ML20092C838
| ML20092C838 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 02/06/1992 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20092C834 | List: |
| References | |
| NUDOCS 9202120121 | |
| Download: ML20092C838 (9) | |
Text
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ATTACHMD(T B
-PROPOS5D CHANGES TO APPENDIX A .
TECHNICAL SPECIFICATIONS FOR FACILITY OPERATING LICENSES NPF 37. NPF-66, NPF 72 AND NPF 77 4
' BEQD Braldwood Revised Pages - - Revised Pages 3/4 3-39 3/4 3-40 3/4 3-40 3/4341 3/4341 3/4 3-42 3/4 3-42
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TA8tE'3.'3-6 h RADIAIION M)NITORING INSTRUMENTATION FOR PLANT OPERATIONS l[f '
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. MINIMUM: ;;
$ ' CHANNELS . ..
CHANNELS APPLICA8tE ALARM / TRIP 1- 1-
. gj illNCTIONAL UNil 'l TD IRIP/AtARM' OPERA 8tE MDDES =SEIPOINT- ACTION 7:
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I. fuel: Building Isolation '- Ad y .
m Radioactivity-High and- .
Y af 7
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Criticality (DRC-AR055/56); 1. 2 <S mR/h 29- '
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- 2. Containment Isolatlon-
.N Containment Radioactivity--
Hi9h.
lIh'M E..Y3 a) Unit 1.(IRE-AR011/12)' 1 L2 All 26 ' MM b) Unit 2 (2RE-AR011/12). I 2 All 26 dhh.
- 3. Gaseous ~ Radioactivity-Tjd Q*
.- :141;
. RCS Leakage Detection -4*.
Y a) Unit 1 (IRE-PM0118) N.A. N.A.
~1 1, 2,.3, 4 28 -
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.g h) Unit 2 (2RE-PR0llB) M.A. I 1, 2, 3, 4 N.A. 3 28 .
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- 4. Particulate Radioactivity- -
RCS teakage Detection ~
N.A.
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a)' Unit.'1 (IRE-PR0llA) . I 1,2,34 N.A. 3 26 b) Unit 2 (2RE-PR0llA) N.A. I 1, 2,.3,'4 N.A. 9 28.
5 H.iin Control Room Isolation-Outside Air Intake-Gaseous .
H.ufioactivity-High
, ""' i- ,332/32: ." eaZ-174338/348) I 2 i,e r . ei! ' ? -=/h 2P
[ a) %;r, A. ( ORE -PR03g8/328) l 2 atakgA-l All i 2 mR/3 27 l 2 All i 2mR/h 2*/
b) Tro.n D ( ORE -PR.055B/3% ~ .
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TABLE NOTATIONS
- With.new fuel or irradiatt_d fuel'in the fuel storage areas or fuel building.
- "" Trip Setpoint is to be established such that the actual submersion-dose rate
~ would not' exceed 10 mR/hr in the containment building. For containment-purge
.i or vent the Setpoint value may be increased up to twice the maximum concentra- ;
tion activity in the containment determined by the sample analysis perfomed ,
prior to each release in accordance with Table 4.11-2 provided the value does 1 not exceed 10% of the equivalent limits of Specification 3.11.2.1.a in accord-ance with the methodology and parameters in the ODCM.
ACTION STATEMENTS ACTION 26 -
With less than the Minimum Channels OPERABLE requirement, operation, may continue provided the containment purge, valves are maintained-closed. * {
ACTION 27 -
With the number of.0PERABLE channels d 1ess than the Minimo. ~
Channels OPERA 8LE requirement, within 1 hourfisolate the Control Room Ventilation System and initiata operation of the Control Room ..
Make-up System.j ACTION 28 --
Must satisfy the ACTION requirement for Specification 3.4.6.1.
ACTION 29 -
With the number of OPERABLE channels one less than the Minimum y l
Channels OPERABLE requirement, ACTION a. of Specification 3.9.125 must be-satisfied. With both channels inoperable, provide an appropriate portable continuous monitor-with the same Alarm Set-point in the fuel pool area with one Fuel Handling Building-Exhaust-filter plenum i Q peration. Otherwise satisfy ACTION b.
of Specification 3.9.12.% -
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" wtc.h s the redundont- trr.;n of Confrol Room Venhtohon, proveded tht redundont train rnetts
-Sc. Minimum C honocis OPERA!SLE. r'e.guiremuit cr ka44* re, & in.p e ble me n s k.c3 to CP&d.ABLC s4.du.* wM 3o h oe
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- tis. tion o pecific ion 3.9. ACTION re not equire prior- July \
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INSTRUMENTATIONL 3/4.3.3 MONITORING INSTRUMENTATION
_ RADIATION MONITORING FOR PLANT OPE *ATIONS LIMITING CONDITION FOR OPERATION ~
3.3.3.1
-the shown specified inlimits.
Table 3.3-6 shall be OPERABLE with their Ala APPLICAiiILITY:l As shown in Table 3.3-6.
! ACTION:
- a. .
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.With a radiction monitoring channel-Alarm / Trip Setpoint for plant operations exceeding the value shown in Table 3.3-6, adjust the l _; Setpoint inoperable. to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel b.-
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y kith'oneormoreradiationmonitoringchannelsforplantoperati inoperable, take the ACTION shown in Table 3.3-6.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by'the performance of the CHANNEL CHECK, iCALIBRATION frequencies shown inand DIGITAL Table 4.3-3. CHANNEL OPERATIONAL TEST for:the
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TARIE 3.3-6 E
R RADIATION MONITORING INSTRIMENTATION FOR PLANT OPERATIONS E
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HINIMIM CHANNEL 5 CilANNELS APPLICABLE- ALARM / TRIP g FUNCTIONAL' UNIT TO 1 RIP /AIAlll! OPERABLE- MODES SETPOINI ACTION U 1.. ' Fuel Buf1 ding Isolation-
- H Radioactivity-High~and -
- Criticality (ORE-AR055/56)
- 1 2 <5 mR/h 29 e' }#
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' 2. Containment Isolation-25>+:
Containment Radioactivity- Mi High a) Unit 1 (IRE-AR011/12). 1 **
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2 All 26 '~
b) Unit 2 (2RE-AR011/12) 1- 2 All **
26 .
- 3. Gaseous Radioactivity- ~
m RCS Leakage Detection A a)' Unit 1 (IRE-PR0118) . N.A. I 1, 2, 3, 4 H.A. 28 o
b) Unit 2 (2RE-PR0118) N.A. I 1, 2, 3, 4 N.A. 28
- 4. Particulate Radioactivity-RCS Leakage Detection
.a) Unit l'(IRE-PRO 11A) N.A. I 1, 2, 3, 4 M.A. 28 b) Unit 2'(2RE-PR011A). N.A. I 1, 2, 3, 4 N.A. 28
- 5. Main Control Room Isolation-Outside Air Intake-Gaseous Radioactivity-High
-(0"E .""^33"/32" ::d ^^5 .""033"/31") I 2 pcr "! i?-m ?7
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-a)Tr..n A (o 6e- P8 631 B/328) ; Asf 6 Im8/h I7 b)Tr..'a a (one -pro 33s/39s) i 2 A38 t--
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TABLEJOTATIONS
- Nith new fuel or irradiated fuel in the fuel storage areas or fuel building.
- Trip Setpoint is to be established such that the actual submersion dose rate would not exceed 10 mR/hr in the containment building. For containment purge or vent the Setpoint value may be increased up to twice the maximum concentra-tion activity in the containment determined by the sample analysis performed prior to each release in accordance with Table 4.11-2 provided the value does not exceed 10% of the equivalent limits of Specification 3.11.2.1.a in accord-ance with the methodology and parameters in the ODCM.
ACTION STATEMENTS ACTION 26 -
With less than the A nimum Channels OPERABLE requirement, operation may continue provided the containment purge valves are maintained closed.
ACTION 27
- With the number of OPERABLE channels ec( less than the Minimum ChannelsOPERABLErequirement,within1hourns~olatetheLontrol l
Room Ventilation System and initiate operation of the Control Room
_ Make up System, g, TION 28 -
Must satisfy the ACTION requirement for Specification 3.4.6.1.
ACTION 29 -
With the number of OPERABLE channels o,e less than the Minimum ChannelsOPERABLErequirement,ACTIONa.ofSpecification3.9.12[
must be satisfied. With both channels inoperable, provide an appropriate portable continuous monitor with the same Alarm Set-point in the fuel pool area with one Fuel Handling Building Exhaust filter plenum in operation. Otherwise satisfy ACTION b.
ofSpecification3.9.12.X smca +m . a re. u u % a onen %
V e nM l o.4.l e n, prom'ded t he. et dan tl ant +ca. i n m e < +.!
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in1 ial o ration Rated rmal Po r on Cy Q 1.
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. TABLE 4.3-3 .. -
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s' i RADIATION MONITORING INSTRUMENTATION FOR PLANT Ei ' :OPERAll0NS-SURVEILLANCE REQUIREMENTS '
6 8
. TDIGITAL.
c CHANNEL 35 ~ CHANNEL CHANNEL: - OPERATIONAL MODES FOR MIICH U. IUNCTIONAL UNII., CHECK CALIBRATION: . TEST . SURVEILLANCE'15 REQUIRED,
- e. 1. ; fuel Building Isolation-n.2 ' Radioactivity-liigh and .
. Criticality:(ORE-AR055/56) 5 RP M *'
- 2. iContainment Isolation-Containment Radioactivity--
liigh z a) Unit' 1 (1RE-AR011/12) $ RC M All b) Unit'2 (2RE-AR011/12)- 5 LRC M. All w 3. Gaseous Radioactivity-1 :RCS Leakage Detection. t
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w a) linit 1 (IRE-PRO 118) S RI' M 1, 2, 3, 4 g'; b) Unit 2 (2HE-PR0118). 5 ' Rl' M 1, 2, 3, 4
- 4. Particulate Radioactivity-.
RCS teakage Detection a) Unit.1 (IRE-PRO 11 A)- 5' Ri' M 1,.2,.3,.4 h) Unit 2 (2RE-PR011A) 5 ' Ra'- M 1,2,3,4
$ .S. Main Control Room Isolation- '
9 Outside Air Intake-Gaseous'.
M Radioactivity-fligh (ORC PR031B/525-
[oN_ybtBl32 3) ^I z . bYTw"3 (CEE-Pit.o35% I 54-B) i 51 R-' M' hti
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.>pu..i.cd id - nu...nic. m!._ aj be cxicad:d to 32 ontF' fer cy;!c I s..by+'
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ATTACHMENT C EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated this proposed amendment and determined that it a proposed involves amendment noto significant an operating hazards considerations.
license involves no significantAccording to 10 CFR 50.92(c)lons hazards considerat if opera of the facility in accordance with the proposed amendment would not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or
- 3) Involve a significant reduction in a margin of safety.
The proposed change does not result in a significant increase in the probability or consequence of accidents previously evaluated. The radiation monitors are designed to provide a response to a radiologicallncident. The operability of these monitors does not factor into the sequence of events required for a radiological release to the atmosphere to occur. They serve to initiate action to prevent a release from unacceptably impacting the Control Room; they do not prevent a -release from occurring.
The subject radiation monitors function to isolate the Control Room Ventilation System (VC) outside air intakes in the event of a high radiation condition. Each train of the VC system is provided with redundant radiation monitors. Only one train of VC is operated at a time. The
- proposed change would allow the operation of a train of VC with a full complement of radiation monitors in the normal configuration. Assuming a limiting scenario of the plant operating with degraded monitoring on the Idle VC train with the occurrence of radioactive release and subsequent failure of the running train, the idle train could be started. The train would still have a single radiation monitor available or already be aligned in the emergency mode per system design. If the initiating event resulted in a Safety injection signal, the ventllation system would automatically align to the post accident mode. This provides a diverse means of providing radiological protection for the Control Room. The proposed change does not alter the manner i in which the actuation signails provided, nor does It have ar. inor.ui on the response of the VC system to a valid actuation signal.
The proposed change does not create the possiblilty for a new or different kind of accident from any accident previously evaluated. The proposed chan e does not introduce any new or different equipment, and it will not result in Installed equ pment being operated in a new or different manner. The change will allow the operation o a fully operable train of VC, rather than require that a train with degraded monitoring be operated in its post accident configuration. The monitors are designed to fallin a safe condition, so required system configuration or operation are not precluded.
The proposed change does not involve a significant reduction in a margin of safety. The proposed change allow the operation of a VC train with full radiation monitoring capability. In the event there is one monitor per train inoperable, the change does not render the plant vulnerable to a single failure which would result in the overexposure of control room personnel.
Additionally, the Control Room is equipped with Area Radiation Monitors which provide an alarm upon detection of a high radiation condition. As such, sufficient means will remain available to mure that the VC system is capable of being both automatically and manually aligned to provide for the mitigation of radiological events.
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