ML20078K764
| ML20078K764 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/17/1994 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20078K763 | List: |
| References | |
| NUDOCS 9411250184 | |
| Download: ML20078K764 (25) | |
Text
..
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ATTACHMENT 2 -
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 Docket Nos. 50-277 50-278 License Nos. DPR-44 DPR-56 Facility Operating License Change Request 93-13
' Main Stack and Vent Stack Radiation Monitoring System Upgrades" List of Revised Pages Unn2 Unn3 59 59 75 75 77a 77a 84 84 86a 86a 93 93 97 97 210 210 211 211
+
212 212 213 213 216c-1 216c-1 9411250184 941117 PDR ADOCK 05000277 i
p PDR J
Unit 2
~
PBAPS T.%
SURVEILLANCE REOUIREMENTS C LIMITING' CONDITIONS FOR OPERATION 3. 2'. D.
Radiation Monitorinc 4.2.D.
Radiation Monitorina Systems-Isolation and Systems-Isolation and Initiation Functions Initiation Functions 1.
Reactor Buildina Isolation 1.
Reactor Buildina Isolation and Standbv Gas Treatment and Standby Gas Treatment System System Instrumentation shall be The limiting conditions functionally tested, cali-for operation are given in brated and checked as indi-Table 3.2.D.
cated in Table 4.2.D.
\\s.. Main Control Room System logic shall be functionally tested as The limiting conditions for indicated in Table 4.2.D.
operation are given in Table 3.2.D.
2.
Main Control Room E.
Drvwell Leak Detection Instrumentation shall be functionally tested, The limiting conditions of calibrated and checked as operation for the instru-indicated in Table 4.2.D.
mentation that monitors drywell leak detection are
~^
E.
Drvwell Leak Detection given in Section 3.6.C, M
" Coolant Leakage".
Instrumentation shall be calibrated and checked as indicated in table 4.2.E.
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Amendment No. 102. I60.184 "ais G
.I
Unit 3 PBAPS L.
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.2.D.
Radiation Monitorinc 4.2.D.
Radiation Monitorina Evstems-Isolation and Systems-Isolation and Initiation Functions Initiation Functions 1.
Reactor Buildina Isolation 1.
Reactor Buildinc Isolation and Standby Gas Treatment and Standby Gas Treatment System System The limiting conditions Instrumentation shall be for operation are given in functionally tested, cali-brated and checked as indi-Table 3.2.D.
cated in Table 4.2.D.
2.
Main Control Room System logic shall be The limiting conditions for functionally tested as indicated in Table 4.2.D.
operation are given in Table 3.2.D.
2.
Main Control Room E.
Drywell Leak Detection Instrumentation shall be The limiting conditions of functionally tested, calibrated and checked as operation for the instru-mentation that monitors indicated in Table 4.2.D.
d drywell leak detection are E.
Drvwell Leak Detection given in Section 3.6.C,
" Coolant Leakage".
Instrumentation shall be calibrated and checked as indicated in table 4.2,.E.
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f1le 8 2 d in w' Amendment No. 104, 162. 189 MAY 0 6 UM
(
i Unit 2 PBAPS TABLE 3.2.D RADIATION MONITORING SYSTEMS TilAT INITIATE AND/OR ISOLATE SYSTEMS Minimum No.
of Operable No. of Instrument f
Instrument Channels Provided Action Channels per tem Trip Function Trip Level Setting by Design
-(2) g Trip 2
Refuel Area Exhaust Upscale, <16 mr/hr 4 Inst. Channels A.or B Monitor Jmt shell. NrNe Ga5 2
" * "i-ng-Upscale, <16 mr/hr 4 Inst. Channels B
-Exhauct-Monitors NAle Gas 1
(3)
Main Stack Monitors Upscale,h0'cph 2 Inst. Channels C-g
& 1.0nso- % C</cc.
i 2
(4)
Main Control Room Upscale, <400 cpm 4 Inst. Channels D
Ml Notes for Table 3.2.D
- 1. Whenever the systems are required to be operable, the specified number of instrument channels If this cannot be met, the indicated shall be operable or placed in the tripped condition.
action shall be taken.
- 2. Action 8
Cease operation of the refueling equipment.
Isolate secondary containment and start the standby gas treatment system.
g A.
and close vent and purge valves greater than 2 inches g
B. Cease purging of primary containment, g
C.
in diameter.
3 D. As described in LCO 3.11.A.5' 5) trip function is required to be operable only when the containment is purging through the SGTS and containment integrity is-required.
If both radiation monitors are out of service, 3.
The action shall be taken as indicate'd in Hote'2, (C).
The trip function is required to be operable whenever secondary containment is required on 4.
(/
either unit.
f ;h
[ $
t Unit 3 PBAPS TABLE 3.2.D RADIATION MONITORING SYSTEMS TilAT INITIATE AND/OR ISOLATE SYSTEMS Minimum No.
of Operable No. of Instrument Instrument Channels Provided Action Channels per Trip System Trip Function Trip Level Setting
-by Design (2)
(1) 2 Refuel Area Exhaust Upscale, <16 mr/hr 4 Inst. Channels A or B Monitor t/ed.5+ sed A/.0 Ga S 2
n:csts 0.1101..y Upscale, <16 mr/hr 4 Inst. Channels D
E:6 r t-Monitors yr 3
paleGas y --
1 (3)
Main Stack ^ Monitors Upscale,($10' cps s 2 Inst. Channels C'
f l.cmo s ce/cc
,r 2
(4)
Main Control Room Upacale, <400 cpm 4 Inst. Channels D
{b Notes for Table 3.2.D
- 1. Whe iver the systems are required to be operable, the specified number of instrument channels If this cannot be met, the indicated shazi be operable or placed in the tripped condition.
action shall be taken.
>g
- 2. Actic 5
Cease operation of the refueling equipment.
g A. Isolate secondary containment and start the standby gas treatment system.
C. Cease purging of primary containment, and close vent and purge valves greater than 2 inches 3
D.
z
.o in diameter.
D. As described in LCO 3.11.A.5 m
The trip function is required to be operable only when the containment is. purging through the I
?it ?
SGTS and containment integrity in-required.
If both radiation monitors are out of service, 3.
O action shall be taken as indicated in Note 2, (C).
5."f
- 4. The trip function is required to be operable whenever secondary containment is required on E:
()
either unit.
L' TABLE 3.2.F (Cont'd)
,'fCtVEILLANCE INSTRUMENTATION
(['
l Minimum No.
of Operable Typ.
Instrument Indication item Channels Parameter Instrument and Range Action
- 11 2
Suppression Chamber LR-8(9)123A, B Recorder 1-21 ft.
(10) (11)
Water Level (wide range) 12 1
Control Rod Position N/A 28 Volt Indicating )
Lights
)
(1) (2) (3) (4)
)
13 1
Neutron Monitoring N/A SRM, IRM, LPRM,
)
0-100%
)
14 1
Safety-Relief Valve P0AM-2(3)-2-71A-L Acoustic or (5)
Position Indication TE-2(3)-2-Il3A-L Thermocouple 15 2
Drywell liigh RR-8(9)l03A, B Recorder 1-lE(+8) R/hr (7)
Range Radiation Monitors Wucle e
d 16 1
Main Stack 4Hgh-Range 6ss RR-0-17-051 6 Regorder 5
'T Radiation Monitor 10 to 10 C"S / cx /c y* / # ^ '
"6#/ (7) 11 e_.i_s W4 Sktl UYe A"y' k5 g
17 1
"crte" ""Dd!:; ";;f -
RR-2979s (L'M t 2)
Regorder C""- / c^ m-% / o **b 6'/-
(7) 13
--!;,t ll';h ": ;; Radiation
"" 2070 ("o;; ; }-
- 10 to 10 Monitor (L ; n
)_
18 2
Drywell flydrogen 2(3)AC872, 2(3)BC872 Analyzer and Recorder
.(13)
Concentration Analyzer XR-8(9)0411A, 0-30% volume and Monitor XR-8(9)04118 19 2
Suppression Chamber 2(3)AC872,2(3)BC872 Analyzer and Recorder (13)
Hydrogen Concentration XR-8(9)0411A, 0-30% volume Analyzer and Monitor XR-8(9)04110
- Notes for Table 3.2.F appear on pages 78 and 78a.0-E 8CT 3 set w
Amendment No, 113, 128, 189, 193
TABLE 3.2.F (Cont'd) d ["rlttANCE INSTRUMENTATION tjI Mini' mum Ho.
- i. of Operable Type Instrument Indication item Channels Parameter Instrument and Range Action
- 11
.2 Suppression Chamber LP,-8(9)123A, B Recorder 1-21 ft.
(10) (11)
Water Level (wide range)
Control Rod Position N/A 28 Volt Indicating )
12 1
.c Lights
)
(1) (2) (3) (4)
)
13 1
Neutr'on Monitoring N/A SRM, IRM, LPRM,
)
0-100%
)
m 14 1
Safety-Relief Valve P0AM-2(3)-2-71A-L Acoustic or (5)
Position Indication TE-2(3)-2-113A-L Thermocouple 15 2
Drywell liigh RR-8(9)l03A,B Recorder Range Radiation lE(48) R/hr (7)
Monitors 'g
.L 16 1
Main Stack-H4 W Range RR-0-17-OSI B Regorder 11 Radiation Monitor 10 ts 10 073
-74g,yw6a/cc (7) f, g t/m+SLk tunde %ye_ Gas EL;S
- I
- 5 17 1
D-M' a- ""DH ; t;f
"" 2"" (Ca l t ^)
Regorder
- " 0; "I3 C':: / #2.7* S#" r,g/cc (7) vo.* usp orn;; Radiation RR-3979g(U.,it3)
Monitor (L:; n;;;;
18 2
Drywell Hydogen 2(3)AC872, 2(3)DC072 Analyzer and Recorder (13)
Concentration: Analyzer XR-8(9)0411A, 0-30% volume and Monitor:
XR-8(9)D411B Suppression [ Chamber 2(3)AC872,2(3)8C872 Analyzer and Recorder (13) 19 2
Ilydrogen Concentration XR-8(9)0411A, 0-30% volume Analyzer and Monitor XR-8(9)04118
- Notes for Table 3.2.F appear on pages 78 and 78a.?
8-s Amendment No. II7, 131, 189, IH, 197 SCT 3 1994 n
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11 Qdat 2
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PBAPS TABLE 4.2.D MINIMUM TEST & CALIBRATION FREOUENCY FOR RADIATION MONITORING SYSTEMS Instrument Instrument Functional Instrument Channels Test Calibration Check (2) 1)
Refuel Area Exhaust (1)
Once/3 months once/ day Monitors - Upscale 2)
Reactor Building Area (1)
Once/3 months Once/ day
[b d
Ab e 6*5 3)
Main Stack Monitor 3 Once/3 months Once
, months once/ day 3
as described in g,
4.8.C.4.a p
4)
Main Control Room Once/3 months Once/18 months Once/ day as described in I
4.11.A.5
)
Locic System Functional Test (4)
'(6)
Frecuency
?
5 1)
Reactor Building Isolation Once/ Operating Cycle R
Once/ Operating Cycle S
2)
Standby Gas Treatment System Actuation z
?
1 E."
a b4
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' 1.
l S'
l
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Unit 3 -
PBAPS TABLE 4.2.D MINIMUM TEST & CALIBRATION FREOUENCY FOR RADIATION MONITORING SYSTEMS Instrument Instrument Functional Calibration Check (2)
Instrument Channels Test 1)
Refuel Area Exhaust (1)
Once/3 months once/ day Monitors - Upscale 2)
Reactor Building Area (1)
Once/3 months once/ day 18
.rtble Gas 3)
Main Stack ^ Monitor s Once/3 months Once/JE months once/ day as described in 4
4.8.C.4.a y
l
, 4)' Main Control Room Once/3 months Once/18 months once/ day as described in l
4.11.A.5 Ei Loaic System Functional Test (4)
(6)
Frequency m
M 5
1)
Reactor Building Isolation Once/ Operating Cycle Once/ Operating Cycle 2)
Standby Gas Treatment System Actuation E
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. li
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s TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION Instrument Cbannel Calibration Frequency Instrument Check 10)
Drywell liigh Range Radiation Monitors Once/ operating cycle **
Once/ month
. unds 19)
Main Stack-H4gh-Range Gc~s once/ eighteen months Once/;;;th Da/
RadiationMonJtor Y((c 7
.o
";;Uf-Once/ eighteen months Once/ ;;th daf 20) lliy. "oagt Radiation Monitor 21)
Drywell and Suppre~ssion Chamber flydrogen Quarterly ***
Once/ month I
Concentration Analyzer and Monitor Perform instrument functional check once per operating cycle.
Channel calibration shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10R/hr and a one point calibration check of the detector below 10R/hr with an installed or portable gamma source.
At least a two-point calibration using sample gas.
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TABLE 4.2.F HINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION Instrument Channel Calibration Frequency Instrument Check 18)
Drywell liigh Range. Radiation Monitors once/ operating cycle **
Once/ month wucle Main Stack +14 tr Range Gas Once/ eighteen months Once/menth-bay 19) 9 Radiation Monitor.
ve,+.S+ncK onde Ra-20)
":::tc. '"d;. ": f Lye Gas Once/elghteen months Once/ =.th hof at
"!;h ".;;.;; Radiation Monitor 21)
Drywell and Suppression Chamber flydrogen Quarterly ***
Once/ month
(
Concentration Analyzer and Monitor g
Perform instrument functional check once per operating cycle.
Channel calibratlob shall consist of an electronic calibration of the f
channel, not including the detector, for range decades above 10R/hr and a one point calibration check of the detector below 10R/hr with an installed or portable gamma source.
At least a two-poi t calibration using sample gas.
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a m-
eamw 3 PBAPS 3.2 BASES (Cont'd) f
~
Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of the standby gas treatment system.
Four instrument channels monitor f~ ~ '
the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor.
Each set of instrument channels is arranged in a 1 out of 2 twice trip logic.
i Trip settings of less than 16 mr/hr for the monitors in the refueling area ventilation exhaust ducts are based upon ini-tiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reactor B,uilding via the normal ventilation path but rather all the activity is processed by the standby gas treatment system.
Two channels of nonsafety-related radiation monitors are provided in the main stack.
Trip signals from these monitors are required only when purging the containment through the SGTS and c'ontainment integrity is required.
The trip signals isolate pri-mary containment vent and purge valves greater than 2 inches in diameter to prevent accidental releases of radioactivity offsite when the valves are open.
This signal is added to fulfill the requirements of item II.E.4.2 (7) of NUREG-0737.
Four channels of in-duct radiation monitors are provided which initiate the Main Control Room Emergency Ventilation System.
Each set of instrument channels are arranged in a one (1) out of two (2) twice trip logic.
Flow integrators are used to record the integrated ficw of liquid from the drywell sumps.
The integrated flow is indica-tive of reactor coolant leakage.
A Drywell Atmosphere Radioactivity Monitor is provided to give supporting information to that supplied by the reactor coolant leakage monitoring system.
(See Bases for 3.6.C and 4.6.C)
Some of the surveillance instrumentation listed in Table 3.2.F are required to meet the accident monitoring requirements of NUREG-0737, Clarification of TMI Action Plan Requirements.
This instrumentation and the applicable NUREG-0737 requirements are:
1.
Wide range drywell pressure (II.F.1.4) 2.
Subatmospheric drywell pressure (II.F.1.4) 3.
Wide range supprpssion chamber water level (II.F.1.5) 1*cle Refe3a5 4.
Main stack high range radiation monitoy,diation monitor (II. F.1.1) k d A d u tle - S c y - E c ui a b u i l f i n s 2 0 ^ # "rnt Q L range ^fa (II.F.1.1) 6.
Drywell hydrogen concentration analyzer and monitor (II.F.1.6) 7.
Drywell high range radiation monitors (II.F.1.3) 8.
Reactor Water Level - wide and fuel range (II.F.2) 9.
Safety-Relief Valve position indication (II.D.3)
The suppression chamber hydrogen concentration analyzer P"'
and monitor are listed as an enhancement made by Mod 5274 (see 3.7.A Bases for a discussion of the CAD hydrogen and oxygen analyzers).
j Amendment No. 102, II2, II3, 156, 184, 193 w
Wn D PBAPS
'3.2 BASES (Cont'd)
Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of e
the standby gas treatment system.
Four instrument channels monitor
[
the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor.
Each set of instrument channels is arranged in a 1 out of 2 twice trip logic.
Trip settings of less than 16 mr/hr for the monitors in the refueling area ventilation exhaust ducts are based upon ini-tiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is processed by the standby gas treatment system.
Two channels of nonsafety-related radiation monitors are provided in the main stack.
Trip signals from these monitors are required only when purging the containment through the SGTS and containment integrity is required.
The trip signals isolate pri-mary containment vent and purge valves greater than 2 inches in diameter to prevent accidental releases of radioactivity offsite when the valves are open.
This signal is added to fulfill the requirements of item II.E.4.2(7) of NUREG-0737.
Four channels of in-duct radiation monitors are provided which initiate the Main Control Room Emergency Ventilation System.
Each set of instrument channels are arranged in a one (1) out of 9
two (2) twice trip logic.
Flow integrators are used to record the integrated flow of liquid from the drywell sumps.
The integrated flow is' indica-tive of reactor coolant leakage.
A Drywell Atmosphere Radioactivity Monitor is provided to give supporting information to that supplied by the teactor coolant leakage monitoring system.
(See Bases for 3.6.C and 4.6.C)
Some of the surveillance instrumentation listed in Table 3.2.F are required to meet the accident monitoring requirements of NUREG-0737, Clarification of TMI Action Plan Requirements.
This instrumentation and the applicable NUREG-0737 requirements are:
1.
Wide range?drywell pressure.(II.F.1.4) 2.
Subatmospheric drywell: pressure :(II.F.1.4) 3.
Wide range suppression chamber water. level (II.F.1.5)
M ^'M S*5 4 i
Main stack high rr.;; radiation monitog (II.F.1.1)
W Sla d W le w. -Pereter hildin; :::f "crt hip-range 4 radiation monitor (II.F.1.1) 6.
Drywell hydrogen concentration analyzer and monitor (II.F.1.6) 7.
Drywell high range radiation monitors (II.F.1.3) 8.
Reactor Water Level - wide and fuel range (II.F.2) 9.
Safety-Relief Valve position, indication (II.D.3)
(-
The suppression chamber hydrogen concentration analyzer l
k:
and monitor.are. listed as an enhancement made by Mod 5274 (see 3.7.A Bases for a discussion of'the CAD hydrogen and oxygen analyzers).
j i Amendment No. 104 II6, II7, i
152, 189, 197 Od 3 29
Unit 2 PBAPS 4.2 BASES (cont'd) m The radiation monitors in the refueling area ventilat;on duct which 2nitiate building isolation and standby gas treatment operation are arranged in a 1 out of 2 twice logic system.
The bases given above for the rod blocks apply here also and were used to arrive at the functional testing frequency.
The air ejector off-gas monitors are connected in a 2 out of 2 logic arrangement.
Based on the experience with instruments of similar design, a testing interval of once every three months has been found adequate.
Radiation monitors in the main stack which initiate containment isolation are not safety-related and are required only during containment purging through the SGTS and when containment grecrity is recuired, an activity which occurs infrequently.
(Therefore, a twelve (12) monthcalibrationintervalisappropriate}
Y The Control Room Intake Air Radiation Monitors are saf e-;-related and are required to be operable at all times when secondary containment is required.
The calibration interval is as described in Section 4.11.A.
The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also.
m~
AtScwl SN"*
N 1* b N"*<
I.5 aS The C 9 ltb t%
l' M c w.;
\\ Amendment 5fo.156,184
./
s :n4
Unit 3 I
PBAPS l
4.2 BASES (cont'd) b The radiation monitors in the refueling area ventilatien duct which initiate' building isolation and standby gas treatment operation are arranged in a 1 out of 2 twice logic system.
The bases given above for the rod blocks apply here also and were used to arrive at the functional testing frequency.
The air ejector off-gas monitors are connected in a 2 out of 2 logic arrangement.
Based on the experience with instruments of similar design, a testing interval of once every three months has been found adequate.
Radiation monitors in the main stack which initiate containment isolation are not safety-related and are required only during containment purging through the SGTS and when containment integrity is required, an activity which occurs infrequently.
. - TL
= Li m,
welv; '12: ;.sa;L celibreties A ci mi 1; ;;;r:;rin e.
m g
/
The Control Room Intake Air Radiation Monitors are safety-related and are required to be operable at all times when
- secondary containment is required.
The calibration interkral is as l ' described in Section 4.11.A.
The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also.
ia Nave IS M N'
'M
,(he c a k]st u> %
l l
. Amendment No. 158, 189 MAY 0 51994
NA PBAPS
'L1'MITIN6 CONDITIONS FOR OPERATION SURVEILLANCE REQU!REMENTS half-lives greater than shall be determined in
.n!:
8 days in gaseous effluents accordance with the TC~
released frca the two methodology and parameters reactors at the site to in the ODCM at least cnce areas at and beyond the per month.
SITE BOUNDARY (see Figure 3.8.1) shall be limited to the following:
- a. Durino anv calendar
...qu a r.t e r : -< 15 mrem.
~
b.
During any calendar year: < 30 mrem.
When the calculated dose frem the release of iodine-131,
. iodine-133, tritium and radionuclides in particulate form, with half-lives greater than 8 days in gaseous effluents exceeds any of the above limits, prepare end submit to the Commission within 21 working days, pursuant to Specificaticn 6.9.2, a Special Report.
The report shall j
identify the causes for eiceeding GZ5(
/
the limits and define the corrective actions that have been taken and 1
proposed corrective actions to l
to assure that subsequent releases will be within the above limits.
Reactor shutdown is not recuired.
t/ww4 Sfacd 4.
During release of gaseous 4a. The M h wastes the following con-M m. C h and main ditions shall be met to stack noble gas radiation
/8 avoid exceeding the monitors shall e c a l. i -
limits specified in brated every -(j$cnthswith ThemaindEUCCCfh** stack 3.8.C.1:
a known radioactive source positioned in a reproducible a.
minimum dilution flow of geometry with respect to 10,000 cfm shall be the sensor, and everv ma intained. v3sy-Slack [
quarter by means of a
- b. One W - M idi4 functional test.
The pMN A monitor channel functional test
(
i Amendment No. )&T, 160 210
(
JUN 12150
Uni: 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
~m ig.y half-lives greater than shall be determined in
'3' 8 days in gaseous effluents accordance with the released from the two methodology and parameters reactorr at the site to in the ODCM at least cnce areas a; snd beyond the per month.
SIT" 'P!'DARY (see Figure 3.8.
11 be limited t o t ' r; foi owing:
,:y calendar a.
ci-ac
,' 15 mrmm.
~
b.
A i ;t, c'f calendar vect Trem.
Whe. cre c;2 e ated dose from the e 'as; e iodine-131,
-iodine _.'
ritium and radionuclides in particulate form, with half-lives greater than 8 days in gasecus effluents exceeds any of the above limits, prepare and submit to the Commission within 21 wcrking days,
} pursuant to Specification 6.9.2, a Special Report.
The report shall
.g7,
'us identify the causes for exceedine g) the lim'its and define the corrective actions that have been taken and proposed corrective actions to to assure that subsequent releases will be within the above limits.
Reactor shutdown is not required.
vewY J7hze k 4.
During release of gaseous 4a. The-rc:ct;... _ ' _..,
wastes the following con-
- ' curt cent and main ditions shall be met to stack noble cas radiation
/$
avoid exceeding the monitors shail b,e calin, #
limits specified in brated every -etrbonths with 3.8.C.1:
a known radioactive source
- a. The main-cff g c. : stack positioned in a reproducible minimum dilution flow of geometry with respect to 10,000 cfm shall be the sensor, and every maintained.vuf54uM quarter by means of a
- b. One reactcr buil:ing functional test.
The
-sutzunt c monitor channel functional test m-.
A.mendment No. IN, 162 210 JUN 12 IH1
-~~
rs
PBAPS duiF % ' ~
~ ~ ~
LIMITING CONDITIONS FOR OPERATION SURVETLLANCE REQUIREMENTS and one main stao.
shall also demonstrate that noble gas monitor control room alars'an-c shall be operable and set nunciation occurs if arty of to alarm in accordance the following conditions exist:
with the methodology 1.
Instrument indicates and parameters in the measured levels ODCH. From and after the above the altra date that both reet:Cr WJ SYad setpoint.
bu.idir,; ah;u;t.:nt 2.
Instrument indicates d
monitors or both main a downscale failure.
stack noble gas monitor.s Additionally, an instrument are made or found to be check shall be performed every day.
inoperable for any reason, The --:::t:r building umf SEM effluent releases via 4b.
their respective pathway Ort:::t ;;nt and the may continue provided at main stack flow rate least two independent monitors shall be grab samples are taken calibrated every M/8 at least once per 8 hrs.
months. Additionally, an and these samples are instrument check shall analyzed for gross be performed every day.
activity within 24 4c.
The,ma - L. tiding _ vel.s+M hours, and at least two
.- rh.;;t ;;nt and the main technically qualified stack iodine and particulate members of the facility sample flow rate monitors staff independently shall be calibrated every verify the release D months. Additi:nc.11y,-
rate calculations.
Or 'n:trum:nt h:9 shi!'
~--
One etc.;ter L.iid' ;
vf d 5 N be p="f^ ~ad ave y day c.
- hiert =nt iodine
-f;r th; r;;;t:r buiMing filter and one main Ph:;:t.mni m ic fiv, stack iodine filter
- rit 9 te, :M :v:ry 200h f:r th: ::t it::t
/
and one r:::t:r build dd in; : h;u:t ;:nt ved
-: pi: fb; r;t: ;; nit:rc particulate filter 4d.
Th6 main nau ampic fl~ 14a=
and one main stack 5"fle pr:::ure particulate filter with
- it;he; 3 hail Le their respective flow
-functionally t::ted "e*y rate monitors shall be 5 =rth: :nd ::librei J operable. From and after
-:.;ry 24 u nth 3.
the date that all lodine filters or all particulate filters for either the ved Sb/(
_ re:ct:r teildi~; e*""
a cnt monitor or the main stack monitor are made or found to be inoperable for any reason, effluent releases via their respective pathway may
-~)
i M
Amendment No. 102. II5.179
-211-AUG 0 21993
~_ _
Unit 3 PBAPS
' LIMITING' CONDITIONS FOR OPERATION SURVEILLANCE REQUIRDENTS and one main stack shall also demonstrate that e
7p noble gas monitor control room alarm an-shall be operable and set nunciation occurs if any of to alare in accordance the following conditions exist:
with the methodology 1.
Instrument indicates and parameters in the measured levels ODCM. From and after the above the alam date that both nnter vedSfacM setpoint.
b'id':; ::h = t = t 2.
Instrument indicates monitors or both main
' a downscale failure.
stack noble gas monitors Additionally, an instrument are made or found to be check shall be performed inoperable for any reason, every day.
effluent releases via 4b.
The = r t bildt; th d J h
- d their respective pathway c h = 0.;;.; and the may continue provided at main stack flow rate least two independent monitors shall be calibrated everyg /5 grab samples are taken at least once per 8 hrs.
months. Additionally, an and these samples are instrument check shall analyzed for gross be performed every day d S b d activity within 24 4c.
The : = i c L ;iein, W hours, and at least two e t nt.2; and the main technically qualified stack iodine and particulate members of the facility sample flow rate monitors sh311 be calibrated every
~.
staff independently M
Mi verify the release Jf months. fddith=";,
D rate calculations.
r 'ntr* Nd :bli One 7:ntr hi? din; deMac<
h ;; ':JRd ;;;, de c.
r % = t sent iodine f:r th nitr b'id' ;
filter and one main StNt =:t : ;k f!=
stack iodine filter M t: r ' t c, rd ri a., -
and one -rentr h'1d 2::h fr the uk.La 4; =hatJr.t-vel-ScM
- 7h fl= i;;; -,16.
particulate filter id.
S: nh.Lw..,1=
and one main stack fir = "'/h pr;n;=
C'tdr t!! h particulate filter with their respective flow f
th="atutedrJCJ rate monitors shall be 5 rr t rd C107;t;d operable. From and after 1
- rica' '" sc.th.
the date that all iodine filters or all particulate filters for either the vwi Sf"M
_r e ctr b'idir6 s hs:t
.*ent monitor or the main
-stack monitor are made or found to be inoperable for any reason, effluent releases via their respective pathway may
'\\
<w
-211-Amendment No. 704, 179, 182 AUG 0 2 !$f3
Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS C~'
continue provided samples E
are continuously collected with auxiliary sampling equipment for periods on the order of 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 /> after the end of the sampling period.
OneW_2st44 ding v'tdJbM d.
__gxa.u c y.t flow rate monitor and one main stack flow rate monitor shall be operable and set to alarm in accordance with the methodology and parameters in the ODCM.'
From and after the date that both33tactcr_
-1 bit 14&ng3cchaust vent Sda' C flow rate monitors or both main stack flow rate monitors are made or found to be inoperable for any reason, effluent releases via their respective pathway may R'@
continue 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 />.
- e. with less than the minimum number of
'/
radioactive gaseous effluent monitoring instrumentation channels l
OPERABLE exert best efforts to return the instruments to OPERABLE status within 30 days and if unsuccessful explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely i
manner.
Sa.
Doses due to gaseous 5.
Gaseous effluents shall effluent releases to be processed through the areas at and beyond the appropriate gaseous waste SITE BOUNDARY shall be treatment system as projected at least once i
described below prior to per discharge Amendment No. -Me.,160 212 NOV O 1 1993 e
e-
-r n
Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS continue provided samples gg.3 are continuously collected with auxiliary sampling equipment for periods on the order of 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 /> after the end of the sampling period.
- d. One rc:cter building-vv sh-Sbac k
-.1
--u
.. - -
- flow rate monitor and one main stack flow rate monitor shall be operable and set to alarm in accordance with the methodology and parameters in the ODCM.
From and after the date that both rc:; tor-huildin, m hauem.muL-v$"fSfaC(
flow rate monitors or both main stack flow rate monitors are made or found to be inoperable for any reason, effluent releases via their respective pathway may cky continue provided the kgf flow rate is estimated at i
least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- e. with less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels i
OPERABLE exert best efforts to return the instruments to OPERABLE l
status within 30 days and if unsuccessful explain
{
in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
Sa.
Doses due to gaseous 5.
Gaseous effluents shall effluent releases to be processed through the areas at and beyond the appropriate gaseous vaste SITE BOUNDARY shall be treatment system as projected at least once i
described below prior to per discharge i
d Amendment No. 70#,185 212 NOV 0 1 1933 e
e h%$
.E s
,...; e; : -.-
PBAPS g)
- LIMITING CONDITICNS FOR OPERATION SURVEILLANCE RECUIREME17TF
- c. Gases f rom the S team mcnth in accordance Jet Air Ejector Dis-with the methodology chat ge shall be and parameters in p.
pr'oct.ssed through the the CDC1.
[
recombiner, holdup pipe, i
off-gas i!1ter, and Sb. The appropriate gasecus l
off-gas stacP.
radicactive waste system eculp=ent as described
- b. Gases from the Mechanical in Specificatien 3.9.C.5 Vacuum Pump and Gland Steam shall be demonstrated Exhauster discharge operable every cuarter, i
shall be processed unless ut111:ed to i
through the off gas p ccess gasecus waste g
- stack, during the previous 13 weeks, by analyzing i
- c. R eacter, turbine,
the gasecus waste radwaste, and recembiner processed through the 1
building atmcspheres appropriate ecuipcent shall.be processed to determine that it through permamently meets the requirements of cr temporarily installed Specificaticn 3. 8.C.I.
?
equipment in the appropriate
~
m building ventilatien system Sc. An air sample shall be and the Daetor.3nriading chtained and analyred
(/d. Wenhttc S tack,
fr:m all building areas with the exceptien cf the with an unmenitered fc11cwing unmenitored exhaust ence per menth.
exhausts:
1.~
Recirculatien M-G
~
Set and Reactor Building Cccling Water ecuipment
- = cms.
2.
Centrci recm utility and toilet recms.
3.
Cable spread recm.
4 Emercency switchgear TComs.
(
5.
125/250 VCC Battery recms and the 250 vtC Battery rec =s.
6.
Ad=inistratien Building maintenance decenta=-
inaticn area.
With gasecus waste being discharged withcut treatment as recuired abcve, prepare and submit to the Ccmmissien
.~"
within 21 werking days i
I 213 Amendment No. 102/104 ceceber n,19e4
~
~ 4TF3. i s
PBAPS fl LFMITING CONDITICNS FOR CPERATICN l S*.;RVEILLANCE RECUIREMEh'TF
- a. Gases f cm the Steam menth in accordance Jet Air Ejector Dis-with the methodology charge shall be and parametere in 5
pr' cessed through the the CDcM.
l o
recembiner, holdup pipe, J
cff-gas filter, and 5b. The appropriate gasecus of f-ga s stack.
radicactive waste system equipment as described
- b. Gases fr=m the Mechanical in Specificatien 3.9.C.5 Vacuum Pump and Gland S team shall be demonstrated Exhauster dis charge operable every cuarter, shall be processed unless utilized to through the off gas process gasecus waste i
stack.
during the previous l
13 weeks, by analyzing
- c. R eactor, turbine, the gasecus waste radwaste, and recembiner processed through the L
i building atmespheres appropriate ecuipment l
shall be precessed to determine that it through permanently
, meets the requirements of un temporarily installed Speci ficati en 3. 8.C.I.
E equipment in the appropriate l
~
building ventilatien system Sc. An air sampl e shal 3 de l
Emilfinc cbtained and analyred
--kib"andthe-Em_m...
b catil:ticr Trh:::t S tack,
f rc= all building areas with the exception cf the with an ur_menitered fc11cwing unmenitcred exhaust cnce per =cnth.
I exhausts:
1.~
Recirculatien M-G Set and Reactor Building Cccling Water ecuipment IcCDs.
2.
Centrol rece utility and toilet reces.
3.
Cable spread recm.
4.
Emergency switchgear rects.
5.
125/250 VDC Battery recms and the 250 VEC Battery recms.
6.
Administraticn Building maintenance deccnta=-
ination area.
With gasecus waste being discharged without treatment s recuired areve, pr e par e and submi t to the Cc==ission l(~' within 21 werking days i
l 213 Amendment No. 102/10c cece=ber 31, 1984
(Awd )
/
PEAPS
.,b y>
TABLE 4. 8. 2 RADICACTIV. GAFFOUS D.STI SAFFLIFG AFD AP.AI.YSIS FFOP MAIF&F mgTSTACK APD.'JtF4fHW.au.!!D'WL Uu+ s-factl.
Samp1e Lower Limit of Samele Tvee Samele Frecuencv Samele Analysis D et ecti en (LLD)(2)(4) e
-4 i
~ Grab Sample Menthly(2)
Cuantitative 1 x 10 '
uCi/ce(3) l Analysis of Identi fiabl e l
Gamma Emitters I
~
l P
-6 Grab SampIe Quart erl y T ritium 1 x 10 uCi/cc
-12 Charecal Feekly(3)
I-131 1 x 10 uCi/ce(7)
Fil ters r
-10
'h.._ P a rti cula t.e Feekly(3)
Cuantitative 1 x 10 uC1/cc(3)
Analyris cf
. Fi] ters Identifiab]e Gamma Tmitterr
-17 I-131 1 x 10 uC i/ c:- ( 2 )
-11 9
P a rti cul a t e Menth]y Cross Alpha 1 x 10 uCi/cc Filters t
(ccmpecite cf k
veekly filters )
-12 Menthly Sr-Po 1 x 10 uCi/cc P arti cul at e Fil ters
-11 (ce=pesite of Sr-90 1 x 10 uCi/ cc
]
weekly filters )
i i
ki
/
Ncble Gas Cen tinuousl y Noble Gas Penitor Grosrj cr7 1 x 10 uCi/cc (Main Stack) 9 Ncbje cas CcntinueusJy NcFl e cas
-f Peniter CrossJ cr7 1 x In uCi/cc (Tcef Vents) 3
- ~..
i'
/
216c-1 Amendment No. 102 /104 cece:: er 31, 1984
(4nd _3 PEAFS e
TABLE 4.8.2 RADICACTIVE GATTCtl5 D.STI SAFFLITG AFC AMAr.YFIs TFor
. g.
.._._c c-a,TCX AFC "-- ' ~ " "
""-~^'"" " '.- -.' ".. _'
.c., a' C "s V f.N T-l Sampl e Lcwer Limit cf Iamtle Tvre Samele Frecuency Sammle Analvsis Detecticn (LLD)(1)(a)
-4 frab Sa=ple Menthly(2)
Cuantitative l'x 10' uCi/ce(2)
Analysis of Identifiabl e Gamma E=itters
-6 Irab Sampl e C uart erl y T ri tium 1 x 10 uci/c I
-12 harecal Yeekly(3)
I-121 1 x 10 uCi/c:(?)
Fil ters
-10
? = rti cula t e reekly(2)
Cuantitative 1 x 10 uCi/c (?)
ters Analyris cf I c'e n t i fi a b] e Q
Camma rmitterr
-17 I-121 1 x 10 uCi/cef )
-31 a rti cul a t e Menth]y Grcss Alpha 1 x 10 uCi/c i1:ers I
Tec=cesite c' seekly filters )
f
-12 arti culat e Menthly Sr-F?
1 x 10 uC i/ cc 11ters
-11 ec=pesite cf Sr oO 1 x 10 uCi/cc cekly filters )
' ebl e Gas Centinuously Nel-l e cas
-/- 6 cniter G:cstj c:y 1 x 10 uCi/cc
'l
! Main Stack)
I c?)e Cas Ccn ti nucus] y YcM e cas
-f
'enitor Crest 47 cr J x In uci/c
~
freef Vents) i i' 6 c '*
^^
Amendment No.102 /10L Decerter 31, 1964