ML19259D177
| ML19259D177 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/10/1979 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19259D178 | List: |
| References | |
| NUDOCS 7910160535 | |
| Download: ML19259D177 (100) | |
Text
Alabama Power Company 600 North 18th Street i, Post Office Box 2641 Birmingham. Atabama 35291 Telephone 205 323-5341 kb C'##,%2t AlabamaPower A
the southem c&tnc syste.m October 10, 1979 Docket Nos. 50-348 50-364 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentiamen:
RE: F. L. Clayton's Letter to Director of NRR dated April 16, 1979 Alabama Power Company submits the proposed amendments to the Technical Specifications for the Joseph M. Farley Nuclear Plant Unit No. 1 incorporating
- Radiological Ef fluent Technical Specifications into Appendix A and the pro-posed draf t Radiological Ef fluent Technical Specifications for Unit No. 2.
This submittal is a result of a meeting with the NRC staf f on June 6,1979 after the referenced submittal. The April 16, 1979 submittal was reviewed and approved by the Plant Operations Review Committee and the Nuclear Opera-tions Review Board. This resubmittal was reviewed and approved by the Plant Operations Review Committee.
Please note that this submittal does not address solidification of radio-active waste. Farley Nuclear Plant is currently utilizing the services of Chem-Nuclear, Inc. to perform solidification of certain radioactive wastes.
The topical report for the Chem-Nuclear process is being reviewed by the NRC staff. A technical specification will be developed by Alabama Power Company and Chem-Nuclear, Inc. following the completion of the staff's review of the topical report.
Also, note that the Minimum Detectable Concentration sensitivity values in Table 4.11 '. for Iron-55 and Potassium-32 have been omitted pending develop-ment of suitable analysis procedures.
The class of this proposed amendment is cesignated acccrding to 10 CFR 170 requirements. This change is deemed nat t' involve a significant ' hazard consideration and is considered a Class III change. A check for $4,000 is enclosed to cover the fees regulred.
79101 60 57:5'55 11(3 154
Director of Nuclcar Reactor Regulation PAGE 2 October 10, 1979 In accordance with 10CFR50.30(c)(1)(1), three (3) signed originals and thirty-seven (37) additional copies of this proposed amendment are enclosed.
If you have any questions, please advise.
Yours very truly, dg b 4A '
F. L. Clayton, bA r.
f' FLCJr/HRF:bhj SWORN TO AND SUBSCRIBED BEFORE Enclosures ME THIS 10thDAY OF October _,
1 .
cc: Mr. G. F. Trowbridge g j{ b-Mr. R. A. Thomas ) I l'otary Public
[/
My Commission Expires: 5-22-82 Me I} - isJ 6
SAFETY EVALUATION BASES All changes were made to comply with NRC requirements /
directives. These changes are more encompassing and restrictive than the present env. tech. specs.
The subject changes do not constitute an unreviewed safety question as defined by 10 CFR 50.59.
Ill: lD6
A ENCLOSURE 1 REVISED TECH SPEC -
(1) DEFINITIONS (2) SECTION 3/4-3, INSTRUMENTATION & EFFLUENTS (3) SECTION 3/4-11, EFFLUENT TREATMENT (4) BASES (5) SECTION 6
/~ 1 E. 7
. tJl k
' 6 ._ $ ,
1.0 DEFINITIONS
$.t
- f.1 DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type at;d are applicable throughout these Technical SpecificationsF OPERABLE - OPERABILITY 1.6 A system, subsystem, train, cmponent or device shall be OPERABLE or .
have OPERABILITY when it is capable of perfoming its specified function (s).
Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, nomal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equip-ment, that are required for the systs, subsystem, train, component or device to perfom its functions (s), are also capable of perfoming their related support functions (s).
CHANNEL CALIBRATION _
1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy
(' to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by any series of sequential, over-lapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK -
1.10 A CHANNEL CHECK shall be the qualitative assessment of channel be-havior during operation by observation. This detemination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be: p, ;,,,g
- a. Ancic;; innel: - 4he inject'on of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alam and/or trip functions.
- Sec NUREC 0:'12, NUREC "!02 and *:UREC ^^52 "St2H2M TecHica!
v Spcci ficction; fc r ?"2' ".
11, ,i;8 r-
__ , m,m srsa _ _...-. _ _. . y _t y _ _.: _
_ _ _ _ _ . _ . ~.. _ _ _
-m. '"*7~A~~ M' M _ m __r
__w
6gj Q t'
\ ,
1.0 DEFINITIONS (Continu2d)
- b. 3i:t:bic charn;?: the i;dectica cf : simulated signal irite the cen:cr te ver fy OPEPra!LI" 'nchdi g cler and/or trip i
g
- (] -
-functic m --
DOSE EQUIVALENT I-131 1.19 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (uCf/ gram) which alene would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present.
The thyrcid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."
SOURCE CHECK 1.29 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
PROCESS CONTROL PROGRAM (PCP) g ,,. 7m y 1.30 A PROCESS CONTROL PROGRAM shall contain the :: p?ing, analy m , o . .h \
! fomulation detemination by which SOLIDIFICATION 4of radioactive wastes
- N f.m liquid syste : is assured.. ng;J Wsub-o.nd $c JeMering , f n,.lleM;re. r sNs e SOLIDIFICATION lipd 1.31 SOLIDIFICATION shall be the conversion of4adioactive wastes from liquid systems to aph-c:e-aau: 'u 4'e 'y d':t #Suted), manclithic, @
immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.32 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offrite doses due to radio-active gaseous and liquid effluents. cad in the calculatica of p;ccc: and @
"auid eff1uent critering instrurentatier :!: m/ trip ctpciate.
~
I 11 - ! J/
' " . " ' , STS 1 1-1 w
+-n. ,
I .. ._ .. .- ._ ..
1.0 DEFINITIONS (Continued) i r*
j G_ASE00S RADWASTE TREATMENT SYSTEM 1.33 A GASEOUS RADWASTE TREATMENT SYSTEM is any systen de igned and in-
.. stalled to reduce radioactive gaseem effluents by collecting primary coolant system offgases fran the primary s3 sten and providing for delay or holdup for the purpose of reducing the total radioactivity prior to rel ease to the envirorment.
VENTILATION EXHAUST TREATf'ENT SYSTEM ,
1.34 A VENTILATION EXHAUST TREATNENT SYSTEM is any system des igned and irstalled to reduce gaseous radiofodine or radioactive material in parti-culate fann in effluents by passing ventilation or vent exhatst gases through charcoal adsorbers and/or HEPA filters for the purpose of renoving fodins or particulates fran the gaseots exhatst stream prior to the release to the envirorment.
Engineered Safety Feature (ESF) atmcspheric cleanup s3 stems are not cors idered to be VENTILATION EXHAUST TREATMENT SYSTD! components.
PURGE - PURGING 1.35 PURGE or PURGING is the controlled process of discharging air or gas from a confinenent to maintain tenperature, p ress ure, humidity, concentra-tion or other operating condition, in such a manner that replacanent air or gas is required to purify the confinement.
VENTING
,s 1.36 VENTING is the controlled procss of discharging air or gas from a confinenent to maintain tenperature, presure, humidity, concentration or other operating condition, in such a manner that rglacenent air or gas is not provided or required during VENTING. Vent, us ed in sys tem nams , dos not imply a VENTING process.
liff 160
- e p.- _ _ . - .
=@ w - w $ *esi www4 - e,.eg m ens a agspe- = ,
m . . -+m- -*e - - 8 e , ,e.
~,l
.. c * .'.
.7 TABLE 1.2 i.
FREOUENCY NOTATION W{P.)
s., NOTATION FREOUFNCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
.... W At least once sm M
At least oweg.,per perIA At least once per 31 days.
7 days.
kys. h -
Q At least once per 92 days.
, SA At least once per 184 dag.
R AT l east once per 18 months.
S/U Prior to each reactor startup.
. P Compl eted prior to each' release.
l N. A. Not applicable.
(?,'/] }h} P"" STN 1-\ w* 6
-. -- - - - = * - - - - - - - - - ~ ~ - - - * * * + - - - - - - - - '*
? - . _ . . - . - . .- -.
-- ~
4.: l _I.NSTRUMENTATION RADI0ACTIVC LIQUID EFFLUENT INSTRUMENTATION 'h so..;
*t. , j LIMITING CONDITION FOR OPCRATION lo IS
- 3. 3. 3. The radioactive liq id effluent monitoring instrumentation channels shown in Table 3.3- shall be OPERABLE with their alam/ trip setpoin';s set to ensure that the limits of Specification 3.11.1.1 are not exceeded.
t o . ... . . .so
........,...r
. . . o m w . m o . .s m m e ... . . ...mm ............o..
,,ith the Offsite Ocss Osiculetica F;nu;l (00CM).
um um-h APPLICABILITY: At ;il t'.me:. e di d
@enekolos eb o ose$rS V8IV'S a.v e. mo C
h - ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel alam/ trip setpoint less conservative than required by the above specification, immediately : :;:nd the reic : cf
-adicactive 'iquid ef#!uent: critered by the affected charac?
-ep. declare the channel inoperable.
- b. WithWecnc numherof c cr acre a nc..;c r:.&c:e\
A 9ofeO liqu.d effluent lessLn$c.*^imumcNn"< nit; ring in reyonel hT.Uen-estre entetice ch'nnel: in;;; rabic, take the ACTION shown in Table 3.3-+er :3,
- c. The provisions of Specifications 3.0.3,and.3.0.4 are not f',
v applicable. A g,,,g,,g) @n SURVEILLANCE REQUIREMENTS to 4.3.3.# Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE.by performance of the CHANNEL CHECX, SOURCE CHECX, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-te. 83 1 /7 1 , l I) { I'.."' STL1 3/4 3- M . G
.o.
j __ . 1 t t e
. . _ . . . . - . . . - _ _ _ . _ _ _.m___ _ . _ _ _
N ~ O - I T 8 9 C 2 2 A N SE O MLL I UEB T MNA A I NR 1 1 T NAE N I HP E MCO ' M ' U R ) ' T 8 e, S 3 4 2 I G c E N i K I R t a )8 ( O m 1 52 T o e 1' I t - n
- N u E i
3 O A L M g R 3 t T n ( n E N i e L E d u B U i e l A L v n f T F o i f F r L E E P
- t n D s n w I r e o U o u d Q T t l w I N i f o L E ne f l M os E B .
E U Ma V R e e r I T yl t o T S t e s t C N iR a a A I v w r 0 if d e I to a n D c R e _ A an G ^ _ R oo d _ - ii i m _ dt u ~a e aa q e ' aA Rn i i L S t
-- ( . [.
sm sr oe rT . . G a b e
)
a5 J
- 5 ol ..
~ .L
,t I g i; i ; .
! l. I i .
!> . I i
i
- , i 1II.i l ! i! [
.. :.' 75 '
l e i 13 TABLE 3.3- W (Continued) - 1 4
, RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRL' MENTATION i $5 i a i ; d MINIMUM lr L CHANNELS l INSTRUMENT OPERABLE ACTION
- z. Flow Rate Measurement Devices it t '
-ar Liquid 5d.;nte Efflucat Lir.c 1 31
,i b. Discharge Canal }//nl/on 4/34 ( T T' 57/) 1 31 2
- 'll
.- c. Steam Generator Blowdown Effluent Line (F7-//to) 1 31 i
LJ 2 5 ' Y a.. L;'.;d Rabsk EKlo,J h= 6am :
/ t 31
,' i) Ade & .A Lk No.1 GT-io854) e g wh L;1.r Lk S.2 C eT-iar8) 1 5l l
1 i. W 1
- a
, b
, b l .- - - - -_ .
- r. . . .
Ed. . 13
~., . i TABLE 3.3-4e (Continued) ..*'l TABLE NOTATION
.k]i . V ACTION 28 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may 4 continue for up to M days, provided that prior to initiating a @ r*l**5': " k.. 3.Ir c
k,he~k)
?s . "*Cl 1. At least two independent samples are analyzfease mde. d in accord-ej. k w;llbe i.deh ance
~w1thSpecLficftiop
<ch;a.g e ,r . a4.11.1.1.3, andt re
'7 }4e emlly 2. At least two technically qualified members of the Facility g e-[ S va.bfiel meder Staff independently verify the cica:c rat; calculation:-
.f & Eddy
? -and discharge valving. J
.. skfC.
Otherwise, suspend release of radioactive effluents via this pathway. ,
,- ACTION 29 With the number of channels OPERABLE less than required by The Minimum Channels OPERABLE requirement, effluent releases via .- this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7uCf/ gram;
- 1. At least once per 8 hours when the specific activity of the secondary coolant is ).0.01 uCf/ gram DOSE EQUIVALENT I-131.
O
- t. - 2. At least once per 24 hours when the specific activity of the secondary coolant is < 0.01 uCi/ gram DOSE EQUIVALENT
! I-131.
as s\hernahe. me.bo b of measor-;n [[ ;s eshsUsheb a wd mo.;nbi .e d in accodo nc e. wi f,. e 4.3-i3 og
~~
ACTION 31 With the number of channels OPERABLE less than required the Minimum Channels OPERABLE requirement, effluent rele via this pathway may continue 4 r-up tc 20 days providenti.Lc Ticw 12. rate 1: c timated ct least once per d hcur: dur N actua!
'aleerer_ [ ump curves may be used to estimate flow.
'L"'. CTC 1 3/4 3-Bq 11': 1G5 x
J
. . I_ _ _ . . _
-z.-~.-- . - - --.
- ._. ..:.: .'... m .. . .
. - .. ;.. .- _ . _.. . . . - . - - - . . . . 2 . ,
la I -s TABLE 4.3 @
- i i i RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l < 4
-A CHANNEL l CllAtlNEL SOURCE CilANNEL FUNCTIONAL _
, INSTRUMENT _CilECK CitECK CALIBRATION TEST
... Gross Beta or Gama Radioactivity
.tonitors Providing Alarm and Auto-matic Isolation !
- a. Liquid Radwaste Effluents Line(CE-lf) O P R(1) Q(1)
L b. Steam Generator Blowdown Effluent 0 M R(h Q(1) Line ( RE- 13 B) i M
=
a
, , m J
!lc f cs
! os p
't l !
'i li
rg i ,,).S:.M,!: __w..... i
-3 ,
8 N ;,
- 13 b
a h TABLE 4.3-W(Continued) I e j RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . b .. CHANNEL CHANtiEL SOURCE CHAllNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION
> TEST .
I l
,l 1 Ji I
i , b ! j! ! M y s a t w I 4 7 l 6
~, -- .-. .-
'~' ,
- 2. Flow Rate Monitors _ . . . -b7-'"5 4 *") FBo:S h
' 3 '
$$ a.LiquidRadwasteEffluentLine/ D(t) N.A.
N 3 R .(f # A . I . , b. Steam Generator Blowdown Line(FT-1/so)D(/) ti. A. R
-Q-tJ.4 l3 3
I c. Discharge Canal Pi/4684 LineIfT-570 D(/) i fl. A. R 4 N. A s
,! i i
e
la TABLE 4.3-+9- (Continued) TABLE NOTATION i: i: - (1%The CHANNEL FUNCTIONAL h3T shall-e+se demonstrate that automatic isolation of this pathway and control room alann annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alann/ trip setpoint.
- 2. 44Nwit f:1? ure. Less of ced"I f '" 19
- 3. In:tre ent %dfcate : dcun:ccie f;il.re. 1 o "
- f '"5I"E f*"*
- 4. hatrom;nt ccatrab nct :ct in perate cdc.
GI N e C H 4 WNE L PU:.CTION Al. TEST sball dew.owshvale o- coMvol l roo nlan 4 F co- .%, c ad:
- i. lub.ed .co.. bis ci,..t ,o.,
.ccobehl ver- l 2.At least two technically qualified members of the Facility
'. ;f;cd by a. tech-) n;al 9v.lifie~~ Staff independently verify the relcas rctc c2!ce! tier.c il
. .,,t,[l7,pg e, end-discharge valve lineup; Plant sbff Otherwise,, suspend release of radioative effluents via this pathway. . g ACTION 36 With the number of channels OPERABLE ess than requirdd by the Minimum Channels OPERABLE requirement , effluent releases via this rate pathway is est mated may at continue least on for up to 3p days proviqed t ie flow veah,' y
^ s 47 pe + houIes. Mov~oFQsfa are dw Me" ' lak. 3 con sme.;nJeb.itelgv 7 sa.P ACTION 37Difh'tTe#numeEEcbaYneisk BI. Te's# s T a Erequ$ ed by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours and these samples are analyzed for gross activity within 24 hourgs _ 1.C'!CN 00 'Jith thc ns.ber of chanach d?:"ACLE ic:: than rcquircd by the
",inimu" Chcnnch 0"E"f2LE rcquirement, inmcdictcly suspcnd
-PURGINC cf radicactiec cf'iucat: vic thi: pcth.:y.
Nov al bothw venhladien m cod;wve idefi"iI*I P"'"' ds..glesofd$pJ 3 "#an.!ysed ** **f'. b (l g: .. lead once ;per Wooa+myrs. .re dakew -~)
~
ACTION 40 With the number of channels OPERABLE one less than required by lb the Minimum Ch'annels OPERABLE requirement, cperatier cf thi: ~
. Sy:t~" ""y ^"th= 2: G t; li tys. 'Jith 'tn;) ch;n ,;h in '
epe-2b ir 't Tcc t "0 eF
+cobg!c,50isolde Me oxg:ew s.T *TN!DSreco 3
,,ithinffl Toive.te de. o.ffeele
.]
-FE-575-l' 3/4 3-e kk'.
m , iib
. ... . -. . ~ . . ..
&f9M44N!.c e"M:n -
-- >= : -
~ ~
's -
+
h-l TABLE 3.3 l (Continued) .g1 ' TABLE NOTATION 2-r-. . . g. G. ACTION 41 With the number of channels OPERABLE less than required by the O Minimum Channels OPERABLE requirement, effluent releases via
'L -
this pathway may continue er _; L 3" is, provided samples are continuously collected with auxiliary sampling equipment h as required in Table 4.11-2. w:-: .i Zi'-- g.- . v ji,
- }}/.
s
* ' 9$ .i. -
y, g
% .s6 90 4 e
?.
p .' e# 9
*e f
e Y
-PMR=MS-1-- 3/4 3- R e
-y
~ '
** 4
. ., , _ 4
^~ *
% ~ . ' '."**
- e S*
(: . .,- % ;. . , %3 , (] .
. :!j%f tye#gg',tgyg
* 'q,g a i it TABLE 4.3 y
~
f
- l. , ?)
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ., A: i'l '
.1,: . . F CHANNEL iG '" 4 3- MODES IN WHICil CilANNEL . SOURCE CHANNEL SURVEILLANCE,
;v INSTRUMENT FUNCTIONAL l- ,
CilECK CilECK CALIBRATION TEST
. REQUIRED "
..%* s -
! ~. . T; -41 te Gas'lloldup System '
' ~;. e , I'; , ,
; ;. i-
- a. Noble c ity Monitor P P R(3)
Q * ; .l
, .l, :
,. g
- b. Iodine Sampler i W
c. N/A N', .
, ,,. N/A , i *
.- Particulate Sampler W N/A
' ~~
N/A I- .[
- d. System Effluent Flow Rate P- N/A
[ ,' , . , Measuring Devi
.Q
* . i
- ,_ y' .'
.I l.* ' e r Flow Rate Measuring D N/A R Q
s l
, W .
- p. : ! 2 ), -6 Waste Gas lloldup System Explosive w Gas Monitoring System '
J. - i M a. Hydrogen Monitor ( Ja /g f) D N/A Q(/) - M ** -
- b. llydrogen Monitor ( oc<tlet )) 0 Q(g)3 N/A i M ** ..- -
i.,r c. Oxygen Monitor (Ju/d ) D N/A Q(g)+ H ** i3 d. Oxygen Monitor ( n o t/4/ _) D N/A Q(g) +- ** M ,
- j.
'.i,, i e a
'e
- s. '
~
,' ] ,.
' I
'g, , l e
,.i . j - - +
~.a
, *, ' 'I LTI
'f j.?.i -
( ,
, g ,
; i. .a.- /) ""! ,8,jIsl#:17/;[Nj(#i M y.b.id.',SY h k M h h .
li .. j i TABLE 4.3 (Continued)
.l 'i ,;r ,:2 RADI0ACTIVEGASE0USEFFLUENTNONITORINGINSTRUMENTATIONSURVEILLANCEREQUIREMENTS';
i - - 9' i
'3 ,i1
' ' . CHANNEL e HODES IN WHICH 3 ' CHANNEL SOURCE . CHANNEL k FUNCTIONAL' SURVEILLANCE -
INSTRUMENT CHECK CHECK' CALIBRATION TEST '*j REQUIRED i ,
. Containment Purge Vent System .
i'
' i* -
'j ,
- a. Noble Gas Activ onitor P-D
~ $-Q(1)' "
'7
- R(3)
- b. Iodine Sampler W/ N/A N/A
'N/A
- i . . c. Particulate Sampler W. N/A
- I7
, 'N/A .
~
- d. System Effluent Flow Rate 2-D N/A - ' '-
2 y Measuring Device Q I .s , .i ., ,. i - p e low Rate Measuring D, 'R' ' N/A . . . Q. : ',
- 7
- . i-
~. ,
- l. .
.g
+ i.'.
1 r . 1 .
~~
I i w 8 , *t
+ x ,
s s __ .* 4
~a . . .
, c'- ,
- 1. i f
I 1 J l , *.. .
_ .:.@ . < c.. .
\ - . - . . _
._ :L ' :. : H .
. .%f table '4.3 dip (C6ntinued) h! RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
$1 INSTRUMENT CHANNEL SOURCE CHANNEL CHANNEL FUNCTIONAL MODES IN WHICH l P. CHECK CHECK CALIBRATION TEST SURVEILLANCE
*K, Vent Header System ,
REQUIRED g
- a. Noble Gas Activity Monitor ~ D M R(g) *
(g e -14 er R E - 2 2 ) QMI)
- b. Iodine Sampler W- N.A. N.A. N.A. *
- c. Particulate Sampler W N.A. N.A. N.A.
- i i d. System Effluent Flow Rate Measurement Device D,
- N.A. R Q
- e C
- c. S=pler Flo; fictc "ccsuc=.cr.t Cc.icc 0 h.A.
h l , 3 R Q
- I 5 S 5>'.esm 32f Air 5jictor Sys/sn
. w 3- I
@, a. Noble Gas Activity Monitor D M be 2,3,+ g R(2) Q(2f
- ' ~
i . (R odineE-IC) Samp ler W- N.A. N.A. ..
- I I
lg c. Particulate W N N.A. N.A.
- li d. System Effluent Flow Rat l Measurement Dev 0, .A. R 'Q
- I i _ .p er Flow Rate ql _. Measurement Device D N.A. R *
[ g> l [ f
! -J l N i
{l 1 J
b ' It TABLE 4.3-4-3-(Continued) TABLE NOTATION .
~.
h ..
*At all times.
recon % <r -
-H s'
~
.[.'.
**During ne5te ses helip systa;; operation 'e ^, 7// ;l4 i m , 4,um.
M . '- '% (1$)The CHANNEL FUNCTIONAL TEST shall ehe-demonstrate _ that automatic . i.?: isolation of this pathway and control room alam annunciation occurs .-
- f. -
it any of the following conditions exist: -
~
. 7I:
- 1. . Instrument indicates measured levels above the alam/ trip
+ setpoint.
- 2. s........s,._... ... Losso-( c p P'w w
_ s _
,- 3. r,.st. m.xer.t ii.Jicetm e i ..scelm Te;;u c. Loss J insluaie=I P o'"*
'. In:tT= t ^^CtT^'- ^t ^^t 'n p;;-ate .T.;de.
(IMffQ The CHANNEL FUNCTIONAL TEST shall .ahe demonstrate that control room 2 alam annunciation occurs if any of the following conditions exist: J
.. . . . u . u ...m . . e . . .u . s.o u ca ...c o 2 u. cu .c c.a avvve uie o a na, u . g
- tpcirt.
- 2. Circuit f fkre.
%.* Instrument indicates a downscale failure.
1.'h Instrument controls not set in operate mode. N %. CHAM.B CALliiPATtorJ s>,Ja sa. s a a a>
* *
- Y ea- oY a.~hc4 gas 2*us radicait;ue, scurc2 'g;g_ g.gg.g, caQi
'ag a. masan,mt qdu eWd. is b 40.:. L de N.di.,4 h., , .
Mu-a.s ra=ha% -sunuzt sp%. r .'". "' - !$- 1 3/4 3-W m e l_ , 73+;.. .- ' ' ' - -
;.~ , ,,
5 _ - - - _--M% ~ _ .?- _ - ? -
.. . v
.>..,_.;....,.,~..
p' .
, . 14 .
. TABLE 4i3 W (Cdntinued)
~
TABLE NOTATION 3 j P M The CHANNEL CALIBRATION shall include the use of standard gas samples U p . containing a nominal: , .- ---
#%k ... . , p h . . ' M .
?
.,,.l . . .
f '
.1. ~$ne volume percent. hydrogen, balance nitrogenM(Iwlek.Ns.sadoko
~
$d' - - - 2.
,'r e gis . ye yo>,,I
_ p p~ent hydrogen, balance nitrogen ( odId Na,. %;}or),. )
- 3. . E' I
..~5. .~ ' loo f,. ,hd.vgee ( dide 2.eyo N
. [ddw,wdor3}
(5), The CHANNEL CALIBRATION shall include the use of standard gas samples . containing a nominal: - N f %. 1. ene .,0!= p==t =ys=, 5 = af tres=: =e 3g. 2. rar <::= per=t =ys=, 5::= nitres =. .. g i.- Leb ,,4 o y C w o.-ce.1 m, o,. l ), - c ~, b-) ou as, fy 2 75 ff- A , 6 L., ac6 ,.Codleto2 3 +o do-).d t- 5 ioo7. x 63,s ( 6,. ,,,, L, g m ,,;h,.,) m.. Wu i l;! 79 S. { 4 .= - ," t w . T'" ;TS -
?/4 3-M,
~d
= . . _
......-_.,.7..........#.
, _ . _- t .t
- ,,y.gus. ~:.
- v. .k .
. ... . . . . ,. ~ .. . g . : . . .
.. ~ ... .
' ~ ' ' ~~ '
W.c 3/4.11 RADI0 ACTIVE EFFLUENTS 4 3.*~. 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION .
.5 .
LIMITING CONDITION FOR OPERATION w. h 3.11.1.1 The concentration of radioactive material released from the site (see Figure 5.1-4) shall be limited to the concentrations specified in 4
. 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides c her
,,j. than dissolved or entrained noble gases. For dissolved or entrained noble P gases, the concentration shall be limited to 2 x 10-4uCf/ml total activity. . APPLICABILITY: At all times. ~.'. 2 ACTION:
*- With the concentration of radioactive material released from the site m-Z- ' exceeding the above limits, 4 '
- R'., restore the concentration to hc
?. -3' b. within the above limitswi&N one bow ib wpivemen,f3 of 3,o.s 1 3.o.+ a.a M q/ ,l cde g SURVEILLANCE REQUIREMENTS
. .1.1.1 The radioactivity content of each batch of radioactive lig c.) waste all be determined prior to release by sampling and analysis /J C! accordanc ith Table 4.11-1. The results of pre-release analy shall L/p be used with calculational methods in the ODCM to assur' at the con-centration at the int of release is maintained within e Ifmits of Specification 3.11.1.
4.11.1.1.2 Post-release ana s of samples . . posited from batch
~
releases shall be perfonned in a danc ith Table 4.11-1. The results of the previous post-release analyse all be used with the calculational methods in the ODCM to assure th he c entrations at the point of re-lease were maintained within e limits of ification 3.11.1.1.-
+ 4.11.1.1.3 The radi ivity concentration of liqui discharged from continuous relea cints shall be detennined by collect and analysis of ramples in cordance with Table 4.11-1. The results of analyses shall be d with the calculational methods in the ODCM to ass that the c entrations at the point of release are maintained within th ej. I s of Specification 3.11.1.1. .
n0 1 j3r! ML ';T'; 3/4 11-1 C Concebk;on of \ ' b ico kh c ma. kev,%
%.\\\\
a.ms skll be Ah.n.,,o,,
; A sed +o bc ~:Y ll+eAc-le)qv:
vo t y fP obb.,m,3 mgns,1 6;w: 3 . m ,e. p L sthN I )s m 5 fee S enki a i M % .d ~ \pi, fro n ,, gesic k Tdle m m
- . m. .. .._._.w...u..-..
mout n.Il-l - y. y . . . . . - . , . g.; - RADIOACTIVE LIQUID WASTE SAMPLING AND ANAL.YSIS PROGRAM F5 s
?Iinio.uo., DetuS- .3 L1 quid Release Type Sampling Minimum - Type of Activity (oneerfa ri,~
g Analysis 4.+ Frequency Analysis ~ M S C ,3 T. ' Frequency
.. pCi/ml)a)(
if;. , e <.4 P, c::x
~- P .. .
.~.! '. A. Batch Waste Re- Each Batch Each Batch' Principa Gamma 5 x 10- - fi.:. lease Tanks 4c Emitters}* 3 .g 4 . , .
*f-M - '
I-131 . 1 x 10-6 Dissolved 3r.d p Entrained Gases.' 1 x 10-5 One Batch /M -M (Gamma Emitters).a
- P H-3 '
1 x 10-5
~
Each Batch ~ M. J .' b -
~'
Composite' Gross alpha 1 x 10-7
~-
~
P-32 _'.._'.^' (4%) v l Each Batch . Q b
^
Composite- j - Fe-55 rw iG E B. S tfen C2o taro v ~P W Principal Gamma S/w do w,tdf composite h Emitterde- 5 x 10-7 I-131 1 x 10-6 n b 4 b du 6 V t;u p astu ,
' Eetrai.;;d C :::
-m e--_,_
_g_
~ -~"e -
n g-- ,_ , e < n..-a_ , 1 x 10-5 H-3 9 , M h
=' -
. Composite - Gross alpha 1 x 10-7 a
'^-6 P-32 -l 3 f Q g Sr-89, Sr-90 5 x 10-8 Composite
-1
,e -6
.Fa-55 W .g 7,,yafst(g,,,, ,,g -7 C. Tudbre Budo;; pf 3 ?
^ cmHths ~ -
i .r an-h>-u 3/4 11-2 I go 1- 4 o/yg [ t , I u
- - - ~ * ---->,; _y t. . .e :.c , , ,
. . . , . _,..c.
- g. - : .g
~
},
k,.~..t 2 : ..+. . Z .^= D
'.\;x ; ; _
- 3. . . .
J . 9/- TABLE 4.11-1 (Continued) i TABLE NOTATION t
. Mkiman kfuefafje . encentnth r (Mp c.) ,
h*! a. Thg 'is the smallest concentration of radioactive material in a M[ sample that will be detected with 95% probability with 5% probability F.: ; of falsely concluding that a blank observation represents a "real" signal. 3.
. ~ .
g.: For a particular measurement system (which may include radiochemical g; m separation):
'4.66 s y _
h M D c.y E V 2.22 Y " exp(-Aat) .Q- , i- where - 17- - i.' ' MDc is the MimmeDeMidle bnchutetNas defined above (as pCi per
- e. ,
unit mass or volume)
... sb is the standard deviation of the background counting rate or of .Q. .the counting rate of a blank sample'as appropriate (as counts per minute)
E is the counting efficiency (as counts per transfomation) C V is the sample size (in units of mass or volume) 2.22 is the number of transformations per minute per picocurie Y is the fractional radiochemical yield (when applicable) A is the radioactive decay constant for the particular radionuclide at ir .the elapsed time between midpoint of sample collection and
.: time of counting (for plant effluents, not environmental samples).
- 1. The value of sh used in the calculation of the Mac! for a detec- ,
J uun system snall be based on the actual observed variance of the background counting rate or of the counting rate of the blank . . samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the Mst.for a radionuclide de-termined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides nomally present in the samples. Typical values of E, V, Y, at shall be used in the calculation. The background count rate is calculated from the back--
ground counts that are determined to be within + one FWHM (Full-Width-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide. TET^ 'r 3/4 11-3 M'i jl 1og i . .uc
~
_ . _ _..._. ~ ~ ' l ..
. . ; .. . _e . . .
- Tl .
l _
~
8f -g
.l TABLE 4.11-1 (Continued)
.d. : ^3-P* ' TABLE NOTATION h@ S.' b._ A cmposite sample.is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which . . .. y the method of sampling employed results in a, specimen which is repre-sentative of the liquids released.
- f. ~
- e. c
'h
.=. _ *.
n. .e
~
c f[ A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, g
, and then thoroughly mixed, M~'"' _d~:S :.. J.m CCCM, to assure representative sampling.
d y.' A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume of system that has an input flow during the continuous release.
*/. The principal gamma emitters for which the MDc\ specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list s
does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and repcrted. Nuclides which are below the Hpc.for the analyses shall be reported as "less than" the nuclide's toc] and shall not be reported as being present at the Npc level for that nuclide. The "less than" values shall not be used in the required dose calculations. only iw Nie eved M
+ ""
- s. so n,. as a a ~h Qri et ho seco a] esnNAyl-CXffh O*I } f M S*
'*j* t .
' n; fp /Jf k)/h bl !Y $
% )&;,, from ADc ~'v:vemeds o G Ta.Ne- H. t l -l -
" -_ 6 of 3d sLilh WaA P" "EN" % 4 1 5'-
g%4- - 7 6 -573-1 3/4 11-4 ]j } j]} J i _ _ _ _ _
--~- - - -
-., . g_
- j- . _.....:
,4.w.,,.
, RADI0 ACTIVE EFFLUEN1S DOSE -
LIMITING CONDITION FOR OPERATION ... l.I ~ 3.11.1.2 The dose or dose comr.itment to an individual from radioactive k - materials in liquid effluents released from the _ site (see Figure 5.1-4) shall be limited:,
;- - ~- ,4 r/ M,r m'O (f-.,~;,. .
..J .
- a. During any calendar quarter: 3 1.5 mrem to the total body and 4 -
f 5 mrem to any organ, and g .
~,..,a 9- b. ' During any calendar year: 13 mrem to the total body and .,
g , f 10 mrem to any organ.
- N a"- APPLICABILITY: At all times.
. ACTION:
(- -
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of
-7
- any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actiohs to be taken to reduce the releases of radioactive materials in liquid 3
effluents during the remainder of the current calendar m?arter and v during the subsequent three calendar quarters so that the cumula-tive dose or dose commitment to an individual from such releases during thesa four calendar quarters is within 3 mrem to the total body and 10 mram to any organ. r
.i
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
- - - 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid c.- effluents shall be datemined in accordance with the ODCM at least once .
per 31 days.
*~
l I s ? L 'r C -STS-1 -- 3/4 11-5 w* 6 O MMM 969 9 64*W f9
-*"*" wb =***===*+-~eer !. ..
' 4
. g . - - , ,,,
,,a-,--- .
_ _ .- _h A'
- _ ----*=-h._ _
Sh . _._.V 1. - . i '.: RADI0 ACTIVE EFFLUENTS 2l!'- LIQUID WASTE TREATMENT , LIMITING CONDITION FOR OPERATION aft _ _ h' pyv gri I- po--ti; ;etif3 -[e 3.11.1.3 TheA liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluert from the site (see Figure 5.1-4) when averaged over.I' V would exceed rem to the total body or-0.2 mrem to any 3g bse org 4 ,w},,y. u,,r - _, . IA5 g],. N81 APPLICABILITY: At all times. - ' ' w .. .. T,i ACTION: .-
- v. .
T ..
. .wim s -m ,m..
- o. -er Vith radioactive liquid waste being discharged without treat-ir.@e.abis Te .i~. c u.o.. ':1 de.72 4)
. n.ent and in excess of the above limits, in lieu of any other
-J report required by Specification 6.9.1, prepare and submit to the
.' Commission within 30 days, pursuant to Sptcification 6.9.2, a Special Report which includes the following information:
- 1. Identification cf the inoperable equipment or subsystems and the reason for inoperability.
d, 2. Action (s) taken to restore the inoperable equipment to L OPERABLE status.
- 3. Summary description of action (s) taken to prevent a recurrence.
- b. The provisions of Specifications 3.0.3 and 3.0.4 ~are not applicable.
SURVEILLANCE REQUIREMENTS
~
ho 'uw reshe.de d ee@ 4.11.1.3.1 Doses due to liquio rele e 11 be projected at least once per 31 days. in accordanca with the ODCM. Q r M epor4 i& s W e ) 4.11.1.3.2 The& liquid rac' waste treatment system shall be demonstrated
, OPERABLE by operating thetliquid radwaste treatment system equipment fee ei icaae M + ".W. < ".,* =
c,,+- u u.-r;i r.mt
.. z,s e:.,at least s. once per 92
---- .. - n...days ..,..u u-!cc t h e .".z z, . q .,u ., a sda
~
- s. e u I Y
% hoQ da,uO a, " % o,aAr:cke.$ C-o.ra.s o ee h O 0.n mem +a %
bbi b.1 3 o v- o. (> m.m s o may oqe
""" T! ! 3/4 11-6 ll .
- , S ..ar-s m
%e m-.
9
* * * - * * * - pe e.a em m.
, _ - e ame _
~
INSERT 3/oi_ The appropriate portions of a liquid radwaste treatment system are those portions which, if used, will lessen the projected offsite doses. If a waste stream is already at or below MDC, for those isotopes which can be removed by the system, the treatment equipment for that stream shall not be considered " appropriate porticr.s" of the waste treatment system. L % .se % a ace more. % ee pod.% d % =. wasb bsm.bmed s % m g be. w sad, b e%de. c9wd wak M e,on\g one. A %se. g.A cos ...A be. onc& sed "*y aereob " il : 106 4 9 0
M% .. rp.j - RADI0 ACTIVE CFFLUENTS LIQUID HOLDUP TANKS * [ 3 LIMITING CONDITION FOR OPERATION y 2 yg 3.11.1.9 The quantity of radioactive material contained in each of the following tanks shall be limited to < fo curies, excluding tritium and T.". dissolved or entrained noble gases. St. ,. . = . . S-
~
k U{ o..E. Obibe tE<Sorary tankg sIcO'- I, werswe iw . 3.y vee
.sa i
- c. .v- o kp%+,f d .
d foF 33 4st APPLICABILITY: At all times. -- - - 9 ACTION: -
~ '
- a. With the quantity of radioactive material in any of the above 2P listed tanks exceeding the above limit, immediately suspend a'l
? additions of radioactive material to the tank and within 48 hrs
;'[ reduce the tank contents to within the limit. . b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
r ~. te SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are'being added to the tank. i
~
2
.
- Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank
> contents and that do not have tank overflows and surrounding area drains - ~
connected to the liquid radwaste treatment system. , PMb-STbi 3/4 11-7 33.- , n7 l l .j i U1 .r% ) e.-
'I
.:-, : c_
~
.w_-- _ = ~ -- _-: .Ti . a =. _ . . .
. . . . .c .. . . .
--"I ' , . ~! RADI0 ACTIVE EFFLUENTS
. .1', "
3/4.11.2 GASEOUS EFFLUEh'TS DOSE RATE ,
=-
- 3. : ~
..,, LIMITING CONDITION FOR OPERATION
.Y , . . . .. - 3.11.2.1 The dose rate due to radioactive materials releaseu in gaseous 7 effluents from the site (see Figure 5.1-3) shall be limited to the - - ~-'
following: ,
.- c -
~.
.k . . . 72 a. For noble gases: .<500 mrem /yr to the total body and '
.f 3000 mrem /yr to the skin, and .,f .
3 '.' b. For all radiciodines and for all radioactive materials in parti-culate form and radionuclides (other than noble gases) with half lives greater than 8 days: 1 1500 mrem /yr to any organ. APPLICABILITY: At all times. .
~
. ACTION: ,
[ a.. With the dose rate (s) exceeding the above lim ts, 4-~":tely- decrease the release rate to within the abov limit (s)wM in owe leur . ~ h Io , fe qv;remmh of sfecific i'% 3.c 1 % 5.o. 5+ . lo m k ff ,y ! . <' SURVEILLANCE REQUIREMENTS wl.
! 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the abo',e limits in accordance with the methods and procedures of the ODCM.
4.11.2.1.4 The dose rate due to radioa'ctive materials, other than noble gases, in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis 1.rogram, specified in Table 4.11-2. .
- g ii , iUU WP
~ ~' ,- ';T'M-- 3/4 11-9
.g
- esD
.m .
. ], ';, .S .,,.7 -
.._ 3 , _ . _ . . . _ , _ . _ _ _ _ _
t' .. . .'.- * * :. . . , .
.; 5b,
- in
(-) TABLE 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Ng.. Minimum Sampling Analysis Minimum 55 Qseous Release Type Type of Detectable Frequency Frequency W-Activity Analysis Conc. (uCi/ml)a Waste Gas Decay P P f 5 Tank 6nszeus 55 Each Tank Each Tank Principal Gamma Emitters 1
- Grab Sampie 3 1 x 10'4
~~~-
==
H-3 1 x 10'* ~
=
._ ==
a-Containment Purge Grab Sample (P) P fo Each Gawa. ly N! for Each Purg Princimi Gaseous 3 Emitters 1 x l-0 4 g. Purged or H-3 1 x 10-o E3 or e W foT~ Cont. I-131** === ContinuousY Purge 1 x 10- F I-133%d h g for Contmuus 1 x 10" Purge
- -~~
_~ ~ Condenser Steam M'h'0 c Mb 'c. **Se= "5 Principal Gamma Emitters % E' I~~
- t. Air Ejector Grab Sample Yi 3 1 x 10-4 :.T45#
a H-3 1 x 10~ bN 1 Plant Vent Stack Me , b,( 7 gb Princica Grab Sample V H-3 mma Emitters 1 x 10-4 $3 1 x 10-6 Continuou/* WD I-131 Cha oal I l 1 x 10 11.?
, 9 I-133 1 x 10-'" I5YII=
Continuous 1e yU rw
%%btt. k [
Particulate Principal, Gamma Emitters 1 x 10.)) gig i Samo1e Continuous l* M ;D;E;;;;=
~
Composite Gross a Particulate 1 x 10'II ' h5 Vl Samole .=-T.= ContinousD Q 1 x 10 # Composite Sr-89. Sr-90 Particula te g Sampie =p
;=. = _
3 $ 1-u " ~" e } e L l0 $22 Af$$$ Ot!!) fefff ana,, wa a a-,,, a
.~ =~
(4 " ' ' (y w
.. - sh
. } l - . -. -- sy, og- -- - -- -
- W:F=+T4= 1 3/4 it-q b=MW-M-me g.s *'
-z.~.___. _
~
~
7g - TABLE 4.11-2 (Continued) if %~ . TABLE NOTATION Mkmm Rttahu.e anccatn% (n p c) i m >- a. The f ;is the smallest concentration of radioactive material in a F sample that will be detected with 95% probability with 5% probability E of falsely concluding that a blank observation represents a "real" . p signal. , . n.c 2.![ For a particular measurement ' system (which may include radiochemical separation): p - tie ^ b1 D c ., 4.66 sg ' ' * \n - , E V 2.22 Y exp(-Aat) . wnere -
~
Mpc :is theNiniumPded4/a fmmf*6 as defined above (as pCi per unit mass or volume) ' sh is the standard deviation of the background counting rate or of trie counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per transformation) 3 V is the sample size (in units of mass or volume) 2.22 is the number of transfonnation per minute per picocurie Y is the fractional radiochemical yield (when appifcable) A is the radioactive decay constant for the particular radionuclide at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples). The value of sb used in the calculation of the NDC for a detection system shall be based on the actual observed variance of the back-ground counting)rather (as appropriate rate or than of theon an counting unverified rate theoretically of the blank pre- samples dicted variance. In calculating the hrc for a radionuclide deter-mined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y and at shall be used in the calculation. The background count rate is calculated from the background counts that are detennined to be within + one FWHM . (Full-Width-Half-Maximum) energy band about the endgy of the gamma ray peak used for the quantitative analysis for that radionuclide.
"WR-STL i 3/4 11-10
~ s 11 .nde
, j
*~.Is.
^
.,l N.Q5 . x .i
- - _ - ___..- ~ . - - -_
TABLE 4.11-2 (Continued) 'r;.. TABLE NOTATION
~ A Q cv t h e. d w ; h S h. M up 3T D fres y m ;5comfe'b f lo 715/,
li-- b. a.' Analyses shall also be perfomed following shutdown, startup, fs g similar operational occurrence which could alter the mixture of radionuclides. ,,,. , , ~. r, g m ,,37,p,,,, h W
- .m
% c. 'ritier n _ r .s are :=..pu.shm 5; teca e ic;st m.& r. a :_.s.aw"f: ..ta y 37
.. .. n-t>
yhe,y geA. 0,,, ~Wy% * ' is 3G ti:7 .V.
./< Go}&e"f Samples snal Da V5"LGcnanged at'E5"ivem least once per 7 %
be completed within 48 hours after charging (or after removal from P'**n daysfand analyses a shall
- i- sampler). Sampling, and analyses shall also be perfomed at least i
". once per 24 hours for at least 7 days following each shutdown, startupfe 7157. or themal power level change exceeding 157. of RATED THERMAL P WER in P***" ~~ one hour. When samples collected for 24 hours are analyzed, he cor-responding tioc's may be increased by a factor of 10. .fv.,,, 215 % f**6- .? { 'I.--4hc'-itium grd :=plc: 2:11 Sc tica ;t icast on;;. pcr 7 da,s .cc.. vcntihti:n exhaust from thc spcat foei pcci ares. J-
- . e3 7: The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
f: o i
- jb. The principal gamma emitters for which the Mac! specification applies V '
exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate enissions. This list does not mean that only these nuc-lides are to be detected and reported. Other peaks which are measur-able and identifiable, together with the above nuclides, shall also
- be identified and reported. Nuclides which are below the Moc..for the analyses shall be reported as "less than" the nuclide's NDc!and shall not be reported as being present at the Npclevel for that nuclide.
The "less than" values shall not be uset in the required dose calcula-tions.
,- i 1 Thc ndic gas continuca monitor chai? bc calibr ted a:ing ?deratory analy m M +be 78 crp! :
. , a. d - en Tsic ". 11-2. @
""". STLi 3/4 11-11
%- C.dah wyopeb k " DES S **S 4
* , ~
j q I I ; i /
-"N**we.e e augw. .._,g.&,., .,_ _, _
-M -- -
v==-s.h - m '-"'em--d--
--F meannue w._ _ _ _ _ _ -u Nr-
y..
- . o e ..
,,.g,,,, s., . -
.- g ,, ..
. . ~ .
RADI0 ACTIVE EFFLUENTS
~ '
DOSE. NOBLE GASES ,. D '1 LIMITING CONDITION FOR OPERATION
.h.. . - -
W: - 3.11.2.2 The air dose due to noble gases released in gaseous effluents fran the site (see Figure shall be limited to the following: h-
.- row a ad ynctw e+ +ho sHe :~ .
g.75. 1
.,, a. During any cale ar quarter: f 5 mrad for gamma radiation and ..
f 10 mrad for beta radiation and, , -
- 7, q,: ' .b . ' ~During any calendar year: 110 mrad for gamma radiation and - - -
4a. ..
< 20 mrad for beta radiation. -
J.s A: 9 . .p . -
~
? - APPLICABILITY: At all times. NM ' . . _ . .
, ~ ,
'.- ACTION: -
f .-
- a. With the calculated air dose from radicactive noble gases in gase-aus effluents exceeding any of the above limits, in lieu of any
, other report required by Specification 6.9.1, prepare and submit C to the Commission within 30 days, pursuant to S a Special Report which identifies the cause(s) pecification for exceeding the 6.9.2, limit (s) and define the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the sub-sequent three calendar quarters so that the cumulative dose during these four calendar quarters is within 10 mrad for gamma radia-tion and 20 mrad for beta radiation. . .
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
~ '
SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations Cumulative dose contributions for the cur-rent calendar quarter and current calendar year shall be detennined in - accordance with the ODCM at least once every 31 days. .
,...,.st 3/4 11-12 -
3 n)
% /L "i .
* --e-- --+ .. . .
M *=6 g e e .ee egye - - >
~
.~.--- - -
. - . - - . . --- w & _s..., ..a. .__u_,___, ; ;
7--~..,---a- _ _ l [._"' 'T _.
- f. , '_ _ , ~. ~ ~ ' -
t _'e - -
~ '
. .' ., I ,#. ..~>-
'^A RADI0 ACTIVE EFFLUENTS DOSE,RADI0 IODINES,RADI0ACTIhEMATERIALINPARTICULATEFORM,AND P RADIONUCLIDES OTHER THAN N0BLE GASES
%. . . - ^l g '
LIMITING CONDITION FOR OPERATION
~~
A W . 3.11.2.3 "The dose to an individual from radiciodines and radioactive j'J'. materials in particulate fom, and radionuclides (other than noble gases) G with half-lives greater than 8 days in gaseous effluents released from !.7 the site (see Figure 5.1-3) hall be limited to the following:
. * - Yom .wel fea cfor St 4he SHR.
j@ih a. During any calendar quarter: f 7.5 mren to any organ and, i'q' - -. . , . py;, b. During any calendar year: f15mremtoanyorgan. . k... O. .Y. .r.
,. APPLICABILITY: At all times. ' -
3c ; . It' ACTIOh-- J ' .a, .
~
- a. With the calculated dose from the release of radiofodines, radio-active materials in particulate fom, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous o effluents exceeding any of the above limits, in lieu of any other L report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the
+ releases of radiofodines and radioactive materials in particulate fom, and radionuclides (other' than noble gases) with half-lives
.~ .
. greater than 8 days in gaseo~us effluents during the remainder of the current calendar quarter and during the subsequent three cal-endar quarters so that the cumulative dose or dose commitment to an individual from such releases during these four calendar quarters is within 15 mrem to any organ.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. .
SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be detemined in accordance with the ODCM at least once every 31 days.
!" :T" 1- 3/4 11-13 ,n),
l. ] l - i< 9
.;. -,.~..._f ..__%-...._. - . _ _ _ , . . . _ . -
~ ,
.,,..-,.-i .S'F ' f _. T_ -f. _.___
,p ., ,
*3 RADI0 ACTIVE EFFLUENTS s t
i y . . . GASEOUS RADWASTE TREATMENT y I. 9. 5 m l . . ...
-M LIMITING CONDITION FOR OPERATION
- , , -,o ,/
4ppgr. tc yorT.oo amc 3y
- g. 3.11.2.4 A%e gaseous radwaste treatment syst , and the ventilation exhaust t treatment s.ystem shall be OPERABLE. The appr priate partions of the gaseous
- .4 radwaste treatment system shall be used to r duce radioactive materials in
-;'; Alew. Q.,v e,, s _ 94~ doses due t air gaseous waste criar to their discharge when he projected gaseous effluent s effluent releases f om the site (see Figure 5.1-3) 'Jh[ s- - 1 when averaged over -2: ay: would. excctd 0.2 nd for gamma radiation and IE 9y4 mrad for beta radiation and the appropriate portions of the ventilation . - 1 2,5 gTxhaust treatment system shall be used to reduce radioactive materials in ; -'- gaseous waste prior to their discharge when the projected dues due to . gaseous effluent releases from the site (see Figure 5.1-3) when averaged ~ 39 o.vgr 1 d ?ye wquid exceed-G.# n. rem to any organ. ,,
- f. %eodewb eder. L g, g . .
~. APPLICABILITY: 'At all times.
~
ACTION: ,
~
. ':ith the g;cc a . assa . cm.icm. ., . ouu/u, cue <enu n ou un exh=:t tre:t==t y;t;- ingerdic for mor; tha 21 ij; or gj W *ith gaseous waste being discharged without treatment and in ex-cess of the above limits, in lieu of any other report required gl . by Specification 6.9.1, prepare and submit to the Commission ti within 30 days, prsuant to Specification 6.9.2, a Special Report, which includes the following infonnation:
- 1. Identification of the inoperable equipment of subsystems and the rtason for inoperability.
- 2. Action (s) taken to restore the inoperable equipment to
~
OPERABLE status.
- 3. Summary description of action (s) taken to prevent a re-currence.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
b e l l ,
; ' ![ ,-
1".."1 STS-1 3/4 11-14
) ,
=*Mou- ,yg. .-.A.,
N M, wge --e me - mmmp h- e e.me== e aso- .-e, "Q . 9 .m,
~
_ j ' * "} ^_ . ' ~ * ' l^ '.*
.>-...r.s~*~
.- ,2 . , - - . . _ , .,
y . bI SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected "ce per; }e{ag ,,in gc ance w m % e 0 ,,7,,,} e p },.. ,, , g , h 8-.. o, . A p .d-4.11.2.4.2 The gaseous radwaste treatment system and ventilation exhaust system shall be demonstrated OPERABLE by operating the lgaseous radwaste QQ treatment system equipment and ventilation exhaust treatment system equip-Ic ment fer :t le::t -f nute:, at least once per 92 days u ' :: th: appr: "'F prfct: :y te '.:: h::: utilf d t- - r
^ - '
-fil a rt-
+- dur * ~; t '. p :; fen: 92 d: . Pfe guadevi;y c::omda.Twe os e.
Ej . b c.. 4.. psews er ,.h
.veIe.s,s e; g~ 4,.d yr. Qr3 jf1N*r;::::
,,,,,,m r ;a.M'"0;;;i" con fi:l
.n9 **..
115J.svd(av..LIn.vs.hQio.8aVo.gq.mm.6 g org an h:.
.l l , ,
c ,, c ,.j3
- 9. . ,
+. . m V 1 . 1 P'n2-STS-b 3/4 11-15 m I
.n-- . . - . .
.g. ...
s; .,,
~'
,,p..
m,. .. . ~ .6 p: .
-6 ,- .
3 , . 4 RADI0 ACTIVE EFFLUENTS -
~1 ~
. DOSE w LIMITING NDITION FOR OPERATION I 50
. p .. ..c ,,
g , . , membaras-rw Fe3 3.11.2.5 The dose or dose commitment to any rcal indi.idal from uranium
~
fuel cycle sources shall be limited to < 25 mrem to the total body
- 1. or any organ (except the thyroid, which shall he }imited to <_75 mrem) over ' ^ -
9 causechve c4. %w gus,%
-~. .
y
.... APPLICABILITY: . At all times. - ..s.,. ; -
.; .- g . ~.nemb1 -qd.2 33- . ..l" ACTION: ,,.;,V . 4-L T ~. . ,
-t% e pobke 5.,,-
"5 ;. .
~
- a. With the calculated dose from the relea of radioactive
. ~ ~ materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3 11.1.2.a, 3.11 1.2.b, 3.11.2.2.a. ~ 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, in lieu of any other O
U-report required by Specification 6.9.1, p epare and submit - 'l ' a Special Report to the Commission pursuan t to Specificction 2-g**' g 6.9.2 and limit the subsequent releases re leases such that 50 the dose or dosa commitment to any real idfi.idel from uranium cole lo." el cycle sources is limited to < 25 mrem to the total body 9"E.w5 or a an (except thyroid, which is limited to < 75 mrem) over 12 cc.. ccaticc months. This Special Report sEall include
@ an ana4st 1 which demonstrates that radiation exposures to
#~any cc, irdi.ida:1- from uranium fuel cycle sources (including hd t c all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standa rd.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. .
SURVEILLANCE REQUIREMENTS 4.11.2.5 Dose Calculations Cunulative dose contributions from liquid - and gaseous effluents shall be determined in accordance with Specifi-cations 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the ODCM. n -. . { 13 f
]e{ ' ., < <D
-n";-ST5-l~
3/4 11-16 4 t .- . - _ _ _ _ . .- . - - -
. f*
c
/J RADIOACTIVE EFFLUENTS 9
EXPLOSIVE GAS MIXTURE
*e. LIMITING CONDITION FOR OPERATION 59:
c Ei 3.11.2.6 The concentration of holdup system shall be limited to < 2% by volume. oxygen in the waste gas
- e. -
- 's .
MJ
- v. - APPLICABILITY: At all times.
@d. ACTION: u _ v . . 17:. a. With the concentration of oxygen in the waste . {: : gas holdup system > P.5 by volume b.t 11". b7 .-h n , restore the concentration of oxygen to (2% W///fi,. !
~59 7 48 hours. . ..
'5. . concentration of - e waste ' -= - gas holdup sy *
. vo - .. iately cuspend all
. additions of o educt. tiie concentra-
~. : .. ' oxygen to 1 2% within en- - . 12 -er The provisions of Specification 3.0.3 and 34.4 are not applicable. SURVEILLANCE REQUIREMENTS v 4.11.2.6 The concentration of . oxygen in the waste gas holdup system shall be detemined to be within the Gove itinit by continuously monitoring the waste gases in the racedinse direkvgi with the hydrogen and/or oxygen monitors required DPEMBLE by Table 3.3-13 of Specification 3.3.3.10.
.o7l I
. .e 9
M % s i". ."', ST =1 3/4 11-18 ~, 4 a _-- -.. . -
- - ^
;. :, - ,.~..'s'=
- _ _ _ v. - .
RADIOACTIVE EFFLUENTS .c . ' GAS STORAGE TANXS
- LIMITING CONDITION FOR OPERATION -
61aSt t-gy; 3.11.2.7 The quantity of radioactivity contained in each gas 3 storage g5 tank shall be limited to ,<7orcocuries noble gases (considered as Xe-133). s3. . . . .: . At all times.-
' ~
n.. APPLICABILITY:
^
fh.4 ACTION: . . $y ,
. . .. ~,.
_. Wasts gi '
- a. With the quantity of radioactive material in anyagas storage
/
'3:. tank exceeding the above limit, immediately suspend all addf-
- y? tions of radioactive material to the tank and within 48 hours -
U reduce the tank contents to within the limit. .c
. b. The provisions of Specifications 3.0.3 and 3.0.4 are not
. . , applicable. . SURVEILLANCE REQUIREMENTS 71 gaSg 4.11.2.fr The quantity of radioactive material contained in each 3gas storage ' tank shall be detemined to be within the above limit at least on e per yy when radioactive materials are being added to the wl hh WWb] i 5 less b 50,088 Cur!'5d6000*0"5'5-
+.o.s.T.x & p .kb 4 rd;~ 6 ~ W J c 4:~ h -
. d e. sb (@
A Le L LAkueLil imabe Jdev-: A h be-e~ ~ d dd b b bkad
~ Jo-ae.e. mMk Meig evv-:n & A 3 **
% k ;. A .3 ex ccc h u . coo e1 e
- l l , . U 4
e
- e F L ST5:T 3/4 11-19 3
-N'- 8N.6 ,,,
- a. : . = - a -. a . -c. --
..w'~i'
- w. .. ._...
..c
'.I -3 ..'
~' ' '
NW-.*.'"*-
- v- . . y _ _ 2 . ~....- _
- u. . ; - c.* v . v '.~.i. , u- ~. .
.i;
( a >
. a , .r.: * .
,Jy
- RADIOACTIVE EFFLUENTS ~
& 4 3/4.11.3 SOLID RADI0 ACTIVE WASTE S** % ~ M U "
.( LIMITING CONDITION FOR OPERATION ~ '
$gw ~W ~ 3.11.3.1. The solid radwaste system shall be OPERABLE and used, applic-
-- able in accordance with a PROCESS CONTROL PROGRAM, for the SOLI FICATION
$f and packaging of radioactive wastes to ensure meeting the req rements of - Fsi. 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of ra oactive D,?. wastes from the site. .. -c. . .
- h. APPLICABILITY: At "all times. if : ,'.. '. . . rv : -
g . ...; j. .
. . ,e - .
f' ACTION: "
~ '
.- v - ~-
Q - - F ~. a With the packaging requirements of 10 C Part 20 and/or 10 CFR et Part 71 not satisfied, suspend shipmen of defectively packaged
, solid radioactive wastes from the si .
3 , . . .
- b. With the solid radwaste system in erable for more than 31 days, in lieu of any other report requ ed by Specification 6.9.1, prepare and submit to the Commi sion within 30 days, pursuant to Specification 6.9.2, a Spe al Report which includes the following infomation: -
- 1. Identification of th inoperable equipment of subsystems and the reasons forf noperability.
2. Action (s)taken restore the inoperable equipment to OPERABLE statu-
- 3. A descripti of alternative used for SOLIDIFICATION and packaging wastes.
4.. Summary escriptionofacIfon(s)takentopreventare-curre e.
- c. The pr isions of Specifications 3.0.3 and 3.0.4 are not app 11 ble. -
SURVEILLAC REQUIREMENTS 4.11.3. 1 The solid radwaste system shall be demonstrated OPERABLE at - least nce per 92 days by: - 1 00
-STS-1 3/4 11-20 11 - ' '/
/
-i q
. - - - - - . . ~ = .-
.d
ii n -
.y ,
, ..... .. . ~-
Md 11 1 SURVEILLANCE REQUIREMENT 5 (Continued) 5
- a. Perfomance of functional tests of the equipment and compo nts of the solid radwaste systen,
- b. Operating the solid radwaste <ystem at least once in t pre-k.
Qn vious 92 days in accordance with the PROCESS CONTROL P OGRAN,
. or . . _ ,. . ,
ti 67 c. Verification of the e.istence of a valid contract or SOLIDIFI- - C CATION to be perfomed by a contractor in accord ce with a .i . PROCESS CONTROL PROGRAM. , yr. 7, 4.11.3.1.2 The PROCESS CONTROL PROGRAM shall be used verify the SOLI- ,. 6/ ' DIFICATION of at least one reprcsentative test specim n from at least every - tenth batch of each type of wet radioactive waste ( g., filter sludges, -
. spent resins, evaporator bottoms, boric acid solut ns, and sodium sulfate solutions).
L a. If any test specimen fails to verify OLIDIFICATION, the SOLI-
~~'
DIFICATION of the batch under test all be suspended until such time as additional test speci. ens can be obtained, al-ternative SOLIDIFICATON paramete can be detennined in accordance with the PROCESS CON OL PROGRAM, and a sub_ sequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the al rnative SOLIDIFICATION parameters detemined by the PROCESS C iTROL PROGRAM. [j b. If the initial test spec .en frem a batch of waste fails to verify SOLIDIFICATION, e PROCESS CONTROL PROGRAM shall pro-vide for the collecti and testing of representative test specimens from each nsecutive batch of the sr a type of wet waste until at east 3 consecutive initial test specimens demonstrate SOLID ICATION. The PROCESS CONTROL PROGRAM shall be modified as r quired, as pr_ovided in Specification 6.14, to
?-
, assure SOLIDIFI ATION of subsequent batches of waste.
\
l I . LUU' e PhR-S -1 3/4 11-21 a
~
.T.~. . , - - . . -...--. ~..:---...
, - . .- n -- . , ,
'.*-~. 2 - -
VV . * :. '
~~
.' 5 ,f,,:,- . .. ::. , -
f , INSTRUMENTATION BASES - i ~~ *:f
- s.
~
l 3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION -J , w 7... 7
- The radioactive liquid effluent instrumentation is provided to "
'[- ~ . menitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alam/ trip .@' setpoints for these instruments shall be calculated in ;x;; tax ,,ith
~
L .- reche '- th: Off itc Oc;; Ociculatica M ueel (00CM) to ensure that b-
. the alam/ trip will occur prior to exceeding the limits of 10 CFR Part 20. - ,i The OPERABILITY and use of this instrumentation is consistent with the -
'g' requirements of General Design Criteria 60, 63 and 64 of Appendix A to - " ' *
?
% 10 CFR Part 50. < z. --r. , , " - r ih .' 3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION ' - -
.: ,, , . r
[T. .,
~ " The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials g.
f in gaseous effluents during actual or potential releases. The alam/triq -_' ~ ' setpoints for these instruments shall be calculated in accordance with pd ~ procedures '- th: Off:it: 00:: 0:1;uiati x M = ni (00CM) to ensure that the alam/ trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and control-ing) the concentrations of potentially explosive gas mixtures in the waste
^
gas holdup system. The OPERABILITY and use of this instrumentation is con-sistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
~
e 1j'a ?R} l s 'J
- p. .
,.y , ,
' . g I"i"' STS 1 8 3/4 3-4 .
t n _ _ _ _ . .___..a.._._..__...,.__ ._ *
...Ae -
'- NA-r N _" ' ' *
} .
~ -. .~ ' '
' f'[" '
3/4.11, RADIOACTIVE EFFLUENTS ~. s . 1, - -
.l f i d BASES l
t--m-I- 3/4.11.1 LIQUIDEFFLUENTS$...I. i t- --
. . ..g. e , ;
- . . . , . . ~ ..
.v 3/4.11.1.1 -
* ' ~
y
~. ,..,,.~..:.. CONCENTRATION
._ ..s ... .. .?.T:c,:?..^ "h.9 . -
'~L' W This' specification is provided to ensure that the concentration of E radioactive materials released in liquid waste effluents from the site to _.
unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides %g additional assurance that the levels of radioactive materials in borites of 7,5 water outside the site will result in exposures within (1) the Section II.'A . .., 3 design objectives of Appendix I,10 CFR Part 50, to an individual and (2) , % the limits of 10 CFR Part 20.105(e) to the population. The concentration
-: limit for dissolved or entrained noble gases is based upon the assumption
- that Xe-135 is the controlling radioisotope and its MPC in air (submersion)
(; was converted to an equivalent . concentration in water using the methods
~'
described in International Commission on Radiological Protection (ICRP) Publication 2. ", ,,
,...4- .
3/4.11.1.2 DOSE . . ~ .
'%* -+... ,. .
* ~
~
This specification is provided to imp 1 ment the requirments of Sections II. A, III. A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation impiments the guides set forth in Section II. A of Appendix I. The ACTION statements provide the required operating flexi-bility and at the same time implement the guides set forth in Section IV.A '.' of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculations in the ODCM implement the requi rments in
. Section III. A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in .
~
the ODCM for calculating the doses due to the actual release rates of - radioactive materials in liquid effluents are consistent with the methodo- . logy provided in Regulatory Guide 1.109, "Calculat# 'n of Annual Doses to ' Pan from Routine Releases of Reactor Effluents for 'he Purpose of Evaluating .
. Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from
; Accidental and Routine Reactor Releases for the Purpose of Impimenting Appendix I," April 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.
~
FWR-STS-1 B 3/4 11-1 - 11 : 202 N N gg . 66 em 66 g M 6 . -* 9 5 e6- D emen e - eh e- .- p *
- gm- en .%e .wb*." W %W *-e.- .me 6 ,.agse.> q
- x. __~
.,n -
.. m. .c.e w. . y a . . .;:.m. s. -
,(.J.0 . RADIOACTIVE EFFLUEf6S - ~ % 1 ,
^
3 BASES' n~. .:. : .
. , %. , .. m . . . s. . j. . . ,,.. .. e _
-/-..
' :cThis spec.ification applies to the release of liquid effluents fran ~. -
fS ,
,L",, each reactor at the site. -
/ .....
c.. .. . . . , ..: -
'j8if ,. -
.:w.: . . w :- .- . r. ..p :p s..w s:dhin. .-- - .
$iS 3/4.11.1.3 LIOUID WASTE TREATPENT ' f-S .-;P' -- ' ^ AmL -
- y. .
. _. . , . . . m ,,. . . . -
*L The OPERABILITY of the liquid radwaste treatment s.ystem ensures tha e. "
a:d this systen will be availsle for use whenever liquid effluents require [H gp treatment prior to release to the environment. The requirenents that the appropriate portions of this system be used when specified provide "
-?
M/i J ance that the releases of radioactive materials in liquid effluents will - -
",. be kept "as low as is reason 61y achievable." This specification imple-ments the requirenents of 10 CFR Part 50.36a, General Design Criterion 60 of /ppendix I to.10 CFR Part 50 and design objective and in Section II.D of ... Appendix A to 10 CFR Part 50. The specified 1imits governing the use of f.t' .
appropriate portions of the liquid radwaste treatment system were speci-fled as a suitable fraction of the dose design objectives set forth in - -
.f -
Section II. A of Appendix I,10 CFR Part 50, for liquid effluents. i , 3/4.11.1.4 i.iOUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the
- , ^
specified tanks provides assurance that in the event of an uncontrolled m release of the tanks' contents, the resulting concentrations would be
., less than the limits of 10 CFR Part 20, /ppendix B, Table II, Column 2, at the nesrest potable water supply and the nearest surface water supply in an unrestricted area.
3/4,,11.2 GASEOUS EFFLUEf6S
+.
'h '
3/4.11.2.1 DP SE RATE . This specification is provided to ensure that the dose rate at any time at the site boundary from gaseous effluents from all units on the site
- -i . will be within the annual dose limits of 10 CFR Part 20 for unrestricted '
areas . The annual dose limits are the doses associated with the concentra- -
; tions of 10 CFP. Part 20, Appendix 8, Table II, Column 2. These limits provide
.. reasonble assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted
; area, either within or outside the site boundary, to annual average concen-trations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)(1)). For individuals who may at times be within the site boundary, the occupancy of the individual will be
, sufficiently low to compensate for any increase in the atmospheric 1
8-3/4 11-2 PWR-ST S-1 an7
,4 11.-
l1 s- \J] ,_d _. I
- __._..i.: .:p,.c Q -i ___ ..... _..._ . .. .
.-_....; 4.c. __ . -. .. .,-e , Q
* . ;2.5;:.d.- %; y; . *
. - . .. , , . > ?- g . :.: . . . 7 . '. .' . - . ~. + f,. .
v ~._.x.s p. = - - _._ x . .- .=-=: -
' . , I. j,' ; [-
. . , . M Q. .q .,< . (.. .
RADIOACTIVE EFFl.UENTS
' ~ '
SES
'*- -m-
. ~ , ..
. . difftsion factor'above that fo'r the site boundary. The specified release m .. rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an _ individual at or beyond the site boundary
)Q;r.' ' to < 500 mrm/ year to the total body or to < 3,000 mren/ year to the skin. U
-- ~
These release rate limits also restrict, at all times,'tha corresponding g thyroid dose rate above background to an infant via the cow-milk-infant ,, m . pathway to < 1500 mren/ year for the nearest cow to the plant. -~:
.. . . ? Ws- Q . = '.*O;,~.; e 2. k- '. u ' ..' * ' = '
t..z s. T .- This specification applies to the release of gaseous effluents fran . . - T all reactors at the site. -- h.v . ?. . . . . h 3/4.11.2.2 DO SE, NO BLE GASES ,,
~
g., _, J.' This' specification 'is provided to implement.the requirements' of ll ' Sections II.8, III. A and IV. A of Appendix ~I,10 CFR Part 50. The Limiting - Condition for Operation implenents the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of gpendix I assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveil-lance Requirements implement the requirenents in Section III. A of Appendix I that conform with the guides of Appendix I to be shown by calculational
- procedures based on models and de t euch that the actual exposure of an individual through the appropriate pathwa)s is unlikely to be stbstantially underes timated. The dose calculations established in the ODCM for calcu-
.' lating the doses due to the actual release rates of radioactive noble gases ~'
in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine
. Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide -
1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," . Revision 1, July 1977. The ODCM equations provided for detennining the air doses at the site boundary are based upon the historical average atmos- ' pheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. 3/4.11.2.3 DOSE, RADIO 10 DINES, RADIOACTIVE MATERI AL IN PARTICULATE FDRM . AND RADIONUCLIDES OTHER THAN NOBLE GASES . This specification is provided to implement the requirenents of Sections II.C, III. A and IV. A of Appendix I,10 CFR Part 50. The Limiting
]]
~
PWR-ST S-1 8-3/4 11-3 ', [] 4 .) 5,-..k.7-.. .. .- ,..*'.a-A
. v - .. .s.- .
.w, ----_g- . --
**[,, -- -
es - - -
. w; . .. p,g _ _2; .)pg . .
., ;m. . - z..y.. . .g. . . . .. _ y. . ,
1 - RADI0 ACTIVE EFFLUENTS v - - -
....".-c.-.
; BASES .
, . t .
~"M. : Conditions for Operation are the guides set.forth in Section II.C of .
- - - Appendix I. The ACTION statements provide the required operating flexi--
~
'y bility and at the same time implement the guides set forth in Section i , IV.A of Appendix I to assure that th'e releases of radioactive materials ~'
in gaseous effluents will be kept "as low as is reasonably achievable." -
.. The ODCM calculational methods specified in the surveillance requirments y' imp 1 ment the requirments in Section III.A of Appendix I that confom-
.AL ance with the guides of Appendix I be shown by calculational procedures - based on models and data such that the actual exposure of an individual - @ through appropriate pathways is unlikely to be substantii ally underestimated. , The.0DCM calculational methods for calculating the doses due to the actual 9' l .. release rates of the subfect materials are required to be consistent with - m the methodology provided in Regulatory Guide 1.109, " Calculating of Annual ~- @ Doses to Man from Routine Releases of Reactor Effluents for the Purpose of p;; Evaluating Compliance with 10 CFR Part 50, fppendix I," Revision I, October - .-'-a 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Trans-
.j. port and Dispersion of Gaseous Effluents in Routine Releases from Light-i Water-Cooled Reactors," Revision 1., July 1977. These equations also pro-f> vide for detemining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radiotodines, radioactive material in particulate fom and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,
- 2) deposition of radionuclides onto green leafy vegetation with subsequent
.' censumption by man, 3) deposition onto grassy areas where milk animals and .C meat producing animals graze with consumption of the milk and meat by man, i and 4) deposition on the ground with subsequent exposure of man.
3/4.11.2.4 MPypbinhe s ob - GASEOUS wyc ytesWASTE s TREATMENT @o e. The OPERABILITY of theAgaseous radwaste treatment system and the ventilation exhaust treatment systems ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the enviroment. The requirenent that the appropriate portions of these systems be used when specified provides reasonable assurance that ~
.Z the releases of radioactive materials in gaseous effluents will be kept
- "as low as is reasonably achievable." This specification implements the .
A requirments of 10 CFR Part 50.36a, General Design Criterion 60 of Appen-dix A to 10 CFR Part 50, and design objective Section IID of Appendix I to 10 CFR Part 50 The specified limits governing the use of appropriate portions of tt systems were specified as a suitable fraction of the dose design objecti.es set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents. , L.64 8 3/4 11-4 33
, ., n c II -
yJ' s.
.- W X .. . ,_, J T W - -
- o .. .. . . . .
,f - .~ *..g-.::;% . , ,. :< l ..
. . . . _. , _ _L _ _ _
3 y;y. g.],g:.m.
, , c, . . . . d F. ,. m -l.;.J .~.'j s.,; f- yT.T.. ,
m.; .- . ' . 6c. . . : .- RADI0 ACTIVE EFFLUENTS . I # 4 , , , , ,,, , m eid ere b e f { .'\
- b ' "
8ASES
~
d ' t
.e., . .,
, ,. m .- .
. c.w :- . . - .
3/4.11.2.5 DOSE h,::. .
- v. &,,. ..% ."; - - *^. ,
n ....,:, 6 : . YWOV. ..... ? ...q.g. 4 .v,.. .
~-: .' ., ,-; -
+ -
This specification is provided to meet the dose limitations o R R y. 190. The Specification requires the preparation a Report whenever the calculated doses fr . radioactive effluent xceed of a tal
!~. twice the design objective doses pendix 1. For sites containt up to ,
4 reactors, it is highly u y that the resultant dose to a r=1 f..di.L G dee-1 will exceed 40 CF 0 if the individual reactors renain wit n the - ' & reporting requir . l evel . The Special Report will ' describe a curse of - .,
$" action which sh d in the limitation of dose to a re! i .d!"!de! ?? forMconsec i ve gs . r. . . . ., o within the 40 CFR 190 limits. For the purposes M of the Spect Report, it may be assumed that the dose commitment to the d i d! !z! from other urantun fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facili-j.F ite N 50 1es)a ;
dt el;s sameMa . '.oledthin. #,, ,r. a4adf,f .tb-usp of s5mnnst be consideIr g i lwa y qg {;.Me.f'* s 3/4.11.2.6 EXPLOSIVE GAS MIXTURE 3 ;,{*( " [*[@, f,* This specification is provided to ensure that the concentration of ' potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the f1ammability 1imits of oxygen. (Automatic control feature is ' included in the system to prevent the hy-drogen and oxygen e ...-entrations from reaching these flammability limits.
a The automatic con. rol feature includesisolation of the source of oxygen .
to reduce the concentration below the flammability limits.) . Main-taining the concentration of oxygen below the fl ammability limits provides assurance that the releases of radioactive materials will be controlled in confonnance with the requirements of General Design - Criterion 60 of Appendix A to 10 CFR Part 50. 3/4.11.2.7 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the . tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 ren. This is consistent ' with Standanf Review Plan 15.7.1, " Waste Gas System Failure." n 9 .c PWR-STS-1 B 3/4 11 :5 11 i i ._ U u
~j u . ,
s
- W= amp eme. . +.e emw- ,..-ame.
, Ewe *.. ee mes==.e+-- %. .e -e .e 4-.. - . .,
.e e S . .
. . m ,. :. . , , ~*
- a.. ..
.WYf. n .-.. .,
. ., ,.; ,. ,~ :. . . . -
- y. . ..
hADI0AC',IVE EFF1.UENTS '
~
Y .
- b,i l BASES
.- g , . .
= . .
,. y,:. . . . . .
~ ~ ' '
3/4.11.3 SOLID RADIOACTIVE WASTE > 7 ..*. . . ,
- s. - . ..... . . , . e .. . .. n v. ... . . ...-. -
The OPERABILITY of"the solid radwaste system ensures that the system T.E El will be available for use whenever solid radwastes require processing and
"' packaging prior to being shipped offsite. This specification implements the requirenents of 10 CFR Part 50.36a and General Design Critaria 60 of M Appendix A to 10 CFR Part 50. The process parameters used in establish-TE
~
ing the PROCESS CONTROL PROGRAM may include, but are not limited to waste . h~ type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.- -
* > E ;-
-c-U. n .
. u. ,,.
.h, .,;.., ., **'~- . f)*h ,- .
' ' .j.1-e o p */
i.; / . n1
- l ,
"L? s
- 3. .
O . , I
.m . .
h.
. M b
- e. .
.t
^s ^ -
- ~ '
,i:i .
*t* - ,
~
.I -
'I I"n'R-STS L B 3/4 11-6
~
.t_.---.... -- _
. .. . . _ _ _ . _ . _ ..,. _ .._.2...__ -
* '=aL i. ;Y.,1w. .
, w...4..
+ .e
. 4's ' *r i . .. s. _ . s= .. ;- **' - -
*:...?.=... . . . .. . : ..~.._...- .
. ~
. . . . , ..,-.s , - . . . . . . . , . . -
^ * . ..g .. .. "*'.* .... '; r
. . , , . . > . s ~ .' . , . ~-..
. . 6 s ..
.. '.:.: .a.g;~ s
. mer;,. ~~ .s.,'--
.a....
'.a".;;
fr.d. . 99.* : . . se. f *
.. . . ,: - ~~.
9 s,.1 . . ,:.. i : >- ' t. .: . y- 2_ =::.ac..Q s r .. . . Qs
.~.'...'"..'.'..s..
;.L.p z ep.;.xe,
, . _ _' ., , - p
. 9.,.
/.. : . , .. . . . ;.. , . . , .
. . . . . _ . ,..a... ...,:, m. ..
. a. . . . ...
.. .. . . . .y . ...~.....
.s .
.n .. w.. . . :. . ;. . . .
~ - . . . . . - .., . .
c....... y .y ,;.:. % .,. - .
...... a. .: ,w:.
- . .. : . . . .:.:s.- M. . -r
. . , . ~.> w....::. A.. -> .. .,,:: c .. ; :. w.,e,.. x;c.. r .- . <,..._..; . ;.: n ; y y :: ,., , . g . .: .. .
- .s
^. . - .
.,s; .,. ..~.v . . , . w. m .. . . . .
- 2. c.
.s. , ...p. - a. .-2. . .c. .. :r.a.a., .v. ,s.
n ~ ". ^; :-
. u:".5.
. m... .. :. y..
. . .. ?.v. .
w ::,
...:... m. ..,s.:
.m .,. .s..
. +p
,w. -:. . g- s --
.-z.
.. w. .......v.. ..,,.s......,.+ .. ..
.e. . . a . . . : , r; . ~. . .. . .
c, . . . . - . . . .. . n
. . . .e . .,,i....,. .........
.w ..... .. e-_G. ..a.; J . -: - g . -?
. . .. y ... . .,. ~t~... .m.. 59.
- j. ...-:=- . ;. .. . .
. .....: ...;..3z,==.v... .y.a,.... .sw.r.s... e,-.
- s. . ..
m.~ yn. .
- 2. . -
. . . < . .. . . ...~ ....,g....
. . .4 .
, ~. .
^#
.. . f .;n . . - * . .
. .~ s
* *. - a-1
?,*M ,, *- T. J ~ w
.&,, . . . . . . .L'_ * .fC**'".L*G.*.*V':* ~ . . ' . ..',..'s M,
. . .f. . . . . . *' . . r. * .
.t. .s.. 2 .,..-
... .; *. '. ) s'i, ,, -',.>.W
. ~. . 1
* .. q r.. , .
*4 *n o'.*
~
. . -a -. . - .,n. .- -
IL;R.- u
- gs .. , -
. . ..v ...,- - ..--
. . ..s... .. . - .. %,g,,,., . . . *. . . .r. .. . ..s,- ,, ,
. . .. . . . .....i...
c STANDARD . ' ' - . - r.- .- . '
- 4. .
. TECHNICAL SPECIFICATIONS . .- g,
" ' rx SECTION 6.0 Nf a v us ADMINISTRATIVE CONTROLS sP
. y . gsv N.' g '\ V
,no .. .
, , i e>
'... 6-. - .
.2 I.
.v . . s
. I
. s. . - .. . . .. . ..
ADMINISTRATIVE CONTROLS
- j. The plant Security Plan.
- k. The Emergency Plan. -
- 1. Facility operations to detect potential nuclear se.fety hazards.
- m. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Nuclear g Operations Review Board. .
AUTHORITY 6.5.1.7 The PORC shall:
- a. Recommend to the Plant Manager written approval or disapproval of items considered under 6.5.1.6(a) through (e) and(j)and(k)above.
- b. Render determinations in writing with re each item considered under 6.5.1.6(a), c) (gard and to (d)whether sbove or not constitutes an unreviewed safety question.
- c. Make recommendatior.3 to the Plant "anager in writing that actions reviewed under 6.5.1.6(b) obove did not constitute an unreviewed safety question.
RECORDS 6.5.1.8 The PORC shill maintain written minutes of each meeting and copies shall be provided to the Vice President-Power Supply and Chairman of the Nuclear Operations Review Board. 6.5.2 NUCLEAR OPERATIONS REVIEW BOARD NORB FUNCTION 6.5.2.1 The NORB shall function to provide independent review and audit of designated activities in the areas of:
- a. Nuclear power plant operations
- b. Nuclear engineering <-
pq
- c. Chemistry and radiochemistry FARLEY - UNIT 1 6-7
'F
z1 s a f5 ')$ cy .
' ' yj
( q;/ 7 s q(k Nh ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 The following audits shall be conducted under the direction of APCO's Manager - Cperations Quality Assurance:
- a. The conformance of facility operatien to provisions contained within the Technical Scecificatiens and applicable license conditions at least once per 12 months.
- b. The performance, training and qualifications of the entire facility staff at least once per 12 months.
- c. The results of actions taken to correct deficiencies occurring in facility equi; ment, structures, systems or metnod of coera-tion that affect nuclear safety at least cnce per 6 months.
- d. The performance of activities recuired by the operational Quality Assurance Program to meet the criteria of Aopendix "B", 10 CFR 50, at least once per 24 months.
- e. The Facility Emergency Plan at least once per 24 months.
- f. The Facility Security Plan at least once per 24 months.
- g. Any other area of facility operation considered approcriate by the NORB or the Senior Vice President.
- h. The Facility Fire Protection Program and imolementing croce-dures at least once per 20 months.
- 1. An indeoendent fire protection and loss crevention crogram inspection and audit shall be cerfermed at least cnce per 12 months utilizing either cualified offsite licensee personnel or an outside fire protection firm.
J. An inspection and audit of the fire protection and loss preven-tion orogram shall be performed by a cualified outside fire consultant at least once per 26 menths.
- k. At eacn scheduled NORB meeting the v anager - Oceratiens Quality Assurance shall .ake a su:rcary reocrt of nese activities. i
~~*
o.N t, m R n AUTHORIri 5.5.2.9 The NORS snall recort to and advise the Senior Vice cresident on these areas of resocnsibility specified in Sections 5.5.2.7 anc 6.5.2.5. RECRCS 11
~
,q l I -
.iu 6.5.2.10 Records of NORS activi-ies shall be precared, accroved and distributed as indicated belcw:
FARLEY - UNIT 1 6-10 Ame: dmer.t No.4
ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION
- 6. 7 .1 The following actions shall be taken in the event a Safety Limit is violated:
- a. The facility shall be placed in at least HOT STANDBY within .
one hour. - -
- b. The Safety Limit violation shall be reported to the Commission, the Manager of Nuclear Generation and to the Senior Vice President within 24 hours. .
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the FORC. This report shall describe (1) applicable circumstances preceding the violation (2) effects of the violation upon facility components, systems s or structures, and (3) corrective action taken to prevent recurrence.
- d. The Safety Limit Violation Report shall be submitted to the Commission, the FORB and the Manager of Nuclear Generator within 14 days of the violation.
6.8 FROCEDURES
- 6. C .1 Written procedures shall be established, implemented and main-tained covering the activities referenced below: -
- a. The applicable procedures recommended in t.ppendix "A" of Regulatory Guide 1.33, Novenber,1972.
- b. Refueling operations.
- c. Surveillcnce and test activities of safety related equipment.
- d. Security Plan implementation,
- e. Emergency Plan implementation,
- f. Fire Protection Program implementation. l j ,
3,h 4 I 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, including temporary changes shall be reviewed prior to implementation as set forth in 6.5 above.
-4 i;,- i ;!
1 I FARLEY - UNIT 1 6-13 Amendment No. 5
- 1
!bM Cu t*tWI $y Aft ADMI!!ISTRATIVE CONTROLS -
6.9.1.5 Reports required on an annual basis shall include: .
- a. A tabulation of the number of station, utility _ and other personnel (including contractors) receiving exposures greater . _
than 100 mrem /yr and their' associate man rem exposure accordirg to work and job functions,gj e.g., reactor operations and surveillance, inservice inspection, routine maintenance, . special maintenance (describe mainti:..:nce), waste processing, and refuelirg. The dose assignment to various duty functions may be estin:ates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20*;In of the the individual total dose need not be accounted for. aggregate, at least 80". of the total whole body dose received fromexternalsourcesshallbeassignedtospecificmajorwor} functions. Inse d d N p 0* *#*' N Y MONTHLY OPERATIttG REPORT
/. 9./ 7 to 6.9.1.# Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management l
- s. Information and Program Control, U.S. fluclear Regulatory Connission, ,
I( Washington, D.C. 20555, with a copy to the Regional Office, to arrive - no later than the 15th of each month following the calendar month covered l by the report. InserYn*Q ~l> (,,q , f, / g REPORTABLE OCCURRENCES 6.9.1. The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures 'co prevent recurrence, shall be reported to the_.NRC. Supplemental reports may be required to
~
fully describe final resolution of occurrence. In case of co.rrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date. Pt0MPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1. The types of events listed below shall be reported within 24 hours by telephone and confirmed by telegraph, mail , ram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup rer within two weeks. The written followup report form. Information provided en the licensee event report form shall be supple-mented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event. UThis ta. .ation supplements the requirements of f 20.407 of 10 CFR Part 20.
,.9 l1 _rc 4
6-15 ~7 AmendmenDo.5 h FARLEY - UNIT 1 l
ADMIf11STRATIVE C0llTROLS
- i. Perfomance of structures, systems, or components, that requires
' remedial action or corrective measures to prevent operation f a , a manner less conservative than , assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically ~ considered in the safety analysis report or technical specifica-tions that require remedial action or corrective measures to prevent the existence or development of an u afe condition. . og ,4 g- . ap THIRTY DAY WRITTEtt REPORTS tV 6.9.1./ The types of events listed belcw shall be the subject of written reports to the Director of the Regional Office within thrity days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Infomation provided1 on the licensee event repor*. fom shall be supplemented, as needed, by additional narrative material to provide complete explanation of the cir-cumstances surrounding the event.
- 1. Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established bylhe technical specifications but which do not .
prevent the fulfillment of the functional requirements of affected systems.
- b. Conditions leading to operation in a degraded mode pemi cted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
- c. Observed inadequacies in the implenentation of administrative or procedural controls which threaten to cause redut'.icn of degree of redundancy provided in reactor protection systems or .
engineered safety feature systens.
- d. Abnormal degradation of systems other than those specified in 6.9.1.8.c above designed to contain radioactive material result-ing from the fission process.
p SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification: a
;l '- -
~
- a. ECCS Actuation, Specifications 3.5.2 and 3.5.3
- b. Inoperable Seismic Monitoring Instrumentation, Specification
[- 3.3.3.3. c, Inoperable Meteorological Monitoring Instrumentation, Specifi-cation 3.3.3.4. FARLEY - UtlIT 1 6-17 Amendment flo. 5 l
ADMINISTRATIVE CONTROLS d
- g. Records of gaseous and liquid radioactive material released to the environs.
O Records of transient or operational cycles for those facility f. components identified in Table 5.7-1. E.g Records of reactor tests and experiments. g W. Records of training and qualification for current members of the plant staff. h /. Records of in-service inspections performed pursuant to these Technical Specifications. if. Records of Quality Assuran:e activities required by the QA Manual.
) y. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k /. Records of meetings of the PORC and the NORB. I pr. Records of secondary water sampling and water quality. 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or "alam signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
. a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
ll'] Sl4 Health Physics personnel or personnel escorted by health physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas. 6-19 Amendment No. 5, 8 EARLY - UNIT 1
, i .
ADMINISTRATIVE CONTROLS
- b. A radiation monitoring deytce which continuously integrates the radiation dose rate in the area and alarms when a preset p
~~~~
integrated dose is. received. Entrycinto such areas with :this monitoring device may be nede af ter the dose rate level in the area has been established and personnel have been made knowl-edgeable of them.
- c. An individual qualtfted in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radf a-tion Work Permit. --
6.12.2 The requirements of 6.12.1, above, shall also, apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shtf t Foreman on duty and/or the Chenistry and Health Phystes Supervisor. Add 4. G k (.14
)
j;,- , . - I1 s _' D FARLEY - UNIT 1 6 Amendment No. 5
)
9
, , ' . . J' _
' . ** Q~'k;r..h ';, . ' .' - ~
~
a ADMINISTRATIVE CONTROLS mmom penenN]5\0 - o k 6.5.1 Pt. ANT OPERATIONS REVIEW COMMITTEE f WJuuueuu uu t (PORC)gyu)g
- ----o - -
~~ RESPONSIBILITIES -
- - -3
;. t. ~-*~ . , .^.' . . - -.. w .* .' - ...
.~
6.5.1.6 The'P4C shall rem.: - .x
~'..2
. 3. p - - , . r.,. 33.. . w ,. g.. . , , ,,, .
. h. Eac.h unplanned onsite release of radioactive material
" to the environs including the preparation and forwarding of reports
?: -
covering evaluation, reemmendations and disposition of the - - 5 N $e 6-7 corrective action to prevent recurrence to the %f Mana.pr-
~ ,'
7,I,. -
.n g . . . , . -: ,
and
.v :
to the._NUCLEAR x_____, OPEIATIONS
- REVIEW BOARD {NORB).
. ._ >_ _1 .. . .. . ..
i
.- -. ns..so m. m....,m., ., _
u :. - n .a . . ' .. a v ,
- g -
- g. , 6.5.2 NUCLEAR OPERATIONS REVIEW BOARDlNORB) . ,
" . . . ~ ~ . . .
AUDITS - .y - 6.5.2.8 r hs C.u.w an awM s sM,\\ be. c.endac.bt4 undse % dice.6 d T.' s APCO's MM.yr - o . ca. bens Camb%'t .Asswro nce.i W 1. The radiological anvironmental monitoring program and the g results thereof at least once per 12 months,
- m. The OFFSITE DOSE CALCUtATION MANUAL and implementing procedure ~s at least once per 24 months.
N'
- n. The PROCESS CONTROL PROGRAM and implementing procedures for solf-i dification of radioactive waste at least once per 24 months.
- . 'h: per' ;- : :: ;f ;;ti;iti r;:Wir;d h th; 0 ;lita .W r;;a l;
~
. . es.u. to acct t!.c e. itcri; cf " ;uict;ry Caid; i.15 "-- ci;r
. '077 et imest cace scr 12 mont.).
6.8 PROCEDURES .
. 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below: .
M" . PROCESS CONTROL PROGRAM implementation. - - -
- i. OFFSITE DOSE CALCULATION MANUAL implementation.
~. n .__ _ _ _ _ _ _ _
- a. wo . .,
,u.
o...... . , , ,. . . . . . . - . . . . . . . . . . . . . . .. . , . ~ . . . ,
/
. ?: 'tcr' ;, ;;i ; th: ;;id n;; ' ";;;ict;;-, C id ".15. .
- g. . The radiological envirormental menitoring program.
PWR-STS-1 , e j i ,
.. O O
,.3 i.
~
.l
. _l
- r .**p - *=w . % f "!,I. _ _ _ _
' =;' * .'"'..;' . Y .'.f . % . ,b ' .-b '. . +. :g ? =5;. ?;; _ . .
' ~
f-
~ '
'AD$INISTRATkVECONTOLN -
~
[ 6.9 REPORTING REQUIREMENTS 4 g -h - ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTy# ,.., ;.: , , , 6.9.1.6 Routine radiological environmental operating reports covering . . .. . ..... F W b *# the operation of the unit during the previous calendar year shall be ~~.' h
.;f submitted prior to May I of each year. The initial report shall be ^"~
submitted prior to May 1 of the year following initial criticality. J . , c; -
-:- . ,- n.n.. ~
,.. e - q ..-r . : , - .. . :. . ,
1
-t 6.9.1.7 The annual radfological environmental operating reports shall . , ,. ; include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities foF. '
- E -
the report period, including a comparison with preoperational studies, ~.~ . ' ." ' W: .. operational controls ~ (as. appropriate), and previous environmental surveil-21 paIe G.)C 1ance reports ~and an assessment of the observed impacts of the plant b operation on the environment. The reports shall also include the results . of the land use censuses required by Specification 3.12.2. If harmful
'?
effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course
# of action to alleviate the problem. .
The annual radiciogical environmental operating reports shall include ' summarized and tabulated results in the format of Regulatory Guide 4.8 (12/75) or Regulatory Guide 1.16 (Rev. 5) (to be pub 11shed) of all radiological environmental samples taken during the report period. In the event that some results are not available for inclu'sion with the 1 \a report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions frcxn one reactor; the result of land use censuses required by the Speciff-
~ cation 3.12.2; and the results of licensee participation in the Inter-1aboratory Comparison Program, required by Specification 3.12.3.
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT , , 6.9.1.8 Routine radioactive effluent release reports covering the -
~~
r*.$* 68 operation of the unit during the previous 6 months of operation shall be Q UA single submittal may be made for a multiple unit station. The submit - tal should combine those sections that are common taall units at the - station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. P R-STS-1 , use ( (h. i . 1,1 ,
. .~- 1. ~.,r.g. ... _._ g- .
y .,
* '-y ,~" ...' V. ;;&; ,.:.t..: .'.l,f.i.i~k ~~ .
. x. M. M::: J.d w M A ~.- SY .i " :'& L
~
. 1. . . i c .-e.hf. .{. ., g> p., ., ,' ,w p . . . . .. . . , ,3., . j ,
, . . j .. ,.,.-
. ', ADMINISTRATIVE CONTROLS
~'
_ % ,, submitted within 60 days afteh January I and July I of each year. The
>^*---- period of the first report shall begin with the data of initial criticality.
Y. ~.- ; :x ..:.n-3 ; y; :. . .;.; 7 .7 - . n.;w . ...; . - .~~ , .
- : ~
6.9.1.9 The radioactive effl'uent release reports shall include a summary. - J of the quantities of radioactive liquid and gaseous effluents and solid - % ~ waste released from the unit as outlined in Regulatory Guide 1.21, - r.E " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and ~4 Releases of Radioactive Materials in Liquid and Gaseous Effluents from C .. Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with - M . . , data' summarized on a quarterly basis following the fomat of Appendix B ' ~- 7:.. W .W * . ; = . ' ; %.T " .- - :" ~' ~ a$yp - thereof.
. -=
..v;;
.a Y %..-~
m.wa
...e. y ao.2,1* m ,* r; w.-w n.wy.s e t - -~. . .w. .w ~ .; ..m
%,9 The radioactive effluent' release report to' be' submitted 60 days after ' ~ 5".; P9e -T January 1 of each year shall include an annual summary of hourly met- .
.ev. eorological data collected over the previous year. This annual summary may -
'e - be either in the fom of an hour-by-hour listing of wind speed, wind.direc-7/. tion, atmospheric stability, and precipitation (if measured) on magnetic " C tape, or in the fom of joint frequency (A distributions of wind speed, wind suggested magnetic tape famat T. ' direction, and atmospheric stability. p is available from the the Hydrology-Meteorology Branch, Division of Site -
.- Safety and Environmental Analysis, NRR, NRC, Washington, D.C. 20555.)
This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or sta-tion during the_,su_ previous calendar year. .f: :=: - ; -t :h :? '_ sch: ' !:'
.. _____.........__.........._.._._-_s.._ _ ss, <__ ,___. _ "_.ss_ .....y..
,s_..ss O en.f', '_ e =__ _et : t:, .', ndf",?d=,k.i e >d= t: their =thiti=__m_s m_ m in;id:,,, th _;.it; b;;.nd:ry {4 .__;
u[ p .sw. w ., -.* - w .w
-.* .j ww. ...y
____m
- w. w . vv . . p s. . .v..
- o. . u s w. " y . . w . . .
__4,___
..,w-1 'n ma' in- th = :; ::=:-t: (:.g.,:pe:f'f et!"4ty, e ;ct'ra 'd-= =d
~r '
h=tf =, ch'?' 5: '~chd:d *- th= repet The meteorological con-ditions concurrent with the time of release of radioactive materials in gaseous effluents (as detemined by sampling frequency and measurement) shall be used for detemining the gaseous pathway doses. The assessment J of radiation doses shall be perfomed irr accordance with the Offsite Dose CalculationManual(ODCM). ,
- n. . . _, _ .m m.... .. ..~...-.--.w,,..__,_.,_._____.,u_. . . .. .. .. u. .: . . _ _e n 2 .7, . . .,. ,.__
January 1 of ::ch ye:r : hall che inckd = =:::=ent of radf atten de::: . - the lik:13 me:t spe: d r=1 ind'"id=1 fica r =tcr reis::e; and other
- rby tr =fe- fee? cyc k :: rce: (inckd hg de::: fr= primary ef#hent
~
.~ . patk: yf ind dire'+ :df:tien) for the prevf eu: 12 consecutive month: te- N chen :=fe: an= .'th 10 C"" 190, Envir;= cat ? ? diction Protection St=- dard: for "=k:r Pa:r Oper:tter.. A : ptabk m thed: for c icukthg the date :=tr1heti= fr= ?f quid =d grece: Of cent: are g1"er *- 90';u'y2 +~y 9 %@ 4y$ o " pm
\p au 6u PWR-STS-1 -
*W 9 \\g 4 )j . - ,,o 11 U D
-_~_ ~ ~ .g_.-._..--_.-- - - - -
7
....a....,,, C.- -i .. .- . --
. - ... . .. . . . . ~
W,- ADMINISTRATIVE CONTROLS . . .
.b c .. _ , , m , _
N. -m>_ v u . u s. .s . w .,.,,~,no,.
.. m. . . ._s,s ... s . , _. _>_
...u. owoo s ....ou.o g
. . w. , now . o u . w.. ... . .. 3 ..
.g(n. , .l*,.,e.., ......
e4 0. fr .* - >___ __
, ;., - . . 7.ngpg
. . _ . . . . . . f.M. ., gg. ,
i J.. ,. . ,.a .n..e,. k.1. .m .. . _. ,_.
.- 1. AJ.._. ,_ A .L. _ o v.m s v. a. . 1..-
A L * ,. ai g,,,, m . ,,, A_4. ,. .a_s-+_ /*^
*. 4.
. a. .e. p , A_4. m_ t_ 4 n_ re d_ e_ra_ e_ n_ M 1_4_ .M. '.f.M. . ,f"f' Y _YYY k.^ ,.. ... . k.1 4. .L. .a M. , A. 4. .e - , , , , . . ,
+u_ .+,,,..__ .u . _;_ , _ _
,r.,,.,
..-___, _. .r. ._,....,. . . . . . .
-____ . n._._.~_._.._.....,__....,%...y,.,._._.m__. _ . me u. . e_ . .
-2, ...
w...... . . .,._,. e . a, a... ._ _. _ _ _ _ _ w-
. . .:...........w._.~....,-
. ' e/*. ( --;;. s*W O *~n:Sc.'NM* *N "": .'h" '.** *
. .iE "q_ . .. .g?h"
?.# N A p ". **: * $ t 6-4 E $..#" A -- >"S "i *' -
#>. The radioactive waste effluent release reports shall include the fo11cwing ,
infomation for each type of solid waste shipped offsite during the report - f@i.. period: u-
, , c . ., - .,.;.p, .
.... Te .. : ' i. .
~
- y. .-
Q ? .*-
- t-Nw;.) r a. . . . , .
. ,; 7 e p s,,,;; .y 3.- =--
' r .'e .
- _u.. . g.4,, .,- Q _ . . .: _
R.,. . . , , . a Cont ti ner . volume, W 'af,p. .a n,.G. ;_.4.y. 4 9,.,, ;c.<c.s cI J,.--
*- -. -e . ' .. f;, -?.. .
- u. ,.. . . ..-..c..\... . ~ .. . .
c . ;m ~ . . ,. e .v.
- .c., .- - v .. .. . . . . . -
b; ,, ' . b. total curie quantity (specify whether detemined,by measurement T .. . 2= or estimate),>. - *
- v..*a. - .-- : - - -
y .
- s. . .
.Q a.
- c. principal radionuclides ()specify whether detemined by measure - .,
- w . . .
e -I s-
;. . , ment or estimate), ,-.. .
- t. ,. . .
...o-...- . . .
? . - .-
,w. r ws
. .. f.... , . . , .
q . , type of waste (e.g., spent. resin, compacted dry waste, evaporator. d. I' - . . . bottems, . . . .. ,, , a . , , . . .
,: ; .- n ,. ,. . .
-c -
.. . n. .:. .
7 ~
- e. type of container (e.g., LSA, Type A, Type B, large Quantity), ~
and .
- f. solidification agent (e.g., cement, urea fomaldehyde)'.
hl . Th r:dic;; tic; m..... u. . . _ .A_ _s ,a._,.,.. _ ,. _, -f_u
- m. ._ ___._,a_J.
... . ...m...
nt r k x :. _ _ _ rep;-t: __,.. u._,_
-hall inchd unph aned r:1:=c:
.o._,..,.,..._.... _,.. . . .,,3. . .
..~ ,. z.z...._m a.._
.. _... a.-. .s -..
y. The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period. MONTHLY __ OPERATING REPORT . n 6.9.1. W Any changes to the Offsite Dose Calculational Manual shall be page 6-l.s- submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective. b cdditi n, ; repc-t of :ny .:f ch: g= l Q l
+--.....u........,-,,,+..__---.._
+t_ ,
_ , + ,
, + , , , + ,,+e,,,
e s ,i i s_ o_ e,,w,o. a _
,4 + s n.
M _ __. A ,__ M-__ A f_ - __ f _ J ,_ . . . _ , __ _ _ . . , _ 1,
. ~- .
..J
-A . L.1.
. ,. y .
. . . . .. w . .c
.,. . . A .L .. - r .. . . _ . . . ,. .L. , .m_ L. A m..L - . . . . - - . -....as A
. .~ .
____A n p
..~ .v _J.*L ,Z s. .L. ._ , u ,.
g
. . . . e PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP -
6.9.1.h * ' ' l - .
- j. Offsite releases of radioactive materials in liquid and gaseous '
pi, 4,7' effluents which exceed the Ifmits tf Specification 3.11.1.1 or 3.11.2.1. - -
- 4
'q PWR-STS-1 'uAude .b
'~& -
3= pygw se
.,6 e
~ _ _ . ~ . - . "
~
*m . .e.
. - A .
l.
~
.m - . -..;;.: p;.. ,.. _
,s .-
,. a ,
e~- -
. . -4... . ..-;..-..- ..,,..- a ... ,
4, ;. - - .
. . ., y. .
.p ; <., . > r-f; . . ,,
. . ~ . . .. - -
^
~
. 4,
. ':: '- l: :. . '3,. : R. .;b' . : . . .:.T ^'.T' ', ' . ,
i
- "' ~ ~ ~
ADMINISTRATIVE CONTROLS
\
/ k. ' Exceeding the 11mits in Specification 3.11.1.4 or 3.11.2.7 for 3;:. ....
the storage of radioactive mateMais in the listed tanks. The . written. follow-up report shall .nclude a schedule and a descrip- ' tion of activities planned and/or taken to reduce the contents . ..
.~.
'9-9 c .=, r . ... .. :
to within the specified limits..sa.,w. e .q- . f c .. . ' -a .
. .;[.:p... .
THIRTY DAY WRITTEN REPORTS , 3: , ggp:<,; g. .;y- y , q . p p{~.f .2.; 3. L ..:.sa I?f ~ .,; ~;. , .: 5,, - s 'lD.*, .: , - . . . - * . T*: , ' ' ;'
.: .e- .
- 6. 9.1.W. ,,- WM *. .
, v;r, ,' - *-]'i$fd : *rd..p:n 4 . y-;..
' .".:,~.. . '. C ' = -
- e. , An unplanned offsite release of 1) more than.1. curie of
~.' -
,, radioactive material in liquid effluents, 2) more than .
' ^l- .' .- -
. , . 150 curies of noble gas in gaseous effluents, or 3) more .
f"1" g,.y ' . than 0.05 curies of radiciodine in gaseous effluents. ~ The report of an unplanned offsite release of radioactive
.'.', material shall., include the following infonnation:
. .. . . .....w,,,
.m. ..: . -
. . . . . o;~ . .
.;,. 1. ,.A description of.the event and equipment involved.
.c . .. .-,. .
_ . . .y . ,. .: .. : g. . .;,:
%s
$ v(
. . . . '2. Cause(s) for the un' planned release. ~
. g ...~. . . -
- 3. Actions taken to prevent recurrence. -
- g.
9
- 4. Consequences of the unplanned release.
~
- f. Measured levels of radioactivity in an environmental sampling medium detennined to exceed the reporting level values of Table 3.12-2 when averaged over any calendar quarter sampling
. period. ,
6.10 RECORD RETENTION 6.10.2 (*1 8 m JS Records o'f analyses required by the radiological environmental g monitoring program. ,
- 6. W PROCESS CONTROL PROGRAM (PCP1 . - -
FUNCTION - K proce.s s u sipVicaM 3 bi. c,owsileveA, b 9'c.9 .ha)\ be, a.i bed f M YKose. curredly in u 6.j#.1 The PCP shell be eppie ed by the Ov..idssicr. prior to impic cntatf0n-W 43 .. .
-- $\
62, 6..W. 2 S.; : Licensee initiated changes to .the PCP c ,_)c. ...k. t -. id r U.- _ _ _ _ _ I. Ei 4I $ h s. Nw r" v1 lo =- C-' M'2- '" ^ * '~'^^ '
-: f C ar.t ".':JedSe--Repect-4oethe-per led 7,43; G;.d N.;! '. ^ :- t '. . - -
ch-tk-4 N-M san PWR-STS-1 6 ,I ,l , - __U ll .ww - -%j. .a;. .. J,e: gn. --g am4.j?.;_ _'
- -: -M.' ~
**T ' GJ-l h'~, % ,;a:M.%u.n. w .L : - .:.tr $~t -J .
~__ '
~-
ADMINISTRATIVE CONTROLS .- e rm (? M N b g wpyuu w--
. --E :"'#icie..tly d-t:11-d infonnation-to total-Ty-support---
jti;c retic. sle-for-the-change-without ber afft of addf -- 7 .n-.i ,, .
- mr_ - . .
- ti:=; c :upplements1-4fomst-fons- -
i h. ~a ditermination-that-the hange-did-not-reduce th: '
.;c '-
..._ _.;_I-Collgo citafh. .. :: '. .-
.u. g r,. , v uo, . .u.._. _m __u. .. m. . . n u a w. _ _ p~. ww w s_, [y1 > i
- g. .
......_.m,..-g...-_...._
...- __2
'c . doc c .tation-of-the-fact-that-the-change-has-beea -
r.,i. - _ - .4.~_._a_ ,na_ a.n,a._ _ _ _ ice,pgagt w- _, .+ u... ,m. .---- . .d.
.. -. p ,; .:n.., . :.=.
w a.
.... .c
.... ?.>. .c .:. . . , -
,x .
...r..~ ..
.. ~
E6
. --Er Shail become effective upon review and :::pt=:: by '.': P:R c.:
l5- .. . a 164.l. shicurol*.-<l.- wdh Ays.ci .WJe&J6. C. %. ) .
- h. 6. OFF I Db5 CALCULATkONMANUAL(00CM) - ..' ~ '
.. .g 1 ^
. _ . .. s. - '
F . .' FUNCTICN :.. . . . .
..- n- . -r
[ 6. .I The ODCM shal1 be approved bh khe Commission prior to implementation.
.?-
fa9 6.yf.2 Licensee initiated changes to the ODCM m y 5: --d p;:ef.d:d th:
.- g,g .u.._,._...
9 eL_9 L _J e
.. s..u.9 oo. ou a.. f.sssu ri r w_ r.,._ s w..o... 3.w_
.. . . . i s., .
.e a . . .i .L.
_ n_
- 9. .r v v m i m. . a-n..-
.,.s. . ._a.s
. . . u.4. . o n. a . .r
. . . -.s. e.L. _
,+
. .a. . - . u. .. - ..L. ..u _-_/.,tm. ,..,
.. .. _.;_ . t.
- z. _- - a. . . .. .a.. .y.,,.,._..,a.._.._
. .... . <..< > > . _ . . , . .. . . , - . . n. . a - 4femat4on-to ,t-c +,. .,.,. ,. .,. . . . . ,,, + + u,
.._,+4.,.,_,3..- < , , -
. .. .6..,,.
.. 3 .....m
- a. . w ... u .._.s. 1-t-of-add +t4c . , ,_
en_. n nl. 'ama_ n+ ,1. . . + 6.Y.-.nfa_ r= f_, t_ kn-su_. mI 4. + +_ nd_ e. .k.n i n T. A
- rr _ __
4 n#n_ re fi_ t_4 n_ n . .- . _ -
..,._..4..+. o.<.
c., , - . .< +wm ,..& , ,. m, m, me. ..+ .6.. m
. o.ncu ._ __
,. 6. .,.... a_ m.a. +. w ,., .,. ,,. 6,
. . . . .. , u..a
. _._;_ ___ , . . . . >m> ,_.,. .>1. ' . . . . __
. _ _ . _ _ . . . , ._; ., m . _ . .
+,,,,,+5,,.,4.,, ,.,.,,,,4,.. ,,,,3,,,.,,,.
_rr ....
-...,uat.u_.
4
... ,,, . . _ 4 fyi-ng-t .u. -
-s-- -
___rAr-r --- --- s---
.. . .u. ..m,- , i
- u. . . .. a. . . . .,. <.. -... u.
. . . ...u. 6. .,. ,, ,. .an ....a....,
. . .. + u. .
,, . , ., ._ u. . _s _s 4 3 4. +.,,.m.<. a_,,,-,..,i.,...i..,.+4.._.., .-_...,-:.
,, ,,o .
.. . . ~ . . . .
- a. .
- a. ,+a. _..
_2 2 .-..... ._. _. u..., .. . ,. + u.m. <,,+
.. . . . . . . .. . .. +u..,+.+,.6..- .- 6. .,. .
. ,m. - u. . .,. .~u - ._. -
m,4 ~_ . _ 4_ , na_ < _ , , ,, a_ ___,.__,-. -_ m.,,
, s i. ,, A,., +..6. e. .e _v, . . 2. Shall become effective upon review and ==pt== h, th; ?;"se.
af ro vek .th . a ct.orkt - wr W G IS t i ft k.a ) s k 6 . i., ,,; PWR-STS-1 edem I! __i .%4 1 av; . m.-. g . . h 9
. _ . . . __ p put *% ) .'. *'t
#.4.e c
.. . : . '. .!' ~ ; . ; -o* 17
.u ;. ' '. _ . , . . . . _ , , , * *
., ; . ... * " s, .
...-r'..~.
. . . . . . y ..
, .,.~ , .. , ,
- d. ADMINISTRATIVE CONTROLS
6.16k MAJOR CHANGES TO RADI0ACTIVtf WASTE TREATMENT SYSTEMS (Liquid, Gaseous w a - A.- and Solid) . . . . .
.2
-- .: - .. 3, , ;.'!. s;. . . . , ,,
6.16.1 1. ensee initiated major changes to the radioactive waste systems N -- (liquid, - ' ~ ~ seous and solid) may be made provided:... ygi:s. a .- ..a. . n . ; M.
. . . n...:m ;
-Q ; - 5. s.::y,+ w . . . 7 80 1. The hange is reported in the Monthly Operating Report for the .t.s ' - perio in which the evaluation was reviewed by the r ?.! ' The discussion of each change shall contain: . . ' . . . ~ Z gj -
^ Qi; i,.f o R C '... i.is.
4 a. a su
'_.*.. A tp..? : . 2 ' .
ry of the evaluation that led to the determina-7~~~- .
'. ! tion t t the change could be made in accordance wita -
~ ' -
h .' . S..; "..T.' . ' . . ' ' . ~ 10 CFR 59; v.,7 ':.*. _ ~ . - '.. .
. . ~ .
7, . ..
.s . -
. b.~ sufficient eta information to totally support the
. L '.' reason for t ch .ge without benefit of additional i - i.[- p or sj, plement at{on{',, ,
- c. a dstailed descr hn the equipment, components -
and the interfaces with other
;_ , . and processes invo y ' -
plant systems; .- ..
,c . :. 1. . . -
- d. an evaluation of the c n ich shows the predicted releases of radioactive ate is in liquid and gaseous effluents and/or quantity o id waste that differ l Q3
. ;. ! from those previously pred in the license application
'and amendments thereto; i e. an evaluation of the change wh1 h shows the expected maximum exposures to. individual the unrestricted area and to the general populatio that differ fran those previously estimated.in the 1 ense application C, "
and amendments thereto; -
' f. a cabparison of the' predicted releases radioactive materials in liquid and gaseous effluents and in solid waste to the actual releases for the perio in which
.the changes were made; - .- . . .
- g. 'an estimate of the exposure to plant operating ersonnel -
2 as a result of the change; and .
-_ h. documentation of.the fact that the change was revi ed '
.- ' and found acceptable by the FORc.; _ . . .
. 2. The change shall beccme effective upon review and acceptanc by the 70 gc.,
PWR-STS-1 ., 6-7 D I1- ong 1i _c.
-L - --~~ - - - -- ... . - . , _ _, ...:.._...
w . . , - .- u
. ; r -
- ,5 _: 3 ..,
. . f p,;.yy. .b K_ . :.._
-,m.eme ENCLOSURE 2 APCO BASES FOR CHANGES TO NRC DRAFT OF (1) DEFINIT!DNS (2) SECTION 3/4-3 (3) SECTION 3/4-11 (4) BASES (5) SECTION 6 3 .nf i , - ._ J
. g. 1p
~ BASES FOR CHANGES TO DEFINITIONS AND SECTIONS 3/4-3 AND 3/4-11
- 1. The modified definition conforms witn the existing FNP Standcrd Technical Specifications. Incorporation of the new definition would affece certain instrument bistable channels which do not have provision for injection of a signal into the sensor.
- 2. FNP FSAR allows shipment of dewatered resins.
- 3. The solidification of several batches in a single liner is a normal practice.
This will result in a non-homogeneous solid.
- 4. See letter from F. L. Clayton of Alabama Power Company to A. Schwencer of the NRC, concerning FNP ODCM.
- 5. FNP environmental monitoring program utilizes this frequency.
- 6. With the discharge valves locked closed no release can occur.
- 7. The action statement (b) permits release with an inoperable channel.
- 8. This language is consistent with the Action statement in other portions of Section 3 of the FNP Technical Specifications.
- 9. As the degraded mode of operation permitted by the Action statements of this specification does not result in an increase in offsite doses or an increased hazard to the public, it is our position that no written report should be re-quired.
- 10. The fourteen-day limit is unreasonably short for obtaining replacement parts for repair of an instrument.
- 11. The normal sample analysis is fully automated from the start of counting to the computer printout of final results, hence, verification of calculations is urnacessary. This was discussed with the NRC staff during our June 6, 1979 meeting.
- 17. If the flow is measured by portable ultrasonic flow measuring devices or other devices which may be available, no degra/; tion will occur in the documentation of the release parameters. This item was discussed with the NRC staff during our June 6, 1979 meeting.
- 13. These instruments have no alarm or trip function, so no Channel Functional Test is possible. NRC staff agreed with this position during our meeting of June 6, 1979.
; ,l , - ,qj i c 'r
4
- 14. This specification as rewritten describes the instrumentation as installed at FNP. NRC staff agreed with this position during our meeting of June 6, 1979.
- 15. The Waste Gas Holdup System is not an effluent pathway. NRC staff agreed with this position during our meeting of June 6, 1979.
- 16. At FNP the undecirable condition is high 02 at the recombiner outlet. Either combination of instruments (a or b) will assure that the 60 ppm 02 limit at the recombiner outlet is not exceeded. Isolation of the 02 supply will also reduce the 02 concentration to this level. NRC staff agreed with this position during our meeting of June 6, 1979.
- 17. This system is already covered by Technical Specification 3.3.3.1 - Table 3.3-6.
Also, the effluent monitor for this system is the vent system monitor. NRC staff agreed with this position during our meeting of June 6, 1979.
- 18. The sampler flow rate measuring device is a part of the sampler and is con-sidered to be attendant instrumentation per definition 1.6. Accordingly, it should not be separately specified. This item was discussed with NRC staff during the June 6, 1979 meeting.
- 19. These samplers are off-line noncontinuous type. This item was discussed with NRC staff during our June 6, 1979 meeting.
- 20. No such instrument is installed at FNP. NRC staff agreed with this position during our June 6, 1979 meeting.
- 11. Dilution flows are stable; therefore, once each shift will provide assurance of adequate dilucion.
- 22. Mormal building ventilation is required to continue at all times.
- 23. The use of auxiliary sampling equipment will provide results that equal those of the normal equipment.
- 24. The SJAE is not operated in Modes 5 and 6.
- 25. These are the calibration gases presently in use at FNP. This position was accepted by NRC staff in our June 6, 1979 meeting.
- 26. No action can be accomplished "immediately". The one-hour time is reason-able. A one-hour time for action does not imply NRC approval of a violation of 10CFR20 as the reporting requirements are in effect. This item was dis-cussed with NRC staff during the June 6, 1979 meeting.
- 27. The effluent releases are not directly related to the mode of plant operation.
Under certain conditions the effluents could be increased by forcing the plant to shut down. As the reporting requirements of 6.9.1.9.b are in effect, any decision to remain at power would be explained in the written report, j r - non 1 > --l
n.
- 28. The sampling and analysis frequency is specified in Table 4.11-1 and should not be restated in the specification. The in-line radiation monitors are calibrated to assure compliance with the 10CFR20 concentrations. Therefore, further documentation of the 10CFR20 compliance is not warranted.
- 29. These gases are measured by the SJAE monitor.
- 30. This added note will prevent excessive reporting of MDC variations caused by the presence of isotopes which may interfere with the detection of the isotopes of primary interest. This possibility is acknowledged in Table 2-1 of the present FNP Technical Specifications, App 6ndix B.
- 31. The modified limits assure that appropriate equipment will be used whenever the projected dose exceeds one-half of the quarterly limit. Th s operation of equipment should result in the lowering of the projected doses from sub-sequent releases. Thus, the one-half value is a reasonable point to start using idle equipment if a projected dose is used. Also, the utilization of equipment which will not remove the isotopea of concern, based solely on en arbitrary limit is not justified. For instance, if floor drains contain only Tritium the utilization of an evaporator would have no effect on the offsite dose and should not be required.
- 32. The surveillance will assure that the equipment is available at a projected dose of one-half the projected dose requirement for the equipment operation.
- 33. This section applies to liquid waste holdup rather than the solidification process.
- 34. (Deleted)
- 35. This monitor is covered by specification Table 3.3-14 and 4.3-14. Also, Table 4.11-2 is applicable to sampling, not monitoring.
- 36. This modification will assure that analyses are manually controlled below 15% power, frequent trips occur during a normal startup. These low-power trips do not warrant an analysis.
- 37. Tritium monitoring of the refueling pool vent system is required on a monthly basis. The original notations e and f are therefore not required.
- 38. The modifications will permit the use of the existing quarter-based computer software rather than the monthly basis.
- 39. The APCo revision is more conservative than the NRC draft. NRC staff agreed with this position during our June 6, 1979 meeting.
b
An
- 40. This modification will eliminate needless radiation exposures in taking measurements of tanks with low inventories. As the addition of over 20,000 curies to a tank in one month is extremely unlikely, the monthly surveillance of the tanks below 50,000 curies will assure the 70,500 curie limit is not exceeded.
- 41. If a system is not operable and all limits are being met, no violations of exposure limits are possible. The spec, as originally written, would re-quire a report of all equipment which remained inoperable for over one month even if the equipment was not required to operate during the in-operable period. This change will avoid this excessive reporting require-ment.
- 42. Since no technically feasible MDC has been established for P-32 and F e-55, no MDC can be submitted at this time.
- 43. Separately specifying contributions from each operating unit in the Environmental Operating Report is not practical.
- 44. This information is already provided in the statistical summary report of personnel monitoring data for plant radiation workers. There is no legal reporting basis for extending this to non-radiation worker employees.
- 45. There is no requirement in 40CFR190 for such an annual assessment or report.
- 46. This is a duplication of prompt report and 30-day report requirements.
- 47. This is a duplication of information already required in the annual 10CFR50.59 report.
- 48. Review of plant procedures and manuals is performed on-site by NRC I&E personnel.
- 49. Requirements of this section are met by complying with 10CFR50.59.
Documentation is available for inspection by I&E personnel.
- 50. This terminology is consistent with 40CFR Part 190.
- 51. Farley Nuclear Plant is in operation and the current PCP is in effect; therefore, the current FCP cannot be approved by the Cmmission prior to impl mentation.
- 52. The PCP does not contain operating procedures. Review of plant procedures is performed by NRC I&E staff onsite. This position was agreed upon by NRC staff during the June 6, 1979 meeting.
~
1,1 . ?_7
. n-ENCLOSURE 3 REVISED TECH SPEC - (1) SECTION 3/4-12, RADIOLOGICAL ENVIRONMENTAL MONITORING (2) BASES 1 li , -- ,,q _ __ u
.-l f , , ._,
k 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING i . l 3/4.12.1 MONITORING PROGRAM 4 LIMITING CONDITION FOR OPERATION fl 3.12.1 The radiokogical environmental monitoring program shall-be con-ducted as specified in Table 3.12-1. . - At all times.
~ . APPLICABILITY:
ACTION: < F /S
- a. the radiological environmental monitoring prograwlot W I conducted as specified in Table 3.12-1, prepare and submit to -
the Commission, in the Annual Radiological Environmental , ~ Operating Report, vacasu=54=esmen the reasons for not conducting the program as required and the plans for preventing a recurrence.
- COMROKO
- b. E(P theAl evel of radioactivity in an environmental sampling medium exceedihe-the reporting levels of Table 3.12-2 when averaged over any cal f ndar quarter, prepare and submit to the h() Commission withingdays from the end of the affected calendar quarter a report pursuant. to 6.9.1.13. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) , concentration (2) + ***> 1*0
, limit level (1) limit level (2) -
When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be suomitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, - 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not'the result of plant effluents; how-ever, in such an event, the condition shall be reported and des-cribed in the Annual Radiological Environmental Operating Report. JF ADE90ATEGtMYLSof g pp
- c. EMAmil k or 'c x 9 p'y 7' ': r ," r unavailable from one -
or more of the sample locations required by Table 3.12-1, in lieu , of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report, which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samolesen The locations from which samples were un-aval table may then be deleted from those required by Table 3.12-1, BAsbD UPDA 7Ws nos7ytWMuo vss censw. l , PWR-STS-1 3/4 12-1 j1 1 O ")
, i i > -/
a, .
.'.s 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING ,} 3/4.12.1 MONITORING PROGRAM 3
LIMITING CONDITION FOR OPERATION (Continued)
- i. - cqg provided the locations fran which the replacement samples we22 obtained are added to the environmental monitoring program as replacement 1ocations, /F At!AILABLF- -
[ The provisions of Specifications 3.0.3 and 3.0.4 are not y applicable. SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be col-lected pursuant to Table 3.12-1 from the locations given in the table and figure in the ODCM and shall be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12-1.
- w k, L)?!!/ A7/M'S AAA P.S&7!!77E6 FRan/ 77/ERE.;70/6SD CA9/PA/A's C dWEhVAE, /F Shir/P/AS 4AE U84474/MALJP Dt/s 7~$
//f2AAh003 89Mh)7/JMS, SAMtMABM U/JM4K6BJz)7f og 70 A/AAFund?7ct.i g/= A076/11/?7M CA//ff'A/A&' AfNAA/EN7.1E 7/A*
A.677 A pypey Af/=6ff SA4'<A AAMMA^* ~70 d'w%M doigAsC7/W Ad7/JA I M/0/ TO THE ANA 'I 70# AEI
$/;,yp,ugy fjA'/a/J . 4/4.2:UM7./DNS FASAf WE W'#4 SCNA.ot/xs s~#HA BE@ASCWA An' 7# AN##'"
Anh/OdDC/C/4L ,EA/Ph?2:/$16U7A4- QPA#A7/fs N' Al # A'# GP #27 6y2A' A'2?)ATHJ/' AE$W/i'AMAWI A ~fNE 7A0ll/D'D/ V S OF 5'MNF/e/)7/cAV +'.D. 2 Aps g-Pjm'eMAS TO Mnf Srpp/PA//vf A//o JJMYJ/S S!A' 4Co0.LG SMS&dAf/Al l 7n' A.LE 3. /2 - / ,
.,g
) > JU PWR-STS-1 3/4 12-2
TABLE 3.12-1 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JOSEPli M. FARLEY NUCLEAR PLANT Exposure Pathway Number of' Sampling Sampling Mode Sample and/or Sample Samples . Frequency & Collec tion Ana' lysis
- 1. Airborne
- a. Particulates Indicator 3 W Continuous Sampler. Analyze Each Sample For Gross Control 2 Sample Collection Beta Radioactivity At End Of Sampling 1 24 llours Following Period, Or As Required Filter Change.
By Dust Loading. Perform Gamma Isotopic Analysis On Each Sample When Gross Beta Activity Is > 10 Times Mean Of Control Samples For Previous Calendar Year. Q At End Of Each Calendar Perform Gamma Isotopic Analysis Quarter Composite Sample On Each Composite Sample. Filters By Location
- b. Radiciodine W Con tinocus Sampler. Analyze Each Radioiodine Canister Indicator 3 Sample Collection At End For Iodine-131.
Conttal 2 Of Sampling Period.
- 2. Direct Radiation Q Con tinuous Measurement Read Accumula ted Gamma Dose Indic^ tor 8 Of Gamma Dose Ra te At Co n t r..,
For Each Dosimeter. 3 Each Loca tion Using 2 TLD Dosimeters With Collection At End Of Sampling Period. W
=
f .) (4 l l -
TABLE 3.12-1 Continued Exposure Pathway Number Of Sampling Sampling Mode Sample And/Or Sample Samples Freq uency & Collection Analysis
- 3. Waterborne
- a. Surface M Composite Sampler.2 Perform Gamma Indica tor 1 Collected Over Sampling Isotopic Analysis On Control 1 Period As Required By Each Composite Sample.
Size Of Sample Container And Composited At End Of Period By Location. Q At End Of Each Calendar - Analyze Each Composite Quarter Fbke A Composite Sample For Tritium. Sample By Location .
- b. Ground Q Grab Sample. Perform Gamma Isotopic Indicator 1 And Tritium Analyses Of Control 1 Each Sample.
- c. Sediment Indica to r 1 SA Grab Sample. Perform Gamma Isotopic Analysis Of Each Sample.
- 4. Ingestion a, tillk Indica tor 3 SM Grab Sample. Perform Gamma Isotopic And Control 1 When Animals Are Iodine-131 Analyses Of Each On Pasture. Sample.
M Grab Sample. Perform Gamma Isotopic And ___ When Animals Are Not Iodine-131 Analyses Of Each On Pasture Sample.
< i r; .
L.. 4 l' d I l 1
TABLE 3.12-1 . Continued Exposure Pathway Number of Sampling Sampling Mode Sample and/or Sample Samples Frequency & Collection Analysis
- 4. Ingestion -
- b. Fish Indica tor 2 SA One Sample Of Each of Perform Camma Isotopic Control The Following Species Analysis On Edible Portions At Each Location: Of Each Sample.
- 1. Game Fish
- 2. Bottom Feed'ng Fish
- c. Forage 4 Indica tor 2 M Grab Sample Cut
- Perform Gamma Isotopic Control 1 From Green Forage, Analysis Which Specifically Includes Iodine-131, Of Each Sample.
(1) Sample locations are shown in Table and Figures in Off-Site Dose Calculation Manual (ODCM) . (2) 'Composite semples shall be collected by collecting an aliquot at intervals not exceeding 2 llours. (3) No applicable indicator milk sampling locations at time of June,1979 Milk Animal Survey. (4) Forage Sampling in lieu of Food Products, f m e-4 ta l ,
s . . . , i .
',._ m .
l . ._ m. TABLE 4.12 q E MWintih' i bEuer48M cWewM47AW f . _ ..._m. ._. LOWER.LI"JIS OI DETECIIO" (EE}}#' n. y G*9 _ .. . -
- e. c .
l Water Airborne Particulate Fish
/~0RMfff
" Milk F::d " e ucts- d Sediment Analysis (pci/1) ( C1jn ) (pCi/kg ,. wet) (pCi/1) .(pC1/Rg, wet) (pCi/kg , dry) gross beta b -2 4 1 x 10 ,
3 b 11 2000-(1000 ) 54 ' 15 fin 130 g 59 30 260 Fe .
.c. .
- 58,60 15 130 m Co ihl 65 30 ?6n 1 2n 952r )hb ./6, 8 -
1J-y- 7 x 10 -2 131 lb. 7 60 i 134,137 15(105)..18 1 x 10-2 130 #5 70f '60 150 ', , 140 Ba-La fo, 79 /4W ,
~
l i g . _a ee l . r2 . (.. -J
. a
- =.
t
," TABLE 4.12-1 (Continued) { ', .
~
TABLE NOTATION .l-
#DL
- a. The AMP is the smallest concentration of radioactive material r in a sample that will be detected with 95% probability with 5% . i probability of falsely concluding that a blank observation -
represents a "real" signal. ' - . For a particular measurement system (which may include radio- , chemical separation): - . Af 0C. + 4.66 s g - g _ ... .
~
E ;V 2.22 Y exp(- AAT) 1
- where is the lower limit of detection as defined above (as pCi . I per unit mass or volume) ,
s is the standard deviation of the background counting rate , orb of the counting rate of a blank sample as appropriate (as ' counts per minute) E is the counting efficiency (as counts per transfomation) V is the sample size (in units of mass or volume) 2.22 is the number of transfomations per minyte per
. picocurie ,
Y is the fractional radiochemical yield (when applicable) . A ,is the radioactive decay constant for the particular radionuclide , t
- AT is the elapsed time between sample collection (ar end of the sample collection period) and time of counting (for environmental '
samples, not plant effluent samples). i
/lDC The value of s sused in the calculation of the bisiik for a detec-tion syst'en snaT1 be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified PWR-STS-1 3/4 12-8 ti _;
g . TABLE 4.12-1 (Continued) g . TABLE NOTATION ,
,_ theoretically predicted variance. kn calculating the b for
- a radionuclide determined by gamma-ray spectrometry, the back- ,
ground shall include the typical contributions of other radio-nuclides normally present in the samples (e.g., potas:%m-40 in milk samples). Typical values of E, V, Y and AT shoulo be used in the calculations.
/ffM
- b. M 9-for drinking water. {g ';
1 T ,tui fu. p. w. od 1 htu. .- O '(. This does not mean that only the radionuclides in Table 4.12-1 - are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported. , WE YU N07 APEAf MJ TAW AVAff CF fhCfggggy,vb, bdA 10 N/APWS TAS7/np ,ma007 RhoM(T/thrf. 6
, /// 4 JEU pp f d b fg M UC7f, U
i
~
PWR-STS-1 3/4 12-9
j . .
.y ,, . .
. RADIOLOGICAL ENVIRONMENTAL MONITORING s
3/4.12.2 LAND USE CENSUS 11
' " ~ ~
LIMITING CONDITION FOR OPERATION M n U F 3.12.2 A land use census shallJe conducted nd shall identiff the loca-tion of the nearest milk animaT^, the nearest residence " " " 6 fem p . ; d _f'. . . . ; f, mbf ieavy 5-.- y c' : ~ ~ :.. :0^ a r ,e i 0:9 c f t h; ". 5 - ' e ~a r~ :: ? x ; . ., c i t.. : d't;,,; oft'p- cN
.e
' ' - e.
2
.,,,,....'h -*~
5 5 3 "' . , u' ,,",,,/,.ueursay
..au '"
we nu,ua..uuu wy
/
^ * '
,k
, ;,4 - a e ,n0 211....-,g..,
c a q 7,; ,, g := tN 7 7c0 ; , u.. ree p p;d a i 7,; y, ,,;r 4g, ,,ogo+ ,i,w n' m2rw me 1 ; ,,, ,4;u ' :: ter: .',0.... dict::ce -
., ., 3 f
. h),/59) h//E a'j /HfTAMMOfM/R GEC7EAS M/TA///4 A/MM OM*A APPLICABILITY: At all times.
ACTION: g
- a. With a land use census identifying al location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification '.11.2.3.1, + pre-pare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report, in 1(afu of any other report, nich identifies the new location (s).
- b. With a land use census identifying a#AM3 /\ location (s) which yields a
__ calculated dose or dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Raport, in lieu of any other report, which identifies the new location. The new location shall be added to Swr /.ES the radiological environmenta] monitoring program within 3_0 days, m :. The sampling, location excluding the control stattori gyp ^ ion having ocat the lcwest calculated dose or dose commitment ('ia the same exposure pathway) may be deleted from this monitoring pragram after (Lc. u u. a.c m_, . - - '-i: J ^ '--d a = mm r-a..n+ s C6MbM"77AS h*//E /a.+.dv s _e c e r .s y 3,
- c. The pr wisions of Specific,ations 3.0.3 and 3.0.4 are not appl i cu>1 e.
4 , 7 Is7 ai YiUdu &CG[ Vt'9MIk" s@h9-C ed -CI (h2--$iIC b C wis d O ry-i-^, tha direc* ion sac +nr w th +ba h4 hest D/Q-i-r. 'ica of -the '; rder cem:n i PWR-STS-1 3/4 12-10 .
-)&dou) OK Go#7 7#4 7 is M$t&Wd /g//;- fcA //w/M/ en/2t/MM7 N.
l . - __. . _ _ . . . . . . _ _ _ _ . . _ . _ _ _ _ . . . _ _ _
j , U \
'.; RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM n ' ~
7' m LIMITING CONDITION FOR OPERATION - 1 3.12.3 Analyses shall be perfomed on radioactive materials supplied as part of an Ir;terlaboratory Comparison Program which has been approved by NRC. APPLICABILITY: At all times.
, ACTION:
lF age- -
- a. &&ttr analysesgot hasag. performed as r quired above, sca, c 9MM the corrective actions taken to prevent a recurrencerto the #^ W E Commission in the Annual Radiological Environmental Operating Repo rt.
- b. The provisions _of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12. '3 -l :ra., ;T Results obtained as part of the above required '" " ^ ^ " ' + - Interlaboratory Comparison Program - ' #- --- g D r r 7 :' L'. ; ; . . " . . . m '. '::::.' shall be R;c' d j .V. 9:
- n! ':di:
; 1p;;;;' r-+n-a-,1 nr->+ < 7 o - mm;a%;a e f ; f pf g y ,, N "y#d ,
' l
, n9 i _. c c PWR-STS-1 3/4 12-11 i -
~j.b TABLE'3.12-2 2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SN4PLES 7'
- L'l y [
Reporting Levels
- pp, f Water Airborne Particulate Fish Milk- L
- Pddata , j Analysis (pCi/1) or Gases (pC1/m3 ) (pCi/Kg, wet)' (pCi/l) (pCi/Kg. Wet)
H-3 2 x 104 ( } ' ' - 1 x 10 3 Mn-54 3 x 104 - , 2 D Fe-59 4 x 10 1 x 10 4 -' I 3 . - R Co-58 1 x 10 3 x 10 4
* ~
2 ! ' g Co 3 x 10 - 1 x 10 4
* . s 2n-65 3 x 10 2 2 x 10 4
Zr-Nb-95 4 x 10 2 (b) - *
, I-131 2
#/ 3 fx 102 ,
Cs-134 30 @ , 10 1 x 10 3 . 60 '* 1 x 10 3 Cs-137 SON 20 2 x 10 3 70 2 x 10 3 Ba-La-140 fx 10 2 ' 3 x 10 2 a For drinking water samples. This is'40CFR Part 14.i value.
'7 'b Totalforparentanddaughter[4:s is /L. Sun o f !a M'vidu d S N*/ Vh e5 h. Mt
{' d cora.bked A aI sy s's of $a/1. J s s h[2 < T , sa ,
# e
* . ;r* I t-i.l -
( , ,, Ie
, .. i
't ; . . . * . . rc? l i . * , s.'*..r 3.... , .
f ., . .
.~
7.{ 4 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING d BA.WS
~.a 9_~. . ~ _
I' 3/4.12.1 MONITORING PROGRAM ,
~
The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and #ar those radinnuclides which lead to the highest potential radiation ex ures of individuals resulting from the station operation. This monit ring program thereby supplements gradiological effluent monitoring program by vcnif.7 :n; th:t t5: measurae.+ concentrations of radioactive materials and levels of radiationter: r. t "gt M :: - ps4 d#A! pt:td on the basis of .the effluent measurements and moceling of tne WW MF environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial,FF QQ operation. Following this period, program changes may be initiated based on operational experience. The detection capabilities required by Table 4.12.-1 are state-of-the-art for routine environmental measurements in industrial laboratories. The yt 94 for drinking water meet the requirements of 40 CFR 141. For more Y MDC complete discussion of the ttS and other detection limits, see the following: 4tDC. (1) HASL Procedures Manual, HASL-300 (revised annually). - (2) Currie, L. A., " Limits for Qualitative Detection and Quantitative
~l; Determination - Application to Radiochemistry" Anal. Chem, 40, 586-93 (1968).
i (3) Hart /w:ll, J. K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537, - (June 22,1972). 4 3/4.12.2 LAND USE CENSUS
~
This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring - program are made if required by the results of this census. The best survey information from the door-to-door, aerial or consulting with local agricul-tural authorities, shall be used. This census satisfies the reoisiremanN of Section IV.B.3 of Appendix Ian 10 cm Part 50.f nc::rit:i-c 9: : c u t-6p- 7 i m- 5 :ycr 9 nrovides a3wd :h;t d.;;rL . NF' CXpC ur If '2": "# 2 e2$' /23:t
'e M
+"a
^3'g..l :; .Jcuc! CGd 4-7"mrac"i--dtg? chce ec..i h. cd 2.. c m ;qd r C # 'b
; :#re tA qucau cy (26 w/yearl or seaQ .m;ctd'oe '--"7:d i... V ete. r%
-Cu.ue I .1C0 fo r ;...au.ap qva L., a l o s Tn h+ o e thi u nim-PWR-STS-1 B 3/4 12-1
), 3, q.
- a
_ . - . . _ - - ~ - .. - - m . . - - 6
a
^. :
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES
, .o
+5 =+ 'o*
j . si;e, t!.cgvn i ;-.n; :: r gticn: ::c re .::d,1) # th ;;M:n ,;; a ur^d '
;.,o..9 vivau ' c a . s, c , c . a . . m. ? ; . . , : f " : - % ' a + + '_ r Eds c '"::c , , ...J G o
. c3 cec.4un y,c.m u-
' ';/ : 72 ~ s ' a r .' -
3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environnmental sample matrices are performed as part of a quality assurance program for . environmental monitoring in order to demonstrate that the results are reasonably valid.
~
11 I I
~
?1 i
i PWR-STS-1 B 3/4 12-2
= = = ease a e . , - -
* * * * * " * * - e e e o es e . e e* e-
. M ENCLOSURE 4 ALABAMA POWER C0h ANY BASES FOR CHANGES IN ENCLOSURE 3 n, a9
} 3, , -, - .-
O h
r Bases for Section 3/4.12 (Continued) Page 2
- 6. During the June 6,1979 meeting, NRC staff agreed with the replacement of annual vegetable samples with monthly forage samples. This change reflects tha implementation of that agreement.
- 7. The samples analyzed by Plant Farley are from other locations and are not related to the operation of Plant Farley. It would, therefore, be intppropriate to include these sample analysis results in a public document concerning our plant. The results of analyses conducted under this program are collated and compared by the agency which ad-ministers the program. The presence of ..ople analysis results which are in excess of the desirable levels in our Operating Report could re-sult in undeserved criticism from various organizations which oppose the operation of our facility.
- 8. Unrealistically low values have been increased to technically feasible levels.
' The I-131 changes were acceptable to NRC staff during the June 6,1979 meeting. The Ba-La-140 limit was not discussed during the meeting. The 2 x 102pC1/1 value is acceptable for an individual limit, but cannot be consistently met as a combinu limit.
1
~
"7
\ , - J
, ' N. BASES FOR SECTION 3/4.12
- 1. The activity levels encountered in environmental samples are very close to background. Due to the poor counting statistics common to environmental sample analysis it is often necessary to perform confirmatory analyses.
Sufficient time should be allowed after the end of the quarter for the performance of any needed confirmatory analyses. NRC staff agreed with this pition during our meeting of June 6,1979.
- 2. Past experience has proven that samples are occasionally unavailable due to the reasons stated in this note. The present FNP Technical Specifications, Appendix B, allow the deviations stated in the note.
- 3. The variations in schedule are allowed by Specification 4.02 for surveillance tests. Due to factors beyond the control of plant manage-ment, the sample availability may fluctuate. This note will avoid
. unnecessary reporting of routine variations in the sampling frequency.
- 4. Table 3.12-1 has been rewritten to clarify the Sampling and Analysis re-quirements.
- 5. The MDC levels stated in Table 4.12-1 are values which were quoted by the University of Georgia Center for Applied Isotope Studies. These are individual isotope values which the center's experience has proved achievable in practical use. As the parent and daughter may not be in equilibrium, the use of a combined MDC is not feasible. The MDC values stated cannot be reasonably expected to apply in the event of atmospheric nuclear weapons
. testing. Thcse changes were discussed with the NRC staff during the June 6, 1979 meeting. At that time it was agreed that APCo would consult with the University of Georgia concerning MDC values. The other changes were approved by the staff in that meeting. ]j'] { ' 4,1
ENCLOSURE 5 ADDED SITE MAPS FIGURES 5.1-3, 5.1-4
) ,,
.I I c. J O
4 5.0 DESIGN FC IURES 5.1 SITE - EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1-1.
. LOW POPULATION ZONE 5.1. 2 The low population zone shall be as shown in Figure 5.1-2.
{ 3 j:)- Si t 5.2 CONTAINMENT . CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced
's concrete building of cylindrical shape, with a dome roof and having the
,_, following design features:
- a. Nominal inside diameter = 130 feet.
- b. Nominal inside height = 183 feet.-
- c. Minimum thickness of concrete walls = 3.75 feet.
- d. Minimum thickness of concrete roof = 3.25 feet.
.e. Minimum thickness of concrete floor pad = 9 feet.
- f. Nominal thickness of steel liner = 0.25 inches.
6
- g. Net free volume = 2x10 cubic feet.
; 2b v
FARLEY - UNIT 1 5-1
4 s..
.r. ..; .
....._v...
~
.. * ~~'
. . .a . . ..
5.0 DESIGN FEATURES 4/ . ... .
. . 5.1 SITE .
- . - - e EXCLUSION AREA P -S.~.J,T.' #: ' ,... .^-#- '- ~d ' - -
nr
, .x e.... . .~;.n ... . .n. .- <, ... ,: . . ,
5.1.1 The exclusion area shall be as shown in Figure 5.1-1. .. _;f "--M .. . h:- : . . , . . .w ..
........ .-. . . . . .. , . . . .- ... ,...+. , :. r . ,. -- .
g.. .,6.u,,....,.......-_-_..*
;.... ;- 9':?. <: .
..y..,...._,,
m.y~:.5:L...
.;. .. g,'
- t. - - -
LOW POPULATION
. . . , ~ ,
.i ,.,T.;., : .an,'7:a.
.L n: .,.... -
. " :.~. ,.'-
S 5.1.2 The low population zone shall- be- as shown in Figure 5.1-2. ..z ' .: ,- -~... . , n
. - = . . . , , . . . . . . .
.,... -. w .., . ~, -. .
$ -i-) . ;, . . ,. - v ' .. :::Y;';j-4 'W
' N -(+. . . '." *"..'_
SITE BOUNDARY FOR..iMW.'. *?.~ %51 ..!$. .. .
. -.c.::Q g . '
.- . GASE005' EFFLUENTS ,..:.::y._. ; ~~f. ,.; ..- r;. r ..:.f,.
~c ..
- 3. . -- ... .. . .
+ , .
y . . . ... s ..re _...,;. . - .. . g 5.1.3. The site boundary for gaseous effluents shall beAshown in - n.. . . - .~a.
.e ,. F1gure-5.1-3. ,- . . - 7.- .: .. ; .> ; . . .
-A... b ...' .- ,., ?. .. ..-..,,._..:- .
1 ._.. .u. . : . u:. ~ . . . .. .. ,. : .. - f %. ,. .
, . .q .- - - '
~
y: .. . . . . . . . ~ . . . . . .. .. ..-
. .. .c .... '
jf j SITEBOUNDAR[FORLIOUIDEFFLUENT5.$~,.., ..
' . . . . . . J., h, , . ,
e . / ., .- .w s -. . .
....n ..
Q 7 5.1.'4 .The site boundcry for liquid effluents shall be hown in ~ - --
- Figure 5.1-4. . . -
q) . t,
% y
) . .
. 9 9g O'
~. . .
.h.
g -
- e. .g s- , . ..
<.,.i . . Q .~
- 3. . .. .
s -
.~.
a.: ... . . .. ..--_: -- .
- r.
.-~ :
PWR-STS 1 1' s.
" ' . . . 5-1" . . ._
.- ^
' s
,7 11 ; ._ ,
-) y
- 6m. .
.- . . w . a. . . - y.- '
...o. *
~: f. . .** ' . . :
7, . , . . , s ..
o 8 8 -
$ PROPERTY LINE (SITE BOUNDARY FOR GASEOUS EFFLUENTS)
METEOROLOGICAL TOWER I h gl '\ N 267,000
\\i ELEVATION APPROX 150 FT BOTH UNITS, 9. ,
9 RELEASE POINT I 1
, UNIT NO. 2 - CONTAINMENT ELEVATION - APPROX 300 FT. I I AND AUXILIARY Bull' DING I
4240 p7 UNIT 2 CONTAINMENT VENT y/ I 4270 FT 4h O 90 O CO TAINMENT VENT"
/ bUNIT NO.1 -
CONTAINMENT AND AUXILI ARY f
/ _
D f JNFORMATION CENTER , . BUILDING f I (NOT COMPLETED - ZERO RIVER T
\ OCCUPATION) INTAKE
\ SERVICE WATER g
\
INTAKE STRUCTURE 'I
\ , \. 3,
-i L __. i RESERVOIR l /
PROPERTY LINE
~
NOTE:SU5FSAR FIGURE 2.1dFOR ;
. TOPOGRAPHICAL MAP OF SITE Figure 5.1-3 Plant Farley Site Map j1 I
ne3
",u Gaseous Effluents
- a. E PROPERTY LINE (SITE BOUNDARY FOR_Li, QUID _EF,FLUENTS) _
N 268,000 N\ s
@, METEOROLOGICAL TOWER
\
I N 267,000 , i
\
W l 7 . i 9 UNIT NO. 2 CONTAINMENT l f t AND AUXILIARY BUILDING gWAUE LINE
/ UNI i' NO. 2 8
/ / Lu ,
i ys f (WASTE UNIT NO.1 LINE f oi
/-
/ -4 .t /
l 2 '%wW CONTAINMENT AND U 2 d
/ AUXILIARY f
/
INFORMATION CENTER BUILDING - C f RIVER T 1 (NOT COMPLET ED) INTAKE i C SERVICE WATER IPE N O
\ INTAKE STRUCTURE RIVER N260500
\ WASTEj- ,
DISCHARGE i 1 {--- POINT I RESERVOIR I
/
PROPERTY LINE Figure 5.1-4 Plant Farley Site Map. - Exclusion Area and Liquid Effluents- }} ,] # } l}}