ML19282C227
| ML19282C227 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/15/1979 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7903220256 | |
| Download: ML19282C227 (110) | |
Text
.
BALTIMORE GAS AN D ELECTRIC COMPANY GAS AN D CLECTRIC DUt LDING DALTIMOR E, M ARYLAN D 21203 ARTMun E. LUN ovm,JR.
March 15, 1979 v.c R.,m.,
s-.
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Calvert Cliffs Nuclear Power Plant Unit No. 1 & 2, Docket No. 50-317 & 50-318 10 CFR Part 50, Aprendix I
Reference:
(a) NRC letter dated 11/15/78 from B. K. Grimes to all PWR Licensees, same subject.
(b) NRC letter dated 1/18/79 from B. K. Crimes to all Power Reactor Licensees, Offsite Dose Calculational Manual.
Gentlemen:
Reference (a) forvarded a copy of Revision 1 to NUREG-0472, Draft Radiological Effluent Technical Specifications for PWRc and a copy of NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants and requested that we use those documents as guidance to prepare and submit Technical Specifications applicable to Calvert Cliffs by March 15, 1979 Reference (b) provided general guidelines for the contents of the Offsite Dose Calculational Manual (ODCM), to be included as a supporting part of our Technical Specifications.
Enclosed is a marked-up copy of the Radiological Effluent Technical Specifications as applicable to Calvert Cliffs. Also enclosed is an outline of the proposed contents of the ODCM.
Since Reference (b) was not received until February 2,1979, we vere not able to develop the CDCM in specific detail to include in this submittal.
Pending approval of the enclosed Technical Specifications and the development of tne necessary computer codes, it is our intention to submit the complete CDCM during the period August 1 - December 1, 1979 Please note that Technical Specifications Section 6 is being changed only as pertains to Appendix I and that the remainder should be as presently contained in our license Technical Specifications. Also, para-graphs 3.11.1.h and 3.11.2 7 vill be completed after obtaining the computer codes for the calculations.
79032202%
Page 2 This submittal is intended as a working submittal to develop technical specification requirements. For this reason ve have not put this letter into the normal format for a Request for Amendment.
It is our intention to submit a formal Request for Amendment after we have completed our inhouse review of the hardware modifications required to implement these Technical Specifications and after our Safety Review Co==ittees have completed their reviews of the proposed Technical Specifications. We expect this to be accomplished by April 15, 1979 We have determined that no fee is required pursuant to 10 CFR Part 170 for this submittal.
However, we have not yet made such a determination for our proposed April 15 Request for A=end=ent since the issue is not clear in our minds. We intent to resolve the issue through discussions with the NRC Staff prior to that time.
Very truly yours, f
ll /.
,/'?
(,'
.y <~ -d.. (L. -
N cc - J. A. Biddison, Esquire G. F. Trowbridge, Esquire Mr. E. L. Conner, Jr. - NRC
--..ee
- i.iR EG-047 DRAFT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS FOR F'n'R ':
CALVL'1LT eu fps wei:t e r.1 Cu Lebc, 1970-3 19
1.0 DEFINITIONS 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 parame.ter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and l alam and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
. The CHANNEL CALIBRATION may be perfomed by any series of sequential, over-L lapping or total channel steps such that the entire channel is calibrated.
CllANNEL CHECK l1.10 A CHANNEL CHECK shall be the qualitative assessment of channel be-j havior during operation by observation.. This determination shall include, hwhere possible, comparison of the channel indication and/or status with
- .other indications and/or status derived from independent instrumentation hchannels measuring the same parameter.
CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be:
a.
Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alam and/or trip functions, b.
Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip g
functions.
SOURCE CHECK l
.l.29 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
E lCESS CONTROL PROGRAM 1.30 r AM (PCP) shall be t a or set of operating procedures detailing sampling, analysis, and evaluation within whic ION of ra wastes from liquid equirements of the PCP are provide
- ica-T'JR-STS-1 1-1
1.0 DEFINITIONS (Continued) 3%4aIEICATION 1.31 SOLIDIFICATIO e the conversion of radin'ct+1u wastes from liquid systems to a homogeneous
- ^ -
uistributed), monolithic, immobilized solid wi+6te volum bounded by a stable Sm*= J oistinct outline on all sides (free-stanW OFFSITE DOSE CALCULATION MANUAL (00CM) 1.32 An 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall be a manual contain-ing the methodology and parsneters to be used in the calculation of off-site doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints. Requirements of the ODCM are provided in Specification 6.15.
GASEOUS RADWASTE TREATMENT SYSTEM 1.33 A GASE0US RADWASTE TREATMENT SYSTEM is any system designed and in-stalled to reduce radioactive gaseous effluents by collecting orfmary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
VENTILATION EXHAUST TREATMENT SYSTEM 1.34 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in parti-culate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing fodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents.
Engineered Safety Feature (ESF) abnospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT S'(STEM components.
F,0 :TO 1-2
TABLE 1.2 FREQUENCY NOTATION NOTATION FRE00ENCY 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 per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
SA At least once per 184 days.
R At least once per 18 months.
S/U Prior to each reactor startup.
P Completed Prior to each release.
N.A.
Not applicable.
BA At W m F 24M I'nT,- T -1 1-3
INSTRUMENTATION RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.
APPLICABILITY: As shown in Table 3.3-11.
ACTION:
With a radioactive liquid effluent monitoring instrumentation a.
channel alarm / trip setpoint less conservative than a value which will ensure that the limits of 3.11.1.1 are met, imme-diately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel in-operable.
b.
With one or more radioactive liquid effluent monitoring in-p strumentation channels inoperable, take the ACTION shown in jj Tab 1e 3.3-11.
o" The provisions of Specifications 3.0.3 and 3.0.4 are not c.
appl icabl e.
i.
I!
- SURVEILLANCE RE0VIREMENTS l!
'4.3.3.8.1 The 'setpoints shall be detemined in accordance with procedures as described in the 00CM and shall be recorded in the (station) log.
4.3.3.8.2 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by perfomance of the CHANNEL CHECK, SOURCE CHECX, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-11.
4.3.3.8.3 Records - Auditab'c records shall be maintained, in accordance with procedures in the ODCM, of all radioactive liquid effluent monitoring instrumentation alarm / trip setpoints. Setpoints and setpoint calculations shall be available for review to ensure that the limits of Specification 3.11.1.1 are met.
PWR-STS-1 3/4 3-44
TABLE 3.3-11 T'
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION WT INSTRUMENT OPERABLE APPLICABILITY ACTION 1.
Gross Radioactivity Monitors Providing Automatic Termination of Release a.
Liquid Radwaste Effluent Line (1)
At all tines 18 b.
Steam Generator Blowdown (1)
At all times 19 Effluent Line a.
Turb h Sd1J,is (fwDivits?
-(4-)--
At !! t h
-20 =
EU ps EfHuent-Lin.
R u
[2. 4.a g ladioactivity Monitors Not h inga domatic Termination m
~-
of Release a.
Service Water System Effluent Line At all times 20 b.
Component C Water ystem gr.t.t'i (1)
At al1 times 2(
l r,- accui,uo,y 3,m...
cui.uc.. am-deep Lcd deminuelizu-c. i iter -
se, r.uc.-;,,a 21u,,,
s :r.: n e: -u
,, o u c
, ~. =....
TABLE 3.3-11 (Continued)
?
RADI0 ACTIVE LIQUID EFFLUENT M0flITORING INSTRUMENfATION 3
s MINIMUM b
CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION Flow Rate Measurement Devices **
i a.
Liquid Radwaste Effluent Line (1)
At all times 21 b.
Discharge Canal (1)
At all times 21 c.
Steam Generator Blowdown Effluent (1)
At all times 21 Line
-4.
m
- u w.;ilm, hvi&'T 2
'L pHad.; L C14leentr4ri='"
-(1)-
.h1 L + imm 2 ^, - -
1.
Me- ^^-t; Obde.. CWucut L lx -(l) lu o ! !....~.
-2k u1
, Tank Level Indicating Devices ****
(for tanks outside plant buildings)
_h-l kWT a.
(1)
At all times 22 b.
()"1 df\\/7 (1)
At all times 22 c
c.., _, - r e, - -, :=r-mm.
,g1)
===At*1TT"tifiiB5 "N 2-
~J.
m -
(1)
At -a4-t-imo
~ ~%
~
- Pump curves may be utilized to estimate flow; in such cases, action statement 21 is not required.
- Required only if alarm / trip set point is based on recorder-controller.
- Not required for tanks which have dikes or retention ponds capable of preventing runoff in the event of a tank overflow and have provi: fons for sampling collected liquids and routing them to a liquid radwaste treatment system.
.R T
TABLE 3.3-11 (Continued)
O
{
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS J NSTRUMENT OPERABLE APPLICABILITY ACTION I
- =mg
,.=u-6.
ContinU0 tis 4o site Samplers and
~"_
Sampler Flow ite Effluent Line M F Q all times a.
Steam Generator Blowdown 19
..=.; P p b.
Turbi of-iding Sumps Effluent (1)
At all times 20
! o, Ui"U h
't'C
- Includes rinse, flush, and slurry waste from secondary system condensate deep bed demineralizer or filter-demineralizers.
TABLE 3.3-11 (Continued)
TABLE NOTATION ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be resumed for up to 14 days, provided that prior to initiating a release:
1.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3, and; 2.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valving; Otherwise, suspend release of radioactive effluents via this pa thway.
ACTION 19 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 14 days provided grab samples are analyzed for gross radio a limit of detection of at least 10 pctivity (beta or gamma) at uCi/ gram; 1.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is > 0.01 uCf / gram DOSE EQUIVALENT I-131.
2.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is 10.01 uCi/ gram DOSE EQUIVALENT I-131.
ACTION 20 With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab sanples are collected and analyzed for gross radioactivity (
detection of at least 10 peta or gamma) at a lower limit of uC1/ml.
ACTION 21 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 14 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
ACTION 22 With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 28 dsys provided the tank liquid level is estimated during all liquid additions to the tank.
With the number of channels OPERABLE less than rengisakey"the Mini tmr-Channels.0PERABLE recuiyr,c:::cn, e.'. a ueilt releases via the affected path antinue for up to 14 days provided the gro activity leve ed at least once per rs during actual release.
PWR-STS-1 3/4 3-48
p TABLE 4.3-11 xi RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CilANNEL CilANNEL SOURCE CilANNEL FUNCTIONAL INSTRUMENT CilECK CllECK CALIBRATION TEST 1.
Gross Beta or Gamma Radioactivity Monitors Providing Alarm and Auto-matic Isolation BA[(3)
DA[(1) a.
Liquid Radwaste Effluents Line D*
P b.
Steam Generator Blowdown Effluent D*
M M (3)
Sd/[(1)
Line
-c. LcLS: Silding-(F4eee-Graim)
C' n.(2)
Q(1)
- h;;,a Cff4 vent,-4rine ~
% Gross Beta or Gama Radioactivity NDfr44 Providing Alarm But f)gh w
h Provid atic Isolationt'U a.
Service Water S fluent Line D*
M R(3)
Q(2) b.
Component Cooling System Eff D*
M R(3)
Q(2)
Line 3.
Continuous Composite Samplers and Sample Flow Measurement Device a.
eam Generator B1 wdown Effluent D*
N/A R
Q rbine Building Sumps Effluent D*
N/A R
y TABLE 4.3-11 (Continued)
Ty RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS T
CilANNEL CHANNEL SOURCE CllANNEL FUNCTIONAL INSTRUMENT CllECK CllECK CALIBRATION TEST
% c ivity Recorders (6) a.
Liquid adDtie6E.Q) gent e"
Line
- % _D p AdrA p R
Q b.
Steam Generator Blowdcw N.A. g' % -R w' N. w g Effluent Line D
Q istfia,rge Canal D
N.A.
R fQY5pg Y
//.,TankLevelMonitors(fortanks 8
outside the building) (7) ll-I RWr fEA g'9/1 a.
D* *'
N.A.
6 N ~S lSl4lT Ok*
N.A.
yBg ygg
- c.
D**
N.A.
D y -
d nA +
ti_.1,-
n --
- __q,
/3,FlowRateMonitors a.
Liquid Radwaste Effluent Line D(5)
N.A.
[ OA
[
b.
Steam Generator Blowdown Line U(5)
H.A.
X.88
[
2.
niuharge.canat W-u w;A.
o __
_ _ o,
TABLE 4.3-11 (Continued)
TABLE NOTATION
- During releases via this pathway.
- During liquid additions to the tank.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
The CHANNEL FUNCTIONAL TEST snall also demonstrate that cong om annunciation occurs if any of the following condiff5ns exist:
1.
Inst '
nt indicates measured levelspb al am/ trip setpoint. N 2.
Circuit failure,.
3.
Instrum ndicates a downs' failure.
f
. Anstrument controls not set in opera in (3) The initial CHANNEL CALIBRATION for adioactivity measurement in-strumentation shall be perfomed usi g one or more of the reference standards certified by the Nationa Bureau of Standards or using standards that have been obtained rom suppliers that participate in measurement assurance activities i th NBS.
These standards should pemit calibrating the system its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at in-tervals of at least once per eighteen mohths. This can normally be accomplished during refueling outages.
(Existing plants may sub-stitute previously established calibration procedures for this requirement.)
PWR-STS-1 3/4 3-51
TABLE 4.3-11 (Continued)
(4) This requirement is applicable only to systems where the service water system or component cooling water system is discharged to an effluent stream.
(5) CHANNEL CHECK shalI consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.
(6) This requirement is applicable only to systems where an alarm / trip action is perfonned by recorder-controller instrumentation.
(7) This requirement is not applicable to tanks which have dikes or re-tention ponds capable of preventing runoff in the event of a tank overflow and have provisions for sampling collected liquids and routing them to a liquid radwaste treatment system.b 46 h d kwe b & Pafs 314-Q tk chand
%%d rwF, PWR-STS-1 3/43-5_2
INSTRUMENTATION RADI0 ACTIVE GASE0US PROCESS AND EFFLUENT MPNITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous process and effluent monitoring instru-mentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specifica-tion 3.11.2.1 are not exceeded.
l APPLICABILITY: As shown in Table 3.3-12.
ACTION:
Wi th a radioactive gaseous process or effluent monitoring in-a.
trwnentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of 3.11.2.1 are met, declare the channel inoperable.
b.
With one or more radioactive gaseous process or effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-12.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not i
appl icabl e.
SURVEILLANCE REOUIREMENTS 4.3.3.9.1 The setpoints shall be determined in accordance with procedures as described in the ODCM and shall be recorded,'- tS. (.. u mm', 1 ;; _
f7 I I
' '4.3.3.9.2 Each radioactive gaseous process or effluent monitoring instrumen-itation channel shall be demonstrated OPERABLE by performance of the CHANNEL
' CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST opera-tions during the MODES and at the fr shown in Table 4.3-12.
4.3.3.9.3 Auditable records shall be intained of the calculations made, in accordance with procedures in the of all radioactive process n
and effluent monitoring instrmnentation alarm / trip setpoints.
Setpoints j;and setpoint calculations shall be available for review to ensure that the i limits of Specification 3.11.2.1 are met.
I e
PWR-STS-1 3/4 3-53
TABLE 3.3-12 E
4, RADI0 ACTIVE GASE0US EFFLUEllT M0flITORIllG IllSTRUMENTATION Q
MIllIMUM CilAtlNELS IriSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION 1.
Waste Gas lloldup System a.
Noble Gas Activity Monitor (1)
Radioactivity Rate Measurement 25 1
S R. : -F.2-c=*=idg^
1}
L. ;fy p.u cute or
.3 i
~
tartHdge" n iietrM. C=piev=44ter-
'+)
ved fy preienu o.' inter 2!
o h, % Effluent System Flow Rate (1) w System Flow Rate 26 Measuring Device Measurement w
in E: ;hr-R om4 ate 44easun4 =3 Ill I
Sampjor Finu Pat
~} I p gc ug gu emno n, M Q Gas lloldup System Explosive Gas MonitMn e
systems of ydr osion)
-.. /_
a.
Ilydrogen Monitor
" " ~ *
- Wilydrogen -
29
- b. Il @ ge W en min (1)
% llydrogen or Oxygen
I TABLE 3.3-12 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION kT MINIMUM CilANflELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION 2[.WasteGasHoldupSystemExplosive I
Gas Monitoring System (for systems not designed to withstand the effects of a hydrogen explosion) 2 ll,dccr. : L.,'
u r (2)
=4Miyuro p -
-3fF L b ",dc:;^
- r Oxygen Monitor
=feje l 4,,A c e. :r Oxygen 30 3.
Containment Purge flonitoring System oh 1
c.
"eb!: C=.^.ctiv%y-Nor.i ter (1) t-Rcdivuu in 6y Rote F
4 Measuremenk (n
b.
Iedinc Complcr4 antridgn (1)
'!er.ify-presene; cf 31
+
turtridge
%-+ie"1=+ ' 9 mpler M e-(-!)
'!erifepresenca nf-f'IL.
fr-c R. %, Effluent System Flow Rate (1)
System Flow Rate 26 Measuring Device Measurement c.
C;..v u riuw note neoau,,,,3
(!)
Cc,,71 c F :., m x -
nm.4-- -
nm..-~,,_
o
TABLE 3.3-12 (continued)
RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION
$1 m
,s,
MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION 4,.
E:: 1s 1
a.
Noble Gas Activity Monitcr (1)
Radioactivity Rate Measurement 27 b.
Iodine Sampler Cartridge (1)
Verify presence of cartridge 31 c.
Particulate Sampler Filter (1)
Verify presence of filter 31 w
d.
Effluent System Flow A
Rate Measuring Device (1)
System Flow Rate Measurement 26 7
W ITH CAL'SAAQ SamplerA ow Rate Fl g
e.
"cru m ; M.!::
(1)
Sampler Flow Rate Measurement 26
. Condensei Evacuation System
\\
,f**,./
(b) Ve ' leader System
/'
s (c) Auxiliary iding V ' ilation System (d) Fuel Sto ;sgA ea llding) Ventilation System (e) Rapast rea Ventilation etem K
eam Generator Blowdown Vent S 2 4
TABLE 3.3-12 (Continued)
TABLE NOTATION
- During releases via this pathway.
- During waste gas holdup system operation (treatment for primary system offgases).
ACTION 25 With the number of channels OPERABLE 1ess than required by the j
Minimum Channels OPERABLE requirement, the contents of the tank may be released to the envirorment for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided j
that prior to initiating the release:
i l
1.
At least two independent samples of the tank's contents are analyzed, and 2.
At least two technically qualified members of the Facility Staff independentiy verify the release rate calculations and discharge valve lineup, Otherwise, suspend release of radioactive effluents via i
this pathway.
ACTION 26 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 28 days provided the flow rate is estimated at least once per 4 rM ACTION 27 With the number of channels OPERABLE le
.an required by the j
Minimum Channels OPERABLE requirement, ffluent releases via this pathway may continue for up to 2 days provided grab samples are taken at least once per hours and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 28 (Deleted)
ACTION 29 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the waste gas holdup system may continue for up to 28 days provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within ensuing 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 30 Number of channels OPERABLE one less than rWdy the Mi nimum enaud _ "mf C recd. m..en c, operation of thi s system may cWto 14 h both channels in-Qilh &e, oe in at least HOT STANDBY within om d n u m,-
m,4 m b
Samfle evy w&A m-oPMcC, 6% p s.
PWR-STS-1 3
3-57
TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 31 With the number 6f channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days, provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the end of sample collection.
PWR-STS-1 3/4 3-58
TABLE 4.3-12 I7 RA010 ACTIVE GASEOUS EFFLUENT M0flITORING IllSTRUMEllTATI0fl SURVEILLAtlCE REQUIREMEllTS
' 'i CilANilEL l'
CilAfillEL SOURCE CilANilEL FUNCTI0flAL ItiSTRUMEilT CilECK CllECK CALIBRAT10fl TEST 1.
Waste Gas lloldup System g
a.
Noble Gas Activity Monitor M
/
,5. J d!ra sem,,le, C: 2 3dg:
D'
- /?
- //
?:/A--
Toi ucu saw aangdus -isitu, C-n/l --
- /f
?!/f -
P*
N/A gBA
)[
), / System Effluent Flow Rate Measuring Device Ca..,.le -T :., Pa'a "ne"ria:
P
?!/?
R 2.
Waste Gas llolduo System Explosive y
Gas Monitoring System E
g_
ii;,arage-itenienr r a tnen,t a ni.
- jn q(4)-
d b_
'f;"ir^;;r, "004 tem (+1terna' c }
"n N/f O(4) is
- d. % 0xygen Monitor D**
N/A Q(5)
%Q ovygan Mnaite- (clici..uou) 0--
n/A Q(C)
TABLE 4.3-12 (Continued)
RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
.u f.5 CilANNEL T
CilANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 3.
Containment Purge Vent System
. ':';'. Oas a6iy;y : un ; ou.
-0^
T R(3)
-4(&
- 4. !^d he64410;-
D'
!!/f i;/A
- /A -
tnrticeluce 3 &pici -~
ve ufn r/A "W
((, % System Effluent Flow Rate D*
N/A gBA
)
Measuring Device wh R,1rnn l g u Iltst r Q a t_ p t'ggg g g jis y
_ e.
.;[A U
u
.Davice _
O
TABLE 4.3.12(Continued) 3 RADI0 ACTIVE GASEOUS EFFLUEllT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL SOUP.CE CilANNEL CilAN!!EL FUNCTIONAL INSTRUMENT CHECK CllECK CALIBRATION TEST y
I ldAld t/ CAT t\\EMEll.
4 Emm het sm1~s p
g a.
Noble Gas Activity Monitor D*
M M3)
%2) b.
Iodine Sampler D*
N.A.
N.A.
N.A.
c.
Particulate Sampler D*
N.A.
N.A.
N.A.
ftp#
d.
System Effluent Flow Rate Measurement Device D.*
N.A.
We7W mu B.MTA e.
SamplerAflowRate Sk M- -
-.t n: W D*
N.A.
W W
w b
Condenser Evacuation Syst,
(b) 'Ve leader System, -
(c) Auxiliary
'ng Ventilatio n System (d) Fuel S age A Building) Ventilation System (e) waste Area Ventil stem
) Steam Generator Blowdown Vent'3 m
TABLE 4.3-l' (Continued, TABLE NOTATION
- During releases via this pathway.
- During waste gas holdup system operation (treatnent for primary system offgase s).
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip se tpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control roo alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION for radioactivity measurement in-strunentation shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards should permit calibrating the system over its intended range or' energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at in-tervals of at least once per eighteen months.
This can normally be accompl?shed during refueling outages.
(Existing plants may substi-tute previously established calibration procedures for this requirement.)
PWR-STS-1 3/4 3-62
TABLE 4.3-12 (Continued)
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
1.
One volume percent hydrogen, balance nitrogen; and 2.
Four volume percent hydrogen, balance nitrogen.
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
2E20 1.
4kwa volume percent oxygen, balance nitrogen; and i
2.
Four volume percent oxygen, balance nitrogen.
PWR-STS-1 3/4 3-63
~
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concent-ation of radioactive material released at anytime from the site to unrestricted areas (see Figure 3.11-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolged or entrained noble gases, the concentration shall be limited to 2 x 10- uCi/ml total activity.
APPLICABILITY:
At all times.
ACTION:
With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, immediately restore con-centration within the above limits and provide prompt notification to the Commission pursuant to Specification 6.9.1.12.
SURVEILLANCE RE0VIREMENTS 4.11.1.1.1 The concentration of radioactive material at any time in liquid effluents released from the site shall be continuously monitored in accordance with Table 3.3-11.
4.11.1.1.2 The liquid effluent continuous monitors having provisions for automatic termination of liquid releases, as listed in Table 3.3-11, shall be used to limit the concentration of radioactive material released at any time fran the site to unrestricted areas to the values given in Speci-fication 3.11.1.1.
4.11.1.1.3 The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.11-1.
The results of pre-release analyses shall La used with the calculational methods in the 00CM to assure that the concentration at the point of releas~e is limited to the values in Specification 3.11.1.1.
4.11.1.1.4 Post-release analyses of samples from batch releases shall be performed in accordance with Table 4.11-1.
The results of the post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release are limited to the values in Specification 3.11.1.1.
PWR-STS-1 3/4 11-1
SURVEILLANCE REOUIREMENTS (Continued) 4.11.1.1.5 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 4.11-1.
The results of the analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release are limited to the values in Specification 3.11.1.1.
4.11.1.1.6 Reports. The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1.9.
h PWR-STS-1 3/4' 11-2 j
TABLE 4.11-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit' Liquid Release Type Sampling Minimum Type of Activity of Detection Frequency nnalysis Analysis (LLD)
Frequency (uCi/ml)a P
P b
5 x 10-7 A. Batch Waste Re-Each Batch Each Batch Principa{_ Gamma lease Tankse Emitters I-131 1 x 10-6 P
~
One Batch /M M
Dissolved and 1 x 10-5 Entrained Gases P
H-3 1 x 10-5 Each Batch M
Compositec
-7
' ^ '
70 Sr-89, Sr-90 5 x 10-8 Each Batch Q.
Compositec Fe-55 P-31 1 x 10-6 3
d B.
Plant Continuous Continuous W
Principal Gamma b
d Releases f Composite Emitters 9 5 x 10-7 I-131 1 x 10-6 M
Dissolved and Entrained Gases 1 x 10-5 H-3 1 x 10-5 Continuousd M
d Composite 7
- X^
', a '
'i d
Continuous Q
Sr-89, Sr-90 5 x 10-8 Composited Fe-55 P-3L 1 x 10 -6 3
PWR-STS-1 3f4 11-3
TABLE 4.11-1 (Continued)
TABLE NOTATION h.
The lower limit of detection (LLD) is defined in Table Notation Aof a.
Table 4.131 of Specification 4.12.1...
- 4. It -1
- 4. II,1.l.3.
i l
b.
For certain radionuclides with 1ow gamma yield or 1ow energies or for s
certain radionuclide mixtures, it may not De possible to measure radio-nuclides in concentrations near the LLD.
Under these circumstances, theLLDmaybeincreasedinverp/Iely proportionally to the magnitude of the gamma yield (i.e., 5 x 10-
, where I is the photon abundance expressed as a decimal fraction), but in no case shall the LLD, as l
calculated in this manner for a specific radionuclide, be greater than 10% of the MPC value specified in 10 CFR 20, Appendix B, e
Table II, Column 2.
i A composite sample is one in which the quantity of liquid sampled is c.
proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is repre-j sentative of the liquids released.
e, 1
d.
To be representative of the quantities and concentrations of radio-active materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream.
Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representa-tive of the effluent release.
A batch release is the discharge of liquid wastes of a discrete e.
vol ume.
f.
A continuous release is the discharge of liquid wastes of a non-di screte volume; e.g., from a volume of system that has an input flow during the continuous release.
g.
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean tnat only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, i
together with the above nuclides, shall also be identified and i
reported.
Nuclides which are below the LLD for the analyses should i
not be reported as being present at the LLD level. When unusual circumstances result in LLD's higher than required, the reasons i
shall be documented in the semiannual Radioactive Effluent Release Report.
l i
l PWR-STS-1 3/4 11-4 i
All-i TABLE ~ ~ (Continued)
TABLE NOTATION I
/3, -
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5%
probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (wnich may include radio-chemical separation):
w 2 + 2. 83[S tto.
'I g
E V
- 2. 22. Y - exp(-Mt) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)
CD ud s is the :trd1 : f.
tic.. ' tk background cc..- t'.;, ;t;-
bor of the counth "+^ of a blank sample as appropriate,f-*-
-,...+,7-
,,,g 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 transfomation per minute per picocurie Y is the fractional radiochemical yield (when applicable)
Ais the radioactive decay constant for the particular radionuclide Atis the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of sb used in the calculation of the LLD for a detec-tion system shall be b the background counti ased on the actual obs rved variance of
- t: or of the coun -
~ t: of the blank samples (as appro,priate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclide detamined by gamma-ray spectrometry, the back-ground shall include the typical contributions of other radio-nuclides nomally present in the samples (e.g., potassium-40 in milk samples).
PWR-STS-1 3/4 IZDI 11-4 4
This figure shall consist of a map of the site area showing the unre-stricted area boundary for liquid effluents as defined in 10 CFR Part 20.3(a)(17).
Figure 3.11-1 PWR-STS-I 3/4 11-5
RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas (see Figure 3.11-1) shall be limited:
During any calendar quarter to j 1.5 mrem to the total body a.
and to j 5 mrem to any organ, and b.
During any calendar year to j 3 mren to the total body and to j 10 mrem to any organ.
APPLICABILITY:
At all times.
ACTION:
With the calculated dose from the release of radioactive materials a.
in liquid effluents exceeding any of the above limits, 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 ex-I ceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such re-leases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any orcar
~":f:__~~.,..,...
'l resul ts of rac io10gicaTT_ _ m _
i, we m.; -
__<r irinkins
--_ea gn_d (2Mte-m% vgical impact on
-mpgthP'-aefd to the requireme(it7
- inished drinkin af 40 C afe Drinking Water Act.
(App 1 a f
d auggi, is emim. T< -
J,
, sci;....;
c t - ha ti;)
..m b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e.
SURVEILLANCE REQUIREMENTS 4.11.1.2.1 Dose Calculations.
Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calcu-lation Manual (0DCM) at least once per 31 days.
4.11.1.2.2 Reports.
The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1.9.
PWR-STS-1 3/4 11-6
RADI0 ACTIVE EFFLUENTS LIOUID WASTE TREATFENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE. The system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent releases to unrestricted areas (see Figure 3.11-1) when averaged over 44-fbc uld exceed mrem to the total body or mrem to any organ.
KPPLICABILITY: At all times.
ACTION:
a.
With radioactive liquid waste being discharged without treatment and in excess of the-above lir.its, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of equipment or subsystems not OPERABLE and the reason for inoperability.
2.
Action (s) taken to restore the inoperable equipment to OPERABLE status.
3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.11.1.3.1 Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days.
4.11.1.3.2 The liquid radwaste system shall be demonstrated OPERABLE at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.
PWR-STS-1 3/4 11-7
RADIOACTIVE EFFLUENTS L10UID HOLDUP TANKS LIM! TING CON 0lTION FOR OPERATION 3.11.1.4*
The quantity of radioactive material contained In each of the followingtanksshallbelimitedtof curles, excluding tritium and dissolved or entrained noble gases, (M-l h~f~
a.
b.
L(- L ELp)7" s
IL APPLICABILITY:
At all times.
ACTION:
a.
With the quantity of radioactive material In any of the above listed tanks exceeding'the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hrs either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specifica-tion 6.9.1.12.
The written followup report shall include a schedule and description of activities planned and/or taken to reduce the tank contents to within the above limit, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.1.4 The quantity of radioactivo 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 1
per'%= days when radioactive materials are being added to the tank.
l Mh k[
- 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 drains connected to the liquid radwaste treatment system.
PWR-STS-1 3/4 11 8
RADIOACTIVE EFFLUENTS 3/4.11.2 GASE0US EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate, at'any. time, in the unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
a.
The dose rate limit for noble gases shall be j 500 mrem /yr to the total body and j 3000 mrem /yr to the skin, and b.
The dose rate limit for all radiofodines and for all radioactive materials in particulate form and radionuclides other than noble gases with half lives greater than 8 days shall be j 1500 mrem /yr to any organ.
APPLICABILITY: At all times.
, ACTION:
With the dose rate (s) exceeding the above limits, immediately decrease the release rate to comply with the limit (s) give in Specification 3.11.2.1 i,'and provide pranpt notification to the Commission pursuant to Specifica-i tion 6.9.1.12.
i l SURVEILLANCE REQUIREMENTS U
h 3l4.11.2.1.1 The release rate, at any time, of noble gases in gaseous
- effluents shal.1 be controlled by the offsite dose rate as established above in Specification 3.11.2.1.
4.11.2.1.2 The noble gas effluent continuous monitors having provisions for the gueuuuses tennination of gaseous releases, as listed in Table 3.3-12, g shall be used to limit offsite doses within the values established in Specification 3.11.2.1 when monitor setpoint values are exceeded.
4.11.2.1.3 The release rate af_tadioactive materials, other than cable gases, in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.11-2.
PWR-STS-1 3/4 11-9
SURVEILLANCE RE0UIREMENTS 4.11.2.1.4 The dose rate in unrestricted areas, due to radioactive materi-als other than noble gases released in gaseous effluents, shall be determined to be within the required limits by using the results of the sampling and analysis program, specified in Table 4.11-2, in performing the calculations of dose rate in unrestricted areas.
4.11.2.1.5 Reoorts The ~ semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1.9.
PWR-STS-1 3/4 11-10
TABLE 4.11-2 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM N I " I '"""
Lower Limit of b,
Sampling Analysis Type of Detection (LLD)
Gaseous Release Type Frequency Frequency Activity Analysis (uci/ml)a B
P A.
Waste Gas Storage Each Tank Each Tank P_rincip_al Gamma Emitters 1 x 10-4b Tank Grab Sample 11-3 1 x 10-6 P
P hg I x 10-4b c
B.
Containment Purge Each Purgec Each Purge Principal Gansna Emitters Grab 11 - 3 1 x 10-6 Sample MAf rJ (DJTHEdbEtt 9
-4b C.
" i:t et!= cin Mi>[ [
fif Principal Gansna Emi_tterb
'l x 10 po ts where ga us Grab effl ts are s-Sample 11-3 1 x 10-6 charge r
tiie fa-w2
- cility, air ejecto, stt_
gener-g ator ash ver e-
.--O 9t cent vents,'
_.? M '^- -'~ :ta..-t(
D.
All Release fypes Continuou Wk I-131 1 x 10-12 as listed in A. B, Charcoal C above.
Sample I-133 1 x 10-10 Continuous Wk Particulate PrincipalGanmaEmitterN
-jj Sample _
4! !2?, '"h - d 1 x 10 ContinuouY M
Gross alpha 1 x 10-II Composite Particulate Sample Continuous /
Q Sr-89, Sr-90 1 x 10 '
Composite Particulate Sample l
TABLE 4.11-2 (Continued)
TABLE NOTATION h.
1 The lower limit of detection (LLD) is defined in Table Notation % of a.
Table 4.12 Lof Specification i.12.1.1
& ll-1 6ll.l.l.3, b.
For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the LLD.
Under these circum-stances, the LLD may be increased inversely proportionally to the magnitude of the ga.mna yield (i.e.,1 x 10-4/I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the LLD, as calculated in this manner for a specific radionuclide, be greater than 107, of the MPC value specified in 10 CFR 20, Appendix 8, Table II, Column 1.
Analyses shall also be performed following shutdown, startup, or c.
similar operational. occurrence which could alter the mixture of radtonucl1desvhes D$ht wream wdeouses b reMel,Je exticwed esal to haji befednmed et leas + mepd2&us & rcfeates art g
y fE6WP-d.
Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
Analyses shall also be performed at least once per _24 ho days I
which could leadhutdown, startup or similar4pnrCiuna eAch s occurrence
- to=significan TEs or decreases in radio-iodine releases. Samp changed and analyzed at the intervals in S lons 3.11.2.1 an hs Q-.When samples collecte 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> are analyzed, the correspondingTtD%mq sed by a factor of 10.
I 3i f.
Tritium grab samples shall be taken at least once per k days from the ventilation exhaust from the spent fuel pool area.
g.
The ratio of the sample flow rate to the sampied 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.
h.
The principal gamma emitters for which the LLD specification will
- apply are exclusively _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 emissions. This list 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 reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances resul t in LLD's higher than required, the reasons shall be documented in the semi-annual effluent report.
i PWR-STS-1 3/4 11-12
RADI0 ACTIVE EFFLUENTS DOSE, NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose in unrestricted areas (see Figure 5.1-1) due to noble gases released in gaseous effluents shall be limited to the foll owing:
a.
During any calendar quarter, to j 5 mrad for gamma radiation and j 10 mrad for beta radiation; b.
During any calendar year, to j 10 mrad for gamma radiation and j 20 mrad for beta radiation; t'
t?we==dosa,gie$sian objectives shall be reduced basedg'1f effluent dicted nobre ftr'eleasesJtom the turbinedsTHffng sampling is not-provide'dN'#JEC-<1~eoji1 objectives shall also be reduced b_asedmirTx~;id'cted pufnTtic'cupency%of are e
Tti Visitor centers within the unres g
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Speci-fication 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines 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 subsequent three calendar quarters so that the average dose during these four calendar quarters is within (10) mrad for gamma radiation and (20) mrad for beta radiation.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appl icable.
SURVEILLANCE REOUIREMENTS 4.11.2.2.1 Dose Calculations Cumulative dose contributions frr the total time period shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least ence every 31 days.
4.11.2.2.2 Reports The semiannual Radioactive Effluent Release Reprot shall include the information specified in Specification 6.9.1.9.
PWR-STS-1 3/4 11-13
9 RADI0 ACTIVE EFFLUENTS 9
DOSE, RADI0 IODINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radiofodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas (see Figure 5.1-1) shall be limited to the following:
During any calendar quarter to j 7.5 mrem to any organ; a.
b.
During any calendar year to j 15 mren to any organ; and i
W 5: d:8n ^hf eHva__ thall be ram ^i bem i7n Tiedicted carbon-14 r_eleua-d QiG1Te~fiu'ildinTFehx.;
a m no g k
4#
sampFfmy is not provided.)
APPLICABILITY: At all times.
ACTION:
With the calculated dose from the release of radioiodines, a.
radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission with-in 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, radioactive materials in particu-late form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents during the renainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose canmitment 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 appl icabl e.
SURVEILLANCE RE0UIREMENTS 4.11.2.3.1 Dose Calculations Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM at least once every 31 days.
4.11.2.3.2 Reports The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1.9.
PWR-STS-1 3/4 11-14
RADI0 ACTIVE EFFLUENTS GASE0US RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION r-1 1
s
!3.11.2.4 The gaseous radwaste tr atment system and the ventil ation exhaust
- treatnent system shall be OPERA E.
The gaseous radwaste tre,tment system shall be used to reduce radioa ive materials in gaseous was prior to their discharge when the proj.ted gaseous effluent air dose due te gaseous f effluent releases to unrestr' ted areas (see Figure 5.1-1) en averaged j over 31 days would exceed &E= mrad for gamma radiation and eeds mrad for
' beta radiation and ventilation exhaust treatment system shall be used to
[d the projected doses due to gaseous effluent releases to unrestricted areas. reduc (see Figure 5.1-1) when averaged over 31 days would exceed 4.a mrem to any loman.
g,g
> APPLICABILITY:
At all times, jACTION:
a.
With gaseous waste being discharged for more than 31 days without j
treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information t
1.
Identification of equipment of subsystems not OPERABLE and
[
the reason for inoperability.
j 2.
Action (s) taken to restore the inoperable equipment to OPERABLE STATUS.
I, 3.
Summary description of action (s) taken to prevent a re-
]
currence.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
l
, SURVEILLANCE REQUIREMENTS l
r4.11.2.4.1 Doses due to gaseous releases to unrestricted areas shall be l projected at least once per 31 days.
4.11.2.4.2 The appropriate systems shall be demonstrated OPERABLE at least once per 92 days unless the appropriate system has been utilized to process radioa:tive gaseous effluents during the previous 92 days.
I PWR-STS-1 3/4 11-15
RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.2.5 The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is 1Tmited to < 75 mrem) over a period of 12 consecutive months.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limi ts of Speci fications 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, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose ccmmitnent to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except thyroid, which is limited to < 75 mrem) over 12 consecu-tive months. This Special Report shat 1 include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to pennit releases which exceeds the 40 CFR Part 190 Standard, b.
The provisions of Specification 3.0.3 and 3.0.4 are not appl icable.
SURVEILLANCE REOUIREMENTS 4.11.2.5.1 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifi-catio ns 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. a nd 3.11.2.3.b, and in accordance with the Offsite Dose Calculation Manual (00CM).
4.11.2.5.2 Reports Special Reports shall be submitted as required under Specification 3.11.2.5.a.
PWR-STS-1 3/4 11-16
4JtADI0ACTIVEEFFLUENTS IVE GAS MIXTURE TSystems designed to withstand a hydrogen M osion)
LIMIT ONDITION FOR OPERATION A
'%; oncentration of hydrogen or oxygen ingthe waste gas holdup 3.11.2.6A The system shali be
,f mi ted to <. 41, by yol ume.
f s
APPLICABILITY: At a times.
gh ACTION:
With the concentratiorbgf/ hydrogen or oxygen in the waste gas a.
holdup system exceeding' t%1imit, restore the concentration toWithin limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
The provisions-;o/?
f Speqifications 0
b.
applicabi
,7
\\.3and3.0.4arenot SURVEILLANCE kE0'UIREMENTS 4.11. 2. 6AP he concentration of hydrogen or oxygen in the 5;Ste gas holdup systemf4 hall be determined to be within the above limits by c*o +inuously moni,tiiring the waste gases in the waste gas holdup system with t
. ( hy -
~
' i-cation 3.3.3.9.
Ph'R-ST3-1 3/4 11-17
9 RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Systems not designed to withstand a hydrogen expl osion)
LIMITING CONDITION FOR OPERATION 3.11.2.6/ The concentration of M oxygen in the waste gas holdup system shall be limited to < 2% by volume.
t APPLICABILITY: At all times.
ACTION:
With the concentration of huudumpmenusuWimp oxygen in the waste a.
gas holdup system > 2% by volume but < 4% by volume, restore the concentration of hendessamusedudenPoxygen to within the limit lI 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
With the concentration of "
oxygen in the waste ll gas holdup system > 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentra-tion of bi ;-
oxygen to < 2% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
ll c.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.68 The concentrations of updsesumasageme oxygen in the waste ll gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the hendespammenalsims oxygen monitors required OPERABLE by y
Table 3.3-12 of Specification 3.3.3.9.
PWR-STS-1 3/4 11-18
RADI0 ACTIVE EFFLUENTS GAS STORAGE TANKS LIMITINGCONDITIONFOROPERATIONjja#
3.11.2.7 The quan y of r ioactivity contained in each gas storage tank shall be limited c ries noble gases (considered as Xe-133).
APPLICABILITY:
At imes ACTION:
a.
With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification 6.9.1.12.
The written followup report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.
f b.
The provisions of Specifications 3.0.3 and 3.0.4 are not F
appl icable.
. SURVEILLANCE REQUIREMENTS
!4.11.2.7 The quantity of radioactive material contained in each gas
! storage tank snall be determined to be within the above limit at least R
'once per t%dummes when radioactive materials are being added to the
{ tank.
]
PWR-STS-1 3/4 11-19
RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION 1
I 3.11.3.1 The solid radwaste system shall be OPERABLE and u d to pro-ide for the SOLIDIFICATION of wet solid wastes, for the < IDIFICATION a d packaging of other radioactive wastes, and to ensur[the meeting of the equirenents of 10 CFR Part 20 and of 10 CFR Part f1 prior to ship-ment o efective containers of radioactive wastes fr m the site.
1 APPLICABILI
- At all times.
ACTION:
a.
Wi th he requirements of 10 CFR Par 0,10 CFR Part 71, and the P ESS CONTROL PROGRAM of Spe fication 6.14 not satisfied, suspen shipnents of defective cc iners of solid radioactive wastes rom the site.
b.
With the olid radwaste syst, not OPERABLE for more than 31 days, whe required to mee 10 CFR Part 20 and 10 CFR Part 71, prepare anu submit to the ommission within 30 days, pursuant to Specifica on 6.9.2, Special Report which includes the j
following info tion:
1.
Identification o quipment of subsystems not OPERABLE and
~
the reasons for ido rabili ty.
2.
Action (s) taken rest re the inoperable equipment to OPERABLE statu.
3.
A descript of alternati used for SOLIDIFICATION and packagin of wastes.
4.
Su.. ry description of action (
taken to prevent a re-C' ence.
c.
The rovisions of Specifications 3.0.3 a 3.0.4 are not ap icabic.
SURVEILL CE REOUIREMENTS s
4.
.1.1 The solid radwaste system shall be demonstrated OPE LE at ast once per 92 days, or there be the capability for SOLIDIFICA N of aste by meeting one or more of the conditions below:
PWR-STS-1 3/4 11-20
SURVEILLANCE RE0UIREMENTS (Continued)
/
a.
By performance of functional tests of the ecuipment and J-ponents of the solid radwaste system.
By operating the solid radwaste system at least onca in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM.
c.
Verification of the existence of a valid contract for SOLIDIFI-CATION to be performed in accordance with a PR (SS CONTROL R0 GRAM.
4.11.3.1.2 Th ROCESS CONTROL PROGRAM of Specificat on 6.14 shall be used to verify th SOLIDIFICATION of at least one r,,dresentative test specimen from at lea every tenth batch of each J3pe of wet radioactive waste (e.g., fil ter si ges, spent resins, evaporator bottoms, boric acid solutions, sodium sulfa solutions, and filte[ media).
The test specimens shall be processed in the diochemical or waste processing laboratory in accordance with procedures o the PROCESS TROL PROGRAM.
If any test specimen " fails to verify SOLIDIFICATION, the SOLI-a.
DIFICATION of the ba under test shall be suspended until such time as additiona test sjecimens can be obtained, al-ternative SOLIDIFICATON aram#ters can be detemined in accordance with the PROC S p0NTROL PROGRAM, and a subsequent test verifies SOLIDIFICAT W.
SOLIDIFICATION of the batch may then be resumed using the ternative SOLIDIFICATION parameters determined by the PROCESS /C JTROL PROGRAM.
b.
If the initial testjjiecimen om a batch of waste fails to verify SOLIDIFICATMN, the PROC S CONTROL PROGRAM shall pro-vide for the collfction and testi of representative test specimens from each consecutive batc of the same type of wet waste unt$f' 3 consecutive initial specimens demon-strate SOLIDIFICATION. The PROCESS CONTROL 90 GRAM shall be modified as' required, as provided in Specifica on 6.14, to assure 50tIDIFICATION of subsequent batches of w te.
4.11.3.1.3 Repo s - The semiannual Radioactive Effluent Re ase Report shall include the following information for each type of soli waste shipped offsit6 durins the report period:
/
a.
container volume, b
' total curie quantity (determined by measurement or estimate I
PWR-STS-1 3/4 11-21
SURVEILLANCE REQUIREMENTS (Continued)
~
rincipal radionuclides (determined b
'asurement or es te),
d.
type of waste
., sp resin, compacted dry waste evaporator bottoms type of co taffe[r (e.g., LSA, e.
y Type B, Large Quantity and i
/
f olidification agent (e.g., cement, urea forma de).
PWR-STS-1 3/4 11-22
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be con-ducted as specified in Table 3.12-1.
APPLICABILITY:
At all times.
ACTIOj{:
a.
With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
(Deviations are pennitted from the required sampling schedule if specimens are unobtainable due to hazardcus conditions, M unave'l-ability, or to malfunction of exammmmem sampling equipment.
If the latter, every effort shall be made to complete corrective l
action prior to the end of the next sampling period.)
b.
With the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table 3.12-1 exceeding the limits of Table 6.9-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, envirorrnental factors or other aspects which caused the limits of Table 6.9-2 to be exceeded. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
c.
Wi th milk r-
-' sampl es unavail able from ugP-mhe sample location $ required by Table 3.12-1, prepare and I
submit to the Commission within 30 days, pursuant to Specifi-cation 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies location #for obtaining ~ tir "Y replacement sampies. The 1ocations from which samples were un-available may then be deleted from Table 3.12-1.pungEWI.'{he locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations, if available.
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
PWR-STS-1 3/4 12-1
SURVEILLANCE RE0VIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations shown on Figure 3.12-1 and shall be analyzed pursuant to the requirements of Tabl es 3.12-1 and 4.12-1.
4.12.1.2 Reports - The results of analyses performed on the radio-
~
logical environmental monitoring samples shall be summarized in the Annual Radiological Environmental Operating Report, pursuant to Specification 6.9.1.6.
li lio t
I t
l PWR-STS-1 3/4 12-2
TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I
- o h
Exonsure Pathway Sampling and Type and Frequency y
and/or Sample Sample Locations **
Collection Frequency of Analysis 1.
AIRBORNE
.Fl, I P., L o,,1 L a.
Radioiodine (1]ca tions~1-5)
Continuous operation of Radiciodine canister.
31TU P8Ptf&-
sampler with sample col-Analyze at-least once per Ulatet lection as required by 7 dayr for 1-131. u e *. M y -
dust loading but at least once per M E M Nitc. h.
Particulate sampler.
4. M ( u-u il. ed e s M - 2. A Analyze for gross beta radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> y
following filtiir change.
Perform gamma isotopic g
analysis on each sample 4,
when gross beta activity is
> 10 times the mean of con-trol sample.
Perform ganina isotopic analysis on com-pusite (by location) sample at least once per 92 days..
cd4 v, A s., rgt u t.1 4o v, yd.1. 0, '/
- g. g ig,2/ y'. 7 2 t.x -
v,TM '(,
%e 2.
DIRECT RADIATION At -least once per 31 days.
Ganina dose._2At least once
> E dosimeters.or i-d per-31 days,
_g instrument for con--
tinuously measuring At--least once per 92 days.
~
.and recording dose (Read-out frequencies are Gamma dose. At least once rate at each location.
determined by type of dosi-
.per 92 days.
meters selected.)
- Sample locations are shown on Figure 3.12-1.
n n,\\
( a n k o. 3
, 'i. 5. ( (
2
\\t- \\A-
TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
.u T5 li, d
L Exposure pathway Sampling and Type and Frequency and/or Sample Sample Locations **
Collection Frequency of Analysis 3.
WATERBORNE
?, *:
a.
Surface (Locations 9 and 10)
Composite
- sample collected Ganina isotopic analysis oven.a-period-o f-<-31+ days.
of each com u wt M y ~~
by location.posite sampie Tritium analy-sis of composite sample at least once per 92 days'.r..J i.. A a /
qy a..%.
t
't,>
c,b,.J u g
b.
Ground (Locations 11 and 12)
At least once per 92_ days-Gansna isotopic and tritium
'Vn A -
analyses of each sample.
ML c.
Driaking (Locations 13-15)
Composite
- sample collected.
1-131 analysis of each over a period of 1 14 days, composite sample; if I-131 analysis is per-formed; or and Composite
- sample collected Gross beta and ganyna over a period of 1 31 days'.
isotopic analysis of each composite sample.
Tritium analysis of composite sample at least once per 92 days.
- , L, : >.
>,,. t. h v. '..o. ll d.
Sediment from (tocations: 18):
At least once per 184 days.
Gansna isotopic analysis Shoreline of each sample.
Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- Sample locations are shown on Figure 3.12-1.
l'
- i..* \\,
Lil l i.
U o,
TABLE 3.12-1 (Continued)
RADIOLOGICAL EtiVIRONMEtlTAL M0filTORING PROGRAM o
!5 b,
d.
Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations **
Collection Frequency of Analysis 4.
INGESTI0ft r
t p,,..
a.
Milk t.
t,.
At least once per 15 days Gamma isotopic and 1-131 when animals are on pastures analysis of each sample, at least once per 31 days at other times.
b.
Fish and In-(Locations 21 and 22)
One sample in season, or at Gamma isotopic analysis vertebrates
- ,1 least once per-184 days if on edible portions.
~
not seasonal ~. One sample of each of the following species:
' ' - WC 1.
y
- 2. E l u c t.
4
,,l, m
c.
Food Products At time of harvest. One Gamma isotopic analysis sample of each of the fol-on edible portion.
lowing classes of food products:
1, 2.
g __ _ _. _,
.At time of harvest.
One I-131 analysis.
sample of broad leaf vegetation.
- Sample locations are shown on Figure 3.12-1.
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. m Radiological Environmental Monitoring Sample Locations (Except for those locations subject to change based on unusual census results. ) PWR-STS-1 3/4 12-6
TABLE 3.12-1A LOCATICUS OF ENVIRON'E' ITAL SAFPLIIiG STATIONS FOR THE CALVERT CLIFFS I'UCLEAR POWER PLANT Docket Nos. 50-317/318 DISTANCE
- DIRECTION STATION DESCRIPTION (FEET)
(SECTOR) 2 Chesapeake Country Club 20,000 SSE 5 Ca=p Conoy 3,000 SE 6 Long Beach 15,000 NNW 7 Flant Outfall Area 2,500 NE 8 Plant Intake Area 5,000 E 10 Onsite Well 600 SE 11 On Site 1,300 WNW 12 On Site 1,600 WSW 13 On Site 2,h00 SSF Jk Cultivated Field on Site 17 On Site 1,200 NW 18 On Site 2,000 SE 19 Knotty Pine 8,900 WSW 20 Lusby 9,900 SSW 21 Long Beach 1h,000 NW 22 Cove Point 2h,000 SE 23 Taylor's Island k0,000 ENE 2k On Site 1,800 NW 26 St. Leonard 27,000 NW 27 Solonens 42,000 S 28 Bertha 17,000 S PS Plant Site k,600 NEW Distance measured fro: plant vent. PWR-STS-1 3/4 12 A
)y t r e n d, e 0 mg 5 ik 1 d/ ei SC p ( s t) ct ue dw o, rg c Pk 0 0 / 6 8 di oC op ) F( D L L ( ) 1 N k/ O li I iC T Mp 1 5 5 C ( 1 1 E TE D F ) O te S w T I h g 0 M sk 0 0 "0 0 3 1 I i/ 3 6 3 6 1 L Fi 1 2 1 2 2 C 1 R p E ( 4 W O E L L B E e A H t T T a l R u O c F i ) 2 2 2 t j ra 0 0 0 S aGj 1 1 1 E P 9 U x x x L e A n { 1 7 1 V ro M b U r M i A I XAM ) b 8 0 1 ) 0 b r1 b 0 e/ 4 1 5 0 5 0 5 i ) 5 b ti ( 1 3 1 3 1 1 ac 0 Wp 0 1 0 ( ( 0 S 2 I a s t s i e C a s b o b 7 L y C N 3 l s 0 1 a a s n e 6, n r g B n o M F Z Z 1 4 0 A r H 4 9 8 5 5 3 3 4 g 3 5 5 5 6 9 1 1 1 2{!L wa M4 c
y TABLE 4.12-1 (Continued) TABLE NOTATION The LLD is the smallest concentration of radioactive material a in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurenent system (which may include radio-chemical separation): LLD = 4.66 sb E V 2.22. Y. exp(-Mt) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) is the standard deviation of the background counting rate sb or of the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per transformation) V is. the sample size (in units of mass or volume) 2.22 is the number of transfomation per minute per picocurie Y is the fractional radiochemical yield (when applicable) Ais the radioactive decay constant for the particular ridionuclide ACis the elapsed time between sample collection (or end of the sample collection period) and time of counting of sb used in the calculation of the LLD for a dete tion systen be based on the actual observed var t the background cou ate or of the countin of the blank samples (as appropri ther an unverified theoretically predicted varian culating the LLD for a radionuclide detenni gamma-ray spe, try, the back-ground shall in e typical contributions o radio-nuclide ly present in the samples (e.g., potassium-* ampies). PWR-STS-1 3/4 12-8
^ t TABLE 4.12-1 (Continued) TABLE NOTATION Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fltctuations, unavoidably small sample sizes, the presence of interferring nuclides, or other uncontrollable cir-cunstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report. b LLD for drinking water. LLD for leafy vegetables. c PWR-5lS-1 3/4 12-9
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the loca-tion of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 5.00 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.
(For elevated releases as defined in Regulatory Guide 1.111 March 1976, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.) APPLICABILITY: At all times. ACTION: With a land use census identifying a location (s) which yields a. a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3.1, pre-i pare and subn.it to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new l ocation( s). b. With a land use census identifying a loca* ion (s) which yields a calculated dose or dose commitnent (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 Specification 6.9.2, a Special Report which identifies the new l ocation. The new location shall be added to the radiological environmental monitoring program within 30 days, if possible. The sampling location having the lowest calculated dose or ! se canmittent (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted. c. The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e. SURVEILLANCE REQUIREMENTS 4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and Octcber 1, by door-to-door survey, o R aerial survey, or by consulting local agriculture authorities. 4.12.2.2 Reports - The results of the 'and use census shall be included in the Annual Radiological Environmentai Operating Report.
- Broad lear vegeEation sampling may be performed at the site boundary in the direction sector with the highest 0/Q in lieu of the garden census.
PWR-STS-1 3/4 12-10
B RADIOLOGICAL ENVIRONMENTAL MONITORING l 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION QNof h Ct c % EFA 3.12.3 Analyses shall be performed on radioactive materials supplied as i g part of an Interlaboraboratory. Comparikbn Program which has been approved by NRC. APPLICABILITY: At all times. ACTION: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. b. The provisions of Specification 3.0.3 and 3.0.4 are not appl icabl e. SURVEILLANCE REOUIREMENTS 4.12.3 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radio-logical Environmental Operating Report pursuant to Specification 6.9.1.6. PWR-STS-1 3/4 12-11
INSTRUMENTATION BASES 3/4.3.3.8 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and ccatrol, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. 3/4.3.3.9 RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm / trip 'setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumen-tation also includes provisions for monitoring (and controlling) 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. PWR-STS-1 B 3/4 3-4
3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of 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. This limitation provides addi-tional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1) the .Section II. A design objectives of Appendix I,10 CFR Part 50, to an iindividual and (2) the limits of 10 CFR Part 20.106(e) to the population. !The concentration limit for noble gases is based upon the assumption that i 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. . 3/4.11.1.2 DOSE h This specification is provided to implement the requirements of 4 Sections II. A, III. A and IV. A of Appendix I,10 CFR Part 50. The Limiting Condition. for Operation implements the guides set forth in , Section II.A of Appendix 1. The ACTION statements provide the required operating flexibility 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". ' " -, im T. oo.A. it:; ' O. J.. m s. n y n o w r -Mf:
- ~h^
r y affected by nl ar+
- o.uns, cnere i s
- feason
- able assurance tha+
uon of the facility will not result 'in r @ i t': concentrations in t inisF:_ J.ns.o, ~m um $ ms
- io
-^7 " ^^t: :# 'C L w The dose calculations in ~~m jthe ODCM implement the requirements in Section III. A of Appendix I
- that confonnance with the guides of Appendix I is to be shown by cal-iculational procedures based on models and data such that the actual
'jexposure of an individual through appropriate pathways is unlikely ito be substantially underestimated. The equations specified in the }0DCM for calculating the doses due to the actual release rates of Iradioactive materials in liquid effluents will be consistent with the ' methodology provided in Regulatory Guide 1.109, " Calculation of Annual ! oses to Man from Routine Releases of Reactor Effluents for the Purpose D dof Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision [1, October 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dis-
- ipersion of Effluents from Accidental and Routine Reactor Releases for 9the Purpose of Implementing Appendix I," April 1977.
NUREG-0133 provides Jmethods for dose calculations consistent with '.egulatory Guides 1.109 }' and 1.113. PWR-STS-1 B 3/4 11-1
RADICACTIVE EFFLUENTS BASES This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the IIquid effluents from the shared system are proportioned among the units sharing that system. 3/4.11.1.3 LIOU10 WASTE TREATMENT The OPERABILITY of the IIquid radweste treatment system ensures that this system will be available for use whenever IIquid effluents require treatment prior to release to the environment. The requirements that the appropelate portions of this system be used when specifIed provides assur-ance that the releases of radioactive materials in liquid ef fluents will be kept "as low as is reasonably achievable." This specification Imple-ments the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were spect-fled as a suitable fraction of the guide set forth in Section li.A of Appendix 1,10 CFR Part 50, for liquid ef fluents. 3/4.11.1.4 Ll0Ul0 HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix A, Table 11, Co!umn 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area. 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose rate at any-time at the exclusion area boundary from gaseous ef fluents from all tnits on the site 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 concentrations of 10 CFR Part 20, Appendix B, Table 11. These limits provide reasonable 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 exclusion area boundary, to annual average concentrations exceeding the limits specifled in Appendix 8. Table il of 10 CFR Part 20 (10 CFR Part 20.106(b)). For Individuals who may at times be within the exclusion area boundary, the occupancy of the Individual will be sufficiently low to compensate for PWR-STS-1 B-3/4 11-2
RADI0 ACTIVE EFFLUENTS BASES any increase in the atmospheric diffusion factor above that for the ex-clusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to j (500) mrem / year to the total body or to j C000) mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to j 1500 mrem / year for the nearest cow to the plant. This specification applies to the release of gaseous effluents from all reactors at the site. For units w'th shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system. 3/4.11.2.2 DOSE, NOBLE GASES This specification is provided to implement the requirements of Sections II.8, III. A and IV. A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.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 Appendix I assure that the releases of radio-active material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III. A of Appendix I that confom with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate path-ways is unlikely to be substantially underestimated. The dose calcula-tions established in the ODCM for calculating 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 Compliar.ce 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 determining the air doses at the exclusion area boundary will be 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, RADIOI0 DINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM Ash RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C, III. A and IV. A of Appendix I,10 CFR Part 50. The Limiting PWR-STS-1 B-3/4 11-3
RADI0 ACTIVE EFFLUENTS BASES Conditions for Operation are the guides set forth in Section II.C of I 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 materials in gaseous effluents will ~be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III. A of Appendix I that confom-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 substantially under-estimated. The ODCM calculational methods approved by NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, " Calculating 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 I, October 1977 and Regulatory
} Guide 1.111, " Methods for Estimating At 1pheric Transport and Dispersion ? of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radiofodines, radioactive material in particulate fom and radionuclides other than noble gases are dependent l i 1 on the existing radionuclide pathways to man, in the unrestricted area. i iThe lare: pathways which are examined in the development of these calculations
- 1) individual inhalation of airborne radionuclides, 2) deposition dof radionuclides onto green leafy vegetation with subsequent consumption 1by man, 3) deposition onto grassy areas where milk animals and meat p;;and 4) deposition on the ground with subsequent exposure.of man. p I
3/4.11.2.4 GASE0US WASTE TREATMENT The OPERABILITY of the gaseous radwaste treatment system and the ventila- ~ tion exhaust treatment systems ensures that the systems will be available j [ for use whenever gaseous effluents require treatment prior to release to j the enviroment. The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the i ! releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the [ requirements 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 l i l to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the ' guide set forth in Sections II.8 and II.C of Appendix I,10 CFR Part 50, for gaseous effluents. 'PWR-STS-1 B 3/4 11-4 i
s RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.5 DOSE This specification is provided to meet the reporting requirements of 40 CFR 190. 3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treat-ment system is maintainpd below the flammability limits of hydrogen and oxygen. '"i _.Jontrol features are included in the system Il to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These M control features include isolation ll of the source of hydrogen and/or oxygen, automatic diversion to re-combiners, or injection of dilutants to reduce the concentration below . the flammability limits.) Maintaining the concentration of hydrogen ! and oxygen below their flammability limits provides assurance that j the releases of radioactive materials will be controlled in confomance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. I { 3/.4.11.2.7 GAS STORAGE TANKS I 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 re.. This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure." Mt3 SOLID RADI0 ACTIVE WASTE The TLqff the solid radwaste system ensures that - will be available for u,hm#.enever_ solid radwastesy ~ rocessing and packaging prior to being shippePtrffsit_e._M_ ecification implements the requirements of 10 CFR Part 5 aW%neral Design Criteria 60 of Appendix A to 10 CFR P,ar.t> s' e process parsm'Thused in establish-ing the PROCESS-PROGRAM may include, but are no d to waste type, wa s , waste / liquid / solidification' agent / catalyst r ste nt, waste principal chemical constituents, mixing and curi PWR-STS-1 B 3/4 11-5 t
5 3/4.12 RADIOLOGICAL ENVIRONfENTAL MONITORING q -P BASES y 3/4.12.1 MONITORING PROGRAM o o-The radiological monitoring program required by this specification yd provides measurements of radiation and of radioactive materials in a those exposure pathways and for those radionuclides which lead to the highest potential radiation expsures of individuals resulting from T M the station operation. This monitoring program thereby supplements the 3 radiological effluent monitoring program by verifying that the measur-p 5-+- able concentrations of radioactive materials and levels of radiation are E,- not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The ini-tially specified 4 monitoring program will be effective for at least the first three -yearse of-commercial-operation. Following this period, program changes may be initiated based on operational experience. The detection capabilities required by Table 4.12.-l are state-of-the-art for routine environmental measurements in industrial 1abora-tories. The LLD's for drinking water meet the requirements of 40 CFR 141. 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 modifi-cations to the monitoring program are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways ivia leafy vegetables will be identified and' monitored since a garden of 'this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To detemine this minimum garden size, the following assumptions were used,1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter. 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 measurenents n' radioactive material in environnmental sample matrices are perfomec, i part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. PWR-STS-1 B 3/4 12-1
O l frM8A88MI TECHNICAL SPECIFICATIONS SECTION 6.0 ADMINISTRATIVE CONTROLS ~% A e 4 w ;- ~ p 4 ' cna% u b truc ua, 7 s er nwhb~ ')%in % g W p g Munna p
6.0 ADMINISTRATIVE CONTROLS 1 RESPONSIBILITY 6.1. The (Plant Superintendent) shall be responsible for overall unit eration and shall delegate in writing the succession to this respons ility during this absence. / ./ 6.2 ORGANIZAXION / OFFSITE / 6.2.1 The offsite rganization for unit management and Mchnical support shall be as hown on Figure 6.2-1. / ,l,' ./ UNIT STAFF / J' 6.2.2 The unit organization shall be as shown on Figure 6.2-2 and: / a. Each on duty shift sha be composed ^ of at least the minimum shift crew composition s wn in Tabl e 6.2-1. b. At least one li.:ensed Oper q's all be in the control room when fuel is in the reactor. c-i c. At least two licensed Operators s y be present in the control room during reactor start-upNcheduled reactor shutdown and during recovery from reac trips. d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor ALL CORE ALTERATIONS shall be directly supervisedsby either a e. licensed Senio'r Reactor Operator or Senior ReactorNperator Limited to Fuel Handling who has no other concurrent'r\\ ponsi-es bilities during this operation. \\ f. A site,/ ire Brigade of at least 5 members shall be maintainqd onsitd at all times. The Fire Brigade shall not include (3) menillers of the minimum shift crew necessary for safe shutdow\\ nN o the unit and any personnel required for other essential unctions during a fire emergency. WR-STS-1 6-1
/ / / l / J s l' ,i o / / / / / ,.I / / This figur .all she'w tne organizational structure and lines o esponsibility for the offsite groups that provide echrylcal and management support for the unit. The 'qr'ganizational arrangement for performance and monitoring Quality Assurance activ-Itles should also ie Indicated. / \\ / / i / / Figure 6.2-1 / OFFSITE ORGANIZATION / \\ / 's / \\N \\ \\ PWR-STS-1 6-2
/ J / / / / / l' / This figure shall show the organizational structure and lines \\of responsibility for,the unit staff. Positions tq be staffed by licensed personnel should be indicatedh \\ / / / / \\ ,i l ^ \\\\ g \\ \\N i j Figure ~6.2-2 g / \\ ,/ UNIT ORGANIZATION \\ '\\.. ,/ \\ / PWR-STS-1 6-3
'e TABLE 6.2-1 MINIMUM SHIFT CREW C0! POSITION LICENSE APPLICABLE MODES > CATEGORY / 1, 2, 3 & 4 /5 & 6 SQL l / l*- OL 2 / I \\Non-Licensed 2' I 7 t \\ /
- Doesnotinc\\dethelicensedSeniorReactorOperatororSenior Reactor Operat'& Limited to Fuel Handling, supervising CCRE ALTERATIONS.
/
- Shif t crew ccr position may be less'than the minimum requirements for a period of timehot to excee'd 2 hours in order to accomodate unexpected absence of 'on duty sfilf t crew members provided immediate action is taken to restoge th6 shif t crew ccrnposition to within the minimum reqalrements of Tabis 6.2-1 A
/ \\ / \\ / / //' ./ / / / PWR-STS-1 6-4 \\ s
ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF OUALIFICATIONS Minimum qualifications for members of the unit staff may be specified by use of an overall qualification statement referencing ANSI N18.1-107i or alternately by specifying individual position qualifications. Ge7er-ally, the first method is preferable; however, the second method is adaptable ta those unit staffs requiring special qualification statements because of a unique organizational structure. 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the (Radiation Protection Manager) who shall meet or exceed the quall-fications of Regulatory Guide 1.8, September 1975. 6.4 TRAINING 6.4.1 A retntining and replacement training program for the unit staff shall be maintained under the direction of the (position title) and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55. 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the (position title) and shall meet or exceed the require-ments of Section 27 of the NFPA Code - 1975, except for Fire Brigade training sessions which shall be held at least one per 92 days. 6.5 REVIEW AND AUDIT The method by which independent review and audit of facility operations is accomplished may take one of several forms. The licensee may either assign this function to an organizational unit separate and independent from the group having responsibility for unit operation or may utilize a standing committee composed of individuals from within and outside the licensee's organization. Irrespe Ff5Mhott::stg, the 1icensee shalI specify the details of nctional element proV for the independent review and audit ess as illustrated in the follo example specifications. .5.1 UNIT REVIEW GROUP (URG) Sug;,T.IDy ~~ 6.5.1.1 The (Unit Review Group) shall function to advise the (Plant Superintendent) on all natters related to nuclear safety. PWR-STS-1 6-5
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.1.2 lhe (Unit Review Group) shall be composed of the: Chairman: (Plant Superintendent) Member: (Operations Supervisor) Member: (Tec%ical Supervisor) Member: (Maintenance Supervisor) Member: (Plant Instrument and Control Engineer) Member: (Plant Nuclear Engineer) Member: (Health Physici-st) ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the (URG) Chairman to serve on a temporary basis; however, no more than two
- alternates shall participate as voting members in (URG) activities at
- any one time.
MEETING FREQUENCY 6.5.1.4 The (URG) shall meet at least once per calendar month and as l convened by the (URG) Chaiman or his designated alternate. QUORUM 6.5.1.5 The minimum quorum of the (URG) necessary for the perfomance of the (URG) responsibility and authority provisions of these technical specifications shall consist of the Chaiman or his designated alternate and four members including alternates. RESPONSIBILITIES 6.5.1.6 The (Unit Review Group) shall be responsible for: Reviw of 1) all procedures required by Specification 6.8 and a. changes thereto, 2) any other proposed procedures or changes thereto as detemined by the (Plant Superintendent) to affect nuclear safety. b. Review of all proposed tests and experiments that affect nuclear safety. PWR-STS-1 6-6
ADMINISTRATIVE CONTROLS c. Review of all proposed changes to Appendix "A" Technical Specifications. d. Review of all proposed changes or modifications to unit systems or equipment tha.t affect nuclear. safety. e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the (Superintendent of Power Plants) and to the (Company Nuclear Review and Audit Group). f. Review of events requiring 24 hour written notification to the Commission. g. Review of unit operations to detect potential nuclear safety
- hazards, h.
Performance of special reviews, investigations or analyses and reports thereon as requested by the (Plant Superintendent) or the (Company Nuclear Review and Audit Group). 1. Review of the Security Plan and implementing procedures and shall submit recommended changes to the (Company Nuclear Review and Audit Group). AUTHORITY 6.5.1.7 The (Unit Review Group) shall: a. R? commend to the (Plant Superintendent) written approval or disapproval of items considered under 6.5.1.6(a) through (d) above. b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question. c. Provide written notification within 24 hours to the (Super-intendent of Power Plants) and the (Company Nuclear Review and Audit Group) of disagreement between the (URG) and the (Plant Superintendent); however, the (Plant Superintendent) shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above. PWR-STS-1 6-7
ADMINISTRATIVE CONTROLS RECOROJ 6.5.1.8 The (Unit Review Group) shall maintain written minutes of each (URG) meeting that, at a minimum, document the results of all (URG) activities performed under. the responsibility and authority provisions of these technical specifications. Copies shall be provided to the (Superintendent of Power Plants) and the (Company Nuclear Review and Audit Group) 6.5.2 COMPANY NUCLEAR REVIEW AND AUDIT GROUP ][ FUNCT 3 6.. .he (Company Nuclear Review and Audit Group) shall functi5 to proviae independent review and audit of designated activities in the areas of: a. nuclear power plant operations b. nuclear engineering c. chemistry and radiochemistry d. metallurgy e. instrumentation and control f. radiological safety g. mechanical and electrical engineering h. quality assurance practices 1. (other appropriate fields associated with the unique char-acteristics of the nuclear power plant). PWR-STS-1 6-8
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The (CNRAG) shall be composed of the: Director: (Position Title) Member: (Position Title) Member: (Position Title) Member: (Position Title) Member: (Position Title) ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the (CNRAG) Director to serve on a temporary basis; however, no more than two alternates shall participate as voting members in (CNRAG) activities at any one time. CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the (CNRAG) Director to provide expert advice to the (CNRAG). NEETING FREOUENCY 6.5.2.5 The (CNRAG) shall meet at least once per calendar quarter during the Initial year of unit operation following fuel loading and at least once per six months thereafter. OUORUM 6.5.2.6 The minimum quorum of the (CNRAG) necessary for the performance of the (CNRAG) review and audit functions of these technical specifica-tions shall consist of the Director or his designated alternate and (at least 4 CNRAG) members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility. PWR-STS-1 6-9
A ADMINISTRATIVE CCNTROLS REVIEW 6.5.2.7 The (CNRAG) shall review: A. The safety evaluations for I) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question, b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR. c. Proposed rests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR. d. Proposed changes to Technical Specifications or this Operating License. Violations of codes, regulations, orders, Technical Specifications, e. license requirements, or of Internal procedures or instructions having nuc' ear safety significance. f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety. g. Events requiring 24 hour written notification to the Commission. h. All recognized Indications of an unanticipated deficiency in some aspect of design or operation of stiuctures, systems, or components that coul d af fect nuclear saf ety. I. Reports and meetings minutes of the (Unit Rev'ew Group). PWR-STS-1 6-10
ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizant of the (CNRAG). These audits shall encompass: a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months. b. The performance, training and qualifications of the entire unit staff at least once per 12 months. c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, d. The performance of activities required by the Operations Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months. e. The Emergency Plant and implementing procedures at least once per 24 months. f. The Security Plan and implementing procedures at least once per 24 months. g. Any other area of unit operation considered appropriate by l the (CNRAG) or the (Yice President Operations). i' h. The Fire Protection Program and implementing procedures at least once per 24 months. i. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm. j. An inspection and audit of the fire protection and loss preven-tion program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years. 1. The radiological environmental monitoring program and the results thereof at least once per 12 months. m. The DFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
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m a.ca PWR-STS-1 6-11
ADMINISTRATIVE CONTROLS AUTHORITY 6.5.2.9 The (CNRAG) shall report to and advise the (Vice President Operations) on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8. RECORDS 6.5.2.10 Records of (CNRAG) activities shall be prepared, approved and distributed as indicated below: Minutes of each (CNRAG) meeting shall be prepared, approved a. and forwarded to the (Vice President-Operations) within 14 days following each meeting. b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the (Vice President-Operations) within 14 days following completion of the review. Audit reports encompassed by Section 6.5.2.8 above, shall be c. forwarded to the (Vice Presider:t-Operations) and to the management positions responsible for the areas audited within 30 days after completion of the audit. 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES: The Commission shall be notified and/or a report submitted a. pursuant to the requirements of Specification 6.9. b. Each REPOP. TABLE OCCURRENCE requiring 24 hour notification to the Commisssion shall be reviewed by the (URG) and submitted to the (CNRAG) and the (Superintendent of Power Plants). PWR-STS-1 6-12
ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in i5e event a Safety Limit is violated: a. The unit shall be placed in at least HOT STANDBY withn one hour. b. The Safety Limit violation shall be reported to the Commission, the (Superintendent of Power Plants) and to the (CNRAG) within 24 hours. c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the (URG). This report shal' describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence. d. The Safety Limit Violation Report shall be submitted to r.ne Commission, the (CNRAG) and the (Superintendent of Power P1 ants) within 14 days of the violation. 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main- .tained covering the activities referenced below: a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978. b. The radiological envirorrnental monitoring program. l c. Refueling operations. d. Surveillance and test activities of safety related equipment. l'ij e. Security Plan %plementation. lf f. Emergency Plan implementation. g. Fire Protection Program imple..entation. r T ^ ^ i i, 2. ;..,,.. y '....... _...... ^ " ce" h,# OFFSITE DOSE CALCULA rION MANUAL impiementation. PWR-STS-1 6-13
ADMINISTRATIVE CONTROLS %c h 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the (URG) and appr,oved by the (Plant Superintendent) prior to implementation and reviewed periodically as set forth in administrative-procedures. 621. (1% dLhd -3 m,;- h 16.8.h Tempora y changes to procedures of 6.8.1,above, may be made provided: The intent of the original procedure is not altered. a. b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected. i -c. The change is documented, reviewed by the (URG) and approved by the (Plant Superintendent) within 14 days of implementation. 6,3. 5, (Lu ORMd). i6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES .!6.9.1 In addition to the applicable reporting requirements of Title 10, O Code of Federal Regulations, the following reports shall be submitted , to the Director of the Regional Office of Inspection and Enforcement g unless otherwise noted. , STARTUP REPORT F 6.3. 1 A summe.ry report of plant startup and power escalation testing j shall be submitted following (1) receipt of an operating license, (2) i amendment to the ifcense involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu- . factured by a different fuel supplier, and (4) modifications that may !have significantly altered the nuclear, thermal, or hydraulic perfor- ! mance of the plant. i., 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program land a comparison of these values with design predictions and specifica-l tions. Any corrective actions that were required to obtain satisfactory l operation shall also be described. Any additional specific details i required in license conditicns based on other commitments shall be in- ! cluded in this report. PWR-STS-1 6-14 1
6.8.3. Each procedure of 6.8.1.b above, and changes thereto, shall be reviewed by the Environmental Engineering Section of the Electric Engineering Department and approved by the Chief Environmental Engineer or his designee prior to implementation and reviewed periodically as set forth in administrative procedures. 6.8.5 Terporary changes to procedures of 6.8.1.b above may be cade provided: (a) The intent of the original procedure is not altered (b) The change is approved by the Project Leader (c) The change is documented, reviewed by the Environmental Engineering Section of the Electric Engineering Department and approved by the Chief Environmental Engineer or his designee within ll, days of implementation. f .p gg[SL k" lt ') \\ bk s s
ADMINISTRATIVE CONTROLS 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or cemencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed. 1/ ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality. 6.9.1.5 Reports required on an annual basis shall include: a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving l rem exposure according to work and job functions,_ gated man exposures greater than 100 mrem /yr and their asso e.g., 1 reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions. b. The results of steam generator tube inservice inspections perfomed during the report period. (CE, W & B&W units only). c. The results of the core barrel movement monitoring activities perfomed during the report period. (CE units only). d. ( Any other unit unique reports required on an annual basis.) s 1/A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station. UThis tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20. PWR-STS-1 6-15
9 ADMINISTRATIVE CCNTROLS ANNUAL RADIOLOGICAL ENVIRCNMENTAL OPERATING REPCRT 1! 6.9.1.6 Routine radiological environmental oparating reports cosering T the operation of the unit during the previous calendar year shall be i submitted prior to May I of each year. P; ' c.'
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ter.r,' yr+tn: g 6.9.l.7 The annul radiological environmental operating reports shall 3 include summ5cles, Interpretations, and statistical evaluationTof the ~ results of the radiological environmental surveillance activltles for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental survell-lance repo.-t? and an assessment of the observed impacts of the plant 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 monitorir;g, the report shalI provide an analysis of the problem and a planned course of action to alleviate the problem. The annual radlological environmental operating reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the repo-t, the report shalI be ubmitted 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 including sampling methods for each sample type, sizMphyWM- *m w+eristicszcL each -sample typessa.nple6-preperetka u.omuds, analytical methods, and measuring equip-ment used; a map of all sampling locations keyed to a table giving distances and directions fecm one reactor; the result of land use censuses required by the Specification 3.12.2; and the results of IIconsee perticipation in the Qual 1ty Assursnce Progrem required by SpectfIcation 3.12.3. SEM1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1 6.9.l.8 Routine radioactive effluent release reports covering the operating of the unit during the previous 6 months of operation shalI be submitted within 60 days after January I and July I of each year. The period of the first report shall begin with the data of Initial criticality. 1 A single submittal may be made for a multiple unit station. The submittal should ccabine those sections that are common to all units at the station; however, for units with separate radvaste systems, the submittal shall specify the releases of radioactive material frcm each unit. PWR-STS-1 6-16
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ADMINISTRATIVE CONTROLS 6.9.1.9 The radioactive effluent release reports shall include a ' summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide c 1 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid LWastes and Releases of Radioactive Materials in Liquid and Gaseous c Effluents from Light-Water-Cooled Nuclear Power Plants," with data p summarized on a quarterly basis following the fomat of Appendix B thereof. 4 iThe radioactive effluent release reports shall include a summary of 'the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, ,with data stramarized on a quarterly basis following the fcSat of Appendix B thereof. !The radioactive effluent release reports shall include an assessment of j the radiation doses from radioactive effluents to individuals due to
- their activities inside the unrestricted area boundary (Figure 5.1-1)
' during the report period. All assumptions used in making these
- assessments (e.g., specific activity, exposure time and location) shall be included in these reports.
, The radioactive effluent release reports shall include the following ? infomation for all unplanned releases to unrestricted areas of radio-
- active materials in gaseous and liquid effluents:
a. A description of the event and equipment involved. b j b. Cause(s) for the unplanned release. c. Actions taken to prevent recurrence. d. Consequences of the unplanned release. f The radioactive effluent release reports shall include an assessment of I radiation doses from the radioactive liquid and gaseous effluents i released from the unit during each calendar quarter as outlined in ' Regulatory Guide 1.21. In addition, the unrestricted area boundary f maximum noble gas gamma air and beta air doses shall be evaluated. The
- meteorological conditions concurrent with the releases of effluents shall be used for detemining the gaseous pathway doses.
The assessment of radiation doses shall be perfomed in accordance with the Offsite Dose Calculation Manual (0DCM). The radioactive effluent release reports shall include any changes wm "'::::: ^.L TZ' ' r to the Offsite Dose Calculation Manual (00CM) made during the reporting period, as provided in Specifications 6.14 and } 6.15. PWR-STS-1 6-18 (wubtid N
a ADMINISTRATIVE CONTROLS MONTHLY REACTOR OPERATING REPORT 6.9.l.10 Routine reports of operating statistics and shutdown experience shall be submitted on a morrthly basis to the Director, Of fice of Manage-ment and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office of Inspection and Enforce-ment, no later than the J5th of each month following the calendar month covered by the report. d O D6M) REPORTABLE OCCURRENCES 6.9.l.11 The REPORTABLE OCCURRENCES of Specification 6.9.l.12 and 6.9.l.I3 below, including corrective actions and measures to prevent recurrence, shalI be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a license event report shall be com-pleted and reference shalI be made to the original report date. PROWT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.l.12 The types of events listed below shall be reported within 24 hours by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, wita a written followup report within 14 days. The written followup report shall in-ciude, as a minimum a completed copy of a license event report form. Information provided on 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, Failure of the reactor protection system or other systems, a. subject to limiting safety system settings to initiate the required protective functio.n by the time a monitored para-meter reaches the setpoint specified as the limiting safety system setting in the technical specifications of failure to complete the required protective function. b. Operation of the unit or affected systems when any parameter or operation subject to a Ilmiting condition for operation is less conservative than the least conservative aspect of the 1imitIng condition for operation estabIished in the technical specifications. c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment. I g ll Y PWR-STS-1 6-19
ADMINISTRATIVE CONTROLS d. Reactivity anomalles involving disagreement with the predicted value of reactivity balance under steady state conditions dur-Ing power operation greater than or equal to 1%4Sk/k; a cal-culated reactivity balance Indicating a SHUTDOWN MARGIN less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if suberitical, an unplanned reactivity insertion of more than 0.55ssk/k; or occurrence of any unplanned criticality. Failure or malfunction of one or more components which prevents e. or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the SAR. f. Personnel error or procedural Inadequacy which prevents or could prevent, by itself, the fulfillment of the functional require-ments of systems required to cope with accidents analyzed in the SAR. g. Conditions arising from natural of man-made events that, as a direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by techni-cal specifications. h. Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report er in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses. I. Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyss in the safety analysis report or technical specification bases; or discovery during unit life of conditions not specifically considered in 6no safety analysis report or technical specifica-tions that requice cemndial action or corrective measures to prevent the existence or development of an unsafe condition. J. Occurrence of an unusua; er important event that causes a algnificant environmental Impact, that af fects potential en-vironmental Impact from unit operation, or that has high public or potential public interest.concerning environmental Impact from unit operation. k. Occurrence of radioactive material contained in liquid or gaseous holdup tanks In excess of that permitted by the limiting condi-tion for operation established in the technical specifications. PWR-STS-1 6-20
i N ADMINISTRATIVE CONTROLS THIRTY DAY . TEN REPORTS 6.9.l.13 The types of events listed below shall be the subject of wr i rtan orts to the Direct e of the Regional Office within thirty dayr .;currence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Informa-tion provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explana-tion of the circumstances surrounding the event. a. Reactor protection system or engineered safety feature In-strument settings which are found to be less conservative than those established by the 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 permitted by a limiting co'dition for operation or plant shutdown re-quired by a limiting condition for operation. c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to,cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems, d. Abnormal degradation of systems other than those specified in 6.9.l.12.c above designed to contain radioactive material resulting from the fission process. e. An unplanned offsite release of !) more than I curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous ef fluents, or 3) more than 0.05 curies of radiolodine in gaseous effluents. The report of an unplanned offs!te release of radioactive material shall include the following information: 1. A description of the event and equipment involved. 2. Cause(s) for the unplanned relcese. 3. Actions taken to prevent recurrence. 4. Consequences of the unplanned release. PWR-STS-1 6-21
ADMINISTRATIVE CONTROLS o) .S f. Measured levels of radioactivity in an environmental sampling T' medium determined to exceed the reporting level values of + Table 6.9-2 when averaged over any calendar quarter sampling o period. When more than one of the radionuclides in Table 6.9-2 are detected in the sampling medium, this report shall be sub-.d mitted if: ,1 concentration (1) concentration (2) limit level (1) + limit level (2) +.. Q l.0 3 When radionuclides other than those in Table 6.9-2 are detected h and are the result of plant effluents, this report shall be y submitted if the potential annual _ dose _to_an individualis equal to or greater than the' calendar year limits of Specifica-tions 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; however, in such an event, the con-dition shall be reported and describec' in the Annual Radiological Environmental Operating Report. SPECIAL REPORTS Special reports may be required covering inspections, test and maintenance activities. These special reports are determined on an individual basis for each unit and their preparation and submittal are designated in the Technical Specifications. 6.9.2 Special reports shall be submitted to tne Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. PWR-STS-1 6-22 4
F TABLE 6.9-2 l REPORTING LEVELS FOR RA010 ACTIVITY CONCENTRATIONS IN ENVIR0faiENTAL SAMPLES $1 Reporting Levels Water Airborne Particulate Fish Hilk Vegetables Analysis (pCi/1) or Gases (pC1/m ) (pC1/Kg, wet) (pC1/1) (pC1/Kg. wet) 3 4 11 - 3 3 x 10 3 4 Hn-54 1 x 10 3 x 10 2 4 Fe-59 4 x 10 1 x 10 4 Co-58 1 x 10 3 x 10 2 4 ? Co-60 3 x 10 1 x 10 2 4 Zn-65 3 x 10 2 x 10 2' Zr-Nb-95 4 x 10 2 I-131 2 0.9 3 1 x 10 3 3 Cs-134 30 10 1 x 10 60 1 x 10 3 3 Cs-137 50 20 2 x 10 70 2 x 10 2 2 Ba-La-140 2 x 10 3 x 10
ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indication. 6.10.1 The following records shall be retained for at least five years: a. Records and logs of unit operation covering time interval at each power level. b. Records and logs of principal maintenance activities, inspec-tions, repair and replacement or principal items of equipment related to nuclear safety. c. ALL REPORTABLE OCCURRENCES submitted to the Commission. d. Records of surveillance activities, inspections and cali-brations required by these Technical Specifications. Records of changes made to the procedures required by e. Specification 6.8.1. f. Records of radioactive shipments. g. Records of sealed source and fission detector leak tests and resul ts. h. Records of annual physical inventory of all sealed source material of record. 6.10.2 The following records shall be retained for the duration of the Unit Operating License: Records and drawing changes reflecting unit design modificc-a. tions made to systems and equipment described in the Final Safety Analysis Report. b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories. Records of radiation exposure for all individuals entering c. radiation control areas. d. Records of gaseous and liquid radioactive material released to the environ. PWR-STS-1 6-24 A
ADMINISTRATIVE CONTROLS e. Records of transient of operational cycles for those unit com-ponents identif ied in Tab le 5.7-l. f. Records of reactor tests and experiments. g. Records of training and qualfication for current members of the unit staff. h. Records of in-service inspections performed pursuant to these Technical Specifications. I. Records of Quality Assurance activities required by the OA Manual. J. 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 (URG) and the (CNRAG). 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirments 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 (OPTIONAL) 6.12.1 in lieu of the " control device" of " alarm 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 in-dividuals permitted to enter such areas shall be provided with or accompanied by ons or more the following: a. A radiation monitoring device which continuously Indicates the radiation dose rate in the area.
- Health Physics personnel or personnel escorted by Health Physics per-sonnel in accordance with approved emergency procedures shall be exempt from the RWP issuance requirement during the performance of their radla-tion protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
PWR-STS-1 6-25
ADMINISTRATIVE CONTROLS b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the ar'a has been established and personnel have been made knowl-edgeable of them. c. An individual qualified in radiation protection pracedures who is equipped with a radiation dose rate monitorir, device. This individual shall be responsible for proviaing positive control over the activities within the area and shall perform periodic radiation surveillar:ce at the frequency specified by the facility Health Physicist in the Radiation Work Permit. 6.12.2 The requirements of 6.12.1, above, also apply to each high radia-jtion area in which the intensity of radiation is greater than 1000 mrem /hr. djin addition, locked doors shall be provided to prevent unauthori into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist. t o
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i 'BWR-STS-1 6-26 J
ADMINISTRATIVE CONTROLS enmuu 6 PROCESS CONTROL PROGRAM (PCP) FUNCT 0N 6.14.. The PCP shall be a manual containing the equipment ope ting pro-cedur , process parameters, set points, drawings and controls and the labora ry procedures detailing the progran of sampling, anal sis, and eval ua ti within which solidification of radioactive wastes rom liquid systems i ured, consistent with Specification 3.11.3.1 d the sur-veillance requi ts of these Technical Specifications. The PCP shall be submit to the Commission at the tJMe of proposed Radio-logical Effluent Technical Specifications and shall/ tie subject to review and approval by the Commiss on prior to implementa ' ion. 6.14.2 Changes to the PCP s all be made by either of the following methods: A. Licensee initiated anges: 1. Shall be submitt to the Commission by inclu f on in the l [ semiannual Radica tive Efflue t Release Report for the 3 l )- period in which th change (s) was made and shall contain: f! a. sufficiently deta ed ip*fomation to totally support ( ti the rationale for t lange without benefit of addi-l tional or supp 1 omation; i b. a determination that the chan did not reduce the i overall coq %mance of the solid ied waste product to existi g criteria for solid was s; and c. documen. tion of the fact that the c nge has been ll reviewe'd and found acceptable by the RG). i / l i 2. Shall become effective upon review and acc tance by the j i (URG), u'nless otherwise acted upon by the C mmission through t writt notification to the licensee. B. Commissicm initiated changes: 1. 1 be determined by the (URG) to be applica le to the acility after consideration of facility design 2. The licensee shall provide the Commission with wr1 _n notification of their detennination of applicability cluding any necessary revisions to reflect facility desi s l 3. Shall be reviewed by the (CNRAG) at its riext regularly scheduled meeting. PWR-STS-1 6-27
ADMINISTRATIVE CONTROLS 6. OFFSITE DOSE CALCULATION MANUAL (0DCM) FUNCTION l 6. 1 The ODCM shall describe the methodology and parameters to be u ed I in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alam/ trip setpoints consistent with the applicable LCO's contained in these Technical Specifications. Methodologies and calcula-tional procedures acceptable to the Commission are contained in NUREG-0133. The ODCM shall be submitted to the Commission at the time of proposed Radio-logical Effluent Technical Specifications and shall be subject to review and apprcval by the Commission prior to implementation. 6. 2 Any changes to the ODCM shall be made by either of the following methods: l A. Licensee initiated changes: 1 Shall be submitted to the Commission by inclusion in the semi-t annual Effluent Release Report for the period in which the I h change (s) was made and shall contain: sufficiently detailed infomation to totally support the a. 3: rationale for the change without benefit of additional l or supplemental infomation. Infomation submitted should ) I consist of a package of those pages of the ODCM to be j changed with each page numbered and provided with an 8 s approval and date box, together with appropriate analyses or evaluations justifying the change (s);. i b. a detemination that the change will not reduce the i accuracy or reliability of dose calculations or setpoint deteminations; and l documentation of the fact that the change has been c. ' reviewed and found acceptable by both the (URG) and l NCNRAG).
- 2. fShall Decome effective upon review and acceptance by both b 3
the (URG) and (CNRAG). j I \\ ) i B. Commission initiated changes. 1. Shall be detemined by the (URG) to be applicable to the facility after consideration of facility design. i l PWR-STS-1 6-28 \\\\ (
ADMINISTRATIVE CONTROLS 2. The licensee shall provide the Commission with written noti-fication of their detemination of applicability including any necessary revisions to reflect facility design. 3. Shall be reviewed by the (CNRAG) at its next regularly scheduled meeting. h~ ~ (uhr m. C+9 usc Poac b)/LAli h O ((I?-C PWR-STS-1 6-29
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