Text

Responds to Civil Subpoena Re M Akings Et Al.Chronological Sort of Dbase File Created to Account for Documents Released Encl
	ML20055E298
Person / Time
Site:	San Onofre, Rancho Seco
Issue date:	04/13/1990
From:	Yuhas G; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Blume M; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20055C206	List: 05000206/LER-1989-006, :on 890320,since Regenerant Holdup Tank a Release Lasted Approx 4 H & 25 Minutes & Required Flow Estimate Not Performed,Release Constituted Tech Spec Violation.Caused by Personnel Error; ML20055C205; ML20055E282; ML20055E293; ML20055E298; ML20055E301; ML20055E304; ML20055E305; ML20055E311; ML20055E315; ML20055E321; ML20055E334; ML20055E345; ML20055E367; ML20055E375; ML20055E380; ML20055E399; ML20055E401; ML20055E491;
References
	NUDOCS 9007110267
	Download: ML20055E298 (95)
	v • d • e

{{#Wiki_filter:- - - - ~~~- hPR 18fn3 MEMORANDUM FORT Michael Blume Regional Attorney FROM: Gregory P. Yuhas, Chief Energency Preparedness & Radiological Protection Branch

SUBJECT:

RESPONSE TO CIVlt SUBPENA REGARDING MICHAEL AKINS, ET AL., PLAINTIFF, VS. SACRAMENTO MUNICIPAL UTILITIES DISTRICT March 21, 1990 NRC Region V made availeble all known agency On Wednesday,in the regional, office or archived from the regional office, records held to representatives of both parties. Mr. S. Mackey of.R. Parker White, Friedman, Collard, & Poswall, for the plaintiff and Mr. F. R. Laupheimer of Crosby, Heafey, Roach & May for the defendant reviewed the documents and identified those items to be copied by their contractor, Glen L. Sharp of Legal Photocopy Service. Our Mrs. Moller-Duck developed a record of each document that was copied. Attached you will find a chronological sort of a dBase file we created to account for the documents released. Many of the documents relecsed are from archived records which.we are currently holding in Ray Fish's old office. We would like to return these records to headquarters as soon as possible. Please advise me if you would like us to retain these records, or if we need to make copies of averytning that was released. Also, do we need to provide copies of any of.these documents u the PDR? Chief Gregory P. Yuhas,dness & Radiological Emergency Prepare Protection Branch Attachment as stated cc: H. Wong Docket File 50-312, Central File RV/gmd GYuhas 4/ /90 REQUEST COPT"3IDDI3 TID)QIDDIST COPY j RlhbI3TIDPY j RlhDI3T COPY ] YES_ /_ N0_ _ YES /_ NO ; YES_ /_ NO ] YES /_ NO ] YES / NO A llNNPDC )Ob$0$$5}$$8888Phhg t Y E_S_, / NO-o P

h 4 i e Pope D. - 1 C/26/90 RANCHOSECOAt!NSSUBPENA RE610N V DOCUMENTS PROVIM D TO R. PARtER NHilE, FRIEDMAN, COLLARD 4 POSNALL AS OF 5/30/90 SUBJEtt TYPE DATE 10 FROM AUTHOR PMi190 RULES /RE65 800tLET 01/13/77 NRC Rad Progra Fed Regist ' RAD PROT STMDARDS 800tLET 01/13/77 IMPLEMENT 40CFR190 INFORMAll0NRPI 12/07/79 COMISSION DENTON i NUNE60543 DIRECTIVE 01/01/B0 NRRICON6EL RULE Mt!No 40CFR190 CONS.CALENDARITEM 01/28/90 COMISS10N R MIN 060E RESPONSE 40CFR190 MEMD 07/07/B1 Hl661NB0fH PA6E SAME RESPONSE 49CFR190 MEMO 07/29/B1 ElBSONRll HIGE'NBOTH SAME P t 20 40.202(B1 09/02/61 RAD.MSit PROTECTION RPT 07/22/B2 NRC PMI50 STATE OF CONSIDERA1. 09/01/82 PROCEDURE CH6 FORM FORM FOR STAi!0N 1 01/07/B3 M61 SAFEif SMUD MELTON PTR REV. CDM. MTF. SMUD OFF. MEMO (CDPY 02/14/63 PRC MEMBER R. DUBRE' S.L. CRUNE PMi 50 LICENSIN6 APPH41 05/31/83 MENMENT 53 DPR 54 LIR 02/22/84 8iMUD RODR16UE! MINER /LIC SMM MA!.. FISH SAMP MEM0 04/19/84 FILE D312 FRPS H NORTH Sl ?!FICANT MI6 NOTICE 04/30/B4 ATTENDEES MC SCARAND mig NRC/SMUD 5-04 84 LtR 05/14/84 WC/MARi!N SMUD RODRIGUE! COUNi[RPART MI6 $UM. MEMO 05/18/04 OlSTRIB MC/0RP8HO CUMIN 0HM PWO V-84 20A PRELIMINARY N011F. 05/18/84 MC EPRPS/RV YUHAS RE0/IECH ASSISTANCE MEMO 05/10/04 EISEMUT DRSS SCMANO ENVIR.MONiiOR.PR06. RPT Ms21/94 MEDIA REPR SMUD/P1 J MRI ' MORN! D RPi/SMUD N0ilFICAT10N 05/21/94 I MORNID RPi/ CORRECT RPI 05/21/04 INTDISTRI WC/RV WENSLANSil I'*t INTERFACE AGREE RPT M/36/04 - MC SMUD 6 HOLAHM l SPEC INSP/IECH mig COPY OF LIR 05/31/04-SMUD. MC/RV NCNSLANSKI TASK 684 39 INTERFACE RPT M/01/M. MC SMUD 6 HOLAHAN CSCONCENTRAi!DNS LTR M/01/04 PowersSMUD Liversore Victor l-LON Linii 0F DETECT. APPROVAL FOM ' 07/95/04 M61RVN BOWSER SMUD 140t 684-39 TAC 55038 EMO 07/18/04 NILLIS NRR NRC/ RAPS YUHAS-CO TECH AS$1 STANCE MEMO 07/20/64-Eisenhut DR$$/NRC Starano PNO-V-84 45 PRELIM!MRYNeilFIC. 07/27/84 INTERNAL NRC/RV YUHAS l-MC INSPECil0N 84 LTR 07/30/04 SMUD NRC/RV SCARAND l 0 IECH SPEC ~RPiL10 EFFLUENTS 08/01/94 MC RMCHO SEC SAME M0Ml ] RPi/RV RPI 08/23/84 INT DISTRI WC/RV CILLIS r i INSP 50-312/64--08 LTR 08/30/04 NRC/ MARTIN SMUD RODR16UEl MORNINGRPT/RV RPT 06/31/B4 INT DISTRI MC/RV NENSLANSKI 14C55038LIOEFFLU. MEMO 06/31/04 LAINAS/DL MULLER /DSI SAME PNO-V 64 60 PRELIMIMRYN0ilFIC. 09/04/04 INT DISTRI WRC/RV ECtHARDI RAD. EFFL. RELEASES LTR 09/10/04 SMUD WC MARilN l . COMPLEi!0N OF TASK E439,MEMD 09/10/04 BISHOP DRS NRR/LICENS EISENHUT ' MORNIN6 RPi,$ MUD RPI 09/11/04 INT DISTRI NRC/RV YUHAS -SliE DATA 40 CFR190 MEMO 09/19/04 FILE 50312 RRPS/NRC YUHAS i HI C00LMT ACTIVliY - MEMO 09/19/04 EISENHUT Div 0F LIC BISHOP l CTICE OF SISN MI6 NOTICE /SMUD 09/20/94 ATTENDEES NRC/DRSS SCARANO l SPEC RPi 84-07 LTR 09/27/64 NRC/MARilN SMUD RODRI6UE! = RESP ENSR EVALUA110N. MEMO 09/28/04 BISHOP EISENHUT DIV 0F LIC a . RPID DOSES IN EICESS MEMO 10/02/84 EISENHUT DRSS/RV SCARANO i in$t INTER 604 39 MEMO 10/05/04 EISENHUT DRS$/RV SCARAND l 1. J

l Page' O. 2= iC/26/90 RMCHO KC0 At!NS SUBPENA RE6!DN V DOCUMENi$ PROVIM D [ 10 R. PMtER NHlit, FRIEDMN, COLLMD 4 POSWALL AS OF 5/30/90 SUBJECT TYPE DATE 10 FROM AUTH0R ] L TECH MI6 09-20-84 MEMO 10/10/04 FILE 50312 NRC/RRPS YUHAS tPNO-V-84-67 PRELIMIMRY N0ilF. 10/11/04 INIDISTRI NRC/RV L.' MILLER UPDATE RS DDSE ISSUE MEMO 10/12/04 J MARi!N DRSS/RV SCARM0

SUMMARY

/LIO DOSE ACT MEMO 10/15/84 DOC 50-312 WC/DRSS Yuhas CilCEOF$16NMT6 UPDATE 10/16/84 AllENKES NRC/SMUD SCMANO IECH mig 10-1684 MEMO 10/18/04 FILE 50312 RRPS/RV YUHAS

'RE8TECHAS$1 STANCE MEMO 10/23/84 81 SHOP DIV0FLIC EISENHUT TEMP PROCEDURE CH6 FORM 10/25/04 PL1 RVN C0 SMUD CAMPKLL J C3 GENERAllN6 STAT. MEMD 10/26/04 MYERS ORP US EPA DUNCM EFFL. ENVIRON. STUDY LTR 10/30/94 WC/MARilN SMUD RODR16UEl -TASEINTER.A6REEENT RPI !!/02/94 INTERNAL MC Bishop -CONF ACTION / STUDY LTR !!/08/84 SMUD/RODRI WC MRi!N TASE 1, 949468 LIR !!/08/04 NM6LER DAt RIDGE MILLER . LCID EFFLUENTS L1R !!/09/84 J AYRE HC J STOLI-CALCULATEDDOSES LIR !!/15/84 SMUD WC LAINAS NHOLE 90DY COUNTS LfR 11/15/04 YUHAS UC KREELE SAR6ENT TASE AGREE. 84 80 MEMO 12/10/04 EISENHUT DRSS/RV SCARANO MR TECH RPi MEMO 12/19/84 DISTRIB OWR KNTON 3 CONVERSAi!DNRECORD TELECON 12/21/04 E BRADLEY WC RV NENSLANSKI RW PATHNAY l SURVEY. MEM0 12/27/04 flLD0-312 FRPS YUHAS RADIONUCLINS/NATER UCID20295rpt 12/27/84 INTERNAL LAMENCE LIVERMORE r RS LMD USE ISSUE KM0 02/20/85 FILD0312 FRPS YUHAS M16, LMD USE CENSUS MEMO 02/22/95 FILE 50312 _FR[S YUHAS - I PROCEDURE CH6 FOM FORM-02/27/85 M61 SAFETY SMUD BJORK l MC INSPEti!ON 85-03 LTR/RPi 02/27/85 SMUDIRODRI MC/DRSS Scarano STATUS OF LRS RECOM. RPT 03/11/85 NRC SMUD SAME 1 NRCISMUDMiG3/12/85 MEMO 03/12/85 RODR16UEl SMUD-SCHW!EGER l PNO-V 85-17 PRELIMINARYNOTIF. 03/15/85 INTEMAL - DRSS/EPRPB YUHAS l RS CHEM / RAD LO6 SMUD10760 03/20/85 COPY SMUD f l 64MMA SPECTRUM ANALYSIS 03/20/05 SMUD A. RHUT l l, RS CD. REL. PEMit

SUMMARY

03/20/85 SMUD DUt!NSON i i DOSE ASSESSMENT MEMO 03/21/85 CON 6EL NRR EPRPB NENSLANSKI l PE C I D CLASS ACTION MEMO 03/27/85 BR166S RE6COUNSE SHOLLENER DOSE ASSESS. TAC 56033 MEMO 04/11/85 CON 6EL EPRP8 NENSiMSKI EVAL /RS EFFL RELEASE PREPUSilCAil0N COPY 04/11/85 NRC-Dat Ridge-Nat'lLat, M0M ID RPi/SMUD RPI 04/26/85 INTERNAL RV f o L PNO-V-85 17A UPDATE-PREllMINARY N0ilF. 04/26/85 DISTRIB DRSS/RV YUHAS COPY /RSREL. PERMIT ENCLOSURE 4.1 06/04/85 UNDISCERN. 'FL Q C.1E/H16H ALARM CHART 06/04/85 UNDISCERN. i L RS CHEM RAD LO6 CHART 06/04/85 SMUD 00760 RAD.AELYRPi(21 COL. 4:20 4 5:19 pe 06/04/85

8. RHUT 6MMA SPEC ANALYSIS RPI 06/04/85 RS CHEM / RAD LO6.

CHART 06/05/85 SMUD00760 P6 789 o l NRR SALP RPT MEMD 08/06/85 tlRSCH NRR S MINER l 'CONVERSA110NRECORD FORM 06/06/85 F KELLIE 6 YUHAS L DOSE ASSES. IAC56033 MEMO. 06/14'85 CON 6EL EPRP8 NENSLANStl . SAMMA SPECTRUM ANALYSIS 07/13/05-SMUD 8RHUT DOSE ASS./ BEEF RS MEMD 07/17/85 FILE $0312 FRPS YUHAS l

F y L 4 - Pepi hoe 3 86/26!D R MCHO SECO AtlWS SUIPE M RE6 ION V Docun[NTS PR0ViK D TO R. PMLER NHliE, FRIEDEN, COLLMD 4 POSWALL AS OF 5/30/90 SUBJECT TYPE DATE 10 FROM AUTHOR SEP,RSi12/83 seso 07/19/05 Distrib. . MC tirsch C3SALP12/83-5/85 eeen 08/01/85 Montgomery H0 McCortie IACK8R INFO FOR LECH-MEMO 08/02/85 UNMRWOOD MC/DRP Chaffee ASSESSMENT RAD CONTA MEMO 03/07/96 J STOL! ' EPRPBRV WENSLM$ti INSPEtil0NRPi/SALP RPT 08/07/85 SMUD NRC Myers/ Mill SEP MEMD 09/09/05 SMUD/RODRI MC RE6/AD JMartin IRANSMlfi R/RS SALP MEMO 09/17/85 i REM NRC/RV Martin 'SALP Lir 09/25/85 SMUD/RODF.! NRC/DRSP Kirsch .t SEMIEFFLUENT RPI LIR 09/26/85 NRCRV SMUD R08R100E! PROCEDURE CH6 FORM FORM 10/04/85 M61 SAFCTY SMUD 8JORK i AtI3 VS SMUD ltr 10/04/85 N160taus 6entounsel DKaplan thNSFER OF LTR ' LTR 10/09/05 J MARilN SMUI Nishieura RESPONSE 10 SALP LTR 10/17/85 J MARilN SMUD .Rodriguer AERIE RAD SURVEY RPI !!/01/85 NRC DOE E666/EM l INCORP SALP 1NSP PRO MEMO 11/06/85 tirsch RPS11 Miller RADIOLC ICE SURVEY RPI !!/14/85 NRC SEP TRMSMiiTAL MEMO !!/15/05 Taylor / dis: NRC/RV JMartin i SALP COMECTION LTR LTR 11/21/85 TaylorCIE NRC Reg Ad Martin SALP ltr 11/25/85 SMUD/Rodri' WC/DRSP tirsch E71/REVIENRPT LTR 12/09/05 N.TIPION MC NENSLAW$ti THANK YOU REV SURVEY LTR 12/09/85 NTIPTON NRC/EPRPB Nenslausti i ... /INSPFEED8Att MEMD 12/10/85 MIRA6LIA DRSS SCARANO l !~ RS LIO EFFL STUDY MEM0/RPI 12/12/85 J Martin SMUD Rodriguer 10CFR 50 DEFINITION INTERNAL MEM0/SMUD 12/16/05 POWERS IRADLEY SMUD

6MM SPECTRUM ANALYSIS PMAMETERS 01/01/86 SMUD AU011 0F SALP MEMO 01/06/86 klRSCH DRSP 6fibert RAD STUDIES /RS RPT 01/23/86 NRC LIVERMLAB NOSHilNET

BAMMASPECTRUM ANALYSIS 02/05/86 SMUD 1

RAD STUDIES /RS RPI. 02/06/86 NRC LIVERM LAI NOSHKlhEi j R$TECHSPEC.4.21.1 MEMO 02/11/86 MINER /LIC D/PNRLIC CRUTCHFIEL' BAMMA SPECTRUM - MALYSIS PARAMETERS 02/13/96 SMUD [ 9PRCliRANALYSIS H20 LTR COPY 02/24/06 S MANOFSKY SEE BELON 8IATES STAFF ASSESS /CONTAM. MEMO 02/26/86 J STOLil PWRLIC RE6M 'I RELEASE EFFLUENT RPT LTR 03/03/06 NRC RV SMUD RODRIBUEZ ' BMMA SPECTRUM ANALYSISPARAMETERS 03/05/86 SMUD I INSP RPT 86-11 RPi/ COVER SHEET ONLY 03/06/06 Cillis REV SCH SALP BD MiB MEMO 06/09/06 DENTON RES ADMIN J MARilN RS CONTROL RM LOG. LO6 416163 03/10/86 SMUD i .RS CONTROL' M LO6 116175 03/13/06 SMUD . HT6 CilCE LIO EFFL. MEMO 03/10/86 DISTRIB D/PWR LIC LALMAN RELEASE /CONIM.EFFL.~ HAM WRiflEN NOTES 03/21/86 GPY ' RE0 CHK 154.21.1 RS MEMO 03/26/96 DISTR NRR DHFI/NRR N. RUSSELL INSPEC.FlELDNOTES HAMWRiffEN 03/27/06 6Yutas INSP RPi 86Ll3. MEM0/FAI 03/28/06 i MILLER PEREI WC INSP RPT 86-06 LTR/RPI 03/28/86 SMUD/Rodri NRC/DRS$ Starant DISPOSAL EFFLUENTS LTR 03/31/86 NRC/MARi!N SMUD RODR16U.!! NRR Mt6, 3/25/86 MINUTES /MEMD 04/01/86 SCARAND EPRPS WENSLESt! 'LIOEFFL. SPEC 4.21.1 MEMO 04/07/06 FILE $0312 NRC/ FRPS YUHAS

o Page C. 4 66126/90 RANCHO SECO AtlNS SU9 PENA REGION V DOCUMENTS PROV!M D i i TO R. PARKER WHITE, FRIEDM44, r i COLLARD 6 POSWALL AS OF 5/30/90 l SUBJECT TYPE DATE 10 FROM AUTH0R ENCLOSURE 1 LIR 04/06/06 MANOFStY C.E.P.lNC. J.MUELLER O AUDji 0 770 RPI 04/11/66 SMUD SPEC INSP RPT B6 15 LTR 04/17/B6 NRC/MARilN SMUD RODRI6UEZ TELECONSN/NRC CONVERSATION RPi FAI 04/21/B; YUHAS RANCHOSEC PE!El INSP RPI B6 13 RPI 04/21/B' NRC J NYN ANALYSIS /8ASIN MEMD SMUDINTEROFFICE 04/24/86 E BRADLEY SMUD D. Kahn REOINTRP.4.21-1 LIR 04/28/06 BUTCHER WENSALWSti SAME M C ENVIR. RPiS.- LIR 04/26/86 RODRI6UE! STOL2,NRC SAME CTEOROLl61CALDATA MEMO 04/29/96 STOL!/ Lit PWRLit CRUTCHFIEL A M UAL 85 OPER RPi LIR 04/30/06 J MARilN SMUD Rodriguet COMENT'ON LERS/SALP MEMO 05/01/96 PARTLOW DRSP tirsch T-621TRiflUM/1985 MEMO 05/02/06 R MILLER SMUD CAMPBELL SPECRPi66-00 LTR 05/09/06 NRC/ MARTIN SMUD J WARD ~ NRC INSP B6 07 LTR/RPi 05/14/96 SMUD/ Nard NRC/DRSP tirsch INTERP OF TECH SPEC EMO 05/16/86 PARR NRR Botcher ilA86-12FMINTERPR. MEMD 05/21/B6 PARR/PWR ISCS/DHFi BUTCHER T RVW PROP, 50-59 CH6 RPi/FAI 05/23/06 NRC/FRPS RS C MYERS INTERP SPEC /4.21.1 MEM0 06/03/96 KALMAN LICENSIN6 CRUTCHFIEL TIA 86 20 FM INTERP. MEMD 06/04/B6 WENSLAWStl PWRINRR STOL! SPEC RPI 86-06 LIR 06/05/96 NRC/MARilN SMUD J. WARD NRC INSP RPT 86-14 LIR/RP1 06/06/96 SMUD/ WARD NRC SCARANO W C INSPECil0N RPT LTR/INSP RPi 86-15 06/06/86 SMUDINARD DRS$/RV SCARANO INSP RPI 86-15 LTR 06/12/86 SMUD/ WARD DRSSRV SCARAND INSP REPORT B6 15 LTR 06/12/86 SMUD NRC/DRSS SCARANO ENFORCEMENT CONF. LTR 06/12/B6 SMUD/ WARD NRC/DRSS SCARAND SEMI-J EFFL RPI REPORT 09/03/86 NRC SMUD l REO REV RS SPECS NOTE 06/13/86 L 61L E RT NRC $ BURNS JEW 86-109 ltr 06/17/86 Martin SMUD Ward Ci/ VIOL. 86-14 6 15 LIR 06/18/86 SMUD NRC J Martin CilCEOFS!6N.MI6 MEM0 06/20/B6 AliENKES NRC DRSS ALLE6. FILE 86 A-048 MEMO 06/20/B6 FILE DRSS SCARANO - SMUD INSP RPi 86-23 INSPEtiOR'SRPi 06/20/86 FILE EPRP8/RV PRENER6AS RE0 FOR TECH ASST MEMO 06/23/B6 Maragila DRSS Scarano REV SCHED B5/86 MI6 MEMO 06/23/06 H Denton DRSP Kirsch SUMIRE6 PERF Ai RS MEMO 07/01/86 PARTLON DE RE6 ADMIN JMARilN MC INSP RPI B615 LIR 07/03/66 JMARi!N SMUD 1 INSP RPI 86-13 LIR 07/08/06 SMUD/ Nard NRC/DRSP Kirsch CSESS SALP 6/1-6/30 MEMO 07/08/06 Distrib DRSP Kirsch ASSESS SALP 6/1-6/30 seso 07/15/96 Distrib DRSP Kirsch NRCENFORCEMENTCOWr LTR 07/18/96 SMUD/ WARD NRC/DRSS SCARANO

INSPRPI8623 rpt 07/18/86 SMUD NRC Prendergas

~IASE INTER.A6REEMENT RPI 07/22/B6 NRR RVW EFFL TECH SPEC LTR 07/22/66 Nard /SMUD PWR/HQ J Stolt RVW SYS ASSESS PR06 LTR 07/23/66 FMiraglia SMUD J Ward SALP 6/1-6/30-86 REMO 08/07/06 DISTRIB/RV RPS/RV L MILLER OFFSlfECONTAMINAllo LIR 08/29/86 RICHARDSON PWRLIC KALMAN -THANKYOU LTR 12/24/86 SMUD/ WARD DRSS SCARAND RPTS/ AERIAL SURVEY-LIR 09/08/66 L Cohen E666 NJ Tipton

PM C.- 5 f/26ff6-RMCHO SECO AtlNS SUBPENA i RE610N V DOCUMENTS PROV!KD I 10 R. PAREER WHlIE, FRIEDMAN, COLLMD & POSWALL AS OF $/30/90 l 1 SUBJECT TYPE DATE TO FROM AUTHDR ) i EVALINSPP906SALP MEMD 09/09/86 SCMMO FRPS 6Yuhas RS IMPL DR6AhllAi!DN CHART 09/29/86 SMUD FAI TH M t YJU LIR LIR 09/29/86 (ALMAN ORP/NRR MEYERS SALP MI6 N/ LICENSEE MEMO 09/29/86 J Partlos DRSP tirsth t EA86110R$ RADIO. MEMO WIDRAFT N OF VI 10/11/86 JMARilN DE LIEBERMAN 0 CUR OR6. CHART CHART /FAI 10/14/86 6 Yuhas C Myers l ' CilCE OF VIOLAi!0N LTR 10/28/86 SMUD/ WARD MC Scarano - REO FOR TECH AS*.i. MEMD 11/06/86 (ALMMILIC PNRLit CRUTCHFIEL . iRMS/SALP RPI 4 REC MEMD 11/21/86 MARTIN RS SALP 80 CHAFFEE INSP RPI B6 14 - LIR 12/01/86 SMUD/ Ward NRC Scarano FA!/LALMM - R$ ROUTINGSLIP 12/19/86 YUHAS EPRP8 NENSLAWSKI ASSESSMENT OF PERF LTR 12/19/06 MAR 11N SMUD WARD GUSMITIAL OF MANUAL L1R 10/20/87 MIRA6LIA SMUD CONARD + JEW 86-982 LTR 12/31/86 Martin SMUD Ward 01 BCHED. RS INVEST. , ROUilNE SLIP 01/14/87 SCMAND EPRP8 NENSLANSK!- AS E SSMENT OF SALP ~ MEMO 01/23/87 DISTRIS RE6 ADMIN JMARilN THANE YOU LIR 01/23/87 RS/ Ward NRC/DRSP Chaffee INVEST. INTERVIEW ORER/PI.38,42,44,47 01/26/87 SMUD NRC MEttS/NRC 'JEI N :2, 87-14 1tr - 02/05/87 M;rtin SMUD Nard INSPECil0N86-42 LIR/RPi 02/19/87 RS/ Ward DRSP/NRC Cheffte IHMt YOU LTR 02/24/87 RS/ WARD NRC Scarano B. MOLLER PEllil0N LTR 02/25/87 NRC B MOLLER SAME R6TECHSPECUNIT1-ProspAmendeent155 02/25/87 NRC I 'RSLIOEFFL. ISSUE HMB NOTES 03/03/87 YUHAS p 'l#SPECil0N8702 LTR ' 03/03/87 SMUD/ Ward EPRPB/NRC Wenslavsti mig ABEN84 ' AGENDA /BAct0P MATER. 03/03/87 SMUD LER 87-020 FAILURE LTR 03/16/87 DCDHQ SMUD WARD N INVEST. INTERvlEW. ORER/EIMIBli31P. 03/24/87 SMUD/KELLI NRC l-INVEST.INi[RVIEW ORK R/PARilAL ElH 32 03/24/87-SMUD NRC/ COWARD- ' INVEST. INTERVIEW ~ ORKR 03/24/87-NRC EIHl81T 32 INVEST. INTERVIEW ORKR.EI. 21, PARTIAL 03/25/87 SMUD MC ' NRC INSP 87-08 LTR/RPI -04/01/87 RS/ Ward RP Branch Chatfee

INVEST. INTER. PApi.

ORDER,E!H181135 04/03/87 SMUD NRC COPY /01 H ~3/87RSLIOEFFLUENT MEM0/ DOCUMENT 04/07/87 FILE PWR/hRR (ALMAN W JEW 87 586 SMUD letter 04/15/87 Miraglia SMUD Ward - MC INSP 87 11 LIR/RPi 04/20/87 RS/ Ward NRC/DRSP tirsch MTS

SUMMARY

DISTRI. LIST 04/20/87 6 Yuhas RS RT6 WISMUD RAD SPEC MEMO 04/22/87' KN!6HTON DRP/SP KALMM 'ASENDA-NCilCE 05/05/87 6Yuhas RS J RSTRIPRPT MEMO 05/19/87 CUNNINGHAM DRPEP 8 RANA 6AN/ % :INPui SAFETY EVAL RP MEMO 05/28/87 CRUTCHFIEL DRSP/RV tlRSCH PROPAMEND$155 LTR 06/D/87 MIRA6LIA SMUD AND06NINI l? 01 IN00!RY/ALLE6 RED MEMO 07/16/87 MARSH /01 CILLIS INHOUSE j. NRC INSPECT 10N 87-22 ltr 08/12/87 Andognini NRC/EPRP8 Wenslawski RS OR6 CHART CHART W/FAI Sheet 10/02/87 RS ' PROP AMEND 155 LIR 10/03/87 MIR46LIA SMUD FIRLli l 'RESIDISERTAC61635 LIR 10/07/07 AND06NINI DRRP/NRR CRUTCHFIEL REV. RESP 10 VIOLAT. LTR 10/08/87 Martin SMUD Anidogini e s 4

t.- PageC'. 6 06/26/90. L RANCHO SECO AtlNS SUBPENA RE6 ION V DOCUMENTS PROVIM D TO R. PARilR M!TE, FRl[DMAN, COLLARD 4 POSNatl AS OF 5/30/90 SUBJEC1 TYPE DATE TO FROM AUTHDR REOR6Mllni!DN/ Lit.. SMUD INTEROFF. MEMO 10/09/87 Directors SMUD 6eoCoward WORK AREA APPEARANCE INTEROFFICE MEMD SM 10/12/87 RSEmploye SMUD Firllt r EEY Pil mig 9 23 67 LTR 10/15/97 AND06NINI NRR MURLEY V10LA110N/EFFLUENis MEMO 10/16/87 NRC/MMilN 01 HAVES CT OF IWESil6AT10N RPf/ selected pgs 10/16/87 01 RV ENC /.UTOFINVEST. LTR 10/16/87 VToensing Ol/HO 8Mayes RPI 0F INVESil64f10N RPi/ COMPLETE 10/16/87 Ol/RV REVIEN OF PA 155 HMDNRITTEN NOTES / / 6tuHAS MMNRITIEN NOTES NOTES 10/22/87 J Martin 6P Yuhas saae RESOLUi10N EF CONCUR LTR 10/26/87 Andognini MC/NRR Knighton 0 01 RPI 5 06-010 MEMO 10/29/87 MC/MARilN DE LIESERMM COMMifMENT

SUMMARY

phaeplet 11/10/87 LIO[FFLUENTSYSTEMS LTR,frt sheet 11/12/87 MIRA6LIA SMUD Unknown R T OF EFFLUENTS REL MEMO 31/12/87 MRSH/0! DRSS SCMANO LIO EFFL PR06RM LiR 11/12/87 KNIGHTON SMUD MD06NINI 11/12/87 MIRA6LIA SMUD Andognini CFFLUENT SYS DESCRIP LTR, 11/13/87 6Yuhas SMUD SMUS/C C Mgt Mtg Booklet RESP 10 NV B7 26 LIR ~ .12/10/87 - MC/MARilN SMUD MD06NINI RS LEA 86 110) 1LMOl COPY) 12/11/87 NRC/MARi!N DE LIE 8ERMM R$EA86110 MEMO 12/14/87 DISTRIS DE LIENRMM REGFORINFDMA110N LTR 12/23/87 SMUD NRC RE6 AD JMARi!N RESPONSE TO REF 1 LTR 01/25/88 NRC/ MAR 1!N SMUD MD06NINI CRiflCAL ITEMS RPi' MEMO 1/1988 02/03/08 MURLEY RE6 ADMIN JMARilN SAFETY EVAL. OF CH65 MEMO 02/12/88 (ALMAN DRPEP/MR CONGEL ' LOCAti] MP/ SAMPLES LTR 03/01/88 YUHASINRC-DAt RID 6E COTTRELL '91RECi]'SDECIS10N DOCUMENT 03/18/88 MURLEY ' INITIATED CALL RPT FORM 03/31/88 Greg Yuhan Rancho Sec E Vochhele .0FFSITERADRELEASE CRITERIA,Rev0 04/01/88 Distrib RS Chi E Oft RS EFFLU. REL MEND. MEMO 04/20/88 R MARSH,01 DRSS/NRC R SCARM0 MOLLER/PEllil0N LIR 06/20/88 CRANSTON NRC STELLO j. 'WiiNESS/ COURT civil SUBPENA 337598 07/18/08 6YUHAS ATTYS. R. WHlIE .8 RACE VS SMUD-LTR/337598 07/27/88 P. White NRC Blume, Atty SECONDMV SW MANA6E. MEMO 08/29/88 Distrib. SMUD i PEilitC/8MOLLER LIR 08/30/86 NRC 8 MOLLER EFFLU.4 WATER M6T. PROJECT Atil0N PLAN 09/28/88 NRC. RANCHO SEC MELANCON j EFFL.lSSUE TIME LINE. HANDNOTE 10/04/88 YUHAS 'EA66 110 EFFL. DISC. eeno 10/11/88 Martin HQ Liebersen t: 84RIARA MOLLER/ PET. MEM0/EDO CONTROL 10/14/88 MURLEY NRC/RV JMARi!N mig N/SMUD EFFLUENTS MEMD 10/15/88 FILE 50312 EPRP6 YUHAS REV. LTR REDM-13 10 RADEVENTMANUAL 10/19/88 NRC RMCHO SEC PETITIC/8.MOLLER MEMD 10/20/88 MURLEY 6EN COUNSE CHMDLER i PROP.C ilCE OF VIOL. POLICYISSUE 12/09/88 COMMISSION NRC STELLO AGE MA/B4tt6R MATER. PROGRAM PLUS NOTES 02/01/89 6Yuhas mig N/ SMUD REL EFF. MEMO 02/06/09 FILE 50312 CPRP8 YUHAS RSREDTOAMEND.SPEE MEMO 03/11/89 6 KALMAN DRPEP/NRR Cunninghas tit 6WISMUD MEMD 03/15/89 SCARAND EPRP8 YUHAS PROJ FOR MR/RES LIR* 04/21/89 D'ANGELO BAllELLE MCCORMACK i .EF C'IER PROJ $1Airj SUMARY. 04/25/89 l i

e i Page C. 7. 2)26/90 RMCHO SECD At!NS SutPENA RE6 ION V DOCURENi$ PROVIDED 10 R. PMEER NHli[, FRIEMM, COLLARD 4 POSNALL AS OF 5/30/90 SulJECT TYPE DATE TO FROM AUTH0R t G LIO EFFL. ISSUE EVENTS BY DATE 05/01/89 .V10L4liDNS/ PENAL 11ES MEMO 05/01/89 ALEIRADIE ENF 0FFICE AJ0M60N WC M16 AlfE O MCE LISI/SMUD 05/01/89 COMENTS/MSTENATER FAI COPY /SMUD MEMO 05/02/89 8066S/SMUD FIRLit/SMU INTERML RiGNISMUDErtDENTS MEMO 05/04/89 FILE 50312 EPRPB/RV YUHAS TRMS. MEASURE. RPI LTR 05/12/89 SMUD EPRPB/RV YUHAS . COMENTS PROP. RULE LIR 05/12/89 EPA SMUD 8Croity LIC EVENT RPI 99-06 LTR 05/16/89 NRC SMUD FIRLli Dit RAD SURVEYS MEMO 05/18/89 R ORTHEN SMUD RUSYLEE COR. E MO 89 0454 EM0/ COPY 05/19/89 0.YONS SMUD R. ORTHEN CLAY CR AliERN4fl0NS MEMO 05/23/89 L. BURNS SMUD

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. S PROCEDURE MANUAL 09/13/89 SMUD R HOLLM POTENT. DEV 00AllIY R TRANS. DOC 14C69016 LIA 10/19/89 BAILEY DRP/NRR LALMM AE ND ll4/LIC DPR 54 LIR 10/26/09 KEUTER DARP/MR LALMAN MPS/Bett9R SAMPLES ltr 02/14/90 6Yuhas 041 Ridge NCettrell L COR/NURE6/CR4286 LTR 03/13/90 RSIKEUTER EPRPB/RV YUHAS . PASS H MONRiiTEN NOTES / / YUHAS LIO[FFLUENT

SUMMARY

TABLE 2 / / ENVIRONSAMPLEAtilV MEMO / / FILE RS NRC/FRPS H. NORTH ..SMUD RESP /lNSP FIND. HAND NOTES / / EPRP5 MC/FRPS 6 HAMADA R$ LAND USE ISSUE MEMO / / FILE 50312 FRPS YUHAS FRPS TRACT!N6 $UMMR RPI / / O ' RECEIPT OF PEill!DN DOCUMENT / / MG MURLEY RS Cli ! TECH SPEC. DOCUMENT / / ADMEND.153 .1994 SMUD AM UAL RPI 800tLET / / SMUD RSLIOEFFLUENT/ DOSE InternalRVBriefing / / 6 Yuhas- ' PRE REi$ TECH SPF.C RPi / / Pg59/13 SMUDEVALLICENSIN6 RPi / / MC/HO l NURE6-0543,2SHIS. 900tLET, frt tover / / NRC/NRR F. Congel l. 0C1020298(draft) booklet I / Liversore HM DM iliEt NorES NOTES,11/13 / / 'RS 6ASES RELEASED 10 Charts 1980-80 / / TABLE OF CONTENTS - 2 sheets / / I 11 PHOTO 6RAPHS RSPH0105 / / MNONRiiiEN NOTES dated 10/17 'l / HAONRiffENNOTES DATED 10/20 / /

CutEFFM61TASIS CHART

/ / C;YlCEOFVIOLAi!DN DRAFT /APPEN0!! A / / SMUD NRC/DRSS Scarano LCTICEOFV10LAi!DN UNS16NEDTYPEDN0?lC / / SMUD NRC JMartin ' !PEC Oi 85-05. LIR 06/05/05 NRC/MARilk SMUD RODR160E! CICCHPi FROM 87-05 ATTACHMENT 7 / / AGENDA HANDNRiiTEN NOTES / / 6 YUHAS 0!Si 1 DENT. IMPR0VEM MSRC AUDIT 16 / / DR1~lN6S/SMUD(4) EVAPORATORS / / SMUD BECHTEL MPS/SMUD (3) SME / / SMUD BECHTEL ' TELEPHONE LO6S - 07/83 THRU 04/04/89 / / YUHAS

y< ?- j i AGENDA i MEETING ON RADIOLOGICAL PLANT EFFLUENTS NUCLEAR REGULATORY COMMISSIQN REGION V, WALNUT CREEK, CA MAY 5, 1987 I 9:00 A.M. DISCUSSION TOPIC IFADER i 1. INTRODUCTION JOHN MCCOLLIGAN 2.: LOWER LIMITS OF DETECTION FOR 10CFR50 ED BRADLEY APPENDIX I COMPLIANCE e 3. DISTRICT-IDENTIFIED IMPROVEMENTS FRED KELLIE t IN PLANT EFFLUENT CONTROL AND ENVIRONMENTAL MONITORING 4. PROPOSED TECHNICAL SPECIFICATION ED BRADLEY~-l' AMENDMENT NO. 155 UPDATE 5. STATUS OF COMMITMENTS MADE DURING RON COLOMBO I JUNE-20,'1986,-APPENDIX ! MEETING IN WALNUT CREEK 6. CLOSING COMMENTS JOHN MCCOLLIGAN i t n g .4 +

6CR(' 1 i DISTRICT IDENTIFIED IMPROVEMENTS IN PLANT EFFLUENT CONTROL AND i ENVIRONMENTAL MONITORrfG l The following represent items identified for which action (s) have been or are being considered and/or undertaken to resolve. ITEM 1 Train operators on responsibilities associated with affluent discharges (45.3.1.29 QTS 25.0072). ITEM 2 Revise setpoints for plant gaseous effluent monitors to ensure unambiguous alarms (45.6.1.3 QTS 15.0011) ITEM 3 Iss'ue a radiological event directions manual to provide more guidance for abnormal situations. (4B.6.1.4 QTS 15.0318) ITEM 4 Issue new manuals to separate event and instrument procedures from the Radiation Control Manual. (43.6.1.5 QTS 25.0038) I ITEM 5 organize and maintain the Health Physics Support and' Environmental Programs group (HPS&EP). i (43.6.1.6 QTS 25.0037 QTS 25.0045) ITEM 6 Issue revised ALARA Manual'. l (48.6.1.7. QTS 25.0031 QTS 25.0039) ITEM 7 Develop technical support and auditing management processes and procedure to interface HPS&EP and Radiation Protection groups. (43.6.1.8 QTS 25.0043) ) ITEM 8 Respond to NRC violation enforcement 86-06-05: I Evaluate actions with implementation of AP.305 and l H2PSA-7. '~ (4B.6.1.9 QTS 25.0026) ITEM 9 Issue completo revisions of the off-Site Dose I Calculation Manual (ODCM). (4B.7.1.1-QTS 25.0023) ITEM 10 Issue the off-Site Dose Calculation implementing procedures manual. (4B.7.1.2 QTS 25.0027) ITEM 11 Issue the ODCM database manual. (4B.7.1.3 QTS 25.0028) ITEM 12 Complete the liquid effluent and 50-mile radius land use census and pathway evaluation. (4B.7.1.4 QTS 25.0029) Page 1

R l ITEM 13 Revise the ODCM Database Manual to include results of I the liquid effluent and 50-mile radius land use census and pathway evaluation. -(43.7.1.5 QTS 25.0030) ITEM 14 Issue off-Site Exposure Control Management Process and Manual. (4B.7.1.6 QTS 25.0032) ITEM 13 Complete off-Site Dose Calculation Sensitivity analysis. (48.7.1.7 QTS 25.0033) ITEM 16 Identify Systems Affected by Health Physics and i Radiation Protection Software. (45.7.1.8 QTS 25.0040 QTS 25.0046) J ITEM 17 Determine Quality Classifications and Establish Performance Standards for Health Physics and Radiation Protection Software. (4B.7.1.9 QTS 25.0041 QTS 25.0047) ITEM 18 Iss m Procedures for Control of Health Physics and Re'Grtion Protection Software Development, f

-=<.iication,-Access, Benchmarking.

4% 7.1.10 QTS 25.0042 QTS 25.0048) ITEM 19-Prepare Procedures for Calculation of Off-Site Dose Associated with Unmonitored and Unplanned Releases (NRC RG 1.21) of radioactive materials. (4B.7.1.11 QTS 25.0049) ITEM 2) Revise _ Technical Specifications Associated with 10CFR50 Appendix I Compliance. x. (4B.7.1.12 QTS 25.0017) t e ITEM 21 Include Additional Sampling / Monitoring Points for the Liquid Effluent Pathway in the Radiological Environmental Monitoring Program. (45.7.1.13 QTS 25.0018) t l' L ITEM 22 Revise the Updated Safety Analysis Report to Reflect L Actual Liquid Effluent Control Practices. (45.7.1.15 QTS 25.0020) L ITEM 23 Review and revise the off-site dose calculation manual. l. (4B.7.1.17 QTS 25.0021) ITEM 24 Borated water system NCR to be closed prior to start up. (4 C. 6.1 QTS 26.0642 NCR S-5912 WR# 113141) i W v Page 2 .i l +. -.. -.. - - -... -... -..... - -. -. -

4 ^ .t c ITEM 25 Radiation Monitoring System a Recorder RJR-013 cannot be easily read. (4C.8.1 QTS 26.0284 ECN R-0457 WRf 115507) b Discrepancies between R-15002B and R-15045. (4C.8.2 QTS 15.0011 Complete) c R-15017A&B not in service. (4C.8.4 QTS 21.011 ECN A-4714 WR$ 84219) d R-15001 and R-15002 - multiple problems. (4C.8.5 QTS 21.0110 ECN A-4052 WRf 114845) q e R-15020 failure rate is high. (4C.8.6 QTS 21.0113 ECN A-0891 NCR s-5156) { f WRs to be completed prior to restart. (4C.8.8 QTS 26.0278 WR#s

112122, 112123,

112124, 115983, 113635, 113758, 115995,

117483, 101708, 106317, 107962)

,i g Main Steam Line Monitor Readout. (4C.S.11 QT8 22.0389 ECN R-1041) ~ r h Inadequate RCS leak detection. (4 C. 8.12 QTS 26.0283) L i Determine use and setpoints for R-15001. (4C.S.13 QT8 27.0063) ) a j some radiation monitoring points are missing from SPDS. (4C.15.3 26.0529 ECN R-1041) l l ITEM 26' Administrative Iodine limits for reactor coolant system. (4C.22.12 QTS 20.0401) t ITIM 27 Develop procedure to calculate releases from MSSV L opening (AP.509).. (4 C. 2 5. 5 QTS 26.0323) ITEM 28 The main. steam valves acoustic monitors are unreliable. (4C.25.6 QTS 26.0221) 3 L ITEM 29 WRs to be completed prior to restart. l (4C.36 QTS 26.0695 WR#s

106893, 114910, 123347)

All related to clean drains system. 1 Page 3 ~ . _. _.. -. ~ _ _,.

t l l .e ITEM 30 Low capacity of secondary waste water system (liquid waste segregation). (4C.37.1 QTS 19.0040.A ECN R-0775) i ITEM 31 Evaluation of 8.P.s shall be done to verify integrity j of testing liquid release pathways. i (4C.37.3 QTS 26.0307 ECN R-0775) l i ITEM 32 Evaluation of modifications needed for integration of primary and secondary waste water processing. e (40.37.4 QTS 19.0040.8) i This should include a review of operating i a procedures to prevent the actuation of the shell l side relief valves of the first through fourth point heater which discharges to the blowdown tank (T-328). (QT8 19.00403) b An evaluation of the feasibility of covering the plant drain in the vicinity of the relief valves needs to be made. some steam traps of auxiiia n steam system c currently drain to storm drains. A proposal to reroute these directly to the RNUT is being evaluated. (QTS 26.1055) f' d I./ An alternate drair syst 7 for the spent fuel pool liner for instance .. V-600 is unavailable is being evaluated. (QTS 26.1062) The CST overflow currently drains to storm. e drains. An interlock to cause an automatic divert to the Retention Basins in the case of CST I overflow is being evaluated. (qts 26.1062) f Revisit the study on controlling of radioactive i liquids in the Tank Fara Area (Leslie Fitz) (40.37.4 QTS 19.00405). ITEM 33 The make-up tanks could not be sampled at power due to i leakage in the system. I (4C.39.1 QTS 21.0102D) o ' ITEM 34 Manual restart of auxiliarp building ventilation followin shutdown from fire protection interlocks is not poss ble. (4C.45.3 QTS 26.0541 ECN R-1142) i + f Page 4 c

+ .,,c '.. N 'N J ITEN H35, An independent review of the Radiological Environmental l Monitoring Program was performed by the HP8&EP group. ] several items were identified for review and resolution (CCTS T860722024). These items include the followings l i Add new offsite enviror.mantal sampling stations a (and relocation of old sites) to provide more representative samples. b Purchase new (modern) air sampling equipment. e Perform training of HPS&EP personnel to ensure consistency of techniques when obtaining samples. i d Revise Tech Specs to be consistent with NuReg-0472. e New types of samples (i.e. water Hyacinth, offsite soil, etc.).have.been proposed. 5 f New vegetation production sites been proposed for sampling purpos(gardens) have i ] es. ITEM 36 Environmental / Gaseous Effluent Effluent Channel surveys do not currently allow a quantitative evaluation. b Gamma Isotopic analysis was not performed by the ( Environmental Contractor on samples containing greater than. 3 pCi/1 of I-131. Counting of composite air samples for Sr-89 and 90 c were not performed if gross beta was below LLD on all filters. d No QC checks currently in place to verify that representative liquid and gaseous effluent samples. are collected. Evaluate the need for a comprehensive quality 1 e control program for the REMP. f Resolve problems with efficiency and background-determinations with count room equipment. upgrade calibration and quality control program to demonstrate the validity of radiochemical measurements, g Incomplete information in 1985 and 1986 semi annual reports (missing assumptions for doses to individuals within the site boundary), h Include on the ECN checklist / cover sheet a block for an independent T.S. 6.17 review for changes to-the radwaste system. MSRC Audit #16, 87-004 ~ Page 5 - -, - -. - + - - - - - -. - - ~.. - -

'l i Y '.A The following items have also been identified and are currently in review for qts implementation: ITEM 37 Evaluate the present radiation monitoring system including: a CAEG and WGH monitor range insufficient. b No nonitoring or sampling capability on hoggers or steam driven Aux Feed Pump, i c Recommend changes based on the study, i ITEM"38 which allows interaction and access of effluentInst sampling analysis data by all groups involved with effluent releases has been effected. ITEM 39 to allow for elevated gaseous releases. Evaluation of t ITEM 40 Check proper operation and leak ti Place on a surveillance schedule. ghtness of RCD-010. i ITEM 41 The assignment for an evaluation of procedures required for recovery from a primary to secondary leak should be performed. t ITEM 42 Condensate and feed pump seal leaX-off back to the condenser under all conditions. t ( (ECN R-1087A) Not all priority 2 and 3 QTS items have been included on this list l L ul l i f Page 6 l 1

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S,a. ' > ~ ~ ' ~ ~ y &g;ty - p. h h" a )@ MARCH 3, 1987 i: MEETING AGENDA 1-. iiL_) [,; r, TOPIC DISCUSSION LEADER W f.n: g. 4 .- I. ~ Opening Remarks fred Kellie b II. Proposed Technical Specification Ed Bradley / i s, .g, Amendment No. 155' III. Development of, Target Dose Richard Oesterling [ff. Methodology for 10 CFR 50 .f Appendix I Compliance , nW; IV.. Radiological liquid Dolan Falconer Effluent Concerns V. Closing Remarks / Discussion fred Kellie i 4 r ,i .io 4q,a wa w dg oA y Ah 5 y %o' nSw5 i... e Es M N3 M NM ~ i LN y Qy yr O-C % O) I - r .l j l r

L,; L. PREFACE ~ l Early 1n 1984, District staff discovered that the liquid effluent dose. ~ calculations were not b'eing performed in accordance with the NRC calculational -methodology and the Rancho Seco Of fsite Dose Calculation Manual (00CM). After correcting the calculations, the District reported a calculated dose via liquid ef fluents to a maximum hypothetical individual of 186 mrem to an adult-total body l and 305 mrem to a child liver for calendar year 1984. The District initiated a liquid effluent control program in October 1984 which significantly reduced the quantity of radioactivity in liquid effluent. As an example, the District reported discharging 0.3 curies of cesium-137 in 1984, and only 0.004 curies of cesium-137 in the first six months of 1986. -Once the calculational errors were discovered, the District also initiated an extensive environmental monitoring program using the Lawrence Livermore National 1.aboratory, conducted an extensive liquid effluent pathway land use census, monitored individuals in the general public for radiation, and submitted numerous reports to the'NRC as required by both 10 CFR 50 Appendix I and 40 CfR-190. In June 1986 (IE Report 86-15), the NRC concluded that "since it has not been reasonably established that a real member of the public received a dose in excess of the 40 CFR~ 190 standard, no violation of 10 CFR 20.106(g) has been identified." A NRC inspection in April, 1986 (86-15) caused the District to reevaluate the 1985 radioactive liquid effluent discharge. A special report (Special Report No. 86-08 June 5, 1986) was submitted to the NRC with the result of this reevaluation. .The District's recalculated dose resulting from radioactive liquid effluents to a maximum hypothetical individual of 4.8 mrem to an adult total body and 16.2 mrem to a child liver for calendar year 1985. The NRC provided a staf f evaluation of the Rancho Seco Radiological Ef fluent Technical Specifications and 00CM on July 22, 1986. The NRC' staff concluded that there is an inconsistency between the Lower Limit of Detection (LLD) as listed in Table 4.21-1 of the Technical Specification Surveillance Standards (Section 4.21.1) and the-Technical Specification Sections (3.17.2 and 4.21.2) relating to 10 CFR Part 50, Appendix 1 design ob.)ectives. Because of the highly atypical characteristics of the cooling water system and of the receiving waters, liquid effluent releases at the present LLO values, if properly calculated, can result in doses in excess of Part 50 Appendix ! and the limits specified in 40 CfR 190. A franklin Research Center evaluation, dated January I?,1987 of the Rancho Seco radioactive effluent releases and radiological environmental monitoring ' reports (TER C5506-657) for the calender year 1984 and the 00CM, complement the NRC staff's evaluation. The attached list of concerns is compiled from the IE Inspection Report 86-15, NRC's staf f evaluation and the franklin Research Center report and sumerize the ongoing concerns regarding the control and monitoring of radioactive materials in and from liquid effluents from the Rancho Seco Nuclear Generating Station. s {l llu

1 ut.g + i ReferencesL

.=: 1. NRC-Inspection Report No. 50-312/86-15 dated June-6,, 1986.

2.: ' Staff Evaluation of Rancho.Seco Radiological Effluent Technical Specifications and Dose Calculation Manual Regarding Offsite Doses from - Liquid Effluent," transmitted to the District on' July 22, 1986, 3. Franklin Research Center Technical Evaluation Report No. C5506-657, ' Radiological Effluent Release and Radiological Environmental Reporting for-1984,. Sacramento Municipal Utility District, Rancho Seco Nuclear j Generating Station,' dated January 12, 1987. 1 i 4.- Special Report No. 86-08. Preliminary Calculated Dose-To The Public i Exceeding.The Numerical Design Objectives Of 10 CfR 50 Appendix I, dated 'l May 9, 1986. ') 5. Special Report No. 86-08. Calculated Dose To The Maximum Hypothetically - Exposed Individual. Surpassing the Numerical Guides for Design Objectives Of 10 CFR 50,-Appendix ! dated June 5, 1986. 1 -i 6 i + 5 .if _____a

n 3 3 { ' NRC; APPENDIX L MEETING

COMPREHENSIVE LISTING Of_ RADIOLOGICAL LIQUID EFFLUENT CONCERhS Source Concern IE Inspection i

Report 86-15 -1. 86-15-01 Failure to establish monitoring / surveillance-procedures to ensure compliance with 10 CfR 50 Appendix 1. Li The District considered that the LLD values in T.S. Table 4.21-1 were adequate to meet Appendix I, and did not establish appropriate n:onitoring programs. or guidelines surveillance procedures ~to assure the doses of-Appendix I were met. 2.- 86-15-02 failure to retain records of radioactive liquid effluent releases. The District was unable to locate the following documentation pursuant to T.S. 6.10.2: Release Permit No. Date Tank i 85-203 10-29-85 ARHUT l 85-213 11-13-85 ARHUT 3. 86-15-03 failure to report pursuant to T.S. 4.21. 3 The District failed to. report positive ~results for Cs-137

i activity which were-identified and measured on-June 4 6,

Q and 17, 1985, in liquid effluent releases 85-98, 86-99, and 85-110 in the Semiannual Radioactive Ef fluent Release Report; dated _ September.26, 1985. 4. 86-15-04 failure to collect monthly composites'for quarterly Sr-89-- Sr-90 analysis pursuant to T.S. Table 4.21-1. from January to November 1985 the District interpreted the-requirement such that samples were only taken from release which showed gross beta, gamma-or tritium activity in y excess of their respective LLDs. This interpretation is inconsistent with the NRC interpretation of the T.S. j l 1 1 ] 1

1. - -f NRC APPEN0!X I MEETING COMPREHENSIVE LISTING Of RADIOLOGICAL LIQUID EFFLUENT CONCERNS Source Concern. i IE Inspection Report 86-15 (con't) 5. 86-15-05 failure.to comply with T,S. 3.17.2. r In the District transmittal to the NRC dated June 5, 1986= (JEW 86-087) Special. Report 86-08, the District acknowledges that the best estimate of the radioactive material in. liquid effluent discharged to the environment in 1985 resulted in a calculated dose to the maximum t hypothetically exposed individual that was in excess of i the values specified in' T.S. 3.17.2 Liquid Ef fluents. Dose.

6. 15-06 failure to conduct weekly 10 Curie-timit Surveillance on 4

- T-621. L The connection of a.non-quality class temporary piping i system, with no automatic isolation capability, to T-621 L. raised a concern as to whether the weekly surveillance on T-621 to determine that.the activity was less than the 10 i L Curie Limit while the temporary system was in operation b had been performed. l. L 7. 86-15-06 USAR does not bound tank failures of either T-621 or.the E BWST. Both tanks ar'e outdoo'rs, not surrounded-by liners, likes, or walls capable of holding their contents. Neither-the-FSAR or the. District provided a safety analysis which l would bound these tank-failures. 2 u ) 8. 86-15-07 failure to perform 10 CFR 50.59 evaluation. The installation of a. piping system specifically intended l to transfer water from the liquid radioactive' treatment ,/ V l system to the RHUTs.for release to the environment was 4 implemented without: first performing a safety evaluation l l pursuant to 10~CFR 50.59, 9. 86-15-08 failure to update USAR. L Discharged liquid radioactive ef fluents f rom T-621 to the ? RHUTs for release to the environment from early 1983 1< through March 13, 1986 and did not update the FSAR to 1 reflect this information pursuant to 10 CFR 50.71(e). .4-t,-e-- w z.-3-. a

. Mid4 e d UW. hih UN mi ,,"r -m m .NRC APPEN0!X 1 MEETING Nio c v g s COMPREHENSIVE LISTING-Of-RADIOLOGICAL LIQUl0 EFFLUENT CONCERNS ~ j l 3 . i s ,,Sourcet Concern i !E' Inspection Report 86-15 (con't) lCUc 86-15-09 failure of PRC to review temporary procedure change.< ~ On January 6, 1986, a temporary change to Procedure A.10 L " Demineralized Reactor Coolant Storage System,"Ewas + approved and implemented which allowed pumping water from T-621 to T-950 A and 8 for offsite release without review-j by the Plant Review Committee (PRC). From January 6, 1986 1 to March 6, 1986, the licensee estimates that about 3 350,000 gallons of water were transferred, p. .11. 06-15-09 failure to manage the-implement and maintain procedures-pursuant to T.S. 6.8. The proper establishment of these procedures considering-c r ? the guidance ~ provided in IE Circular No. 80-18:' "10 CFR 50.59, Safety Evaluations for Changes to Radioactive Waste l Treatment Systems," could have resulted~in recognition of l the need to perform a 50.59 review, update the FSAR,'and 1 assure proper sampling of T-621 prior to' transfer such' ] that compliance with T.S. 3.17.2 could have-been achieved. i ' ' 120 86-15-09 AP.2, Revision 21 was not consistent with T.S. 6.8.3.C. 7 y -m The review of non intent changes to procedures can be = delegated to :a Group Supervisor, reviewed by the PRC Chairman and approved by the Plant Superintendent'if T.S.- 6.8.3.c. were revised,;however, the revision to A.~10 was considered an intent ;hange in' view of the FSAR 4 information. m-j 1 13'. > 186-15-10 Inadequate error analysis associated with reported radioactive releases. The estimation of error in Section H of the Semiannual radioactive Effluent Release Report provides an inaccurate: evaluation of the error associated with the reported t releases. s N 3r [ ( i. f r

m c.., 1, j', ? JH 7 ui NRC'APPEN0!X ! MEETING COMPREHENSIVE LI TING' Of._ Rh0!OlbGICAL LIQUID EFFLUENT CONCERNS r ,j+ 1 Source' Concern-s 'IE Inspection i Lt Report 86-15 (con't) q '14.; 86-15-11' Incorrect reference.in Technical Specifications. 9 + q T.S. 6.9.2'3.1 incorrectly refers to T.S. 6.14 in describing what infornation must be included with revisions ofi.the-00CM. 15.1 86-15-12 Errors in,the 1985 Semi-annual Radioactive Effluent Reports. January - June 1985 July - December 1985 i

Table 2A Releases
Table III-A:
Table 2C
Table III-B-

'* Section H

Table III-C-4 Section I,' Table'l
Table IV-A
Section V cc".
Table VI B 16.

86-15-13 failure to justify Revision 3 changes to 00CM pursuant to .T.S. 6.16'. 4 1 Revision 3'of:the 00CM effective September 23. 1985, was. submitted with.the Semiannual Radioactive-Effluent Release-Report dated September 26, 1985.- That report and the subsequent : report did' not/ contain information to totally f suoport the rational 4for the change. Inl addition. the 3 i change. included'a revision of the bioaccumulation factor E for. cesiumLf rom 2000 pCi/kg per pC1/l 'to 1400 pCi/kg per' L pCi/l without a determination-that the change would not-h '.,E reduce the accuracy.of the dose determination. 17. 86-15-AA : ' Inappropriate changing of the onsite laboratory LLO to l facilitate'thefrelease of potentially contaminated liquid. P 11 8. 86-15-BB Ineffectiveness of the District's management of l radioactive materials in liquid effluent. h a. l,' li i

!y g w t g nit td. e Ml+p e } ', _ NRC APPEN0lX I MEETING' i w f Aif CONPREHENSIVE' LISTING'Of RA01ULOGICAL LIQUID EFFLUENT CONCERNS ed # 'l,_ _ ${ f% Source Concern a gp; 1 , Hi; IE Inspection-ReDort 86-15 (Con't) L .g s 6 g t '19. 86-15-CC Inadequate measuring -and reporting of ra'dioactiv' e W materials in liquid-effluents.- F Failure to establish appropriate surveillance:and h monitoring procedures. J Failure' te. ":sintain records. M Failure to report observable y activity. e fik, Inconsistent interpretation of radioactive ^1iquid M;hy. waste. di! . 20.- 86-15-0D Inadequate -LLD's-for 10'CFR 50 Appendix I: compliance. p $4, - Current LLO specifications in T.S. Table '4.2$1' are f-M, inadequate to provide management with reasonable: assurance ml that the numerical guides for design ' objectives in.10' CFR .".o.. 50, Appendix I are being' met. ";in ^l 9

21. ; 86-15-EE Technical Specification errors and ommissions regarding-10

[4 CFR 50, Appendix I requirements, W t,' g)g, e 22. 86-15-ff-Inadequa'te land use census. -l p .c mN The'1and use census is not completed 1 1n a timely manner 4 Ml and during a representative; time of the year. w'% f;h"' # 23. 86-15-GG Improvementiin the quality of= technical work and reports. - Various-reports contained-inaccurate'information and'were 'o not submitted in a timely; manner. 4 124. 86-15-HH Inadequate radiological environmental monitoring program, f M" The REMP does not address the liquid effluent pathway. i

25g '86'-15-11 Inadequate 'staf fing, training,- peer review and-management it oversight'.

The-timeliness, accuracy and completeness of 4' technical work in the radiological effluent l management $i;. area indicates inadequate staf fing, training, peer ' review M;P and management oversight, um O. , gt qm i i, s i, i fj ; s ,!l D ? i4( p [A l e H im,'. _7-l i a ]y .l + ax g k';hh::,%'

e,?.?, p ' ~ ~ x ~ ~' ~ ~ ~ ~ ' ~ ~ l y-NRC' APPENDIX-! MEETING- ^ ,~:. COMPREHEhSIVE -LISTING Of RADIOLOGICAL-LIQU10 EFFLUENT CONCERNS o ..h Source. Concern- !I. NRC Staff-

7 I

Evaluation (* f Dated 07-22. 7 4 ~ .l, It is not clear from the Rancho Seco documentation . reviewed whether the District used, for the~ purpose of calculating the reported.of fsite doses, the actual LLO values, or lesser values for radionuclides in effluent measurements 'where concentration in' excess of the LLO 1 valves were not detected. 4 2. The potential may exist for concentrations of radioactive materials and levels of radiation in'the environment that are higher than' expected on the basis of the effluent measurements,'and possibly exceeding regulatory limits. j 3. -A more frequent land use census may be necessary. / r 4.. LThe dose calculational models do not take into account-the effects of the long-term buildup of concentrations of:

i tradion'Jclides in bottom sediment or doses due to ingesting aquatic-foods, or direct radiation f rom the long-term buildup of radionuclides on land irrigated with a

contaminated water. 15,' .There is a. greater likelihood that offsite doses at' Rancho > 'Seco will: approach the dose-limits.when compared'toothe more typical plants envisaged by the regulatory: standards with-similar waste characteristics and waste treatment to: ' that: at. Rancho Seco. Therefore..to provide assurance that-plant operation 3 maintains releases below the dose limits, atypically greater levels of accuracy or conservatism may be needed in-quantifying. liquid releases, identifying' nearby land uses and' calculating offsite doses at Rancho Seco. 3 l ' 1

~ -.. - = .j

- y

.s .3 + 3 g 1 x;,, j NRC APPEN0!X-I MECTING t -l l COMPREHENSIVE. LISTING Of RA0!0 LOGICAL LIQUID EFFLUENT: CONCERNS ~ 1-- [I,, - .i L Source ~ Concern-4 e

I' n'.

Franklin Research Center Report-W TER-L5506-657 7 1. -- Table 3.22-l' of Technical Specification Section 3.22 h m on the Radiological Environmental Nonitoring Program i does not contain' provisions to perform gamma ; isotopic- .i analyses - for =the ~ following sampling pathways as ,j specified by the model RETS (NUREG-0472): surface p ~ 'n[% water, mud and silt, milk, fish, and food, s 2. Technical Specification Table 3.22-2 which specifies the reporting level for radioactivity concentration.in j environmental samples, does not contain reporting i '.9 levels for individual-isotopes specified by the model 1 RETS (NUREG-0472). Also, applies to the food products. - j .>J 3. TLD result's in Table 3 of the 1984 Annual Radiological r Report were reported.in units of mres/qtr; however, j the same numerical values.were discussed in Section FY II.c.11 in units of mrad /qtr without a discussion of 4 the unit.

Lf L

4. No reporting levels existed for algae or. mud and silt samples. 1 n Mv v J 5. For fish' samples ' taken f rom Rancho Seco Reservoir, the- [, District reported "all' fish samples contained low ) [I.lc . gross beta activity;-the highest ^value was 0.8 pC1/g ~l [{ dry." One. sample had an insignificant.-but-j measurable Sr-90;value. However, a separate study by i J the Lawrence Livermore National Laboratory-I h,' (UC10-20295),l initiated by:the licensee, showed high i yo concentrations of Cs-134 and Cs-137-in fish samples, o 1 6. .The 1984 Annual Radiological Report does not T specifically state that CEP performs analysit of ^> environmental samples for the Olstrict, hy J lt fi \\ l l l t 1 'a!'

~ ^ n y 'T; ^~ ~ ^ l 3,.. 7 .A '?. 3 =.o ,v 'l 5 NRC APPEN0!X't MEETING 2 qw COMPREHENS VE LISi!NG Of. RADIOLOGICAL. LIQUID EFFLUENT CONCERNS.

4. 4 '

f 5 g s Source' Concern 111. Franklin Research l ' Center-Report-TER-C5506-657 (con't) 7. . Releases of quantitities of radionuclides in liquid I

' c effluents which should have been reported as giving calculated whole body and' organ doses in excess.of 10 CFR 50 design objectives during 1981, 1982, and 1983

~ o-went unreported until early 1984 because of errorsLin input parameters to the computer code for calculating 1 doses. As'a result of the errors, the calculated l UT doses reported were-below the'10 CFR 50 values, i e' - 8.- .There appears to be an inconsistency in the values of. t the calculated organ-doses. plotted with I-131 and particulate releases in figure 2-1.d. of the Annual y Radiological Reports, t ,i

a..The maximum. organ dose for 1983 is to the thyroid at 0.75 m1LENE,'which is the same as the maximum u

. organ dose to the thyroid of a child at,0.61 m) WSW H reported.in Appendix f of the 1984 annual Report. However, the high release in 1982 compared to;the: i calculated organ dose is apparently'due'to the; fact that the releases during 1982 (but not 1983) were dominatedLby Co-58, for.which Regulatory Guide s 1.109 contains the entry "NO-DATA." The calculated 1; maximum organ doses for 1980 throughL1984 appear'to be consistent with being primarily due to 1-131.. - b. In :1985, the District reports maximum doses due.toi 1 c tritium, iodines. and particulates in airborne; ,g effluents,'but does not specify location, type of individual..or whether whole body or' organ dose.

es

f

c. The value of 0.75'6. mrem.obtained by summing the~

1985 maximum quarterly doses is smaller than the' I q; sum of calculated' doses in an infant via'the 01 gas-milk. cow pathway (0.92 mrem) at the location for which-the highest organ dose due to gaseous-n- effluents was reported in the 1983. The value of. 0.92 mrem was obtained by summing. values taken from the Licensee's ~ table containing all dose calculations for the year, , ? .Y-1

_ ~- ( '_ O 1 1

l L

.NRC-APPEN0!'X I MEETING l, + i COMPREHENSIVE LISTING Of RADIOLOGICAL LIQUID EFFLUENT CONCERNS. [ Sourc_e Concern j j. !!!. Franklin Research L Center Report t TER-C5506-657 (con't) 9. In the environmental nonitoring report for 1985, the 'I District included a comparison of plant measurements . of' airborne gross beta' activity with measurements performed by the State of California at the same j - locations and noted higher readings by.the State of' l -California program. However, the graph provided of the data shows the measurements were from different- ,( time periods and, therefore, not comparable. i E 10. In 1984, the District should have reported an Annual: b Radiological-Environmental Operating Report and two' l-Semiannual-Radioactive Effluent Release Reports per the Licensee's. Technical Specification 6.9.2: The District only submitted one Annual Radiological Report. y 11.

Except for the TLDs,. the monito' ring and sampling-

.j locations)were incompletely.. identified. Most j identifications were only by'name or code number. The-table and map identifying sampling!1ocations and L giving'distancesiand directions, required 'by Technical .i Spectfication 6.9.2;2.2'Jwere:notlincluded. 12. . The reports did'notiinc1Ede summarized and' tabulated results. in a consistent format (e.g.,: TLO results were reported quarterly forceach location, resultsiof weekly milk' sampling;were.' reported only in a' quarterly composite by' location ~, ' analyses :of mud' and silt 14 samples were: reported for;each sample, etc. T 13. The frequency at which samples were analyzed was not - stated for.most samples. y 14. The comparisons with:preoperational-studies,1 M operational controls.. and previous reports, as 4 required by Technical Specification' 6.9.2.2.2, were - generally cursory or omitted. g 9 15. -The volume of radioactive solid waste shipping containers was given in cubic feet rather than cubic meters. The solid waste was given in cubic meters. 't .I - l 1.- +

.,.m

/ i c g NRC APPEN0!K ! MCETING z . COMPRCHENSIVE LISTING Of RADIOLOGICAL LIQUID ifFLUENT CONCERNS'- v w ? ( Source Concern Ill. Franklin Research-L g Center Report

TER-C5506-657 (con't) q

16. -

Solid waste data were not given in 6-ecnth periods,. but only in annual ~ totals, i -- IL The Technical Specifications do mot contain a, provision-to. treat ~ 11guld ef fluents, as required by the model RETS (NUREG-0472) Specification 3.11.1.3.-- 18.- The District has not consnitted to project the liquid - doses to the unrestricted areas at least once per 31 = days as specified by the model RETS (Specification 4.11.1. 3). '9. Revision 3-of the ODCM is not consistent with the n-. criteria of NUREG-0133 and contains numerous discrepancies. (see Attachment A). l t ( 1-: L_. U L H py n. 1 lN ly; ).i 4 i W L i t h7 [ 'l [ ja ~ . l.

,.ay, s l, ;?. ATTA00(DrT A .TER C5506-657 v. c 4. mmgans .i y; The Licensee has submitted a revision (Rev. 3) to the existing Offsite

t Dose Calculation Manual (4) submitted in'the Semiannual Radioactive *tffluent

b melease Reports

through December 31, 1985. This revision of the existing

) i GICM has been evaluated against the current NRC guidelines and was found to ll consist of manerous discrepancies which are deemed to be inconsistent with the eriteria of NURPG-0133.. The Licensee's 0004 revision therefore cannot be considered an acceptable reference document unless these deficiencies are t properly addressed. These deficiencies have been discussed in the text and-are listed in the following: f + g-J' Liquid Effluent Setpoints m [ y Ij; o Licensee's Equation (2.1-2) should be: o l g - Ct = (F + fl. 1 I f L I'- I[(MPC1)) si J 1 1 j h rather than: I IS MPCI) Ct

II + II i

[ f i-as stated in the OrJ1.

b; The Licenseee'r. minimum dilution flow rate (F = 800 gpe) seems small, o-compared wit *. the maximum acceptable flows rate (f = 300 gpm).. The, Licensee should also provide nominal flow rates for comparison.

Since the RHUT monitor setpoints are based on a default radionuclide o

.4 L

mix, Section 2.1.1.1, then a comparison should be made between the .[ prerelease isotopic analysis and the default mix to ensure.the setpoint is conservative. This-is particularly true in case of the 1984 releases when cesissa isotopes were released.in disproportionally large amount. h 1 tion (2.1-7) does not appear to consider the requirement that. o 5l,~ i MPCi Ci , 11 g Equation (2.1-7) should be equivalent to Equation (2.1-4) except that the nuclides are measured and are not the default mix. ~

The Licensee submitted a revision to ODCM in the Annual Radiological Report 3

for 1984. D-14 9* wwv M v v e m ~ m -2

p j r n. I/( " *J -ATTACHMENT; A (CONTINUED) .f y y TER 45506-657 J 1 3 r --(. ,a .o. In Equatioa~ (2.1-7), it:is not clear why the high alarm setpoiet~1s. increased by the factor;1.25. A low or intermediate alarm may I ^ . justify a setpoint increase;to prevent spurious alarms, but the high '..- -alarm setpoint should not be increased. The detector efficiencies *11sted in Table 2.1-1 aust be current 1i o-p values and specific for the WRrf sanitor detiector in use. The data-in Table 2.1-1 appear, to be for a detector system that may or may not-be in'use. ~ J .j Gaseous Effluent Setsoints. The Licensee has not specifically committed to using the highest: TI o annual aver 69e (X/Q) values, and thus the conservatism is not ensured.. I In Section'3.2.1.1, Table'3.2-1 should be referenced instead of Table o 3.1-1. The justification for the l' 25 correction factor in Equations o 1 . (3.2-0), - (3.2-9), and (3;2-10) is not clear. Decreasing the flowrate: in Equations (3.2-8) and (3.2-9) is acceptable to ensure the 10CFR20.< E t ' limits are not exceeded. However, increasing the high alarm setpoint-by 1.25;in Equation.(3.2-10)Jis not acceptable as the monitor's p response is. independent of flow. a The detector efficiencies-listed in Table 3.2-2 must be currerst o-lc o-values and specific to'the detector system in use. It is not clear, .how a single set of values.is applicable to several monitors as 1; indicated in the footnotes to Table 3.2-2. ~ .The Licensee has not explained how the total-maximum permissible o - i. 7,, concentration (TMPC) is obtained or what are the units of TMPC. o: Equation'(2.1-2)* isfincorrect.. It should be written as, I l MDF = (MPCF)(R)'- R T instead of i MDF = (MPCF)(R) o .i The justification for the 1.25 factor in Equation (2.1-1) is not-d o clear. Decreasing the flowrate will not change the monitor's response to the volume of;11guid seen by the detector. An adjustment' can be made by multiplying Equation (2.1-4) by 1/1.25 with the 1, justification of decreasing the batch release rate to ensure against } exceeding the 10CFR20 concentration limits. L 'l Liquid Concentration and -Caseous Dose Rate- (10CFR20) I' The Licensee has not comitted to using the highest annual (X/Q) o values to ensure conservatism. >Should be Equation (2.2-2), as the Licensee has mistakenly numbered all the. equations under Section 2.2. i D-15 m

... _ -._ _ _.-.. _.._ _._ _ - _ ~ w o a ) 9 i ,N ATTACHMENT - A ~ (CONTINUED) ,}; TER-C5506-657;; s o' The 1.ioensee has not addressed the possibilities of simultaneous ' It releases from various release points. 'In Section 3i3.2, the definition for Pp contains a reference to o l, Table 3.1-1, whereas the reference should be to Table 3.3-1. i-1 o; The espressions for Irrigated Foods in Section 2.3 oontain the factor 1100 and Np.;'It is not clear that these factors belong in these espressions since these expressions are siellar to Equation (4) on page; 1.109-3 of Reg. Ouide 1.109. -{ o The espression for Irrigated Paods: Milk contains the ters = n.- (1-FNATER). However, FNhTERs1.0 for allk from Table 2.3-4, which L seros out the dose contribution to the allk pathway from cows drinking contaminated water.- The expression for tritium'on page 16 of Section 2.3. is not an i o expression for dose, but an espression for the tritium l-concentration. Additionally, it is not clear that the factors 1100 ' j or My belong in this concentration espression as indicated by 1 L Equations (A-14) or (A-16) in Reg. Guide 1.109.- Not'e 1 in the description of variables on hge 19 of the submittal-o: states the tiloaccumulation factor for cesium in freshivatorifish:is a 2 site-specific factor of 1400 instead of the 2000 PCi/kg per pCi/ liter ,g s recommended in Reg. Guide 1.109. I. Table 2.3-1 lis:s an infant's usage parameter of 0 liter / year for o allk instead of the 300 liter / year recommended in Reg.. Guide 1.109. ,s Table 2.3-1 lists freshwater fish usage factors of 21, 21, and 35, [ o j kg/ year instead of the 6.9,16, and 21 kg/ year values roccernende'd in i ] Reg. Guide ~ 1.109 for the child, teenager, and adult, respectively. i c. Table 2.3-3 does not include a t value of 24' hours for leafy '-vegetebls:s for. the maximum exposed individual as recosamended in Table. [ p l ~ E-15 of Reg. Guide 1.109. - I f'4,f o Table 2.3-3 lists the release holdup and transit time as 72 hours j' instead ~ of 24 hours as recommended for t in Table E-15 of Reg. h Guidel'1.109. 1 The definition of R.jak on Page 70 should have units of o I m2(meem/yr) per (uci7sec) for D/Q dependent pathways instead of j (area /yr) per (uCi/sec.) The inhalation and ground orposure pathways should be included with o the listing on page 71 of Section 3.4.2. The usage parameter for fruits, vegetables, and grain in Table 3.4-22 o-should have units of kg/yr instead of kg/hr. 'l j 1 1 D-16 l~ l I a-1 ,,-n.,

PN cP k... ir .y 9 ! ATTACHMENT A '(CONTINUED) 1 ? ,a ,L.; c TER C5506'-657'. m,- 1 - ~ -y The Sc-90 bene and total body values fotr the Lagostion o j pathuays for all age groups la Appendia A are incorrect as [ to Rog. Guide 1.109. y mpared 5 4 ,The values on page 156 are. interchanged for the o values for I-131. The same situation salets for 1-135. b Lievid Rahte Treatment c ( 4 effluent prior to discharge.The Licensee's RETS does o i e liquid projection is therefore lacking in the CDCM.The provision for monthly The Licensee has not pcovided a flow diagram defining th o g paths and components of the radioactive liquid waste treatm L e effluent Gaseous Radweste Treatment system. The Licensee's method for projecting the monthly gaseous d o clarity and a' specific approach." The' Licensee should pr ose lacks specific method for projecting,the monthly dose. e The Licensee has not;provided a flow diagram defining th ~ ff'} o-i paths and co'aponents of the radioactive gaseous waste trea ee uent i system. Environmental Monitorino procram i [i Specific parameters of distance and the ' direction sector f lo o centerline of the reactor and additional infomation for - rom the - environmental monitoring program are not. included in-the 0 although the 00CN-AP.307i "Environmestates the information is contained in procedure ntal Monitoring Manual." submitted the procedure;was not reviewed. included i The procedure must be {; s The ILD description. in Section 5.1. should be ' modified o consistent with the model RETS, to read ~ "The 14D is' defined . to be purposes of these~ specifications,i as the smallest -concentratio y , for radioactive material in a sample that will yield a not count E only 5% probability of' falsely ' concluding ~ th , above ~ represents a ~ 'real' signal." ~ In addition,' the A on defined for both the effluent and envirormental samples term should be as follows:. { Effluents 1 ,y w A t = the elapsed time between-ths midpoint of sample collection and time of counting. s Environmental l O t = the elapsed time between sample collection sample collection period, and time of counting. , or end of the D-17 i - ?

m,. . j. c.f 4, j}( N.lv, TECHNICAL SPECIFICATIONS RANCHO SECO UNIT 1; No /jyjf( ^ TABLE OF CONTENTS N/G OfGjn '/de Section 'Page 1.16 RESTRICTED AREA 1-7 1;17 SITE BOUNDARY 17 1.18 DOSE EQUIVALENT I-131 1-7 3, 4 1.19 MEMBER (S) 0F THE PUBLIC 1-7 155> 1.21 MAXIMUM HYPOTHETICAL INDIVIDUAL 1-8 L V l 1.22 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1 4 L R-(REMP) MANUAL

2..

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS ~ 2-1 2.1 SAFETY LIMITS, REACTOR CORE 2-1 { y 2.2 SAFETY LIMITS, REACTOR' SYSTEM PRESSURE 2-4 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION 2 5 3. LIMITING CONDITIONS FOR OPERATION. 3 H +- 3.1 REACTOR COOLANT'$YSTEM 3-l' 3.1.1 - Operational Components 3 ! 1 x j.~ 3.1.2 ' ,,. Pressurization,.Heatup, and Cooldown Limitations - 3 l. 9 3.1.3 Minimum conditions for Criticality 3-6 b 1 3.1.4 Reactor Coolant System Activity 3-8 h t -3.1.5 Chemistry 3-10 h, .l i ( n I, I Ll! -l Proposed Amendment No. 155 iia

i l.

1 .i. .g. g II

'I _k i e '[ RANCHO SEC0 UNIT-1 -) TECHNICAL SPECIFICATIONS j; ,J yi TABLE OF CONTENTS (Continued) g m.3 4 >s n E, ' Section P3 dl 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING w 4-83 4.27 LAND USE CENSUS 4'-86 g 4.28 EXPOLOSIVE GAS MIXTURE 4-87 k 4.29 FUEL CYCLE DOSE 4-89 Y 4.30 INTERLABORATORY COMPARISON PROGRAM SURVEILLANCE REQUIREMENT 4-90 ',3 '4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 4 91 VENTILATION AND AIR CONDITIONING [ 5 DESIGN FEATURES .5-1 5.1 SITE '5-1 o 155> 5.1.1 Exlusion Area 5-1 ' ow Population Zone h~ 5.1.2 L 5-1 5.1.3 Site Boundary for Gaseous Effluents 5-1 7 5.1.4 Site Boundary for Liquid Effluents 5-1 5.2 CONTAINMENT 5-2 5.2.1 Reactor Building 5-2 -5.2.2 Reactor Building Isolation System 5-3 5.3 REACTOR 5-4 5.3.1 Reactor Core 5-4 5.3.2 Reactor Coolant System 5-4' x ~ 5.4 -NEW AND SPENT FUEL STORAGE FACILITIES 5-6 5.4.1 ~ New Fuel Inspection and Temporary Storage Rack 5-6 5.4.2 New and Spent Fuel Storage' Racks and Failed 5-6 Fuel Storage Container Rack 5.4.3-New and Spent Fuel-Temporary Storage 5-6 5.4.4 Spent Fuel Pool and Storage Rack Design 5-6 4 Amendment No.155 - vii i 1 i 1') d

( RANCHO SECO UNIT 1 J ' TECHNICAL SPECIFICATIONS ___ v.~ LIST OF FIGURES (Continued) Figure- '3.5.2-7 Core l'abalance vs. Power Level, O to 40 EFPD L3.5.2 8 - Core Imbalance vs. Power Level, after. 30 EFPD 3.5;2-9 Core Imbalance vs. Power Level, after 300 EFPD with APSRs Withdrawn 3.5.2 10 Deleted 3.5.2-11 Deleted 3.5.2-12 Deleted ~3.5;4-1 Incore Instrumentation Specification Axial Imbalance Indication 3.5.4 2 Incore Instrumentation Specification Radial' Flux -Tilt Indication

p

~3.5.4-3 Incore= Instrumentation Specification 3.18-1 General Layout of Site 4.13-1 ' Main'Steamilnservice Inspection 4.13-3. M&in Steam. Dump Inservice Inspection 155v 5.1-1 Exclusion Area' 15.1-2 Low Population: Zone 5.1-3 . Site Boundary for Gaseous Effluents < -5.1-4 Site Boundary for Liquid Effluents 6.2 SMUD Organization Chart 6.2-2 Plant Organization Chart Proposed Amendment No. 155 1 Xii

,.,v y- ~~ --' ~ ~ ~ ~ ~ " ~ ~ ~ f 4 3 j f f' Yl' f h ; i

3. lW M

m; y_: L 9 4 @M WQ,1 p. RANCHO SECO UNIT 1 // TECHNICAL SPECIFICATIONS y Definitions.

p(t: 1 1.15 OFFSITE DOSE CALCULATIO MANUA (ODCM) l [R 9

v M ,j1SS, Vk r/.- An OFFSITE DOSE NUAL (00CM) shall be a manual containing the escrip f the methodology, algorithms and d j S"' /1 4_ . parameters to be used in the calculation of offsite doses : y%j.N J I resultin from the release of-radioactive material in gaseous and s& liquid e fluents and in the calculation of gaseous and liquid ( y a' effluent monitoring instrumentation alarm / trip setpoints. Nt 1.16 RESTRICTED AREA 'P "@Y rm That portion of the site property, the access to which is gg controlled by security fencing, equipment and personnel. NM ' 1.17 SITE BOUNDARY g m, j[ The boundary of the SMUD owned property. )[i ' ' ' 1.18-DOSE EQUIVALENT I-131 W The DOSE EQUIVALENT I-131 shall be that concentration of I-131 M .(microcurie / gram) which alone would prcduce the same thyroid dose s '155> via the inhalation pathway as the quantity and isotopic mixture of + /7 I-131, 1-132, 1-133. I-134 and I-135 actually present.. The %"A s thyroid dose conversion factors used for this calculation shall be those listed in ICRP Publication 30. " Limits for Intakes of-M y Radionuclides by Workers," 1979.. M' ff l'.19 MEMBER (S) 0F THE PUBLIC 4 (( MEMBER (S) 0F THE'PUBLIC shall include all individuals who by virtue of their occupational status have no formal association z, with the plant. This category shall: include non-employees of the 'i Ifcensee who are permitted to use portions of the site for i ,i recreational, occupational, or other purposes not associated with y plant functions. This category shall not include non-employees i such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an' area that is 4 controlled by the licensee for purposes of protection of a individuals from exposure to radiation and radioactive materials.

u. m

[ l1 i t s 4 e gl' 1 . Proposed Amendment No. 155 1-7 4 l g sw, ,.., a

7. [t, s RANCHO-SECO UNIT 1 ,J',. TECHNICAL SPECIFICATIONS Definitions 155> 1.21 MAXIMUM HYPOTHETICAL INDIVIDUAL l The MAXIMUM HYPOTHETICAL INDIVIOUAL concept is':onsistent with its ~ i use in the US NRC Regulatory Guide 1.109 and 10;FR50, Apgendix 1. The MAXIMUM HYPOTHETICAL INDIVIDUAL is characterized as maximum" with. regard to food consumption, occupancy, or'other usage or exposure pathwayL parameters in the vicinity of Rancho Seco that would represent an individual or composite of individuals with habits greater than. usually expected for the average of the sopulation in general'. No single individual-would be expected to >e exposed to all " maximum" value.,the potential effluent exposure pathways at the The MAXIMUM HYP0THETICAL INDIVIDUAL is a hypothetical receptor of ' j,' radiological exposure (mren) resulting from the discharge of. O(4 radioactive. effluent (curies). The methodology to convert curies into area is described in the ODCM.- The purpose of the-00CM / calculation =is to compare the resultant effluent exposure or dose-with the numerical l guides for design objectives in 10CFR50, Appendix 1. F The MAXIMUM HYPOTHETICAL INDIVIDUAL concept is NOT used to }. demonstrate compliance with 10CFR20.106. 1.22 - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) MANUAL The RADIOLOGICAL ENVIRONMENTAL MOL TORING PROGRAM (REMP) MANUAL l shall-be a manual:containing-the description of the Rancho Seco radiological environmental monitoring program. The REMP manual 1. ..shall, contain a description of the environmental samples to be' collected, the sample; locations, sampling frequencies, and sample o

[

. analysis criteria. 9 .g\\O ^ hG ^h. re L 'l L Proposed Amendment No. 155 1-8 - ~. - =

15E. RANCHO SECO UNIT 1 TECHNICAL $PECIFICATIONS Limiting Concitions for Operation 3.17 LIQUID EFFLUENTS 3.17.1 Concentration The concentration of radioactive material released at any time 155>< beyond the site boundary (see Figure 5.14) shall be limited to the 1 concentrations specified in 10 CFR Part 20. Appendix 8. Table !! I 1 y Column 2 for radionuclides other than dissolved or entrained nobie gases. For dissolved or J shall be Ifmited to 2x10 gntrained noble gases, the concentration 9 pCi/m1 total activity. j kApp1tcability At all times Action J With the concentration of radioactive materiai released from the site to /. unrestricted areas exceeding Specification 3.17.1, restore concentration L '155> within the specification ilmits as soon as practicable and report in the next g < Semiannual Radioactive Effluent Release Report. 4a Bases This Specification is provided to ensure that the concentration of radioactive materials released in ifquid waste effluents from the site to areas beyond the lFfr site boundary for liquid effluent will be less than the concentration levels specified in 10 CFR Part 20. Appendix B. Table !!, Column 2. 4Mr This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside t e will result in exposures k < within the limits of 10 CFR Part 20.10 to MEMBER (S) 0F THE PUBLIC. The-i concentration limit for dissolved or en ined noble gases is based upon the assumption that Xe-135 is the controlling radioisotopes and its MPC in air (submersion).was converted to an equivalent concentration in water using the methods described in International C(seission on Radiological Protection (ICRP) Publication 2. { L l Proposed Amendment No. 155 3-70 m.- 2 ,.,_,.........._..,y y

t 155>. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.17.2 Dose 155> The dose or dose commitment to a MAXIMUM HYPOTHETICAL INDIVIDUAL from radioactive materials in liquid effluents released from the site (see Figure 5.1.4) shall be limited to: i i a. Less than or equal to 1.5 mrom to the total body and to less than or equal to 5.0 mrom to any organ during any calendar quarter; and, i b. Less than or equal to 3 mrem to the total body and to less than or equal to 10 mrea to any organ during any calendar year. 1 Applicability At all times l Action a. With the calculated dose or dose constitment from the release of i radioacthe materials in liquid effluents exceeding any of the above limits, prepare end submit to the Cosmission within

155, 30 days a Special Report. This Report will identify the cause(s) for exceeding the Itmit(s) and define the corrective actions to be taken to reduce the releases of radioactive material in liquid effluents and the proposed corrective l

actions to be taken to assure that subsequent releases will be in compliance with the above annual limits during the remainder of the current calendar quarter and for the subsequent three calendar quarters. i Bases l This specification is provided to implement the requirements of Sections II.A. r III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix 1. The, L ACTION statements provide the required operating flexibility and at the same ' . time implement the guides set forth in Section IV.A of Appendix ! to assure that the releases of radioactive material in liquid effluents will be kept "as l' 155>< low as is reasonably achievable." The dosc calculation methodology in the (, ODCM implement the requirements in Section III.A of Appendix ! that i conformance with the guides of Appendix ! be shown by calculational procedures k based on models and data, such that the actual exposure of an individual ' through' appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCH for calculating the doses due to the actual,elease rates of radioactive materials in Ifquid effluents are consistent with the methodology provided in Regulatory Guide 1.109,. i " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," l [. L Revision 1, October 1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for t) g 155> ~ purpose of ImplementinD Appendix I," April 1977. There is reasonable i assurance that the operation of the facility will not result in radionuclide concentrations in finished drinking water that are in excess of the requirements of 40 CFR 141. l Proposed Amenhent No.155 y' \\

- ~ AANCHO SEC0 UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.22 RADIOLOGICAL ENYlRONMENTAL MONITORING i The radiological environmen'tal monitoring program shall be conducted as specified in Table 3.22-1. Applicability At all times sf-s Md Action With the radiological environmental monitoring program not being a. conducted as specified in Table 3.22-1, prepare and submit to the 155 s Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. (Deviations are permitted from the required sampling schedule if specimens are i unobtainable due to hazardous conditions, or seasonal gg unavailability.) l b. With the level of radioactivity in an environmental sampling medium exceeding the reporting level of Table 3.22-2 when avera gg g calendar quarter, prepare and submit to the Colonission wged over any 4 thin 30 days af ter the level of radioactivity has been determined, a Special Igg p Report pursuant to Specification 6.9.5 which includes an evaluation, h g, :; of any release conditions, environmental factors or other aspects A 4,g [y define corrective actions to reduce emissions such that potential which caused the reporting limits to be exceeded. This report will 0 4 p4 - exposures will meet specification 3.25. When more than one of the i l ,gg radionuclides in Table 3.22-2 are detected in the sampling medium,' i this report shall be submitted if: Concentration (1) + Concentration (2) + 1 ,,10 reporting level (1) reporting level (2) lgf p When radionuclides other than those in Table 3.22-2 are detected and I are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is' equal to or greater 7] than the calendar year Itaits of Specifications 3.17.2, 3.18.2, and i g 3.18.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, the condition shall be reported and described in the Annual Radiological Environmental Operating Report. ( With milk or fresh leafy vegetable samples unavailable from any of c. the sample locations required by Table 3.22-1, prepare and submit to ISf'? the Connission within 30 days a Special Report pursuant to l Specification 6.9.5 which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then /p be deleted from Table 3.221 provided the locations from which the (53'~r replacemet samples were obtained are added to the radiological environmental monitoring program as replacement locations, if available. Proposed Amendment No.155 L 3-81

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS - Limiting Conditions for Operation J.22 (continued) Bases (continued) 155>< The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher Ig.y n; than expected on the basis of the effluent measurements and ODCN modeling of the environmental exposure pathways. The specified monitoring program is in effect at this time. Program changes may be initiated based on operation 1 experfence, and changes in regionai population or agricultural practices. The* 13y 7 samp1(lo:ations have been listed in the Radiological Environmental Monitoring 4 Program (REMP) Manual to retain flexibility for making changes as needed, gpf r The detection capabilities required in Table 4.26-1 are state-of-the-art for routine environmental measurementr,in industrial laboratories. The LLD's for drinking water meet the requirement of 40 CFR 141. 4 "D ~ [ N (c0 ' \\ W jt w>h ' t Proposed Amendment No. 155 3-82

. ~.... _ _ I .r RANCH 0 SEC0 UNIT 1 + TECHNICAL SPECIFICATIONS ) Limiting Conditions for Operation Table 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling and Exposure Pathway Number of Collection Type and Frequency and/or Sample Samples

Frequency of Analysis i

1. AIRBORNE A. Radiciodine 8 Continuous oper. Radiciodine canis-I and Parti. ation of sampler ter. Analyn at ISSu culates with sample least once. Weekly collection as for I-131. 1 required by dust loading but at Particulate least once per sampler. Analyze l

week, for Gross lieta

E><-

radioactivity at i least 24 hours following filter change. Perform l ' gamma' isotopic. analysis on each sample where gross beta activity is greater than 10 I 155> times the yearly-swan of control samples for the same sasple period. Perfons ganna iso-topic analysis on l composite (by location) sample + at least once per quarter. 2. DIRECT Greater than 40 At least once Gamma dose. At RADIATION locations with 2 per quarter. least once per dosimeters at each . quarter. location. i 155u

Sample locations are shown in the REMP manual.

m[), - Proposed Amendment No ISS 01C D j'

.e RANCHO $ECO UNIT 1 TECHNICAL $PECIFICATIONS Limiting Conditions.for Operation Table 3.22 1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling and Exposure Pathway Number of Collection Type and Frequency and/or Sample Samples

Frequency of Analysis 4.

INGESTION 1666 a. Milk 4 At least weekly Gamma isotopic when animals and are on pasture; I-131 analysis of at least once each sample, per month at other times, b. Fish and 3 At least Gamma isotopic-7 Inverte-quarterly. One analysis on edible brates sample of each portion of each ( of several

sample, e'

species as V shown in the g@f REMP manual, c. Food 4 At time of h6r. Gamma isotopic vest. One sam-analysis on pie of each of edible portion the several of each sample, classes of food products as shown in the RENP manual.

Sample locations are shown in the REMP manual.

2 g9 A h /) f ~ 0 t Proposed Amendment No.155 3-85 ) l

- e, t 1 RANCHO SEC0 UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.22-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ) sampling and Exposerc Pathway Number of Collection Type and Frequency and/or Sample Samples

Frequency

_of Analysis l 3. WATERBORNE 155> a. Surface 1 Timed composite Gamma isotopic sample collected and trftfum mon thly** analysis of each composite. 3 Grab sample Gaissa isotopic and collected tritfun anal monthly. each sample.ysis of l b. Runoff 1 Grab sample Gamma isotopic and collected tritium anal fortnightly. each sample,ysis of c. Ground 2 At least once Gamma isotopic, per quarter, and tritfum I analysis of each sangle. d. Mud and 2 At least once Gamma Isotopic Silt L semi-annually, analysis of One pint sample each sample. of the top 3" of material 2 ft. frou shoreline.

' Sample locations are shown in the,REMP manual.

< ** Applicable when sampler is declared operational. Timed composite is at a pre-established frequency and is not proportional to quantity of waste discharged. Proposed Amendment No.155 3-84 y ~ .r ~w.- .,e_.

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' 7 Seporttag Levels g

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1 RANCHO $ECO UNIT 1 TECHNICAL $PECIFICATIONS Limiting Conditions for Operation i 3.23 LAND USE CENSt'Sg k b bf Og A land use census shall be conducted annually and shall identify the I 'A A. location of the nearest milk animal, the nearest residence and the /- nearest garden

of greater than 500 square feet producing fresh g &'

leafy vegetables in each of the 16 meteorological sectors within a g pgd [ distance of five miles. 155> [ The Land Use Census shall also inclade information relevant to the liquid effluent pathway and gaseous effluent pathway such that the { ODCM and the REMP can be kept current with the existing environmental and societal uses surrounding Rancho Seco, i l M ic # s 1 App'icabili_ty At all times ) Action With a land use census identifying a location (s) which yields e a. calculated dose or dose commitment greater than the values currently 155> being calculated in Specifications 4.21.2 and 4.22.3. ideritify the i new locations in the next Annual Radiological environmental l l Operating Report. J b. With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathwn) 20 percent greater than 6t a location from which samples are currently being obtained in accordance with Specification 3.22. add the new location (s) to the ydiological gpvironmental jpnitoring (. pogram within 30 days. The sampling location (s), exf uding the Tontrol station location, having the lowest calculated dose or dose commitment (s) (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this o land use census was conducted. Identify the new location (s) in the next Annual Radiological Environmental Operating Report and also include in the report a revised figure (s) and table for the REMP manual reflecting the new location (s). ,Rt g n i P l G Q

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

1 i Proposed Amendment No.155 3-87 'I 1

s j RANCHO SEC0 UNIT 1 TECHNICAL SPECIFICATIONS _ _. 3.23 (Continued) Bases This specification is provided to ensure that changes in the use of I 155> unrestricted areas are identified and that modifications to the gadiological gnvironmental apnitoringgogram and the ODCM are made if required by the results of thiTeensus. This census satisfies the requirements of Section l IV.B.3 of Appendix ! to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant expcsure i pathways via leafy vegetables will be identified and monitored since a of this size is the m' nimum required to produce the quantity (26 kg/yr) garden of \\ leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: (1) that 20 percent of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage); and (2) a vegetation yield. of 2 kg/ square meter. / 155> In addition, by gathering information on the liquid effluent pathway and the gaseous effluent pathway, the census will ensure that proper radiological environmental monitoring and radioactive effluent controls are in place for the adequate protection of the health and safety of the general public. l e YgP a (7?yff Y+ 4 s#gq c E t t Proposed Amendment No. 155 3-88 +-.-o m w .,.s,.,, y ,y,,, ,, + - - - +, ,m-.--- ---,m-.-a m.n--w,.m--y,-w-y,,.,..v, 3------ -w- ,y-w aqe-

_-_ _.. _ ~ _ .t i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS [urveillance Standards 4.21 LIQUID EFFLUENTS 9 4.21.1 Concentration 3 Surveillance Requirements f The concentration of radioactive material at an i in ifquid effluents released from the site shall be continuously nitore in accordance with Table 3.151. The liquid effluent continuous monitor having provisions for automatic terwination of liquid releases, as listed in Table 3.15-1, shall be used to limit the concentration of radioactive material released at any time from the 155>< site to areas beyond the site boundary to the limits given in Specification 3.17.1. Q \\hO T d The radioactivity content of eac ba of radioactive liquid waste to be discharged shall be determined pr or to release by sampling and analysis in accordance with Table 4.21-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the g gpg concentration at the point of release is limited to the limits of j Specificatton 3.17.1. lCf7A Post-release analyses of samples composited frcm batch releases shall be performed in accordance with Table 4.21-1. The results of the post-release analyses shall be used with the calculational methods in the ODCM to assure t l ( g gf 7 4; that the concentrations at the point of release were limited to the limits of / Specification 3.17.1. i Bases l This Specification is provided to ensure thet the concentration of radioactive

materials released in liquid waste effluents from the site to areas beyond the site boundary for liquid effluent will be.less than the concentration levels (ST' M specified in 10 CFR Part 20, Appendix 8. Table II, Column 2.

464 This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within IST r< the limits of 10 CFR Part 20.106 (e) to MEMBER (S) 0F THE PUBLIC. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotopes and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods de. scribed in International Comnission on Radiological Protection (ICRP) Publication 2. 155> There are no continuous releases'of radioactive material in liquid effluents from the plant. All radioactive liquid effluent reica::: ' from 'the plant are by batch method. ( Proposed Amendment No. 155 4-69 ,--rv.-- m. .--. -. ~. ,.v,,. -.._,ms.__,,., ~...,... _,.., ,,...., -,,,, ~,

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.21-1 RADI0 ACTIVE LIQUlb WASTE SAMPLING AND ANALYSIS PROGRAN Sampling Minimum Analysis Type of Activity Lower Limit Liquid Release Frequency Frequency Analysis Of Detection Type (LLD) (uct/ml)(a) 3 Each Batch Mn-54, Fe-59, 5 x 10-7 7 A. Batch Waste (BY-Eoch Batch lease Tanks D Co-58 Co-60 P P In-65, Mo-99, t Cs-134' Cs-137 ~p Ce-141, and Ce-144 p[. Y (c) 'p .Y v-- I-131 1 x 10-6 j 155> Dissolved and 1 x 10-5 Entrained Gases { (Gamma Emitters) Each Batch Com)osite(d. e) H-3 1 x 10-6 P

4 Gross Alpha 1 x 10-7 Sr-89, Sr-90 5 x 10-8 q

\\(f h or yt Proposed Amendment No.155 4-70

. :\\ t RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance. Standards TABLE 4.21-1 (Continued) RADIDACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAN Table Notation I7 The lower limit of detection (LLD) is defined in the ODCN. These LLD a. values are sufficient for demonstrating compliance with the Itaits in ? Specification 3.17.1 (10 CFR 20. App (numerica. Table !!, Column 2) and not endix 8 the values in Specification 3.17.2 l guides for design objectives in 10 CFR 50, Appendix !). b. A batch release is the discha e of If quid wastes of discrete volume. Prior to sampling, each batch ill be isolated, and then thoroughly , 6 7( mixed, to assure representative sampling. I Other peaks which are measureable and identifiable, together with the c. ,W7 listed nuclides, shall also be identified and reported. Nuclides which are not observed for the analysis shall be reported as "less than" the instrument's LLD, and shall not be reported as being present. The "less than" values shall not be used in the 00CM evaluatiom. However, if the nuclide is measured and identified at a value less than the Table 4.21-1 ( LLD value, it shall be reported and entered into the 00CM evaluations. i L d. A composite sample is one in which the quantitfscharged and 1!les of liquid sam prosortional to the quantity of liquid waste d which the metiod of sampling employed results in a specimen which is representative of the liquids released. If each composite Gross Beta is less than 5x10-8 uCf/m1, Strontium - ;g f 7 e. analysis is not required. Y Vy 1 L Proposed Amendment No. 155 4-71

I ?, { k 1 155>f n \\ RANCHO SECO UNIT 1 \\' TECHNICAL SPECIFICATIONS V } \\/ Surveillance Standards A y [ sfp 4.21.2 Doses Dose Calculations b [ j i Cumulative dose contributions and cumulative dose projections associated with the release of If quid effluents from the site (see Figure 5.1.4) shall be detemined in accordance with the methodology described in the Offsite Oose Calculation Manual (ODCM) at the following frequencies: q,* Prior to the initiation of a release of Ifquid effluent containing . a. radioactive material; and, b. Weekly, based on gama-emitter and tritium analyses of effluents releastd' during the previous seven days; and, c. Monthly,. based on gama-emitter and tritium analyses of radioactive effluent releases during the previous calender month, and the results of strontium-89, strontium-90, and gross alpha analyses perfomed on composite samples shall be added to the monthly dose calculation. A dose tracking system shall te cperated Jno maintained. Operating parameters shall be adjusted in accordance with methodology described in the ODCM such that the dose values at any time, when projected to the er:d of the appitcable time period, do.not exceed the doses specified in Technical Specification 3.17.2. Bases This specification is provided to implement the requirements of Sections II.A.* !!!.A. and IV.A of Appendix I, 10 CFR Part 50.. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix 1. The ACTION statements provide the required operating flexibility and, at the same time, implement the guides set forth in Section IV.A of. Appendix ! which assures, by definition, that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable." The dose calculations methodology in the ODCM implements the requirements in Section III.A of Appendix ! that conformance with the guides of Appendix ! be shown by < calculational procedures based on models and data such that the actual proposed Amendment No.155 4-72 t

l %Q \\b I 155> RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS M S2 l c' @i Surveillance Standards j i J exposure of an individual throu!)h appropriate pathways is unlikely to be substantially underestimated. "he equations specified in the 00CM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Dose to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1. October 1977, and Regulatory Guide 1.13, " Estimating 1 Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. 5 Target dose values have toen chosen such that the dose limits prescribed in Technical Specification 3.17.2 will not be exceeded at the 95 percent y confidence level. The methodolony oresented.Ln the ODCM provides for adjustment of operational and a6alysis paramete7bto factor in variables such - ~ as annual radiological release volume,' oiscnarge canal flow rate, and current t cumulative dose. qsd glmt' The dose tracking cystem provides for prompt updating of cumulative dose and contains feedback mechantims to assure that the target dose values are not exceeded. The tra: king system also contains review and approval of Atd 1 radiological releas s t ple management levels. g There is also reasonable assurance that the operation of the facility will 'not result in radionuclide concentrations in finished drinking water that are in excess of the requirement of 40CFR141. 4 4(1 ( l ( t l. e v 4 j V ~ Ny N I: 4 Proposed Amendment No. 155 4-72a j I ~

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS --- Surveillance Standards 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING Surveillance Requirements i The radiological environmental monitoring samples shall be collected per Table i 155> 3.22-1 from the locations shown in the Radiological Environmental Monitoring Program (REMP) manual and shall be analyzed to the requirements of Tables 3.22-1 and 4.26-1. Bases 155>4 The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the r6diological effluent monitoring program by verifyteg that the measurable concentrations of radioactive materials and levels of radiation are not higher gyrg than expected on the basis of the effluent measuremen s and 00CM modeling of the environmental exposure pathways. The specified monitoring program is in effect at the present time. Program changes may be initiated based on operational experience and changes in regional population or agricultural tgf 74 practices. The simple locations have been listed in the REMP manual to retain flexibility for making changes as needed. E l lgf 7 The detection capabilities required by Table 4.26-1 are state-of-the-art for routine environmental measurements in industrial laboratories. The LLD's for drinking water meet the requirements of 40 CFR 141. l h {' i t 1 Proposed Amendment No.155 4-83

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance standards Table 4.26-1 (Continued) MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)#e d Table Notation a. The LLD is defined in the ODCN. Analyses shall be performed in such a manner that the stated LLO's will be achieved under routine conditions. Occasionally background - fluctuations, unavoidably small sample sizes, the presenc,e of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological-Environmental Operating Report. b. LLU tor drinking water. LLD shown ig for composite analysis. For individual samples, c. 5x10-2pC1/m is the LLD. d. Other peaks which are measurable and identifiable, together with the nuclides in Table 4.26-1, shall t,e identified and reported. 155u e. Total for parent and daughter. Proposed Amendment No.155 4-85

I f t ?, 1 RANCHO SEC0 UNIT 1 TECHNICAL SPECIFICATIONS O Surveillance Standards 4.27 LAWD USE CENSUS W Surveillance Requirements [&5 l The land use census shall be conducted an@by using methods that will provide the best results, such as door tq-door survey, aerial survey, or by consulting local agriculture authorities. 155> The land use census or portions thereof, shall be conducted during the appropriate time of the year to provide the best results. ) Reports The results of the land use census shall be included in the Annual-Radiological Environmental Operating Report. 1 Bases M This specification is provided to nsure that changes in the use of 155>. unrestrfeted areas are identifie and that modifications to theladiological < Jpvfronmental nitoringpogram and 00CN are made if required 5y the results Tf this censu. This cenfus satisfies the requirements of Section IV.B.3 of Appendix ! to 10 CFR Part 50., Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via i leafy vegetables will be identified and monitored, since a garden of this-size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetable assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: (1) that 20 percent of the garden was used for growing broad-leaf vegetation (i.e.,similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/ square meter. 155> In addition, by gathering infomation on the liquid effluent pathway and the gaseous effluent pathway, the census will assure that proper radiological environmental monitoring and radioactive effluent controls are in place for the adequate protection of the health and safety of the general public. i t Proposed Amendment No. 155 4-86 4 m --e.+ ,-,--.,e v-e, .r n- - - + - ..e--- --a

- n._;.=_.;;.:... j t 3 RANCHO SEC0 UNIT 1 TECHNICAL SPECIFICATIONS Design Features 5. DESIGN FEATURES .55r.5.1 $1TE i 5.1.1 _Excluston Area 1 The EXCLUSION AREA shall be shown in Figure 5.1 1. t l 5.1.2 _ Low Population Zone i The LOW POPULATION 20NE shall be shown in Figure 5.2 2. r 5.1.3 Site Boundary For Gaseous Effluents The SITE BOUNDARY FOR GASEOUS EFFLUENTS shall be shown in i 5.1-3. 5.1.4 Site Boundary For Liquid Effluents e The SITE BOUNDARY FOR LIQUID EFFLUENTS shall be shown in Ffgur 5.1-4 1 P h t i ) Proposed Amendment No.155 5-1 B

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hl i N, J. N' .j RANCH 0 SEC0 UNIT 1. i. TECHNICAL SPECIFICATIONS Administrative Controls I RESPONSIBILITIES (Continued) { i 1. Review of the Plant Security Plan and implementin procedures and shall submit recommended changes to the Plan o the Chairman of the Management Safety Review Comittee. j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Plan to the Chairman of g the Management Safety Review Committee. j f

155, k.

Review of every unplanned release of radioactive material to 1 the environs including the preparation and forwarding of reports covering evaluation recommendations and disposition of I the corrective action to prevent recurrence to the Nuclear Plant Manager and to the MSRC. s 1. Review of' major changes to radweste systems. m. Review of Process Control Program (PCP) n. Review of the Offsite Dose Calculation Manual.(00CM) and shall 5 submit recommended changes of the ODCM to the Chairman of the MSRC. i AUTHORITY 6.5.1.7 The Plant Review Committee shall: a. Recommend to the Plant Superintendent written approval or disapproval of items considered under 6.5.1.6(a) throup 4 (d)

above, b.

Render deteminations in writin each item considered under 6.5.g with regard to whether or not 1.6(a) through (e) above constitutes an unreviewed safety question, c. Provide innediate written notification to the Chairman of the Management Safety Review Committee of disagreement between the PRC and the Manager of Nuclear Operations or the-Plant Superintendent; however, the Manager of Nuclear Operations shall have responsibility for resolution of such disagreements pursuant to 6.5.1.1 above. RECORDS 6.5.1.8 The Plant Review Comittee shall maintain written minutes of each meeting and copies shall be provided to the Plant Superintendent, Manager of Nuclear Operations and the Chairman of the Management Safety Review Committee. Proposed Amendment No. 155 6-5 .x. - -.,, + -. -

~ /. l RANCHO SECO UNIT 1 1 TECHNICAL SPECIFICATIONS i Athinistrative Controls ) AUDITS 6.5.2.8 Audits of. facility activities shall be performed under the j cognizance of the MSRC. These audits shall encompass: a. The conformance of: facility operation to all provisions contained within the Technical Specifications and applicable Itcense conditions at least once per year. b. The performance, training and qualifications of the entire facility staff at least once per year. I c. The result of all actioni taken to correct deficiencies occurring in facilitf equipment, structures systems or method i-L of operation that affect nuclear safety at least once per six l months. l i L

d.. The performance of all activities required by the Quality Assurance. Program to meet the criteria of Appendix *t",

l 10CFR50, at least once per two (2) years, e. The Factif ty Emergency Plant ud implementing procedures at I l least once per two (2) years, j f. The Facility Security Plan and implementing procedures at least once per two (2) years, g. Any other area of facility operation considered appropriate by the MSRC or the General Manager, h. Compliance with fire protection mquirements and implementing procedures at least once per two (2) years. i f. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either l qualified offsite licensee personnel or an outside fire protection firm, j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than three (3) years, i 155H k. The Radiological Environmental Nonitoring Program and the 4. results thereof at least once per 12 months. Ndd4, M, / 1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

Proposed Amendment No. 155

+ 6-9 .i f

f, ..J I,. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

~

Aeninistrative Controls gfp The PROCESS CONTROL PROGRAM for the SOLIDIFICATION of m. radioactive wastes from liquid systems at least once per 24 months. 1 'k n. The performance of activities required by the Quality Assurance Program to meet the criteria of US NRC Regulatory Guide 4.15, ( Revision 1. February 1979, at least once per 12 months. AUTHORITY ~ 6.5.2.9 The MSRC shall re> ort to and advise the General Manager on those areas of respons1 >ilty specified in Section 6.5.2.7 and 6.5.2.8. RECORDS 6.5.2.10 Records of MSRC activities shall be prepared, approved, and 8 distributed as indicated below: a. Minutes of each MSRC meeting shaII be prepared, approved and forwarded to the General Manager within 14 days following each meeting. b. Reports of reviews encompassed by Section 6.5.2.7 e, f, g and h above, shall be prepared, approved, and forwarded to the hneral Manager within 14 days following completion of the review. c. Audit reports encompassed by Section 6.5.2.8 above, shaII be forwarded to the General Manager and to the management positions responsible for the areas audited within 30 days af ter completion of g the audit. 6.6 LICENSEE EVENT REPORT ACTION 6.6.1 The following actions shall be taken should an Event require a ,V Licensee Event Report (LER): l a. The Commission shall be notified pursuant to the requirements L of Section 73 to 10 CFR Part 50, and L b. Each event requiring an LER, per Section 73 to 10 CRF Part 50, h shall be reviewed by the PRC and the resulting LER shall be submitted to the Manager of Nuclear Operations or the Plant Superintendent, and the Executive Director, Nuclear, or the General Manager prior to its submittal to the Commission. Proposed Amendment No.155 6-10 .a ~,y~.-._-.,,,,.-~~-,yw,-,

'. ~. 1 f.' RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS j ~ j, Ahtnistrative' Controls '6.7 SAFETY LIMIT VIOL.A.T_ ION 6.7.1 The following actions shall be taken in th; event a safety Limit is violated: The provisions cf 100FR50.36 (c) (1) (1) shall be complied with a. immediately, b. The Safety Limit Violation shall be reported to the Plant. J - Superintendent, the Manager of Nuclear Operations, the Chairman of the MSRC and to the Commission immediately. i A Safety Limit Violation Report shall be prepared. The report c. shall be reviewed by the PRC. 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 i recurrence. d. The Safety Limit Violation Report shall be submitted to the Commission the MSRC, the Manager of Nuclear Operations and the Plant Superintendent within 10 days of the violation. 6.8 PROCEDURES I 6.8.1 Written procedures shall be estabitshed, implemented and maintained i covering the activities referenced below: The appitcable. procedures recommended in Appendix "A" of ~ a. Regulatory Guide 1.33, November 1972. b.- Refueling operations. Surveillance and test activities of safety related equipment, c. d. Security Plan implementation. e. Emergency Plan implementation. - f.. Fire Protection Procedures implementation, p 155G g. Process Control Program. <7 A hu Offsita Dost G11culation Manual. MS a 'N4O ~ 'Radioacti jve EfWe Control Program. ----[oWM do9 M N3, MV Radicaiffve Environmenta ring Program manuai. Quality Assurance Program for the Radioactive Effluent Control 'p / ' Program and the Radioactive Environmental Monitoring Manual using the guidance in US WRC Regulatory Guide 4.15 Revision 1, 4 February 1979. 6.8.2 $ach procedure and ahinistrative policy of 6.8.1 above, and changes I thereto, shall be reviewed by the PRC. Those matters pertaining to items 6.8.la, b, c. g, and h, above shall be approved by the Plant Superintendent prior to implementation and reviewed periodically as ( set forth in each document. The manager of Nuclear Operations shall also approve Security Plan and Emergency Plant implementing procedures. Proposed Amendment No. 155 6 11 i [

v>, s { :b h4 y,y i ' + 5 %,, = RANCHO SECO UNIT 1- @N;w.o TECHNICAL SPECIFICATIONS o n Administrative Controls b[g ' 6.8-PROCEDURES (Continued) c T 156> L6.8.3. Temporary changes to procedure 6.8.1'above may be made provided: k -( a.- The intent of-the original procedure is not altered.

b. -

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected. The change is documented, reviewed by the PRC and approved by c. the Plant Superintendent wi+.hin seven (7)< days of implemen- 'tation. 6.9 REPORTING REQUIREMENTS 5.9.1 In addition to the applicable reporting requirements of-Title 10, Code of Federal Regulations, the following reports shall be . submitted to the Director of the Regional Office of Inspection and Enforceau. unless otherwise noted. 3tartup Report 6.9.1.1 A sumary report of plant startup and powerescalation testing shall be submitt following (1) Receipt of an operating license; (2)- amendment of the license involving a planned-increase in power level; (3) installation of fuel that has.a different design or has been manufactured by a different its l supplier; and s(4) e modifications'that may have signis O.antly altered 'the nuclear, thermal or hydraulic performance of th plant. The' report shall address each of the-tests identified in the FSAR and shall include 'a description of the measured values of'the operating conditions or characteristics obtained during the~ test program and comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in Ifcense conditions based on other commitments shall be included in this report.

6. 9.1. 2

- Startup reports shall be submitted within (1) Winety (90)' days-following completion of the startup test program; (2) Ninety (90) , days following resumption or comencement of commercial power operation; or. (3) Nine (9) months following initial criticality, whichever is earliest. If the Startup Report does not cover all-three events (i.e., initial criticality, completion of. startup test program and resumption or commencement of commercial power: operation), supplementary reports shall be submitted at least every three (3) months until all three events have been completed. Proposed Amendment No. 155 6-12 i c.

-.~ - _.-~ _. g W RANCHO SEC0 UNIT 1 y*g _ TECHNICAL SPECIFICATIONS p 1'- Administrative Controls 1 ./ 6.9.2' Environmental'. Reports- ) y., 6.9.2.1. Annual Radiological Reports l Annual reports covering the activities of the unit, as described 155> below, for the previous calendar year shall be submitted as follows: 6.9.2.1.1 - Annual Occupational Radiation Exposure Report ~ The Annual Occupational Radiation Exposure Report shall be submitted to the Comnission within the first calendar quarter of - e?ch calendar year in compliance with 10CFR20.407. . _J -6.9.2.1.2 Annual Exposure. Report The Annual Exposure Report shall be submitted to the Commission within the first calendar quarter of each calendar year in accordance with the guidance contained in Regulatory Guide 1.16. l .6.9.2.2 Annual' Radiological Environmental Operating Report L h at [. lgry <. 6.9.2.2.1 Routineqadiological gnvironmenta13peratingieports covering p the operation of the unit during tR previous calendar year p -ggy7q shall be submitted prior to May 1 of. each year. 15T:P c 6.9.2.2.2 The Annual radiological Jnvironmental Jperating reports shali i inc1Fde sumiliaries, intefpretations, affd statistifal, evaluation of the results of the radiological environmental surveillance . activities for the report period. including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports, and an j assessment of the observed impacts-of the plant operation on the environment. The reports shall also include the results'of the land use censuses;- If harmful effects or evidence of irreversible damage are detected by the monitoring 4 the report action to alleviate the problem. problem and a plan,ned course of shall' provide'an analysis of the p L 155><' l-a \\. 5 {, 7i' Proposed Amendment No. 155 6-12a 1 o

~~ ' RANCHO SEC0 UNIT 1-

4 TECHNICAL SPECIFICATION $-

f. # "

Administrative Controls 6.9.2.2.2 (Continued).- 4 * ' ' Thejnnual gadiologicaljnvironmentalmeratingsports shall incrude summarized and tsbulated resuTTS in theYbreat of 155pi Regulatory Guide 4.8, of all-radiological environmental' samples taken during the-report period. In the event that some results are not available for inclusion with the report the report shall be submitted noting and explaining the rea, sons for the misting results. The missing data shall-be-submitted as soon as possible in a supplementary report.. The reports shall also include the following: a summary - ' description of the radiological environmental monitoring program; including sampling methods for each sample type, size and physical characteristics of each sample type, sample-preparation methods, analytical methods, and measuring equipmenti used; a map of-all sampling locations keyed to a table giving distances and directions from one reactor the result of' land-- use censuses,.and the results of ifcensee; participation in:the-Interlab Comparison Program. The annual-report shall also F155>c include information related to Specification 4.29, Uranium Fuel-Cycle Dose. 6.9.2.3 Semiannual Radioactive Effluent Release Report Routine radioactive effluent release reports covering the operation of the unit-during.the previous six months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report shall begin with the date of initial x criticality. 6.9.2.3.1. The radioactive: effluent release reports shall include a summary .of:the quantities of radioactive liquid and gaseous effluents and solid waste released from the. unit as outlined in Regulatory- -Guide 1.21. " Measuring, Evaluating. :and Reporting Radioactivity in Solid Wastes'and Releases of Radioactive Materials in Liquid

and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,* with data summarized on a quarterly basis, following the format of Appendix B thereof.

r155>- The radioactive effluent release report shall include a summary <L of hourly meteorological data collected over the report period. h Proposed Amendment No. 155 6-12b i l.i M------_= ~ - - ~ - ^ ^ ~ ~ ~ ~

.a1 + RANCHO SEC0 UNIT-1 .? ']Q -TECHNICAL' SPECIFICATIONS l ,y

Administrative Controls-6.9.2.3.1

. Continued) o,

The radioactive effluent release reports shall include an-155L assessment of the radiation doses from radioactive' gaseous and-liquid effluents to individuals due to their activities inside'

,i the site bounda'y (Figures 5.13 and 5.1-4) during the report r

v. -

period. All assumptions used in making these assessments (e.g., I specific activity, exposure time, and ' ocation) shall-be-included in.these reports. . The radioactive effluent release reports shall include the-following information for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents: a.; - A description of= the event and equipment involved. ' b. Cause(s) for the unplanned release. ij c. Actions taken to prevent recurrence. [ - Consequences of the unplanned release. d.- H Q &s The radioactive effluent release reports shall include an 1 y : :([ [^- assessment of radiation doses from the radioactive liquid and z. gaseous effluents released from the unit during each calendar b a, quarter, as outlined in Regulatory Guide 1.21. The assessment '" [ 4 of radiation doses shall be performed in accordance with the. -i

1 Offsite Dose Calculation Manual (ODCM).

'The radioactive effluent release reports-.shall include any changes to the PROCESS CONTROL-PROGRAM (PCP) and/or Offsite Dose' j Calculation Manual (00CM) made during the reporting period,'as provided in Specificatfur.s 6.15 and 6.16. a The radioactive effluent release report'shall: include tables for. comparison with Specifications 3.17.2, 3.18.2 'and 3.18.3. 'The -.s -. dgly-Deggaber,xagort;shall.ig,ls comparison with the annual-values n Spec ca o 3.18.2, and 3.18.3. t -The radioactive effluent release report shall also include events described. in Specifications 3.17.1,-3.17.3, 3.18.1 and .<-^ '3.20. r q i Proposed Amendment No. 155 6-12c

,g7 - - - - - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ^ ~ ^ v F % G. f -RANCHO SECO UNIT 1 1 ~ ,3, # TECHNICAL SPECIFICATIONS '~ k.au,, . [(6.9.2.3.1 Administrattwe Controls ' { d Continued) .s 15'5> I 1

t The Semiannual Radioactive Effluent Release Report shall include -

a the following information for each type of solid waste shipped offsite during the report period: a. Container volume, 'b. Total curie quantity (determined by measurement or estimate), e Principal radionuclides (determined by measurement or c. 0 estimate), ,s, d. Type of waste (e.g., spent resin, compacted dry waste evaporator bottoms), .u; Type of container (e.g., LSA, Type A, Type B. Large e. i Quantity), and l[ f.. Solidification agent (e.g., cement, urea formaldehyde). MONTHLY REPORT. l

6.9.3 of operating and shutdown experience, of lifts of the Pr

,l Safety Valves or*EMOVs,. of major safety related maintenance,y System 1 tabulations of facility changes.-tests or experiments-requiredand pursuant to.10 CFR 50.59(b), shall-be submitted on. a monthly basis to the Office of Management Information and Program Control U. S. 1 T - Nuclear Regulatory Commission, Washington, D. C. 20555, with a copy to the ~ Regional Office, postmarked 'no later than the month following the calendar month covered by the rep.15th day of each ort. ~ .-D o LICENSEE EVENT REPORT a 6.9.4 The LICENSEE EyfJll REPQBIS of Spectftcation 6.9.4.1.below,- includin corrective actions and measures to prevent' recurrence. shall be reported to the NRC as Licensee Event Reports. Supplemental repor 1 may be required to fully describe final resolution of occurrence. ts case of corrected or supplemental reports, a License Event ReportIn date, pursuant to the requirements of 10 CFR 50.73.sha11 i ex .N * \\ '< i. Proposed Amendment No.,155 6-12d a t E [

h RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS y, y,g.% Administrative Controls 17, ' MCENSEIEENTREPORT-N X~ '6.9.4.1' The types of events listed below shall be the subject of written. L' reports to the Director of the Regional Office within thirty (30). days of. occurrence of the event. The written report shall include, as a minimum, a completed copy of.a licensee event report fore, pursuant to 10 CFR 50.73 and the guidance of NUREG-1022. a. (1) The completion of any nuclear plant shutdown required by the plant's Technical Specification; or-(11) any operation or condition prohibited by the plant's-Technical Specifications; or (iii) Any deviation from the plant's Technical E Specifications authorized pursuant to 10 CFR 50.54(x). b.. Any event or condition that resulted in the condition of the j nuclear power plant, including its principal safety barriers. i-t being seriously degraded. or that resulted in the nuclear power p plant being: (1) In an unanalyzed condition that significantly compromised i plant safety; (ii) In a condition that was outside the design basis of the I L plant; or L L (111) In a-condition not covered _by the plant's operating-and emergency procedures. any: natural phenomenon or other external condition that posed an-c. a actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of. u duties necessary for the safe operation of the nuclear power ' plant. -1. WWtr ownt--oMpendit'- N -- ~ -- -^ - ^' r-_; ectuation of any Engineered Safety Feature (ESF), including the-Reactor Protection System (RPS). However; actuation of an ESF, including the RPS, that resulted from and was part of the s preplanned sequence during testing or reactor operation need not p. be reported. L e. any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed.to: 1. Shut down-the reactor and maintain it in a safe shutdown condition; .~ Proposed Amendment No. 155 . i Ch 4 6-12e I r

,- ; }[.g. .,- m .-1 RANCHO SEC0 UNIT 1 TECHNICAL SPECIFICATIONS i Administrative Controls LICENSEE EVENT REPORT' ~ 2. ' Remove residual heat; 3. Control the release of radioactive materiali or 4. Mitigate the consequences of an accident, f. - Events covered in paragraph 6.9.4.1.e of this section may include one or more procedural errors, equipment failures, i and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacies.: However, individual component failures need'not be reported pursuant to this paragraph if' redundant equipment in the same system was operable and, available to perfom the required safety function. - g. Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple systems or two independent trains or. channels to become inoperable in a single system designed to: 1. Shut 'down the reactor and maintain it in a safe shutdown condition; 2. Remove residual heat; 3. Control the release of radioactive material; or 4. Mitigate the consequences'of an accident,

h.

1. Any airborne radioactivity release that exceeded 2 times s .the applicable concentrations 'of the limits specified in: Appendix.B. Table !! _of.10 CFR 20 in unrestricted areas,- when averaged over a time period of one hour. 1

2..

Ahy liquid effluent release that exceeded 2 times the. limiting combined Maximum Pemissible Concentration (MPC). (see: Note 1 of Appendix 8 to 10 CFR 20) at the point of-t entry 'into the receiving water (i.e., unrestricted area)f for all-radionuclides except ' tritium and dissolved noble gases. when averaged over a time period of one hour. 1. Any event that posed an' actual threat to the safety of the-nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant including' fires, toxic gas releases, or radioactive releases. j. Failure of the pressurizer EMOVs or Primary System Safety Valves. Proposed Amendment No. 155 155>< 6-12f i

a 1 l:.r.df - RANCHO SEC0 UNIT 1- - V^ ' TECHNICAL SPECIFICATIONS ?* o ,v Administrative Controls i j.'1 1Special Reports =\\ 6.9.5 Special reports shall be submitted to the Regional A'dministrator.- .a Region V Office, within the time period specified for each report. These _ reports shall be; submitted covering the activities identified' below pursuant to the requirements of the applicable reference c specification: A. A one-time only. "Narra'tive Summary of Operating Experience" will' be submitted to cover the transition period (calendar year _ 1977). 8. A Reactor Building Structural integrity report shall be. p - submitted within ninety (90) days of completion of each of the ^ + following tests covered by Technical Specification 4.4.2 (the integrated leak rate test is covered in Technical Specification. p -4.4'1.1). 1. Annual' Inspection [* t 2. Tendon Stress Surveillance e, 3. End Anchorage Concrete Surveillance-p 4. Liner Plate Surveillance t iL C., Inservice Inspection Program n h >. _ i D. Inoperable Accident Monitoring Instrumentation 30 days (3.5.5) 4 E. Status of' Inoperable Fire Protection Equipment F. ' Inoperable Emergency Control Room /TSC Ventilation Room Filter System 1! El ._G. RadioactLve Liquid Effhent Jlosa,. - M da Im H. Noble Gas Limits 17 30 days (3.18.2) I. Radioiodine and Particulates 1 30 days (3.18.3) q J. Gaseous Radwaste Treatment 30 days (3.19) ,} K. Radiological Environmental Monitoring Program 30 days.(3.22) 1 a L. Environmental M'onitoring Point Substitutions 30 days (3 22) J '1SSH M. Solid Radioactive Wastes i 30 days (3.21) 1 d N. Fuel Cycle Dose 30 days (3.25) i 0. Deleted i; h q P. Steam Generator Tube Inspection 30 days (4.17.5) Proposed Amendment No.155 }f

]ST p4.

6-12g 5 J, = --- = N

,e g y y= V p ri < w RANCHO SEC0' UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls L b. Records of.new and irradiated fuel inventory, fuel transfers and I assembly burnup histories. L Records of facility radiation and contamination surveys, c. i d. Records of radiation exposure for all individuals entering radiation control areas. Records of gaseous and liquid radioactive material released to' e. the environs. f. Records of transient or operational cycles for those facility p, components designed for a limited number of transients or cycles.

j l

L .g.. Records of training and qualification for current members of the: i plant operating staff, h. Records of in-service inspections performed pursuant to these: Technical Specifications. i 1. Records of Quality Assurance activities required by the QA Manual. j. Records of review perforvad for changes made to procedures or ' equipment or reviews of tests and experiments pursuant to { 10CFR50.59. 4 .k.- Records'of meetings of the PRC and the MSRC. 1. Records for Environmental Qualification which are covered under the provisions of paragraph 6.14. 1 155x. m. Records for the Radiological Environmental Monitoring Program., 1 Records of'the maintenance of all hydraulic snubbers If sted in- -n.. Table 3.12-1. 6.11 RADIATION PROTECTION PROGRAM-x' V Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be-approved, maintained and adhered to for all operations involving: personnel radiation exposure. i .6.12 Deleted I' 1-Proposed Amendment No. 155 6-14

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ML20055E298

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