Text

Proposed Tech Specs Section 15.7 RETS Re Removing Items Identified in GLs 89-01 & 95-10 as Being Procedural Details & Relocating Items to Appropriate Documents
	ML20108A001
Person / Time
Site:	Point Beach
Issue date:	04/24/1996
From:	; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20107N199	List: ML20107N195; ML20108A001; ML20108A012; ML20108A019; ML20108A022; ML20108A035;
References
	GL-89-01, GL-89-1, GL-95-10, NUDOCS 9605020048
	Download: ML20108A001 (56)
	v • d • e

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1 o

TABLE OF CONTENTS Section Title Eag.t 15 TECHNICAL SPECIFICATIONS AND BASES 15.1 Definitions 15.2.1-1 15.2.0 Safety Limits and Limiting Safety System Settings 15.2.1-1 15.2.1 Safety Limit, Reactor Core 15.2.1-1 15.2.2 Safety Limit, Reactor Coolant System Pressure 15.2.2-1 15.2.3 Limiting Safety System Settings, Protective Instrumentation 15.2.3-1 15.3 Limiting Conditions for Operation 15.3.0 15.3.0 General Considerati9n 15.3.0-1 15.3.1 Reactor Coolant Systes 15.3.1-1 15.3.2 Chemical and Volume Control System 15.3.2-1 15.3.3 Emergency Core Cooling System, Auxiliary Cooling i

Systems, Air Recirculation Fan Coolers, and Containment Spray 15.3.3-1 15.3.4 Steam and Power conversion System 15.3.4-1 15.3.5 Instrumentation System 15.3.5-1 15.3.6 Containment System 15.3.6-1 15.3.7 Auxiliary Electrical System 15.3.7-1 15.3.8 Refueling 15.3.8-1 15.3.9 Effluent Releases 15.3.9-1 l

15.3.10 Control Rod and Power Distribution Limits 15.3.10-1 15.3.11 Movable In-Core Instrumentation 15.3.11-1 15.3.12 Control Room Emergency Filtration 15.3.12-1 15.3.13 Shock Suppressor (Snubbers) 15.3.13-1 15.3.14 Fire Protection System 15.3.14-1 15.3.15 Overpressure Mitigating System 15.3.15-1 15.3.16 Reactor Coolant System Pressure Isolation Valve 15.3.16-1 15.4 Surveillance Requirement 15.4.1 15.4.1 Operational Safety Review 15.4.1-1 15.4.2 In-Service Inspection of Safety Class Components 15.4.2-1 15.4.3 Primary System Testing Following Opening 15.4.3-1 15.4.4 Containment Tests 15.4.4-1 15.4.5 Emergency Core Cooling System and Containment Cooling system Tests 15.4.5-1 15.4.6 Emergency Power System Periodic Tests 15.4.6-1 4

15.4.7 Main Steam Stop Valves 15.4.7-1 d 5 15.4.8 Auxiliary Feedwater System 15.4.8-1 vit Anomalies 15.4.9-1

$8' 15.4.9 Reacti6g~l 1 Operctic=1 Environmental gidfo}itor ng og 15.4.10 o

Mon 15.4.10-1 mo 15.4.11 Control Room Emergency Filtration 15.4.11-1 mg eu 15.4.12 Miscellaneous Radioactive Materials Sources 15.4.12-1 80 15.4.13 Shock Suppressors (Snubbers) 15.4.13-1 15.4.14 Surveillance of Auxiliary Building Crane Lifting n

Devices 15.4.14-1 oE 15.4.15 Fire Protection System 15.4.15-1 15.4.16 Reactor Coolant System Pressure Isolation Valves Unit 1 - Amendment No. 96 15-1 Septe:6cr 3, MB5 Unit 2 - Amendment No. MG

Leakage Tests 15.4.16-1 TABLE OF CONTENTS (Continued)

Section 111]3 Eagg 15.5 Design Features 15.5.1-1 15.5.1 Site 15.5.1-1 15.5.2 Containment 15.5.2-1 15.5.3 Reactor 15.5.3-1 15.5.4 Fuel Storage 15.5.4-1 15.6 Administrative Controls 15.6.1 Responsibility 15.6.1/2-1 15.6.2 Organization 15.6.1/2-1 15.6.3 Facility Staff Qualifications 15.6.3/4/5-1 15.6.4 Training 15.6.3/4/5-1 15.6.5 Review and Audit 15.6.3/4/5-1 15.6.6 Reportable Event Action 15.6.6-1 15.6.7 Action To Be Taken if a Safety Limit is Exceeded 15.6.7-1 15.6.8 Plant Operating Procedures 15.6.8-1 15.6.9 Plant Reporting Requirements 15.6.9-1 15.6.10 Plant Operating Records 15.6.10-1 15.6.11 Radiation Protection Program 15.6.11-1 15.7 Radiological Effluent Technical Specifications (RETS) 15.7.1 Definitions 15.7.1-1 15.7.2 Site Description 15.7.2-1 15.7.3 Radioactive Effluent Monitoring Instrumentation Operability Requirements 15.7.3-1 15.7.4 Radioactive Effluent Monitoring Instrumentation Surveillance Requirements 15.7.4-1 15.7.5 Radioactive Effluent Release @[Dj~pl@lel@j C65Ee'iifMilin Limits 15.7.5-1 15.7.6 RadfoTdflWEffluent Sampling and Analysis Require-ments 15.7.6-1 15.7.7 Operational Environmental Monitoring Program 15.7.7-1 15.7.8 Administrative Controls 15.7.8-1 i

I i

Unit 1 - Amendment No. %

15-11 S:;:t:-i r 3,1005 Unit 2 - Amendment No. 400

1 15.3.9 Effluent Release Radioactive Effluent Release limitsE{fG@lfs@l]N[*a@]'eMj@

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1 Unit 1 - Amendment No. 97 15.3.9-1 October 10, 1985 Unit 2 - Amendment No. M1

NOTATION USED IN TABLE 15.4.1-1 S-Each shift D-Daily W-Weekly Q-Quarterly M-Monthly P-Prior to reactor criticality if not performed during the previous week.

R-Each refueling interval (but not to exceed 18 months)

PWR-Power and Low Power Operation, as defined in Specifications 15.1.h. and 15.1.n.

HOT S/D-Hot Shutdown, as defined in Specification 15.1.g.l.

COLD S/D-Cold Shutdown, as defined in Specification 15.1.g.2.

REF S/D-Refueling Shutdown, as defined in Specification 15.1.g.3.

ALL-All conditions of operation, as defined in Specifications 15.1.g, h and n.

NOTES USED IN TABLE.15.4.1-1 (1)

Not required during periods of refueling shutdown, but must be performed prior to reactor criticality if it has not been performed during the previous surveillance period.

(2)

Tests of the low power trip bistable setpoints which cannot be done during power operations shall be conducted prior to reactor criticality if not done in the previous surveillance interval.

(3)

Perform test of the isolation valve signal.

l (4)

Perform by means of the moveable incore detector system.

l (5)

Recalibrate if the absolute difference is 23 percent.

(6)

Verification of proper breaker alignment and that the 120 Vac instrument buses are energized.

(7)

Radioactive Effluent Monitoring Instrumentation Surveillance Requirements are specified in S::ticr.15.7.' iSI E M MI N M fS E N @ I @ !d M E M I E 89fil.5$!.11!M N 51-(8)

Verify that the associated rod insertion limit is not being violated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> whenever the rod insertion limit alarm for a control bank is inoperable.

(9)

Test of Narrow Range Pressure, 3.0 psig, -3.0 psig excluded.

Unit 1 - Amendment No. 157 Page 5 of 6 Unit 2 - Amendment No. 461 0::;;icr ", 1000

l 1

15.4.10

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Unit 1 - Amendment 97 Unit 2 - Amendment 101 15.4.10-1 Get:bcr 10, 1005

15.6.5 REVIEW AND AUDIT (Continued) e 15.6.5.1 Manaaer's Suoervisory Staff (Continued) f.

Review violations of Technical Specifications, such reviews to include reports, evaluations and recommendations.

g.

Perform special_ reviews, investigations or prepare reports thereon as requested by the Chairman of the Off-Site Review Committee.

n.

Review the Facility Fire Protection Program at least once per 24 months to ensure the program meets established commitments and requirements.

1.

Investigate, review, and report on all reportable events.

j.

Review every release of radioactive material to the environment fiWK{K]^d

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Such review will include a summary of evaluation, recommendation and disposition of corrective action to prevent recurrence.

k.

Review all changer to the [@j}Qi[cbij ]E$1{jKd5M]M PCP =d 00CM. 15.6.5.1.9 The Manager's Supervisory Staff shall have the following responsibility: a. Serve as an advisory committee to the j Manager. b. Make recommendations to the Manager for proposals under items a. through d. above. In the event of disagreement between a majority of the Supervisory Staff and decisions by the Manager, the course of action will be determined by the Manager and the disagreement recorded in the Staff minutes. Unit 1 - Amendment No. 446 15.6.5-3 Unit 2 - Amendment No. H 0 h = ry 27, 1004

15.7 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS) RETS do not directly expand the responsibilities of the licensed operators of the Point Beach Nuclear Plant Units 1 and 2, and the material contained in this section of these Technical Specifications will not be the subject of SR0/R0 licensing examinations. 15.7.1 DEFINITIONS The definitions for frequently used terminology in these RETS are stated below. These definitions are supplemental to those definitions provided in Section 15.1. a e.m.4...., n. =v +. c..,ia o. v. s. n-a m. 4. m..,,..m = +

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.m c. c. 4., 4. m - o,n 4....mn..+.,. ym. .A 4., J. + m m _, + 4.,.., + m v. .v ....,... v l i Unit 1 - Amendment 97 15.7.1-1 October 10, 1985 Unit 2 - Amendment M1

1 f 4 V = the :: plc :ize in unit; cf volume or :::: :: :pplicabic, ) 2.22 x 10' = the number of disintegration: per minute per micrecuric, Y = the fr: tion:1 radicchemical yield, when applicable, 1 - the r:dic;ctivity de :y constant for the p;rticul:r radienuclide, and it - for plant effluent:, it i: the cl:p;cd ti=c between the !dpcint cf

=ple eclicction :nd ti: cf ccunting:

for enviren:catal :::ples, 1 it i: the cl:p:cd tiac between ::=plc 0011cetien, or end cf the J cclic tion pericd, :nd the time of ecunting. Typic:1 eclue: cf E, V, Y, and it will be used in the calculation. It

hculd be reccgnized that the LLD is defined : :n a cricri (before the fact) limit reprc:enting the ::pability of

urc=cnt sy:tc: :nd act ::

n ; cc:tericri (;fter the f::t) limit fer particular =ca:urc cat.

fG. Members of the Public Members of the public include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, j occupational, or other purposes not associated with the plant. BO. Offsite Dose Calculation Manual (0DCM) The Offsite Dose Calculation Manual contains the methodology for the determination of gaseous and liquid effluent monitoring alarm or trip setpoints, the methodology for determining compliance with release limits, and the methodology used in the calculation of offsite doses due to radioactive gaseous and liquid effluents. $E. Radioactive Waste Handlina 1. Process Control Program (PCP) The Process Control Program contains the methodologies used to ensure Unit 1 - Amendment 97 15.7.1-2 October 10, 1985 Unit 2 - Amendment 4M

l that the processing and packaging of solid radioactive waste will be accomplished in such a way as to assure compliance with 10 CFR Parts i l 20, 61, and 71, and all other Federal and State regulations governing the disposal of the radioactive waste. 2. Solidification The conversion of liquid wastes into a form that meets shipping and burial ground requirements. $$Tisdin11sEEITTM1IiiiHBliid MaTiir'fiWf6HfF61?i~nFAEolinH6 Tiff *MariFM l IE@i[FafEijl4fMEgisamsteMilitIWfs17sB'EiniElifl1[Eftjtsten i i IlocAPXpjj[f63iDGEMM8?ifiHM$grngiffaDHiEidliiET]WifffDH 1 l [N@jlEE6TRB3d3HUf$ifEW3(EfpEj[fil@EMll[@ Nil! ' l EliMiiHiiii!Gi?P313EBBianlisERIEfff6Esf5MERIssiliitid i tiEin2anmerfdtiggi!!watlifHirasinEistisisi1RfEffgtig11 pianIfEstriews1Ng!igifRpBWMistiinigasmIpilmisissi liDI@IsiiiblVANGEiildNiEEEEEEEililidirnM!giggi~Migggi s ia3inEngipT5EftsiEggEIsleiiEgga3mmermillillifiut EfiHE3EMNHHiiSHIN5sTaERM8tIEiDEfEERBIEHEB10 Hit gi@!PassunugmoiFsWiglia13nregEH75ssiaiNT;9iiisia1Eif EBgtssiegigTfHilgB1MfsFEMMtWggDilEingiliEE!!ijirfflifM HitiifffsFBIMtHE2 IGD 5annel F. Source Ch: k l A: Orce ch::k h :n :::::::ent of cher.n:1 rc:p::::.;h:n th: ch nnel detect r b exp:::d t: : :: r : Of itsre::cd r: diction. 1 C. Unre:tricted "re: An unre:tricted cr:: h :ny cre: :.t Or 5:y nd th: :it: b end:ry hcr :::::: net :::trelled by th: licen::: f r purp ::: Of protecti:n Of ind hide:h frc expe:;r: te r:dhti:n :nd rr.dic: th: ::terkl. l l H. C:::::: ",: die::t h Effl;:ent Tre:t=ent 5 :t = The gacecus radicactive effluent treatment :yste= con icts of those l

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lI. 15.7.2 SITE DESCRIPTION \\ Figure 15.7.2-1 is a site map for the Point Beach Nuclear Plant Units I The site ahp shows the site boundary and points within the site and 2. l boundary from which gaseous and liquid effluents are released. Fence locations are approximate. l l l( I l l l ( Unit 1 Amendment 97 15.7.2-1 October 10, 1985 Unit 2 Amendment 101

1 i

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15.7.8 ADMINISTRATIVE CONTROLS 15.7.8.1 Duties of the Manaaer's Supervisory Staff The duties of the Manager's Supervisory Staff with respect to these radiological effluent technical specifications are listed in Specification 15.6.5.1.8 at Items j. and k. 15.7.8.2 Audits A. Anauditoftheactivitiesencompassedbythegi$[iMQ3 MMBifiTENENIBIE @jjBJQ Offsite Dose Calculation Manual {@Q@[jj M A39 IMfBEi M S3Hi $Ffg}{g"jfg$gg[$jMT@(Mj] and. theProcessControlProgram{gg((anditsimplementing procedures shall be performed utilizing either offsite licensee personnel or a consulting firm. S. A: ::dit f th: r:dicl:;te:1 : ;ir:::::t:1 :::iteria; progeem-::d th: r:: lt; thr:;f :hil h perf.=d etili:ing ith r :ff;it: 1i:::::: ;;r:::::1 r : ;;:1ifi:d

1 tin; fi:.

lG. The results of the audit; in A : d S above shall be trans-mitted to the Vice-President - Nuclear Power and the Chairman of the Offsite Review Committee. 15.7.8.3 Plant Operatina Procedures EiW6sid[jg M M MjijilifEllflHNEI M $flil (NkIM ENdlM$$3f8}((Q hearm1(tilmffdiH11iiirfif4MilDEIEiiiii3EiiiiMillBBil r IRIsairdisiDri1HIsi!iEinirsiffmissrciEsigitigiligiuwma BDI#IMTdBli3XifJIdlBilH3ffliEEEilliiilflIiiH#Till !Eelp!GugingilicigtizitnswiWisrssmiriinW60Hinir:ss#4 HEIKfiEEgilintaraHIHisanssfirmisbeelt3HiiiiliFfH Keiraniend1MHibliM13!RAEMIEi!Siiini!NiEHifiMIH EE!MIHiihtIEMHisiillif3tBQK!2eNiUfidsi59!! NF11MMD918I13EEHEff3EisliE0fEiifDiiifiliililli KiiiilBillEBIfliiiirifHiiEifEHiF11GB623BIGHr5EfNi HE1HiiiiWif21!3fa181HEiiiEsH!BffilIli31EE3GI BEHHii!BIHIMI;IDriiE!IBlikliriHHi1IIBlWJJHHIEEihi REHiliH3fliiiifENHBitiMi1EiHfRiiEEfEENB1EliM BiiHEMIEMneIE! IPR 2M{EfiM61sElliiEFif fRIHElfffMEEEERHiBMtIEE4 iib 3EIEEE&iiii!M Unit 1 - Amendment No. +M Unit 2 - Amendment No. 4H 15.7.8-1 Januacy -?.5, 1000

i 1 EnmJn6T6ii3 Eta!amandirleamiliMJBathmIissREE i L61!Iiii1MIAMJiiiDiiiliEHiiii0iidiliiiDuiiramewr ini EDiiiiliiliiiliiiGiiiiiiiiRfARGiiifMBaum9Ramtmnpif3il lilih09AliiiilEliffiilksAmmEdlilN5iilliiliamss!saHE%fffsiB5! iiiifinnemKuniiiiiiiiiiBiEf!iEiilifeleNRMIGiWIEG l Niiiidiil l liBEtaneamiersrmnaismajirporteammittipiralisiiiEIE garturagigginggiigagitsMirima3re Miltiliiiiiir#31iiill3iiiifJEEEiWiiffiliiilHEtifinuiiiitil l IliiiiMiBRMiiiiHii]DDD3iliiHiiidiliiiifMBETai! HiilMMiliiEdiiliBaitBailidiEGigiiiiiimidiii?fENEdiit l liEMiliiEiiiil3Hiii81Hii!IfMil10mitpilINiiEHHin?IHi i NisiiiE5KIBlaiisili3EiiVEiiiiiiiiKWHiiifISEMMill IEgiNwesi1MINnuluC@i1FinEibM FliHMiisiitt3I6iTmE9M!TilihiiBWedli?1MiliiiE8 liiBiliiltlitiiSJiiffd2iliiiXBIiiiMiliiniit gifLRiiiigBigf61IttngiigcH1HnnasranJlliiiiigI(egnEMARIntM idii1EHiiM3EittiE0Hiiiif5M11siiRiiiiEWiifdili!M l REiiiiifEEiliiiDililNsiifEfEEBHWlTriliEtINs@li liiEiihiHHiiMIMIBDIan36iiEfiiBlii~ Etf91F9 fit 0TsliEEil i tiiFliiiiligtiliiisiliisairttiirgs)M*armigiggIttis ElI6flBIDMMtHIFiHMilinEDiE553?ifilHiDi l DisinnHI ITII2FIM55 Elf 6HIUNiifTRElDBEI(I5EfdijiiE91@il liiiiBBBIfffillEliEUBEfiEfilisilff!3HHBIIXf HEIBM2iffiliit!E~fHiinifsiiHiiiDinifiT6iiiiiiiiiiiifD i

EEHelii!LhitttBEGIgli iggaasitigsg!Hiiggi; UTS11MfRGiDHTHii!KtRitiEEif2rRfeiffMN#1rili lilif0BBI!

METiliiilBBliEfFif1EISEE6TRIBiTfeIE5EifG iiERfilfEEGIElB3si1HiEB1EIEIDEiEEIEiWiBilff 1HfINGREDE!!EffMIENflyfflgjQijlEggfJEJEgj 13EttIIIfl#iiBEMEtMIEEEEif3!I(Fg{M$gl{ HEEWifiRIEreIEIBIE#iBiliiiEiiiiiBIIII!ElifiliH DIsiTRI!EiEiiBI3f3tS3T6!IlisI5iili MMEEEIMERH l 1 Unit 1 - Amendment No. M G l Unit 2 - Amendment No. H3 15.7.8-2 A = ry 25, 1"SS l

$ 1 @~Illiierdif$lyIf M M " M U E EITil d disiiYlill HiilfEEEiDMi105EiGEEii3iilDiBilastansEIEli EUEgigxiiiiipiiw, efsimiimiiggagt=*rgg RiiisRHigimEraniffRWgmiipwaiiniREMUE1H sesMiliCHi31ili3MI L N 48Bai20lil2Ct5iMEJNIBBEi i liBEllilimiiilEEEiiiiiETt imiX3HEmmaEiWil'2DENiiiii2 liHIGEtif4NDaanapiniEiDiEGiDJEliB NIHEEli3EliiDIiiiiiiiSTfE1FREEMMiiEt1 REM EfhgiggigniailrMEG2sresMllil5EFrifiil3M IDEREFBlii3fiRTRii!M i The ^OM : d th: PCP :h:ll b; ::t:blich:d : d :: int:!::d in 1

: rd = : eith the pr vist::: Of :p::ific: tic 15.5.0.

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. d :nvir: = =t:.1 :: niter 1:g :h:11 bc :ddr::::d i th: 03:1ity A::: = :: Pag==.

15.7.8.4 RETS Reportina Reauirements The following written reports shall be submitted to the Administra-tor, U.S. Nuclear Regulatory Commission Region III with a copy to the Director, Office of Inspection and Enforcement, USNRC, Washington, D.C. 20555 within the time periods specified. A. Annual Monitoring Report i A report covering the operation of PBNP for the previous twelve ] (12) month period or fraction thereof, ending December 31, shall be submitted by May 1 of each year containing: 1. $fg IEN5lEEMEXEMiiiiiiBIECifTd!1H?fiH HHHEsiisiHERDiHHMEDEHERDEHiH HlilliEffiliillimliiEBEdf6TFBRSI!!! liffiWRiiiMEsiillifEHfENiiBHffHi EffWd_BEw_EIDD_CHWd? REC _M_Ta_FN_silisiifs_i_fT_BE_tV!_B_ H m m W S Inf: = tion r:1 tive t; th: q::ntitic: Of liquid, g:::: s

nd : lid redi ::tiv: effluent: rel::::d frc: the f::ility, :nd efflu::t vele::: : d in :: int:ining the l

Unit 1 - Amendment No. MB 15.7.8-3 Unit 2 - Amendment No. ISS July 5, 1005

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y... r, 2. New and Soent Fuel Receipts and Shioments a. Number and type of new fuel assemblies received during the reporting period, if any. Unit 1 - Amendment No. 463 15.7.8-4 Unit 2 - Amendment No. i.c.e e,

i. n. n. e.

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4 a t b. Number of spent fuel assemblies shipped off site during the reporting period, if any. j 3. M Nii!aerJs14mlTfBliM#iirsifEMWJ#E8iEDH liiiniutsurmrisgrgrdsmtiingirstgstng Whats#etBelHiFIEtERHarsiEEHiDs~a~sDDM E EBiE E Ef##R E 9J R OM r..a........, u......:..

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..J ..r.. 7.. A..L. L.. j b. ^ :"- try Of : rv y rc: lt: duria; the r:p;rt'ng 4 p:ried includia; ; ::::::t :: : y :i;r.ific::t p;rtic: af the operati:n:1 Envir:n=:ntal M: nit: ring Pr:ge - j

t :: de:ted.

l l 4. Leak Testino of Sealed Sources Results of required leak tests performed on sealed sources j l if the tests reveal the presence of 0.005 microcuries j l or more of removable contamination. 5. Meteoroloaical Data Meteorological data shall be kept in file on site for review by the NRC upon request. The data available will include wind speed, wind direction and atmospheric i stability. The data will be in the form of strip charts 1 or hour-by-hour averages stored in electronic form for each of the parameters. l 6. 00CM : d PCP RENtKP Chanaes A description of changes to the [$M, ODCMk3g@y ] or PCP which were implemented and became effective during the reporting period ]@K$fs~nl@lt~@ l Unit 1 - Amendment No. 149 15.7.8-5 i Unit 2 - Amendment No. 1&& Oct:b r IS, 1991 1 i 4

MIEMII[$1flE5DEE21E2 Ih; dC 7iPtiG 6 11 includ: = ffici::t inf:; :.ti = t: =pport the r:ti:=l: f:r th: 0h=;= =d : d:t::-inti= th:t th:

h=;: =ill =t 7:d::: th: :::r:11 :ffectiv=:= cf th:

"C" Or S M. f:r th: S M, thi: titt:1 til i=1ud: r;;i nd 000" ;;;= :.ff::t:d by th: 0h=;: id=tified with : revi:i= ":r =d :ppr ::1 d:tc. 7. Snecial Circumstance Reports In accordance with note 7 to MQl Table 15.7.21 $ a. [, if the Waste Gas Holdup System Explosive Gas Monitor is out of service for greater than 14 days. b. Inaccordancewith15.7.7.B.23hE@,factorswhich render the LLDs :t:t:d in T:bl: 15.7 7 2 unachievable. In accordance with 15.7.7.E.2 K E g, failure of c. the analytical laboratory to participate in an Interlaboratory Comparison Program. B. Measured Radioactivity Above Notification levels If the confirmed level of radioactivity remains above the notification levels specified in Tame 15.7.7 2 Of :p::ific:ti= 15.7.7 "Op:r:.ti:=1 5 vir== t:1 ".=iteria; "r:gr="[tJe]$, a written re-port describing the circumstance shall be prepared and submitted within thirty days of the confirma-tion that a notification level was exceeded. C. Radioactive Liauid Effluent Treatment If the radioactive liquid j y y j M effiuent treatment system is inoperable and liquid [(fE{sosj effluents are being discharged for 31 days without the treatment required to meet the release limits specified in E:: tin 15.7.5K@j $Q], a special report shall be prepared and submitted to the Commission within thirty days which includes the following information: 1. Identification of the inoperable equipment or subsystem and the reason for inoperability. Unit 1 - Amendment No. 97 15.7.8-6 October 10, 1905 Unit 2 - Amendment No. 441

2. Actions taken to restore the inoperable equip-i ment to operable status. 3. Summary description of actions taken to prevent a recurrence. O. R: die::tive C:::::: Effluent Tre:tzent If the r:dic::tive g:::::: affl; nt tre:t:ent :y:te= i; in Op;r:ble :nd g ::::: Offl; nt; :r: being disch rged for 31 d;y: eith::t the tre:t: nt r q:f r:d t: :::t the rele::: li it: :p::ift:d in Secti:n 15.7.5, : :p::ici rep;rt :h:11 be pr:p;r:d :nd ::b:itted t; the C:::i::ica withir, thirty d:y: which includ:: the felle ing infer : tion: 1. Identific: tion of the in:per:ble equip ent er ::b y:t =

nd the rc :en for in per:bility.

2. Actier.: t: ken te rc:ter: the in per:ble equipment t0 Oper:ble :t:t;;. 3. !"- :ry d::cription f ::ticr,: t: ken t prevent a feeeeeeeee r $G. Radioactive Effluent Releases If the quantity of radioactive material actually released in liquid or gaseous effluents during any calendar quarter exceeds twice the quarterly limit as specified in S : tion 15.7.53@j]$$,aspecialreportshallbepreparedand submitted to the Commission within thirty days of determination of the release quantity. 15.7.8.5 Maior Chanae to Radioactive Liauid. Gaseous and Solid Waste Treatment Systems Licensee initiated major changes to the radioactive waste treatment systems (liquid, gaseous, and solid) shall be reported to the U.S. Nuclear Regulatory Commission with the annual update to the FSAR for the period in which the major change was complete. The discussion of each change shall include: A. A sumaary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59; B. Information necessary to support the reason for the change; C. A description of the equipment, components and processes involved and the interfaces with other plant systems; i l Unit 1 - Amendment No. 97 15.7.8-7 Oct bcr 10, 1985 Unit 2 - Amendment No. 101 i i 1 l

D. An evaluation of the change, which shows how the predicted releases of radioactive materials in liquid effluents and gaseous effluents and/or quantity of solid waste will differ from those previously predicted in the license application and amendments thereto; E. An evaluation of the change, which shows the expected maximum exposures to an individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; F. An estimate of the exposure to plant operating personnel as a result of the change. I MI7I# ICE N - $393ii[IENNIIIEf97filiaffil!!EffiniiHfiigETf!5sIMIMI F3n HiTWf3DiiiiEiM8fEsmseIEDTffMTin@LMM NIirslii1NIf5MIENidiEEfffBliHBitiliDEHER visiggiJriffsiis3KniiaiTFdiEEGH $788[EREMHsili M iliEXEsiE M PiFiliE HMENRKiMrdi11NdiEEsig!IiMrissiRIIR - HECeffiliffl6liiilWiiHlillfiffilaiEEEUNfslif6ilIH EHiE!UFilmimigN6Essureggg11mm EBifiMKliE3ittiiMEX@Hi2IMHiisl!!iHbH HEB15iinifEinliiHYiBE1Hf1HDnilff1H HiEHinitill!2ill gardaregliisissimatiniigrgggiigitnriis'figigg ENH1H9deramMEliHMIMEingEM isiiHfETiiElBiiiiiEMf!IBEf3HEEEiME HEEINasifiistifliB1 EmillilWIE11E!i osIsifiEHi1RHHEWENB s HE M E E31iii[8Muir M E E lfifflia NE5EIEEi3lNNEEE E3?iHIHEEfMKWKMEM E E E BJi!ENER8E M E91I3fiO M 1511H!! R!H E EfR IiBJfB E iH fi N BIifi M E! E I R!I Unit 1 - Amendment No. 97 15.7.8-8 Octatr 10, 1035 Unit 2 - Amendment No. M1-

<,,o Ef05EAMist9 Hit 96EANNI((ISIEIAN@10E tW %Q yh-W.D-Y A R E iG9N'%W$(DA Edd$fff05IIIf5f0NIUIDIIfi4MPPLr(I{$Maig LEEE E Eetatee M EBTEE H i H i D i H Id H D E ttEC BET II E a l B J hT5f61setefEMMMEuns3fforKliEig IEEEGRHRIBEWUse~if9EElliHHH5! einnsnEEH3fm1 HIE 93ffEDIEMiHM IIEEEMfJiBEEMI E3HEEEs~s~GIfEfEtisR5ffwMEBl%TJ1E Mi18iHi!E!IL*TaiHE M II!E E f E EHi M fH HiNHiEM2 USSistiiMMEfEGHE!EIEtHilFIEffsifli .-,N Eiel!9 M #lE9PJAP81;4ete djrgig3pyp ie M ar g,g E99RA j EEEif]IEI?HffREt.riMEsi!E)INEf13BH BEE HIfR TI E K rJ H EfB E N ER E M I M 51CDI N CIB M H6 M ifEEE E E I E lfd Hisi M f G D i ffA EIsi H E N i!I E M IaI E i1 E B i ElHHHILHEiWiMTJt iEiHEWifEEE@iKE!ES HiHD E IHIG E E E E M tBIEIEIH _ _ i _j i g g_ s, _! d _s!pl _g i _g h,j,;j j Leg

YiMihTiddffT5iD"tbTi_fi_iisilitii6iniSIIHWiii"g*.i'sIFijli~rd._liij r-e] -+he<mww gM stgg@<m f w el<.wM~<ms[ 7!-;**prpsg*!$g

- a-w 4 m gp pj jga&

3L ima 31y aj g1$1 9 3 Unit 1 - Amendment No. 97 15.7.8-9 Oct;ber 10, 1985 Unit 2 - Amendment No. 401

m This binder contains manuals that are either new or have been revised to contain material removed from RETS pursuant to GL 89-01 and GL 95-10. The following manuals are enclosed: Radiological Effluent and Materials Control and Accountability Program (REMCAP) Manual Radiological Effluent Control Manual Environmental Manual Offsite Dose Calculation Manual -}}

ML20108A001

Contents

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ML20108A001

Text

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