ML20084U587
| ML20084U587 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/12/1991 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20084U579 | List: |
| References | |
| NUDOCS 9104190309 | |
| Download: ML20084U587 (84) | |
Text
{{#Wiki_filter:- - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _ _ _ _ _ _ _ ____-_____ _ _ _ _ - ___._ l LAR 90-0023 Markod Up Technical Sp2cifications ) Tage 1 of 84 i I INDEX 1 DEFINITIONS l SECTION PAGE 1.0 0(FIN!TIONS DEFINED TERMS......................,......................... 11 T H E RMA L P 0 W E R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 RAT E D T H E RMAL P 0 W E R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 OPERATIONAL M00E............................................. 11 ACT10N....................................................... 11 O P E RAB L E - O P E RA B I L I T Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 REPORTABLE EVENT............................................. 1-2 CONT A I NME NT I N T E GRI T Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 CHANNEL CAllBRAT!0N.......................................... 12 CHANNEL CHECK................................................ 12 CHANNEL FUNCTIONAL TEST...................................... 1-3 C O RE AL T E RAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 S H UT DO WN MA R G I N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 10ENTiflED LEAKAGE........................................... 13 U N I DE N T I F I E D L E A KAG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 P RE S SU RE BOUN DARY L E A KAG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 CONT ROL L E D L E A KAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 QU AD RAN T POW E R T I L T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 DOS E E QU ! V AL ENT l 131. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 T. AV E RAGE D I S I NT E G RAT I ON E N E RGY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 STAGGERED TEST BAS!5......................................... 1-5 FREQUENCY NOTAT10N........................................... 15 AXIAL POWER IMBALANCE........................................ 1-5 SHI EL D BUILDING INTEGRITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 REACTOR PROTECTION SYSTEM RESPONSE TIME...................... 15 SAFETY F EATURE RESPONSE T IME. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 PHYSICS TESTS................................................ 1-6 STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIME..... 16
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P ROC E S S C O NT ROL P R 0G RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 6a knendment No. 38. 86. 93 day!$ BESSE. '.JNIT 1 1 9104190309 91o4 9 PDR P ADOCK 05000546 PDR
1 1 LAR 90 0023 Marked Up Technical Specifications Page 2 of 84 INDEX DEFINITIONS SECTION PAGE 1.0 der tN!T1035 (Continued)
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- P Li, Li b w pr- p .ruw, e s e a e e s e e s , , s a a e , e e a e e a e e e g e e s . . e e i e s e i e i e i i ww MEMB E R( 5 ) 0F T HE PUBL I C. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 6b S I T E B 0UND ARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 6b U N RE ST R I CT E D ARE A. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 6b 4.......m, b-..,...... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . .. . . . . . . . . . . . ..
CORE OPERATI NG L IMIT S REP 0RT. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 6c 1 -7 OP ERAT 10HAL H0 DES (T ABL E 1.1 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i FREQUENCY NOTAT ION (TABL E 1. 2) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 i I 4 1 l i l l DAVIS-BESSE.: UNIT 1 la koendment No. 58, 144 1
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l LAP, 90 0023 ! Harked Up Technical Specifications Page 3 of 84 INDEI i
;, LIMITING CONDITIONS FOR OPERATION AND SURVII' U.NCE REQUIREMENTS i !stCTION Pact ;l 3/4.2 POVER O!sTPlwrION LIMITS i
3/4.2.1 AIIAL F0VER IMRALANCE . . . . . . . . . . . . . . , . 3/4 2 1 1 3/4.2.2 NUCLEAR REAT FLUE 807 CIANNEL FACTOR - Fg . . . . . . . 3/4 2 5 3/4.2.3 HUCLEAR ENFEALFY K!lt 307 CIAltitL FACTORg- FN . . . . . 3/4 2 7 i [3/4.2.4 OUADRAFT F0VER TILT . . . . . . . . . . . . . . . . . . 3/4 2 9 3/4.2.5 DNS PARAMETERS. . . . . . . . . . . . . . . . . . . . . 3/4 2 13 f 3/4.3 INSTRUMENTATION 3/4.3.1 P1 ACTOR PROTECTION SYSTEN INSTRUMENTATION . . . . . . . 3/4 '3 1 3/4 3.2 SAFETT ST5 TIM INSTRUMENTATION l' Safety Features Actuation System. . . . . . . . . . . . 3/4 3 9 Steam and Feedvater Rupture Control Systen . . . . . . 3/4 3 23 Anticipatory Reactor Trip Sys tee. . . . . . . . . . . . . 3/4 3 30a 3/4.3.3 MONITORING INSTILUMENTATION Radiation Monitoritig Instrumentation. . . . . . . . . . 3/4 3 31 Incore Detectors. . . . . . . . . . . . . . . . . . . . 3/4 3 35 Seismic Instrumentation . . . . . . . . . . . . . . . . 3/4 3 37 Heteorological Instrumentation. . . . . . . . . . . . . 3/4 3 40 Remote Shutdovn Instrumentation . . . . . . . . . . . . 3/4 3 43 Pos t. Accident Instrumentation . . . . . . . . . . . . . 3/4 3-46 Fire Detection Instrumentation. . . . . . . . . . . . . 3/4 3 52 W46 W QgaA T A Q f outgpfg _ . - .. . - , Me s t o r ' -, ' -_ _- ^. .- _ _ - ^. ^ ^. ' - . 3 / 4 3 - $] 3/4.4 REACTOR C001Rff 3YSTEM 3/4.4.1 C0014ff LOOFS AND COOLANT CIRCULATION 5tartup and Fever Operation . . . . . . . . . . . . . . 3/4 4 1 Shu t d own and Ro t S t andby . . . . . . . . . . . . . . . . 3/442 3/4.4.2 SAFETT VALVES - $5VfD0VN. . . . . . . . . . . . . . . . 3/4 4 3 3/4.4.3 SAFETT VALVES AND FILOT OPERATED RILIEF VALVI - OPERATING . . . . . . . . . . . . . . . . . . . . . . 3/4 4-4 j DAVIS.BESSE, UNIT 1 IV ^**" **" ' '
LAR 90 0023 Marked Up Technical Specifications Page 4 of 84 INDEX h i LIMITING CONDITIONS FOR OPERATION AND SURVEILI.ANCE REQUIREMENTS 1 SECTION l PACE i i 3/4.11 PAD 10 ACTIVE EFFLUENTS 3/4.11.1 LI QUI D E r rLUDrt s . . . . . . . . . . . . . . . . . . 3/4 11-1
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1 1 LAR 90-0023 Markcd Up Technical Specifications rage 5 of 84 1 l INDEX l
- 1. BASES e
I SECTION PJii 3/4.9.6 FUEL HANDLING BRIDGE OPE RABILITY. . . . . . . . . . . . . . . . . . . . . . . . . 8 3/4 9 2 3/4.9.7 CRANE TRAVEL FUEL KANDLING BUILDING. . . . . . . . . . . . . . . . . . . . . B 3/4 9 2 3/4.9.8 COOLANT C I RCUL AT I ON. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/ 4 9 2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM. . . . ... . . . . . B 3/4 9 2
. 3/4.9.10 and 3/4.9.11 WATER LEVEL REACTOR VESSEL AND I
S TO RAGE P00L . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 9 2 1 3/4.9.12 STO RAGE POOL V EKT ILAT !0N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/ 4 '9 3 l,3/4.9.13 SPENT FUEL POOL FUEL ASSEMBLY STORAGE..................... B 3/4 9 3 i 4 i 3/4.10 SPECI AL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT. INSERTION AND POWER DISTRIBUTION LINITS..... B 3/4101 3/4.10.2 PHY S I CS T ESTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 /4 10- 1 3/4.10.3 R EACTOR COOL ANT L00PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/ 4 10 1 3/4.10.4 S H UT DOW N MARG I N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 10 1 i ~ 3/4.11 R4010ACT!VE EFFLUENTS 3/ 4.11.1 - L I QU I D EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11 1 1. 3/4.11.2 GAS EQU S E F FLUENT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 131 7'
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LAR 90-0023 Marked Up Technical Specifications Page 6 of 84 li N OtstcN rtATunt$ SECit0N pfg 5.1 $ttE Exclusion Area.................................... ............ 51 I w D^*- 'l-a-t -- ia tL IArit c.1 w-- - r , , ,-o u,.x,. m,.m,,,,1,.,,___1_. i . . . . . .
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_w . y Configurttion.................................................. 51 Design Pressure and Temperature................................ 54 S. 3 REACTOR CORE fuel Alsemblies................................................ 54 Control Rods................................................... 54
- 5. 4 REACTOR COOLANT SYSTEM Design Pres sure and Tempera ture. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54
{ Volume......................................................... 55 S. S METEO ROL OG I C AL TOWE R L OCAT10N. . . . . . . . . . . . . . . . . . . . . 5. 5. . . . . . . . . . . . l 5.6 -FUEL STORAGE i , C r i t i ca l i ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-5 i L Drainage....................................................... 55
-Capacity....................................................... 56 5.7 COMPONENT CYCL IC OR TRANS !ENT t. tMIT. . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 6 DAVIS BESSE. UNIT 1 XIV Amendment No. 38 . . . , . , ,....,-..r.- -=-r --+- r ' ' ' ' " " * * ' - - -
- i LAR 90-0023 Marked Up Technical Specifications 1
Page 7 of 84 { INDEX l ADMINISTRAT!VE CONTROLS SECTION g Mee t i ng F r eq u e n cy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 69 Q u o r um . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .6. 9. . . . . . . . . R e v i ew . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6. .1 .0. . . . . . A; d i t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 1 1 Au t ho r i ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 12 Records................................................... ( 12 6.5.3 Technical Revi ew and Contro1. . . . . . . . . . . . . . . . . . . . . . . . . . . . .6 12 6.6 RE PORT ABL E EVE NT ACT !0N. . . . . . . . . . . . . . . . . . . . . . . . . . . 6. .12a .......... 6.7 S AF ET Y ( ! Mit V 10L AT 10N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6. .13. . . . . . . . . 6.8 P ROC E DU R E S AN D P R0 GRAMS . . . . . . . . . . . . . . . . . . . . .6. 13 .................
- 6. 9 REPORTING RE0V!REMENTS 6.9.1 Rou t i n e Repo rts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 14e 6.9.2 Special Reports.......................................... 6-18 6.10 R E C O R D R ET E KT ! 0N . . . . . . . . . . . . . . . . . . . . . . . . . . . .6-. 18 . .a. . . . . . . . . . . . . .
'6.11 gi RA0!Aff0N PROTECTION PR0 GRAM................................. 6 20 11 I!
l 6.12 HIGH RAQlATION AR1A.......................................... 6-20 I.6.13 i' ENV I RONMENTAL 00AL I F I CAT 10N. . . . . . . . . . . . . . . . . . .6. 21 .............. 6.14 P ROC ESS C0KTROL P ROGRAM (PCP ) . . . . . . . . . . . . . . . . 6. 2. .2 . . . . . . . . . . . . . 6.15 0FF5 ITE DOSE CALCUL ATION MANUAL (0DCM) . . . . . . . . . 6. 22 .............
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LAR 90-0023 J Marked Up Technical Spselfications Page 9 of 84 ZM cC r " A " The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test 4 and determinations to be mace to ensure that procest-ing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomolished in such a way as to assure compliance with 10 CrR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
.b Ws: T 6 The OFFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and parameters used in the calculation of offsite cosas resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program. The 00CM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Pro-grams recuired by Section 6,8.4 and (2) descriptions of the infocmation that should be included in the Annual Radiological _ Environmental Operating and Semi-annual. Radioactive Effluent Release Reports requireo by Specifications 6.9.1.10 -and 6.9.1,ll.
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LAR 90-0033 Marked Up Technical Specifications Page 10 of 84 DEFINITIONS , . . - - . ---- yk
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' 1.37 NettR($) 0F THE PUBLIC shall include all ponens who are not ecemational'.y associated with the plant. This category sees not include emeleyees of the utility, its centractors er veneers. Alse escluded from this catsoery are persons was enter the sita ta service eeuipment er to make oe'(veries. This catagery does include persons who
- use portions of the site for recreational, occupational or other purposes not associated ,with the plant.
$ITE B00NOAkY 1.34 The SITI BOUNDARY shall be that line beyond which the lane is neither owned, nor leased, nor otherwise controlled by the licensee.
pat!TRICTEDARIA 1.39 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not centnlled by the licensee for purposes of protection of individuals thus amosure to raciation and radioactive estarials or any area within the SITE 80LMDARY used for residential quarters or for Ineustrial, camercial, institutional, and/or recreational punases. The definition of ' UNRESTRICTED AREA used in islesenting the Radiological Effluent Technical Specifications has been amanned over that in 10 CR 20.3(a)(17). The U P-l RESTRICTID ARIA beuneary asy coincies with the esclusion (fenced) area beune-
- - 4ry, as defined in 10 CM 100.3(a), but the UNRESTRICTED ARIA does not include I areas over wetar bedies. The concept of UNRESTRICTED ARIA 3. established at or beyond the SITE BOUNDARY, is utilized in the i.IMITING ColCITIONS FOR OPERATION to toep levels of reaisective asterials in lievid and gaseous effluents as low as is reasonably achievaele. oursuant to 10 CFR 50.384.
OEWATTRING Dg4ero . L eo _ --a...
. . _ . . _ g 'f; .n .-_-.
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rits- E i s: W :Z Z 9 " ~ " ~ ~ ~~ 1 i DAVI$-lt15E, UNIT 1 1 1-6k Amendment No. 86
LAR 90 0023 Marked Up Technical Specifications rage 11 of 84 TASLI 1.2 FRf0VENW NOTATt_qN NOTATION FRt0VENCY
$ At least once per 1.2 hours.
O At least once per 24 hours. V At least once per 7 days. M At least once per 31 cays. Q At least onca per 92 aays. SA At least once per 6 months.* l A At least once per M sentas.*
. f/U Prior to each rsectar startun.
"M r n ::n -} :::.
N/A Not toplicable.
*!n these Technical Specifications. 6 months is defined to be 184 days, and 18 months is defined to be 550 days.
,~ cay!$ Stast. UNIT 1 13 M"""I 'N'
LAR 90-0023 Harked Up Technical Sp2cifications Page 12 of 84 INSTRUM Aft 0N l RA010 ACTIVE 70VfD EF8tVENT W N!708160 IN$7RUMENTATION
, 1 t,1N! TING CONDIT N FOR OP(RATION 3.3.3.9 The radio ive liovid effluent monitoring instrumentation channels !
shown in Tacts 3.3=., shall be OPERA 8LE with their stars / trip setecints set to ensure that the 1 its of Specific.ation 3.11.1.1 are not exceeceo. The l alars/ trip setpoints o these channels shall be detemined ano acjustad in accordance with the met cology and parameters in the 0FFl!TE 00$t CALCVLA- 1 T!ON MANUAL (00CM). 1
- APPt,!CABILITYt At all time 4 ACTION!
- a. effluent monitoring instrumentation channel With alars/ atrip recicactive setpoint leslioa @bgservative than recuired by the acove specification, without a msuspend the release of radioactive 11ouid effluents monito Y the affected channel, or ceclare the channel inoperacle, or enan setooint so it is acceptacly conservative.
- b. . With less than the minimum n e of radioactive licuid effluent monitoring instrumentation chann s OPERA 8LI, talte the ACTION shown in Tacle 3.3 15. E.nort best ef fe to return the instruments to CPEAASLE status witnin 30 cays and if unsuccessful, exclain in the next Sesiannual Radioactive Eff1 nt Release Report, wny the inoperaDility was not corrected in a moly manner,
- c. The provisions nf Specifications 3.0.3 a a 3.0.4 are not applicable, l
$VRv[f t.LANC[ R(QUIR(M(NT$ ,
4.3.3.9 Each radioactive liouia effluent switoring inst ntation enannel ! sna11 be demonstrated CPERA8LE by perfemance of the CHANNE CH(CK, $00RCE ! CHECK. CHANNEL CAlllRATION AND CHANNEL FUNCTIONAL TEST opera ens at the frecuencias shown in Table 4.3 15. l l l l l OAY!$ lESSE, UNIT 1 3/4 3 57 Amendment No. 86
S
- i c.
TAttE 3. 3 - 15 O RADIOeCTIVE LIQUID EFFLMENT NONITORING INSTEMNDtTATIcet N urarnum g ruassets t 4 INSTasuprT aFamaaLE AFFLI ILITY acTIost
- ' 1. Gross Radioactivity Healters Frevidleg Alares and Amtematic Termienties of Belease
! a. , Liguld Raduaste Ef flueet Line h ' 1 (1) 23 (either Wiscellaneses or Cleen. but met both sleuttaneously) o[f,
- 2. Flow sate IIeasurement Devices yY, h a. Liguld Raduaste Efilment Line 1 (1) 24
- b. Diluties Flew to Collection Bos 1 (I) 24
- 3. Cross Beta er Gamme Badleectivlt Nemiters Providleg Alors But ygg Freviding Autoestic Teral se ; ;;. "
et Release ,13 w e6
- m. Turbine Buildi Store Sewer Drain 1 (1) 1" 8 24, 25 ,gw wg E
O 7 h b e, 3
=
LAR 90-0023 Marked Up Technical Specifications Page 14 of 64 TABLE 3.3-15 (continueo) TABLE NOTATION (1) Dur g radioactive releases via this pathvay ACTION 23 Vith the number of channels 0FERA8LE less than reautree by the Hintaus Channels OPERABLE requirement, ef fluent releases may be resumed, provideo that prior to initiating a releases least two independent samples are analysed in accordance th Specification 4.11.1.1.1 for analyses performed with
. ep(atch A as tvo independent verifications of the release rate ca ns are performed:
- 3. At le tA\indeoendentverificationsofthedischarge valving r riormed l
Otherwiss, susp lease of radioactive effluents via this pathvay. ACTION 24 Vith the number of annels OPERABLE less than required by the Hintaus Channels 0F LE requirement ef fluent releases via this pathway may continue p vided the flow rate is estimated at least once per 4 hours during etual releases. Pump curves may be used to estimate flov. ACTION 25 Vith the number of channels PERA4LE less than required by the Minimus Channels OPERABLE reg resent, offluent releases via this pathvey may continue provided at at least once per 12 hours. grab samples are collected and lysed for gross radioactivity (beta or ganas) at a lover limit detection no greater than 10 U WCi/al. l r l DAVIS-BESSE, UNIT 1 3/4 3-59 Amendment No. $$, 135
l IABIE 4.3-15 RAnIGACilVI IlfilD IIIItRNI MWillDRINr. INSIRINNIAIIDH SERVilli ANCE RIqutRIMENIS O a h DiANN8. L SOURCE OlANNLL Ii DNAL g OffCK OMCK CAtlBRAlfall EST
- INSIRieENI E Gross Beta er Gamma Radioactivity 3 1.
Monitors Providing Alarm and g Amtematic Isoletten I3I qIII Liquid Radeaste Effluents Line D IU P R a.
- 2. Flow Rate Monitors b
S R Q Liquid Raesasto Ef fIment Line D(4) . a. Of N.A. R Q
- b. Dilution iIow to Collection Bom Y
8
- C
"?"
~18
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~ g .#" g "a E
=
~
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. 7 2
3.,
LAR 90 0023 Marked Up Technical $pacifications Page 16 of 84 TABLE 4.3*15 (Continvee) Tillt NOTATION (1) Duri nleases via this pathway. (2) The C (L FUNCTIONAL TEST shall also comonstrate that automatic solation of this pathway and control room alam annunciatio occurs if the instrument incicates sessund levels above e alors/ trip setpoint. (3) The initial C L CALIBRATION for radioactivity sensurement lastrumentation s 11 A performed using one or sort of the reference stancarcs 6cifified by the National luteau of
- Stancares or using s s that have been obtained free suppliers that partici n osasurteent assurance activities with M85. Thest standa 8 16 permit calibrating the systee over its intanceo f energy and rate capac111 ties.
For sucsecuent CHANNEL CALI N, sources that have been relatec to the initial calibr t should be used, at intervals of at least once per eighteen . For high range monitoring instrumentation, whe n c411brati th a radioactive source is imoractical, an electronic calibre ion say De suostitutea for the raciation source calibration. (4) CHANNEL CHECK shall consist of verifyi indication of flow curing pericas of n1 ease. CHANNEL CHEC snal) be saae at least once cally on any cay on wnich continuous, ericotc. or batch releases are sace. P l l l DAV!$ BESSE. UNIT 1 3/4361 Amendment No. 86 l l v9 - . - - . , _
LAR 90-0023 Marked Up Technical Specifications l' age 17 of 84 INSTtLWENTATtDN WA.
.. S. .T.E. 6, A. 5 ,A,f, l...N.M .0.*... '4.. E.M ,m,,,,,m, m ...,
. . . . ..... ....... < m. ,37,,.m,.. $ . . . . . ~ . u t!MITING CONOTTION FOR OP! RATION T os *a 3.3.3.4f" The4 r93. 4 .s a-*
= ----: .6te.n
--"- -' y)"-" soni to r ' et- - itt'e : 2r !-
-- " -' ' ' " small be OPERML1 with am% setoointe set t5-ensure that the limits of Specification 3.u.2 are not exceeoec. -4+e-
- ! -'t 4: ._,2 e 4-u ^f
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ans.4ek: t n ' - -
- i. . . _ - _ 1. ,.xi. , ..u
~ g,,t,.,3g ti.r..y. y Deta3 4 r..n o t. m w.it p. mp t. k . ACTION: h wask gas syson eyta With : r r i----i n :: , n t: :f, n r^ monitor 4*g-i.,;; w .:. n ar. a. c:rci alarw449 settoint less conservative than roovirec ey the anove Specification. =! ten r! y :rr:n 2: r;':.;; ;f
! r 'e nt*"* ; : c'*'" -te r -tterr by 15: eff=:n = = n!, er oeclare the enannel inoceraale :r rr;: 2: :: :f r.: ;; :t i;-
l r r i e ty r r ^tt": ad c.umply with ACTS 0# b. r-'-'-- 146 EAT *(,,, " ^d
- b. F .l ', = 'r: " :- the -' 8 - -_-^:7 r'ertin ;rr7: Ofdin-t-
.ry..u_
_ 1. . _ 2 m ......_ .. 4.. ......t. amenin, e . .. .m .
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l " i' ri $rds- n L Ae4444sti n Ef*'ert *:!:n: " nn w-
! n; ' nn a t ' ! ty _n = n r;;c;;'r;ti m ar.r..
I i' C. The provisions of Specifications 3.0.3 and 3.0.4 are not applicaole.
$URVf!LLANC! tt0VIREMNTS
- g. . . . al& f. AT a.. ' O. ". . . . . . .
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LAR 90-0023 Pcrk4 Up Technical Specificatitns Page 19 of 84 i a I ;
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I E TASIE 3.3-16 m ' 3 i BADIOACTIVE CASEGW5 EFFIDENT NostITORING INSTRINeENTATION g :: NENslNRt y M INSTRISIENT OPERASt.E E AFFt.ICASILITT FARA00ETER ALTIeM I. Naste Gas Decay System (provides setematic feelaties) a3 Noble Gas Activity Benitor 1 (I b Radleectivity Neasurement 26 , b. Effluent System Flow Rate 1 se System Flow Rate Measurement 21 IIesserf ag Bevles 5 l y
- 2. Vaste Gas Systes (O7 /
\
(provides alare functies) >
- a. Ozygen Noetter 1 (2) Z Ozyges 29
- 3. Containment Forge IIemitering Sys (provides automatic !seletten)
- a. Isoble cas Activity isor 1 (1) Radioactivity Neasurement 28 i
r n i O s
E h TABLE 3.3-16 (Continued} E g RADIDACTIVE GASSOUS EFFLiftsfr NOI8ITORING INSTBtBIEFTATION y h, NININUIl renamnet t
- INSTRWIENT Gramaane AFrg.ICASILITY L FAEAfGETER ACTION
- 4. Station vent stecit kl (provides alare functies) y4 a., Noble Gas Activity Honitor 1 (I) O_.
Radioactivity Neasurement 28
- b. Iodine Sampler Cartridge
*g 1 (1) Verify Presence of Ju Cartridge
- c. Farticulate Sampler Filter 1 (I) Verify Presence of Filter 30
- d. Effluent System Flow (I) Systee Flow Rate Rate Iteaserlag Device 21 ,
messerement {
- e. Sampler Flot, Rate Measuring 1 (I) Sampler Flow Rate Bewice 21 nesserement 7g
%E-{
m a. 8 o#5
- e 22 i
X
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LAR 90-0023 Marked Up Technical Specifications Page 22 of 84 TABLE 3.3-16 (Continued) TABLE NOTAff0N (1) During ra osctive vaste gas releases via this pathvey. (2) During addit ons to the vaste gas surge tank ACTION 26 Vith the number of channels OPERABLE less than required by ye Minimua Channels OPERABLE requirement. the contents of thg tank may be released to the environment provided that pri r to initiating the release
- 1. t least tvo independent samples are analysed in aciordance with Specification 4.11.2.1.1 for analyses '
perLormed vith each batcht
- 2. At le\s t tvo independent verifications of the release rate ca eu ons are pectormed:
- 3. At least opendent verifications of the j
discharge are performed. l ACTION 27 Vith the number of 1s OPDA8LE less than required by the Minimum channels 12 requirement, effluent releases via this pat my y continue provided the flow rate is estimated at 1 nee per 12 hours. ACTION 28 Vith the number of channe -6PERA8LE less than required by the Mintsua Channeis OPERAh releasesviathispathwayaq(.Erequirseent,efiluent continue provided grab samples are taken at least on e per 8 hours and these samples are analysed for gross ctivity vithin 24 hours. ACTION 29 Vith the number of channels 0F LE less than required by the Minimus Channels OPERABLE requ roment, additions to the vaste gas surge tank may continue p vided another eethod for ascertaining oxygen concentratio , such as grab sample analysis, is taplemented to provida se sureaants at least once per four (4) hours during desassin and daily during other operations. ACTICH 30 Vith the number of channels OPERA 512 less t an required by the Minimum Channels OPERA 8LE requirement, e luent releases via this pathway aey continue provid samples are continuously collected with auxiliary sampling quipment, as required in Table 4.11-2. , Amendment No. If,135
- DAVIS-BESSE, UNIT 1 3/4 3-65
IAtlE 4.3-16 RAHIDACIIW CASIfpf5 ElllHINI pe411106il{lN51MIMENIAlloff $4NIVE Ill, ANCE MI)MIMN!NIS T
. E M ~
CN4 feet L 50HBC[ CHAf5It t iINICI tel510esullt DECK OIECK cat 1884I1088 51 E
. 3. Wste Gas Decay System III q(3)
- a. liable Gas Acttwily Blonller- P P 3(5
- b. I f fluont Systee F low Sate P III N/A R q
- 2. W6te Gas System
- a. Gwygen Monitor S I2I A Q I0I M/A
- 3. Cental e t Pertre vent system
- o. flessle Gas Activity Healter 9( F I ;M( R II q III
- 4. Statsen vent Stu t
- a. Sloble Gas Activity 9 tent BI M R I qI *I 5N5 is. Ioellne Sampeter W N/A N/A N/A S{
g c. PartItalate 1er W(I) N/A le/A N/A *6c 1" S E d. System twent iIow Rate gg) ,gu 2 fleas eeent Sevite S N/A R N/A *$ S 1 , e. aeg.ler flaw Rale n ,o Measestement Devlte W ,g N/A R N/A - 8
LAR 90-0033 Marked Up Technical Specifications Page 24 of 84 TABLE a.3 16 (Continvec) TABLE NOTATf0N (1) Durin radioactive wasta gas releases via this pathway. (2) During a itions to the wasta gas surge tant. (3) The CHANNEL FUNCTIONAL TEST shall also comonstrate that automatic isolation of this pathway ane control rose alars annunciation occurs if the natruonnt indicates measuree levels above the alars/ trip se int. (4) The CHANNEL TUNCT)QNAL JEST shall also comonstrate that
- control roos alarmin(pleistion occurs if the instrtament indicatas seasuree i ve eve the alars/ trip sotacint.
(5) The initial CHANNEL CA ~ T' N for radioactivity measurement instrumentation shall b o reed using one or mere of the reference stancares certi ted,3g the National Bureau of Standares or using stancareg have been obtainee free suppliers that participata fit syrement assurance activities with NS$. Theaastandaressyl tvit calibrating the systes over its intenose range of one. g; rata cassailities. .. For suasecuent CHANNEL CALIBRATION, ources that have been related to the initial calibration sneul be used, at intervals of at least once per eignteen sonths. F high range monitoring instrumen-tation, wnere calibration with a re cactive source is isorac-tical. an electronic calibration may e suestitutte for the raatation source calibration. (6) The CMANNEL CALISAATION shall incluce the use of stancare gas samoles containing a nominal:
- 1. One volume percent oxygen, balance nitro en; and
- 2. Four volume pe, cont oxygen, balance nitrog .
(7) During containeent purges. (8) When used in a continuous noce. 0AV15+8E13E. UNIT 1 3/4 3 67 Amendment No. 86 i l
. . . _ , . , . , _ _ , . . _ , . _ . . . . _ . . _ , - ~ . . _ , _ , . . - - , m ,- .
LAR 90-0023 Harked Up Technical Specifications Page 25 of 84
' 3/a, RADI0 ACTIVE EFFLUENTS 6 3/4.u. LIQUID TFFLUENTS CONCEKTRAT N
~ LIMITING COND N FOR OPERATION
- 3. u.1.1 The conc tration of radioactive material released in licuio effluents to UNRESTR ED AREAS (see Figure 3 u-1) shall be limited to the concentrations so ifisc in 10 CFR Part 20.106 for racionuclices other than dissolved or entrained not,la gases. For cissolved or entrainec no01e gases, the concent tion shall be limited to 2 x 10** sicrocuries/m).
APPLICABILITY: At all time . ACTION: (
- a. With the concentration of ra l effluents tve material ralsased in liceid to UNRESTRICTED AREAS ex (ec g the aoov: .
*+s. without l celay restore the concentration to i .the accor ; w...
- b. The provisions of Specifications 3. and 3.4.4 a w :e applicable.
SURVEILLANCE REOUIREMENTS '
; 4. u.1.1.1 Radioactive licuid wastes snail be samole;. Tatte 4nd 4.analyzed u-1.
accorcing to tne sampling and analyais program 4.n.1.1.2 The results of the radioactivity analy s small be used in accorcance with the metandology anc parameters in t 00CM to assure snat the concentrations at the point of release are mainta oc within the limits of Specification 3.n.1.1. 9 DAVIS-8 ESSE, UNIT 1 3/4 11-1 Amendment No. 86 i
- . _ . _ . . ~ . . . . . _ . , - - . -.- -- . . - . . - . _ - . . - . . .
LAR 90-0023 Marksd Up Technical Spacifications Page 26 of 84 TA8LE a.11-1 ! RADICACTIVE (!0VfD WASTE SAMP(ING AND ANALYS15 PROGRAM Minimum t.ower unit Liquid Release Type Sasoling Analysis Type of Activity of Detection Frequency Frequency Analysis (LLD) (yci/al), P P A. Satcn Waste Ea Batch Each Batch Principal Gamma 5 x 10'y D Release Tanks a bittees' I 131 1 x 10**
- One Baten/M Dissolved ano 1 x 10
Entrainoa Gases P '@ H-3 1 x ig Each Baten C s1
/ Gross Alpha 1 x 10" Composite c
$r-89, $r-90 5 x 10.a Each Baten k55 1 x 10'*
8.. Turcine Building- 8 Prin pal Gaana-- -5 x 10
- Sumo /$ tors Continuous 5 bitte Sewer Orain I Ul f
\ 1 x 10' P P Principal G $ x 10
.7 3 C. Concensate Each latch Lach Satch l Deeineralizer Esitters#
Bacrwasn f .. I-ul x 10 N l. DAVI5-BESSE, UNIT 1 3/4 11-2 Amendment No. 86
LAR 90-0023 Marked Up Technical Spscifications Page 27 of 84 4 Y TA8LE 4.121 (Continued) TA8L[ @ TATION
- a. The LLD s the smallest concentration of radioactive material in a sample will be cetectsJ with 955 probability with 5% procanility of falsely oncluding that a blank ooservation represents a "real" signal.
For a particula measurement systas (wnich may incluce racio cnemical separation): gg , 4.66 s b
- E*V - 2.2. ' Y axp(-Aat) d
.nere p LLD is the lower limit o adection as cefined above (as DCi per unit mass or volume); p sbis the standard deviation At background counting rate or of the counting rata of a b) sample as appropriate (as counts per minute);
f
. E is the counting efficiency (as ce ts per transformation);
V is the sample size (in units of mass e volume); 2.22 is the nuncer of transforsations per inute per picoeurie; Y is the fractional radiochemical yield (wnen policacle); A is the radioactive cecay constant for the part ular radionuclice; at for plant affluents is the elapsed time between t. siccoint of sample collection and time of counting. It should be recognized that the LLD is defined as an a orderi (before the f act) limit recrosenting the capaci11ty of~a measure nt system and not as an a costeriori (after the fact) limit for a particular measurement. DAVIS-BESSE, UNIT 1 3/4 11-3 Amendment No. 86
l l LAR 90-0023 l Marked Up Technical Specifications Page 28 of 84 TA8LE a.11 1 (Continued) TA8LE NOTATTQN
- b. The peine al gasses esittars for which the LLD specification will apply an e.xclusi ly the following radionuclides: Mn-54 Fe-59, Co-58, Co-60, In-65, Me-99, Cs-134. Cs 137, and Ce-141. For Ce-144, the LLD is 2.0x10-8 pC1/a Other peats which an esasund and identified shall also be reporte Nuclides which are elow the LLD for the analysis should not be reported
, as being present at he LLD level. When unusual circumstances result in l LLD's higher than reo redfthe reasons shall be documented in tne Semi-annual Radioactive Effl s/ Release Report. N l
-- c. A composite saacle is one (pich
. the method of sasoling employed results is a specicen wtaica tpresentative of the liquids mioased.
x
- d. A batch release is the discha'rge Quid wastes of a discrete
, volume,
- e. When the monitor is out of service, grab sasole shall be taken and analyzed once every 32 hours if condensate pump discharge exceecs 3.x10-5 pct /mi gross beta or g .
l f. If an isotopic analysis is unavailable, g s beta or ganea : measurement of batch release say be suostitu a provioed the concentration released to the unrestricted a does not exceed 1 x 10*' pCi/a1 and a coacosite samole analyzed for princioal gaana esitters wnen instrumentation is vailante. , i l l l 1 OAVIS-BESSE, UNIT 1 3/4114 knendment No. 86 I
LAR 90-0023 Marked Up Technical Specifications Page 29 of 84 Ra0 ACTIVE EFFLUENTS DOSE LIMITING CO ITION FOR OPERATION 3.11.1.2 The e or dose commitment to a MDeER OF THE PUBLIC from racio-active materials n liouid effluents released to UNRESTRICTED AREAS (see Figure 3.11-1) sha 1 be limited:
- a. During any lendar quarter to less than or equal to 1.5 ereas to the total ocy and to less than or equal to 5 areas to any '
organ, and
.-- b. During any calen year to less than or ecual to 3 menes to the total bocy and o less than or equal to 10 areas to any o rgan.
APDLICABILITY: At all times,
' ACTION: V<(f' A
- a. With the calculated dose from elease of radioactive materials in liquid ef'19ents exceeding
- the anove liatts, in lieu of a Licensee Event Report, prepare suosit to the Commission within 30 days, pursuant to Specificatio 6.9.2, a Special Report that identifies the cause(s) for exceedi the limit (s) ano defines the corrective actions that have been ta n to reouco the releases and the proposed corrective actions to be ten to assure that sucsequent releases willi be in caso11ance with the ove limits,
- b. The provisions of Specifications 3.0.3 and .0.4 are not applicaole.
SURVEILtANCE REOUIRD'ENTS s 4 4.11.1.2 Cumulative dose contributions from liquid effluents or the current calonaar quarter and the current calendar year shall be oeterm ed in accorcance with the methodology and parameters in the 00CM at le t once per 31 days. DAVIS-BESSE, UNIT 1 Amendment No, 86 3/4 11-5
i l LAR 90-0023 Marked Up Technical Specifications Page 30 of 84 8 E ii EEE ~ '
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. A T'w dis .
(U ny i !- l r s g z 0 AVIS-BESSE, UNIT 1 3/4 11-6 Amendment No, 86
LAR 90-0023 Marked Up Technical Specifications Page 31 of 84 i l u RADICACTTVE EFFLUENTS L. VID RADWASTE TREATMENT SYSTEM LIMITI CON 0! TION FOR OPERATION 3.11.1.3 e liquid red =4ste treatment systen shall be used to recuce the racioactive ' terials in liquid wastes prior to their discharge wnen the projected dos due to tne liquid effluent to UNRESTRICTED AREAS (see Figure 3.11-1) uld exceed 0.06 ares to the total bocy or 0.2 area to any organ in a 3 cay perioc.
. APPLICABILITY: At I times.
ACTION: l a. With radioactive waste being disenarged without treatment l and in excess of ove limits, in lieu of a Licensee Event i Report, prepare and t to the Commission within 30 days, j pursuant to Specific n .2,a Special Report that incluces the
; following information:
- 1. Explanation of wny 1 uid awaste was being disenargeo without treatment, ice a ion of any inoperaole equipment or suesystems, and the o for the inoperability ,
- 2. Action (s) taken to restore inoperanle equipment to OPERABLE status, ane
- 3. Summary description of action (s taken to prevent a recurrence,
- b. The previsions of Specifications 3.0.3 a 3.0.4 are not aoplicable.
SURVEILLANCE REQUIREMENTS s 4.11.1.3 In any month in which radioactive liquid affluen is being discharged without treatment, cosas due to licuid releases t UNRESTRICTED AREAS snall be projected at least once per 31 days in accorca e with the eetnocology and parameters in the 00CM. DAVIS-BESSE UNIT 1 3/4117 Amendment No. 86
. i!
i LAR 90 0023 l Harksd Up Technical Sp2cifications l I' age 32 of 84 RADIDACTIVE grrtugxTs ' LIQUID HOU)UP TANKS" t LIMITING CONDITION FOR OPERATION
- 3. The cuantity of racioactive eaterial contained in eacn of the foi unprotected outdoor tanu shall be limitaa to less than or soual to 10 curies, excluding tritium and dissolvec or entrainec noole gases.
- 4. Outsica tamporary tank.
APDLICABILITYt At all times. ACTION:
- a. With the quantity of radioactive material in any of the aDove listaa tants exceeding the above limit, insediately suspene all accitions of radioactive material to the tant and within 48 hours reduce the tant contents to within the limit, anc cascribe the event teacing to this condition in the next Sesiannual Radio-active Effluent Release Report.
- b. The previsions of Specifications 3.0.3 anc 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4 The quantity of radioactive natarial contained in each of the above.l Tsted tants shall be determinec to be witnin the above limit by analyzing a representative sample of the tant contents at least once per 7 cays wnen radioactive antarials are being accec to the tank.
" Tanks included in this specification are those outcoor tants that are not surrounced by liners, aikas, or walls casaale of holding the tant contants i or that do not have tant overflows and surrouncing area crains connectec
! to the liquid rassesta treatment systan. I l OAV!5-8E53E, UNIT 1 3/4 11 Amendment No. 86
.- . -. . - . .-. _~ _ - . - - _-
LAR 90-0023 Harked Up Technical Specifications Page 33 of 84
;I
!!RADI CTIVE EFFLLWrs
' 3/4.11 CASEOUS EFFLUENTS
-l !
,lDOSERATE
. LIMITING COND
- ION FOR OPERATION l'
l 3.11.2.1 The dose te due to radioactive materials released in gaseous effluents from the si e to areas at and beyond the SITE BOUNDARY (see Figure 3.11-2) shall b liatted to the followingt
- a. For noble gases: Less than or equal to 500 areas / year to the total body and less tha or equal to 3000 aress/ year to the skin, and
.i b. For iodine-131, for itius, and for all radionuclides in particulate ,j form with half lives a ester than 8 days: Less than or equal to 1500 mress/yr to any organ. ; APPLICABILITY: At all times. (
t A_CTION: p/ 1 a. Vith the dose rate (s) exceeding e above limits, without delay restore the release rate to within the a e limit (s).
- b. The provisions of Specifications 3.0. and 3.0.4 are not applicable.
I I i I {SURVEILLANCEREQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous of uents shall be determined to be within the above limits in accordance with e methodology and parameters in the CDCL 4.11.2.1.2 The dose rate due to iodine-131, tritius, and all rae(onuclides in particulate form with half-lives greater than 8 days in gaseous e uents-shall be determined to be within the above limits in accordance with the thodology and ps:ameters in the ODCM by obtaining representative samples and pe forming analyses in accordance with the sampling and analysis program specifie in Table A.11-2. N Amendment No. A6,135 DAVIS-BESSE, (JNIT 1 3/4 11-9
- 1- .
i IABIE-4.11-2 RAn30ACIIVE GASEDUS WA51E SAMPtING AND AMAtYSIS PROGRAN I 5 Minimum Lower tielt of y Gaseous Release type _ Sampling- Analysts Iype of Detectlen(gtD g frequency frequency ActIwIty Analysis (pCI/el) l C m P P-l c Waste Gas Becay [ach Each Principal Gamma Emitters' 1 0 2 Release Release j-t U Grab'5 ample H-3 [1xle ' P P ~. Containment Peerge Each Purge fach Purge Principal c - tiers' 1 x le Grab Sample t s H-3 [ I x 10',
~*
[ Station Vent Stack M M Princ b Eeltters* 1 m 18 ;
- Grab Sample ~,
h bf I x 19 Continuous g C M f1-131 1 x le as W se Centi Particulate Principal C- Emitters' Sample *I x li gg; M 2a" Continuous t Ceaposite w18 Particulate Gross AIpha 1 x 10 "co ouo S Sample 5 " 40
?A -l Continuous h 4 g,,p,,gg' ?
{ o Particulate Sr-89* Sr-90 1 x 10 '
~
I
- g,
-Sample m ,
- h v Continuous Noble Gas Noble Cases. %
Monitor Gross Beta or Gamma 1 x 10". **
~
X s
LAR 90-0023 Harked Up Technical Specifications Page 35 of 84 TABLE 4.11-2 (Continued) TABLE NOTATION
- a. The L is the smallest concentration of radioactive material in a sample at will be setected with 95% pronability with 5% procacility of fais concluding that a blank observation represents a "real" signal.
For a partic lar measurement system (which may include radio-enesical separation): gg , 4.66 s g EV 2.22 Y exo(-Aat) wnere LLD is the lower li t-6 detection as cefined aeove (as oCi per unit mass or vol sb is the standard devi the background counting rate or of the counting rata o k sample as accrocriate (as counts per minute); E is the counting efficiency htspertransformation); V is the saacle size (in units o beds or volume); 2.22 is the nuncer of transformatio per minuta per picoeurie; Y is the fractional radiocnemical yiel (wnen soolicable); A is the racioactive decay constant for t particular racionuclide; at for plant affluents is the elapsed time be n the sidocint of sample collection and time of count ng. It should be recognized that the LW is cefined as an a criori (before the' fact) limit representing the cacanility of a easurement system and not as a costeriori (after the fact) limit for particular measurement.
- b. The ratio of the sasole flow rate to the samoted stream flow te snall be known for the time period coverec by eacn dose or cose rate
- calculation sace in accorcance with Specifications 3.11.2.1 and 3.11 .2.3.
DAVIS-EESSE, UNIT 1 3/4 11-11 Amendment No. 86 i l
LAR 90-0023 Harked Up Technical Specifications Page 36 of B4
, TABLE 4.u-2 (Continued)
TABLE NOTATION
- c. The principal g tiers for which the LLD specification will apply are axelusively th 1 owing radionuclides: Kr-87, Kr-68, Xe-133, Xe 133a, Xe-135, an 8 for gaseous emissions and Mn-54, Fe-59, Co-58 Co-60, In-65 Mo-99, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list a t mean that only these nuclides are to be aetected and reported, e ear.: wnich are seasured and identified, together with the anove nu id , shall also be identified and reported.
Nuclides which are below the f r the analyses should be recorted as "less than" the nuclide's LLD d hould not be recorted as Doing present at the LLD level for th uclide. The "less than" values shall not be used in the required dose 1culations. When unusual circumstances
- result in LLD's higner than requi , the reasons shall be occumented in the Seniannual Radioactive Efflue Release Report.
DAVIS-BESSE, UNIT 1 3/4 11-12 knendment No. 86
l LAR 90-0023 Harked Up Technical Spscifications Page 37 of 84 1 RADICACT E FFFLUtiT5 -[ 005E - Not GASES 1 i LIMITING CONDI N FOR OPERATION l 3.11.2.2 The air se due to noble gases released in gaseous affluents to anas at and beyond e SITE BOUNDARY (see Figure 3.112) shall be limited to the following:
- a. During any cal . dar cuarter: Less than or eoval to 5 mraes for gamma radiation anc 1 s tha or equal to 10 mraas for beta ractation , and
- b. During any calenca e
- Less than.or equal to 10 meads for gasuna
- radiation and less equal to 20 nraes for beta raciation.
APPLICABILITY: At all times. [ l ACTION:
- a. With.the calculated air dose f adioactive noble gases in gaseous af fluents exceecing any of th liafts, in-lieu of-a Licensee Event Report, prepare and suas he Commission within 30 cays, l pursuant to Specification 6.9.2, pecial Report that icentifies the cause(s) for exceeding the 11 t(s) and defines the corrective actions that have been taken to re ce the releases and the proposed corrective actions to be taken to p; re that suosequent releases will be in compliance with the above sits,
- b. The provisions of Specifications 3.0.3 a 3.0.4 are not applicaole.
SURVEILLANCE REQUIREMENTS 4.11.2.2' Cumulative dose contributions for the current ca endar ovarter and current calencar year for nocle. gases shall Oe deterinined i accorcanca with the methodology and parameters in the 00CM at least once per 1 cays. DAVIS-5 ESSE, UNIT 1 3/4 11-13 Amendment No. 86 li o
LAR 90-0023 Marked Up Technical Specifications Page 38 of 84 10 ACTIVE EFFLUENTS 005 100!NE-131. TRITIUM, AND RADIONUCLIOES IN PARTICULATE F0PM LIMITING ONDITION FOR OPERATIOir 3.11.2.3 Th dose to a MEMIER OF THE PUBLIC from iodine-131, tritius, and all racionuel es in particulate form with half-lives greater than 8 days in gaseous effluen released to areas at and beyond the SITE BOUNDARY (see Figure 3.11-2) s 11 be limitec to the following:
- a. During a calendar cuarter: Less than or equal to 7.5 meems to any organ a d, I b. During any ca near year: Less than or equal to 15 arems to any organ, iApoLICABILITY: At all times l AC* ION:
F(
- a. With the calculated dose h the release of iodine-131. tritium, anc racionuclides in part u%e fem with half-lives greater than 8 days, in gaseous affluen caecing any of the aoove limits, in lieu of a Licensee Event r , preoare and suosit to the Commission within 30 days, pu to Specification 6.9.2, a Special Report that identifies the caus for exceeding the limit anc cefines the corrective actions that have een taken to recuce tne releases and the proposed corrective action to es taken to assure tnat suo-secuent releases will be in comolia a with the acove limits,
- b. The provisions of 5pecifications 3.0.3 no 3.0.4 are not acolicaDle.
SURVEILLANCE REOUIREWENTS s 4.11.2.3 Cumulative dose contributions for the current lancar cuarter anc current calencar year for iodine-131, tritius, and ra onuclides in particulate form with half-lives greater than 8 days shall catarmined in accorcance with tne methocology and parameters in the 00C. at least once per 31 days. DAVIS-BESSE, UNIT 1 3/4 11 14 Amendment No. 86 l i
I LAR 90-0023 Marked Up Technical Specifications Page 39 of 84 I l' , g I & 5E
^
T =E<- l ! I !! E E SE S i
- z-
-l gj !!*
5 5 \ ~ d r L
=)
5 = 1 > 1 C .
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- I dl; p bi
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<ii L QU i ,
l I= x OAVIS-BES$!, 'JNIT 1 Amendment No. 86 3/4 11-15
LAR 90-0023 Marked Up Tochnical Spocifications Page 40 of 84
' rah 0ACTIVEE'FLUEVf5
- GASE0 RA0 WASTE TREATMENT SYSTEM LIMITING C DITION FOR OPERATION
- 3. u. 2. 4 The E005 RA0 WASTE TREATMENT SYSTEM shall be used to recuce radioactive sat ials in gaseous waste prior to their discharge woen the projected gas us-effluent air doses due to gaseous effluent releases to areas at and be no the SITE SOUNDARY (see Figure 3.11 2) would exceed 0.2 mrad for gamma istion and 0.4 ared for beta radiation in a 31 cay period. The VENTILAT N EXHAUST TREATMENT SYSTEM shall be used to recuce I radioactive meterials gaseous waste prior to their disenarge wnen the projected-ooses cue,to eous effluent releases to areas at and beyond
_ the SITE SOUNDARY (see i re f.y 2) would exceed 0.3 mrom to any organ in a 31 cay period. v ll APPUCA8IL!TY: At all. times.. [ ACTION: ll
;' a. With the gaseous waste bei arged without treatment and in excess of the aoove 1 s in lieu of a Licensee Event Report, prepare and s the commission within 130 days, pursuant to specificat 6.9.2, a Special Report that incluees the following info tion:
'l 1. - Explanation of why gaseous ra ste was being disenarged
- without treatment, identificatto of any inopersole equipment or suosystems, and the asons for the inoperability.
- 2. Action (s) taken to restore the inopera le equipment to OPERABLE status, and
- 3. Summary description of action (s). taken to vent a recurrence..
~
- b. ~The provisions of Specifications 3.0.3 and 3.0.4 are t applicable..
SURVEILLANCE REQUIREMENTS s
- 4. u.2.4' When systems are not being utilized,' doses due to gaseous releases to areas at and beyond the SITE 500 HOARY shall be projected at least once per 31 days in accoreance with tae setnocology and parameters
-in the 00CM.
)
DAVIS-8 ESSE, UNIT 1 3/4 11-16 Amendment No. 86 l l 3
LAR 90-0023 Marked Up Technical Specifications Page 41 of 84 I' RADICACT!VE EFFLUENTS EXPl05fvE GAS MIXTURE (Hydrogen rich systems not cesigned to withstand a nycrogen explosion) LIMITING CONDITION FOR OPERATION , 3.11.2[The concentration of oxygen in the waste gas systas shall be limited to less than or equal to a by volume whenever the hycrogen 1 concentration axceecs 4% by volume. l APpt!CABIL UY: At all times. i ACTION:
- a. With the concentration of oxygen in the waste gas system greater than 3 by volume but less than or ecual to 4%
by volume, recuce the oxygen concentration to tas acove limits, within 48 hours,
- b. With the concentration of oxygen in the waste gas system greater than 4% by volume and the hycrogen concentration greater tnan di by volume, immeciately suspenc all aceitions of-wasta gases to the systes and recuce the concentration of oxygen to less than or equal to a by volume without celay,
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not acplicable.
SURVEft. LANCE PE0VIREMEKT5 4.11.2[Theconcentrationsofoxygeninthewastegassystesshallbe determined to be within the above limits by monitoring the waste gases in tne wasta gas system as required by "' ' ' " ' Specification 3.3.3. . L l S
- DAVIS-BESSE, UNIT 1 3/411.g Amendment No. 86 l
I
LAR 90 0023 Marked Up Technical Specifications Page 42 of 84 RA OACTTVE EFFLUENTS 3/a. 3 SOLID RADI0 ACTIVE WASTE ' LIMITING NOITION FOR OPERATION 3.u.3 The s id radweste system shall be used in accordance with a PROCESS CONTROL PROG to process wet racioactive wastes to meet shipping anc destination buri i ground requirements. ApoLICABILITY: At 11 times. ACTION:
- a. With the provi ons of the PR0':E55 CONTROL PROGRAM not satisfied, suspena shipmen of defectively processed or cafectively pacraged solid racioactive est s from the site,
- b. The provisions of 50 ations 3.0.3 and 3.0.4 are not applicatie.
SURVEILLANCE REQUIREMENTS tA ~ s m
- 4. u. 3 THE PROCESS CONTROL PROGRAM sha used to verify the SOLIDIFICATION or DEWATERING of'at least one representa test specimen free at least 10% of the batches of each type of wet radioacti wasta (e.g., filter slueges, spent resins, evaporator bottoes, boric acid solu ions, and socium sulfate solutions),
- a. If any test specimen fails to verify OLIDIFICATION, the SOLIDIFI-CATION of the batch unoer test shall suspenced until such time as aceitional test specimens can be ob inea, alternative SOLIDIFI-CATION parameters can be determined in a orcance with sne PROCESS CONTROL PROGRAM, anc a subsequent test ve fies SOLIDIFICATION.
50LIDIFICAT!0N of the baten may then be res d using the alterna-tive SOLIDIFICATION parameters catermined by he PROCESS CONTROL PROGRAM.
- b. If the initial-test specimen free a batch of was fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall rovice for the collection and tasting of representative test speci ns from each consecutive batch of the same type of wet wasta unti at least 3 consecutive initial test specimens demonstrate SOLI ICATION.
The PROCESS CONTROL PROGRAM snail be socified as recui . as cro-viced in Specification 6.14, to assuro SOLIDIFICATION of uosecuent batenes of wasta. DAVIS BESSE. UNIT 1 3/41118 Amendment No. 86 l
LAR 90 0023 Marked Up Technical Specifications Page 43 of 64 PA0!0 ACTIVE EFTLUENTS ',. 3/4.11.3 SOLID kO10 ACTIVE WASTE St;RVEILLANCE REOL'I 1ENTS (Continued)
- c. If any test so isen fails to verify DEWATERING, the OEWATERING of that batch un r te t shall be suspenced. Alternata OEWATERING parameters can be eta ined using the PROCESS CONTROL PROGRAM.
If a sucsequent tes ifies DEWATERING, 0 WATERING of the caten I say be resumed using ternative parameters cetersinec Dy tne PROCESS CONTROL PROG
- d. If the test specimen fall p{herifyDEWATERING,thePR PROGRM snali provide for t ting of a representative scocimen of the same type wet wasta f .secutive Datenes until-at least 3 test specimens comonstrate ING. The PROCESS CONTROL PRO-GRAM shall be modified as provi in specification 6.14 to assure OEWATERING of sucsequent Datches f wasta, i
l
- l DAVIS BESSE. UNIT 1 3/4 11-19 Asnendment No. 86
l LAR 90-0023 l Marked Up Technical Specifications Page 44 of 84 RADI0aJTVE ErrLUENTS 3/a.11.a\ TOTAL 00$E LIMITING CON TION FOR OPERATION 3.u.4 The ann 1 (calendar year) dose or dose coesitaent to any MEMBER OF THE PUBLIC due to releases of radioactivity and to ractation from urani a fuel cycle sources snal be limited to less than or ecual to 25 areas to tne total bocy or any organ, capt the thyroid, which shall be limitaa to less than or equal to 75 areas. APPLICABILITY: At all nes. _ ACTION:
- a. With the calculate s from the release of radioactive materials in licuia or gaseous uents exceeding twice the limits of Specification 3. u.1. . . u.1.2.b. 3. u.2.2.4. 3. u.2.2.b,
- 3. u. 2. 3. a . or 3. u. 2. atuations should be nace including l direct raciation contri from the reactor units and f ree out-sica storage tants to cet whether the aoove limits of Specification 3. u.4 have caecec. If suca is the case, in lieu of a Licensee Event Re , brocare anc suosit to the Commission within 30 cays, pursuant to Pication 6.9.2 a Special Reoort that cefines the corrective a n to De taken to recuce suosecuent l releases to prevent recurrence exceecing taa above limits anc includes tne senedule for achiev g confomance with the acove limits. This Soecial Report, as finec in 10 CFR Part 20.405c, i sna11 incluce an analysis that esti tes the raciation exposure (cosa) to a MEMBER OF THE PU8LIC fr uranium fuel cycle sources, including all effluent pathways and a et raciation, for tne calencar year that incluces the releas s) coverso by this reocrt.
It sha11'also oescribe levels of raciati and concentrations of radioactive eaterial involved, and the ca e of the excesure levels or concentrations. If the estinatac dose ( exceeds the acove limits.
, and if the release condition resulting in v lation of 40 CFR Part 190 i nas not alrency been corrtCted, the Special R rt shall incluce a request for a variance in accorcanca with the visions of 40 CFR Part 190. Submittal of the recort is consicere a timely reovest, and a variance is grantac until staff action on t request is complete,
- b. The provisions of Specifications 3.0.3 anc 3.0.4 are not applicaole.
SURVEILLANCE REQUIREWENTS s
- 4. u. 4.- Cumuistive cosa contributions from liquid anc gaseous efflu ts shall be catermined in accorcance wita Soecifications 4. u.1.2, a. U.2.2, an a .11. 2*. 3, and in accorcance with the setnocology and parameters in the 00CM.
DAVIS-BESSE, UNIT 1 I 3/4 11-20 Amendment No. 86
LAR 90-0023 Marked Up Technical Spacifications Page 45 of 84
!!4. V F.ADIOLOCICAL ENVIRONMERIAL MONITORING
)/4.12 MONITORING FROGRAMS LIMITING DITION TM OFEpa!"':
3.12.1 The diological environmental monitor.ing program shall be conducted as specified in le 3.12-1. APPLICABILITY: all times. ACTION:
- a. Vith the radio gical environmental monitoring program not being conducted as sp ified in Table 3.12-1, in lieu of a Licensee Event Report. prepare a submit to the Commission, in the Annual Radiological Environmental Oper so ingRyortrequiredbySpecification6.9.1.10a description of the r for not conducting the program as required and the plans for pre a recurrence.
- b. Vith the level of radios 1* as the result of plant effluents in an environmental sampling me a a specified location exceeding the reporting levels of Table 3 en averaged over any calendar quarter, in lieu of a Licens ve Report, prepare and submit to the Commission within 30 days, pur Specification 6.9.2, a Special Report thr.t identifies the caus s exceeding the limit (s) and defines the corrective actions t '
effluents so that the potential an ( enose to toreduce radioactive A MEMBER OF THE PllBLIC is
'l less than the calendar year limits Specification 3.11.1.2, 3.11.2.2.
and 3.11.2.3. When more than one of te radionuclides in Table 3.12-2 are detected in the sampling medium, t{sreportshallbesubmittedift concentration (1) concentrathn (2) reporting level (1) , reporting leve (2) + ... > 1.0 - Vhen radionuclides other than those in Table .12-2 are detected and are the result of plant effluents, this report sh 1 be suesitted if the
- potential annual. dose to A MEMBER OF THE PUBLI is equal to or greater
, than the calendar year limits of Specifications 11.1.2. 3.11.2.2 and 7
3.11.2.3. This report is not required'if the sea red level of i; radioactivity var act the result of plant effluents however, in such an event, the condition shall be reported and described n the Annual Radiological Enviroceental Operating Report. 11
,5 c. Vith silk or fresh leafy vegetable samples unavailable f one or more
.. of the sample locations required by Table 3.12-1, identify '.ocations for
.) obtaining replacement samples and if practical add then to 1, e
;i radiological environmental monitoring program within 30 days. The
'; locations from which samples were unavailable may then be dele d from the monitoring program. In lieu of a Licensee Event Report and ursuant
! to Specification 6.9.1.11, identify the cause of the unavailabili of
'; samples and identify the new locations (s) for obtaining replacemen samples in the next Semiannual Radioactive Ef fluent Release Report a also include in the report a revised figure (s) and table for the ODCM reflecting the nov locations (s).
0 AVIS-BESSE, UNIT 1 3/4 12-1 Amendment No. S6,135
LAR 90-0023 Marked Up Technical Specifications Page 46 of 84 RAD! G! CAL ENVIRONMENTAL MON!TORIN
.l.!MITIN ONDITION FOR OPERATION
;i .
ACTION: (Con nued)
- d. With ecimens unobtainable due to hazardous conditions, seasonal unavat bility, malfunction of automatic sampling equipment and other 1 itimate reasons, every effort will be made to complete correctiv action prior to the enc of the next sampling period.
All deviat ns from the sampling schedule will be documented in the Annual diological Enviromental Operating Report pursuant to Specificat 6.9.1.10.
- e. The provisions Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS / 4.12.1.1 The raciological environme a pursuant to Table 3.12-1 from the sp e i nitoring samples shall be collecteo ocations given in the table and figure (s) in the ODCM and shall be ana rsuant to the requirements of Table 3.12-1, and the detection capabili guired by Table 4.12-1. 4.12.1.2 Cumulative potential dose contrib tions for the current calendar year from radionuclides detected in environm tal- samples shall be detemined in accordance with the methodology and parame rs in the ODCH. l L DAVIS-BESSE, UNIT 1 3/4 12-2 Amendment No. 38,135 1
Y l I ABt E 3.12-I hADIGIOGICAt INVIRONMENIAI MONIIORING PROGRAM C sk Type a requency Engmsure Pattway Number of Representative Analysis C Samples and Sample locations, Collection f requency and/or Sample
,M b Quarterly dose quarterly 27 routine monitoring stations either E I. DIRECT RADIAIION with two or more desleeters or with Q one instrument for measuring afwi .
g recording dose rate continuously, placed as follows: an inner ring of stations, generally one in each acteoroloDical sector In the general area of the SITE SOUNDAR1f; an outer ring of stations, one in - M each seteorological sector in the
- 6- to 8-ke range free the site except the sectors over take le;
~[
the balance of the sta ns to t>e placed in special I rest areas such as populatio enters, nearby -sxe-residences, sc areas to se Is, and in I or 2 as control stations. fh$
*E$
l o#S F - i'
- it ir 3 r
" ?-
o 5
i IAlltE 3.12-1 (Continued) RADI0l0GICAL INVill0lgENIAI MWilDRING PROGRAN Y= Number of Representative h Exposure Pathway and/or Sample Samples and Sample locations, Collection fretysency [T,--of
..,"Analysis I'requency
.m E .2AIR 30ltNE 4 ,
H Radiolodine and Samples from 5 locations Continuous samp Radlelodine Cannister: . Particulates operation wl sample F U I .nalysis weekly. 3 samples free close to the 3 SITE collecti ekly, or 30lNBARY locations, la different more f ly if i - sectors, generally from areas of re st Particulate Sampler: higher calculated annual average Cross beta radioactivity j groundlevel S/q. enelysi w change;gCfollowing
"" I'*E*Pfilter C
I
- I sample from the vicinity of a d analysisd **fo composite
- nearby community, generally / (by location) quarterly.
7 area of higher calculated 1_ average groundlevel D/ 1 sample from a trol location, 15-30 km dist . ,2e 5 E To
- 3. WATERBORNE *7, e a. o
- a. Surface 2 les Weekly composite Compositefortritjun "co g sample (Indicator and geese isotopic 3." 8
= location is a analysis monthly. mY" E centinuous,
' *S !
M composite trit.kle- - 3
?, feed) g m '
. b. G Sample from one source Quarterly Gamma Isotepic and y onlyifjlkelytobe tritium analysis "
$ affected quarterly. --
*~
n IB
ase p *-
, l IABIE 3.12-1 (Continued]
RAD 1010GICAt (NVIR0fefMIAL I40N!!DRING PROGRAM 9 type and f reque h Exposure Patlway Number of Representative of Analy Samples and Sample locations, Collection frequency M and/or Sample - I sample from the nearest Weekly composite Gross be on sonthly E c. Drinking' source. sample. coepe e. Irltlig Q a assa-Isotopic g alysis on quarterly 1 sample from a control location composite. I-131 analysis on each composite when the dose calculated for the consumption of the water is greater u 4 than I aree per year. 1 q/ ~ ally Gamme isotopic anal
- d. Sedleent free I sample from area with existing seelannually.
- Shoreline or potential recreational value
- 4. INGE5110N Seelmonthly when Gamma Isotopicd erw -oxr-
- a. Milk If available, samp3 free milking 1-131 analysts seel A%$
anima!s up in 2 ations within animals are on monthly when animal *7o 8 he distanc vlag the highest pasture, monthly l dose pote 1. at other Llees are on pasture; noe $*? j g at otier Lines. ,gg e ~ aU co e y ample from milking animals "E e 3 at a control location 15-30 km 3. distant and generally in a less 0 2 prevalent wind direction. E* X
~
; I a
IABIE 3.12-1 (Continued) RADIGI X.lCAI ENVIRONMENI Al MDNITORING PROGRMt Y m M Exposure Pathway theber of Mrpresentat ive Iype and equency
,a and/or Sample Sanples and Sample locations, Collection Frequency o lysis E
U.b e Fish I sample each of 2 commercially I sample in season. amme isotopic analysis d and/or recreationally leportant en edlele portions. species in vicinity of site. I sample of same species in I areas not influenced by plant { discharge. O c. Food Products Samples of ey to 3 different kinds th n avall- Gamma Isotopic d aw f, of broad leaf vegetation growth I e. 3-131 analysis. two alfferent offsite locati f higher predicted annua! av ground-level 9/q If mit
.Is not performed. /
1 sample of e of the stellar Monthis een avall- Gamma Isotopic and broad leaf tation grown able. I-131 analysis. w x e-15-30 D prev stant in a less nt wind direction if SE$ eo sampling is not performed. $"? g oES
. ~
l E ~0 l 2 i'
- 1
% i E O w
Sus. I l E. h
LAR 90-0023 Marked Up Technical Specifications t Page 51 of 84 l TABLE 3.12+1 (Oontinvec) TABLE NOTATION "Specif parameters of distance and direction sector from the centerline of one re tor, and acettional description where pertinent, shall be proviced f each and every sasole location in Table 3.12-1 in a table and figure ( in the 00CM. Refer to NUREG 0133, "Pnparation of Racio-logical Efflu t Technical Specifications for Nuclear Power Plants". Octeoer 1978, o to Radiological Assessment Brancn Technical Position, Revision 1, Nov er 1979. It is recognized that, at times, it ney not be possible or or icaole to continue to obtain sasoles of the necia of enoice at the most esired location or time. In these instances suitable alternative media an locations may be chosen for the particular pathway in cuestion and appre iate s stitutions nace within 30 cays in the
- raciological environne al toring program. In lieu of a Licensee Event Recort and pursuan t cification 6.9.1.11, identify the cause of the unavailacility of s es that pathway and identtfy the new location (s) for cotaining r i nt samoles in tne next Sesiannual Racicactive Effluent Release e ano also incluce in the report a revisec figure (s) and taole fo t CM reflecting the new location (s).
D one or more instruments, such a a urizac ion chamoer, for measuring anc recorcing cose rate continuous e usec in place of, or in aceition to, integrating cosimeters. FDP e purposes of this taDie, a thermoluminescent cosimeter (TLD) is oc to be one chosonor; two or more phosoners in a packet are cons e as two or more cosimeters. Film Dacges sna11 not be used as cosime es for seasuring cirect raciation. The nuncer of direct raciation monitoring tations ray be reduced accorcing to geograpnical limitations; e.g., at an o an sita, some sectors will be over water so that the nuacer of cosimeters y be recuced accordingly. The frecuency of analysis or reacout for TLD syst s will cepend upon tne char-acteristics of the specific system used and sho in be selectec to cotain optimum cose information with minisal facing.
"Aircorne particulate sample filters shall be analy d for gross beta racioactivity 24 hours or nors after sasoling to all for racon anc thoron caugnter cacay. If gross beta activity in air partic ate samples is greatar than tan times the yearly mean of control samples, g isotopic analysis sna11 be perforsec on the incividual samples, d
Gamna isotocic analysis means the icentification anc cuant ication of gamma esitting racionuclices that may be attributacle to tne ffluents from tne facility,
' Groundwater samoles shall be taken wnen this source is taoped f crinking or irrigation purposes in areas wners the nycraulic gracient or re 9arge properties are suitable for contamination.
DAVIS-BESSE, UNIT 1 3/4 12-7 Amendment No. 86
1 1 IA01E 3.12-2 h REPORilNG ((VELS FOR RADIDACIIVITY CONCENIRATIONS IN ENVIRefetENIAL SAMPLES
- Reporting levels 4
Cen i
- Water Airborne Particulate fish Milk Vegetab g Analysis (pCl/1) er Gases (pC1/m8 ) (pCl/kg. wel) (pCl/1) (pCl/ , wet)
U y H-3 2 x le** Mn-54 1 x les 3 x 10* Ie-59 4 x 108 1 x 104 w Co-58 Ce-60 1 x 108 3 x 108 3x1 x1 n
- 0*
m In-65 3 x 108 Y < a Ir-h-95 4 x 108 . 1-131 2 .9 3 1 x 108 Cs-134 30 to 1 x les 60 I x 108 [(h aw . Cs-137 50 29 2 x 108 70 2 x 108 w1$ ' e Ba-ta-140 x 108 3 x 10
= .:- ,
2 *for lag water samples, this is the 40 CfR 141 value. If no drinking water o g. . y exists, a value of 30.000 pCl/Ilter may be used. s 3 p
. 1 0
2 > 1 O a
L
~
I l IAulE 4.12-1 y lower IIMIIS OF DfitCIION (llD)#
- S.
w E ~ A!rborne P M Icelate U Fish Mith food Fr s Sedleent Or Gas 2 (pCl/kg. wet) (PCl/1) (PCl/k wet) (PCIllf. dry) go.j yggs ( /1) (ptt/m ) E b U Gross Beta 4 3 x 10-8 o 3,, 2000'* 15 130
$4g
- 30 260 53 -
a fe l 1' 58, 60g , 15 [ 65g , M 15 957 , 7 x le- I M 1 131, D 130 15 60 150 15(10 ) IB 6 0-a 134. IJ1g , w" N 5 15 15 g;w 140,a uL$ hh g3 F IEITE: This I does not mean that only these nuclides are is be detected and reported. y* g Otl peats which are measurable and identifiable, together with the above nuclides, =r g iI be ident1iied and reperted. 1 a
<* O
- no drinking water pathway esists, a value of 3000 pCl/t say be used. -
E 0 1
LAR 90 0023 Marked Up Technical specifications l' age 54 of 84 TABLE 4.12 1 (Continued)
. TsBLE NOTAft0N
- 4. The L is the smallest concentration of radioactive material in a sample at will be ootected with SM probability with n probacility of falsel concluding that a blank cDeervation represents a "real" signal. ,
l For a particu r measurement systes (which may include radiochemical separation): g, 4.66 a b l E*V 2.22
- Y
- exp(*Aat)
~
where LLD is the '. lower li i detection as cefined above (as DC1 per unit mass or vol , sb is the standare cavi tron f the backgrouno counting rate or of the counting ra blank samole as appropriate (as counta per sinute). - E is the counting efficiency is nt6 per transformation). V is the sample size (in units f ss or volume). 2.22 is the number of transfomat na per minute per picocurie. Y is the fractional radiochemical yi d (when applicable). A 12 the radioactive secay constant for the particular racionuclide, at is the elapsed time between end of the sample collection period and time of counting. l Typical values of E V, Y and at should be used in th. calculations. l l DAVIS SESSE, UNIT 1 3/4 12 10 Amendment No. 86 l
LAR 90-0023 Natked Up Technical Specifications l Page $$ of 84 i TABLE 4.12 1 (continued) TABLE NOT& TION The LQ s cefined as an e criori (before the f act) liett representing the ckDa 11ty of a measurement system anc not as a posteriori (af ter the fact) init for a particular sensurement. Analyses sha be perforsed in such a manner that the stated LLDs will be acnteved u er routine concitions. Occasionally backgrounc fluctuations, u volcatis small sasolo sizes, the presence of inter-faring nuclides, r uncontrollable circumstances may rencer these LLDs unschiev& ole. In ucn cases, the contributing factors will be icentified and ces ibed in the Annual Radiological Environmental Coerating Report. For more complete disc the LLD and other cetection limits, see the following: (1) KA$L Procedures Manua A R-300 (revised annually)', (2) Currie, L. A. , " Limits f o tative Detection and Quantitative Determination
- Acolicati clochemistry anal. Chem. 40, 586-93 (1968).
(2) Hartwell, J. K., " Detection L 'or Radioisotootc Counting Techniques". Atlantic Richfle) Muw' ore Company Report ARN-2537 (June 22,1972).
- b. '. LD for drinking water.
- c. If no crinking water pathway exists, a val of 3000 pCi/ liter may to used.
ci. ;0 only when specific analysis for 1131 reou d. 0AV!5 BE13E, UNIT 1 3/4 12 11 Amendment No. 86
l LAR 90-0023 Marked Up Technical Specifications Page 56 of 84 f
^
3/4 b RADIOLOGICAL ENVIRONM M AL MONITORIN0 3/4.12 LAND USE CEW5V$ LIMITING O!TIONS FOR OPERATIONS 3.12.2 A lan use census shall be conducted and shall identify within a distance of 8 (5 miles) the location in each of the is seteorological sectars' of the n rest milk animal, the nearest resieence and the nearest paroen of greater han 50 m8 (500 ft8) proeucing trosa leaf vegetation. APDLICABILITY: At a times. ACTION:
- a. With a land use en identifying a location (s) that yields a calculates cose a commitment greater than the values currently being ca in Specification 4.11.2.3, in lieu of a Licensee twent o , identify the new location (s) in the nu t Sesiannual R ctive Effluent Release Report, purst. ant to Spec"ficat 1.11.
- b. With a land use census to hngalocation(s)thatyields a calculates cose or oose t' nt (via the same uoosure pathway) 20 percent greater a location from which samples are curnntly being in accoroance with Specification 3.12.1, sed the ation(s)ifpractical to the radiological environment itoring program within 30 days. The sampling location (s ucluding the control station location, having a lower c culated nose or cose commitment (s), via the same unosure atnway, aey be coleted from this monitoring program. In lieu of a Licensee Event Report and pursuant to Specifica on 6.9.1.11, identify the new location (s) in the next Semiannu ' Radioactive Effluent Release Report and also include the report a revised fi ure(s) and taale for the 00CM re lecting the new location (s .
- c. The provisions of Specifications 3.0.3 and 3.0. are not
, applicanie. l l suavEILLANCE REQUIREMENTS , 4.12.2 The land use census shall be conducted during the growing eason at least once per 12 months using that infomation that will provi the or by best results, such consulting local agriculture authorities. The results of the as by a door-to-coor survey, serial survey, land us census snail be inclueed in the Annual Radiological Environmental .
. Operating Report pursuant to 50ecification 6.9.1.10.
DAVIS 6 ESSE, UNIT.1 3/4 12-12 keendment No. 86 e tuus
., .,--, ,y_---. , _ _ . _ , --, , . . - ... _._.-.--,,..-.-,...,,,.,___...,.4,...,,,.,_.,..._.gr,. .,..,.%, 6,yg, .,..,_,,mm,.y..%.,,.e,-.www ._m..,.,wo_ , -
LAR 90 0023 Marked Up Technicol Specifications Page $7 of 84 _RADI ' 0GICAL ENV!RONMENTAL MONITORING 3/a.12\ tviERLABORATORY COMPAR!$0N 0 CRAM P: LIMITING C O! TION FOR OPERATION 3.12.3 Analy a shall be performed on radioactive asterials supplied as part of an Inte laDoratory Comparison Program that has Dean aDorovec Dy the Consission. APDLICAB!L!W: At 11 times. ACTION: _ a. With analyses ing perforced as recuired above, report the corrective acti s n to prevent a recurrence to tre Commission in th 1 Radiological Environmental Operating Report pursuant t . ification 6.9.1.10.
- b. The provisions of 50 tions 3.0.3 anc 3.0.A are not applicamle.
$URVEILLaNCE REOUTREWENTS J, A.12.3 A summary of the results obtai as part of the cove recuitec Interlaboratory Comparison Program shall e incluced in tne Annual Racio-logical Environmental Operating Report pu want to specification 6.9.1.10.
DAVI$ BESSE, UNIT 1 3/4 12 13 MenMnt M. M
LAR 90 0023 Marked Up Tochnical Specifications Page 58 of 84 l ! IN$tt1.D*fMTATt0N SA$[$
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7
...,,... _ _ _ . . , _ y-
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=
_ .=_=_=.=-_.==..=.._.----- __ . L wsne. grs sptsm y wmar <'s PAM k men, toe ox a4.m.+ted. .le yk wes,Jea.mn assim. ofw9t.ssoas 4tsnk. Ox edwule- n c.**cadhn bsty is, moniMed +o ensar<ga , +h saq'ths d uncen+y$*thn m of pef %fially aglosive, gas mirtur.> un++ined in &, l wask 34 treatmen+ .njstem i s main +=ined below the. flammdlli+y limits of hydro 3en with oxyjen-l OAvis-St358 uMIT 1 B 3/4 3 6 Amendment No. 86 l l i i
=
1
LAR 90 0023 Marked Up Technical Specifications rage 59 of 84 rah 0aCTIVEEFFLUEVf5 BASE 3/a.11.b!0010 EFFLUENTS 3/a.11.1,1 NCENTRATION This specifica on is provided to ensure that the concentration of radioactive sat ials released in 11ould weste affluents from the site to unrestricted a as will be less than the concentration levels specified in 10 CFR Part 20. . This liettation as implemented by the 00CM pro-vides accitional ass ence that the levels of radioactive materials in bodies of water outsico the to should not nsult in axposuns exceecing (1)
~
the Section II.A cesign ejAives of Appendix 1.10 CFR Part 50, to an individual and (2) the 1 f W f 10 CFR Part 20.106(e) to the population. The concentration lisit f gases is based upon the assumotion that Xe 135 is the controlling r tape and its MPC in air (sunsersion) was converted to an ecuivalent c tretion in water using the setnoes described in !ntarnational Commission on p ogical Protection (ICRP) 8ublication 2. 3/a.11.1.2 00$E Thia specification is provided to i i the reoutrements of Sections II.A. III.A and IV.A of Appe , 10 CFR Part 50. The Limiting Concition for Operation isol ts the guides set forth in Section II.A of Appendix !. The ACTION tenents provide the recuired - operating flaxibility and at the same ti implement the guices set forth in Section IV.A of Appendix ! to assu that the releases of radioactive material in liquid effluents wil e kept "as low as is reasonnely achievaale". Also. for fresh wete ites with drinking water supplies which can be potentially affected by p t operations, there is Masonsole assurance that the operation of the f 111ty will not nsult in racionuclide concentrations in the finisned dei ing water that an in excess of the requirements of 40 CFR 141. The o calculations in the 00CM implement the requirements in Section !!!. A Appendix ! that conformance with the guides of Appendix ! is to b hewn ey cal-culational procedures based on mooes and cata such that e actual exposure of an individual through appropriate pathways .is .likely to be suostantially uneenstimated. The soustions specifie in the 00CM for calculating the cosas cue to the actual release rat of racioactive materials in licuid effluents are consistent with e methocology provioed in Regulatory Guice 1.109. " Calculation of nnual Doses to Man from Routine Releases of Reactor Effluents for the oss of Evaluating Compliance with 10 CFR Part 50, Appencix !". Revisio 1, October 1977. l L DAVIS-8 ESSE, UNIT 1 3 3/4 11 1 Amendment No. 86 ! I
LAR 90-0023 Marked Up Technical Specifications l' age 60 of 84 RADI0 ACTIVE EFFLUENTS BA$t$
!i
?4 : 1.1.2 _ I O'_'! D " ' !?' " * ^?"li the requires hat the appropriate portions of this systes b vhen specified provides nee that the releases of radio materials in liquid affluents vill be
- lov as is rea achievable". This
, specification taplements the requ CFR Part 50.36a, General Design
- riterion 60 of Appandix A to 10 art d design objective Section II.D
, if Appendix I to 10 CTR P . Based on a ces sis of treating liquid radvaste, the spe 1 sits governing the use of appt e portions of the Liquid rad treatment system were specified as the dose des ectives as Le i in Section II.A of Appendix I, 10 CTR Part 50, for liquid e t g 3/4.11MIOUID fl0LDtTP TANKS Restricting the quantity of radioactive material contained in the specified +
tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations vould be less than the limits of
- 10 CTR Part 20, Appendix B. Table !!, Column 2, at the nearest potable water
. supply and the nearest surface water supply in an unrestricted area.
u 4 i I l. it -
- 1
!I I
DAVIS BESSE, UNIT 1 8 3/4 11 [ l
I LAR 90 0023 Marked Up Technical $pacifications Page 61 of 84 l 3,A0f0ACTIVEE8FLUEWTS l Bast 5 i- _ 3/4.U.2\ASE005E8FLUENTS j 3/4.u.t.1 St ILATE This specificat n is provided to ensure that the cose at the SITE BOUNDARY f gaseous effluents from all units on the 4 site will be with the annual deso limits of 10 CFR Part 20 for J unrestricted areas. The annual dose limits are the cosas associated with the concentrati of 10 CFR Part 20. Appenoix 8. Table !!. . These limits provice sonacio assurance that radioactive saterial discharged in gaseous e luents will not result in the exposure of a
- memoer of the puelic outs e the site boundary to annual average con-centrations exceeding the sits specified in Appendix 8. Tacle 11 of 10 CFR Part 20 (10 CFR Part 0.106(a)). For sempers of the puolic wne may at times De within the si be oary, the occupancy of that memoer of the public will be sufficie I pw to compensate for any increase
- ve that for the site bouncary.
in the atm9scheric diffusion fa The specified release limits rest a corresponding gasna and beta coses & Dove background to an indiv' u or Deyond the unrestrictec i area bounaary to i 500 area / year to 1 bocy or to ( 3000 ares / year to the skin. These release limits al rict, at all times, the corresponding thyroid doses above bac u to a child via the inhalation i pathway to i 1500 orea/ year. l l l CAV!$ BESSE. UNIT 1 B 3/4113 Amendment No. 86
. LAR 90-0023 Marked Up Technical Specifications Page 62 of 84
.,i RA0!0ACT E fFrLUfWT5 g ini$ \ . 3/4 1.1.2.2 Ob.WOBLEGMES This soecificati is provided to isolement the nouirements of Sections
!!.6, !!!.A and 1 A of Appendia 1,10 CFR Part 50. The Limiting tenettien for Operation isol nts the guide: set forth in Section !!.8 of Appencia 1.
The ACTION statement pmvice the recuired operating flexibility and at the same time isolement guides set forth in Section IV. A of Appendix ! to assure that the reless of radioactive saterial in gaseous af fluents will be teot "as low as is r sonably achievanie." The Surveillance Recuirements ismiseent the requirement in Section !!!. A of Appencix ! that confors with the guices of Appencia ! be hown by calculation procacures baseo on
- socals and cata such that t tual exposure of an indivicual through the appropriate pathways is un11 to be suestantially uncerestimated. The cose calculatinns estaolishec he 00CM for calculating the cosas oue to the actual release rates of ra tive noble gases in gaseous affluents are consistent with the methoco revicea in Regulatory Guice 1.109,
" Calculation of Annual Doses to Routine Releases of Reactor Effluents for the Purpose of Evalu como11ance with 10 CFR Part 50 Appenaix 1, " Revision 1, Octooer 1 a Regulatory Guice 1.111. " Methods for Estimating Atmospneric Transport ispersi:n of Gaseous Effluents in Routine Releases from Light-Water- d Reactors," Revision 1, July 1977.
DAVIS-BE5SE, UNIT 1 B 3/4 11 4 heenoment No, 86
LAR 90-0023 Marked Up Technical Specifications Page 63 of 84 RA010 ACTIVE EFFWENTS l l BASE 5 i 3/a.11.2.3 Ob. R.A0O!00f NES RA010 ACTIVE MaTERI AL IN PARTICULATE FORM ANO RADIONUCLIGU OTNR TMAN NOBLE GA5E5 This specificatio is provided to implement the recuirements of
$ections !!.C. !!!. and IV. A of Appendix 1,10 CFR Part 50. The Limiting C.onditions for Opera ion are the guides set forth in Section !!.C of Appendix !. The ACT! statements provide the retuired operating flexi-0111ty ano at the same ice implement the guices set forth in Section !Y. A cf Appencix ! to assun at the releases of radioactive materials in gaseous effluents will be ept "as low as is rossonaaly acntevaels." The cecified in the surveillance recuirements implement the recuirements ll00CMesiculationalmethocs Section !!!. A of Appendix ! that conformance
~
l { with the guices of Appencix e shown by calculational proceouns basec ,
, i on socals and cata such that t. actual exposure of an incivicual througn I
!i appropriate pathways is unlikel to suestantially uncerestimatec. The ll00CM methons for calculating the o cue to ne actual release rates of
! the sucject materials are consiste the methocology proviceo in
'I Regulatory Guice 1.109, "Calculatin nual Doses to Man from Routine -
l iReleases of Reactor Effluents for th I e of Evaluating Como11ance j with 10 CFR Part 50, Appencix !." Rev i Octocer 1977 anc Regulatory Guice 1.11.1 "Hethods for Estinating A' ic Transport and Dispersion , of Gaseous Effluents in Routine Releares ignt-water-Coolec Reactors," ) Revision 1. July 1977. l l .The release rate specifications for radicioc radioactive material in ! particulate fore and racionuclices other tnan o e gases are cependent on the existing racionuclide pathways to man, the unrestricted ans. The patnways wnica are examined in the oevelopee t of these calculations are: 1) individual inhalation of airDorne racion lices 2) cecosition of racionuclices onto g nen leafy togetation with sua uent consumption by man, 3) coposition onto grassy areas where milk ani is and mest procucing animals gra2e with consumption of the silk and seat b san, and 4) deposia tion on the ground with suesequent exposure of man. 3/a.11.2.a GASEOUS RADWASTT TREATMENT SYSTEM The recuirementa that the accropriate portions of these sys s be used, j when specified, provides reasonaale assurance that the relea s of l racicactive natorials in gaseous effluents will be kept "as 1 as l reasonably acnievencle". This specification isolements the reo roments of 10 CFR Part 50.m. General Design Criterion 60 of Apoencix A o 10 CFR Part 50. The specified limits governing me use of approp ' ate portions of the systems were specified as a suitacle fraction of th cose design oejectives set forth in Sections 11.8 anc II.C of Appenc !. 10 CFR Part 50, for gaseous affluents. DAV15 BES:E, UNIT 1 8 3/4 11-5 Amendment No. 86
LAR 90-0023 Marked Up Technical Specifications Page 64 of 64 8.AD10 ACTIVE trtWEWS q BASE 5 3/4.11.2[EYPlostvfGASMinURE This specification is provided to ensure that the concentration of potentially explosive gas sixtures contained in the waste gas treatment systan is maintained below the flannacility limits of hydrogen with oxygen. Maintaining the concentration of hydrogen or oxygen below their flamman111ty limits provices assurance that the releases of racio-active materials will be controlled in confonnance with the reavirements of General Design Criterion 60 of Appencia A to 10 CFR Part 50. 3/4.11,3. b : "^
^
- S: ' 'I'!
i n..a_... .:- .g e 7 ;> ::: 2 ;. 2; . . - .f a ;7.; f;;;;g j . > . . . . .. ..>. .. >>>...>.. . ,.. ... _. . ..z.. ..,a. . . > . . . . > . .
-!: ; !I' ) .b ! '!:N , "Na l-S DAVIS SE33E, UNtt i 9 3/4 11.g Amendment No. 86 I
LAR 90-0023 Marked Up Technical Sp2cifications Page 65 of 84 F.A0f 0 ACTIVE FULUEWT5 BASES \ 3/4.u.4 TAL 00$E This specifi tion is provided to meet the cose limitations of a0 CFR Part 190 that we been incorporatec into 10 CFR Part 20 by 46 FR 18525. The specificati reevins the preparation and supeittal of a 50ecial Report whenever e calculated cosas free plant generated radioactive effluents and di t radiation axceed 25 areas to the total bocy or any organ, except the t roid, which shall be limited to less than or toual to 75 areas. ~ For sites containing up to 4 reactors, it is highly unlikely that the nsultant cose to a CF THE PUBLIC will axceed the cose limits of 40 CFR Part 130 if the vidual reactors remain within twice the cose design oojectives of A 1x I, and if direct radiation cosas free the reactor units and o ' e storage tant.s are kept small. The Special-Report will descr' course of action that should result in the limitation of the n I cose to a MEMBER OF THE PUBLIC to within the 40 CFR Part inits. For the pumoses of the Special Report, it may be assumed 4the cose commitment to the MEM8ER OF THE PUBLIC from other ura %e 'uel cycle sources is negligible, with the exception that } contributions free other nuclear fuel cycle facilities at the i site or within a radius of 8 as sust be consicered. If the dos to any NEMBER OF THE PUBLIC is estimated to axceed the requirements 40 CFR Part 190, the Special Report with a recuest for a varia e (providea the release concitions resulting in violation of 40 CF Part 190 have not alreeay been corneted), in accordance with the prov ions of 40 CFR Part 190.u and 10 CFR Part 20.405c, is considerec o be a timely reouest and fulfills the roovirements of 40 CFR Part until NRC staff action is concleted. The variance only n1 stas to the inits of 40 CFR Part 190, and does not apply in any way to the other uirements for cose limitation of 10 CFR Part 20, as accressed in Spec ications 3. u.1.1 and 3. u.2.1. An individual is not considend a M [R OF THE PUBLIC curing any period in which he/she is engaged in carry g out any operation that is part of the nuclear fuel cycle. l
}
l OAVIS BESSE. UNIT 1 B 3/4117 Amendment No. 86 l
l LAR 90-0023
. . Marked Up Technical Spacifications Page 66 of 84 344. U R.ADIOLOCTCat (W1RONMENTAL MONTTORING BA$
3/4.U\MONTT0RINGPROGRAM The racio) ical sonitoring progran recuired by this specification pro-vices seasu sents of radiation and of radioactive materials in those exposure pat.. ' ys and for those redlanuclides which lead to the highest potential radi ion exposures of individuals resulting from the station operation. Thi nitoring pmgram therecy supplements the radiological effluent monitori program by sensuring concentrations of racioactive materials and leve of raciation which may De concared with those expectec on the basi of the effluent sensurements anc mooeling of the environmental exposur pathways. 3/4. U,2 LAND USE CENSU This specification is provi I ensure that changes in the use of unrestricted areas are ident and that socifications to the sonitoring program are saae if recuirec e suits of this census. This census satisfies the requirements of $ o IV.B.3 of Appenoix ! to 10 CFR Part
- 50. Restricting the census to ga f greater tnan 50 ma provices assurance that signo .ut axoosu lys via leafy vegetaoles will be icentified and so tored since a i of this site is the sinimum recuired to produce t.se cuantity (26 ear) of leafy vegetables assumed in Regualtory Guide 1.109 for consumet n by a child. To osterstne this sinious garcen site, the following aan ions were nace: 1) 20% of the garoen was used for growing broad leaf ve tation (i.e., similar to lettuce anc caobage), and 2) a vegetation yield of kg/ma ,
3/4. U. 3 IWERLABORATORY COMPAR!$0N PROGRAM The requirement for participation in an approved terlaboratory Comoari-son Program is reovided to ensure that independent necks on the precision and accuracy of the measurements of radioactive mat ial in environmental sample matrices are performed as part of the cuality surance program for environmental monitoring in orcer to comonstrate that e results are reasonaoly valid for the purposes of Section IV.8.2 of encia 1 to 10 CFR Part 50. DAVl$-BE$$1. UNIT 1 g 3/4121 heendment No. 86
t.AR 90-0023 Marked Up Technical Spacifications Page 67 of 84 5.0 DESIGN FEATURES 5.1 SITE EXCLU5!0N AREA. 5.1.1 The exclusion area is shown on Figure 5.11, LOW POPULATION ZONE 5.1.2 The low population zone is shown on Figure 5.1 2. 5[2 CONTAINMENT
\ 6 "
CONFIGURATION 5.2.1 The containment structure is comprised of a steel containment vessel, having the shape of a right circular cylinder with a hemispherical dome and ellipisodal bottom, surrounded by a reinforced concrete shield building. 5.2.1.1 CONTAINMENT VESSEL
- a. Nominal inside diameter = 130 feet.
- b. Nominal inside height = 285.5 feet.
6
- c. Net free volume e 2.834 x 10 cubic feet,
- d. Nominal thickness of vessel walls = 1 1/2 inches.
- e. Nominal thickness of vessel dome
- 13/16 inches.
- f. . Nominal thickness of vessel bottom
- 1 1/2 inches.
5.2.1.2 SHIELD BUILDING
- a. Minimum annular space a 4.5 feet.
.. b. Annulus nominal vol me a 678,700 cubic feet. l c. Nominal outside height (measured from top of foundation base to the top of the done) = 279.5 feet d.- Nominal inside diameter = 139.25 feet, j- e. Cylinder wall minime thickness
- 2.5 feet.
l f. Dome minimum thickness = 2.0 feet. I g. Dome inside radius = 125.29 feet. DAVIS BESSE. UNIT 1 5-1 i
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LAR 90 0023 Harked Up Technical Specifications
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I la , e S*- / 0 OAY!$ it!!!, ;'N!T 1 p ,, 15 Amendment No. 86
t LAR 90-0023 Marksd Up Technical Specifications l' age 71 of 84 1
; A/fd 0AlLY ,
ADMINISTF.ATIVE CONTROLS )
, i 6.8.3 (deleted) ,
i 6.8.4 The following pregrams shall be established implesented and sintatted l
- a. Primarv Coelant Sources outside Containment A program to reduce leakage f rom those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as lov as practical levels. The systems include makeup, letdown, seal injectien, seal return, low pressure injection, containment spray, high pressure injection. vaste gas, primary sampling and reactor coolant drain systess. The program shall include the following (1) Preventive maintenance and/or periodic visual inspection requirements. and (11) Integrated leak test requirements for each system at refueling cycle intervals or less.
- b. In-plant Radiatten Monitoring A program which will ensure the capability to accurately deter-sine the airborne iodine concentration in vital areas under accident conditions. This progras shall include the following (1) Iraining of personnel, (ii) Procedures for monitorir.g. and l (iii) Provisions for maintenance of sampling and analysis l equipment.
i i I f Amendment No. 9.!!.II'IIi I ! DAVIS-BESSE. UNIT 1 6-14 I
LAR 90 0023 Marked Up Technical specifications Page 72 of 64 ADMINISTRATIVE CONTROLS 6.B.4 (Cont.)
- c. Post.Accjdent $smolino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodittas and particulates in plant tastops affluents, and containment atmosphere samples under accident conditions. The program shall include the following: .
i (1) Training of personnel, (ii) Procedures for sampling and analysis, ; (111) Provisions for maintenance of sampling and analysis Ck . 4- 1 Al$ k 6.9 rep 0RT!NA REOUTPEMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting reautrements of Title 10, Code of Federal Regulations, the following reports shall be submitted 3 j to the appropriate Regional Office unless otherwise noted, t STARTUp REPORT 6.9.1.1 A suunnary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operatin license, (2) ; amendment to the licensee involving a planned increase n power level, (3) installation of fuel that has a different design or has been manu. factured by a different fuel supplier and (4) modifications that may have significantly altered the nuclear,, thetsal, or hydraulic perfor. mance of the plant. 6.9.1.2 The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operatinti conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica. tions. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional spea.ific details reeviredininthis Ciudad license conditions based on other connitments shall be in. report. 6.9.1.3 Startup reports shall be sutaitted within (1) 90 days following completion of the startup test program or commencement of commercial power ope,ra(2) tion, or (3)909days following months resumption 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 DAVIS BC$$E, UNIT 1 6 14e
LAR 90-0023 Harkod Up Technical Specifications l' age 73 of 84 h bCRX "I 4 Radioactive Effluent Controls Prodram A orogram snail be proviced conforming with 10 CFR 50,36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably acnievable. The program (1) shall be contained in the 00CM, (2) shall be implemented by operating procecures, and (3) shall in* clude remedial actions to be taken whenever the program limits are exceeced. The program shall include the following elements:
- 1) timitations on the-oceracility of radioactive liouic and gaseous tonitoring instrumentation including surveillance tests and set
- point determination in 6ccoraance with the methocology in the 00CM,
- 2) timitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appenoix B, Table !!, Column 2,
- 3) Monitoring, samoling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the 00CM,
- 4) Limitations on the annual and Quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conform-ing to Appendix I to 10 CFR Part 50,
- 5) Determination of cumulative and projected dose contributions from racioactive effluents for the current calendar cuarter and current calendar year in accordance with the methodology and parameters in the 00CM at least every 31 days,
- 6) Limitations on the operability and use of the licuid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radio +
activity when the projected doses in a 31 day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix ! to 10 CFR Part 50,
- 7) timitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the $1TE BOUNDARY conforming to the doses associated with 10 CFR Part 20 Appendix B, Table II, Column 1, I
l
L.AR 90-0023 Marked Up Technical Specifications Page 74 of 84 g Q $ (r.,4 I T 00MTD S) Limitations on the annual ano avarterly air doses resulting from noble gases releasec in gaseous ef fluents f rom eat.n unit to areas heyond the SITE BOUNDARY conforming to Appendit I to 10 CFR Part 50 I
- 9) Limitations on the annual and ouarterly doses to a MEMBER OF THE PUBLIC from locine 131. Iodine-133, tritium, and all racio- i nuclides in particulate form with half lives greater than 8 days ;
in gaseous offluents released from each unit to areas coyond the 1 51TE BOUNDARY conforming to Appendix ! to 10 CFR Part 50, '
)
1
' 0) Limitations on the annual aose or aose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
9 Radio) oical Environmental Monitorina Program A program shall be proviced to monitor the radiation and radio
- nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental expo-sure pathways. The program shall (1) be contained in the 00CH, (2) conform to the guidance of Appendix ! to 10 CFR Part 50, and
'3) include the following:
- 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the method-ology and parameters in the 00CM,
- 2) A Land Use Census to ensure that changes in the use of areas at anb beyond the SITE BOUNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and
- 3) Participation in a Interlaboratory Comparison Program to ensure that incepencent checks on the precision and accuracy of the measurements of racioactive materials in environmental sample matrices are performed as part of the Quality assurance pro-gram for environmental monitoring.
L.AR 90-0023 Marked Up Tochnical Specifications rage 75 of 84 ADtt!N!$TRAffyr covrPOL5 I The Annual Radiological Environmental Operating Report coverinc the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall incluce summaries. interpreta-tions, ano analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The materia) provided snal) be consistent with the objectives outlined in (1) the 00CM and (2) 5.ections IV.B.2, IV.B.3, and IV.C of Appendix ! to 10 CFR Part 50. AWUst RA0!0LOGf tAL tWf t0*Drfal 0PrUffMG treceT g3,g,gw._ _ ._m m_ _ , ._ ___ ___.m_-_,
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a 7ta Mey 1 of'ess'h yeeS The"inNta1 reportlhaII'be auteiites pI 1 of the year following initial erittsality.
% Annue safelegical Emimmenul Operating Resens shall i use seonries, i rymutiens, ans an analysis ef tmnes ef the suit: ef the asielefisal e nalusing a samea meenul surveillance activities for et period,
- lentrols, as aco me en with theviu presserttional tA operettenal
, and previous emistuetes, I surveillance wru and an asses of the e6eerves issatu the plant operation an the environment. The ru shall also ins se sensusas reevired by 5p the resulu of lane testion 3.32.2
% Annunt Radielevisal tavi 1 ing Aeoerta shall incluse the tsults of analysts of 411 roeielegi amirenanntal resistian sensu emirensensat samsles ans of all euring the series pursuant to tne esattens sectified in the Tatte Fi in the 00CM, as well as summar=
sed ans tasulated results of e ane yees anat same ine1 visual resul measuremenu. In the event M resort shall be a re not avalfatte. insiusten with the report, noting and amelatni oissing resulta The sting esta a shall be suosit the reasons for the seen as peasible in supplementary .
% reporta e
'neielegical aise inclues the following; a sumasey eos 1stion of the urvering ironmental annitaring prograss at least the 1 le mass
'tireest sensling leastions bayee to a taale giving sistances art' from the sentarline of one reertart the resolu of Itcans petite in the Interlaborsury Casserisen progres, reeviree ey ggestig;12 ,
3J,ans visauss{en,ef ay analyses in waith the M OAVIS-tESIE, UNIT 1 6 17s Amendment No. 26,93 >
. _ _ , __.______.,.m_... , _ _ , . . . _ , . . . , _ . , _ _ . _
LAR 90-0023 Marked Up Technical Specifications Page 76 of 84
, ADMIN!$TILATIVE CONTROL 3
$EMIANNUAL RADICACTIVE EFFlutW7 AfLEASE Rf>0RT
- 4. 9.1.11k:di= "Miunin "un ^;':r: ";;;".; =;;cly r, ,.,,;f
r; =tt r' ; r; pui:n ' r:O; ;f :;; c.M. ;; 11 L ;_1;m in 60 days after January 1 and July 1 of each year. The period of th Pir report shall begin with the aata of initial criticality.
%e Rad etive (ffluent Release Resorta shall include a summary of ne nuantitiet f racisactive liquid and gaseous affluenta and solid sta eleased f the unit as evtlined in Regulatory Guise 1.21 " suring,
- valuating, a Reporting Redieactivity in Solid Wastes and esses of ladioactive
;eelea Nuclear P Mate als in Lieule and Gaseous Effluenta free ght watar-
- Planta,N Revision 1, June 1974 wit esta summarited in a duarterly basis 1 ewing the fomat of Appens a thereof.
%e Recieactive Effluent' lease Report to be sute ted within 60 days ifter January 1 of eacn yea shall include an an I suustry of heurly
.uteerelegical data cell ver the previo year. This annual suonary any be either in the fem of an r-by-hour 1 sting on magnetic tape of rine speed, wind airection, staes ric s 111ty, and precipitation (if seasured), or in the fore of joint distributions of wind speed, rind direction, and ataespheric stati' . This same report shall incluse m assessment of the radiation dose sue the redieactive lievid and paseous affluents released free unit o station during the previous
;alenaar year. This same rope shall also lude an assessment of the adiation ooses free racisa, e liquid and ga us effluents to NDGER$ l 4F THE PUSLIC eue to their ivities insiee the TI $00NCARY
- Figures 3.11 1 and 3.11- during ,tne report perj, . All assuestions isec in nating these a samenta, i.e. , specific act ty, exposure time ma location, shall - inclueed .in these reporta. The sessment of
'adiation doses sh be performed in accorsance with the thocology ma parameters i the 0FFSITE 00$f CALCULATION MANUAL (00CM
%e Radioact e Effluent Aalosse Report to be sutaitted 60 days ter Ianuary 1 - each year shall aise inclues an assessment of raciat loses likely east axposed MOSEA 0F THE PUSLIC free reacter esses i knd a r nearpy urania fuel cycle sources, including esses free pri l iff)ftnt pathways and direct radiation, for the previous calencar year t
$sEr conformance with 40 CFR Part 1M, Environmental Radiation frotection R eneeeee-?= nz' =: * = = "--- & -
The Semiannual Radioactive Effluent Release Report covering the op'er-ation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The report shall in- , clude a summary of the quantities of radioactive liquid and gaseous effluents 1 and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in con- 1 (formancewith10CFR50.36aandSectionIV.B.1ofAppendix!to10CFRPart50 l DAVIS lESSE, UNIT 1 6-17b Arnendment No. 86 { f
LAR 90 0023 Marked Up *ochnical Specifications Page 77 of 84 AONINI$TRATIV( CONTRCl$ SEMIAhAL RA010aCTIVf EFFLUENT #ELIA$f REPORT (Continued) k rse Radi etive effiu.nt R.i.ue R.p.rs. swii inciu.e tne foi&ing infor.stion for each ass of solid wasta (as eefined by 10 CFR Part $1) stippee offsite during the port period
- a. Con iner volume,
- b. Total rie ovantity (specify wnether detarsined by sensurement or esti ),
j c. Principal r ionuclides (specify wnether detemined by l esasuresent estiesta), 1
- d. Source of waste processing eseloyed (e.g. . dowatered spent .
nsin, compactee ry wa ta, evaporater battans),
- s. Type of container ( Type A, Type 8, Large Quantity), and
~
- f. $olidification agent e ont(e.g., cement,unaformaldehyde).
Tse Radioactive Effluent Release shall include a list and description of unplanned releases free the site ICTED ARIAS of radioactive esterials in gaseous and If ouid eff1 during the reporting period. The Radioactive Effluent Release Reports include any changes made during the recorting period to the PROCESS DL PROGRAM (PCP) and to the 0FF51TE Dost CALcVLAT!0M MANUAL (00CM), as 11 as a listing of new locations for cose calculations ana/or environmental no toring toontified by the land use census pursuant to specification 3.12.2. L DAY!$ SE55E, UNIT 1 617c Amendment No 86
-me-. --
LAR 90 0023 Marked Up Tochnical Sp;cifications l Page 78 of 84
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' l ADMINISTRATIVE CONTROLS L
< l;l SPtcIAL P.tPORTS l 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory l Coseission in accordance with 10 CTR $0.4 vithin 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 specifications I a. ECCS Actuation. Specifications 3.5.2 and 3.5.3. 1 t
.l l b. Inoperable Seismic Monitoring Instrunestation, Specification 3.3.3.3.
- c. Inoperable Meteorological Monitoring Instrumentation. Specification
. 3.3.3.4.
- d. Seismic event analysis. Specification 4.3.3.3.2.
ll
! e. Fire Detection Instrumentation, Specificattee 3.3.3.8.
i i
- f. Fire Suppression Systems. Specifications.3.7.9.1 and 3.7.9.2. )
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l LAR 90 0033 Marked Up Technical Specifications Page M of H u /r A*W!v!!"*RA?!YC CONT 20L5 __
- e. Records of changes made to Operating Protegures.
- f. Reccets of radicactive shipments.
;. seccres of sealed scurce anc fissten cate:ter test tests anc results.
- h. Recorts of annus) physical inventary of all sealed tource material of recort.
6.10.2 The fo11owing records shall be retained for the duration of the Facility Operating LLcense:
- 4. Records and draVing changes reflecting f acility design mccifi.
cations nace to systams and sceipment castribec in the final Safety Analysis Report,
- b. Records of new and irradiated fuel inventary, fuel transfers and assemD1y burnup histories.
- c. Recorts of radiation e.xposure for all individuals entering radiation control areas.
- d. Records of gassous and liquid radioactive material released to the environs.
- e. -Records of transient of c'perational cycles for these f acility components identified in Table 5.71.
- f. Recorts of reacw tests and e.xperiments.
- g. Records of training and cualiftention for current memners cf the plant staff
- h. Records of in. service inspections performes pursuant to inese Technical Spectfications, i.
Records of Quality Assurance activities requine by the CA Manual. J. Records of reviews perfereed for changes made to procedures or enviament or reviews of tests and experiennts pursuant to 10 CFA 50.59.
- t. Recerts of meetings of the SRA and the CNR8.
- 1. Records for Envi,'onmntal Qualification wnich are covered uncer the provisions of Paragrapn 6.13.
DAY!5 8t.551. UNIT 1 6 19 Aaenonent Orcer ats. Cet. No.
- u. rl.. [ . !.
I
1,AR 90-0023 Marked Up Technical Spocifications l' age 80 of 84
,, ACMINIST UTIVE CONTROL $
ortman P.ETEffiiON (continued) i I
- a. Records of analyses required ny the raciological environmental monitoring program that would permit evaluation of the accuracy of the analyses at a later cate. This should incluce pestacures
! ef fective at specified times and QA recera showing that these
' procacures were followed,
- o. Records of the service lives of all safety related hydrau-
; lic and sechanical snubbers including the date at whten the service life consences and associated tastallatton acc maintenance records,
- f. kc.40M5 Of rta,f e's.W & ft/bfrMM bf bjG made to th OFFSITE bo36 cat C04 A TloA)
M AN UAL. and. % PRocLS$ coM TR.ou PROGR A M , t DAV!5-BESSE. UNIT 1 6-194 knendment tid, gy , 94
LAR 90 0023 Marked Up Technical Specifications Page 81 of 84 ADMINISTRATTVE CONTt0LS 6.14 PROCE$$ CONTt01. PROGR.AM (PCP)
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l DAVIS-SESSE UNIT 1 6-22 Amendment No. 86
LAR 90-0023 Marked Up Technical Specifications Page 82 of 84 J N $66
- a. Shall be documented and records of reviews performed shall be retain-ed as required by Specification 6.10.L(. This documentation shall contain:
- 1) Sufficient inferrulon to support the change together with the appropriate analyses or evaluations justifying the change (s) and
- 2) A determination that the change will maintain the overall con-formance of the solidified waste product to existing require-ments of Federal, State, or other applicable regulations,
- b. Shall become effective af ter review and acceptance by the SAS and the approval of the Plant Manager.
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- a. Shall be documented and records of reviews performed shall be retain-ed as reouired by Specification 6.10.2p. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations,
- b. Shall become effective af ter review and acceptance by the 3RB and the approval of the Plant Manager,
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire 00CM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the 00CM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
_ - , _ _ . . . _ _ . _ - . _ _ _ . _ . . _ m_-_ .____ _ ~ -..__ _ - ____ _._ LAR 90-0023 Marked Up Technical Specifications Page 83 of 84 l ADMIN!!?tATIV( CONTROL 5 6.16 R CHANGES 70 RADICACTIVE L20VfD, GA5E0VS De0 50L!D WASTt TH ATMENT SYUEM5 6.18. Licenses initiated sejer changes ta the radioactive waste systans (liquid, gaseous sq solid):
. Shall be reported ta the Cassrlssion in the maata to the Safety Analysis Report. The discussion of esca enange sna11 contain:
A suunnary of the evaluation that led to the determination that the change could be made in accareance with 10 CFR Part 50.59; -
~
- b. fficient detailed informatten to tata11y s et the roasen for the enange without be it additional or sweelemental info ;
- c. A detai ription of the equipment, component 4 processes involved and the interfacts e plant systass; j
- d. Ae evaluscion cnange, which shows the predicted of radioactive antarials-in 11 q gaseous affluents and/or cuantity e d gasta that differ free those p i ly predicted in the license applicat i amenaments thersta;
- e. An evaluation of the , which shows the aspectaa maximum amnes e to individual in the UNRESTRI .AAEA and ta the general population tha tiffer from these previously esties n the license application and amenenen thereta;
- f. A camparison of the predicted releas of reaisactive estarials, in 11ouis and gaseous effluents and in solid wasta, to tne actual releases for the perite prior to when the changes are to be ones;
- g. An estimate of the exposure to plant operating personnel as a result of the '
enanget and DAv!$-SESSE, UNIT 1 6 23 kBendment No. 86
LAR 90-0023 Harked Up Technical Specifications Page 84 of 84 k ADMIN!$iRATIVE CONTROLS 6.11 %)0R CHANGES TO RADICACTIVE LIQUID, GASEOUS, AND SOLIO W ASTE hREATMENT SYSTEMS (Centinued)
- h. Documentation of the fact that the change was reviewed and found acceptable by the Station j Review Board.
- 2. Sha become effective upon review and acceptance by th Station Review Board.
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@d DAVIS-BESSE. UNIT 1 6-24 Amendment No. 86 I
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Docket Numbor.50 346 ' License.Hitmber NPF-3 Serial Number.1815 Attachment 2 1 i REVISED OFFSITE DOSE CALCULATION MA!!UAL. k I
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