL)gical Assessm production O and approved by appropriate i

s.

l j Temporary changes may be made provided the intent of the original procedure is i' not altered and the change is doeumented and reviewed by an individual (other i than the author) from the Radiologleal Assessment Braneh or the POSL, within i 14 days of implementation. i k 8.9 rip 0RTING REQUIREMENTS f ROUTINE REPORTB 1 )l ki addition to the appueable reporting requirements of Title 10, Code { 8.9.1 of Federal Regulations, the fouowing Administrator, Region I, U. R. Nuclear ta chan be submitted to the Regional i tory Commission unless otherwise { noted. l BTARTUPREPORT 8.9.1.1 A summary report of plant startup and power esentation testing shau he submitted fouewing (1) rocelpt of an operating Meense, (2) amendment to the license involvi a planned ineresse in power level, (3) installation of fuel that t has a different er has been manufsetured by a different fuel suppuer, and j (4) modifications t may have signifloantly altered the nuclear, thermal or j hydraulle performanee of the plant.

t 8.9.1.1 The start report shan address eneh of the tests identitled in the l

pSAR and shall a description of the measured values of the operating eenditlens or eharnetaristles obtained during the test m and a comparison of these values with design predlettens and speelfles eerreetive i i estions that were required to obtain antisfactory operation also be i deseribed. Any additlanal speelfle detaus required in lieense senditions based on 4 other commitments shan be included in this report. l 4 i 4 i MILLSTONE - UNIT 1-4-17 Amendment No. SS,48, si, WW,106 l \\ ~.

ADMINISTRATIVE CONTROLS THIRTY-DAY WRITTEN REPORT (Contled f Reactor protection system er engineering safety feature instrument a. settings which are found to be less conservative th'an those establ,shed by the technical specifications but which de not prevent the fulfillment of the functional requirements of affected systems. ~ b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation of plant shutdown required by a Mmiting condition for operation. Observed inadequacies in the implementation of administrative or c. procedural controls which threaten to cause reduction of degree or redundancy provided in reactor protection systems or engineered safety features systems. d. Abnormal degradation of systems other than those speelfled in 6.9.1.8.c, above, designed to contain radioactive materla! resultfrig from the fission process, j ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l i 6.9.1.10 Routine Annual Radiological Environmental Operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. r The Annual Radiological Environmental Operating Report shall include that information delineated in the REMODCM. SEMIANNUAL RADICACTIVE EFFLUENT RELEASE REPORT 6.9.1.11 Routine radioactive effluent release reports covering ti.e operation of the unit during the previous 6 months of o 60 days af ter January I and July I of each yar.peration shall be submitted withi l A supplemental report containing dose assessments for the previous year shall be submitted annusUy within 90 days af ter January 1. The report shau include that informatioh deuneated in the REMODCM. t Any changes to the REMODCM shall be submitted in the Semlannual Radioactive Effluent Release Report. SPECIAL REPORT 5 6.9.2 Special reports shall be submitted to the Regional Administrator, Region t,0. 5. Nuclear Regulatory Commission, within the time perled specified i for each report. These reports shall be submitted covering the activities identified below pursuant to the requirement of the appucable reference specifications a. In-service inspection Results, Specification 4.4.F. MILLSTONE - UNIT 1 6 21 Amendment No. #, #, N, W.106 .m

o b. Primary Containment Leak Rate Test Results, Speelfloation 4 e. (Deleted). d. Speelfication 4.8.B.3. Materials Radiation Surveillance Spee Fire detection instrumentation, Speelfloation (3.12.E.2) e. f. Fire suppression systems, Speelfloations (3.12.A.2, 3.12.B.2, 3.12. C.2). 3.8.D.2, 3.8.D 3 and 3.8.D.4.Radiologleal Effluent Reports g. t E s. n 'l MILIATONE - UNIT 1 6-21a Amendment No. #f, #5, if, y,106

< ADMINISTRATIVE CONTROLS B 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE ) CALCULATION MANUAL (REMODCM) Section I, Radiological Effluent Monitoring Manual, shall outline the sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionucUdes releasedasa result of station operation. It shall also specify operating guiddines for radioactive waste treatment systems and report content. Changes to Section I shall be submitted to the Commission for approval prior to implementation. i Section II, the Offsite Dose Calculation Manual (ODCM), shall describe the. methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with ' ~ - - the applicable LCO's contained in these technical specifications. Changes to Section II need not be submitted to the Commission for approval i ' prior to implementation, but shall be included in the next Semi-Annual Radioactive Effluent Release Report. 6.16 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the Unit shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents. These procedures shall specify the use of appropriate waste treatment utilizing the guidance provided in the REMODCM.

• The solid radioactive waste treatment system shall be operated in accordance with the Process Control Program to process wet radioactive wrates to meet shipping and burial ground requirements.

1 .y ~ 4 1 MILLSTONE - UNIT 1 6-26 Amendment No.106 -n.----- -}}