ML20137C515
| ML20137C515 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 01/13/1986 |
| From: | Stevens J Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8601160341 | |
| Download: ML20137C515 (48) | |
Text
..
.. J ua
~
+ %g , , UNITED STATES 8 n NUCLEAR REGULATORY COMMISSION i
- ;E > WASHINGTON, D. C. 20555
% , , , , , ** JAN13 q Docket Nos.: STN 50-454, STN 50-455 and STN 50-456, STN 50-457 -
Mr. Dennis L. Farrar Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Farrar:
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 TECHNICAL SPECIFICATIONS - SECOND DRAFT By letter dated October 7,1985 we sent you the first draft of the Braidwood Station, Units 1 and 2 Technical Specifications. Based on our continuing review, and your submittal of November 20, 1985, we have made changes to the first draft. Enclosure 1 is a summary of these changes and Enclosure 2 is revised pages incorporating the changes. Replacing the pages in the first draft with the pages in Enclosure 2 will constitute the second draft of the '
Braidwood Technical Specifications.
During a November 20, 1985 conference call, we informed you of two items that should also be included in the Technical Specifications for both Byron and Braidwood Stations. The first item involves modifications needed to mitigate certain high energy line breaks, as described in your Augus 2, 1985 letter.
-YouwillbeexpectedtosubmitproposedTechnicalSpecifica(ionsafterwe t complete our review of the modifications.
The second item involves the need to have Technical Specifications for the diesel-driven auxiliary feedwater pump batteries. The Byron Technical Specifications should also address the diesel-driven essential service water makeup pump batteries.
The above changes are not all inclusive since our review is still in progress.
Some of these changes also apply to the Byron Station, Units 1 and 2, Technical Specifications. An amendment request from you will be be needed to incorporate these changes into the Byron Technical Specifications.
B601160341 86011344 DR ADOCK O y
. - JAN 13 mg 1
j
. For further clarification, call the Braidwood Project Manager, J. A. Stevens,
, at 301 492-7144. -
_ Q rtNci M 17.u Ja ce'A. Stevens, Project Manager PWR Project Directorate #5 Division of PWR Licensing-A
Enclosures:
As stated cc: See.next page 1
a 4 f
i i
i l
l l
Mr. Dennis L. Farrar Braidwood Station Commonwealth Edison Company Units 1 and 2 cc:
Mr. William Kortier Ms. Lorraine Creek Atomic Power Distribution Route 1, Box 182 Westinghouse Electric Corporation Manteno, Illinois 60950 Post Office Box 355 Pittsburgh, Pennsylvania 15230 Jane M. Whicher, Esq.
, 109 N. Dearborn Street Joseph Gallo, Esq. Chicago, Illinois 60602 Isham, Lincoln & Beale 1120 Connecticut Ave. N. W. Elena Z. Kezelis, Esq.
Suite 840 Isham, Licoln & Beale .
Washington, D.C. 20036 Three First National Plaza Suite 5200 C. Allen Bock, Esq. Chicago, Illinois Post Offices Box 342 Urbana, Illinois 61801 Eric Jones, Director Illinois Emergency Services Thomas J. Gordon, Esq. and Disaster Agency Waaler, Evans, & Gordon 110 East Adams 2503 S. Neil Springfield, Illinois 62705 Champaign, Illinois Ms. Bridget Little Rorem Appleseed Coordinator 117 North Linden Street
-Essex, Illinois 60935 Mr. Edward R. Crass Nuclear Safeguards and Licensing Division Sargent & Lundy Engineers 55 East Monroe Street Chicago, illinois 60603 U. S. Nuclear Regulatory Commission Resident Inspectors Office RR#1, Box 79 Braceville, Illinois 60407 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
6
?
'* ENCIOSURE 1
SUMMARY
OF CHANGES INCORPORATED INTO THE .
BRAIDWOOD SECOND DRAFT TECHNICAL SPECIFICATIONS PAGE
SUMMARY
OF CHANGE Index XVI, 1-3, and 1-9 Typographicalerror(s) corrected 2-2 Figure incorporated 2-9 Typographical errors corrected 3/4, 1-22, 2-3, and 2-5 Figure incorporated 3/4 3-20, 3-28, 3-32, 23-38 HELB temperature monitoring LC0 requirements incorporated.
Additional information needed.
3/4 3-45 Pond Screen Howe seismic monitor-ing incorporated based on the R.G.
1.12 requirement to monitor an independent structure having a different response spectrum than containment.
3/4 3-48 and 3-49 Typographical error corrected.
3/4 3-56 LCO revised based on the site-specific Braidwood chlorine detection instrumentation design.
3/4 3-60, 3-61, 3-63, and 3-64 Typograhical errors corrected.
3/4 4-29, 4-33, 4-34, 4-35, and 4-36 Figure incorporated.
3/4 4-37 Site-specific changes made to the lead factor.
3/4 4-40 Figure incorporated.
3/4 7-12 Site-specific change to incorpor-ate ESW return valve surveillar.te requirements.
Attachment 1 PAGE
SUMMARY
-0F-CHANGE 3/4 7-13 Site-specific change to incorporate UHS surveillance requirements.
3/4 7-25 Figure incorporated.
3/4 8-10 Site-specific requirements incorporated for the diesel-driven AFW pump battery.
3/4-12-4 Site-specific drinking water surveillance changes incorporated.
B 3/4 2-3 Figure incorporated B 3/4 4-5 Typographical error corrected.
B 3/4 4-13 and 4-14 Figure incorporated.
5-2, 5-3, 6-3, and 6-4 Figure incorporated. Figure 5.1-1 is deficient by not addressing the requirements of 5.1.3 and by using the terminology " Lake" instead of " Pond." A revised drawing will need to be submitted by the applicant.
- 6-24 Incorporated the requirements of L Amendment I to the Bryon Station Technical Specifications.
i-l
0 6
4 BU.DSUIE'-2 BRAIDWOOD SECOND DRAFT TECHNICAL SPECIFICATION CHANGES 4
h ..
BASES SECTION PAGE 3/4.4.5 STEAM GENERATORS........................................... B 3/4 4-3 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE............................ B 3/4 4-4 3/4.4.7 CHEMISTRY........... ..................................... B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY......................................... B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............................... B 3/4 4-7 TABLE B 3/4.4-la REACTOR VESSEL TOUGHNESS (UNIT 1)................ B 3/4 4-11 TABLE 3 3/4.4-lb REACTOR VESSEL TOUGHNESS (UNIT 2)................ B 3/4 4-12 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>1HeV) AS A FUNCTION OF l FULL POWER SERVICE LIFE........................ B 3/4 4-13
' FIGURE B 3/4.4-2 EFFECT OF FLUENCE AND COPPER ON SHIFT OF RT NDT FOR REACTOR VESSEL STEELS EXPOSED TO IRRADIATION AT 550*F........................... B 3/4 4-14 3/4.4.10 STRUCTURAL INTEGRITY..................................... B 3/4 4-16 3/4.4.11 REACTOR VESSEL HEAD VENTS........ ....................... B 3/4 4-17 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS.............................................. B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS............................... B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK..................'............ B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT....................................... B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS...................... B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES.............................. B 3/4 6-4 3/4.6.4 COPEUSTIB LE GAS CONTR0 L. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-4
, DRAF DEC 021985 BRAIDWOOD - UNITS 1 & 2 XVI -
4 l
' DEFINITIONS O i.<:,
E - AVERAGE DISINTEGRATION ENERGY -
1.12 E shall be the average (weighted in proportion to the concentration of ^
s each radionuclide in the sample) of the sum of the average beta and gamma energies per disintegration (MeV/d) for the radionuclides in the sample.
ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include .
diesel generator starting and sequence loading delays where applicable.
,, FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:
- a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or
- b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to , interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or '
- c. Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.
MASTER RELAY TEST
, 1.16 A MASTER RELAY TEST shall be the energization of each master relay and s verification of OPERABILITY of each relay. The MASTER RELAY TEST shall incit.de a continuity check of each associated slave relay.
MEMBER (S) OF THE PUBLIC 1.17 MEM8ER(S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not.: include employees of the licensee, its contractors or vendors and persons who enter the site to service equipment or to make deliveries. This category does
] include persons who use portions of the site for recreational, occupational, or other, purposes not associated with the plant. ,
BRAIDWOOD UNITS 1 & 2 1-3 '
DRAFT C
DEcis1985
~
, t l
TABLE 1.2 OPERATIONAL MODES g .
% RATED AVERAGE COOLANT CON T
- MODE eff THERMAL POWER
- TEMPERATURE
- 1. POWER OPERATION > 0.99
> 5% > 350*F
- 2. STARTUP > 0.99 < 5% > 350*F
- 3. HOT STANDBY < 0.99 0 > 350 F
- 4. HOT SHUTDOWN < 0.99 0 350*F > T
> 200*F avg
- 5. COLD StiUTDOWN < 0.99 0 < 200*F
- 6. REFUELING ** < 0.95 0 -
< 140*F
, v. .
j -
- Excluding decay heat.
- Fuel in the reactor vessel with the vessel head closure bolts less than fully
) tensioned or with the head removed.
DRAFT MCo E85
~
.:c-
. ... :,, ac ; .w .y . n . . 5~i 5 i)- .
BRAIDWOOD UNITS 1 & 2 1-9 - . . ; ;,;_....
H . ;, , .
l l
- .l%e$N r- .
p
670
- t;. ._ f, -_ . -jg =="!=
i :";- = = = --d = g;;j= "--- ;.n :2 =gg g:M 2
.=.= o- - - - - -
~
--- - +
_. _ .,_ : _.~_5__:-._
-l-_: -,.;
660 h
=1(_ = -Z
=__
_. . _ . .._ g _. _._ .
1= 2400 PSIA t b =?
650
-- -- _- -s_.- _ .
5= ..._
. _ _ .== : _ . _-.. - - . .. g-5
..-. . = ...cA_ . .v ._..
_v_ ..
a ___=dh-, _ . _ _ . . . .
-~
Z Zk~ ~ . " - ~ _._ ; ;_-
_ . _ _w ._ ;_.
- 640 - - ' - -----
_.==- i-2250 rsia ---E - - - - -
x --
.__3_ A.
u=.
w _ _ . _
w_ _.......
CE . _ . .
_A '--~-h . __: -
b qr 'T-'q .
\- !:--
I w g --
_ . _ . _ v -
g 630
-- - * =
m x ._.
wg i
. . _4.._ , _ .
H '~~ ~~ ~ -
w Z;_.
.',Z'\I~~ .
Z. - _- r_ 5 ---Z Z - :Z:~ :.-'" :. .__ZZ _ ZZ Z... - C --=3 r*= . , M.
o Q:-- =t=-- __ =-K : Ej.= == -- - -a,--. - .M= **'- -M
@ 620 J- MY "-E- -
~
4M E ----
c-+- ==: N'55 -- --
= :- - - ZSk X
= =_ . -
_ .E:;'s;h
. _-c r;- \%
_ _. .__.- _I860 PSIA . . , . .a =_C. . _ . ___ . . .
T
____--- g:
. y -_-)_
. % ~*C - 21 "---
. .. . . . . . ~ ' ~ ~ '
~
(--
610 ,?-_ . . .~_ ~ .__~ _ _Z.. . Z_. T.._ ._ .q'E_;
-._ - . _ . . Z_. .__' ~~4 .Y,
-' _ __, _.m x
. .i . . _.-. . _ _ .._ r _
. 4_ . h-" . _ . . _. ___ . ._
__.N .i h.3_-
s
.#.= . _ _ --- -
--'3-600 - -
-ElfMiM 2Z = Eaa__ .
.=_._
a ~"-- - ~ ~
~ 'C - ---
_ _ . . EWFE=.i a _Zi-Ni-u_ _=l-.s _ __ _ . ..._._= _-. :_ -r--- =c-h.._. . _ . .sli\
.=;u. == --- -
._ . , . _ __ _ =
2- ::
-~--
...-= ._ mr
.- =- . - = =_
UN_. . =- _,
590
=1:.= =4= --
- - - ==s:s 55 s;- -iEEN
m_
=_
-= =j =- _._.. _..___ == :-t=
==.__. . _ . ..
.;_4.
=_}
. .= . _ _._=_4:, _,\ -
= . .
l I . .
b- _
_- bbhbk.EN:
itu -=q=n ==F == = ==E r =
=i 91= " =' =: =p :!:
580 -
to 40 60 80 100 120 POWER (PERCENT)
FIGURE 2.1-1 QRAFT g
REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION BRAIDWOOD - UNITS 1 & 2 2-2 i
v y
=
S TABLE 2.2-1 (Continued)
~
TABLE NOTATIONS (Continued)
, NdTE3: OVERPOWER AT ,i g (1 + tsS) 1
( tyS )
y ( 1 )
AT (y ,7s3) (y , 7s3) 5 AT, [K 4 - Ks 1 + tyS 1 + toS ) T - Ks D(y ,1 7s3 - T9 - f 2(AI)}
w 9=
Where: AT = As defined in Note 1, 1 + trS
= As defined in Note 1, 1+TS2 l
Tx, t2 = As defined in Note 1, 1 T5
= As defined in Note 1, 3
T3 = As defined in ote 1, e AT, = As defined in Note 1, K4 = 1.072, Ks = 0.02/*F for increasing average temperature and 0 for decreasing average temperature, Ec3 N TS 7
cm =
= 1+t57 The function generated by the rate-lag compensator for T,y9 dynamic compensation, '
ty = ~
Time constants utilized in the rate-lag compensator for T,yg, ty = 10 s, l 1
As defined in Note 1,
=
1 + tsS is = As defined in Note 1, l 4 E
1 l
l l
l 228 - . .
2n--
= - - -
w
_/
v.
200 -T_ . _.--_._ f ... -
- . y
/
_ .f.-; 8AN K B -
. -f 180 #
- .f I (100%,161)L 160 {(0%,162); .f
.j f --
I 140 ^
~l __
h =
i/ BANK C /
6
/- .i 120 -
s 5 / /
t: :-- : i f a 100 s
2 3" / #
w =_.,_
- - . - - -f
./
[
m - Z[ )$ BANK D 8
E m-ifs.c -j 60 . . _ _
- . - -- s-
? 40 (0%,47) .
.. . m y
_f
!(m,0.)7.
0--'"'~ 20 ~ -- ~ 40' 80 80 100 RELATIVE POWER (Percent)
DRAFT Roos mag FIGURE 3.1-1 _ ---
ROD BANK INSERTION LIMITS VERSUS THERMAL POWER FOUR LOOP OPERATION BRAIDWOOD - UNITS 1 & 2 3/4 1-22
i l
l 1
FIGURE 3.2-1 AXIAL FLUX DIFFERENCE LIMITS AS A _
FUNCTION OF RATED THERMAL POWER ,
l l
l
- Em :
- :w O :
"i .a i
-'m$:i i:2
$iNi at::z
- p. -:
100
-UNACCEPTABLEis(.11,90)._ EEE(11,,90)] UNACCEPTABLE VPERATJON --. i OP,ERATION
- - - s.-
.I~
80 _'
-i '.
.i '.
g ,f5ACCEPTABLEF: OPERATION,M, i '.'-
1
( 31,50) : (31,50)
~
e _
N z - r --
- 0
-50 -40 30, 20 -10 , 0 10 20 30 40. _50
~
FLUX DIFFERENCE (AI) %
HAFT 3/4 2-3 DEC 02 285 t
BRAIDWOOD - UNITS 1 & 2
, t Il to 7
h li i i i l I!!! I li ii! !!!! ]
!!ii Bli iI!!Ill!!!!!ill I i i i i! I iji ll l !! i l i 'l !
i.Is.0,i.0: g lii '!'! !T i
~
5 i i r!!
i !
ii i i ;..i !
l i Il j l- l l
' !i!
I i i l it i!!! ! ! ! li ! !!! 1 !I ! ii i i 'i i i l l i Il I li 'L 'i
~i iU 'Ii E !!.i II) r!]I I' '}llj,l_10.8, 0.Mi
@ . i.0 i
'8 iIII T ! - j i
.fI i ijh lj , [} f.'
i
,.E
.!M d
- ' i '
I i l it ,:fi .: ! 'l .' !I ! !
! i I
t fi!, l,jji. f, .{- t :::-- o f,ili I
. . 7.1. ,:
. I. i.l i 1
l
- p -
1 ll 1 ! : -
i i l L 3l e=
' i -l !
N O.8 .1
' i' j
! I '(
E~
I i .
l
! l i i i l i i 'I
, s d . I. i I I
. [ l(
' I O I *I s'i II ! i 8-
"ll
'! ins
' i i
(12.0. 0.'05; "
tl8 l I l.i i ll i l:; ,; .I : ! t 1 8 .
J l0.8 ,
r r -
n ti ,I
- l w 3 . . ; : <j
- s g . 1.
- 2 : (- i i {.
- O .jjj j j i l [ ; l j ii., jj ! ; l as a i l i 1
u, a .
'I. } l !. ! ,
s jjj i. j .
l l j"ll l. l
- _, g,4 .
ti* . t .I i "i 'l !'
I I ,. -
i l l I l I
j .
i i
. t. ! !, l 1
1 i li i i
- . .i -
j i 1
. 0.2 3 . .
! i i l I I i Li
' ' ~
0 l g
'g ! 0 . 2 4 4 3 10 12 14 16 N
f a CORE HEIGHT IFT) -
' lz:
OT W -
FIGURE 3.2-2
- i KIZ)- NORMAllZED Fo(Z) AS A FUNCTION -
! OF CORE HEIGHT -
l 1
w.,
f TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEAiURES ACTUATION SYSTEM INSTRUMENTATION E
O
- MINIMUM 8
TOTAL NO. CHANNELS CHANNELS - APPLICABLE g FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION ti
- 9. Engineered Safety Features .
H Actuation System Interlocks o.
to a. Pressurizer Pressure, 3 2 2 1,2,3 20 P-11 -
- b. Reactor Trip, P-4 4-2/ Train 2/ Train 2/ Train 1, 2, 3 22
- c. Low-Low T,yg, P-12 4 2 3 1,2,3 20
,$ d. Steam Generator Water Level, 4/stm. 2/stm. gen. 3/stm. 1, 2 20
,, P-14 (High-High) gen. in any gen. in 4, , operating each
,o stm. gen. operating stm. gen.
'10. ' Steam Generator Blowdown ( ) ( ) ( ) ( ) ( )
System HELB Isolation
- 11. Auxiliary Steam System ( ) ( ) ( ) ( ) { }
p HELB Isolation Q.
2e;
-tQ)
D / THIS PAGE OPEN PENDING RECEIP1 OF W-4
, ,o g
w me b INFORMATION i dJM THE APPLICANT
'h -
t,.J.' - -g M2.t ?
g-44
w-TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION TRIP SETPOINTS TOTAL SENSOR TRIP ALLOWABLE o FUNCTIONAL UNIT ALLOWANCE (TA) Z ERROR (SE) SETPOINT VALUE i
E 8. Loss of Power U a. ESF Bus Undervoltage N. A. N.A. N.A. 2870 volts >2730 volts.
N w/1.8s delay w/11.9s delay 8' b. Grid Degraded N Voltage N.A. N.A. N.A. 3804 volts >3728 volts w/310s delay w/310 1 30s delay
- 9. Engineered Safety 4
Feature Actuation System Interlocks u .
) a. Pressurizer Pressure, '
w P-11 N.A. N.A. N.A. 11930 psig 11936 psig ,
- b. Reactor Trip, P-4 N.A. N.A. N.A. N.A. N.A.
i
, c. Low-Low T,yg, P-12 N.A. N.A. N.A. >550*F
>547.6*F 37j
- d. Steam Generator Water See Item 5.b. above for all Steam Generator Water Level Trip Level, P-14 Setpoints and Allowable Values.
(High-High)
- 10. Steam Generator Blowdown ( ) ( ) ( ) ( ) ( )
System HELB Isolation
- 11. Auxiliary Steam System ( ) ( ) ( ) ( ) ( ) -,
- HELB Isolation
'l
,?
ho ."23 M
THIS PAGE OP&l PENDING RECEIPT OF INFORMATION 1-ROM THE APPLICANT
', to y b
m
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- 7. _ Steam Generator Water Level-Low-Low ,
- a. Motor-Driven Auxiliary Feedwater Pump -<EG
- b. Diesel-Driven Auxiliary ,
Feedwater Pumps 160
- u. (
- 8. Containment Pressure-High-2 Og e<u Steam Line Isolation 17 $g U n.
- 9. RWST Level-Low-Low Coincident with Safety Injection Eg g,
Zr Automatic Opening of Containment '-<100 5*
Sump Suction Isolation Valves Z$ -
[O .
- 10. Undervoltage RCP Bus 7 f
"' Z
- a. Motor-Driven Auxiliary Feedwater Pump 160 $o
- b. Diesel-Driven Auxiliary Feedwater Pump 160 ,g O
- 11. Div kion 11 for Unit 1 (Division 21 for Uni' 2) ESF Bus Undervoltage
<1 ac U Q Motor-Driven Auxiliary Feedvater Pump 160 f. Z
- 12. Loss of Power
- a. ESF Bus Undervoltage 11.9
- b. Grid Degraded Voltage 1310 1 30 delay
- 13. Steam Line Pressure - Negative Rate-High (Below P-11)
Steam Line Isolation 17
- 14. Phase "A" Isolation Containment Vent Isolation 17
- 15. Auxiliary Feedwater Pump Suction 7 Pressure-Low-Low 5#31 l Automatic Switchover to ESW N.A.
- 16. A ca Temperature N
- a. Steam Generator Blowdown System ( )
HELB Isolation
- b. ' Auxiliary Steam System HELB Isolation- ( ) .
, BRAIDWOOD - UNITS 1 & 2. 3/4' 3-32 . , , , _
f sr q; ;; y . ~ , , ; . .eq :_;
, f ., ^ ; . ,_
E CD NE HAR II L.
C I 4 4 4 4 '
U , , , ,
HIQ SWEE 3 3 3 3 3 3 3 E VR )
DRR , , , , , , , ) d OOUS 2 2 2 2 2 2 2 2 -
e MFSI s
, , , , , , , , " s e 1 1 1 1 1 1 1 1 ( ( a g _
p a _
EY ' ) ) y t VAT . . . . . . b l ALS o -
LEE A. A. A. A. A. A. e .v SRT Q N s N N N N N Q ( ( b1r t
.e -
R EY n
e ) ) y a 2. d n .
TAT ) m . . . )
SLS 1 e
1 m 3. u AEE ( A. r A. A. A. A. A. ( l4n MRT M N i N N N N N M ( ( e a u nn q non T e aii N NS R hta O OE cat I IT e cn T T c ) )
eii A AC n )
lfa T UI ) . a . . . . . .bim l
TG 1 l 1 Sac l
E CO ( A. l ' A. A. A. A. A. ( I ret M AL M N i N N N N N M ( ( Sepo U e A pS n R v Bo nro T r S L u Tied p
N A S S I G N E n N O n TAl ey M I I o N E S TET i O D nl
) T T ACA t ) ) I E .nn d S N PUIRT . . c ) ) . . . T Ryao e Y E ITVES e 2 3 A Elh u S M RCEPE A. A. j ( ( A. A. A. T Gtcn n E TADOT N N n MM N R N N ( ( O Gn o i N R I N AeEi t O I L TdLt n I U A y E SnBa
- T Q N t L eAi .
C A E O e B a pR c y
( U R LI f A eEna T GET a T ndPul 2 C E ONA S ) ) onOne
- A C LNRT . . . . i nr 3 N AAES l s ea y S A NHPE A. l A. A. A. ydh 4 E L ACOT N M a N N M N M M ( ( aetma R L di rl E U I r D ffae L T E N o 2iold B A V O f 5 . 6r a eg e A
T E R F U S LA I
T e v
o y Of O a
Z ,$ h c) ,$$"Q] yvndm r eetat ini Y
T E
ER NB NI .
b a' ,
m{3 Em g@gg i.
vbs e
otth eye F AL A.
A HA . .
E tt it S CC N R 1 R R R N R R ( ( s el ascir D m einbo E L e l aaf R E t yl r
_ E NK I ) ) ttl et aii p n E NC . . . . . .
N AE e A. A. A.
l eoi o
I HH A. e A. A. div G CC ) N S S N N N N N S ( ( ebryp N d tauat E e s srsl e u k ee es n e ec , r tprr
_ i e g ro e e n oo e
_ t nn g a ul r t w e feh n oo w a t tr u 2 a o m by gt
_ o ii o t l ae s 4 1 W dn e asa C tt L n l o et s - - wo t ll rtd
_ ( aa - ho o V Fn e P P r oi s l eul n uu wti v I r o l t y arooo g tt oit r d y P , , t ,Ba S h hvy n cc LWc e e tm p l se g2 e b re i AA - e d d ee r i r4) ro m na n ltj n a ft e r 1h os an d e cd enn r U r as z T T n- g tI eo itonn T p in veI e g Syi epi a ti al tuo I O ta ed w s e S r r wG ,H rB St ro i N a s Liy o u D d u o o - el a - t v p yt U c mcy ct P B en s t L mlh nij yl rufi
- i oia Tne d ro c - aeg eH ro he id L t t gl Sif f F i ei a w evi G as cdrrn A a uoe Woa o S r et r e o teH m iI anoeo N m ALR RCS E G na R L SL( me l EUfVc
_ s O o iu at iB es xL I t s gt T u . . o . . nc . . . . ty uE
U . . . 0 1 12 3
_ F 7 8 9 1 1 (( (
1 e s
""[ ,5 $c o
_ > e8ohoi Mg*T,f9i *,. g -
Fh wh
~
. ' .i
'l fy0gi5 i -
' ,N yl d 5]' QI .b Oo;,g5' '
TABLE.3.3-7 SEISMIC MONITORING INSTRUMENTATION !!.
MINIMUM MEASUREMENT INSTRUMENTS INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE
- 1. Time - History Accelerographs
- a. Aux. Elect. Rm, OPA02J N.A. 1
- 2. Triaxial Peak Accelerographs
- a. Cont./ Reactor Eq. Accumulators -2 g to +2 g 1
, b. Cont./ Reactor piping -2 g to +2 g I
- c. Aux. Bldg./ Cat. I piping -2 g to +2 g 1
- 3. Response-Spectrum Analyzer 5 *~-
Aux Elect Rm, OPA02J None .1
- 4. Triaxial Atceieration Sensors
- a. Cont./10W - 377' -2 g to +2 g 1
- b. Cont /10W - 502' -2 g to +2 g -
1
- c. Cont./10X - 426' -2 g to +2 g 1
- d. Free Field /39 + 00E, 41 + OOS -2 g to +2 g 1
- e. Aux. Bldg./18N - 426' -2 g to +2 g 1
- f. Braidwood Pond Screen House -2 g to +2 g 1 l
i .. -.
3 DRAFT m,.
. BRAIDWOOD - UNITS 1 & 2 3/4 3-45 ..
6 TABLE 3.3-8
) METEOROLOGICAL MONITORING INSTRUMENTATION ;
' MINIMUM INSTRUMENT LOCATION OPERABLE 1, Wind Speed Nominal Elev. 34 ft 1 Nominal Elev. 203 ft 1
- 2. Wind Direction Hominal Elev. 34 ft 1 Nominal Elev. 203 ft 1
- 3. Air Temperature - AT Nominal Elev. 30 ft/199 ft 1 l
. ilk-DRAFT KC O2ses x
BRAIDWOOD - UNITS 1 & 2 3/4 3-48
. t l
A -
TABLE 4.3-5
--) ..
METEOROLOGICAL MONITORIflG INSTRUMENTATION SURVEILLANCE REQUIREMENTS
_ CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION
- 1. Wind Speed
- a. Nominal Elev. 34 ft D SA
- b. Nominal Elev. 203 ft D SA 2., Wind Direction
- a. Nominal Elev. 34 ft D SA 5"--
- b. Nominal Elev. 203 ft D SA .
- 3. Air Temperature - AT Nominal Elev. 30 ft/199 ft D SA l
)
DRAFT 4 INE0 0 2 1985 xs
)
SRAIDWOOD - UNITS 1 & 2 3/4 3-49 '545
INSTRUMENTATION CHLORINE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION i 3.3.3.7 Two independent chlorine detection instrumentation channels, with their l Alarm / Trip setpoints adjusted to actuate at a chlorine concentration of less than or equal to 5 ppm, shall be OPERABLE.
APPLICABILITY: All MODES.
ACTION:
- a. With one chlorine detection instrumentation channel inoperable, re-store the inoperable instrumentation channel to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain operation of the Control Room Emergency Ventilation System in the recirculation mode of operation.
- b. With both chlorine detection instrumentation channels inoperable, l within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the Control Room Emergency Ventilation System in the recirculation mode of operation.
- c. The provisions of Specification 3.0.4 are not applicable.
~
SURVEILLANCE REQUIREMENTS 4.3.3.7 Each chlorine detection instrumentation channel shall be demonstrated OPERABLE by performance of a functional test in accordance with the manufac-turer's recommendations at least once per 31 days and a CHANNEL CALIBRATION at least once per 12 months.
7 MAFT DEC 0 2 1985
~ .
BRAIDWOOD - UNITS 1 & 2 . 3/4 3-56 ,,. a ,_
m y r n, w ,sp + ,yg
- ~ ...
. . .: . , m
TABLE 3.3-11a (Continued)
~
' i FIRE DETECTION INSTRUMENTS l
, (UNIT 1) i INSTRUMENT LOCATION INSTRUMENT TYPE
- TOTAL NUKSER OF INSTRUMENTS
~
Heat Flame Smoke
- 6. Station Battery Room Zone 67 Elev 451 Detection 13
- 7. Diesel Generator Room Zone 37 Elev 401 Suppression 6 Zone 38 Elev 403 Suppression 6 Zone 71 Elev 401 Detection 1 Zone 72 Elev 401 Detection 1
- 8. Diesel Fuel Storage 4.
/ Zone 39 Elev 401 Suppression. 1 Zone 40 Elev 401 Suppression 1 Zone 27 Elev 383 Suppression 3 Zone 28 Elev 383 Suppression 3 Zone 10 Elev 383 Detection 6
- 9. Safety Related Pumps I
Zone 41 Elev 383 Suppression 2 Zone 42 Elev 383 Suppression 1 Zone 16 Elev 364 Detection 2 Zone 18 Elev 364 Detection 10 Zone 19 Elev 364 Detection 3 Zone 20 Elev 346 Detection 3 Zone 21 Elev 346 Detection -
3 Zone 11 Elev 330 (Unit 2) Detection 23
- 10. Fuel Storage Zone 39 Elev 401 Detection 26 Zone 38 Elev 426 Detection 3
- 11. Auxiliary Building Zone 70 Elev 451 Detection 11 Zone 17 Elev 364 Detection 37 Zone 40 Elev 364 Detection "
7 Zone 11 Elev 383 Detection 37 Zone 8 Elev 401 Detection 36 Zone 23 Elev 426 Detection 6 Zone 25 Elev 467 Detection 7 Zone 64 Elev 401 Detection 5
Zone 65 Elev 401 Detection D ) 5 Zone 14 Elev 401 Detection U g 4
) 2one 15 Elev 401 Detection 4 M0 02 E 3/4 3-60 BRAIDWOOD - UNITS 1 & 2
U TABLE 3.3-11a (Continued)
.) FIRE DETECTION INSTRUMENTS p' (UNIT 1)
~
' INSTRUMENT LOCATION INSTRUMENT TYPE
- TOTAL NUMBER OF INSTRUMENTS Heat Flame Smoke
- 11. Auxiliary Building (continued)
Zone 17 Elev 346 (Unit 2) Detection 32 Zone 40 Elev 346 (Unit 2) Detection 12 Zone 12 Elev 459 (Unit 2) Detection 11 Zone 22 Elev 467 (Unit 2) Detection 18 Zone 62 Elev 451 (Unit 2) Detection 11 Zone 61 Elev 439 (Unit 2) Detection 7 Zone 75 Elev 426 (Unit 2) Detection 33 TABLE NOTATIONS
- A single detector in a zone marked " Detection" will alarm in the Main Control Room. A single detector in a zone marked " Suppression" will initiate suppression and alarm in the Main Control Room.
') **These are Containment Ventilation temperature switches. Upon receipt of a Hi-Hi temperature, suppression must be manually initiated. These switches are not 72D supervised.
- The fire detection instruments located within the containment are not required to be OPERABLE during the performance of Type A containment leakage rate tests.
^
- DRAFLe . . s DEC 021985 D k e
BRAIDWOOD - UNITS 1 & 2 3/4 3-61
, _ _ _ w . - , - . ~ ' ' ' '
TABLE 3.3-11b (Continued)
FIRE DETECTION INSTRUMENTS D,
(UNIT 2) .
INSTRUMENT LOCATI'ON INSTRUMENT TYPE
- TOTAL NUMBER OF INSTRUMENTS Heat Flame Smoke
- 6. Station Battery Room Zone 67 Elev 451 Detection 6
- 7. Diesel Generator Room Zone 37 Elev 401 Suppression 4
. Zone 38 Elev 401 Suppression 4 Zone 71 Elev 401 Detection 1
. Zone 72 Elev 401 Detection 1
- 8. Diesel Fuel Storage Zone 39 Elev 401 Suppression 1
- 4. . Zone 40 Elev 401 Suppression 1 Zone 27 Elev 383 Suppression 3 Zone 28 Elev 383 Suppression 3 Zone 10 Elev 383 Detection 6
- 9. Safety Related Pumps '
Zone 41 Elev 383 Suppression 2
) Zone 42 Elev 383 Suppression 1 Zone 16 Elev 364 Detection 2 Zone 18 Elev 364 . Detection 3 Zone 19 Elev 364 -
Detection 2 Zone 20 Elev 346 Detection 3 Zone 21 Elev 346 Detection ~
3 Zone 11 Elev 330 Detection .
23
- 10. Fuel Storage f
Zone 39 Elev 401 (Unit 1) Detection 29 l Zone 38 Elev 426 (Unit 1) Detection 3
- 11. Auxiliary Building .
% #3 : "
l Zone 17 Elev 346e: - ; -
Detection ? . - - - -
32 Zone 40 Elev 346 Detection 12 -
Zone 22 Elev 467 Detection 18 Zone 62 Elev 451 Detection 11 Zone 14 Elev 401 Detection 4 Zone 15 Elev 401 Detection ~
4 Zone 64 Elev 401 Detection 3 Zone 65 Elev 401 -
Detection N 3 ;
Zone 61 Elev 439 Detection 7 i Zone 70 Elev 451 Detection 11 DEC o 21985 BRAIDWOOD - UNITS 1 & 2 3/4 3-63 _.
. :" Y.-
9
l TABLE 3.3-11b (Continued)
')
FIRE DETECTION INSTRUMENTS p,'.
(UNIT 2) '
INSTRUMENT LOCATION INSTRUMENT TYPE" TOTAL NUMBER OF INSTRUMENTS Heat Flame Smoke
- 11. Auxiliary Building (continued)
Zone 75 Elev 426 Detection 33 Zone 25 Elev 467 Detection 7 Zone 17 Elev 364 (Unit 1) Detection 37 Zone 40 Elev 364 (Unit 1) Detection 7 Zone 11 Elev 383 (Unit 1) Detection 37 Zone 8 Elev 401 (Unit 1) Detection 36 Zone 23 Elev 426 (Unit 1) Detection 6 Zone 12 Elev 459 Detection 11
- 4. .
TABLE NOTATIONS
- A single detector in a zone marked " Detection" will alarm in the Main Control Room. A single detector in a zone marked " Suppression" will initiate suppression
) and alarm in the Main Control Room.
- These are Containment Ventilation temperature switches. Upon receipt of a Hi-Hi temperature, suppression must be manually initiated. These switches are not 72D supervised.
- The fire detection instruments located within the containment are not required to be OPERABLE during the performance of Type A containment leakage rate tests.
~i =
MAFT DEC 0 2 1985 a
BRAIDWOOD - UNITS 1 & 2 3/4 3-64 "* ifMl4
~
~ T E (
2 ,
c o*
250 \1 t- \ n E
a k\
b 1.
> i h*
4 "
I h UNACCEPTABLE '
O \ OPERATION 1 h o r E \
m .
z 150 \
$ T -
o k O ' -
0 A g
-, \ <
< \
E '
(
g 100 -
- n. ' t u \
g e
2 , ,
T p
'Z ACCEPTABLE k
$ a ^
- i. OPERATION ,
l -
,4 g t '
- s 5'
0 w
m \ -
x m =
7 O s' s O
0 -~~i >
20 30 40 50 60 70 h ^80 90 100 I
PERCENT OF RATED THERMAL POWER g witng g FIGURE 3.4-1 7 DEC 0 2 1985 DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVLTY LIMIT VERSUS PERCENT OF', RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY > 1pCi/ GRAM DOSE EQUIVALENT I-131 1
BRAIDWOOD - UNITS 1 & 2 3/4 4-29 9
i
' ' e l 3000 '
l 12AK TEST LIMIT
/ J /
- / /
' / ; ;
2000 I
~~ f j ) I
- t (
E i )
8 ( l
/ /
t l l 8 i !
> / /
O EEATUP RATES j i 5 1000 UP 70 60'T/ER
/
( x
~
/
CRITICALITT LIMIT .
/ BASED 05 INSERVICE NTDROSTATIC TEST
/
-' TEMPERATURE (267'F) .
FOR TEE SERVICE FERIOD UP TO 32 EFFT *
~
0 0 iOO 200 30: 400 INDICATED TEMPERATURE (T)
DRAFT DECog39g5 FIGURE 3.4-2a REACTOR COOLANT SYSTEM HEATUP LIMITA710NS APPLICABLE UP TO 32 EFPY (UNIT 1)
BRAIDWOOD - UNITS 1 & 2 3/4 4-33
l l
l
- 3000 1
\
12AR TEST LIMIT i ) i
- n. ! l l 8
2000 / / /
/ /
/ ;
/ /
l
& f Y
f
/ /
/ /
/ /
(~ "- . A ,,TEs / /
UP To 60*F/ n _/ /
< %1000 !
CRITICALITT LIMTT h /
7 BASED ON INSEnv1CE
/ BYDaOSTATIC TEST
- /
/ TEMPERATURE (255'F) ron m stav1c1
+ "'
PER1oD UP To 16 EFFT "
n_, 1 9 100 200 300 400 EOCATED TEMPERATURE - DEG F FIGURE 3.4-2b REACTOR COOLANT SYSTEM HEATUP LIMITATIONS
- .DEC 0 21985 '
APPLICABLE UP TO 16 EFPY (UNIT 2)
BRAIDWOOO - UNITS 1 & 2 ;/4 4-34
3o00
/
E ;
I 2000 /
- )
)
(~ y e .
1000 4 /
coauca un rm j?
vdV/
~
_ *% -- - 183?/
,_ so 60 k &
=57/
.- 100 % ' f o
$ ioo 200 soo do N'HCATED TEMPERATURE - DEG F FIGURE 3.4-3a T REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS _
APPLICABLE UP TO 32 EFPY (UNIT 1) ~ DEC 0 21985 BRAIDWGOD - UNITS 1 & 2 3/4 4-35
4 b_ _ _
i~
L1
)
r O. /
I 2000 I
/
M l
( /
1000 /
4 j.
,_ -- cootaan wn *s/n S
,ar o -- P 20
'o
&bf/
- Es>;/
- ---- so, , ,'
loo s }'
O 100 200 300 40u EOICATED. TEMPERATURE - DEG F ,
, FIGURE 3.4-3b REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS APPLICABLE UP TO 16 EFPY (UNIT 2) -
DEC 0 21985 BRAIDWOOD - UNITS 1 & 2 3/4 4-36
w - -
J' TdV 42
? ;:
~'
- eo TABLE 4.4-5 fr b REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITHDRAWAL SCHEDULE UNIT-1 o -
I
'E CAPSULE VESSEL LEAD Z
NUMBER LOCATION FACTOR WITHDRAWAL TIME (EFPY)*
'N U 58.5* 3.6 1st Refueling e
.t . "
X 238.5* ,
3.6 6 o- V 61* 3.0 10 Y 241* 3.0 15
. j. w W 121.5* 3.6 Standby 3
,.3 2 301.5* 3.6 Standby ,
,b UNIT-2 U 58.5* 4.05 1st Refueling W 121.5 . 4.05 4.5
?O 8.0 X o2 238.5* 4.05 to b h V 61* 3.37 15.0 Y M 241* 3.37 Standby --
Z 301.5* 4.05 Standby 1
- Withdrawal time may be modified to coincide with those refueling outages or reactor shutdowns 1
- 7. , most closely approaching the withdrawal schedule.
e?:
e: . .s.
4
7:.
U
' L i: . '
.;;: lb! l $ ,i[t , ;;;,; ; 7;y j; ;} ej % y[ yJ ]7 31.{*- .
i*I 3)! -E ' iUjMi. dii ?! -HI : --
- .; !;p d!i i'i: -idj[i i di 1[;j rijpih1.y2.ii i idi'IEi isi %Eiiii lii is iH-si 41: .n!4H I .
j; iii "3 d;i mi i!!-# i-0j." ij: ip di =- ;;p4i- pii g~- :q: 33 as
. , , , ;ie- # =msi amw:4mir Jim , s '
ihypi; g w; e 3m :. g s. F.r. > r=.= e x g
$!$du 'I=::i 45i !!h iUi 's iii !if @ ! i: Fil' h dii dilig.: ;Ib : ; l@ p,;;p .g .jij :in E*;=:g_ - cf.fi: E -
.E_T ,b Y-dI! ii? E nid:# :iE!!!. :
N- :N; .uf ! -il! lh -dfihji !ih #i #. .iii. ii.!
. i}i. i .l.i.j 4 ~. . ~ .~. . ...r . . MF -t-:n . = . . i.f. .
35i 5' h N 3 2 -
hiii 1 i'h Ni NE i'hi! if1 ij!' iji Mb !!! h fjhNh .: hijp
- ii si rH iiiidij'ii;
- = :
5:: Tij; :j i :p; i di ;ifi j;p y7 ;@ !!;rh:F $. : Sh Qh :iii Hid .
.i:-
25NI- :
i f3ii" :.:i NE dii iiF Hii iiU di iP! i lNi 1 3:- iip $i lN: ljji lI i; iis@ .:p = iib ;;ij ly:i:3;j m. :n: ui EipIJJi rdM!p: iii iii "ii
- d- dii !ip-hi :E [i j;p jpi yi .jp :liiyp ;ii. .; 2:l Fqii j;i}. . gig ,a{.;
IdlEE:$3F i@ s^iEi 2!i lii -
h .
!$jjp lii pi! itij[4; JF Ii- h!. :p. a.;; :;: :9; lig:p [.. 3p g.
a IENIi lifiE$lilii! ih! S :: :p 3 E jdj ji!. .it (j 'ih iliUfi fl iij F.10- 22:4 :> lie i E :
- ib Ph - .
i i ijdE.! Idili!: -
"/ L= iiii i: iid: Ph@: - --:- 4- - " - - -
-$i .u. u;:: ..:1Agil A
~ ~
!.lii:: * :j-: Selected Peint en des Caerwe: ;$ Z $: U. $ 'c;p
- "' :-- 'IU :m": .. .~ =.
ii mas
- . 1 :
i ::. - . ,iiii i.j.
- ij-fi! .
- . . p. .i f d(ii
,,,, in:_iIF y --. -. ..=
. ~ .= . .". . ; .~_r.__. ' . . ..
,E %n:
- F'i- -C i: .. I TI:;: np isneiflii im !:i= iiiinin .ii 5'i;.g ;y :.:
Y i # ff
~
N E M 9 E 'M- 4f:.:;- :---- "E iii.- :=; :: : ::.niibs.
.~.'.
3 g - -- -- --
~ - - " -- -
-e=- :r= +m m ; e =*e p"mi ai em@;- acsas=#
l =z.=
".5E
==Ea:ic ei :Wi!==di e=.=_n.,
h =
fh s.a
'ndil m
as _m.ess me imm.
{$$!!#I.En-s;tw-.u.,rs.w..e.. .m.u. . _.1
- 9*:4Ig)iii: Ej 25 "-==
h;=i := m=i=
r du F~-'
f ggp=sgwie 5
1'.551513"
- "n. . . .e. .w.. ..e:e
==- = .ii Iqq i:i) i.
.g .
. #i iidii ti5253 '-T : :.F EG qFir"r::=:t; ::dii!;i 3hriji -si UE di:ir :i :: lMii'-iii? 'i ; :- :;i:hri. ,
_.g iil3i Id '. . ! "jgip ih: F;; iip-ih: -:ui :52i=::E. :n' :.Hyrr 13. :.4. .;.;;;3:.g tgg ;;.;
- jyFqg;
- 7;t_;.
. r-..
_#_ % MEi:isfiii s h::7si Bjk4 Pi: # .= sr:i' 2-Ts ii:iili: imtiu iiii:F j ::iN -* i [! iip 5::it'. @Mi ns :.F. -
. _.I 2dS' N'@ Mi&I i k! i !ii!!! hEEi!E iii: =il ji ~'"ilii: iiii Tr' di:isi "2 -
u.y JEijEr Qj a.ii!S-i ;jl{i-siE@ ff gj =p, :4jjj; ipt. gj gj{p: .,= ;gggg gpji;g= giig 3 g :=x= - agig ;34; "dEIf!EIIN#N$iE SF '..N.klEj?.h .7,p ; : ."IE T: a: -, gip _ Hr is]!!I!!!! : glE"
"=
5==" '/tilMii'E~
i5}is i.d5i5 N dE iui:IiNiF difi -$ REiE :P isi #111; :--tij.i u.,. !5-#iik iih!-ip [ Q ig " d".!:LEM;i.
iE!iE ~ihT;;i idi l' ih T.N.t:~ij 5 "" iii. Ici15; Eii.n ::i"i- ]ic
=
=_t = -
fj:lE j'u)G :.:.jaEg-irsig pi.
l' 5-5 i!SNS33IF- E ainii;22:iih 2 -# '
au 9. .= f ];', - up {g egj didgi- l.gicg- jjj-jg.
=s qb4si2-e + := sig. di-w g ;;; 2;s;- uiaai: i s; .a = i y;y:.:a: ;. . jia.E=1ep=g.jy.q=r
[
=
ith: hhih :i i= i 3 :s ! a. : :iiig: -spm .. ;p;gaiie=g rg j.i. :j ;g_gg q_ g d!!!i: lib. is rii! M; = ::.-:iF: r-ii: 'jji i 2iiji3; i g usi sii i:.i1:p [. - :1,m: in:ggir.jpgi i :.i.g: gi..
j N:35i :N ' 'n "** ::::F : M m '-Mg .. .. m u.. g j n :. ; ._ _ _E;-L;:- n:)i-i ;;-gu
- s. reg .p; sm g[. - g g3ig 3:3=. g.;g
=gi; == :a i=- : :. ggx=j a; ism m 5:y:7 .;
12--i=!
-i=:i t=4!F i =*
aiF-" " . . . " . . -/ "up :- = . . . .:=.~= =._=_=.-_ . " :==.4=
1 et=.
.ni i;-. ecF si+43g =-ih=p : sim: , u,,:w m= fs .y # i3i. ;'x:=:e;... x. . . .
~ - - " -- - -
rw= =n i.:nr,:. n- r r.m.e f4eim*w=m' ' E= a'=w;g-m a w:: a . . . sr
.a _
Hi If 5 I$ !Ei5 E!! 'E 'ii.: 2N}Edj iij iiii ! iii:
~
- "i i" Hf;i icij ip i : Ji-i@iD Ei:Ej.i:.ljiEiTsi-:.!!iig-ij 35 E I5i5!!!f tE: 5 : := --ifi}h "Fiib iiii SI: iG}dj' :. M4pirl@ @ = ;T: li1@ji:i ).. ]j : =- E-i.,i ,
m ! iiii iiii iLi iiji :ni , i9 y iHi lii try : ini j 5:pil. f q!ilusijg;!si: Erip ::n.g gg=..sgi.3 ::3; : jij-qiij: =- gL. aa .g. ;.g. .: .p..
_ q. .-. . . . . . .
. .q. .. i.
- r. . .- g.:
7_,. g gg. .g. qgg33; ...r_
g:.g
,_- 55'i'. *N- [i -
i I-?-5: j N- ;fii,351[J;; p ,TCl4g? ji
.. .9 :" i. s! i:p @ iujQp iih ; jii yh zu j:-;=; ;}i 'gj dij :ii. : i;I: ;i:
-"-i n
.:u:. p.
.. ._ .:. . . .M .R - -
.a.up : :- npai . dip"y"i-i! gi= g:igj,ipu up :-
.a:i . .:$ q. . . . . .2 : m!: - m.
.h.. .:.= . .:; -
-NF ;i!i hi! n- i .'iliti FF F ; up is tu. 45 f i :j lpi4: ia! E gn4p .
- p
- =j -2.y!@:.jjj4fii . u.. 4:y[:j
-j'jiij " in. :ih ig: dii iti . !:- i -
n! i.1:ziji.i:l iihi a iij[ditti:!
-  g LIMITING CONDITION FOR OPERATION 3.7.5 The essential service cooling pond (ESCP) shall be OPERABLE with:
- a. A minimum water level at or above elevation 590 ft. Mean Sea Level, USGS datum, and
- b. An essential service water pump discharge water temperature uf less than or equal to 98"F.
APPLICABILITY: MODES 1, 2, 3, and 4 ACTION:
With the requirements of the above specification not satisfied, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS I
4.7.5.1. The ESCP shall be determined OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average water temperature and water level to be within their limits.
4.7.5.2 The ESCP shall be determined OPERABLE at least once per 18 months by the performance of a hydrographic survey to verify: -
- a. That the ESCP bottom elevation is less than or equal to 584 feet.
- b. That the ESCP slopes exhibit no excess degradatior.
DRAFI M 0 2 198 5
,.x ,
BRAIDWOOD.- UNITS 1 & 2 3/4 7-13 _-
I .
10 9 _
8 7 )
- REJECT g
G,
3 2 f CONTINUE TESTING . m
/,
.- 2 / ,
1 l
ACCEPT l- 1 r
}
10 20 30 40 50 60 70 80 90 100 N
, DRAFT FIC'JRE 4.7-1 _
C 0 21985 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST BRAIDWOOD - UNITS 1 & 2 3/4 7-25
ELECTRICAL POWER SYSTEMS 3/4.8.2 D.C. SOURCES g
l OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1* As a minimum the following D.C. electrical sources shall be OPERABLE:
- a. 125-Volt D.C. Bus 111 fed from Battery 111 for Unit 1 (Bus 211 fed from Battery 211 for Unit 2), and its associated full capacity charger, and
- b. 125-Volt D.C. Bus 112 fed from Battery 112 for Unit 1 (Bus 212 fed from Battery 212 for Unit 2), and its associated full capacity charger.
- c. 24-Volt D.C. direct-driven diesel auxiliary feedwater pump battery banks and associated chargers.
APPLICABILITY: MODES 1, 2, 3, and 4.
CTION:
- a. With one of the required battery banks and/or chargers inoperable, restore the inoperable battery bank and/or battery bus to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With the normal full capacity charger inoperable: 1) restore the affected batte.ry and/or battery bus to operable status with the opposite units full capacity charger within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and 2) restore the normal full capacity charger to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.8.2.1.1 Each D.C. bus shall be determined OPERABLE and energized from its battery at least once per 7. days by verifying correct breaker alignment.
~
l l 4.8.2.1.2 Each 125-volt battery bank and its associated charger shall be demonstrated OPERABLE:
- a. At least once per 7 days by verifying that:
- 1) The parameters in Table 4.8-2 meet the Category A limits, and l.
A '
- 2) The total battery terminal voltage is greater than or equal to 126 volts on float charge. -
- This s;5ecification is only applicable prior to Unit 2 operation in M005 4.
t .
BRAIDWOOD - UNITS 1 & 2 3/4 8-10 . >~. .
& & ff
?(%]f': . , :y: ~ Gf:Qj,ys%Q:gh. r,
' -!)
m m
) ) u ro
. i - eC 4 n ) yt .
y ( o pt ) y
. t si 4 l r r i ma ue)g l
) y
. i it
- I r
h sesr
- v dsa sre t
( r l i nyc i ot n g(8 a eot s r e e k :t sfr d coo .asf r Y
t e r cg al al o y a n adcsrty a s e e a n latqeu a . e iael eu C
N i
n w l p ig ay o ni y e 'e ebat q E
) l nhhry ni n s m d o ; c (b ass 4 r ott e sass U a i a al ei oiI e trs oi QS C s S rl gpe cps ct snraeocps EI y onot imyir i eowprimy RS e l e afati pol pa shf gpol FY L
n a n
t t a escsol hosy t
oCa ou yw n tq l dhert em oCa i
l u bi sr ipr me s o
.a iymii aiaf o
ss ntt aeetroo mfs .a i 1 c syeaot i ym EF o3 i sl t mcr l u ahi ay1ou s sl o1e l u i 1 t oal m a t ahi PO d r rniaf mtt ml 3 p c n ni m t t a Gaf goq u Y a I mni ma -1ml oasmni T R P aorGaan oaihoaor Gmt 1 cctt pgmt Y
er r l o e
) y C p .
6 l .
N rm ,f v s ( she E e a yi o e dits DU l sl t yl osni NQ p kys ebp ei y o w AE mhel u l pd a m lpea rl mr R atetd e GF siwn mos mpn ,h N w ey ai a adt IN s srb sk eo LO unoq nub ea .
e1m M PI ooied . epr y ee3re A MT uitreg t g l tw1ot R AC ntcfrn ih r i- - fi G SE i ae ii sty e s2I rs O onl t o prnpp eo L tnelrlrqa eud R L pok r P O C
opooeo mme o- e u a mee m G Cocmrl C1 w Q ovhso N Cowic I
j ) R -
d O d u e T Q f n
(~ u I -
/ otu ot n N : a , D yer so ts cd ss i O s ocs l thg a re rt t
n M n tor e ig 0e 1l ut ei o oc t C
o L A
i t
e l odv tee nie ihg l
oeen se e f n ey l
( T a sYctl c a rlho of oteo rmb o N c oRea i er t pti wa r 1 E lAsld vhe nm t stld t M o cD un tv oanc m t feaie n
- ) l Ntcu e a .a e orwkt o 2 N O
1 mUnl o hg cxie e r me ar rb a c c 1 ( e oOear tnl a o h e g0 e 3
. R I
S N
v rBrcg e mvu i a rnd di et rs et a o cnn8fi a' V E O i
f f
Efte oand of moa tn n eekna f
m E N V I sTfsg rhnn r d sw oy hni o L E I T a eIi ea f tn po l ftihe r B
A L TDA ANC c
r lSdhr p
y aa fsni aaw ud me o ok rtb f ge etd; e fdi T A FTAO ,t ee ri eo y wdl e f meniv li eQ l .
C ON L st ll fl aeiha pnt mua/
l e D pnin l
I ES s sr pp petsug pn G RSEE e h mode mm sf mo ei m e r i nieco. a r
,el aml O EELL l etsha ai l aa a shul ai L BRPP p e ntu smul oce stma akv ss l h st O MPMM m reo n ecl v ec e ee py t m pt c a I UEAA a hhifn n ae no0r nn ml e mpas ec D NRSS S Tttoa Oacl Ol3p an noouhi no A OO So Otcstd' Ol R .
d n
Y as AE e )
WL HP et na 5
( g 1 TM AA il e du e e n c d n gNM""T W I PS n oc r fi r a o f n
u k) n ER b r o z RO o ot b ir r u r i
r c@ o to gu, U/ r da t e S G D SD d
.. ON i RaP a . . .
PA W a b c X . . ,
E 2 .
3 h ' e55 N
- N
~
w) 4 v
{
1.00 .
.:l . h
- h
. g:! -
0.90 .
I-g :-
I, :-
.J.l '.-
.l : -l l. 2. i:
0.30 : .
I-
- ! . 4: ! g.
.:l : n: . . .:1, . ,: ;- .
0.70
- .l- : -
.I. I j. .
- i {.;
- .- -
s .:.
I
.= : .
- l
. .I 4, . .- .j: .e. ..l:: . Target' Flux Differenos;;
~ ~ ^ ,..'
a 0.60 :^ J
/ ". .
iii -
q -
- il-i I . : 2::
l : -
- ;;j . g -
w -
- ;9 - 3.. .;g.. .
g
- !r ::1 - '
iiiii - - - *- .
i ': :iii 0.50 . . ::':: .... .
N ' ' - i;i!
iil ' ': I n. . liin. I:s !- ii" i i- 2: -: __ "..'
- h. i .
- h !!!d I
-N .
. O 5 0.#
=g i -
_i gg ggg P
y
,a
?gg...
i.i r 3 4 - - - -
- i. ' ::l::
.... :=:
g ..
( * - -
il j:. n;;;
. ij i- i-l :- ii; i .
0.30 '
' ~
- l i ii - -
.- . i g
'. ?!iii :Hi.
. . 5 .p.
~'
e .. . .
0.20 .
3 i
l - iiii- -g -- -
iH :n; -
i-jn -
l ...
t 3E" :I.
l -
0.10
- : i- :r
'+
- -l n,: j i
. . . . g.,
- j l 0
-30% -20% -10% 0 +10% +20% +30%
INDICATED AKIAL FLUX DIFFERENCE .
FIGURE B 3/4 2-1 TYPICAL INDICATED AXIAL FLUX DIFFERENCE VERSUS THERMAL POWER
^
DRAFT DEC 021985 BRAIDWOOD - UNITS 1 & 2 B 3/4 2-3 b
-.-..._y.. _.3__ ,, .-__# - . - - _ . , - _ . - , - _ . - , - . , _.-.-. . - _...~_ - .%.._,_,m._.- . - - . , . . _ ~ - . .,-..-_,
REACTOR COOLANT SYSTEM (g' DEC 0.2 1985 BASES OPERATIONAL LEAKAGE (Ctatinued)
The Surveillance iaquirements for RCS pressure isolation valves provide added assurance of val' e integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady-State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady-State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits
-y provides time for taking corrective actions to restore the contaminant concen-trations to within the Steady-State Limits.
The Surveillance Requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.
3/4.4.8 SPECIFIC ACTIVITY -
The limitations on the specific activity of the reactor coolant ensure that the resulting 2-hour doses at the SITE B0UNDARY will not exceed an appropriately small fraction of 10 CFR Part 100 dose guideline values following a steam generator tube rupture accident in conjunction with an assumed steady-state reactor-to-secondary steam generator leakage rate of I gpm. The values for the limits on specific activity represent limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific site parameters of the Braidwood Station, such as SITE BOUNDARY i
iocation and meteorological conditions, were not considered in this evaluation.
The ACTION statement pemitting POWEk OPERATION to continue for limited time periods with the reactor coolant's specific activity greater than 1 microcurie / gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which .say occur following changes in THERMAL POWER. Operation with specific. activity levels exceeding 1 microcuri2/ gram DOSE EQUIVALENT I-131 but within the lin.its shown on Figure 3.4-1 must be restricted to no more than 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> per 3 year (approximately 10% of the unit's yearly operating time) since the activity 5 .) levels allowed by Figure 3.4-1 increase the 2-hour thyroid dose at the SITE BOUNDARY'by a factor of up to 20 following a postulated steam generator tube
, BRAIDWOOD - UNITS 1 & 2 B 3/4 4-5 ,y ,
7b /
,._e-,r ,,y.,,,____,-_._.,,__,.,_.,_y- , , - - , - _ _ _ _ - _ , - . _ _._4.~, -____
O
. 4
= =: :-==. . - - - -
- . - - =-:.==.--:==. .==--. . - - - . .
] "'
2 f
,. , e
. I ! l
. . l l' ,'
lll
) i f i } 3 I *I 6{ ,j e i 0 1 6 I I ,
. i . i . i , , , . .i . .. . . , ! i.
6 . . 6! ll i el l }
6 . 4 . il l g it ,
. . .. leis i6 e e6 i . \.. , i i ...
= = - - r--. =m .: n- =if g:Y91/4T r - 1.2 x 1019 N/cm2.
, :--- . . _ - --r-
_._ _. .c
/ _ . .
~
e f
I
- t. ~ - - . .;. .. y -, = _ = -= - = . - -. .
.==-g- - - - -
- ~ ~
_ 4 ' . -.~ 1.~2:M-t-M /1=Z
.Z ~r_T --- - - _~ ~ ~ ~ __
F
- i- A ~~~
-~ 2 a
2 1
/
f
/ N~ .3/4T. -2.7 N,/c. m x.10,18 2
S '
[ .
'i l
_i. ,: ;;
. u .
. f -- . .
. . E .u
- u. . , .
.m
. ~
f i?! 'I tl . , i e t
- i i t , i et i i ! 6ei jg g f 6 e,ee es
+1- a.,' . 1~+-+=
i e l l l i el
=_=.
. i ii
.. ==
i i iel 6 2 $ Y.. f h: . ~ Y * ^'~
f ... W_' -.__= = ~. -L'
~ ~ ~
g 7 m---- -_ . - - _ . -- - -
" _f - f'.'~ - - - -
! , /. . .. . . .
~ ~ ~
- - ::= ' ~~LEZ f Z.-Err ='
4 . . _ _ _ - ~' ._Z I_~_~_
.g _ -- -i' '.E_ .Z
- 1;

=
I F
~-j . 1
,'j l . r
}
! i i ! , t i l i t
! i i **6 i i e i Il i l l e i l i ! .
Ilh! f k.1 I *l ' l I !
1_0.". 0 10 - ~ ~ 20 * ~ ~30 ' ~ ~40 ~50-~~~~~
~
EFFECTIVE FULL POWER (Years) T FIGURE 8 3/4.4-1 _
FAST NEUTRON FLUENCE (E > 1 MeV) AS A FL'NCTION OF FULL POWER SERVICE LIFE DEC 0 21985 BRAIDWOOD - UNITS 1 & 2 5 3/4 4-13
l ' #
=
5 5 -
5 0 #8 l 1 1 11 I i l l i l lllillilllilllilil!illl i llllllllilllillili il
' L
- 1. ! I! ! i ilj$ UPPER UMcT
' ; ; j .
-;0.30% COPPER BASE,0.25% WELD y - -
J j j jj, ,,, gi o' Tj;y 3% IE-:'E ,h o.ai'.'h lav I[] [ ! fhj y __
_=_= . _..
i._2_0.25% COPPER BASE,0.20% WELD m m: k e ,,
m - -
- n . ::
+
l li! !Kd5g.bg ...a ? ,,,oir'"T !!i'Jj
_....=*'",
yg " 3,,,nive,'s f
h @**
1 i !; 6oW'
.. _ __ ____. - 1 ! '
't -
1 I e, 200 i ,;,,,r , ,a,- _ ,;, o,w--
y' r ag g,,sp h;
U " ,.", .in h;.
" ;b
~
[ .,,l."""" $h .=
,k l _
-,,,,,,,,o" g 4o"-
ov,,;,,,
i a a.j
. I
}
, LOWER UMIT
"',,o p s* ,
i ,
,4
,,,.* ,,..."""g,no l j " '
,i -
..;,- i[ ,,l p- ,o 9
P
- j.- --,- ,[n-3-s. .
.s,e'a
.,4 .{ s
,;.f -
E ,;;;;- -
, .s .+ t,'i 4
1, , r .
w
' lip I ; 9 i E .a-- ! u,, I I ii L .,,fML
. J i ;i i _..aaT i i i i l i '.!i:
~. ' '
%3E m / oid".i:i;i 'i W
" . .- "f' =
N !i! L !
"" ! I i llll ! ! 'i. . i I d !
R $ sa*'' 'i l i.e .Hf1'I ihl !!! ri :!p ! i l' i 11 i i!' hk !b!EE dii l :i di 3 'O
_ ,.r- -- 'TT ! ! i !l.1 liil iii. Esoi' M@iEN.4 70.20% COPPER BASE,0.15% WELD il [
h .., , ,v 'hN i!ll ll :! !lhl!hh i i I
i i j N
N D 0.16% COPPER BASE,0.10% WELD b. h l ,
I"'TJj t ;p NO.10% COPPER BASE,0.05% WELD t j
, ,,,,.- j ;
!) . .. .
g 2
! ! I i M !N! !d !d! l E
! I 1 -~
l l 1 . II ~
!! !l! 5 I ! !l . ) l! ! Ih l.l ] -l il 1
f : t<-}!!j lI'
[ I bl !.l!
ll l l .
1 4 .
g s i i i
. _ _ , i .. . . .
- g l
- t ,
52
= '
l I l a
2 l! l ll1 l ! i !l i d~ T lI l Ilp h : 1 r -
10 1s 2 4 s a 10 w 2 4 s e 10 "
res O C I
, %, FAST NEUTRON FLUENCE IN/CM . E >1 MeV) , or n 5
llp
N*n M FIGURE B 3/4.4-2 EFFECT OF FLUENCE AND COPPER ON SHIFT OF RT FOR NDT REACTOR VESSEL STEELS EXPOSED TO IRRADIATION AT 550 F
i h i E
l, a'
!!! / I -
l l .
! . ._ j
,j,1 -
I:!! I I ,1 i iI ,
I i ,I' l,
i I 'I;
- f:
O p \
q . . i.
s I N I il
\
\
\ -
I I I \ M M M PtNDINC R@@T Q@
NTW MM THE APM.6NT
, j( -
{-
N } /
) U
]l' A I" i I gi
\r 7 T
I t,me!(
3 ;
,i I
N t C- % ;- - :
N
\ \ l
_y
. N i I
I s
g d!
L
' I
\
- \ h- l
. :J + --g
' - ;J. e.
FIGURE 5.1-1
~
EXCLUSION AREA AND UNRESTRICTED AREA FOR RADIOACTIVE LIQUID EFFLUENTS DEC 02 %
8RAIDWD00 - UN?~.5 1 & 2 5-2
l l
l i-
- = . -
.a .
~
523 .
~ .
S 3
/ * ':
I- ". . "
~
=
E3
)Gdi .
O E
, a
- i: .. 5
(- :
- . . i 5- ::
.E 1 : .
- :. 4
.=
\:
.l'l
~
FIGURE 5.1-2 LOW POPULATION ZONE (L.P.Z.) DEC 0 2 1965 PUBLIC FACILITIES AND INSTITUTIONS WITHIN 1.125 MILES OF THE SITE BRAIDM)00 - UNITS 1 & 2 5-3
I li n l11 lei Iklll-- .
till. y11 .il .-
lil ,1Il
-11lll-.!Il lil illll
{r _
l1 lll lE iii ib ll,! il lil
[
i
! ii m
Ill lll!
v . g!
I'l -
ill Ei
(
= , '_ E Il U -
ll al 's 11 m -
lll;~ I llll,IlIlll '
_ gl .
r --
!; 'i!!-
lIlI!! .
111 Ili Ill ll1 till ,-lil
, lIl
- r- r- r- ,r- ,-
I l -II.=ll '
+'.I
~
l ll lij Ili
, . , DRAFT 3-3 0 2 1985 BRAIDWOOD - UNITS 1 & 2
)) IJ IJ jl 1
3 j -
il 1}-
}![.]1 -
l1 1
8 j si:15 ,
jj ljj n -
1 i .
m Al 3-z j - -
!1 1 li -
gi
$8
- (. .
,l-l 'j gj--Il _
il ;j jj .. - ..
J l- -
il m .
n ,
a) n ,
11 11 1 ))
))} 111 11 1 11 DRAFT
. DEC 0 21965
']}j _" lj - Il ""
}
l, BRAIDWOOD - UNITS 1 & 2 6-4
- --<- -. , , . . ,__._.._,--.-._,...,,-.-y,, . . - , . , . , . ~ - , . - - _ - _ - - - _ _ . - . . , . _m. , - ,y , . - - _ .--,-,,,,y-
~ ~
DRAFI
, ADMINISTRATIVE CONTROLS 02 %
HIGH RADIATION AREA (Continued) , source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be
, controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Rad / Chem Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high '
radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
~
- a. A radiation moiitoring device which continuously indicates the radiation dose rate in the area; or
; .. b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or
- c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for
) providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the Radiation Work Permit.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved l@P which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area. During emergency situations which involve personnel injury or actions taken to prevent major equipment damage, continuous surveillance and radiation ~ monitoring of the work area by a qualified individual may be substituted for the routine RWP procedure. For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located withir. large areas, such'as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded (by a more substantial obstacle than rope),
] conspicugusly posted, and a flashing light shall,be activated as a warning .
device. BRAIDWOOD - UNITS 1 & 2 6-24
m
~
i JPN 1s ngg For further clarification, call the Braidwood Project Manager, J. A. Stevens, at 301'492 7144. I' x: /)
~
Janice A. Stevens, Project Manager c,. PWR Project Directorate #5
/ Division of PWR Licensing-A 4
Enclosures:
As stated cc: See next page Distribution: h NRC PDR Iocal PDR PDf5 Reading File T. Novak mRrn E. Jordan B. Grimes J. Partlow J. Stevens M. Rushbrook ACRS (10)
- a OFC *yD#5 :PD#5 n : : : : :
...._ ,...._______:.____D _:. .....__ ..:..._________:...... ____.:__........___......._____
NAMs!j(01shan :JStevg6ji' : : : : :
.DATE :l/ O/86 : / //3 /86 : : : : :
OFFICIAL RECORD COPY I l _ - _ _ _ - _ _ . - _ _ _ _ _ _ _ .}}