ML20087D838

Proposed Tech Specs Table 3.3-6 & 4.3-3 Re Radiation Monitors Assigned to Each Train of Control Room Ventilation

ML20087D838
Person / Time
Site:	Byron, Braidwood
Issue date:	01/13/1992
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20087D837	List: ML20087D834 ML20087D838
References
NUDOCS 9201170163
Download: ML20087D838 (9)

Text

p

i. .

ATTACHhENT B PROPOSED CHANGES TO APPENDlX A TECHNICAL SPECIFICATIONS FOR FACILITY OPERATING LICENSES NPF 37, NPF 66, NPF-72 AND NPF-77 i Byron Braidwood Revised Pages Revised Pages 3/4339 3/4 3-40' 3/4340 3/4 3-41 3/4 3-41 >

-3/4342 3/4 3-42 l

l' 9

-- S r t

l5 l

t .

l-l' l

/ sci:lD705:6 =

!~ L9201170163 920113 iPDR< ADOCK 05000454-

- "PDR 3 - P ~ --

_. . v C 34 % i e..

-Q

~ *' g/

TA8L.E 3.3-6 m -

g NADIATION MONITORING INSTRUNENTATION FOR PLANT OPERATIONS. ;d o a x

3&7.

c 5

CHANNELS MINIMUM CHANNELS APPLICABLE ALARM / TRIP 3

[ - ':j d IIINCT10NAL UNIT TO TRIP / ALARM- OPERA 8tE MDOES SETPOINT ACTION

• -[

~

e. 1. Fuel Building Isolation-- - '.

m Radioactivity-High and  ;

Criticality (ORE-AR055/56) 1 2 *

<5 mR/h 29 ' T w. >-

2. Containment-Isolation- - ~

Containment Radioattivity- .

'g fligh E a) Unit 1 (1RE-AR011/12) 2 **

1 All 26  : ~.

b) Unit 2 (2RE-AR011/12) **

1 2 All , 26

_y T-R

3. Gaseous Radioactivity-RCS Leakage Detection -[

• ' a) Unit 1 (IRE-PRO 11u) N.A. 1 1, 2, 3 N.A. . . 28

'g h) Unit 2 (2RE-PR0118) N.A. I 1, 2, 3, 4 M.A. ,

28

4. Particulate. Radioactivity-RCS Leakage Detection 1 a) Unit.1 (1RE-PR011A) M.A. I 1, 2, 3, 4 N.A. 28 b) Unit 2 (2RE-PR011A) H.A. I 1, 2, 3, 4 M.A. 28 5 Main Control Room Isolation-Outside Air Intake-Gaseous .

• 1 H.nlicactivity-liigh

-440 F;;212/32" h.4 GRE-T;0330/20") 1 2 per ^!' $ ? -=/h 29 o) %;n A . ( ORE -PR03:S/328) 1 2 intake -

52 All i z mR/3 27 Q Tro.n D ( ORE -I'n.o35B/398) 2 AH i 2 mR/h 27 I

i

.a- w

. . - - - -. - . . _. . . . - . - - . _ - . . ~ . - . . . . . . . ._-

y TABLE NOTATIONS

~ '

"With new fuel or irradiated fuel in the fuel storage areas or fuel building, i

• • Trip Setpoint is to be established such that the actual submersion dose rate l would not exceed 10 sR/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 anzlysis performed l 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 00CM.

ACTION STATEMENTS ACTION 26 -

With less than the Minimus Channels OPERA 8LE requirement, operation may continue provided the containment purge, valves are maintained closed. -

ACTION 27 -

With the number of OPERABLE channels mW1ess than the Mini ='=

Channels OPERABLE requirement, within 1 hourfisolate the Control]

Room Ventilation System and initiate operation of the Control Room i Make-up System.j ACTION 28 -

Must satisfy the ACTION requirement for Specification 3.4.6.1.

ACTION 29 -

i With Channelsthe number OPERABLE of OPERABLE requirement. ACTION channelsa.one of Specification less than the 3.9.12 Minimum y must be satisfied.- With both channels inoperable, provice an- '

appropriate portable continuous monitor with the same Alarm Set-point in the. fuel pool area with one Fuel Handling Building Exhaustfilterplenumiq/peration. Otherwise satisfy ACTION b, of Specification 3.9.12.%

L Qwh to +he redundant- ircin of Confrel Room venblohon, provided the redundani- fr ain meet's the Minimum Channe.ls OPER.ABLF. rtSU reme.nt cr h4ere. 6.k in,p44 4 ale. me n s ken to OPM-NBLI <OS' 'd 6M'" k %8 o r . s.Je m*4 o. s,=. I L.p. A to tk. dem ,in e.n ye d %

Sr ci6cdon (.. $.J. ta & n tk.e. .f. ((* iaH 6 30 da.a-(C6.d4 * *@ h mayadeIi4y o,nd -Sa. pt n. Q re,ts M *provid*5 'tk*--

j &4m.

~

1. tis tion o) pacifi ion 3.9. ACTION re not equir rior July 1 who there 1 no irra ated fue in the s rage p 1.

BYRON - UNITS 1 & 2 3/4 3-41 w '-

y :t - g - - -w- --, _ . _ _ _ , _ . . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ . _ _ _ , _ _ _ _ _ __._m . _. _. ._._.

u,.

s T 11 .

n g; f 4 ,.' .

-=w I

. '"'.: 4

~TA8tE 4.3-3 ._, f

-Q' TM%

g-l' RADIATION MONITORING'INSTRUMENTAT!ON FOR PLANT pd z

OPERATIONS SURVEILLANCE REQUIRtNENTS -,jp

.# w l@ # %r

~

y DIGITAL.

9 m

- ?.{

7 C CHANNEL -

H CHANNEL- . CHANNEL

. -OPERATIONAL' M00ES FOR ndHICH

]Qf FUNCT10f**1 UNIT. CHECK Call 8 RATION' TEST SURVEILLANCE'IS REQUIRED 2M6

m , 11#}

1. . Fuel Building Isolation-Radioactivity-High and yMl ]

l Criticality (ORE-AR055/56) S R M * *

g g M

2. . Containment Isolation-Containment Radioactivity- I'

[gG p

.High J , MW) Sq H

a) Unit 1 (1RE-AR011/12) S R M All .

' A58

[ b) Unit 2 CRE-AR011/12) S R M All - f lj(- e .,.

w g i 3 .' Gaseous _ Radioactivity-- , 'iy N RCS Leakage: Detection , ';4W a) Unit.1 (IRE-PR0118) 1,2,3,4 0 ^

~

S R M ~

b) Unit 2.(2RE-PR0116) S R M 1, 2, 3, 4 -

3 ,

4. 'Particul' ate Radicactivity-RCS Leakage Detection +

a) Unit'1 (IRE-PR0llA) 5 R M' 1, 2, 3, 4 i.

b) Unit 2 (2RE-PR0ilAl 5 R H 1,2,3,4

" . . Main Control Race} Isolation-Outside Air. Intake-Gaseous Rad i oac t i v i ty- H i gh -( ^^5 - 7"l0010/320*-

- = =; GNE-ine33;/2001 ' S R M All

.u) hn A (. ORE-TKo3:5/528g. ,

b) Tru.n B (ogg-PRO 556/51g) 5 R M AH

• With new fuel or irradiated fuel in the fuel storage' areas or fuel building.

(~

j

J.11o. , '

hh f $$kh

• " S ' '

n_{m  %;y a ' % ^ 6.

'..  : ,~ '

lNf ,

iINSTRUMENTATION-

.g 3/4.3.3 MONITORING INSTRUMENTATION' RADIATION MONITORING FOR PLANT OPERATIONS-I

~

""~ <

LINITING CONDITION FOR OPERATION - '

(

3.3.3.

t. . The radiation monitorin instrumentation channels for plant operations shown the in Table-3.3-6 spectfied liefts. shall be OPEb8LE with their Alarm / Trip Setpoints withi ,

APPLICABILITY: As shown in Table 3.3-6.

ACTION:-

ra.

With a radiation monitoring channel Alarm / Trip Setpoint for plant

operations exceeding the value shown in Table 3.3-6, adjust t.a 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 declarts the channel '

q b.-

With one or more radiation monitoring channels for pit.nt' operations 4 = inoperable, take- the ACTION shown in Table 3;3-6. .

l c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

p' t <

it t

.o

- i

. SURVEILLANCE REQUIREMENTS N

l F "

4.3.3.1 JEach radiation monitoring instrumentation channel for plant operations

.shall be' demonstrated OPERABLE by'the performance of.the CHANNEL CHECK, CHANNEL 1

!~

? CALIBRATION ifrequencies shownand DIGITAL in_ Table 4.3-3.-CHANNEL OPERATIONAL TEST for the MODES and p

h,- >

I J .

fofofoaff1o f fffrly$ff1 ) cfffy1In/// ,

-BRAIDWOOD-- UNITS l'& 2 3/4 3-39 l -

l.

v~ , , -- - , - .- -

_.?

m TABIE 3.3-6 .

~

3-k RADIATION MONITORING INSTRilMENTATION FOR PLANT OPERATIONS 7 8

o

• MINIMUM CllANNElS CHANNELS APPLICABLE ALARM / TRIP

~

3 FUNCTIONAL UNIT TO 1 RIP /AIAHft 0PERABLE MODES SETPOINT ACTION d 1. Fuel Building Isolation-Radioactivity-High and

• • Criticality (ORE-AR055/56) 1 2 * .

N

<5 mR/h 29' '

2. Containment Isolation- . , '

Containment Radioactivity- ~-

High a) Unit 1 (1RE-AR011/12) 1 2 All **

26 b) Unit 2 (2RE-AR011/12) 1 2 All **'

26 .

]" 3. Gaseous Radioactivity- s m RCS Leakage Detection '7 i

o a) Unit 1 (IRE-PR0118) N. A. I 1,2,34 .N.A. 28 -

b) Unit 2 (2RE-PR0118) N.A. I 1, 2, 3, 4 N.A. 28

4. Particulate Radioactivity-RCS Leakage Detection a) Unit 1 (IRE-PR011A) 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"i-P20310/320 ::d 0*E-P2033S/313) .I 2 pcr ""

' ? " 'h 77 a)Tr.;n A (0 6E- P8631 B/326) [ [' ail 6 gng/h 17 b) Tr..'a 6 (o As - PRO 33s/398) i 2 4 88 4 z mAjh 29 l

l l

l.

. . . . ~ -

j,- y, :Q t a; 3 +

t f*

TABLE NOTATIONS' j

-"Nith new fuel or irradia+ed fuel in the fuel storage areas or fuel building.

• • Trip Setpoint is to be estahN shed such that the actual submersion dose rate would not exceed 10 mR/hr in the containment building. For containment purge or vent the Setpoint vale 'cy be increased ut, to twice the maximum concentra-tion activity in the conta m ent 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 ifth the methodology and parameters in the ODCM, ACTION STATEMENTS ACTION 26 - With less than the Minimum Channels OPERABLE requirement, eperation may contwue providad the containmoit purge valves are maintained closva; ACTION 27 -

Sith tlie number of OPERABLE channels W ~ess than the Minimum Channe's OPERABLE requirement, within 1 hourKisolate the control Room Ventilation System an1 initiate operation of the Control Room

__ Make-up Systes g, l

[ ACTION 28 Most sattsfy the ACTION requirement for 3pecification 3.4.6.1.

ACTION 29 - ' Vith the number of OPERABLE chc.nne'.4 one less tr,tn the Minimum f-Channels OPERABLE requirement, ACTION a. c.' Specification 3.9.12[

must be su.4sfied. With both channels inoptrable, provide an appropriate 3.*irtable continuous monitor with the same Alarm Set-

-point in the h.91 pool area vith one fuel Handling Building Exhaust filter p.3num-in operdion. Otbarwise satisfy ACTION b

} of Specification 3.3.12 7

-%-v f 1,0 f + c. k -}.6 4% e p g,,) & n h g g.+ { f L $ 01 4 -( C.6nkf0 h ho0M Ve dI(c.4.len7 p revid e d t h e_ et (u.n ti ant + r e.i n . at1 e e f.!

Jh I r, i m u.m C h a n s1 4 ls OPE R j h t. 3LE n 9ule meM; or -

i q( u'x.~ -~ =~

- a M -t:k.a. meyer* b5 menWev h to OPEiRA%!.E M5 *L$'"

o v-Sw kwi c% Sysmed R yt 6 ti.e. Gemression yur5mt. 40

- -I)3 h i

-badc+M*n 4,.%.'2. : w eb ne. -Q lle aw4 3o a i:f.,,:f provtde.s tie dam.5s.v G tbs.*mopee4.l.'.Il4y o mL tie. ylans, & e e stp-Wam,. j l-o 'isfaw* ion of 5 ification 9.12 A saa b.no\requir prior ini al o Qtion at ,, 5% Rated Npmal -P *e(on Cy 1. \

l l BRAIDWOOD - UNITS 1 & 2 2/4 t-41

+-

shgpg fp

+

jdQs *

. TA8tE 4.3'3 .

• 2 li

-g n

gp B RADIATION MONITORING'IN'TRUMENTAT10el FOR PLANT - .? d?

g CPERATIONS SU2VEILLANCE REQilIRRENTS JJ 8 rg E

DIGITAL:

CHANNEL'

[h/

Q CHANNEL CHANNEL' . OPERATIONAL._ MODES FOR MtICH~ p - QM: Tg%

FUNCTIONAL !'Ng CHECK CALIBRATION TCST SURVEILLANCE IS REQUIRED.

c -.

M. nif N

• • - 1. Fuel Building Isolation-

-Radioactivity-High and ~ h Criticallty (ORE-AR055/56)_ 5 R M * ~~%B2 .-Q:

mm

2. Containeer.t kolation--

Containment Rad oactivity-

"'"hfkk y 7 High -

ZJW Mdk

~

w a) Unit 1-(1RE-ARO110 2) S R- M All

) b) Unit 2 -(2RE-ARGIL ,G ,

5 R M All

-e y^,.:t Y 3. Gaseous Radioactivity-  ; - -

N RCS Leakage Detection "

.u.

a): Unit 1 (IRE-PRO 118) 5 R M 1, 2, 3, 4 ~

1 b) Unit.2 (2RE-PR0118) 5- R M- 1 2,3,a {} - "

, T

4. ' Particulate Radioactivity-RCS Leakage Detection a) Unit:1 (IRE-PRO 11A) ~ S R M 3, 4 -

b) Unit'2-(2RE-PR011A) .

5- R H 1, 12, 2, ' 3, E.

5. Main Control Room Isolation-Outside Air Intake-Gaseous Radioactivity-High (^^E ""a?!"/2?"

-end-ORE 4 ROT'S/3'?) R 4 All

. a) Trda A (o AE - P80318/318) 5 b) Tresa 8( otE- PA.o 338/3q s) s 6 m AJJ

• With new fuel or irradiated fuel in the fuel storege areas'or fuel-building.

ATTACHMENT C

, EVALUATON OF SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated this proposed amendment arid determined that lt involves no significant hazards considerations. According to 10 CFR 50.92(c) a proposed amendment to an operating license involves no significant hazards considerations if operation 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 posrAliity of a now or different kind of accident from any accident previously evaluatod; or

3) Involve a significant reduction in a margin of safety.

The proposed change does not result in a significant increase in the probabi:lty or oo'bequence of accidents previousif evaluated. The radiation monitors are designed to provide a tosponse to a radiologicalincident. The operability of these mor3 tors does not factor into the sequenca of events required for a radiological release to the atmosphere to occur. They serve to Initiate action to prevent a release from unacceptably Impact!ng the Control Room; they do not prevent a telease from occurring.

The subject radiation monitors function to isolate tha Con %I Room Ventilation System (VC) outside air intakes in the event of a high radiation conditloc. Each train of the VC system is provided with redundant radiation monitors. Only one train u iC is operated at a time. The propocad change would allow the operation of a train of VC with a full complement of radiation monitors in the normal cunfiguration. Assuming a limiting scenario of the plant operating with degraded monitoring on the Idle VC 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 ventilation system would automaGeally 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 in which the actuation signalis provided, nor does it have an impact on the response of the VC system to a valid actuation signal.

The propossd change does not create the possibility for a new or different kind of accident from any accident previously evaluated. The proposed ch 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 configuratloa, The monttors are designed to failln 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 evont there is one mcnitor 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 ensure that the VC system is capable of being both automatically and manually aligned to provide for the mitigation of radiological events.

/ sci:lD705:7