ML20092M936
| ML20092M936 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/31/1984 |
| From: | Mayweather L SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20092M911 | List: |
| References | |
| NUDOCS 8407020423 | |
| Download: ML20092M936 (12) | |
Text
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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361 UNIT SONGS - 2 DATE June 15, 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 _
Ext. 56223 OPERATING STATUS
- 1. Unit Name: San Onofre Nuclear Generating Station, Unit 2 2.. . Reporting Period: May, 1984
- 3. : Licensed Thermal-Power (MWt): 3390 4.. Nameplate Rating (Gross MWe): 1127
- 5. Design Electrical Rating (Net MWe): 1070
- 6. Maximum Dependable Capacity (Gross MWe): 1127
- 7. Maximum Dependable Capacity (Net MWe): 1070
- 8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
NA
- 9. Power Level To Which Restricted, If Any (Net MWe): NA
- 10. Reasons For Restrictions, If Any: NA This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 744 3,647 7,152
- 12. Number Of Hours Reactor Was Critical 744 2,766.4 5,379.1
- 13. Reactor Reserve Shutdown Hours _
0 0 0
- 14. Hours Generator On-Line 744 2,692.2 5,253.9
- 15. Unit Reserve Shutdown Hours 0 0 0
~16, . Gross Thermal Energy Generated (MWH) 2,513,823 8,803,518 17,297,053
- 17. Gross Electrical Energy Generated (MWH) 829,282 2,976,553.5 5,888,518.5
- 18. Net Electrical Energy Generated (MWH) 791,141 2,818,930 5,594,575
- 19. Unit Service Factor 100 73.82 73.46
'20. Unit Availability Factor 100 73.82 73.46
- 21. Unit Capacity Factor (Using MDC Net) 99.38 72.24 73.11
- 22. Unit Capacity Factor (Using DER Net) 99.38 72.24 73.11
- 23. Unit-Forced Outage Rate 0 5.50 4.67
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling, September 1984, 3 month durations
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup: NA-
- 26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA-8407020423 840615 PDR ADOCK 05000361 R pyg
m AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-361 UNIT SONGS - 2 DATE June 15,1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 NN) NTH May 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1102.56 17 1024.29 _
2 1086.29 18 1021.13 3 1099.33 19 1033.35 4 1102.65 _
20 1042.02 5 1082.08 21' 1047.77 6 1056.38 22 1032.29 7 1085.56 23 1108.54 8 1085.46 24 1101.29 9 1079.54 25 1095.25 10 1083.23 26 946.35 11 1041.85 27 1102.88 12 1016.42 28 1100.79 l 13 1008.08 29 1107.46 14 1026.17 30 1099.46 15 1024.98 31 1091.58 16 1034.02 2941u
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UNIT SHUTDOWNS AND POWER REDUCTIONS' ' DOCKET NO.'5C-361 j UNIT NAME S(NGS - 2 l ' REPORT MONTH. MAY ,-1984. DATE June ! S. Ists4 l, T COMPLETED BY L. l. 4avweather TELFPHONE f7141 492-7700 j'
Ext. 56223 l
. Method of Shutting. .
Duration .
Down.. LER System Component. Cause & Corrective ,
2 -3 4 4 l 1 .
Action to-
! No. Date Type .(Hours) Reason .. Reacto r No. . Code Code Prevent Recurrence NA NA NA NA NA. NA NA NA' NA NA ,
i l
l 1
l
! 1 . .
2 3 4
(- F-Fo rced Reason: ._ Method: IEEE Std 803-1983
- S-Scheduled A-Equ i pment Fa i l u re ( Exp l a in)' 1-Manual .
B-Ma initenance or Test 2-Manual Sc ram.
C-RereieIing 3-Automatic Screm.
D-Regtilatory Restriction 4-Continuation from E-Opes ator Tra ining as License Examination Previous Month F- Admi n i st ra t ive 5-Reduction of 20%
G-Opet a t iona l . Erro r ( Expla in) or greater in the H-Othe r (Explain) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2941u 9-Other (Expla in)
I
7
SUMMARY
OF OPERATING EXPERIEN'CE FOR THE MONTH DOCKET NO. 50-361 UNIT SONGS - 2 DATE June 15, 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 Date/ Time Event May 1, 0001 Unit is in Mode 1 at 100% reactor power, turbine load is 1152 MWe gross. Full power operations are planned.
May 2, 0114 Received wide range radiation plant vent monitor 2RI-7865 hi-hi radiation alarm due to a rupture diaphragm on C011 (standby waste gas compressor) rupturing while pumping the waste gas surge tank to one of the waste gas holding tanks.
May 2,- 0129 Declared Unusual Event, Tab All, in accordance with the SONGS Emergency Plan.
May 2, 0136 Terminated. Unusual Event following isolation of C011.
May 4, 1954L Reduced reactor power to 90% to perform stop and governor valve testing.
May 5, 0011 Raised reactor power to 100% following completion of ,
turbine stop and governor valve testing.
May 5, 1430 Received plant vent stack radiation monitor hi-hi alarm due to a' leak identified in hydrogen and oxygen monitoring equipment in the waste gas system.
May 5, 1840 Declared Unusual Event due to airborne activity exceeding limits of the SONGS Emergency Plan.
May 5, 1845 Terminated Unusual Event following isolation of the hydrogen and oxygen monitoring equipment.
-May 6,. 0040 Reduced reactor power to 90% for oil leak repairs to HP Stop Valve 2VV2200E.
May 6, 1015 Raised reactor power to 100% following completion of repairs to 2UV2200E.
May 11, 1800 Reduced reactor power to 90% to perform turbine stop and governor valve testing.
m
d .
l Datt/ Time Event }
i May 12, 0100 Raised reactor power to 100% following completion of turbine stop and governor valve testing. Turbine load is 1072 MWe due to the removal of Third Point Feedwater Heater E041 from service for leak repair.
- May 18, 1810 Reduced reactor power to 90% to perform turbine stop and governor valve testing.
May 18, 2059' Raised reactor power to 100% following completion of turbine stop and governor valve testing.
'May 22, 2230. Returned Third Point Feedwater Heater E041 to service l and restored turbine load to 1153 MWe gross.
May 26, 0005 Reduced reactor power to 90% to perform turbine stop and governor valve testing.
'May 26, 0500 ' Reduced reactor power to 65% for performance of CEA ,
exercises.
. May 26,- 1330 Raised reactor power to 100% following completion of turbine stop and governor valve testing and CEA exercises. ;
May 31, 2359 Unit is in Mode 1 at 100% reactor power. Turbine load is'1152 MWe gross. Full power operations are
~
planned.
i T
t
- 2941u b
7 REFUELING INFORMATION DOCKET NO. 50-361 UNIT SONGS - 2 DATE June 15,1984 COMPLETED BY L. I. Mayweather TELEPHONE- (714) 492-7700 Ext. 56223
- 1. Schedul'ed date for next refueling shutdown.
September l1984 -
- 2. . Scheduled date,for restart following refueling.
> December 1984
~ 3'; 'Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes What will these be?
Proposed Technical Specification changes will be submitted to the NRC for Shutdown Cooling System Modifications (Proposed Change Number (PCN) 126), for the reload analysis (PCN 147-153),for
-inclusion of heated junction thermocouples (PCN 128), and for Steam Generator tube wall thinning criteria (PCN 141).
- 4. Scheduled date for submitting' proposed licensing action and supporting
--i nformation.
Not yet determined.
- 5. Important Licensing considerations associated with refueling, e.g. new or different fuel design.or supplier,'unreviewed_ design or performance analysis methods, significant changes in fuel design, new operating procedures.
Not'yet determined.
- 6. .The number of fuel assemblies.
Ja) In the core. 217 b) In the spent fuel storage pool. 0
- 7. Licensed spent fuel storage capacity. 800 Intended change in spent fuel storage capacity. NA lL Projected date of last refueling that can be discharged to spent fuel storage pool. assuming present capacity.
Approximately 1997.
'2941u
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.'NRC: MONTHLY OPsRATING REPORT
- ., 7 DOCKET NO. 50-362
- / UNIT NAME SONGS - 3 c
DATE June 15.1984
%s y COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700
'/ Ext. 56223 OPERATING-STATUf .
+
x 3
- 1. Unit Name: Sa'n 0nofre Nuclear Generating Station, Unit 3
- 2. Reportin.g Period:s May, 1984 -
- 3. Licensed Thermal Power (MWt): 3390
'4. Nameplate Ratir.gs(Gross MWe): 1127
- 5. Design Electribal Rating,(Net MWe): E1080
- 6. Maximum Dependable Capactty (Gross MWe): 1127
- 7. Maximum Dependable Capaci,ty ,(Net MWe)
- - 1080
~
- 8. If Changes _0ccuV In'Capac.1ty' Ratings (I.tems Nc=ber 3 Through 7)
Since Las't Report, Give Reasons: g>
< NA
- 9. Power Level To Which Restricted, If Any (Net MWe): NA
- 10. Reasons For Restrictions, If Any: -
- NA x
~ -
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E_
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This Month Yr.-to-Date Cumulative q , .. ., ,
- 11. ' ilours[In Reporting Period 744 1,463 1,463
- 12. Numbei .0f Hours Reactor Was Critical 540.67 1,284.67 1,284.67
- 13. Reactor Reserve Shutdown Hours ~
0 0 0
- 14. Houis Generator 0n-Line 398.983 1073.183 1073.183
.15. Unit, Reserve Shutdown Hours ,
x 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 1,157,057 3,342,251 3,342,251
.17. Gross 1 Electrical Energy Generated (MWH) -381,721 1,112,275.50 1,112,275.50
- 18. 'at' Electrical Energy Gene' rated (MWH) 349,775 1,043,067 1,043,067
- 19. Unit Service Factor ,
'. 7 53.63 73.35 73.35
- 20. -
Unit Availability Fac(er 53.63 73.35 73.35
- 21. Unit Capacity Fact'or (Using-MDC Net) 43.53 66.02 66.02 f l22. Unit Capacity Factor (Using DER Net) . 43.53 66.02 66.02
- 23. Unit Forced Outage Rate
- 0 0 0 124. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
3 3 , .s NA-u ~ ;-,
- 25. If' Shut;D6wn At End Of. Report Period, Estimated Date of Startup: NA 261_-Units In Test Status (Prior To Commercial Operation): Forecast Achieved d * ~
INITIAL' CRITICALITY , NA NA INITIAL ELECTRICITY ' NA NA
^ ,- . i COMM,ER,CI A. L OPERATION NA NA
' ~
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2 ,$ ,A } e
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-362 UNIT SONGS - 3 DATE June 15,1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 MONTH' May 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1092.10 17 0.0 2- 1081.29 18 0.0 3 1095.21 19 0.0 4 1031.04' 20 0.0
.5 0.0 21 _ 0.0 6 0.0 22 412.60 ,
7 335.25 23 808.06 8 475.77 24 980.85
-9 0.0 25 1101.00 10 0.0 26 1109.31 11 0.0 27 1101.17 12 U.0 28 1093.35 13 0.0 29 1104.27
~14 0.0 30 1089.17 15 0.0 31 1077.42 16 0.0 2941u
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-UNIT SHUTDOWNS AND POWER REDUCTIONS . DOCKET NO.~ 50-362-UNIT.NAME
- _3 REPORT MONTH MAY, '
1984' .
DATE ! I3 _ _ _ .Im-
.. COMPLETED BY.L. l. MaWea the r TELEPHONE 1714) 492-7700 m Ext. 56223 t, . .<.
r.. ',
Mett'od of Shutting -
- j - - Du ra t ion .Down. LER System' Component Cause ac Corrective . '+ !
f'c 'r, J , .2. ~3 4' 45> 2 Action to '
j ,. /
[ No. ~' Date.; (Type (Hours) Reason . Reactor .No. : Code. Code, -
Prevent Recurrence - .; ,
L (:
.5 q/' 840505 . . }'
.S? 53.067' . B, 3^ NA NA NA .- p - Scheduled outage for turbine -
, g f
,Js of generator hearing adjustment. e j it 6
b .
B. 3' NA
. R # ,
Scheduled outage for correction of-84,0508f- S ,237,618 ;, /~
p NAW * ,A A '
~
bearing eingnment on ' turbine .
/ ,.
gene ra to r.
,* , 3i .
7 840519 , .S 26.883 8 3 NA NA Scheduled outage for further
'NA . + , , turbine generator balancing.s . . , ./
.i ' .
,- / ,,. j 3-8 8405205; j? S ; 16.833 8 3- ) / NA - NA~ NA . Scheduled outage to balaa[9 turbine #.
f* 1 t n p * - .
e u*,
genera tor coupling,
^
+
- p l4 g 3* ,d CJNA...
9 -B$521 4S. -10.616 .Ek t
g NA NA Scheduled outage for further "- -
, . turbine generator balarcing. ,
~
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_[
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r) A s *;
E ~ . ;
, m 3
,I '
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~ A 1 2. 3 3 /s 4 lEEE Std 803-1983 -
+ -
. F-Fo rced Reason: . . . , . . Method: ** ' --
S-ScheduPad 4 1-Manual,, J .
A-Equipment failure -(Explain) t ,
4 B-Ma intenance or Test 4' 2-Manua4 Scram. / .
-C-Refueling 5 - -
3- Automa t ic Scram. / /
- 0; Regulatory Restriction - ' . j 4-Continuation from ,
E70perator Tr, tining & License Examinatt'on + '?revious Month -
i F- Adm i n i st ra t ive 5-Reduct. ion of 20% -
G-Ope ra t iona l Error (Explain) or greater in the H 'Othe r ( Exp la in) .. past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2941u 9-Other ( Explain)
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH t
DOCKET NO. 50-362 UNIT SONGS - 3 DATE June 15, 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 E Ext. 56223-
.Date/ Time Event May 1, 0001. Unit is in Mode 1 at 100% reactor power, turbine load is 1152 MWe gross. Full power operations are planned.
.May 4,1_
1800 Commenced power reduction to commence outage activities including bearing adjustments of the turbine generator to correct axial vibrations.
May'5,. 0041 Manually tripped main turbine generator from 75 MWe gross -
to commence' outage activities.
May'5,. ~0102 . Reactor tripped due to high level in Steam Generator E-089.
.May 5,- .
2100 Entered Mode 2.
May 5, 2215-
~
Entered Mode-3 to repair a cooling water line leak to the lower bearing-lube oil cooler for Reactor Coolant Pump _P0003.
May 6 2240 Entered Mode 2 following repair of P003.
May 6,- 2300- Reactor critical.
Ma'y 7, . 0344 Entered Mode 1.
May 7,.
0545 Synchronized generator and applied block load.
May 7, 1500 Reactor power at 60%.
May_8, 0324 Commenced power reduction to correct bearing alignment on the turbine generator. ,
lL May 8, 2228 Manually tripped the turbine generator.
May 8,-- 2235 Reactor tripped on high level in Steam Generator E-088.
May 15, .1127 Entered Mode 2.
May;15, 1147. Recctor critical.
May 18, 1428 atered Mode 1.
L
-Date/ Time Event May 18,~ 2005 Synchronized generator and applied block load.
May 19, 0300 Manually tripped main turbine generator for further balancing of turbine.
May 19, 0318 Entered Mode 2.
May 20,. 0340 ' Entered Mode 1.
May 20,, 0553 Synchronized generator and applied block load.
-May 20, '1150 Manually tripped main turbine generator to balance generator. coupling.
May 20, 1215 . Entered Mode 2.
May 21, 0212 Entered Mode 1.
.May 21, 0440 Synchronized generator and applied block load.
-May 21, 0950 Manually tripped main turbine generator for further balancing of turbine.
May 21, 1045 Entered Mode 2.
May 21, 1905~ Entered Mode 1 following completion of outage.
.May-21, 2027 Synchronized generator and applied block. load. Commenced power increase and evaluation of turbine vibration readings.
May 23,- 1000 Increased reactor power to 80% and commenced heat treatment of the circulating water system.
May 24, 0800 Increased reactor power.to 100% and noted acceptable turbine vibration readings.
May 31,- - 2359 Unit is in Mode 1 at 100% reactor power, turbine load is 1136 MWe gross. A reactor shutdown is planned to repair-excessive inleakage from RCS' loop drain isolation valves into the reactor coolant drain tank. ,
2941u
p RF. FUELING INFORMATION DOCKET NO. 50-362 r
UNIT SONGS - 3 DATE June 15,1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223
.1. Scheduled date.for next refueling shutdown.
Not yet. determined.
- 2. Scheduled date for restart following refueling.
Not yet; determined.
- 3. Will refueling or resumption of; operation thereafter require a Technical
-Specification change or other license amendment?
Not yet determined.
What will these be?.
'Not yet determined.
- 4. Scheduled date for submitting proposed licensing: action and supporting information.
.Not yet. determined. ,
- 5. ~ Important-Licensing' considerations associated ~with refueling, e.g. new or different' fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
Not yet determined.
- 6. The numberiof fuel assemblies, a) In the core.- 217 b) In the-spent fuel storage pool. 0
- 7. Licensed spent fuel storage capacity. 800
' Intended change in spent fuel storage capacity. NA
_8. ' Projected date of.last refueling that can be discharged to spent fuel storage pool assuming present capacity, c NA
'2941u'
, D Enclosure 1 OFFSITE DOSE CALCULATION MANUAL REVISION 9
-sm ,,,^s- , , _1 hNhbhf Nf
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L OFFSITE DOSE CALCULATION MANUAL
_. -REVISION 9-This revision incorporates SONGS 3 into the ODCM. It includes the addition of Radiation Monitors 3RT-7821- (pages 1-7 and 1-10), 3RT-7821
>(page 1-11), 3RT-7818 and 7870-1 (page 2-3) and 3RT-7804 (page 2-4);
'their. calibration constants; (page 1-13 and 2-10); Flow
-Indicator 3FI-3772; and the. administrative value to account for simultaneous: releases from both~ SONGS 2 and SONGS 3 (pages 2-3, 2-4 and 2-5). In addition, this revision added a statement which had been removed in a previous--revision (page 2-2, 2-4 and 2-6) and renumbered pages for text:(page'i) and Tables (page-111).
The. calculational methodology for; Unit 3 is identical to that of Unit 2 Tand uses the same conservative assumptions, _ therefore the changes do K not reduce the accuracy or reliability of dose calculations or setpoint determinations.
This revision was presented and accepted by the Onsite Review Committee on November.9, 1982.
L-s 4..
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.. . _ - ...- -. .u..- -~~~w--
f, ODCM Rev. 9 - November 15, 1982 DDCM
(
TABLE OF CONTENTS
.P,agg LIST OF FIGURES ................................................... gg LIST OF TABLES ..............'...................................... ., .. 111 I NT R OD U CT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . gv ..........
1.0 LIQUID EFFLUENTS 1.1 Li qui d Effl uer.t Moni tor Setpoi nts . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.1.1 Batch Release Setpoint Determination . . .. . . . . . . . .
1.1.2 1-2 '
Continuous Release Setpoint Determination ....... 1-8 1.2 Dose Calculations, for Liquid Effluents . . . . . . . . . . . . . . . . . . 1-14 1.3 R ep re se n t a ti ve Sa=;11ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1- 17 1
2.0 GASEOUS EFFLUENTS 2.1 Caseous Effluer.t Hor.itor Setpcints ...................... 2-1 2.1.1
(', 2.1.2 Flert Stack .....................................
Condenser Evacuation Syster. .............
2-1 2.1.3 2- 3 C ont a i r.me nt P u r ge . . . . . . . . . . . . . . . . . . . . . . . ......
. . . . . . . .. 2-L 2.1.4 Waste Gas 2.2 Header............................... .. 2-6 Gas eous E f flue nt Dose Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-11 2.2.1 2.2.2 Noble Oases ..................................... 2 *1 Radiciocines and Particulates ................... 2-12 q 2.3 Gaseous Effluer.t Dose Calculatien ....................... 2-14 2.3.1 Noble Gases ..................................... 2-14 2.3.1.1 His tori cal Meteorology . . . . . . . . . . . . . . . . 2-14 2.3.1.2 Concurrent Meteorology . . . . . . . . . . . . . . . . 2-15 2.3.2 f Radiciodi nes and Parti culates . . . . . . . . . . . . . . . . . . . 2-17 2.3.2.1 Histori cal Meteorology . . . . . . . . . . . . . . . . 2-17 2.3.2.2 Concurrent Meteorology ................ 2-19 3.0 PS0JECTED DOSES ................................................ 3-1
[p 3.1 Li qu i d Dose Pr o je ct i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.2 c ase ous Dose Pro je c t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . 3-1 a.0
(. .
DPER&BILITT OF EQUIPMEN! ....................................... 4-1 5.0 R&t20LD3ICAL ENVIROEP.EETAL MONI!C.S. K3 .......................... 5 **
n
_.---m....
...3.-
ODCM \
(.x .
1 LIST OF TAB.'ES
_ Table ,
Title Page
. 1-1 Liquid Effluent Radiation Monitors Calibration Constant.................................... 1-13
$ 1-2 Dose Commitment Factors Ai
............................ 1-16 -
2-1 Gaseous Effluent Radiation Monitors Calibration ' '
Constant.................................... 2-10 2-2 Dose Factors for Noble Gas and Daughters ............... 2-21
- 2-3 Dose Parameters P ik .................................... 2-22 '
2-4 Controlling Location Factors ........................... 2-23 2-5 Dose Parameters R g for WX.' Sector ...................... 2-24 thru i 2-25 2-5 Dese Parameters F.g for }@[ Sector I. <
....................... 2-27 thru j 2-30
( 2-7 I Dese Pa a eter Rg for NR' Sector ....................... 2-31 th u I :
2-34 i 2-S Dose Parameter R 3 for jl Sector ......................... 2-35 l i 2-9 Dose Parameter R i g for )NI Sector ....................... 2-35 !
2-10 Dose Parameter R 3 forjg:, Sector ........................ 2-37 2-11 Dose Parameter R g for ENE Sector ....................... 2-38 2-12 Dose Parameter Rg f or J Se c t or . . . . . . . . . . . . . . . . . . . . . . . . . 2-39 i 2-13 Dese Parameter R g for ESE Sector ....................... '2-40 thru 2-41 2-14 f Parameters Used to Calculate R g ............n.......... 2-42 5-1 Rediologiesi Environmental Monitorin SEB ple Loca t i ons . . . . . . . . . . . . . . . . . . . g 5-2 thru ;
. . . . . . . . . . . . . . . . . . . . ' 5-7 5-2 (
Radiolosseal Environmental Monitorin
..........................g..................
Locat10ns ....
5-8 5-3 Sector and Direction Designation I k.
for Radiclogical Enviromeents: !
Esci tori ng Sa .ple Loc a t ier. Ma; . . . . . . . . . . . . . . . . . . . . . . . . . 5-9 111 Rev. 9
___ _ _ _. _ _ _ _ _ _.. _,_- _ _.___ _ _ ...-_ _-82 _ -.
11-15
- - - - 4A ~~~~ --O - -
i
. ('
If there is no release associated with this monitor, the monitor setpoint i should be established as close to !
background as practical to prevent spurious alaras and yet assure an a: arc should an inadvertar.t reIesse occur. ,
i 2RT - 7817, 3R7 - 7617 q 0.1F{Cg3 C, < gg (1-6)
Where:
4 >
IC g, A The values cf {Cgg and A (as defined in Steps 1) and 2) above) for the .
f neutralization sar.;. F = 430 sp.'pu.;
(a number of sa ; pue;s to be rur.).
The 0.1 is an administrative value used to account for I the potential activity from other releases. This assures that the total concentration from all release points to the plant discharge will net result in a i
release of concentrations exceeding the limits of j
10CFR20. Appendix B. Table II, Column 2 from the site.
i l
( I l
1-7 Rev. 9 11-15-52 ;
- - - - - . - 1 '--
NOTE: If C,, 5 { Cy3 then no release is possible. To increase q,, increase dilution f3ow F (by running more circulating water pumps), and/or decrease the effluent flow rate R (by throttling the flow as measured on 2FI 3772 and 3FI 3772), and recaleclate i C,
7 using the new F. R and egaation (1-6).
If there is r.c release associated with this cenitc*, the monitor setpcir.:
i should be esta 11shed as close to backg*ound as practical to prever.t spurious alares and yet assJre ar, ala*.t shou
- c a , f r.advertant release occJa.
1.1.2
_Continueus Pelease Setreint Determinatier.
Step 1) The isotopic concentration for the continuous releases are obtained for each release stret:
(steam generator blowdern or turbine building sump) free the sum of the respective sensured concentrations as determined by analysis:
i
( C
{C,3+C,+Cg + C,
- C7 , (1-7) i 1-S Rev. 9 11-15-E2 l
Step 2)
The adjustment factor. B. for each release atream (stem: generator blowdown or turbine '
building sum;) is determined using: ,
B= IC y3 + + ct t
C, C, + C MPC Fe (1-E:
1 MPC MPC MFC s t a MFC Fe Ste; 3)
The setpoint for each continuous release ,
radioactivity monitor may now be specified '
based on the respective values of i
{Cgg. F. B i and R to provide cor.;11ance with the limits cf 100FR50. A;pendix E. Tatie II Column 2. Tne 1
monitor setpcint (cp ' is taken from t' ?
('
a;;11 cable calibration constants given in Tatie 1-1 to correspond to the calculated monitor limit. C. g l
i
_2RT - 7617. 3R7 - 7817 9
i C, < 0.1 [ICgi R3 (1,9) i l ,
(
Where:
l l
!C 1
gg. B a values of IC g g and B (as defined in ;
i ,
Steps 1 and 2 above) for the stear generator blowdown.
t I
! l 1-10 ,
. Rev. 9 (
11-15-82
~
. . . . _ . . ..-..,.s- - - - -
A-~-~ ~~ =
e
( R = 400 gpm where R is the effluent flow rate at the radiation monitor as defined in Step 2. :
i i
The 0.1 is an administrative value to account for the potential activity in other release pathways. This i assures that the total concentration fror. all release points to the plant discharge will not result in a release of concentrations exceeding the limits of 100fR20. Appendix B, Table II, Cclumr. 2 froc the site.
N0!!: C, 4 {Cgg then no release is pessible. Tc increase C m , increase the dilutien flow F (by running more circulating water put;s), and/or decrease the effluent flow rate R (by i
thrcttling the flow as measured on 2fI-3772),
and recalculate q, using the new values of r, 7 and equation (1-9).
2RT - 78?), 3R7 - 7821
, o.1 r { cg3 c<
a no. (1-10) k 1-11 sev. 9 11-15-82
- - - ~ - -- -
(y, Table 1-1 Liquid Effluent Radiation Monitor Calibration Constants Monitor Co-60e 3 133e Ca-137' 2 /3ni-7813 2. 08 E-9 3.14 E-9 4.59 E-9 2RT-7817 2.11 E-9 3.20 E-9 4.71 E-9 2RT-7821 2. 06 E-9 3.17 E-9 4.61 E-9 3RT-7817 2.24 E-9 2.99 E-9 4.63 E-9 a 3R7-7821 2.15 E-9 3.30 E-9 4.72 E-9
?
l
'b Ci /cc /c;r.
(~
O
'd O'
k 1-13 Bew. 5 11-15-E2
c
~ . .:-n _ - -- u : e -
- I P
MPC = the 10CFR Part 20 concentration for the limiting radionuclide present in sample analysis in yC1/cc ,
(i.e., smallest MPC) flow rate a the plant vent flow rate in era e 83,000 cfm/ fan (a r.o. of fans to be run)
(X/Q) 2.4 E-5 sec/m3 the annual everage atmosphere dispersion 2120 conversion of eft to 2 3/sec 0.85 is an administrative value used to account for potential activity from other gaseous release pathways The alarm setting is determined by using the calibration constar.t fo- the applicable Plant Sts:k Airborne Monitor given in I
Tatle 2-1. The alarm setpoint is the ept value corresponding to the concentration C, which is conservatively assumed to be the isetope cf greatest sensitivity for the monitor.
If there is no release associated with this monitor, the monitor setpoint should be established as close as practical to o' background to prevent apurious alarms and yet assure en alarm abould inadvertent release occur.
74 k
i i
i 2-2 g,,, 9 L w
. . :.. - ._ _ _ _ _ . _;u_ - -
i 2.1.2 Condenser Evaeustion System - 2RT - 7818, 2F7 - 7610-1 3RT - 7818 or 3R7 - 7870-1 i For the purpose of implementation of Specification !
311.2.1, the alars setpoint level for noble gas mor.itors is based on the gaseous effluent flow rate and '
meteorological dispersion factor.
The concentration at the detector is determined by usinE: i i
C < (0.1) (0.5) (2120) (x,;)
P 47,3) ii 7 ,, )
where:
i i
C a the instantaneous concentration at the detector in uC1/cc 4
MPC :
the 10CFR Part 20 concentration for the limiting radionuclide present in seaple analysis in pCi/cc (i.e., smallest MPC) i flow rate a the condenser evacuation system flow rete in cfm a 1,000 cre (I/Q) 2.4 E-5 sec/m3 the annual everage atmosphere dispersion 2120 e conversion of crk to m3 /sec
- k. .
2-3 p,v. 9 _, _
--.. . .... w . -n .a ' .- -
-s - + ---% -- - -
(' O.1 is an administrative value used to account for potential activity from other gaseous release pathways.
0.5 is an administrative value used to account for r'eleases from T both SONGS 2 and SONGS 3 aisultaneous.
The alarm setting is determined by using the calibration constant for the corresponding Condenser Evacuation Systet Monitor given in Table 2-1. The alare setpcint is the cpm value corresponding to the concentration, C which is conservatively assamed to be the isotope of greatest sensitivity for the ocnitor.
4 If there is no release ass:ciated with this nonitor, the coniter setpoint should be established as close as practical to i
background to prevent spurious alarms yet assu e an ala m sheuld an inadvertent release occur.
2.1 3 Containment Purse - 2RT - 7804-1. 3RT - 7504-1 9 For the purpose of implementation of Specification -
3.11.2.1, the alare setpoint level for noble ses monitors is based on the gaseous effluent flow rate end meteorological dispersion factor.
The concentration at the detector is deternised by using:
k
("'II C < (C. 55) (0.5 ) (2123) IX/; (flow rate ) (2-!i i 2-5 w
, ._. ....o-
-u.
. l
{/'
)
where:
C the instantaneous concentration at the detector in 9C1/cc i
MPC the 10CFR Part 20 concentration for the limiting
{
radionuclide present in sample analysis in yCi/ce. ,
(i .e. , smallest MPC) flow rate a the containment purge flow rate in efe a 40.000 cfm fu12 purge 2,000 eft mini purge (X /C ) 2.4 E-5 sec/m3 the ar.naa! average at=csphere dispersier.
212D conversion of cf: to e3/see i.
5 c.45 is ar. administrative value used to accour.t for p:tential activity fror. other gaseous release pathways.
0.5 is an ad=inistrative va2ue used to account for simultaneoas g
releases from both SON 35 2 and $0N35 3.
The alare setting is determined by using the calibratior. constar.t for the Containment Airborne Mo-itor given in Table 2-1. The alars setpoint is the cpc value corresponding to the eencontration, C which is conservatively assumed to be the 1
isotope of greatest sensitivity for the monitor.
2-5 gg
. . . .~... -..n.__. a.
u
.,.. is o' ,
If there is no release associated with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious alaras yet assure an alara abould an inadvertent release occur.
2.1.4 haste Gas Header - 2/3 RT-7814, 2/3 RT-7808 For the purpose of Specification 3.11.2.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and meteorological dispersion factor. Sir,ce the waste gas head 9r discharges to the plant vent stack, either 2/3 RT-75';
er 2/3 RT-7808 may be used to monitor waste gas header releases.
2/3 PT '606 Wher. plant vent stack monitor 2/3 RT-7808 is being used to monitor waste gas header releases, the set;sint determined by equation (2-1) will provide automatic termination of release free the waste gas header.
Determine the maximum permissible unste gas header effluent flow rate corresponding to the vent stack monitor setpoint in accordance with the following:
t g4 (0.9) C F
{ C yg (2-4) l l
l t
s-s Rev. 9
. .__. - .---- - - - -- ~ ~- -
o, .....
, ,o
- Table 2-1 Caseous Effluent Radiation Monitor Calibration Constants Monitor Kr-85*
Xe-133' 2RT-7804-1C 2.78 E-8 3.90 E-8 3RT-780t-1C 2.05 E-6 1.67 E-8 ' ci 2/3RT-7805 C 2.76 E-8 3.72 E-8 '
2 /3R*-7814A 3.21 E-8 2/3RT-7814B 4.49 E-8 4.24 E-5 3.61 E-5 2RT-7818A 3.06 E-8 2R -7818B 5.30 E-8 5.85 E-5 3.77 E-5 3RT-7612A 3.14 E-8 3RT-761BE 4.55 E-S
- 3. 00 E-5 2.63 E-5 2FT-7865-1 (Iow) 1.41 E-S 2RT-76 55-1 (nic) 3.02 E-8 g 2R:-7655-1 (hish) 5.33 E-5 6.61 E-2 3RT-7865-1 (low) 1.41 E-8 3RT-7615-1 (sic) 3.02 E-B 3hT-7865-1 (high) 8.02 E-5 2.39 E-2 2RT-7E-* - 1 (low) 1.41 E-E 2RT-7870-1 (mid) 3.02 E-S 2RT-7870-1 (high) 1.07 E-4 2.87 E-2 3RT-7870-1 (low) 1.41 E-8 3RT-7870-1 (sid) 3.02 E-8 T 3R7-7870-1 (high) 1.08 E-4 2.17 E-2
- pC1/cc/cpre 4
2-10 3,y, 9 W