ML20101S778
| ML20101S778 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/31/1985 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20101S775 | List: |
| References | |
| NUDOCS 8502050637 | |
| Download: ML20101S778 (46) | |
Text
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.,, REACTIVITY CONTROL SYSTEMS
~ 3/4.1.3 MOVABLE CONTROL ASSEMBL!t.$
FULL LENGTH CEA POSITION LIMITING CONDITION FOR OPERATION
' The CEA Motion Inhibit and all full length (shutdown and regula ,
3.1.3.1 ting) CEAs shall be OPERABLE with each CEA of a given group within 7.5 inches (indicated position) of all other CEAs in its group. ,
APPLICABILITY: MODES 1* and 2*.
ACTION:
- a. With one or more full length CEAs inoperable due to being immovable as a result of exc'essive friction or mecha interference or known to be untrippable, be in at least HOT STAND 8Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the CEA Motion Inhibit inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
4
- 2. PI' ace'and maintain the CEA drive system mode switch in either the "Off" or any " Manual Mode" position and fully.-
with' draw all CEAs in groups 3 and 4 and withdraw the EA CEA in roup 5 to less than 5% insertion. k y
- 3. - BNd s .
L
- c. With one full length CEA inoperable due to causes other than addressed by ACTION a, above, and inserted beyond the L Steady State Insertion Limits but within its above spec alignment requirements, operation in MOD '
time of < 14 days per calendar year.
d.
With one full length CEA inoperable due to causes other than addressed by ACTION a, above, but within its above spec alignment requirements and eithe! fully withdrawn or wit the Long Term Steady State Insertion Limits if in CEA _'
group 5 operation in MODES 1 and 2.may continue.
s See Special Test Exceptions 3.10.2 and 3.10.4. .
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8502050637 850131 ? >
PDG ADOCK 05000317
' P PDR 3/4 1-17 . downMlMM '
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'll cal. VERT CLirn - UNIT 1 $& l$ f r Nf h%g gh; J N r. . .q
a TABLE 3.3-10 . -'
POST-ACCIDENT MONITORING INSTRUMENTATION i 9 .
E
- MININUM E CHANNELS-INSTRUMENT OPERABLE P
5 1. Deleted .- k .
.. 2. Conta,inment Pressure 2 l 3. Wide Range Logarithmic Neutron Flux Monitor 2
~
- 4. Reactor Coolant Outlet Temperature 2 ,
- 5. Deleted T d
- 6. Pressurizer Pressure 2 ,
. 4r s
- 7. Pressurizer Level ' 2
-Y O 8. Steam Generator Pressure 2/ steam generator
- 9. Steam Generator Level (Wide Range) 2/ steam generator i'
~
10.- 2
. Feedwater Flod.
{- 11. Auxiliary Feedwater Flow Rate 2/ steam generator g
- 12. RCS Subcooled Margin Monitor 1 S
" PORV/ Safety Valve ' Acoustic Flow Monitoring 1/va'Ive 13.
x ].*
- 14. PORY Solenoid Power Indication 1/ valve
.- =
l5 Ccdaiensk Llaler Lied (WW 12any) . I R.
N A, % ,
aja
'j RM g ,'T g;
,. . r . -4.. s
- s. < ,. _ :pd}
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_ . _ _ _ < Ii_s$$UN[ J h_
TABLE 4.3-10 .
n POST-ACCIDENT MONITORING INSTRUMENTATI0fl SURVEILLANCE REQUIREMENTS r"- '
N CHANNEL CHAT:NEL 4 . CHECK CALIBRATION n INSTRUMENT C 9 4 1. Deleted w
M R
- 2. Containment Pressure E M N.A.
q 3. Wide Range Logarithmic Neutron Flux Monitor M R
- 4. Reactor Coolant Outlet Temperature
-[-
- 5. Deleted "
M R Pressurizer Pressure R, 6.
.n '
M R
" 7. Pressurizer Level ,
O .
M R
- 8. Steam Generator Pressure Steam Generator Level (Wide Range) M R j 9.
M R
- 10. Feedwater Flow .
M R
- 11. Auxiliary Feedwater Flow Rate M R k 12. RCS Subcooled Margin Monitor E PORV/ Safety Valve Acoustic Monitor N.A. R 2 13.
S N.A. N.A.
g 14. PORY Solenoid Power Indication is conta;wd Waer bal'(Wit AwI) n- R 2
- I .
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REACTOR COOLANT SYSTEM i 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION A 3.4.6.1 The following Reactor Coolant System leakage detection systems 4 shall be OPERABLE:
- a. A containment atmosphere particulate radioactivity monitoring, system,
- b. The containment sump level alarm system, and
- c. A containment atmosphere gaseous radioactivity monitoring system.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a.
With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containmegt m 3tmosphere are obtained and analyzed at least once per,24_ ,,
"f hours when3.he required gaseous-sttd/or particulate radioactivity monitor , 4 ing system is inoperableX,cthen.ise, be in et leest ;0T SitOOY
- t,;..
t N g. rM10' " "TDOL?! .;f t5in the f 11ch; 30 P.;;,;h.
.an4 e. -lWa;.ttsehe a s5$Ety -
SU VEILLANCE RTQifffUfDf1T ~ &'
4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:
- a. Containment atmosphere gaseous and particulate monitoring systems-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, and
- b. Containment sump level alarm system-performance of CHANNEL CALIBPATION at least once per 18 months.
l
.. CALVERT CLIFFS - UNIT'l 3/4 1-13 .,
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- b. WHk only detec % n sprem one o f the abo e regui<ed /esksge openitats , opera tion. m.y ly
fo ,-
cenhnue up to 3c days pro vided' JAs t a t :i '
l
/eas t once per .2 4 hees : .-
5
- 6) yeab .wnyie s o f +4e een inm,,en t a410spAe<e-N'l are obtaiated and snalyted, and ,
b
$0 lhe Reac ice Cov/ ant yS slen wske ihstenIwy -
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oslance of suxscianace squigwix7 ;
Y. t'. &. 2. c i.s y, toersed. ;
t
=
- c. WiVkall lbre e regu tred leaksye delecG cys&s ;
Inoperable , res+ ore af less F ese. leakoy defeck l sys ket h 6PEM8L6 staFus y;{ fin + hours er i be in as least HOT 3rAnosy w;1Ain tire nex t 4 Asurs /
=
$nd in Col.D SHUTDOWN w,'lh m de lellCain .3 0 h w es.' _
Q -- _
. / ~~ - .- W ~
1
, 8 i
- q zpscnr Acrius b. and c. absve in pa e ,'
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-;s REACTOR COOLANT SYSTEti e
REACTOR COOLANT SYSTE:4 LEAKAGE LIMITING CONDITION FOR OPERATICN [
. +
+
3.4.6.2 Reactor Coolant System leakage shall be limited to:
- a. No PRESSURE BOUNDARY LEAKAGE, f
- b. 1 GPM UNIDENTIFIED LEAKAGE,
- c. 1 GPM total primary-to-secondary leakage through steam generators, and
- d. 10 GPM IDENTIFIED LEAKAGE from the ' Reactor Coolant System.
APPLICABILITY: MODES 1, 7, 3 and 4.
ACTION:
- a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 houts and in COLD SHUTCCWN 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 any Reactor Coolant System leakage greater than any one of tne above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate td within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STAND 8Y 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 4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
C'tku orga se cas a.A(i) Monitoring the containment atmospnere particulateAradioactivity
- " ~
ondu.4aj the contoineent wied'A5egra6 g3No".sso tiNtaO'm#eniters is M $rableNTIMny. mute d Ts.2 barnom te o YEalnes in morwa bo
- b. Monitoring tfe dontainment sump discharge frequency'at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, when ec.untsnmnt war tewlab is OPEAA8tl,
- c. Perfor-ance of 'a Reactor Coolant System water inventory balance at 1 g during steady state operation ankt hst
- P"" Tc'e,epsjpfwheg g o ind 3, de snutdown cooling mode, and
~
CAL'lERT CLIFF 5-UN!T I 3/4 4-11
- 40. ! 3 geg
s ,
n TABLE 3.6-1 -b 3= * .
r p?l v
- ~
cONTAlfir1ErlT ISOLATI0rl VALVES ;
r- r*
u y
n .
n PENETRATION ISOLATION ISOLATION VALVE ISOLATION -*
g NO. Ci!ANNEL IDENTIFICATION NO. FUNCTION TIME (SECONDS) .jQ m
1A SIAS A CV-0400 PS-6465-CV R.C. and Pressurizer Sampling <7 -d
- SIAS A - CV-5400 es-5466-cV ~
D da E SIAS A Ci-5467-es 5167- c# 77 r '
3 SIAS B CV-5464 rs-5Y61-cV 77 N
\,_ <%'
l a '-
SIAS A CV-2100 v4s-lifo-cV Containment Vent Ifeader to Waste' <7 #@
SIAS 8 CV-ZiBi--wGS-2431-cv Gas {7 1 t-. j a
I C .' SIAS A CV-500 ctc-506-cV RCP Seals Controlled Bleedoff <7 I
' SIAS B CV-;0; cyc-Sog.cv 77 3 u -
N -
h - -
7 4 o' ID NA S"' ~ Post Accident Sampiing
~ ^: P5-6529-Sv' Liquid Return to RC Orain Tank NA'
? I um ,
2A SIAS A CV-;l; cvc-5/5-cv Letdown Line <13
_ 1
( '.
. SIAS 0 CV-SI G cvc-5d 6-c V (13 y NA 7:13 CYC. sos _NA ..
NA -7F.3- 1 cvC-lo3
- HA
=
h 28 -NA -CV-;; 7 CVC-5/7-CV Charging Line NA 4> MA CV-510 cVC-Sif-CV 4
i 7.
HA Jj NA - CV- 51
- cVc-5/f-CV NA j+
= NA' 0." 21 ^".2 - 2 cvc-435- AV NA
. rm 210-:-2 cyc-is+ ra '
s . :f a
' ~
-
- h t ri
.5 g'
r eo UN'N .e
>fQ;"ty
,naLMM s
4
, n 4$
( TABLE 3.6-1 (Continued) ;?;
l Q .
19 G
m CONTAINMENT ISOLAT10ft VALVES -
w PENETRATION ~!SOLATIO1 ISOLATION VALVE -
ISOLATION =
0 NO. CHANNELS ' IDENTIFICATION NO. FUflCTION TIME (SECONDS) Y.
- Tl
. NA 494- ILR T- I NA 7 C .1 -
=
7
~
flA +94- netT 7. ilA s
- ) :: 4
' .- f E A b-5%2.- no v +'
8 SIAS A ."^7 i' " Containment Normal Sump <13 -S SIAS B .0" a 53 - ~13
~
ca s -Syss v no v u .
N 9 NA 220".2.1 .gI.340 Containment Spray itA e ilA -200;;3-2 -37 32.4 -
NA ro o .
10 f4A 220:;2-1 51-330 Containment Spray flA flA 2300:2-2 SI-316 fiA t
I f 13 C PA-/Y/O - C V (3)
[ -
R CPA-IVIl- Cv (30
'l
- de ,
D r* . -1 2
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m
. Dl 1 ;
s a l
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s -
- AW ' ,
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,y < Qg '.
'h;{.;,-e.'
- svi+ ,
, ' A _l; L _ is;, ~~,, . , . ll ,;.
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- f _, = m;.fkjp f; f$$!Yl&:h}g jfx5);;!? llff*
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t i
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. s TABLE 3.6-1 (Continued) .{q I n r- .
g C0fiTAlli!!EflT ISOLATIO!1 VALVES .
n
--s ISOLAT10!i VALVE ISOLATION 9 PErlETRATION ISOLATION "
n TlHE (SEC0tt05)
IDEt4TIFICATI0li fl0. FullCTION C ti0. CHAfillELS
%l cPA- /4/2 -cv (.3)
I
n
- 9. c Po-I'll3 - c v ( 3) 7.
-s 15 SIAS A -EV- 52 01 AE-5291-CY Purge Air Monilor 17 SIAS D CV- 5:02 AE-5242-CV 37
.6 N
.-e 16 CIS A CV- 333 2 cc -3f32-c'V Component Cooling Water Inlet 118 W
W .
a w
CIS B CV-3033 cc-3F33-cv Component Cooling Water Outlet 118 l-2~ 18 ,
- i l L" flA 223 1 IA'337 Instrument Air liA
- 19A <13 CIS A
- ;3V-:C33 In-logo-nov lia 198 . HA 10-2 ' rA-tavo* Plant Air NA NA i3G-l ^ PA-foff
- E 223 #.-3V4 2 Hitrogen Supply NA -
g 20A NA ,
CV-Gi 2 ^ #2 -612.-cv' ilA -
> g NA tiA 7 g NA CV-622 ^ #2 -622-cv4 NA [
a tiA CV-632 ^ dz-632-CV
- CV-64 2 ^ N2 -6V2-C V 4 NA g NA . . ,
m us %>
.e l 3
- [ 3 - "
- { i.
~[ . N' , NJ , ' ';., h2 k-ki
.. I mL J ..w
f.
,\ -
TABLE 3.6-1 (Continued) .
n p
,j CONTA!NMEitT ISOLATION VALVES
[
rc:
- o 150LATI0tf 1 PENETRATI0tt ISOL AT10rl ISOLA 110ti VALVE '3?
n FUilCTION Tit 4E (SECONDS)
CitArifiEL IDEtiTIFICATI0rt (10. 9; C 14 0 .
' ; NA
- 20B IIA 223 ' N2 -389 tiltrogen Supply fiA - ti;r
' NA 223 2 Nr-345 :._4:.r C '
=-
tJA 223--I N2 - 3V6 tiltrogen Supply 2 20C NA IIA .
NA 223 2 n2-39A 1 k ~
23 SIAS A CV-4260 R.C. Drain Tank Drains 9 .g Acw-4260-cv .
.~
SV- 5531- Oxygen Sample Line j g 24 SIAS B z.
- ps - eS3 8 - s v m 11A g E 37 NA -29 4- PS W - /019 Plant Water
" liA --
NA 44M- e5 W-/008
Demineralized Water tiA 38 HA CV-54G P DW- 5%0-cv
- A Safety injection Tank Test Line tiA -
y 39 NA -13C"3 1 SI- W3 ~
' HA flA I20",3-2 sI-455 g .L
- o. "'
D -
52- 652 - NOV (4 Shutdown Cooling itA c3 r 41 NA E0V-552 (2) NA .jy y HA MG V - 051 (2)
- sz-sso -n ov (z) @
.mt e R' US d4
,cy ,.
l?
. "igA
'[,
, iegpy-o __-
f ~
4.-
4 [
3 A) n ' f. . .
> ' TABLE 3.6-1 (Continued) A G
m K, a g r
m CONTAINt1ENTIS0tdTIONVALVES .- ,
a n p o
ISOLATION VALVE ISOLATION e ;
r-E,,
PENETRAT 10:1 HO.
ISOLAT1014 CilAtiliEL_ IDENTIFICATIOtt 40. FUNCT10tl TIME (SECONDS) 'bg v.
7
~
- 44 tiA -MS F P-I*41 - A fire Protection NA
-N 8 pp-J41- 6 NA s HA
- flA M0?-0200 pp-r,200-ricy .y tiA ,
-4
- v
'y
- rs- Gs40n-Sv A 0A ^ n .- ilydrogen Sample Outlet
!. 47A flA LV-C' '
HA Q.
HA 5V-s W Afm,.';3. flA .;
PS-6S6'TA-SVN ' 'i eg - ss40 &'~ s v t ' '
47b liA u-6'A00
- Hydrogen Sample Outlet fiA NA f~
M -
flA SV - 6".,072 -
PS-6So7f-SV A cn ,8 pS. sf40f-$ V e u 47C tiA SV-0'AGT ^ liydrogen Sample Outlet NA ;[
NA LV-00077 *- -
NA PS - le SO 1 F -S V **
ps- GS90 4 -S V k g
flydrogen Sample Return NA 470 flA SV-L'A00 * ,
SV 00070
- NA NA PS - bS0 7G-SV W
~
L: g- 6900-r<o v o 48A SIAS-b rip"0V 5000 Containment Vent isolation < 20" ~
y 5IAS-A "0V '.00: 120** 3 i
u s ne- 6908 -noV y-
,y re j
= f-O ..+
. 9 A .A
~ s sy A- ..e :. ..
..a..
- u. * "
f- .
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1$
r*
,- r
.-' ' .y!.?N, Q- . ,
,5
- """ k Y3s Dt
- _ I, ';;; , *
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- X? ' <N. s a , , , ,
y , , j'*y K j., ,, ." _b ' j g
- f f '-'
- w w <;. .. ;qQg
- n; -
Q U
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.4.
4f i
n i .p TABLE 3.6-1 (Continued) > ;.
E . CPTAINMENT ISOLATI0ff VALVES /a m --
P
~
PENEIRATION 150LAT!0ft ISOLATa 4 VALVE ISOLATION NO. CliANNEL IDENTIFICATION NO. FUNCTION TlHE (SECONOS) --
p 3 Y.+3 .
. 488 NA 230-1 H P- /D V, Hfdrogen Purge inlet NA q
. g NA I40V-0303 HP-69o3-rtov NA ,
M t %
i;
- es- c S900-SV W 49A NA L V- 0M00' SV ';070^ '
Hydrogen Sample NA p .
.J-11 L HA HA :=p L rs -6s07 6-SV t ..s;%' j' rs - 6S+c C - s v s.
498 NA SV-66466^ Hydrogen Sample NA p- TJ NA SV-00070 . NA :
u s
es-sfo7C-SV 4 es-sceseb-Sv e -2 7 49C NA ';V- 0M00 - Hydrogen Sample NA f_ T2 m
NA SV-00070- NA P s - 6f0 7 b -5 V
.g g 59 NA 2""3 ' SFP-170 Refueling Pool Inlet NA 4{
. NA 20"3 1 S F P -/71 NA j
}
. J$
., 60 NA 130 2 6S"/F3 Steam to Reactor Head Laydown NA #
2 o
NA i0 I ES -f YJ. NA $.
- T s:
N
- t*
d O
g *.-+
4 .
4 4' '
4 +
w , o. , n , +
- i , ts .f
. .; ., ., . . ; s; gg
\
~
5 s.
. . ml t.
TABLE 3.6-1 (Continued) y
. ., y n
- CONTAINMENT ISOLATION VALVES h N, y 4 PENETRATION ISOLATION ISOLATION VALVE ISOLATION DT n NO. CHANNEL IDENTIFICATION HO. FUNCTION
. TIME (SECONDS) b C c*f A 61 MA 75Y-1 S FP- t76 Refueling Pool Outlet NA -fg; NA 203M-1 s/P-t7Y HA 'N
- NA 'M NA 293M-1 s rP- 11.2.
NA E HA 203" 1 SpF-/g9 Z
62 SIAS A MV-0573 Containment Heating Outlet <13 PH -bS19 - r10 V , ,n,
, . 64 NA 23" I PH-l % Containment Heating Inlet NA f
, y g (1) Manual or remote manual valve which is closed during plant operation.
I (2) May be opened below 300*F to establish shutdown cooling flow. ,4 (3) Containment purge and containment vent isolation valves will be shut in MODES 1, 2, 3 and 4 <
per TS 3/4 6.1.7 and TS 3/4 6.1.8, respectively.
- May be open on an intermittent basis under administrative control.
- Containment purge isolation valves isolation times will only apply for MODES S and 6 during e7 R which time these valves may be opened. Isolation time for containment purge and containment g' 3*
g vent isolation valves is NA for MODES 1, 2, 3 and 4 per TS 3/4 6.1.7 and TS 3/4 6.1.8, g~
g respectively, during which time these valves must remain closed. q g 4 r,
5ff, I .
>A n N,
'W
, em "
'{ ;
n.. .
q .
,q,3
.c yg .
qf-419 q . x , 3- 4 , ,
u - u g
,y PLANT SYSTO4S ,
~
SURVEILLANCE REOUIRE'iENTS (Continued)
- b. Visual Inscection Acceotance Criteria -
Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, and (2) that the snubber installation exhibits no visual indications of detachment frem foundations or supporting structures. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of estab-lishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and/or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8.d.
as applicable. When the fluid port of a hydraulic snubberX is found ,l to be uncovered, the snubber shall be determined inoperable unless it .
can be determined OPERABLE via functional testing for the purpose of .
establishing the next visual inspection interval .
For the snubber (s) found inoperable, an engineering evaluation shall be
~
performed on the component (s) which are supported by the snubber (s).
The scope of this engineering evaluation shall be consistent with the licensee's engineering judgment and may be limited to a visual inspec-tion of the supported component (s). The purpose of this eng'ineering evaluation shall be to determine if the ccmponent(s) supported by the snubber (s) were adversely affected by the inoperability of the h
snubber (s) in orde- to ensure that the supported c mponent remains capable of meeting the designed service.
- c. Functional Tests ,
At least once per 18 months during shutdown, a representative sample of 10% of the snubbers in use in the plant shall be functionally tested either in place or in a bench test.*X For each snubber that l
does not meet the functional test acce'ptance criteria of Specification 4.7.8.d, an additional 5". of the snubbers shall be functionally tested until no more failures are found or until all snubbers have been functionally tested. -
"-TMmuirement i s al so-app 14c-able-to-snubbers-served-by-e-comon-hydrad4e-
-reservMr . .
- / The Steam Generator snubbers 1-63-13 through l-63-28 need not be functionally *l .
tested until the refueling outage following June 30, 1985. .
I li CALVERT CLIFFS - UNIT l- 3/4 7-26 Amendment No. 33,/ /,
i 1
' ' - + Q .. - . se e m- .4' * *
. .:y I
FLANTShSTEMS
~
SURVEILLANCE RECUIREMENTS (Continued i - -
- e. Snubber Service Life Monitorinc' ,
?
A record of the service life of each snubcer, the date at which the (
. designated service life cemences and the installation and maintenance j
. records on which the designated service life is based shall be main- N tained as required by Specification 6.10.2.m. ~
[
At least once per 18 months, the installation and maintenance records for each snubber listed in Table 3.7-4 shall be. reviewed to verify that ) [
the indicated prior to the next service life has scheduled not been snubber exceeded service or will not be exceeded ( i life review.** If the indicated service life will be exceeded prior to the next scheduled (
snubber service life review, the snubber service life shall be re- I
. evaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next, scheduled service S 1.ife review. This reevaluation, replacement, or reconditioning shall be indicated in the records. f i
. f) Snubbers Served by a Common Hydraulic Reservoir
~'
[;
N /
Snubbers served by a ccmon hydraulic reservoir,pe ndicated by a.
bracket in Table'3.7-4. All reservoirs seev4ns c=re than one snubbr.r q g snall be inspected to ' ensure adequate hyd'raulic level:
N/
- 1. Within 7 days after ry.acfor startup following 'a major outage or follcwing any maintenance in the immediate vicinity of these snubbers,,resnvoirs, y or associated hydriblic piping; and x
- 2. Efe'ry 31 days. + 25%.
x N
,/ -
'N
,I i .
l
- The Snubber Service Life Program shall be fully im,plemented by January 1,1983. k "The provisions of Specification 4.0.2 are applicable. ,
,f
)
O
! CALVERT CLIFFS - UNIT 1 3/4 7-E6b Ame::dment No. //,
m
%F i
a TABLE 3.7-4 ,
9 g SAEETY RELATED IlYDRAULIC SNUBBERS * ,
m
- n g
n SNUBBER SYSTEM SNUDDER INSTALLED ACCESSIBLE OR ll!Gli RADIATION ESPECIALLY DIFFICULT C NO. ON, LOCATION AND ELEVATION INACCESSIBLE ZONE ** TO REMOVE 5,
u (A or I) (Yes or No) (Yes or No) b 1-11-1 SERVICE WATER PUMP #13 M SUCTION 5' A No , No (
1-11-2 SERVICE WATER PUHP #13 SUCTION 5' A No No ,
I 11 3 EERY!CE L'".TER "'J" "!3 . ,
h sucT:0;; S' '
A h 1-11-4 SERVICE WATER PUHP #12 M SUCTION 5' A No No
[ 1-11-5 SERVICE WATER PUMP #12 N SUCTIO!I 5' A No No 4 3 SERY !CE ""TE". '"l" "Il
-506l'= S' 5 "3
1-11-7 SERVICE WATER PUHP fil SUCTION 5' A No No 1-11-8 SERVICE WATER PUMP (11 ,
SUCI10!I 5' A No No g 1-11-9 SERVICE WATER PUMP #11 A No No a SUCTION S'
- m. . . .
1-11-10 l_k l
SERVICE WATER.llEADER FROM TURBINE BLOG. S' A No .
2: Be. ..
1o~
,, .# g
, kh 'm:. N h[ f,sff .an
.5 h
^
- l3f * ,
i+ - ,
.~-= j *G.9' f *;* i t
}). $f
I c.
3 TABLE 3.7-4 r ,
A SAFETY RELATED llVDRAULIC SNUBBERS
- d .
n C ', P.intiER SYSTEH SNUHDEll INSTALLED ACCESSIDLE OR llIGli RADIATION ESPECIALLY DIFFICULT 4 , r o. O!!, LOCATI0tt At!D LLEVATION
_ ItlACCESSIBLE__ 20flE*
- TO REMOVE y (A or 1) (Yes or Ho) (Yes or No) c .
_ l It-11 SEHVICE IIATElt FROM C0!!TAINMENT
_ COOLERS 5' A No Tes -
1-Il-IIA SERVICE WATER PU11P SUCT10?1 ,
I! Ult 5* A No Yes
! '? I2 S!.0 Y :C E '.!? Tin ." 0 0" C 0"'A !;0 0 ;!
- = cas S- A :t vs R
1-11-13 SERvlCE WATER FR0ft CONTAlHMENT COOLERS S' -
A No No 7
3 1-II-14 SERVICE L'ATER FROM CONTAINMENT ~
t.00LERS S' A . No No 1-11-16 SEltVICE WAIER PUMP DISCllARGE IIEADER 5' A No No .
I ii-17 M RiiG KAiER FUni Li3CiinR E lI7 %% ',' ?. "O M
. I-11-18 SERVICE WATER PUMP DISCllARGE IIEADElt 5' A No No a .
,.] I- 1-18A SERVICE WATElt PUMP DISCilARGE -
j! litADI.R 5- A No llo b
. (',s A Ma
., - i. ._ i. e.
i ne ernu f er Laa.T. ru,- -De. -nnaD
- - - -ntCrtIADer m
+-
- <1.V ' is g'
f fs. .. . - . *i "* * [^. .).J,5 ,
7 ;,zg , 4 m ," gg 3
. . ,c : . .mm:.
i'f [e~ ~' e: E ,h '
~. ~ ~. '
. , , LUjjf { if;?
TABLE 3.7-4 9 " g SAFETY RELATED llYtNIAULIC SiunflERS* UE
-s .
p Sr4UBBER -SYSTEH SNUBBER INSTALLED ACCESSIBl.E CR ll!Gil RADIATION - ESPECIALLY DIFFICULT
~
+;; H0. ON, LOCATION AND ELEVATION INACCESSIDLE 10NE** TO REMOVE y (A or I) (Yes or No) (Yes or No) b ! !! 20 SE"'."CC '#.TER ;"ar ;12 '
U 9?SC".""CE 5'
- H
. l Mc ,
1-11-21 SERVICE WATER PUMP fl2 SUCTION S' A No
. No 1-11-22 SERVICE WATER PUNP #13 ,
UIScilANGE 5' f
, A No No , p
, 1-12-1 DISCllARGE #12 COMPONENT g COULING lix 15' A No No
[, 1-12-2 UlstilARGE #12 SERVICE
= WATER IIX 15' A No No 1-12-3 DISCIIARGE #11 SERVICE WATER llX 15' . A No No 1-12-4 INLET #11 COMPONENI COULING llX 15' A No No 1-12-5 INLLT #I2 COMPONENT COOLING tlEAI EXCilAtlGER 15' A No No j 1-12-SA int.ET E12 COMPONENT COOLING g !! EAT EXCllANGER 15' A No No g-1-15-1 SUCTION llEADER CUFFONENT COOLING PUMPS 5' A No - i .'
en.
, .Nef : s .. . c .f
'k
~ . syn E
_ 2.. .. s ' #< 7
- q ,5 l l.c z ;M \Q " K ' b- * / n. ,l"* tkc
)} .; .
'{ . - M(( 'gg.. * * ,;g j ;, '
g,_,.g.
. R- '-=
- b 4*weq ,,ypi-;:g % s g ,,Q{.y];Me_f,i'so.T S R. W N.
- U( ?
n TABLE 3.7-4 l:
,- SAFETY RELATED liVDitAULIC SNUBBERS
- h * "t BBER I:0.
SYSTEM SNUi1BER INSTALLED ACCESSIBLE OR ll!GH RADIATION ESPECIALLY DIFFICULT q UN, LOCATION AND ELEVATION INACCESSIBLE ZC3E** TO HEMOVE
'p (A or I) (Yes or No) (Yes or No) f.
C 1-15-2 SUCTION llEADER COMP 0ilENT 2 COOLING PUMPS S' A No No . , 1-15-3 CD:4PONENI' COOLING PUNP SUCTION #7
'FiltNI COFIPONENT C00LlHG llEAD TANK 5' ' A No No 2 7
1-15-4 COMP 0HLNT COOLING PUMP ,' , DIScilARGE IILADER 5' ' A No No y R l-15-5 00!!PONENT COOLING PUMP #12
^ DISCitARGE 5' A No No 7 -
*g 1-15-6 COMPONtNT COOLING PUMP DISCilARGE IILADER 5' A No No I-1S-6A C0FPONEN! COULING PUMP UIStilANGE IIEADER 5' A No No
l C'"'"Mr C*J!. !E !'".E ! 'l :
- 1. E : "^"' '! 5' " "^ W
- y. 1 15-0 CollPUNENT COOLING FROM '
7,! WASTE LVAPS. 45' A No No u h 1 15-9 C(X1PONENT COOLING WATER - g FH0H MISC. -10' A No No f 1-15-11 NASIEPH0CESSINGSYSEM-10' A He y . # No q < v g - 7 d, , 7- q
.h . 9 .,
' l' 'd t b' \ u .m,' -
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. w ,;
w A .- e. 9 J.
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=.s g .
e c O O .r. E m ;; J. . . >. >- = = - .. 3 N W >. a # $_. .. 4. - -a r N ac..~ S E em Ow a - . W. - .n U
- a. m- u O
=== to mm .: .- - -. .c .c . ; mw .c > - N :D www * *C U aC M M wZ c < - , W E = - ..e e - W - - N, e N, e .t.d c c, n w J , N m m . = e. - - N m => oc = a; i =: m m s >. 3, W w M W w ea C. = = w w w - . === - 3 / w J es: Ci C 'I J N - 4 ui 6 - m a,C_m :> u , u: ,, c* mJ u, u. . 6J W D h =m s a u a a . >: > C C = :: = - - . g g w .. . m a . = -. - = = w W C -- -, W W E E , f' as i aur N N w w m ,- E e e 2.' 2: E t C 23 **J J -Q G. >i ..,i Ub - W W :q. , s.. n, s
- e. ,.. m m m m i
g w W W W a g g i t.i - m. > . =, _ , a a mg v, v ,
- t. .
'-, g q; . . 4c W. e. e, .. @. . N. + + . ~ R. -R. =. 2 M, IE m y; W; -r. - - - ~ , w ,a v, ~~ *.)1. ;Q 7,.8,:q sy s CALVERT CLIFFS-UNIT 1 . 3(47.31 t Amendment No. y-79,'K w f; ., v y, .@is ;k,'iike p ;.'g%9 s>y . s 'yw. p g s: 4, .. ;% fig' ;wn L yn ".* As, , ^ s - , ;. 8 ' n' <ji x . [ "')l ~ 1 . , 4w 1 % 1sttillCy 8 o v n;s -t 6 . M 6W *
- 4-
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- 3. w 6 .J K Q .
=. 4 y a C C O O C C O .?* KC u J = A = = = = = = 2 > . o W # E. , a*. . - s m - m , . .. c. 7,6..-, . ;w. 3m 9rM ti,ql e E q 3;M mw
- g. *
. :; i; y 9.9 : e u W . m o . .,s . s -.e a. C . > > > > > >= > .s,; J + N >= >= >enI k ., <
- i ' <t Jg t i.h wa q :' 2wl p W
.ng 4 m , . gj: 4 : - n ..rw., m v v y-g #; a. -D. ., i E .J w' - ===. :, .1 - n. wa- .,.,_ .a gms . o -m e e ~ - .J. _ - mw ., - - mu,,,) < a , . P . w w f*) . E v. T - . OW .U = i 'm) -m a = . < = - o p . < .} ,;$-.:gs 5 5 Es 0.5 . .E .E .E E. - .E .E s4 . E'- E >= >' W > >=- 6 >= >= > 'M . .= < - - > G .C k- w ., m w ,,<>
- u. ,., .
as; D;"i tC: E Ei E E =m o E m El '5 E 3 E E. m E E. 5 m E E-5 - - - i.- > - - a.R m m m m 8 , m m. m g* O t 81 % E & E & B B , g!n ai H. E .:3 a -m N N_ E.a N E Na. E. - ."'l . .E- . M. .E . -- M E. -. f"3 E. f) E $1 . - t W, W W > W 48 - ' W 4 68 4 4. >= J W), u> M- > tW D WD'- 41 > WD . UD UD. 4 $'e . ~g k , - ki'g ks/g k k, 4 g k' y k -g k ' kh..g . b :c-f, - * * * * * "*' * * *' " - ** *- 's4 ff3 "E ' i- . 6 9 b .6 , , ',) , f [ ' c}. . c - .M' ' y k N-[Wl' \ . g g gl g gr ' . m an 4Cl 4 N CD- Cl - -xt y e c g ,k; '% @ 'n f' i N ' N l. N N N N N N .N 4,a g.. C L s -e: g- e 6 e e e #,, .,2 s d,e e' y N f*J N. N N N 'Va pO p:: C N. N-y 1 6 . ni i bfl ; W --A .4 .A k** , m. W 4 ,'=-< y a4.4'
- , ,- -s: *
+ e t . s ,. . ; t . 's.cn ' .V. .--u '-TM@+$_r. av .ym _n .i - -- -- -: - y l.' ,lWUh :~ i s ,e nk . - :w+;14,g . . . , , w6;.g -_ _.MER(Ct.F"'.~-UNIL1 ~ ' " 'I - 3/4 7-37 - , f As:ende.ent'Ngj: " TABLE 3.7-4 C^ r- -< SAFETY RELATED liVDRAULIC SNUBBERS
- 9-t a
'n ACCESSIBLE OR HIGli RADIATION ESPECIALLY DIFFICULT.. g '. :UBUEft SYS1EM SNUBBER INSTALLED ZONE ** 10 REMOVE n fl0. Oil,l.0 CATION AND ELEVATION INACCESSIBLE y (Aorll- (Yes or flo) (Yes or No) C
- 3
" m. . en .s i. crnu. .s m - -- er a.m.a.y rn , n. .m .. r .n,a,* , r,a, n. .=.= .. .a r u. ,. Ca^'_ E" !! ? 4 2 ' ! Y:: "c eM _1 fn v is L l O fs nO. .s n f f, f" ifATrn si u rw r s 6.i Y.n us ena.a in ss. T.A. e t. =.** s *vs s T. C^'"I" ! ? ? ' 3 ' l Yc: "c l-60-3 SERVICE WATER 10 CONTAINMENT
- COOLER #12, 65' I Yes No 1-60-4 SERVICE WATER TO CONTAllMENT
- C00tElt #14 66' - I. Yes No t' .< , ,v, n. . .,ni.,,,..~
un . ...,c, ....m. c . . .. .no. em.,.,...-- C ^^'. '" f M 55 ' ! Yc "o u. A ' - M- 5 SERV !CE "*TE" E"a". C0"T*.HIDENT-C40LER-744, 50' ! Yes No-SER"!CE 'F.TER E"0" CC"ThtNMEWf Il0-5A Ca^'E.1 !!4 5a' I Y:: ": 1-60-6 SERVICE WATER FROM CONTAllMENT COOLER #12, 53' I Yes No t% - ~ A Am xu. uj g;o - 's.- 1 jW fA .g::# 7 7. . ,, , ji 4 .. g . i.. . hI b f' [ 1_[h,b D! ;" I ,lp 4 fi ch l _t f . #I. ; ;4t]g 'u I. ~ j 4 T O; . L .r U . C .fp ,.p I - T F -; FE I V ; y DO ,; YE LR M ;(D t. .M L JV AO o : o c o o o o o o IT l f M i t n f l i t l f i t i t N C E P S. f . t 0 t .N I T A* , ,x I* ;; DE s s s s s s s s. ; AN e a e e e e e e e- ,r R0 7 Y Y Y m Y Y Y Y Y Y ~ ;: l i G l i l t S . R ' E _ , D R R O E_ U L H S E L B_ I. . B S. C I S 4 I S E_ I ' I : I I I I I ! - L , SC . + 7 U EC A CA f 3 R C i, D A I_ ' ' f E Y I . L I . A B D x T E . %'3 T A I i E t i : T T' N E T N' E T i t E T N E l E a I l ' : E T N l H H l ; I : e e R l. l i
- 1 ['
- l
# E H f l N I N I l l Y T H 0. E1
- t. I.
't n l l
- l l N I
A T A T Al A T . ?. E 1 i. ,A t. A A N l i N F L. A l
- u. C .T T T O t
u t u O ; A S /. I V.. S f. t. . t C ,O .C N = O N C N O C C t t C H C N C n.q i L . u e 0 O U ,Rq l i l, .r = , O : O O R R R Ms ,l. I ! ._ T T T F F F F' R i '6 C < R '4 R '4 uW
- w R '3 R '3 '3
.E t_. t 1 A _ .i 6 !f Le : T4 l4 R3 l 4 I4 lR. 4 3 t s E4 ; R t. t. l !. :T T l l T l T U 0_ A3 " .A1 " .: AI A1 A1 A1 Ai A1 N l. 'I 1 UO W1 U : U! W1 H1 W1 Wl W1 Sl # # : ! # f # E # ' A- - 1 C .E t : I E E E' E L - H'. 1 R C" CR r : Ct : Cst CR CR CR CR , L (N - E :: V1 'I. l E ~ Vl 'I. 1 .IL I I I : I i l I E IE . I sL " . .VL Vt VL VL VL s i= I ' S Y S f. g ( O MC O M T C
- RO
.SC EO == E S: R0 . E. f 0 0 Rn Eo SC k0 t SC 0 Ro I SC o RO EO SC REOO SC; ; s"~ f_ . O [' = ,= ,~ 'm 4~ A Ai ,i R ^ . ^. 0 0 1 I 2 2' - E - D . 8 " - 9 - a 1 1 1 I 1 1' - p] in0 1 0 0 +0 .
- c. 0 0 0 0 0 0'.
6 i;- v l 1 6 ' ?6 . r 6 6 6 6 6 .il t%t S 1 1 l : 1 1 1 1 1 1 ' [ y b' dn t g .S q S O :;e - ! $t ;y C2,- t' 4 ytN ~ .ys[. p . y ~ .Q.y ih-syr ~- e o O~ Q TABLE 3.7-4 G 'g SAFETY HELATED llYORAULIC SNUBBERS * . p 9 SNUBBER SYSTEM SNun81R INSTALLEI) ACCESSIBLE OR lilGil RADI ATION ESPECIALLY DIFFICULT $ NO. ON, LOCAll0N AND ELEVATION INACCESSIBLE 20NE** TO REMOVE d- (A or 1) 7 es or No) (Yes or No) 5 ~ l-61-17 CONTAINMENT SI' RAY D/ Stim No No S/D ll/X -15' A l-63-9 S.G. #11 EL0tt00WN ORIFICE LINE 70' I Yes tio 1-63-10 #1 L0ilDOWN ORIFICE l-63-11 NITROGEN to S.G. #12 74'e I Yes No 1-63-12 NITROGEN to S.G. #12 69' I Yes No k' 1-63-13 STEAM GENERATORS 75'#:; I Yes No ? <r l-63-14 SILM GENERATORS 75' , I Yes No 1-63-15 . SILM GENERATORS 75' q l Yes No 1-63-16 STEM GENERATORS 75' I Yes No f 1-63-17 . STEM GENERA 10RS 75' I Yes No a R 8 (* . ,.r. s
- . c .
a ;g ..m > e,J ., * . M' . I' j ' ; 'i * . ',G ';- .N ') _ \;J N. ;. p p ; . .7i j T k [ -m ., . v, ) w s e-y- g , . A v . 0% , .n, w, ,+ m -w+;., tv w - w> g, s =E
- 3. w w <'e.. .
am o c ? a <o m 2 2 e .e = z e z e e z e = e z z e s - @ -c og; -- a ~ = ;+g s
- s. :+
m w i z \ o eO w .c -.; u , , # e e ou o e m * *
- y C y v v a v
, gg . # # # # # > > > - - - - N O = >- e - m e W a u .c QW n w w we-x a-w u CW , u -g o _ _ _ _ _ _ - - - - - - , a mu< N m w w!w v <- m 5 o wx a > .a = - - x O w a w = . > Q3 w A ,. _ \ _\ N yA cy Ab b *- v ^ N^ ,, Y ~ - u w w-w m .a 4. . . . . e e e m a w x o w - m rw m o N N N s s ~ N rs .a ea N N f% y =" = = w m w ~ w = w = m = c c3 W3 Ws WE Go er e o o o o o - - - - e w< < e = < < < < I. g 5 , ~ e a 5 w-mz = w w w = = = .g w a= c z w z w z w = e-sc a_ c.- - ~ - "z z w m u w *Q d d 0 O d d d c c c c C e 5 8' g 5 z 3 5 5 wT 5 m 5m w5 5 = R w z> -a m w w u a w aaG w mag m ~e ~ r = = -g a m,f o 5 E $ 8 ~ N hhhhh97 $E = A A A - - . 999999k ------ r., CAL'/ERT CLIFFS-UNIT 1 3/4 7-52 Amendment No. ,83,gg . Q , ,.9-w .>y . 4., ; - 1.] L 4 g d v 3A 1 4,.- . ;pyg .- * .ii n [ d, ' b . .J . . c.
- v-
- 4; .
D . , ;}1 W - m ,' #,sr.;.J, w ' 1:? _- ww **=== L ==> O ? !I E$ E O O e O e C e 0 e 0 e G - J
- p. O g o O <>
= O = = >- >- >- >- > .9 3. 4 ? .- se O = .9 = 3: - , J - H 4' = .C. - = >C 0 .*?. U >= - y w - _a L w , - F.,M. : .. Q **** . =i === = O 'n. .., W <
- 1. O O O d) O O O O O O O O O- - . m Cw O 3 2 = M E E E E E E E E
- et: =
go a . 1nf ,I E g N O 5 = w >= C -t ? 7 A &
- , . y
- ' t ^
l M CW , W J a c': WC == * = W == O .L = c:3 A -m O < < < a: < < < < ac; < < < < m ew ev ww v w -" v< . a e _- . W= " E D 'E; .* . _ m g == . c::
- en c N N N N N N w N N N N N N -
= , q w c z = Z 2 3 E ' ~
- O c c w O O C C ac; w w w O. .C ' -a p.- W w w w -
. == == W ==1 W->- =,1 , =' w w w > W >= ac: a CC t. J c w w .c: a::: == <ic <J <- - w w- . . . :> w > > J J J J J-D D = WW H H . J w J .J D D D D ' / m w < ac" m A e M M w'a ~ .:. = w acl: ::a 3 < c c A A1 4- s. > <> ac; < ac: : t. > > :. - >- >- w n . ac; u U at: U ec: U C:<<! U- ~v ,.x
- w mJ O. C C
- W . .
M w zw >- >- W < > p O O E = w = w x w EJ'S' W- $w =- . ac: == s ac; m W ' e.-. m C N N N i. . .. .- 7.-. y -W g N ;, l I i
- z - o w w w tJ E LJ 3 w aC em , am , aan c . > A c. z a g- .g ' 3 .c tg ;g:3 ff -
c: a =- I r - == == == . *; . am. , es = . . . ! 5 >- a :s e J J . ~ .a s^J ser,- .z . iii c. Do =- e. e. c.s. i ,. j c. . - z z z z .:C'- rwm m i 3P A CN ON ac: aC aC <f'l' 's == M >== at: M. M. M. 6 Jc J
- p. wN w
wN ;W w >= w *EC w, w p= w( tag e -W. ~p=.' =w wo BN P.= ZN oN CiN N t J WN N w0 'M M >= M >== M M . M;-' M "Z f - -w c: w C. a w c. = w* .*gOo; z es; c. .a aug .m egg Z = = g g" t 3-l A x c. .== == - == == >=
- K Z Z 3 cd WE xA
. M= c i i MD ze mD r e.- @ *::3 re-
- >D.
.t cn >- O e c. 3 >- < =3 D >= <c $. $ ~ $& I $',~I N S - g , g es o ,o . e N c3 Ch C - N *M :T . y m e <c- ae ac= e *er ac" 4 d W ~ th - m ,> e . e i e m a m e m e m i m e m e m 8 8' t=1 ' . m' cc m m m es 'E ==> g g3 2 33 c) C3 c3 C 03 C C C _O' E-g a e e a e a e, ,.t j g ,e ,, i a p . pe - p-= *== rs= P'- *** ,**"" ,8*= j.,, J .. A ~ /.' . e4; _ mn:.T :urrs . umi 1 m 7-50 dencnen: No./ , 1,= - .h- - .y, 'N .. ~.< mm + > j E# ? ' * "j 'h; _ f.'? % 4 m , d u y h h k - bb P' # " > ns_. , P l y i ; REFUELING OPERATIONS b SHUTOOWNCOULINGANDCOOLANTCIRCULATION LIMITING CON 0! TION FOR OPERATION , 4 3.9.8.2 Two (2) 4rt;=dht shutdown cooling loops shall be OPERABLE *f. l , APPLICABILITY _: Mode 6 when, the water level above the top of the irradiated fuel assemblies seated within the reactor pressure vessel I is less than 23 feet. I l ACTION: . )I
- a. With less than the required shutdown cooling loops OPERABLE, 4 initiate corrective action to return loops to OPERABLE status within one hour. 'l
- b. . The provisions of Specification 3.0.3 are not applicable. 4 l
SURVEILLANCE REQUIREMENTS ) ( 4.9.8.2 No additional Surveillance Requirements other than those required by ( Specification 4.0.5. , i I B , ) p. gr j. f(, , t-
- Normal or emergency power source may be inoperable for each shutdown cooling loop. ,
done shutdown cooling loco may be replaced by one spent fuel pool cooling loop 4 7 when it is lined up to provide cooling flow to the irradiated fuel in the 4 7 reactor core and tne heat generation rate of the core is below the heat 4 7 removal capacity of the spent fuel pool cooling loop. , d ;r r 4 7 Amendment No.gs '4 CALVERT CLIFFS - UNIT 1 ~ GLVERT CLIFFS - UNIT 2 3/4 9-Ba AmendmentNo.# Y 9 D . w'T l -* 4 ,- - a- my ms., '?$ . . , ,[ 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 8ASES 3/4.5.1 SAFETY INJECTI0t TANKS The OPERABILITY of each of the RCS safety injection tanks ensures that a sufficient volume of borated water will be imediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the safety injection t,anks. This initial surge of water into the core provides the . initial cooling mechanism during large RCS pipe ruptures. The limits on safety injection tank volume, boron concentration and pressure ensure that the assumptions used for safety injection tank ' injection in the accident analysis are met. . - . The safety injection tank power operated isolation valves are considered to be " operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met. In addition, as these safety injection tank isolation valves fail to meet single' failure criteria, removal of power to the valves is required. The limits for operation *with a safety injection tank inoperable for any reason except an isolation valve closed minimizes the time exposure 'of the plant to a LOCA event occuring concurrent with failure of an addi-tional safety injection tank which may result in unacceptable peak . cladding temperatures. If-a closed isolation valve cannot be imediately opened, the full capability of'one safety injection tank is not available and prompt action is required to place the reactor in a mode where this capability is not required. 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEM _S_ The OPERABILITY of two separate ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration. Either subsystem operating in conjuncticn with the safety injection tanks is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated b ak sizes ranging from the double ended break of the largest RCS cold leg pipe downward. In addition, each ECCS subsystem provides long ter. core cooling capability in the recirculation moda durin the accident recovery period. ~m_. Sc.eAffached .CALVERT CLIFFS - UNIT 1 B 3/4 5-1 b nd g MS. v .J b A + $ t.a< Anyn% i . 4 ?,' k$ ?' [fgr) , %, . foe %s cI N Iob ynawe t % i n j e e sek u[p ,s keo,,, ~ m f( ak # .. 'llljf ' 7g ' A s& $r M&s & l~ pssm s% sye.dio L emJn>l 4,c v-NC Mf ,: C. a, Y N OilNet,. denn .shtm Ch OV~k3C, Q k h,tr- l0w f M S }h h j .a 00y 510 h Ve {rts, bl$ hL yr$hni OS &, &p4k qq ym y, Q ; 'j , ~ ep% desiy is ed% h em e reliaW Eeeeop eu. k to R*sfe.I s p si , 8 e ls , fDY C yhtf3E k NIOWI t haC Ch Oc[d ' bc(& fjpg=lp ggir & h, LfI Tlu S95% ksIqs J cp f:*~isn un ic%i vHL fla. assup, ;n & c s . . l M ris. y Y 9 4 S 9 be t 4 8 ,g MF W$ @ < . -g s f K - . 'A #:~ l&%). t 4 , g EMERGENCY CORE COOLING SYSTEMS N' y h BASES - The trisodium phosphate dodecahydrate (TSP) stored in dissolving . baskets located in the containment basesment is provided to minimize the possibility of corrosion cracking of certain metal components during operation of the ECCS following a LOCA. Tne TSP provides this protection by dissolving in the sump water and causing its fjnal pH t'o be raised to > 7.0. The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be main-tained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the' system is in its minimum resistanc'e configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injecti.on points equal to or above that ~ assumed in the ECCS-LOCA analyses. The requirement to dissolve a repre-sentative sample of TSP in a sample of RWT water provides assurance that the store: TSP will dissolve in borated water at the postulated post LOCA teeperatures. ' 3/4.5.4 REFUELING WATER TANK (RWT) The OPERASILITY of the RWT as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LCCA. The limits on RWT minimum volume and boron concentration ersure that 1) sufficient water is available within contain-ment to permit recirculation cooling flow to the core, ano 2) the reactor will remain subtritical in the cold condition followino mixing of the RWT and the RCS nater volumes with all control rods inserted exceot for the most reactive control assembly. These assumptions are consistent with the LOCA analyses. The contained water volume limit includes an allowance for water $ not usable because of tank discharge line location or other physical characteristics. CALVERT CLIFFS - UNIT 1 B 3/4 5-2 Amendment <No;3 h 7 M y .,sq ' :n u , 1. vg ! / WSC& REACTIVIT( CONTROL SYSTEMS _ 3/4.1.3 MOVABLE CONTROL ASSEMBLIES FULL LENGTH CEA POSITION _ LIMITING CONDITION FOR OPERATION The CEA Motion Inhibit and all full length (shutdown and regula 3.1.3.1 within 7.5 inches (indicated position) of all othe , APPLICABILIT(: MODES 1* and 2*. ACTION: a. With one or more full length CEAs inoperable due .to being . iceovable as a result of excessive friction or mechan interference or known to be untrippable, be in at least liOT STANDBY within 6 hours. b. With the CEA Motion Inhibit inoperable, within 6 hours either: 1. Restore the CEA Motion Inhibit to OPERABLE status, or 2. Place and maintain the CEA drive system mode sw either the "Off" or any " Manual Mode" position and fully withdraw all CEAs in groups 3 and 4_a
- 3. i h c.
With one full length CEA inoperable due to causes other tnan addressed by ACTION a, above, and inserted bevond_ the Steady State Insertion Limits but within its above specified alignment requirements, operation in MODE tic:e of < 14 days per calencar year.
- d. With one full length CEA inoperable due to alignment requirements ano either fully withdrawn or within the Long Term Steady State Insertion Limits if in CEA group 5, operation in MODES 1 and,2 may continue.
See Special Test Exceptions 3'.10.2 and 3.10.4. CALVERT CLIFFS-UNIT 2-3/ 4 I-17 [MM M. g h i = .=. -~~$___ TABLL 3.3-10 . g; POST-ACCIDENT MONITORING luSTRUMENTATION C MINIMllM CHANNELS r) OPERABLE O INSIVyMENT < ft E 2 b'- y 1. Containment Pressure . 2
- 2. Wide Range Logarithmic Neutron Flux Monitor c:
- 2 f& f
~' 3. Reactor Coolant Outlet Temperature , 2 ,
- 4. Pressurizer Pressure 2
- 5. Pressurizer Level 2/ steam generator 4 6. Steam Generator Pressure ,
2/ steam generator err
- 7. Steam Generator l'evel (Wide Range) c' 6 8. Auxiliary feedwater Flow Rate 2/ steam generator [
Y . RCS Subcooled Margin Monitor 1 f_; 9. - PORV/ Safety Valve Acoustic Flow Monitoring 1/ valve 10. 1/ valve R 11. PORV Solenoid Power Indication a- 12. Feedwater Flow 2 i 8- f I to ? n. Containesk V.hkr Lud DJich Ra, .y .) b N .5 - r . .,'./.r
- w .g' .
- *L
- q
-4 . . M 7 I ru - - - TABLE 4.3-10 * - POST-ACCIDENT N0filTORiflG INSTRUMEriTATION SURVEILLANCE REQUIREMENTS ' .n N ,1 ,. CilANttEL CllANNEL M INSTRUMENT CilECK CALIBRATION . n 1. Containment Pressure M R [ 2. Wide Range Logarittunic Neutron flux Monitor M , N.A. [ - E 3. Reactor Coolant Outlet Temperature M R -4 m 4. Pressurizer Pressure M R *
- 5. Pressurizer Level M R
- 6. Steam Generator Pressure . M R
. '/
- 7. Steam Generator Level (Wide Ran'ge) M R i ,'
R* c. .- '8. Auxiliary Feedwater Flow Rate M R y A 9. RCS Subcooled Margin Monitor M R
- 10. PORV/ Safety Valve Acoustic Monitor N.A. R f 11. PORV Solenoid Power Indication N.A. N.A.
?1 12. Feedwater flow M R I k I3 Coda;6mid l0alir- Lav<I. (tGdi O r) M R l % a P- g . . i. M
- 4
'7 4, . . L 4 s ..) r- e .3 2,y ) [' . i ., ~ -l i}i.. y,% Li ' A
- cff.s;;Ni' '
i . 7 l 6: y 1i . . .;s y- . . , . w. ., . := ' W REACTOR COOLANT SYSTEM M 3/4.4.6 REACTOR COOLANT SYSTEM LEAXAGE LEAKAGE DETECTION SYSTEMS U 'a LIMITING CONDITION FOR OPERATION is . 3.4.6.) The'following Reactor Coolant System leakage detection systa " shall be OPERABLE: I
- a. A containment atmosphere particulate radioactivity monitoring,,
system,
- b. The containment sump level alann system, and ,
- c. A containment atmosphere gaseous radioactivity monitoring system.
APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: a.. . . With only two of the ab6ve required leakage detection systems OPERA 8LE, operation may continue for up to 30 days provided grab samples of the containmen 4tmosphere are obtained and analyzed at least once per 24-hours wheh 3 he required gaseous *nd/or. particulate radioactivity monitor- !Y!!!!S,f 8
- 1YlNibNd*N!5[d53,k b b"kb=
- 6. W cE-- k_
attached eset)) ' . . . . . . . . . . . . . . . - . . . . . . . , - . - . . . . - c~ SuiiVE!LEANCE REQUIRem.nTs 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE ,by: ,
- a. Containment atmosphere gaseous and particulate monitoring 6 systems-performance of CHANNEL CHECK, CHANNEL CALIBRATIONiand CHANNEL FUNCTIONAL TEST at the frequencies-specified in Table 4.3-3, and
- b. Containment sump level alarm system-performance of CHANNEL CALIBRATION at least once per 18 months.
h CALVERT CLIFFS - Uti!T A. 3/4 4-13 ?, g 4:, yh a / [y .- - ,., y,,. -- ,;]w
- b. Wik only one oS }he a bo ve refaire d les Asge de +ec fan systen.s O P E A /1 6 L E , operedtk MAy :
cen Wna e. foe ap ro 30 days provided fAs e a t },l / east coce pe, .2 y hou <s :
- 0) grab wnyle s o f +Ae cen h<inneni a 4rosphers.
I') are obtained and snalyEed, and , \. 'f; [2) fNe Resc iw Cco/ ant y S s& wske-dr&/wy - bs/a nc< of suuttu nact ntquixwtar ' Y. I'. 6.2. c i.s y, forned,
- c. Wi6 all lbree reguired leaksje de fec% cysus inoperable , res+ ore s+ less+ one. leskoy defec/4n syskn M 6 P E M 8 8. 6 s+a lu s w;ffin y- h n ,S se p
be in a + lea s t HOT STAND 8y wilAin the nex t & Awes 1 dn d in C0LD SHufboWH y,'} hon lhe. /pll pain) .30 haes. ~~__ Q ...A. _ _ I p s' C A T ACTidxs b. sn d c, absve en pag e 3 / y y --/ 3 4 s - OIL vfx Y cuff.5 - um 7 .L 7 p - p. a ~ , dti 'b'\ .d REACTOR COOLANT SYSTEM If f REACTOR COOLANT SYSTEM LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
- a. No PRESSURE BOUNDARY LEAKAGE, .
l
- b. 1 GPM UNIDENTIFIED LEAKAGE, J:
- c. 1 GPM total primary-to-secondary leakage through steam generators, g and
- d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System. ~h:
.1 APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: . ~
- a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY
~ within 6 hours and in COLD SHUTDOWN within the following 30 4 hours.
- b. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hcurs or be in at ;
least HOT STANOBY. within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits oy: Giber orgsseou a.^0) Monitoring the containment atmosphere particulatefradioactivity "di A*e gS N [as % W batnods hem emwpwWllis e utsinsesona3<1scharge ne. kriWnumutr 2.4.s.t. fr
- b. Mon oring the containment sump once per 12 hours, when de e,no;nme wmp tem atum is 'opsgARE,
~
- c. Performance of a Reactor Coolant System water inventory balance tj
#^'*F Tic'epTat lysg gjgegg w8en JJ operalinfg,gin tdeduring shutdown steady state cooling operation mode, and andat has CALVERT CLIFFS-UNIT 2 3/4 4-14 . OG!3A n m;u gt a ( l My ib v, l n TABLE 3.6-1 p - ~= M CONTAINiiENT ISOLATION VALVES ' hip S L J n' PENETRATION ISOLATION ISOLATIO!! VALVE ISOLATION i t C NO. CHANtIEL IDENTIFICATION NO._ FUNCTION TIME (SECONDS 1 a a N[' 1A SIAS A -CV-5465- PS-5%S-CVR.C. and Pressurizer Sampling -<7 ly SIAS A EV 5466 PS-5#6-cy 1 E g SIAS A CV-5407 PS-SM7-C V ?"1 51AS B M44t Pb-SWi-CV m :f.i la SIAS A SIAS B C+41eeWO-B180 cV Containment Vent lleader to Waste <7 CV-2101 @S-dl%l'-CVGas <7 7 i% . A IC SIAS A CV40C bVC-Sc6-CYRCP Seals Controlled Bleedoff <7 9 R** SIAS B CV-595 CVC-So6-CV 57 a g i i 1D HA -&V -6523 : PS-fos 29-3yPost Accident Sampling 2;
- N Liquid Return to RC Drain Tank NA 2.~t SIAS A C"-515 CvC-sl5-CV Letdown Line <13 SIAS B CV- 5 5 cvC-SI6-CV 71 3
- NA 7M3-+ CV C- loS nA a NA ?M3 4 CVC-1O3 -
nA $' k ~ -@ 2B NA CV-517 CVC-Sil-CV Charging Line NA ~i 3 NA GV-518 CMC-61%-CV - NA 3 " NA f,Ve Cvc-Sl9 -CV NA J E NA SP410"O-2 CVC-456-NY NA - ~ NA 310M3-2 C VC- 24 nA ,i., ct \ p ~ ... e esie' 4 , .4 - ;% l. y '[ ? , _ , Q,g . * . ? . i . 4M d) TABLE 3.6-1 (Continued) $ n
- d. a-g Q CONTAINMENT ISOLATION VALVES y> .
m n ' -i- PENETRATION ISOLATI0tl ISOLATION VALVE ISOLATION Y:P:. p NO. CHANNELS IDENTIFICATION NO. FullCTION TIME (SECONDS) .[Q *;; 'J - -p 7A NA Bilnd Flange ILRT NA 3 NA W) I L &T-1 - NA C 5 H 78 NA Blind Flange ILRT HA' N t!A ItriILRT-2 fA ' h- 7 8 SIAS A M0W-Stet EAO-54(ea'bainment Normal Sump <13 3 SIAS 8 MOV-640 EAD-5%3-mov a j3 R- 'g NA 23"3_3 s1-340 Containment Spray NA NA E38MI-e SI-52fo itA ? N 10 g 73.u3_-3 51- SM Contairrient Spray t1A A 23"#.3-2 S L 3
- ftA
=: c PA -l'Ito -CV(3) ' ' 3 <7** SIAS A CRS A CV-1410 (3} Purge-Air Inlet ;g SIAS B, CRS B CV-1411 (3) -77**
- g. ceA-tyss- cv(3) ,
R E .1 2 .. ir' a. e si. 1 y . Y. ? \ ( -- ,c l TABLE 3.6-1 (Continued) , 1., Q G C0tlTAltillEtiT ISOLATION VALVES f.,ri.- " ISOLAT10ft VALVE ISOLATION PErlElRAT10ft ISOLATION ' CllAliflELS IDEllTIFICATION NO. FullCTION TIME (SECONOS) P N0. ( q g? CV-1-i;2 (3) /cpe-lyta-CV (3) ^U 14 SIAS A, CRS A Purge Air Outiet ~<7** _ <7** . SIAS D. CRS 0 CV !113-(y C.PA-lH13-CV CO @[ -- ! c- . l .a. <7 15 SIAS A EV=Sf91 RE-SJ91-CV Purge Air Monitor , " c ~~I7 q I SIAS B CV -- 52 024E-5292-CV , Y CIS A CV-3C32 cc 5s52-CV Component Cooling Water inlet <l8 16 g 6 _ m 't CV-303 CC.-3855-CV Component Cooling Water Outlet <18 w 18 CIS B a NA $ b 19A flA 4;L3 -} IR- 176 Instrument Air - ~ "0"- 2080 I A- 2cso-rnov 33 CIS A . ~ - pp-i39 Plant Air fiA 190 nA 'n ; ;3-; e P A- scN4* NA 7 flA ' .g y 20A tjA p g,_3qI fiA g NA cv_;;zmN._ 2 bgg #0y)IitrogenSupply NA y g- N NA y, NA CV-622 2 - 622-CV . ; _g - NA NA CV-632 "N2- (c 52-CV ( NA -cy_;.; g = N2 - G42.-CV F liA N r g j ?j . t d- 2A*g 9 r . . '( , s. *: {l TABLE 3.6-1 (Continued). .j- . a G CONTAlHitENT ISOLATION VALVES 9 , s
- PENETRATIOil ISOLAT10ft ISOLAT10ft VALVE ISOLATION d P NO. CitAfitiEL 10ENTIFICAT10fi -NO. FUNCTION TliiE (SECONOS) [ '
? 208 ilA -2t M'h/ 2-~548 Hitrogen Supply NA 9 , tiA ttht Ny ~395 NA ;f.h - g 1 20C tlA N h/.-399 2 Hitrogen Supply fiA I'^ IIA teF2N2~398 . ) .k 23 SIAS A CV-4266 64w- EC.OrainTankDrains <J 3 .p ,- 3 - S',' 5531 PS-4531-SV0xygen Sample Line <7 24 SIAS B - $ 37 flA 1"bt PdW-3NO Plant Water NA Q NA H2-+ PSd-lOCS liA m _ ~ ~ 38 - ifA C'! - 54 50
- DW-S%C'De neralized Water f' ^
u 1-3 gig-i SI-M Safety Injection Tank Test Line flA i-39 ftA g IIA I 30:13-2 SI- 965 NA 3 3 '6 2 p se2-movc) ":N ", 41 ilA 240V-652 (2s Shutdown Cooling f(A / 2 flA MSV-65i ( ZiSI-GS i-(DOV (2.3 ttA $ ? o + 9- * **c. . ' * ,4 m + - . ; 4,h E ' SM[G _ ( ., 3
- h
. r- ~ ,N e Ykh O c-TABLE 3.6-1 (Continued) Ir% h' a CONTAltit1ENT ISOLATION VALVES ), A P PEtiETRATION ISOLAT 10ti ISOLATION VALVE ISOLATION .$ G,, NO. CilANt;EL IDENTIFICATION ti0. FUt4CTION TIME (SECONOS) Wx w . 44 NA 2 3 0 1 FP-195-A Fire Protection tiA c-NA -220 1 FP-140-6 NA tiA ".0V 0200 ' F9-fo2.OO-tYb/ E NA .., ~ P S - b S V0 A -S V * ' 47A tiA SV-05?.LA * - Hydrogen Sample Outlet NA s tiA 5V-6507A cP6%sc7ss-SV* NA : ;, e a ps-GSHOE-54 W 478 NA SV-0540; " li rogen Sample Outlet NA . t1A SV-0507i. SS-6So7E $N tiA %u ps-GSHof-SVN cn 47C NA SV 5510f ^ liydro NA t4A SV- 0;;7T -PS-660795V+ gen Sampl e Outlet NA w 1 470 NA SV-6;f.GG PS-GSHOS*SJ M11ydrogen Sample Return NA NA SV-6;07G 650%-s4 NA . 1 -r 2 J 48A SIAS A tiDV-6)G6HP-Om-Montainment Vent Isolation < 20** <,
- 8m SIAS B T10V- 090lHP-6901-InoV T_ 20** j_ a 3
3 r' rif n% Z P s M .D .* y . n .y - '4 @ ,. ' }li ' w - i. A 4? -QD + , - :h., ..syget A:;y II GgI ~ t - .d Sf m 7 J,(f.fs ^ 3 1R.qm,St[g/dM3%t 1 4 ? g. ., gt yy; ) : S d. ( NN OO D ' I C : TE
- AS AA AA AA AA AA AA AA NN NN k',
1 l Nf iN : L( iN t NN NN O - } SE I M O I T '.,.g ; l k .f , Q n ; ',y T w .} o ' Q d y :p: a . ' ; L { N d~ 0 t t a 1 e e e , T l l H C C1 n n ' f i e I r U e e o ' f e l p l l l t g p p o c S r m m m o a E u a a a P e ) V P S S S R d L g e A n n n n n o u V e e e e i t n g g g g
- oG *o4 l l i N o *oM e m t
n o O I do rV y V rV Sy-d6 v r6 sd-Vr5 Sd-T R f u a e T im y0 L e t A bTyD C 6H6 c H 7) i l I R S ( L - T C , - 1 O S 3 0 0 4 c7 o C w S> H 'o l S 6 - I 9 6 S ro #f e G g G S, r 8C l 3 . T N EN O 4- - S S 5 b 5 - 7l F l 31 E V 10P P 3 P- P= - - E L M t LN AO - H P- e p* P PP: H-N B t l VI O3 G ; 0 C" 0 D ee F1 5 f A T A T NA T M 30 G 7 0 7 j0 0 7 gg nn SS S' E E N OC 1 5 M ;0 5 5 4 0 5 5 aa 2 , O C I I TF 0 V - - 0 ; 5 0 0C 1 l FF M1 M' 3 0 1 AI 3 0 V y V V VV 3" 3 3 LT Ol i 2 l1 5; SS 5E dd nn 2 2' 14 . SE ii + I D l 1 % + I ' BB j-l N OL I E TN l AA AA AA AA AA AA AA At NH NN NN NN NN NN iN t LA OH SC I N O I T A . 8 A 8 C RO 8 9 9 9 0 9 0
- TN 4 4 4 4 5 5 6 .
E N E P 3 Q g g ~ h q nw ., c= " N wD [# 3a $ fl.a 7.s _ 4a 3 = T 5 I ;f! i;, l ! o .a, n # 'h5s . 4 TABLE 3.6-1 (Conti nued)- ~f . .y. 9 CONTAINr1ENT ISOLATION VALVES @ c-4 4, v 9 PENETRATION ISOLATION ISOLATION VALVE ISOLATION E NO. CilANNEL IDENTIFICATION NO. FUNCTION TIME (SECONDS) P yQ *;; 61 NA ffMM 9 9-13+ Refueling Pool Outlet fiA Jy ? . NA 99-3tM SF 9 - M NA SM . HA 293ft-4 SF 9- GO NA M c- NA 293it4SF P- @c HA Y ' *-= -1 PH- G 579-' rov % 62 SIAS A HOVHHrM Containment Heating Outlet ~<13 % . 2 Jit + a 64- NA esfM PH-537 Containment Heating inlet NA w s, (1) Manual or remote manual valve which is closed during plant operation. ) q y Sm (2) May be opened below 300*F to establish shutdowri cooling flow. -j$ 7 N m.r. (3) Containment purge and containment vent isolation yalves will be shut in MODES 1, 2, 3 and 4 per TS 3/4 6.1.7 and TS 3/4 6.1.8, respectively. l 7~ i .
- May be open on an intermittent basis under adminlstrative control. fd
** Containment purge isolation valves isolation times will only apply for MODES 5 and 6 during which dj time these valves may be opened. Isolation time for containment purge and containment vent isola- 9 4 E' tion valves is NA for MODES 1, 2, 3 and 4 per TS 3/4 6.1.7 and TS 3/4 6.1.8, respectively, during t in S which" time these valves must remain closed. ;d n - U .@ q ~ u WD n ~, O g ,'Q' ;o Q .l .k s' v b""- 1 u p 7 'd-gh w g 'D, ' A ...# '# , go $.g c} :g ; <.M, :t . . wg9 9 .s n ,, ,. 2 _;g 3, '* 1 .v yk . l ~ , ,z,:Q2g yQ _ , , ~ ~ ~ . ' , ~-w.g (^} }, , _-. yvva. 'a f.; " -. ~ ' ' 1.[' . d ., * ~ t, S ?h 4 .- p' n t i N.T.I ,. . .~ , ~% . ,.- . u fl .a ,y y w . ..g u ,_ w ; m . , .. ag .Y a- bhk ,' " ' i . $.;, 3 , .. p a \ [ If s l * ":' [.jd . ,4
- Y *
#Q{ ', lj . * ' f : l , l ' REFUELING OPERATIONS
- 1. ' SHUTDOWNCOELINGANDCOOLANTCIRCULATION g
j .l LIMITING CONDITION FOR OPERATION , 3.9.8.2 Two (2) '-d:;;.;ct shutdown cooling icops shall be OPERABLE *.f. [' APPLICA8ILITY: Mode 6 whan.the water level above the top of the irradiated fuel assemblies seated within the reactor pressure vessel 1 ( is less than 23 feet. ACTION: h
- a. With less than the required shutdown cooling loops OPERABLE, -
initiate corrective action to return loops to OPERABLE status within one hour. I
- b. .The provisions of Specification 3.0.3 are not applicabie.
I i SURVEILLANCE REQUIREMENTS 4.9.8.2 No additional Surveillance Requirements other than those required by Specification 4.0.5. (I 4 i O - l ) <[ (,
- Normal or emergency power source may be inoperable for each shutdown cooling loop.
#0ne shutdown cooling loop may be replaced by one spent fuel' pool cooling loop th when it is lined up to provide cooling flow to the irradiated fuel in the 9 reactor core and tne heat generation rate of the core is below the heat 47 removal capacity of the spent fuel pool cooling loop. , d;;r f7 ,CALVERT CLIFFS.- UNIT 1 _ Amendment No. H CALVERT CLIFFS - UNIT 2 3/4 9-8a Amendment No.18 g h) \ n -Qg$ ^ c 4 LJ .3/4.5 . EMERGENCY CORE COOLING SYSTEMS (ECCS) BASES - 3/4.5.1 SAFETY INJECTION TANKS The OPERABILITY of each of the RCS safety injection tanks ensures that a sufficient volume of borated water will be imediate.ly forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the safety injection tanks. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures. The limits on safety injection tank volume, baron concentration and pressure ensure that the assumptions used for safety injection tank injection in the accident analysis are met. The safety injection tank power operated isolation valves are considered to be " operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed, automatically whenever permissive conditions are not met. In h addition, as thase safety injection tank isolation valves fail to meet single failure criteria. . removal of power to the valves is required. The limits for operation with a safety injection tank inoperable for any reason except an isolation valve closea minimi:es the time exposure of the plant to a LOCA event occuring concurrent with failure of an addi- ~ tional safety injection tank which may result in unacceptable peak cladding temperatures. If a closed isolation valve cannot be imediately opened, the full capability of one safety injection tank is not available and prompt action is required to place the reactor in a mode where this capability is not required. 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two separate ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration. Either subsystem operating in conjunction with the safety injection tanks is capable of sucplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward. In addition, each ECCS subsystem o provides long tem core cooling capability in the recirculation mode Lj - during the acci nt recovery period. A f fo<Ald e CALVERT CLIFFS - UNIT 2 83/45-l dm2d*d O '-- as, .i: 1 ; ,- ' 'Poc%s el %. 101 presure t% injedibfsysk,,Are e.omn k . a ha substk 7kir ine&da k l~ pswn sdeg hjedio L ex Jrvi 4, c v-x6 A ' L ortkee. devn .s%~ 05 ev-3aL, a m h.ir- luprawa say ;yiA loop isaldk vatus. AH44 %t pr% at ik Lp44 aa umaa, 4. sysk disiy is ad% k wr< reliaW Eat opnk ok.fo % sfevi perkd ol y syslon qctalk hilowly <, lost 0 GolsJ beidid prive h rteirenfafb. LS TItt Sysk disly J p.B~Ir :-t centithd '"Hi IAL GL$unyf Q jn k ( , e '1 Sis. o a O O $ [ #k ' *l ( , / "'}}