ML20235V159
| ML20235V159 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/24/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-89095, NUDOCS 8903100063 | |
| Download: ML20235V159 (40) | |
Text
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Log # TXX-89095 File # 10014 916 clo 7UELECTR/C Ref.,# 10CFR50.36 February 24, 1989 W. J. Cahill Executive Vice Presiden, o
U. S. Nuclear Regulatory ' Commission w
Attn: Document Control Desk Washington, D.: C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N0. 50-445 PROPOSED CHANGES TO THE TECHNICAL REQUIREMENTS MANUAL'(SUPPLEMENT)
REF:
TV Electric Letter to NRC, TXX-89038 dated January 24, 1989 Gentlemen:
The referenced letter provided the NRC with a draft copy of TV Electric's
~ Technical Requirements Manual for CPSES Unit 1.
The following is a list of attachments to this letter providing revisions to TV Electric's draft
-Technical Requi~rements Manual to address NRC staff concerns. -
Technical Requirement 1.2 (Table 1.2.1), " Engineered Safety Features Response Times," (Update response times and table
. notations.) -
Technical Requirement 3.1 (Table 3.1.1), " Containment Isolation Valves," (Update notes and leak test requirements.) -
Technical Requirement 4.1, " Snubbers," (Add Technical Requirement for surveillance of snubbers.) -
Technical Requirement 4.3, (Bases), " Station Service Water,"
(Clarify that this requirement is in addition to Technical Specification 3/4.7.4.) -
Technical Requirement 5.1, (Table 5.1.1), " Containment Penetration Conductor Overcurrent Protective Devices,"
(Provide clarifications to the table.)
a IR d
a 400 North Olive Street LB 81 Dallas, Texas 75201
j-p -' 'p < (' 4s "
'TXX-89095-L
_.. - February 24, 1989 Page,2'of 2'
~
If you require additional information concerning'this revision, please contact
.this office.
Sincerely, f
_~_ _.
William J.
ahill, Jr.
L JDS/grr c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3)
_ = _ _ _ - _ - - - _ _ _ - - _ _ _ _ _ _ - - _ _ _ - _ - - - - - - - - - - - -. _ _
u
TXX-C90,9,5
{
Pfge 1 of 3 Technien1 Reruirem ne 1.2 (crntinued)
TABLE 1.2.1 ENGINEERED SAFETT FEATURES RESPONSE TIMES INITIATION SIGNAL AND FUNCTION 1
RESPONSE TIME IN SECONDS 2
i 7.
Steam Line Pressure - Negative Race-High Steam Line Isolation 7
8.
Steam Generator Water Level - High-High a.
Turbine Trip N.A.
b.
Feedwater Isolation 111 9.
Steam Generator Water Level - Low-Low a.
Motor-Driven Auxiliary Feedwater Pumps 160 b.
Turbine-Driven Auxiliary
~
Teodwater Pump 160
- 10. Lose-of-offsite Power Auxiliary Feedwater N.A.
- 11. Tri;
-8._11 S ir. 7::l u e:r ? :;;
gTEI All A-;11..y 7..J. ;;; " ;p;
"^
- 12. RWST Level - Low-Low Coincident with Safety Injection
~
Automatic Initiation of ECCS
<30 Switchover to Containment Sump
~
ud. 480 V
- 13. Loss of Power (6.9 # Safeguards System Undervoltage)
- a..*9 kV Preferrd, 6-i 0ffsite Source Undervoltage
<[1 i..
2 a. '" } 2,,
- 6. E n g A )l G ih A k s. q #m.t k y f 7!! : : : r.L a, ct) 4usOhdervoltde c.4 49 kV 5
~
l d.. (. 9 kV a.nd. 48,0 V grd Ye t 6 10 (,g9) 7 c
e:a. s.%-d L ec.A
/
L.hc.h ag e (.ht.s 6 r Yg, O WWA:
C, k bO Y l o a b rid. L)cdc.rve d a, e
- 6. (o 3(t,9).
_ k i
A
/\\
,ONg h 1.2-7 Rev. 0,
e
T'XX-89tf95 '
- Page 2 'o f 3 DRAFT Technical Reovirement 1.2 (continued)
TABLE 1.2.1 TABLE NOTATIONS (1)
Diesel generator starting and asquen'ce loading delays in.cluded.
y (2)
Diesel generator starti.ng delay not included. Offsite power available.
(3)
Diesel generator starting delay included.
f c8afr f a.I ckarg ar p=-p t ars ;'icJJeal.M
.ia alu ded. C al M
(4)
Diesel generator starting and sequence loading delays not,e included. """ ; n :,;Ei, u.s.hd:4. dalfc fr.4 s A y 3 3
ps -pe m %.1J sd 44-).
e Ties Limit includes opening of injection path valves.
n additional time is allowed for coupletion of the of the pump suction from the VCT to the 1937 M
.u (6)
Includes containment pressure relief line isolation only.
(
(7)
Response Time Limit is up through pump breaker closure -
only. Both times shown include sequencer loading delays and the larger number also includes diesel generator starting delay.
-(f) desycMSc Dm.s. mured k c>wipt uQ oQcVVo ok C. c.
1.2 5'NGIhzzmED SArr.u FEAKvaES ACTUATION STatras RESP 0BSE TDGE The bases for the Engineered Safety Features Actuation Systen are contained in the CPSES Technical Specifications. The measurement of response time at the specified frequencies provides assurance that the Engineered Safety Features actuation associated with each channel is completed within the cias limit'assamed in the safety analyses. No credit was taken in the l
analyses for those channels with response times indicated as not applicable. Response tias may be demonstrated by any series of sequential.
overlapping, or total channel test measureaancs provided that such tests demonstrate the total channel resysase time as defined. Sensor response time verification may be demonstrated by eithers (1) in place onsite, or I
offsite test measurements, or (2) utilizing replacement sensors with
)
certified response cias.
1 (r ) Seps d l bs fu..f c.k.q g p p sdha. b% &. vc.r to &
i RsMt* (tusr selves 09%, %., Vc.T < alm class) is as i~ isefuled.
& S e p.sdis.\\ i.ru sfer. o $ cksyQ p+ p Swdim $rm ' Eks. VCr E* N M T (.f d T' v4. lees
., 3 % ^x ^\\. q,f u$ tb Vcf. nl<e
- c. lust) 25 inclade J.
o 33 3., m 3.
3 j
o
}q) % aMwaJ.sec*b' 1s a Howa 6le~ k ra'ile g a o Ks n
Q. brea k e r +@ kc M^M-fouree
-w
~
_v,
_ w v % ~ ^- n ehe t______________
4' u
TXX.-89095 Page 3 of 3 l
JUSTIFICATION FOR CHANGES TO TABLE 1.2.1 These changes to the time response Table 1.2.1 of the Technical Requirements Manual are based on circuit design allowing two seconds for the alternate offsite source to correct the degraded condition before tripping the alternate feeder breaker. The additional two seconds is directly related to the noted channels since therie signals go through a common agastat that has a two second time delay (27-3Z/1EA1).
l l
1
Attachnient 2 I
7tX-89095 Page 1 of. 24 DRAFT TECINICAL REQUIRDGNT 3.1 TABLE 3.1.1 c.-
m p CONTAll0ENT ISOLATION VALVES tu; i Th f'V NY orts A4>.)
FSAR TABLE ISOLATION, 4TPt-j TDtB l LEAE TEST /
VALVE NO.
REFERENCE NO.*
LINE OR SERVICE (Seconds) R_IQUIREPENTS 1.
Phase "A" Isolation Yalvee e,
A Lm 157-2154 20 Feedwater Sample 5
t ;e L ///A (FV to Sea Gem #1)
IMV-2155 22 Feedwater Sample 5
"::: 14/4 (FW to See Gen #2) s
)
1H7-2399 27 Blowdown From Steam 5
Sote+.A//A g
Generator #3
'\\
187-2398 28 Blowdown From Steam 5
- n 1 Al/4
~
Generator #2 I
1H7-2397 29 Blowdown From Steam 5
C 1-4/A
/
Generator #1
/
187-2400 30 Blowdown From Steam 5
OnIJA Generator #4
\\
/
\\
1-8152 32 Letdown Line to 10 C#"
Latdows Heat Exchanger 1-8160 32 Leedova Line to 10 Ce Letdown East Exchanger C
1-8890A 35 IER to Cold Leg Loope 15 L.;e?ih
- 1 & #2 Test Line D
re;e a L
I 1-88905 -
36 ERE to Cold Les Loope 15, ~ E
.j f3 & #4 Test Line 1-8047 41 Reactor Makeup Water 10 C
to Pressure talief
& RC Pump Stand 7s 1-8843 42 SI to RC System Cold 10
- F A
Les Loops fl. #2. f3. f4
/
Test Line
(
t l
1 3.1-4 Rev. 0
At.tachrr, ant 2 TkX-89095 Page 2 of.24 DRAFT TECENICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued) i
/m,-
^
N CONTAINMENT ISOLATTON VALVES _(it Sh'
/
(
)
O
('
MAggggy ( 4eris M6 FSAR TABLE
- IS0!ATION \\.1TPS-./
TIME
/ LEAK TE$T VALVE NO.
REFERENCE NO.*
LINE 01 SERVICE (Seconds) REQUIRENDrTS 1.
Phase "A" Isolation Yalves N
i C#'
1-8881 43 SI to RC Systen Ist Leg 10 e "ne 1 ^, 4 s
Loops #2 & #3 Test Line
(
L 1-8824 44 SI to RC System Hot Lag 10 f 0... O ^ 4/4-Loops #1 & #4 Test Line c,
s' 1-8823 45 SI to RC System cold Les 10
\\ Ten: 13 A[A Loops #1. #2, #3. & #4 j
=
Test Line g
"s i
.A
,Q 1-8100 51 Seal Water Retura 10 C
and Excess Letdown 1-6112
'51 Seal Water Retura 10 C
and Racess Latdows 1-7136 52 RCDT Esat Enchanger 10 C
to Waste Bold Up Tank LCV-1003 52 RCDT Rest Enchanger 10 C
to Vasca Mold Up Tank 1HV-5365 60 Domineralised Water Supply 5
C IHV-5366 60 Dominera11 sed Water Supply 5
C 1H7-5157 61 Containment suay Pump 5
C Discharge 1HV-5158 61 containment Suny Pump 5
C Discharge 1HV-3447' 62 Instrument Air to 5
C Contaissent
,.7l
- q
[ - 5;n 2 : 0 /y, )l C,,
1-8825 63 RER to Eet Les Loops 15
- 2 & #3 Test Line j
s 1HV-2405 73 Sample from Steam 5
- 1 M/A Ceserator #1 7
jy 1HV-4170 74 RC Sample From Not Legs 5
C 3.1-5 Rev. 0
Atjachmeet 2 TXX-89095 Page 3 of g DM TECENICAL REQUIRDENT 3.1 TASLE 3.1.1 (Continued)
,f G '
)
CONTAINMENTISOLATIONVALVES[(wTi fj (x
j L
( Alorts &
TSAR TASLE
^ LIS011 TION (LEAKTEST/
MPG-TIME VALVE NO.
REFERENCE NO.
- LINE OR SERVICE (Seconds) R$0UIRDENTS 1.
Phase "A" Isolation Valves (Continued) 1HV-4168 74 RC Sample From Hot Les #1 5
C
~
1HV-4169 74 RC Sample From Het Leg #4 5
C '^\\
s 1HV-2406 76 Sample from Stem 5
5::; 1-M/A Generator #2 l
i 1HV-4167 77 Pressurizer Liquid 5
\\, C y '
Space Sample 1HV-4166 77 Fressuriser Liquid 5
C Space Sample 1H7-4176 78 Pressurizer Steam 5
C Space Sample 1HV-4165 78 Fressuriser Stem 5
C,- 7,-
Space Sample
)
1H7-2407 79 Sample From Steam 5
5::: 1-k 4 Generator #3 1HV-4175 80 Accumulators 5
C' 1HV-4171 80 Sample Frca 5
C Accummiator il 1HV-4172 80 Sample From 5
C Accumistor #2 l
1HV-4173 70 Sample From 5
C Accumniator #3 1HV-4174 40 Sample From 5
C Accumulated #4 1HV-7311 81 RC FASS Sample 5
C Discharge to RCDT 1HV-7312 81 RC FASS Sample 5
C-
-]
7 Discharge to RCDT 1HV-2408 82 Sample from Steam 5
5::: LM Cenerator #4 4
3.1-6 R:. O
, Attachment 2 TXX-89095 Page.4 of g4 DRAFT TECERICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued)
, O ~~~
CONTAINMENT ISOLATION VALVES (_=T;.' y ]
\\
NAEDaht dorrs Mb) v ISOLATION MP3- )
FSAR TARLE TIgg LgAg Test VALVE NO.
REFER 5CE NO.*
LINE OR SERVICE JSeconds) REQUtIDENTS 1.
Phase "A" Isolation Yalves (Continued) 1-8871 83 Accumulator Test and Fill 1D C
1-8888 83 Accumulator Test and Fill 10 C
1-8964 83 Accumulator Test and Fill 10 C
1HY-5556 84 Containment Air FASS 5
C Retura 1N7-5557 84 Containment Air FASS 5
C Retura 15Y-554A 94 Radiation Monitortas 5
C Sample 1HY-5545 94 Radiation Monitorias 5
C Sample 157-5558 97 Containment Air FASS Inlet 5
C 1HY-5559 97 Containment Air FASS Inlet 5
C IHY-5560 100 Containment Air FASS Inlet 5
C 15Y-5541.
100 Containment Air FASS Inlet 5
C 1HY-5544 102 Radiation Monitoring 5
C Sample Retura 1H7-5547 102 Radiation Monitoring 5
C Sample Retura 1-8840 104 Ns 8#Pyly to Accumniators 10 C
1-7126 105 En Supply to RC Drain 10 C
Tank 3.1-7 Rev. 0
- - - - - - - - - - ~ ~
~;
, Attachment 2 TXX-89095 Page 5 of 24 TECHNICAL REQUIRDENT 3.1 TABLE 3.1.1 (Continued)
,N CONTADOENT ISOLATION VALVES (, 2;,7 e (
{
AloTESyfp}
Y
"~fSOLATION \\
fTPE-
/
FSAR TABLE Tygg Lggg 7ggy VALVE NO.
REFERENCE NO.*
LINE OR SERVICE (Seconds) R3dWIREMENTS 1.
Phase "A" Isolation Valves (Continued) 1-7150 105 En Supply to RC Draia 10 C
)
Tank 7 \\
8 L-1HV-4710 111 CC Supply to Excess 5
S;; - A[A Leedova & RC Draia Tank Rest Exchanger
)
f 1HV-4711 112 CC tatura From Encess 5
5::: 1- //A Letdova & RC Draia Task Rest Ezebanger 15V-3486 113 Service Air to 5
C Containment 1HV-4725 114 containment CCW Drais 5
C Task Pumps Discharge 1HV-4726 ile Containment CCW Draia 5
C Tank Pays Discharge 1-8027 116 Nitrogen Supply to FRT 10 C
1-8026 116 Nitrogen Supply to FET 10 C
1HV-6084 120 Chilled Water Supply 10 C
to Containment Coolars 1HV-6082 -
121 Chilled Water 1stura 10 C
from containamat Coolers 1HV-6083 121 Chilled Water Return 10 C
From Containment Coolers 1HV-40755 124 Fire Protection System 10 C
Isolation 1HV-4075C 124 Fire Protection System 10 C
Isolation 3.1-8 Rev. 0
Attactvnent 2 I
3
'TXX.89095 Page 6 of 24 '
1 DRAFT TECWICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued) 3 ^h CONTAINMENT IS01.ATION VALVES IMn;
~
{
}
'\\,NAgDitM i jeffS Mk ISOLATION 9Tp9-TSAR TABLE TIME LEAK TEST)
VALVE NO.
REFERDCE NO.*
LINE 01 SERVICE (Seconds) / REQUIREMENTS l
v-2.
Phase "B" Isolation Yalves 1HV-4708 117 C Retura Prom BCP's de 15 C
Motors CCbeturaFromBCP's 157-4701 117 l
-4045 C
Motors 1HV-4700 118 C Supply to RCP's 1915 C
=
Meters CbturaPromICP's 1EV-4709 119 4415 C
Tae st.arri.e vJ 157-4696 119 CC Estura Prom RCP's 4e15 C
Thermal Barrier 3.
Containment Yestilation Isolation Yalves 157-5542 58 Bydrogen Purge Supply EA C
187-5543 58 Eydrogen Purge Supply NA C
187-5563 54 Bydrogen Purge Sepply R&
C INV-5540 59 Eydrogen Purge Ezheast NA C
1HV-5541 59 Eydrogen Purge Ezheast N&
C 1HV-5542' 59 Eydroges Purge Exhsmst NA C
1H7-5536 109 Containment Purge Air h.5 C
l Supply 1H7-5537 109 Containment Purse Air JEA 5 C
l Supply 1HV-5538 110 Contaiment Purge Air M.5 C
l Exhaust 1HV-5539 110 Containment Purge Air N# 6 C
[
Exhaust 3.1-9 Rev. 0 l
.iii.w..
......aw ii....-i-i.iim I
, Attachment 2 TXX-89095 Page 7 of 24 DRAFT TECDICAL REQUIREMENT 3.1
{
TASLE 3.1.1 (Continued) f CONTAINMENT ISOLATION VALVES ' :4 0 Ti s
k MAgdtDN MeTIS Mb
'y'ISOf.ATION g
-79PG-I FSAR TABLE TIME LEAKTEST/
VALVE NO.
REFER UCE NO.*
Q E OR SERVICE (Seconds) REQUIREMD TS x_ A__-
3.
Containment Ventilation Isolation valves (Continued) 157-5548 122 Containment Pressure 3
C Relief 157-5549 122 Containment Pressure 3
C
}
Relief
,n/L 4
Manual Valves
'e-sm, b
IMS-711 4a TDAFU Pump Waru>up Vilve N.A.
5;;; 1, l' 0 i
g IMS-390 5a Ns Supply to Steam N.A.
5;;; ; ///A Generator #1
'T 1MS-387 9a Ns 8#Pply to Steam N.A.
5::: 1#/4 Generator #2 1MS-384 13a Ns 88791y to Steam N.A.
t 5::: IM[A Generator #3 k
Tarm-upValve 1MS-712 17a TDAFW N.A.
5;;; 1, 1MS-393 18e Na Supply to Steam N.A.
5;;; i M/A Generator #4 1FW-106 20b Ns 88Pyly to Steam W.A.
5;;; L4[4 Generator #1 IFW-104 22b Ne 85Pply to Steam N. A. f 4eee-i-/[A Generator #2
- -"-110 21 On
- A, 0--.11;;
- 5. t..
5::: 1 1FW-102 24b We Supply to Steam N. A. \\
5 :: 1 A/A' Generator #3
/
1""
1;"
l' ;
"^
"^"" '
I 1FW-108 26b Ns Supply to Steam N.A.
( Lie i M!4 f
.m.
Generator f4 b(/s 1-7133 52 RCDT Isar Exchanger to N.A.
C i
s#
Waste Soldup Tank p
3.1-10 Rev. O
....._.1 TXX-89095 DRAFT Page 8 of 24 TECWICAL REQUIRDENT 3.1 TABLE 3.1.1 (Continued)
CONTAINMENT ISOLATION VALYt3 (, -20 **. 0 7'
b Q Mduam dous m (
_I
~ ~ SOIATI 45PE-TSAR TABLE TIME LEAK TES VALVI NO.
REFERENCE No.*
LINE OR SERV!CE (Seconds ' REQEIR M S 4
Manual Valves (Continued) 15F-011 56 Refueling Water it. A.
C Purification to Refueling Cavity 15F-012 56 tafueling Vater N.A.
C Purification to Refueling Caving 15F-021 67 Refueling Cavity to N.A.
C Refueling Water -
Purification Pep 137-022 67 Refueling Cavity to N.A.
C Refueling Water Purification Pump 15F-053 71 Refueling Cavity N.A.
C Sktsmar Pump Discharge 15F-054 71 Refueling Cavity N.A.
C Skimmer Pump Discharge m
k
/
MSN Bypass from Steam N.A.
Ne$a 1,+tt N Generator #1
(
M N Sypass from Steam N.A.
Nety'1, M l Gemarator #2 x
1H7-23353 11 MSN Sypass from Steam N.A.
Note 1. M l Generator #3
\\
15 MS N sypass from Steam N.A.
Nake,1, M N
Generator #4 5.
Power-operated Isolation Valves 1 M/A 1HV-2452-1 4
Maia Steam to Auz. FFT N.A.
From Steam Line #1 5
N:
II:
iD N.A.
Ce;e 1 N!A 1PV-2325 Steam Generator #1
/
C-t 3.1-11 Rev. O
. Attachment 2 1
TXX-89095 Page 9 of 24 DRAFT TECINICAL REQUIREMENT 3.1 TABLE 3.1.1 (Continued)
(m-; *) )
(
CONTAINMENT ISOLATION VAL
%,KkEINUNf< Aforts ML ISOLATION
-MPe-
)
T5AA TABLE TIME
" LEAE 7ES V VALVE NO.
REFERENCE NO.*
LINE OR SERVICE (SecoMe) bTfEMINTS 5.
Power-Operated Isolation Valves (Continued)
^N 1FV-2326 9
9dN:
$f: Me*
N;A.
5::: 1-M[A Steam Generator #2 N I-?
D Y=*
I N.A. N 5::: 1 M[4 1F7-2327 13 Steam Generator #3 I
j' 1HV-2452-2 17 Main Steam to Auz. FFT N.A.
5:n 1 #[4 From Steam Line #4
\\
N IFV-2328 18
- N I-
+D N.A.
Oe;.1-/[A Steam Generator #4 1EV-2491A 20e Anziliary Feedvater to N.A.
5::: 1-M/4 Steam Generator #1 1HV-24915 20s Auxiliary Feedwater to N.A.
5;;.1 4[4 s
/
1HV-2492A 22a Auxiliary Feedwater to N.A.
5::: 1 Mf4 Steam Generator #2
\\
/
s 157-24923 22a Anziliary Feedwater to N.A.
5::: 1 M[A Steam Genarator #2 i'
1HV-2493A 24a Auxiliary Feedwater to N. A. [ rn: 1 M/4 Steam Generator #3 N
s 1HV-24935, 24a Anziliary Feedwater to N.A.
!=; i N[A Steam Generator #3 1HV-2494A 26e Auxiliary Feedwater to N.A.
(/ TC; 1 NfA 1HV-24945 26a Ammiliary Feedvater to N.A.
In; 1 Af4 Staan Generator #4 1-47013 33 RER From Iot Leg Loop #4 W.A.
5:0: E MN/
1-8701A 34 REE From Hot Lag Loop #1 N.A.
Ne;e", 84 7!
C.
)
1-8809A 35 RER to Cold Leg Loope N.A.
Me;e i;0 l
- 1 and #2
/-
J 3.1-12 Rev. 0
4'
'TXX-89095 DEAFT
{
Page 10 of '20 TECENICAL REQUIRDENT 3.1 TABLE 3.1.1 (Continued) ca;- e $) )
.i CONTAINMENT ISOLATION VALVES I
~
y NextkN AfoTY5 A^tb FSAR TABLE
~ v I$0LATIO
-PFPS-TIME LEAK TES VALVE NO.
REFER D CE No.*
LINE 01 SERVICE (Seconds) ~1 REQUIREMENTS 5.
Power-operated Isolation Yalves (Continued)
Cy x
l L "; : + ;O--
1-88093 36 RIE to Cold Les Loops N.A.
- 3 and #4 1-8801A 42 "ig. "--f Safety Injection N.A..
"::: FA[A to Cold Les Loops #1, #2,
(
s
- 3, and #4 N/fA 1-88018 42 "T "-M Safecy Injection N. A. (
5:::
to. Cold Les Loope #1, #2, N
- 3, sad #4 s
fl u C
1-8802A 43 SI Injection to*Est Les N. A. (\\,
5;;e ?-fi Loops #2 and #3 R.JS C
1-88023 44 SI Injection to Eet Leg N.A.
";;e 4 's Loops #1 and #4 1-8835 45 SI Injection t old Leg N.A.(I
.;; ' 12.-
Loops #1, #2, #3, and #4 att.
1-8351A 47 Seal Injection to RC N. A.,
-wi.
Puny (Loop #1) 1-83513 44 Seal Injection to RC N.A. 7 C ^ ' ^ T. ? ~
Puny (Loop #2)
AIA 1-8331C 49 Seal Injection to EC N.A. \\
-,wier Puny (Loop 3) i A/A 1-8351D 50 Seal Injection to RC N.A.
S MO ~~s Y Pump (Loop #4)
N. A. k
";C lav-4777-54 containment Spray to
- P Spray Reader (Tr. 3)
C s
1HV-4776 53 Containment Spray to N.A.
Ce;; 3 Spray Header (Tr. A)
C 1-8840 63 RER to Rot Lag Loops N.A.
- 0 Y
- 2 and 93
~
j 3.1-13 Rev. 0
- Attachment 2 k
TXX-89095 Page 11.of 26' DRAFT TECENICAL REQtTIRDENT 3.1 TABLE 3.1.1 (Continued)
[
CONTADOGNT ISOLATION VAL $ bcTi (,'
y' l
k
(
3
~K/ NAEIN1H '
Norss Mk ISOLATIO 4455-TSAA TABLE TDgg f, gag y
VALVE NO.
REFERENCE NO.*
LINE OR SERVICE (Seconds) 'R'siiimariEifiS a
c.-
5.
Power-operated Isolation Yalves (Continued)
- ~
N/A 9 1-8811A 125 Containment Recire.
N.A.
%;; 1. 10-Sump to RER Pumpe (Train A) x 1-88115 126 Containment Recire.
N.A.
% ;e 1, 1C Sump to RER Pumps
/
(Train B) b&
)
157-4782 127 Containment Recire.-
N. A..,
i: 1, !?
7 to Spray Pumps -
(Trais A)
\\
AlA
\\
N 4
1EV-4783 128 Containment Racire.
N.A.
%;e 1, 10-to Spray Peps (Train B) p_s 6.
1-8818A 35 RER to Cold Lag Loop f1 N. A. / %;e : ". -
(
0 1-84185 35 RER to Cold Les Loop #2 N.A. '
%;; ; W I
C, 1-8818C 36 RER to Cold Les Loop #3 N. A.'
\\
1-8818D 36 RER to Cold Lag Loop #4 N.A.
% ;e : u
(
1-8046 41 Reactor Makeup Water to N.A.
C Presonriser Relief Tank and RC Pump Stand Pipe
\\, M/4 1-8815 42 High Esed Safety Injection N.A.
< S;; 2-to Cold Les Loops fl. f2
- 3. and #4 7
C ISI-8905A 44 SI to RC System Het Lag N.A.
~ %;;
i-l Loop #1
\\ '
C ISI-89055 43 SI to RC System Hot Les N.A.
L %;;
i
- l Loop #2 C
iSI-8905C 43 SI to RC System Hot Leg N.A.
-L;. 4 FI Loop #3 J.)
3.1-14 Rev. 0
Attach r.ent. 2
?
'TXX-89095 Page 12.of 24-DRAFT TEC BICAL REQUIREMENT 3.1 TA8LE 3.1.1 (Continued)
/
CONTADDENT ISOLATION V4LVES h e Q,
,m Gw (as a )'
\\
ISOLATI
-fTPt y l
TSAR TABLE TIME LEAE TEST l
V4LVE No. REFERENCE NO.*
LINE OR SERVICE (Seconds) REQUIRGENTS 6.
Check Valves (Continued)
[~
C ISI-8905D 44 SI to RC System Not Lag it. A.
Loop #4
/ u. I ;-
ISI-8819A 45 SI to RC System Cold N.A.
0; e 0 ;;.
l Lag Loop #1 N. A. (, I n : 3 g / l C
i 1SI-88193 45 SI to RC System Cold Lag Loop #2 C
ISI-8819C 45 SI to RC System' Cold N.A. / rn; t3-l Lag Loop #3
(
/
C 1SI-48190 45 SI to RC Systes Cold N.A.
t r;n : 0-Lag Loop #4 v
1-8381 44 Charging Line to N.A.
C Regenerative West
(~~~~'
Enchanger p [A s'
1CS-4368A 47 Seal Injection to RC N.A. k C '2 *~d, Pimp (Loop #1)
/
dl4 1CS-43688 44 Seal Injection to RC N.A.
t Crd Puay (Loop #2)
ICS-4364C 49 Seal Injection to RC N.A.
/ C-2M+
'h '
Pump (Loop #3)
N A/M 1CS-436d 50 Seal Injection to RC N.A.
(- A-e v7 L
Ptaip (Loop #4) w v ICS-8180 51 Seal Water Retura and N.A.
Cr.
Essess Letdows C
'^
C 1CT-145 54 Containmost Spray to N.A.
5 ::n*
N Spray Header (Tr. 5)
)
ICT-142 35 Containment Spray to N.A.
Spray Header (Tr. A)
A ICI) iCT'030 62 Instrument Air to N.A.
C j
j ConCaianose s
x 3.1-15 Rev. 0
,1
.Attachinent 2 TXX-89095 DRAFT Pado 13'01 24 TECINICAL REQUIREMENT 3.1 l
TABLE 3.1.1 (Continued)
O_,
)
CONTADOGNT ISOLATION VALVEN Qae
, ' ")
-- _MAEntDM, dcTES Mb )
ISOLATION
-MPG-TSAR TABLE TIME LEAK VALVE NO.
REFERENCE No.*
LINE 01 SERVICE (Seconds) REQUIREMENTS 1-8841A 63 RER to Hot tag Loop #2 W.A.
! : 2[
C 1-88413 63 RER to Bot Lag Loop #3 N.A. [50 1;p v
x_-
ISI-8968 104 N Supply to Accumulators N.A.
C ICA-016 113 Service Air to N.A.
C Contafamaat ICC-629 117 CC Return From BCF's N.A.
C
=
Motors ICC-713 118 CC Supply to RCP's Motors N.A.
C ICC 831 119 CC Escurn From BCF's N.A.
C Thermal Barrier ICE-024 120 Chilled Water Supply to N.A.
C Concaineent Coolers 7.
Steam Line Isolation Signal A. + 3 r
t1m $tsm frsm %u m Nota 1, p;.12 1HV-2333A 1
-415M-44-C.cnar6he 4'l 5
1HV-2409 3
Drain From Main Staan 5
\\ :::e 1 N/A Lisa #1 a,3 N:* Mf I S W -ft G,a m h. Sk u m W
eocca.hr # 2.
5 \\
Note 1,7,12 1H7-2410,
6 Drain From Main Staan 5
5::: 1 N/A Line #2 A+3 r *\\
1HV-2335A 10 6 $r 5
Note 1HV-2411' 12 Drain from Main Steam 5
h 5::: 1 A//4 N
Line #3 av 3 v% t. Man 7 hk W
1HV-2336A 14 6Catacts.E=r.4 4 5
.\\ Note 1,;,12 s
1HV-2412 16 Drain From Main Steam 5
5::; 1 A//4 Line #4 s
3.1-16 Rev. O
1
. Attachment 2 I
TXX 89095 Page 14 of 24 DRAFT TECENICAL REQUIRDENT 3.1 TA8LE 3.1.1 (Continued) 1 CONTAINMDrr IS01.ATION VA[VES t Nm e s /
1 l
-~
fj M
dgES Mb
'ISOLATIO N
/
TSAR TABLE TIME LEAKJES/
VALVE NO.
REF 5ENCE NO.*
LINE 01 SERVICE (Seconds)
I1LDENTS 8.
Feedwater Line Iselation Signal 4e 7
j 3
~~
1H7-2134 19 Feedwater footeesee-
'5 Note iT-i+4ae Steam Generator #1 3
/
1FV-2193 20e Feedwater Freheat Bypass 5
Note b-44-h Line s.G. #1 r
to 3
1HV-2185 20d Feedvater '- ' " -
5 Note-1, 12 W Bypass Line S.G. #1 3
15V-2135 21 Feedwater Isoturtour'tT 3
Note 1, 1;Lr x Steam Generator #2 3
/
17Y-2194 22e Feedwater Preheat Bypass 5
Note 1, 42" r Line S.G. #2 N
3 INY-2186 22d Feedwater 4seteesee-5 Note 1, 4-2 L Bypass.Line S.G. it 3
1H7-2136 23 Feedwater 4eelstees b 5
Note 1, 42h Staan Generater #3 3
s IFV-2195 24e Feedwater Freheat typass 5
Note 1, M M Lina S.G. #3 3
1HV-2187 24d Feedwater 4eo4estee.
3 Note 1. 421 Bypass Line S.G. f3 3
(
1HV-2137, 25 Feedvster 4sotseeseb 5
Note 1. M b Steam Generator #4 3
IFV-2196 26/C, Feedwater Freheat Bypass 5
i Note -1. 4 2N Line S.G. f4 3
3 INV-2188 26(L Feedwater -Esetsetoe-5 Note - 1. 12 0
/
Sypass Lina S.G. #4 9.
Safety Injectica Actuation Isolation 1-8105 44 Charsias Line to 10 C
Regenerative Heat Exchanger 3.1-17 Rev. 0
1
. Attacttnent 2 TXX-89095 DRArt Page 15'of 24 TECINICAL REQUIRDENT 3.1 TABLE 3.1.1 (Continued)
' ).__
n CONTAIl0ENT ISOLATION VALVks (~w ii h
~
N
& / darfs M b \\
301ATIO 4TPf-j FSAR TABLE tdt 3 EAK T K VAL 7E NO.
REFERENCE NO.*
LINEORSERVJI (Seconds)- REQUIRDENTS 10.
Relief Velves f
,~
7(
1-87088 33 RER From Not leg Loop f4 N.A.
. G. " IN 1-8708A 34 RER From Hot Leg Loop #1 N.A.
/ 5:n i Al/A 1MS-021 Sb Main Steen Safety Valve N.A./
3 Note !. it h S.G. ft 3
1MS-022 Sb Main Steam Safety Valve N.A.
Note 1. ;;;,
S.G. f1'
/
/
3 1MS-023 Sb Maia Steam Safety Valve N. A.!
Note-1, M w S.G. #1
\\
1MS-424 Sb Main Steam Safety Yalve N.A.
Note, 4;h S.G. #1 3
1MS-025 Sb Maia Staan Safety Valve N.A.(N" Note 1,-li h S.G. #1 N.A.,! Note 1, fr:7.6 3
1MS-058 9b Main Steam Safety Valve S.G. #2 3
1MS-059 9b Main Steam Safety Valve N.A. i Note i, 12 %
S.G. #2 3
1MS-060 9b Main Steam Safety Valve N.A./
Note i, -;;h S.G. #2 4
1MS-061 9b Maia Steam Safety Valve N.A.
Note., it W x 8.G. #2 1
9b Main Steam Safety Velve N.A.
/ Note T, M to S.G. #2 3
1MS-093 13b Maia steam Safety Valve N.A.
Wats I, 00 6 s
S.C. f3 3
IMS-094 13b Main Steam Safety Valve N.A.
Note 1. W
]
7 S.G. f3 3
1MS-095 13b Main Steam Safety Valve N.A.
No te -1,
' ; ? ^
S.G. f3 3.1-18 Rev. 0
Attachment _ 2
'TXX-89095 Page 16.of 24' DRAFT TECWICAL REQUIREMENT 3.1 TA8LE 3.1.1 (Continued) >,
a w\\
CONTAINMENT ISOI.ATION VALVES A T' vf f
i J
i MAXIMUM ' doris */6 SOLATIONI N FSAR TABLE TIME DEAK.,
VALVE NO.
REFERENCE NO.*
LINE OR SERVICE ISeconde) REQUIREMENTS 10.
Relief Valves (Continued) g,7
/
3 1MS-096 13b Maia Steam Safety Valve N.A. [
Nota 1,10^;
5.G. #3
\\
m 3
1MS-097 13b Main Steam Safety Valve N.A.,' Wete -1,
!!;.',0 i S.G. f3 I
s N
3 1MS-129 ISb Main Steam Safety Yalve N.A.
Notei,l,1%j S.G. f4 3
1MS-130 18b Maia steam Safety Yalve-N.A.
Note i, 4;L 5.G. f4 3
1MS-131 18b Maia Steam Safety Yalve N.A.
Note i, i-;20 S.G. 94 s
3 1MS-132 ISb Main Steam Safety falve N.A.
" Note 1. 4:20 5.G. 94 3
1MS-133 18b Jind Steam Safety Yalve N.A.
Note 1, 4424
)
s im s.G. 94 f
_Mk4m %d hlr i.
'/
i s
v 1RC-036 41o b [\\.3tandpipe RE W To FRT & NCF N.A.
C
,w:w: : :: wa 1WF-7176
- 52a, 5.A.
C 6
h a.l d e d' ermal kg:l;:d IDD-430 60s.
- -._ _ _ ":::: _ ;1 -
N.A.
C 7
3e:sbdwMesi llkb IVD-907 416.,
"'::h;e N.A.
C i
b r:M isa N r M kh 1F5-193 80 s,
- =
s....
N.A.
C 1CC-1067 lie o.,
Nd-N.A.
C
,,..w___
Lh Nb 1CH-271 1209
-.11;' Je; e
--rr-i..
N.A.
C h
- h...b.-.M..N...L.e%.be ht'.
N.A.
C 1CH-272 121a.,
rr 7 C:rtri-- :: C::1000-3.1-19 Rev. O
1 1 ;'
- TXX-89095 I
Page 17.of 24 10 Q.r\\ieb Y \\Vts
- x 173-114 74A hehrkio%%eulQff M4 6
1.Ps-19 5 1h hkh.
hi 4.I;d a.A e
1.P 3 - 1%
hbh. hl %;J s.4 e
itoP-1l~ll
%)s
'Pevebli.~ Ymd S!ieb d.4.
C i SI - til2.
%3% O li.~ T k n u.! S h N 4.A.
L 1
l O
e 3.1 - li c
. Attachment 2 TXX-89095 Page 18 of 24 '
DM TABLE 3.1.1 (Continued)
[
TABLE NOTATIONS l
- Identific ton code for containment penetration and associated isolation valves in AR Tables 6.2.4-1, 6.2.4-3, and 6.2.4-3.
Note 1:
Thes are closed systems which meet the requirements of NURE q 800 Section 6.2.4 II.6 paragraph o.
These valves are therefo e not required to be leak tested.
Note 2:
These vai e inside containment are part of closed systems outside con siament which are in service post accident at a pressure in cess of containment design pressure and satisfy single failur criterios. These valves are therefore not required to be oak tested.
Note 3:
These are closed stems outside containment which are in service post accident and e a water filled loop seal on the containment side of he valves for a period greater than 30 days following the acciden These valves are therefore leak rate tested with water of a ressure of,F,.
Note 4:
These ESF valves are no ly open and renais open dettag post-accident conditions.
est-accident they are contimaally pressurized in escess of con ainoast pressure from sa ESF source which meets the stagle fails criteries. These valves are therefore not required to be 1 tasted.
Note 5:
An effective fluid seal on these trations is provided by the suction sources to the residual b removal pumps during and following as accident.
In addition, these containment isolation valves are non-automatic, r.re not r post-accident sad are located inside. red to operate tainment. These valves are therefore not required to be tested.
Note 6:
All four MSN bypass valves are locked e in Mode 1.
During Mode 2, 3 sad 4 saa MBU bypass valve may opened provided the other three NN bypass valves are locked ci sad their assoaisted WNe are closed.
Note 7:
Thesenare parallai ESF valves that are normally osed, but are deet p ed to spas darias post-accident conditions. Failure of one veBee to spes will not prevent system pressurisati es both pidae of both valves in encase of contafen,at pres These valves are therefore not required to be leak tested.
Note 8:
These valves located outside containment are aermally el and see a pressure ta encess of containment pressure is post-cident conditions. A valve stem leakage check will be performed a
quarterly basis to ensure no significant stem laakage would cur in post-accident conditions.
Note 9:
These valves require steam to be casted and are thus not require to be tested until the plant is in MODE 3.
\\
3.1-20 Eev. 0
- Attachment 2 TXX-89095 DRAFT Page 19 of 24 TABLE 3.1.1 (Continued)
TABLE N0fATIONS Note 10: Thas valves will have water against them during post-accident condit to preclude any release of containment atmosphere to the envi at.
e normally l'ocked closed and are opes only to warm Note 11: These valves up the steam ou ly lines prior to normal surveillance testing.
Note 12: These valves are uded for table completeness, the requirements of Speci cation 3.6.3 de not apply. Instead, the requirements of Specifi tion 3.7.1.1, 3.7.1.5 and 3.7.1.6 apply for main steam safety val
, estastaan isolation valves, and feedwater isolation valves, spectively.
}
BASES s
3.1 CwsAIiinine a I!" ' TION FALYE5 The OPEIABILITT of the containment isolation val ensures that the containment atmosphere will be' isolated from the sa ido environment la the event of a release of radioactive asterial to the ces e atmosphere or-pressurization of the contat====t and is consistemt vi requiremmets of General Design Criteria 54 thressh 57 of 10CFR50, A.
Contaiansat teolaties within the ties limite specified for t se isolation valves designed to close automatically ensarea that the re of radioactive material to the environment will be consistems with assumptions used in the analysee.for a LOCA.
l 3.1-21 Rev. O J
1 6 % 69.,7
.iXX-84095
~
Page 20 of 24 TABLE 3.1.1 (Continu:d)
,y TABLE NOTATIONS
/
/-
(
- Identification code for containment penetration and associated
,/ isolation valves in FSAR Tables 6.2.4-1, 6.2.4-2, and 6.2.4-3.
/
hte 1:
These valves are part of closed systems which meet the l
requirements of NUREG-0800 Section 6.2.4, II.6 paragraph
~
These valves are therefore not required to be leak o.
j' tested by Appendix J,Section II. H.
l, Note 2:
These valves inside containment are in service (or
'/
ressurized) post accident at a pressure in excess of tainment design pressure and satisfy single active c
s fai re criterion. These valves are therefore not requir to be leak tested, Appendix J,Section II. H.
Note 3:
These are sed systems outside containment which are in i
service post cident and have a water filled loop seal on I
the containment ide of the valves for a period greater N.s than 30 days foll ing the accident.
These valves are therefore leak rate sted with water at a pressure of 1.1' l
P as lowed in Appe ix J.
{
Note 4:
These valves are normally o n and remain open during post-accident conditions.
Po -accident they are h
continually pressurized in exce of containment pressure Wd
/
from an ESF source which meets the ingle active failure
,/
criteria.
These valves are therefor not to be tested by
,/
Appendix J. Section !!. H.
,I x
iI Note 5:
An effective fluid seal on these penetratio is provided by the suction sources to the residual heat r val pumps
./
during and following an accident.
In addition, ese j
j containment isolation valves are non-automatic, a not
,1 required to operate post-accident and are located in e
containment. These valves are therefore not required t ~j{
be testedy by Appendix J.Section II. H.
/
\\
. Xy
'g
\\
f
\\
- a. M. d s k G v e.
cern ho l
/ w~
\\
\\,~
N
\\
e A'
- - - - - - - ~
~~
~
1
, Attachment 2 TXX-89095 2 %MT b'O Page 21.of 2R TABLE-3.1.1 (Continued)
('
p
,3 N
TABl.E NOTATIONS
\\
te 6:
These ESF valves are nomally closed, but are designed to P
(
open during post-accident conditions.
These valves are part of closed systems outside containment which are in sN service post accident.
They are initially closed with N upstream pressure in excess of containment design pressure 9 pplied to the valve which satisfies single active failure c 'teria.
During Hot Leg Recirculation these valves are
(
ope ontinually pressurized by an ESF source which meets N
single ilure criteria.
(RHR pumps are cross-connected
/,
to the S ump suction to meet single failure criteria)
In the event he valve is not opened post-accident, leakage of con neent atmosphere is prevented by pump pressure on the s tem side and a water seal on the containment side of e valve. The combination of the
\\
valve disc seal and th ouble stem seals preclude the possibility of significan tem leakage under the low s o
/
containment pressure condit s seen in the postulated
/
/
post-accident condition.
In 1 of type "C" testing,
/
i stem leakage measurements wi11 be ducted quarterly to S
verify the integrity of the stem sea ressure boundary.
Miote 7:
These are butarede!arallelESFvalvesthatareno 11y closed, I
igned to open during post-acciden onditions.
Failure of one valve to open will not prevent s tes
,N' pressurization on both sides of both valves in ex s of containment pressure. These valves are therefore no
~r (
required to be leak tested, by Appendix J.Section II.
l v
/ 5t: Si~~ /ITabledoesnotlistlocalvent,drainand-testconnections M
/
" W**4 q as they are a special class of contginnent isolationvalves and a
%d to 3
/
itomeetcontainmentisolationcriter{awhenlocatedwithin)
[
the penetration boundary.
mj ei:
These valves inside containment are initially out of
- 4N service with SI system pressure in excess of containment
/
esign pressure which satisfies single active failure cr e applied against a upstream outside containment s
isolati ve. Subsequently during Hot Leg
\\
Recirculation valves are placed in service (or pressurized) at a pre in excess of containment design - s pressure form an ESF source h meets single active failure criteria.
(RHR pumps are s-connected to the j
SI pumps suctions to meet single failur teria)
These valves are s m yVore not required to be teste.
\\
v
TXX-89095 Page 22.of. 24' TABLE'3.1.1 (Continued)
TABLENbTATIONS
\\
['
ote'10:
These ESF valves are normally open and remain open during.
initial post-accident conditions (valves close at initiation of Hot Leg Recirculation). Post accident they n
are open in operation in excess of containment design l
pressure from an ESF source providing an ESF function and i
i are part of closed systems outside containment, active or closed and continually pressurized in excess of containment design pressure from an ESF source which meets
/
tile single active failure criteria. When the valve is c1 ed post-accident, leakage of containment atmosphere is
./
pre nted by pump pressure on the system side and a water seal the containment pressure conditions seen in the postula d post-accident condition.
In lieu of Type "C" testing ' Stem leakage measurements will be conducted quarterly y verify the integrity of the stem seal
~l pressure bo dary. These valves are therefore not required to b tested.
\\
Note 11:
These valves inshje containment are initially in service s
(or pressurized) p'ast-accident at a pressure in excess of
\\
containment design p(essure from an ESF source providing 1
an ESF function and ahe part of closed systems outside containment.
These vahes are subsequently taken out of service (during Hot Leg circulation) with RHR System l
Pressure in excess of cont the closed upstream outside(inment design pressure against
' containment Isolation Valve.
The pressure source meets sin ]e active failure criteria.
Thesevalvesarethereforeno)tpuiredtobetested.
N Note 12:
This ESF valve is normally open an'd remains open during i
s initial post-accident conditions pressurized in excess of containment design pressure from an E5f source which meets the single active failure criteria proMding an ESF function.
This valve is closed during HK Leg Recirculation with the SI cross connect va ves (8821A.8) closed and are part of closed systems outsi containment.
When the valve is closed, the combination of e valve disc seal and the double stem seals preclude t i
possibility of significant stem leakage under th low containment pressure conditions seen in the postu ted post-accident condition.
In lieu of Type "C" testi stem. leakage measurements will be conducted quarterl to
- y verify the integrity of the stem seal pressure boundar 1,
This valve is therefore not required to be tested.
l J'
)\\
4
T 99
'M Y
E)
Page 23 of 24 '
TABLE 3.1.1 (Continued) y i
TABLE NOTATii)NS f- ~
ote 13:
These valves inside containment are initially in service (or pressurized) post-accident at a pressure in excess of containment design pressure and satisfies single active failure criteria. These valves are subsequently taken out
\\
of service (not pressurized) upon initiation of Hot Leg
\\ containment. Recirculation mode and are part of closed systems outside These valves are therefore not required to s
{
tested.
Note 14:
Thi SF valve is normally closed, but is designed to open durin p,ost-accident conditions. The valve is initially closed with upstream pressure in excess of containment design pressure applied to the valve which satisfies single activa failure criteria. During Cold Leg I
Recirculation'the valve remains closed with the RHR cross
\\
connect valves (8716A,B) closed and is part of closed
\\
systems outside containment.
During Hot Leg Recirculation this valve is opened and remains open continually pressurized in excess'of containment design pressure from
/
an ESF source which meets the single failure criteria.
In t
the event the valve is nots pened post-accident, the o
combination of the valve disc seal and the double sten seals preclude the possibilif of significant stem leakage k
under the low containment pres re conditions seen in the postulated post-accident conditi In lieu of the Type i
"C" testing, stem leakage measur s will be conducted quarterly to verify the integrity ofNthe stem seal pressure boundary. Thesevalvesaret%eforerot required to be tested.
s Note 15:
These valves inside containment are initial out of service and are part of closed systems outsid containment. Subsequently during Hot Leg Recir glation these valves are placed in service (or pressurized) at a pressure in excess of containment design pressure an
/
l ESF source which satisfies single active failure crit ia.
/
x These valves therefore are not required to be tested.
\\\\
/'
i v'
]
l 9
_m______-------.--
q f.
9 T NMT M
Page.24*of'24'
' TABLE 3 d.1 (Continued) N TABLE NOTATIONS
[
e 16:
At initiation of injection these valves are closed with m
water from the refueling water storage tank providing roximately 50 ft. of head on these valves. During J
Rect tion phases the valves are opened suppling water
)
to ESF pu or 30 days. Water in the suction sump J
provides a seal en the containment atmosphere and
(
these valves.
These v uts are therefore not required to be tested.
Note 17:
These valves are nomally locked clos are open only
\\t to wam up the steam supply lines prior to no f
llanc Q ing.
su
/
Note 18:
All four MSIV bypass valves are locked closed in Mode 1.
During Mode 2, 3, and 4 one MSIV bypass valve may be y
l opened provided the other three MSIV bypass valves are
/
locked closed and their associated MSIVs are closed.
1
/
Note M: \\
These valves require steam to be tested and are thus not required to be tested until the plant is in M00E 3.
3.j x Note 26: /
These valves are included for table completeness, the requirements of Specification 3.6.3 do not apply.
Instead, the requirements of Specification 3.7.1.1, 3.7.1.5 and 3.7.1.6 apply for main steam safety valves, mainsteam isolation valves, and feedwater isolation valves, respectively.
BASES a
3.1 CONTAl a nI ISOLATION VALVE 5 The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with 1
the requirements of General Design Criteria 54 through 57 of 10CFR50, Appendix A.
Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
Attphaent 3 TM-89095 Page 1 of 6' PhNTSYSTEMS 3/4.7 UBBERS LIMITING CON FOR OPERATION
The only snu requirements are those inst if their failure of failure ofed on nonsafety-r excluded from the system ed systems and then only have no adverse effect on any safe ich they are installed would ed system.
APPLICABILITY: MODES 1, 2, 3, 4.
systems required OPERA 8LE hose MODES.
5 and 6 for snubbers located on ACTION:
With one or snubbers inoperable on any systes, within 7 store the operable snubber (s) to OPERABLE status and perform anrs replace or re-uatio er Specification 4.7.9g. on the attached component or declare t neering eval-em inoperable and follow the appropriate ACTION statement for ttached
'C'"! :LL""CC "50S!"~ %5 Tf5rs/nl5 pts.rm/s 4/,l -ti.r Each snubber shall be demonstrated OPERA 8LE b following augmented inservice inspection program in :ffitir t the y performance of the ments of 5 specification 4.0.5.
require-j Usa, *E-gd (
s.-
Inspection Types
~~
~ E..
of the same design and manufacturer, irrespe
{ '3 b.
Visual Inspections Snubbers are categorized as inaccessible or accessible durin operation. N ach of these groups (inaccessible and accessib1 ) ma reactor be inspected independently according to the schedule below.
first inservice visual inspection of'each type of snubber shall be The performed after 4 months but within 10 months of commencing POWER OPERATION and shall include alpsnubbers.
c4 q Sf8
~
If all snubbers of each the second inservice visual inspection shall be pe first refueling outage.'
p gM shall be performed in accordance with the follcwing schedule:Oth No. of Inoperable Snubbers of Each Type subsequent Visual per Inspection Period O
Insoection Period * **
1 18 months 2 253 On W O k 12 months 2 25%
2 6 months 2 25%
3,4 5,6,7 124 days t 25%
8 or more 62 days : 25%
31 days
- 25%
- The inspection interval for each type of snubber shall not be lengthene more than one step at a time unless a generic probles has been identified and corrected; in that event the inspection interval say be lengthened one step the first time and two steps th reafter if no inoperable snubbers of that type are foung 04, AAY JV
- The provisions of Specification 4.0.2 are not applicable.
0%'C;;7;As U"!T 1 3f.; 7 4u O
.* Altadhinent 3 TXX-89095-.
Page 2 of 6 RW
'"l".~3^A py$fAfsPECTJ04S
-;"'"!:".L" "00'!M""5 (Continued) y_isual Inspection Acceptance Criteria c.
Secur e Visual inspections shall verify that:
(1) there re no visible indications of damage or impaired OPERABILITY the foundation or supporting structure are '.a,;;u)r.;ttachments to 2 a ers fee attachment of the snubber to the component and to the snubber; secure. _
anchorage are '.;.;.;;i c.;i.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERA 8LE for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snu b O f" tive of type that may be generically susceptible; end', ) the affected spec-OPERABLE per 4;. f %;;f-- ' ' ^" snubber is functionally tested in the as-fo inoperablecommonhydraulicjfluidreservoirshallbecountedasAll snu inoperable snubbers.
C,gg 7
d.
Transient Event Inspection An inspection shall be performed of all snubbers attached to sections transients as determined from a review of operationa visua~1 itSpection of the systems'within 6 months following such an In addition to satisfying the visual inspection acceptance event.
criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following:
(1) aanually induced snubber movement; or (2) evaluation of in place snubber piston e.
Functional Tests t
DuringthefirstrefuelingshutNwnandatleastonceper18 months thereafter during shutdown, a representative sample of snubbers of The sample plan for each type shall be selected prior to period and cannot be changed during the test period. The NRC Regional Administrator shall be notified in writing of the sample plan selected for each snubber type prior to the test period or the sample plan used in the prior test period shall be implemented:
1)
At least 10E of the total of each type of snubber shall be functionally tested either in place or in a bench test.
For each snubber of a type that does not meet the functional test acceptance criteria of ;;;L.. n of that type of snubber shall be f
'.7.',7.", an additional 10%
more failures are found or until ionally tested until no been functionally tested; or 1 snubbers of that type have 7eshLspeck M.lf 1
0 w if T W rV
e TXX-89095.
Page 3 of 6 g
ggS
(~}
-,,,,,,,,. e em --'^~-'-( Con t i nued) functional Tests (Continued) 7'esdM 4.
e.
2)
A representative sample of ea :h type of snubber shall be func-tionally tested in accordance total number of snubbers of withFigure4.lbl.
"C" is the ance requirements of '---!'fe tf r '
?."". type found not meeting the accept-4
}
The cumulative number of snubbers of a type tested is oenoted by "N".
and of each day's testing At the i
vious day's total plus cur, rent day's increments) shall bethe n
."N" and "C" (pre-plottedonFigure4fpl.
If at any time the point plotted falls in the Reject be functionally tested. region, all snubbers of that type shall If at any time the point plotted falls in the " Accept" region, testing of snubbers of that type say be terminated.
When the point plotted lies 1.n the " Continue Testing" region, additional snubbers of that type shall be tested until the point falls in the " Accept" region or the
" Reject" region, or all the snubbers of that type have been tested; or 3)
An initial representative sample of 55 snubbers shall be func-tionally tested. For each snubber t
~
functional test acceptance criteria,ype which does,not meet the another sample of at least-one-half the size of the initid1 sample shall be tested until-
~~
the total number tested is equal to the initial sample size c
I multiplied by the factor,1 + C/2, where "C" is the nimber of snubbers found which do not meet the functional test acceptance criteria.
The results from this sample plan shall be plotted using an " Accept" line which follows the equation N = 55(1
+ C/2).
Each snubber point should be plotted as soon as the snubber is tested.
If the point plotted falls on or below the
" Accept" line, testing of tpet type of snubber may be terminated.
If the point plotted falls'above the " Accept" line, testing must continue until the point falls in the " Accept" region or all the snubbers of that type have been tested.
Testing equipment failure during functional testing may invalidate that day's testing and allow that day's testing to resume anew at a the day of equipment failure are rotested.later time provided a The representative sample free the snubbers of each type and reviewed before The review shall ensure, as far as practicable, that they are represen g.
tative of the various configurations, operating environments, range of size, and capacity of snubbers of each type.
Snubbers placed in the same location as snubbers which failed the previous functional test shall be retested at the time of the next functional test but shall not be included in the sample plan.
additional sampling is revufred due to failure of only one type ofI snubber, the functional test results shall be reviewed at that time to determine if additional samples should be limited to the type of snutbar which has failed the functional testing.
/4 F2e ^
/1t$chf,7ent 3 gxx-89095 Page 4 of 6 ML'"T CY T:Z 5573/EAlSPECT/MlS h
O'.T! R_' t"% Z^"P SPL (Continued) f.
Functional Test Acceptance Criteria The snubber functional test shall verify that:
1)
Activation (restraining action) is achieved within the specified range'in both tension and compression; 2) both tension and compression, within the s 3)
For mechanical snubbers, the force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and 4)
For snubbers specifically required not to displace under without displacement. continuous load, the ability of the snubbe Testing methods may be used to measure parameters indirectly parameters other than those specified if those results can be correlated to the specified parameters through established methods, Functional Test Failure Analysis g.
An engineering evaluation shall be;made of each failure to meet th (i
functional test acceptance criterra to determine the cause of the failure.
in selecting snubbers to be tested in an effort to de OPERABILITY of other snubbers irrespective of type which may b subject to the same failure mode.
For the snubbers found inoperable, an engineering evaluation shall be performed on the components,to which the inoperable snubbers a attached.
The pur$ose of this engineering evaluation shall be to deteristne if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting designed service.
lock up er fatis to move, i.e.If any snubber selected for function evaluated and, if caused by man,ufacturer or design deficien snubbers of the same type subject to the same defect shall be func-tiens11y tested.
This testin the requirements stated in ';g requirement shall be independent of
- '**~t'
?.7.t? for snubbers not meeting the functional tes acceptance criteria.
Tesf/Inspu% Oe.
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TXX-8909S Page 5 of 6 m's 5'!*!!!L%G CW:CCF1'(Continued) h.,
Functional Testino of Repaired and Replaced Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced.
snubbers and snubbers which have repairs which might affect the Replacement functional test results shall be tested to meet the functi criteria before installation in the unit.
service, and the freedom-of-motion test must ha within 12 months before being installed in the unit.
i.
Snubber Service Life Program The service life of hydraulic and mechanical snubbers shall be monitored to ensure that the service life is not exceeded b surveillance inspections.
various seals, springs, and other critical parts shall be dete mined and established based on engineering im*ormation and shall b extended or shortened based on monitored test results and f history.
Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the..snubbes
"~
is required to be OPERA 8LE.
The parts replacements shall brdocu-Tex.kw'%\\-~mented and the documentation shall be retained in accorda 5 specification 6.10.3.
(
ce = = P:?? - tw:T :
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h TXX-89095 e 6 of,6 10, 9
8-7 REJECT 6
V p-
..... C 5
y
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CONTINUE
/
[
TESTING r'
3
/
2 t
ACCEPT 1
r 0
10 20 30 40 50 60
~70 80 90 100 N
l l
1 FIGURE 4.X-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST l
COMANCHE PEAK - UNIT 1 3/4 7-25
[
Mtachment e
~~
DRAFT IXX'89095 TEC10ffCAL 'REQUIRDENT 4.3 Page 1 of 1 iASa g
/*.3 STATION SERVICE WATER SYSTEM The inclusion of this requirsaient for Unit 2 Statios Service Water Pump availability while Unit 1 is operating in MODES 1 through 4. the attendant Test / Inspections Jo-demonettste availability, and the compensatory esasures to be taksir ia che event s' Unit 2 Service Water.Pysy is nos availablef provide the necessary level of administrative controla to assure acceptable
'results from the Probabilistic Risk Assessasat (FRA) for loss of Unit 1 Station Service Water.
Ths
%Jrs a,re, 4 add,$me, fo k tape
[
in % 7%utel spes;f.anks.t 7^
Coe 4,'V1.9M.m Suvos ul enstao's
(
The Test / Inspection requirements for the Unit 2 Station Service Water pump
/
availability are adequate to ensure that power is available to the pump and g the pump is capable of pumping upos,densed. The cross-commect discharge path valves are tested at least osca per 18 aosah's by-stroking these valves through their' fall range of motion. These cross-coasset valves are also verifisd to be capable of being opened or already opes by as administrative check by e==f aias logo or other inforestion to determine if these valves are out-of-service 'for asiatenance er, other reasess.
}
-7 w
o.
4.3-2 Rev. o p
T(X-80$5 1
Page 1 of 4 DEAFT T3tl3NICAL m etREMENT 5.1 TABLE 5.1.1 CONTADRIDT PENETRATION CONDUCTot vvsam.vaRST FRCFTECTtys DEVICE 5 DEVICE NUMBER AND !.0 CATION SYSTDt POWERED 1.
6.9 KVAC from Switchgears a.
Switchgear tua LA1 BCP fil 1)
Primary treaker 1PCPIl a)
Raiay 5211-51 b)
Raiay 26 1
k N 2.
2) laskapTrNs 1Al-1 or 1Al-2 a)
Raiay 31Mi3 b) 3alay 51 for 1Al-1 c)
Valay 51 for 1Al-2 d)
Relay 86/1A1 b.
Switchgear Sua IA2 BCP #12 1)
Primary Breaker IPCPI2 a)
Raisy SSE1-51 b)
Eslay 26 f
S.
2)
Relay 5131/3 l
b)
Balay 31 for LA2-1 e) talay 31 for 1A2-2 4)
Batay 44/1A2 c.
Sudeshoner See 1A3 BCP #13 1)
Petaary Breaker IPCPI3 RelaySh-51 lJN a) b)
salar to c) salay 88It d) 'Eg si mg
"") Ah.so 4 5.1-4 Rev. O i
5 i Attachmpt 1
I Td-89095 i
Page 2 of 4 DRAFT TECWICAL REQUIRDENT 5.1 TABLE 5.1.1 (Continued)
CONTAIIDENT PENETRATION CONDUC*08
{
vvuan,vmRENT PRutsG IVE Dav&CE5 DEVICE NUMBER AND I,0 CATION SYSTBt POWERED 1.
6.9 KTAC from Switchgears (Continued) i 2)
Baekap Breakers 1A3-1 or LA3-2 a)
Raiay 51k3 b)
Islay 51 for 1A3-1 c)
Reiay 51 for 1A3-2 d)
Relay 84/1A3 d.
Switchgear Sua 1A4 BCP #14 1)
Primary Breaker 1FCFI4 a)
Islay Sell-51 b)
Relay 26 e
talay set d
d i
i ut.
2) r 1A4-1 or 144-2 a)
Islay 5 $
l b)
Raisy 51 for 144-1 c)
Relay 51 for 144-2 d)
Relay 84/1A4 2.
440 VAC fram Switahsmars 2.1 Devisa Lasatian -
a== =4 - t 440F Switchenare 1551, 1852, teatre. Fama 1ES3 and 1E54 and CRIN Test Fana 4.
Primasy Besakers - 1 FEAT 1, IFE&TI, 15M&T3. 1FEAY4, 173C51 and 1FRC32
.b.
Bashup Breabers - 1E51-1, 1853-1,1553-1 M,1E54-1, &T'-1E613 hd ST"-If 8 24 fMIW 3
1)
Lang Time & Iassantaneous Relays
- hg h
1E51-1 3 (183 >1) h4 (1m-1) hg
[h(1EB4-1) 2)
7-g-
5.1-5 Rev. O I
...-v
m Attachmp t 5 Tn-89095
' Page 3 of 4 DBAFT TECWICAL REQUIREMENT 5.1 TABLE 5.1.1 (Continued)
CONTAIIM DT F WITRATICE CONDOCTOR uvaan.vakENT FRusan,atrs OsvtCE5 DEVICE NUMBER mfd I,0 CATION SYSTEN g
2.
440 VAC from Switchgears (Costiaued)
[Y[
~
)
Time Delay Balays 02-lu2-1x < int-t> j]56724" 2-18 (1I52-1)b
.,FE471 62+1642-13 (ggg,gy $2=' 462-13 gggpg)
LFNAT3 1aLY4 02-tu 2-13 (inkt) 42-1662-1x (134-1)
- sm.at lasi.s2 2.2 Device Locaties - 4407 Centatassat Switahgear 1E34 Polar Crane a.
Primary Breaker - 18CCF1 b.
Baeksp Breaker 1554-1 %d 6T-/E 824
) grej TdErr 2) v.
3.
440 TAC f rol Centers 3.1 Devise Leastama
- HC/C 1EB1-2 Contatsmaat Numbers listed below.
Putmery and Beahnp
- Beek primary and beskap breakers asashers have identical trip rattaes and are in the sene ICC Ceapt. These breakers are General Elastria type TEED er TEFE with thermal-eagnetic trip elemmats.
- Assectated circuit breaker shown is parentheses e.g., 1E53-1. La backed to 1FFAT3 and 1FWC51.
5.1-6 ter. O
.fXf8.%95 i
--Page 4 v i 4,
Pay.
s.1-Li l
2, 4 80 MA C. [cw S~9ckyo TS [ Conn nue5)
- 2) ~Tiou.
Dc.]o.7 Tk\\'yS llk b 2' I (IEb\\-l EZ"I5 (jpMAVI)
IPNAVI M
1pMAvl ggg BT-teSIS) m M
62-l (IEEL-l 62-Ix EEi' IPNAVL w
IFNAVE (lFN4Vt)
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Sv-re Bzy')
62.-l - (/581-l 62-l)(
JpgAyi IlFNAV3)
I IFNAV5 Ardt ST-163G)
OEMAVN
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t AV4 qq STlESI4) b (IEM-l G_2-IX
( fpgegi)
IFNCBI M
IFNCB)
BT-lE BI5h b (lE B4-l 6_2-!.6 gjpg egg} '
)FWCB2, gp-jf52d I
1804 z,z. w i ee.LouA, m i
.s s M e o e I f t '
3 o ?cimary Breaker - 15 CCPl l
b, b ckup B<ed.ec IEBH-l acd BT-)EB2A 0 Lons T; m &
a
/
J M)
IstcP
- 2. Ti% be.
Mc-W-
!L -- (153+l
.sSL (lsccp)')
15CCP) g,jggq) 15CCP)
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