ML20062G815: Difference between revisions
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| number = ML20062G815 | | number = ML20062G815 | ||
| issue date = 08/06/1982 | | issue date = 08/06/1982 | ||
| title = to Inservice Testing Program for Pumps & Valves | | title = to Inservice Testing Program for Pumps & Valves | ||
| author name = | | author name = | ||
| author affiliation = ALABAMA POWER CO. | | author affiliation = ALABAMA POWER CO. | ||
Latest revision as of 19:47, 6 January 2021
| ML20062G815 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/06/1982 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML20062G810 | List: |
| References | |
| PROC-820806, NUDOCS 8208130180 | |
| Download: ML20062G815 (46) | |
Text
_ - - _ _
- b. , s u.
SUMMARY
OF REVISION 2 TO THE J. M. FARLEY NUCLEAR PLANT UNIT 2 PUMP AND VALVE INSERVICE TESTING PROGRAM DESCRIPTION / REASON FOR CHANGE Pages 3-2, 3-3, 3-16, 3-23, 3-28, 3-29, 3-42, 3-44, 3-60, 3-67, 3-71, 3-73, 3-77:
Test alternate was changed from "RR" (test each reactor refueling outage) to "NT" (no testing required) in order to clarify the intent of Relief Request 3.1.3 for the following valves: Q2B13V038,Q2B13V054, Q2E14V001, Q2E21V058, Q2E21V115A-C, Q2E21V119, Q2E21V213, Q2G21V204, Q2G21V291, Q2G31V013, Q2P11V002, Q2P16V075, Q2P17V083, Q2P17V159, and Q2P19V002.
Pages 3-16 and 3-17: The normal position for valves Q2E14V003 and Q2E14V004 were charged from "C" (closed) to "0" (open). This corrects a previous clerical error.
Pages 3-21, 3-23, 3-31, 3-51: Relief Requests 3.1.32 and 3.1.33 were added to valves Q2E21V015, Q2E21V056A&B, Q2E21V254, Q2E21V257, Q2E21V258 and Q2N21V001A-C. These Relief Requests were inadvertently omitted on a previous revision for these valves.
Pages 3-21 and 3-103: Relief Requests 3.1.49, 3.1.32, and 3.1.33 were added to Table V-1 for valves Q2E21V016A&B. Relief Request 3.1.49 explains why these valves should not be tested during normal plant operation.
Page 3-27: The " Function" for valve Q2E21V077C was revised to refer to " Loop 3" instead of " Loops 1&2". This corrects a previous clerical error.
Pages 3-30, 3-33, and 3-103: Relief Requests 3.1.50, 3.1.32, and 3.1.33 were l
' added to Table V-1 for valves Q2E21V253 A, B, and C. Relief Request 3.1.50 explains why these valves should not be tested during r;ormal plant operation.
Pages 3-32, 3 - 33, 3-102: Relief Requests 3.1.47, 3.1.32, and 3.1.33 were added to Table V-1 for valves Q2E21V259A-C and Q2E21V265. Relief Request 3.1.47 explains why _ these valves should not be tested during normal plant operation.
Pages 3-33, 3-34, and 3 103: Relief Requests 3.1.48, 3.1.32, and 3.1.33 were added to Table V-1 for valves Q2E21V326A&B and Q2E21V327A&B. Relief Request 3.1.48 explains why these valves should not be tested during normal plant operation.
I
~" Page 1 of 3
( C208130100 820006 i PDR ADOCK 05000364
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Pages 3-34 and 3-104: Relief Requests 3.1.51, 3.1.32 and 3.1.33 were added
- to Table V-1 for valves Q2E21V336A and B. Relief Request 3.1.51 i explains why these valves should not be tested during normal plant operation.
Page 3-45: The "P&lD/ Sheet Number" was changed from "D-205003/1" to "D-205033/1" for valve Q2N11V001C. This corrects a previous clerical error.
Pages 3-52 and 3-53: The " Valve Numbers" were changed from "FCV2919A,B,8C" to "FCV479,489,& 499". This corrects a previous clerical error.
Pages 3-65, 3-66, 3-68, 3-104: Relief Requests 3.1.52, 3-32, and 3-33 were added to Tabic V-1 for valves Q2P16V010A-D, Q2P16V043A-0, and Q2Pt6V207A-D.
Relief Request 3.1.52 explains why these valves should not be tested during normal plant operation.
Pages 3-68, 3-69, and 3-104: Relief Requests 3.1.53, 3.1.32. and 3.1.33 were added to Table V-1 for valves Q2P16V514, V515, V516 and V517. Relief Request 3.1.53 explains why these valves should not be tested normal plant operation.
Page 3-70: The " Actuator Type" was changed from "A0" (air operated) to "M0" (motor operated) for valves Q2P16V545 and V546. This corrects a previous clerical error.
Page 3-73, 3-74, 3-75, 3-104, and 3-105: Relief Requests 3.1.54, 3.1.32 and 3.1.33 were added to Table V-1 for valves Q2P17HV3067. HV3095 and HV3443.
Relief Request 3.1.54 explains why these valves should not be tested during normal plant operation.
Page 3-88: This change elaborates on Relief Request 3.1.6 and emphasizes the possible consequences of testing these valves, Page 3-93: References to " upstream" were changed to " downstream" on Relief Request j
3.1.17. This corrected a previous error. Relief Request 3.1.18 was l
' elaborated on to emphasize the possible consequences of testing these valves during normal plant operation.
Page 3-94: Relief Requests 3.1.20 and 3.1.21 were elaborated on to emphasize the possible consequences of testing these valves during normal plant operation.
Page 3-97: The sentence "This action would put the plant in an unsafe condition",
- was removed from Relief Request 3.1.31. This sentence is not necessary for this Relief Request.
l Page 2 of 3
s . ..
Page 3-100: The sa.ntence "This test is beyond the scope of cold-shutdown testing" was removed from Relief Request 3.1.39. The sentence "These tests are beyond the scope of cold-shutdown testing", was removed from Relief Request 3.1.40. These sentences were removed because they are not necessary for '.hese Relief Requests and are subject to misinterpretation.
i 4
1 4
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l i
Page 3 of 3
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Joseph M. Farley Nuclear Plant - Unit 2 Inservice Testing Program Revision 2 List _of Effective Pages Remove Pages Insert Pages Remove Pages Insert Pages 3-2 3-2 3-60 3-60 3-3 3-3 3-65 3-65 3-16 3-16 3-66 3-66 3-17 3-17 3 3-67 3-21 3-21 3-63 3-68 3-23 3-23 3-69 3-69 3+27 3-27 3-70 3-70 3-28 3-28 3-71 3-71 ,.
3-29 3-29 3-73 3-73 3-30 3-30 3-74 3-74 3-31 3-31 3-75 3-75 3-32 3-32 3-77 3-77 3-33 3-33 3-88 3-88 3-34 3-34 3-93 3-93 3-42 3-42 3-94 3-94 3-44 3-44 3-97 3-97 3-45 3-45 3-100 3-100 3-51 3-51 3-102 3-102 3-52 3-52 3-103 3-53 3-53 3-104 '
3-105 L
t
Table V-1 Valve Test Program .
System Name: Reactor Coolant System Revision Numoer: U System Number: Q2B13 ,
(Note: See Table V-2 for Legend of Symbols)-
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Val " Numb" E * * ** I
-8 P&ID/Sh 5 U3 % 3 3 E U U ; Pr EE TPNS Other O Number O O!S G S E E # $ EE D Function Remarks Pressurizer Press. Trans.
V026A 2-8090A 2 D-205037/2 F-2 A 1/8 N M C Q NT 3.1.29 -- to Dead Weight Press. Gen.
LT --
NO --
Pressurizer Press. Trans.
'?o26B 2-80908 2 0-205037/2 F-2 A 1/8 N M C Q NT 3.1.29 -- to Dead Weight Press. Gen. p l LT --
NO --
4 V031A 2-8010A I D-205037/2 D-5 C 6 PR SA C SRV --
NO -- Pressurizer Safety Valve V031B E-8010B 1 D-205037/2 D-4 C 6 PR SA C SRV --
NO -- Pressurizer Safety' Valve V031C ?.-8010C 1 0b5037/2 D-3 C 6 PR SA C SRV --
NO -- Pressurizer Scfety Valve V037 2-8047 2_; Dh2b5037/2- B-10 A 1 O_ , A0 0 q j* --
f.'O --
eNr$ze hfief Tank fit - --
NG 10 .-
LT --
N0' ' --
Reactor Make-up Water to ~
2 V038 2-8046 2 D-205037/2 B-10 AC 3 CK SA 0 SV NI 3.1.3 --
Pressurizer Relief Tank LT --
NO -- ,
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Table V-1 Valve Test Program -
Revision Number: 2 Syst m Name: _ HHSI CVCS System -
(dote: See Table V-2 for Legend of Symbols)
System Number: Q2E21 B
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NO -- Boron Injection Tank Discharge l 2-8801A 2 D-205038/1 _C-5 8 3 IGA M0 C -Q* --
V004A ll MT -- NO 10
-- NO -- Bo'ron Injection Tank Discharge D-205036/1 0-5 B 3 GA M0 C Q*
V004B 2-8801B 2 .
MT -- N0 10 Boron Injection Recirculation C-8 C 1 CK SA 0 CV -- NO --
Pump Discharge _.
l ,V006A 2-8940A 2 D-205038/1 Boron Injection Recirculation l SA 0 CV -- NO --
Pump _ Discharge 2-8940B 2 D-205038/1 D-8 C 1 CK Boron Injectionl _e_irculation C l V006B 3.1.38 <
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l MT -- N0 10
~ ~ ~
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{j{49 HHSI Pumps Discharge to Boron 2l' 3 GA M0 C Q* CS~ 3.i. -- Injection Tank _ 2-8803A , 2. D-205038/1 G-7 B V016A MT -- NO 10 i.lI'49 HHS1 Pumps Discharge to Boron 4 I G-7 8 3 GA M0 C Q* CS_, 31$$ Injection Tank V016B 2-8803B 2 D-205038/1 i l MT -- N0 10 l Revision 2
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. Table V-1 Valve Test Program 2,
'HHSI CVCS System Revision Number:
System Name: (Note: See Table V-2 for Legend of Symbols), , System Number: Q2E21 O . x 8 5 0 8 2 i B B % - e U -.E .E o ? E .h E EJ
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Valve Number , ? 3g , o g g , ag gy E p l 8 E% 0 % .$c o ,8 r C Ti
- e. n:
h3 ma Function Remarks u . lumber a m> m > -- H TPNS Other i
-~iiSITLiiS H Q d RlIR to RC HL D-205038/1 F-2 AC 6 CK SA C CV RR 3.1.36 --
Loops 1 & 2 V077A 2-8993A 1 _ LT -- NO -- y __ HHSI/LHSI and RHR to RC HL Z V077B 2-8993B 1 D-205038/1 G-2 AC 6 CK SA C CV RR 3.1.36 -- Loop.s 3 LT -- NO -- HiiS'l/LHSI and RHR to RC HL 2-8993C 1 0-505038/1 G-2 AC 6 CK SA C CV RR 3.1.2 -- Loop 3 V077C LT -- NO -- CV RR1 3.1.2 -- HHSI Pumps Discharge to RC D-205038/1 G-3 XC 2 CK SA C LT NO -- Loops HL i V078A 2-8990A 1 -- HHSI Pumps Discharge to RC
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CV RR 3.1.2 J; Loops HL D-205038/1 G-3 AC 2 CK SA C LT NO -- V0788 2-89908 1 3.1.2 HHSI Pumps Discharge to RC
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T' CV RR Loops HL G-3 .AC._ 2 CK SA C
-_ 10 V078C 5-8990C 1 D-50'5038/1 LT CV RR 3.1.2 -- HHSI Pumps Discharge to RC 2-8992A 1 0-205038/1 G-3 AC 2 CK SA C _LT --
J0 -- Loops _EL V079A
. CV RR 3.1.2 -- 'HHSI Pumps Discharge to RC 2-89928 D-205038/1 G-2 AC 2 CK SA C LT - _ _._N0 Loops _HL V0798 1 HHSI Pumps Discharge to RC 3.1.2 CV RR D-205038/1 G-2 AC' 2 CK SA C NO ,-- Loops HL V079C 2-8992C 1 LT --
_ _ Revision 1~~ 2/82 Revision 2 t 53784
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Table V-1 Valve Test Program
~
HHSI CVCS System Revision Number: 2' System Name: (Note: See Table V-2 for Legend of Syn.bols) . System Number: Q2E21 n - s 8 5 0 - 5 7 E L E % - e 0 E R e R ; 3 E f! d
% *% M R e e a 3 m p ai a ~ .g .~
c E 8" C S - a :E Valve Number . ? Es . g 3 g y y *g %." 3 P&lD/Sh g g- y - u g g -g 33 ma Function Remarks
. lumber u o> m > -
2- r r ~. n: TPi4S Other v i 3.1.50 -- RC from Reg. Heat Exchanger l2 V253C 2-8149C 2 D-205039/1 A-6 A 2 GL A0 C Q* CS j j:)) -- Shell Side to CVCS Letdown E
"** ""9" MT -- NO 10 P _ _ . . _._ _ _ _ _ . . _ . . _ _ _ _ . . _ .
g LT -- NO -- a, RC from Reg. Heat Exhanger 3.1.19 2 V254 2-8152 2 D-205039/1 A-11 A 3 GL A0 0 Q* CS j:{:jj -- Shell Side to CVCS Letdown Heat Exchanger MT -- NO 1_0 LT -- NO -- 2
,V257 2-8107 2 D-205039/2 E-1 A 3 GA MO 0 Q* CS j:[,jj --
to Re_g. Heat Exchanger 3 MT -- N0 10 LT -- NO -- 3.1.19 CVCS Charging Pump Discharge l2 2-8108 2 D-205039/2 E-2 A 3 GA M0 0 Q* CS 3:j:jj --
.to_ Reg Jeat_fxchanger 3 V258 MT --
NO 10 LT -- NO --
- - . . . . _ Revision 2 0
53704
- e
Table V-1 Valve Test Program Revision Number: 2 System Name: HHSI CVCS System ~ (Note: See Table V-2 for Legend of Symbols) , System Number: _ Q2E21 e e w
^ Q - h b ^
o 8 0 R ." E @ . G3 D R ~ 8 's b .!i e
$ 3 ,0 8 E eO E N 5 E N '
$ U E " ** 0" E * *
;& E 'E Valve Number O 5 U3 % 3 3 E O* %*
Fun: tion Remarks P&ID/Sh O SS 'v7 ' s # S , , ## "3 TPNS Other O Number C ging Pump Bypass Orifice i V259A 2-8109A 2 D-205039/2 E-4 B 2 GL M0 0 Q* CS f Iff t MT -- NO 15 ~ y - - - - - 3147 Chargiiig Pump Bypass Orifice M F-4 B 2 GL M0 0 Q* CS j;j]j -- Line V259B 2-8109B 2 D-205039/2 MT -- N0 15
],j,47 Charging Pump Bypass Orifice 3
2 GL M0 0 0* CS 3.1,3} -- Line , 2 0-205039/2 G-4 8 V259C 2-8109C MT -- NO 15 ' SIS RHR HX to Charging Pumps F-6 AC 3/4 PR SA C SRV -- NO -- Suction V263A 2-8116A 2 0-205039/2 LT -- NO SIS RHR HX to Charging Pumps 3/4 PR SA C SRV -- NO -- suctinn V2633 2-3116B 2 D-205039/2 J-6 AC LT -- NO -- CVCS BA Filter to Charging H-9~ B 2 GL M0 C Q* RR 3.1.37 -- Pumo Suction V264 2-8104 2 D-265039/2 MT -- NO 15 Revision 2 4 9 5370t m+ y
Table V-1 Valve Test Program 2 Revision Number: HHSI CVCS System System Name: (flote: See Table V-2 for Legend of Symbols) . System Number: Q2E21 a - s 8 s : 8
^
a 's; B % a' d 2 ? .8 e R .h E
* % *% E ?; u e & B - 53 -
8" C ~ S - e :E m t: .- c .E
? '5s ,y, gs g@ [ gg a 8 %."
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%u . lumber i o m> m > c. :- r -
TPHS Other s Charging Pump Bypass Orifice
-- t?
8 3 GA MO 0 Q* CS 3.1.33 Disc._to. Seal _. Water _ Heat 2-8106 2 -D-205039/2 D-4 V265 Exchanger JiT -- N0 15__ _ . . _ _ _ . . _ . . _ . . _ _ _ _ Y _ _ _ _ . Charging Pump Suction from t! G-6 B 8 GA M0 O Q* -- NO -- Rdsidual HX.._ V324A 2-8130A 2 D-205039/2
- MT -- N0 15 Charging Pump Suction from 8 GA M0 0 Q* -- NO --
Residinal ' HX . _ _ G-6 B V324B 2-8130B 2 D-205039/2 MT -- N0 15 Charging Pump Suction from 8 GA M0 0 Q* -- NO -- Residual Heat Exchanger 2 D-205039/2 G-6 8 V325A __ 2-8131A MT -- N0 15 Charging Pump Suction from 8 GA MO 0 Q* -- NO -- Residual Heat Exchanger 2-8131B 2 0-205039/2 H-6 B V325B MT -- NO 15 __ 3.1.48
~j jj -- Charging Pump Disc.
4 GA M0 0 Q* CS V326A 2-8132A 2 0-205039/2 G-3 8 _ MT -- NO 15 . Revision 2 9 m. E l
Table V-1 Valve Test Program Revision Number: 2-System Name: HHSI CVCS System (Note: See Table V-2 for Legend of Symbols) , Systen Number: Q2E21 s 8 5 0 8 2 E 5 8 % - 2 E R e c ; .h E !!J m
; % *% E R u e & B - Ga G 5 8" C " S - e :2 .%
Valve Number ? '5 % o s @ { g y .8 %.% a P&ID/Sh g og ,y 7 g , g g gg 3,3 Function Remarks B ilumber o m> m - n r - ~ n:
. ma TPNS Other v
-. 3.1.48 4 GA M0 0 Q* CS j:j:)) -- Charging Pump Disc.
V3268 2-8132B 2 D-205039/2 G-3 B MT -- NO 15 y 3.1.48 $ 2-8133A 2 0-205039/2 G-3 B 4 GA M0 0 Q* CS j:j:jj -- Charging Pump Disc. V327A MT -- NO 15 3.1.48 4 GA M0 0 Q* CS 3:j:)) -- Charging Pump Disc. , V327B 2-8133B 2 D-205039/2 H-3 B _ MT -- N0 15 3.1.51 - - ~ Charging Pump Suction from Refuelina Water Storage Tank G-7 8 GA M0 C Q* CS ji:]j V336A 2-LCV1158 2 D-205039/2 B MT -- NO 15
- 3.T.51 - Charging Pump Suction from 2-LCV115D 2 D-205039/2 H-7 B 8 GA M0 C Q* CS j,j:]j --
lefueling Water Storace Tank V336B MT -- NO 15 Revision 2 9 5370 2 me - g
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Table V-1 Valve Test Program 2 Revision Number: System Name: Service Water System (Note: See Table V-2 for Legend of Symbols) System Number: Q2P16 B 3, 8 E a b 7 a L 5 % - a R e # ; .b E Ed m e a 3 p 3,' a % *% 8 E; s_ e c .5 8" O " S - a :E ." ."
? U% . # 8 g a u .*8 %.%
Valve Number a gg g
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,7 , Function 3
re ca v> _, u ,i lumber a vi > vi > .c = r e TPNS Other 3.1.52 Service Water to A-7 B 12 GA M0 0 Q* CS 3:l:$$ Containment Coolers V010A 2-M0V3019A 2 D-205003/1 MT -- NO 75 Y Service Water to 8; M0 0 0* CS j:j.5j a i:33 -- Containment Coolers D-205003/1 C-7 B 12 GA V010B 2-MOV3019B 2 ' MT '-- N0 75 3.1.52 Service Water to D-205003/1 E-7 B- 12 GA M0 0 Q* CS $:!:$$ -- Containment Coolers V010C 2-MOV3019C 2 MT -- N0 75 3.1.52 Service Water to F-7 12 GA M0 0 Q* CS $ $$ -- Containment Coolers V010D 2-MOV3019D 2 0-205003/1 B MT -- NO 75 3.1.52 Service Water Discharge A-10 B 10 GA M0 C Q* CS 3:!:]$ -- from Containment Coolers V043A 2-M0V3024A 2 D-205003/1 MT -- N0 65 ~ 3.1.52 Service Water Discharge D-205003/1 C-10 B 10 GA M0 C Q* CS $:!:$$ -- from Containment Coolers V043B 2-MOV3024B 2 MT -- N0 65 , Revision 2 5370 m_ -g
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Table V-1 Valve Test Program-Revision Number: 2 System Name: Service Water System (Note: See Table V-2 for Legend of Symbols) System Number: Q2P16 _ D 3, 8 5 0
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Table V-1 Valve Test Program . 2 Revision Number: System Name: Service Water System - (Note: See Table V-2 for Legend of Symbols) System Number: Q2P16 . m
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V516 None 3 D-2000f3/8 MT -- NO 75 2 y 3.1.53 Service Water Supply to (g D B 24 B M0 0 Q* CS j:j:jj -- Tu/bine Building - Train B V517 None 3 D-200013/8 MT -- NO 75 Service Water Supply to 12 B MO 0 Q* -- NO -- Diesel Building - Train B VS18 None 3 D-200013/3 B-3 B MT -- N0 75 Service Water Supply to Diesel 12 B M0 0 Q* -- NO -- Building - Train A V519 None 3 D-200013/3~ B-3 B MT -- ND 75 Emergency Service Water 42 B M0 C Q* -- NO -- Recirculation Line to Pond - V538 None 3 _ _ _ _ _B D-200013/8_ . . _ C-10_. Train B MT -- N0 45 Emergency Service Water E-9 B 42 B M0 C Q* -- NO -- Recirculation Line to Pond - V539 None 3 D-200013/8 " MT -- N0 45 Revision 2 l
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Table V-1 Valve Test Program . Revision Number: 2 System Name: Service Water System (Note: See Table V-2 for Legend of Symbols) System Number: _02P16 i u 3, 8 5 0 h
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Table V-1 Valve Test Program Revision Number: 2 pst;m Name: Component Cooling Water System yst:m Number: (Note: See Table V-2 'for Legend of Symbols) Q2P17 n
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3.1.4 Test Requirement Valves shall be leak tested with the differential pressure in the same direc-tion as applied when the valves are performing their safety functions. 3.1.4.1 Basis,for Relief i These valves provide primary isolation for containment sump penetrations with no provisions for leak rate testing with the differential pressure in the same direction as applied when the valvas are performing their function as required by IWV-3420(c). i 3.1.4.2 Alternate Testing Leak rate testing will be performed by applying the differential pressure between the primary and secondary isolation valves. . 3.1.5 Test Requirement Exercisa check valves for operability at least once every three (3) months. 3.1.5.1 Basis for Relief The only positive means of exercising this noraally closed valve is by direct-The initiation of AFW during power ing AFW flow into the Steam Generators. operation will result in unnecessary thermal shock to the Auxiliary Feedwater-to-Main Feedwater connection. An introduction of cold water into the second-ary system will also cause power transients. 3.1.5.2 Alternate Testing AFW flow will be directed through the valve at the design flow tate of tne AFW system at cold shutdown. Verification of this flow through the valve in conjunction with verification that the control valve position is the same for each test will provide assurance that the valve has opened sufficiently to perform its function. 3.1.6 Test Requirement Exorcise the valves for operability at least once every three (3) months. 3.1.6.1 Basis for Relief It is not practical to exercise these valves during normal plant operation or at cold shutdown per IWV-3410. The exercising of thesa valves would introduce chlorides and fluorides into the secondary systems. This would jeopardize 2 the secondary water chemistry and possibly cause steam generator damage. 3.1.6.2 Alternate Testing These valves will be exercised at reactor refueling outages. 3-88 Revision 2
=
-+
pressure (600 psig). It is assumed for the purpos of th2 cycling test that the downstream check valves have failed. Venting of the downstream pressure l2 cannot be accomplished under any conditions because of the radiation hazard to plant personnel. 3.1.17.2 Alternate Testing If the Once every three (3) months the cownstream pressure will be measured. pressure is less than or equal to 550 psig, then the valve will be full-stroke 2 exercised. If the pressure If is greater than 550 psig, the valve will not be the downstream pressure prohibits quarterly testing, exercised that ouarter. ) the valve will be full stroked at cold shutdowns. 3.1.18 Test Requirement Exercise the valves for operabiiity at least once every three (3) months. 3.1.18.1 Basis for Relief The operability testing (full stroke) of these valves during normal operation could cause a loss of system function. The failure of these valves in a non-conservative position during a cycling test would cause the loss of the RCP seal water cooling function resulting in possible RCP seal damage and a possible j 2 reactor trip. The design of the valve will not facilitate a partial-stroke test. 3.1.18.2 Alternate Testing The valves will be full-stroke tested for operability at each cold shutdown. 3.1.19 Test Requirement Exercise the valves for operability at least once every three (3) months. 3.1.19.1 Basis for Relief The operability testing (full stroke) of these valves during normal operation could jeopardize the charging function of th3 CVCS. Failure in a nonconserva-tive position would eliminate the VCT as a source of RCS charging and possibly cause a reactor trip. The design of the valves will not facilitate a partial-stroke test. .- 3.1.19.2 Alternate Testing The valves will be full-stroke tested for operability at each cold shutdown. 3.1.20 Test Requirement Exercise the valves for operability at least once every three (3) months. 3.1.20.1 Basis for Relief The operability testing (full stroke) of these valves during normal operation would jeopardize the RCP cooling function. Cycling of the valves would inter-rupt the CCW supply to the reactor coolant pumps. Also the failure of the 3-93 Revision 2
# valves in a nonconservative position during the cycling test would result in a loss of the systeg function. This would require stopping the reactor coolant pumps to prevent overheating and damage which would result in a reactor shut- 2 down. The design of the motor-operated valves will not facilitate a partial-stroke test.
- I 3.1.20.2 Alternate Testing ;
The valves will be full-stroke tested for operability at each cold shutdown. 3.1.21 Test Requirement i Exercise the valves for operability at least once every three (3) months. 3.1.21.1 Basis for Relief The operability testing (full stroke) of this valve during normal operation would cause an interruption of instrument air supply to instruments and equip-ment associated with the RCS. Also, a fa' lure in a nonconservative position during a cycling test would cause a complete loss of instrument air supply to the containment resulting in a loss of RCS level control which could cause a 2 reactor trip. The design of the valve will not facilitate a partial-stroke test. 3.1.21.2 Alternate Tec, ting The valves will be full-stroke tested for operability at each cold shutdown. 3.1.22 Test Requirement Exercise the valves for operability at least once every three (3) months. 3.1.22.1 Basis for Relief The operability testing (full stroke) of these valves during normal operation is not possible. The bypass valves are interlocked with the MSIVs such that when the MSIVs are open, the bypass valves are closed. The design of the valves will not facilitate a partial-stroke test. 3.1.22.2 Alternate Testing The valves will be full-stroke tested for operability at each cold shutdown. 3.1.23 Test Requirement Normally inaccessible valves with remote position indicators shall be visually observed at the same (or greater) frequency as reactor refueling outages to confirm operability of position indicators. 3.1.23.1 Basis for Relief Remote position indicators will be used to verify valve position per IW-3300. However, visual observation of valve operation is not practical. Such obser-vation would require removal of the valve protective chamber which is also considered to be a portion of the containment pressure boundary. Since the valve is provided with redundant inaicators, position is accurately reflected by the remote indications. 3-94 , Revision 2
3.1.30 Test Requirement The valve will be full-stroke tested for operability at least once every three
. (3) months.
3.1.30.1 Basis for Relief The operability testing (full stroke) of this valve during Duringnormal normal operation or operation, cold shutdown could cause a loss of system function. opening the valve dumps all instrument air into the CTMT atmosphere causing During a a loss of RCS pressure control for spray and a loss of letdown controi. cold shutdown, exercising the valve would cause loss of pressure control and ' level control. Valve design does not facilitate a partial-stroke test. 3.1.30.2 Alternate Testing The valve will be full-stroke tested for operability at each refueling outage. 3.1.31 Test Requirement Exercise check valves for operability at least once every three (3) months. t 3.1.31.1 Basis for Relief The operability testing (full stroke) of this normally closed check valve per IWV-3520 during plant operation, cold shutdown, or refueling is not practical. The only means of full stroking the valve is by initiating the Containment Manu-Spray System which would cause excessive damage to equipment in CTMT. ally exercising the valve would require removing the valve bonnet after drain- I2 ing the RWST. 3.1.31.2 Alternate Testing The valve will be verified as operable during the quarterly testing of the Containment Spray Pumps. Due to system design, the valve can only be partial-stroke tested. . 3.1.32 Test Requirement IWV-3410(g) and IWV-3520(c) state that when corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup. A retest showing' acceptable operation shall be run following any required corrective action before the valve is returned to service. 3.1.32.1 Basis for Relie_f' The plant Technical Specifications provide the requirements and plant condi-tions necessary for plant startup. 3.1.32.2 Alternate Testing The test requirement will be satisfied before the valve is required for plant operability as defined in the plant Technical Specifications. 3-97 , Revision 2
3.1.39 Test Requirement Exercise check valves for operability at least once every three (3) months. 3.1.39.1 Basis for Relief . . Operability testing of these normally closed check valves per IWV-3520 during normal operation or cold shutdown is not practical. During normal operation, exercising these valves with flow would introduce sodium hydroxide into the RWST (ECCS water supply). During cold shutdown, both trains of the system would have to be made inoperable in order to drain the system for bonnet removal and manual exercising of the valve disk. I2 g 3.1.39.2 Alternate Testing The valves will be verified as operable by removing the bonnet and manually full-stroke exercising the disk at each refueling outage. 3.1.40 Test Requirement Exercise check valves for operability at least once every three (3) months. 3.1.40.1 Basis for Relief Operability testing of these normally closed check valves per IWV-3520 during power operation or cold shutdown is not practical. During power operation the CTMT if not available. During cold shutdovn, valve disassembly or an air test for flow verification requires draining a portion of the system. g2 3.1.40.2 Alternate Testing The valves will be verified as op.erable by removing the bonnet and manually full-stroke exercising the disk at each refueling outage. 3.1.41 Test Requirement Exescise check valves for operability at least once every three (3) months. 3.1.41.1 Basis for Relief Operability testing of this normally closed check valve per IWV-3520 during normal operation or cold shutdown would require that the boric acid system be made inoperable, thus placing the plant in an unsafe condition. 3.1.41.2 Alternate Testing g The valve will be full-stroke tested at each refueling outage by verifying that the maximum required flowrate passes thru the valve. 3-100 Revision 1
, Revision 2
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3.1.44.2 Alternate Testing A partial-stroke test will be accomplished during the quarterly testing of the MDAFW pumps. Acceptance of the pump test will provide assurance that the valve has partially opened. A full-stroke test will be accomplished by providing Verifica-
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MDAFW pump design flow to the Steam Generators during cold shutdown. tion that design flow is reached provides assurance that the valve has opened in order to perform its function. 3.1.45 Test Requirements I Exercise valves for operability at least once every 3 months. 3.1.45.1 Basis for Relief The Technical Specification requires that these containment purge supply and exhaust valves be closed during modes 1 through 4. Consequently, no exercising of these valves can occur unless the plant is in mode 5 (cold shutdown) or mode 6 (refueling). 3.1.45.2 Alternate Testing These valves will be full-stroke tested for operability at each cold shutdown. l 3.1.46 Test Regsirement Exercise check valves for operability at least once every 3 months. 3.1.46.1 Basis for Relief The operability testing (full stroke) of the main steam isolation valves during normal plant operation would cause an interruption in the main steam flow and initiate a turbine trip. In addition, these valves are designed for only one closure at plant operating conditions, after which maintenance is performed on these valves. 3.1.46.2 Alternate Testing The calves will be part-stroke exercised during plant operation and full-stroke exercised every cold shutdown.
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3.1.47 Test Requirement Exercise the valves for operability at least once every three (3) months. l 3.1.47.1 Basis for Relief i The operability testing of these valves during normal operation could cause 2 damage to the charging pumps. If problems occur with the pressurizer level control or FCV-122 normal charging would isolate. This would result in inade-l quate cooling and subsequent damage to the charging pumps if the mini-flow valve for the pump was closed. l 3-102 Revision 1
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In addition, cycling of the common mini-flow valve (Q2E21V265) causes pressure transients in the reactor coolant pump seal water return line which can affect l reactor coolant pump seal performance. 3.1.47.2 Alternate Testing The . . as will be full-stroke tested for operability at each cold shutdown. 3.1.48 Test Requirement Exercise the valves for operability at least once every three (3) months. 3.1.48.1 Basis for. Relief The operability testing of these valves during normal operation could cause a
. loss of system function and put the plant in an unsafe condition. If a sa'fety injection were to occur during testing of these valves and a particular charg-ing pump were to fail to start, the ability to inject water into the RCS could be lost.
3.1.48.2 Alternate Testing The valves will be full-stroke tested for operability at each cold shutdown. 3.1.49 Test Requirement Exercise the valves for operability at least once every three (3) months. 2 3.1.49.1 Basis for Relief The operability testing of these valves during normal operation could put the plant in an unsafe condition. Stroking these valves during power operation
. will lower the boron concentration of the BIT unless the valves are isolated from the operating charging pump. The charging pumps are isolated by the dis-charge header isolation valves which could result in the loss of the safety injection function as discussed in Relief Request 3.1.48.
3.1.49.2 Alternate Testing The valves will be full-stroke tested for operability at each cold shutdown. 3.1.50 Test Requirement b Exercise the valves for operability at least once every three (3) months. 3.1.50.1 Basis for Relief Cycling of these valves will cause pressure surges in the letdown line which can cause Letdown Orifice Relief Valve 8117 to lift. 3.1.50.2 Alternate Testing The valves will be full-stroke tested for operability at each cold shutdown. 3-103 Revision 2
3.1.51 Test Requirement Exercise the valves for operability at least once every three (3) months. 3.1.51.1 Basis for Relief - Cycling of these valves causes 2000 ppm borated water to be injected into the-RCS from the RWST while the valve is being cycled. This results in small boron transients in the RCS. 3.1.51.2 Alternate Testing a' The valves.will be full-stroke tested for operability at each cold shutdown. 3.1.52 Test Requirement , Exercise the valves for operability at least once every three (3) months. 3.1.52.1 Basis for Relief Cycling of these valves can cause a pressure surge in the Service Water System which results in service water automatically isolating to the Turbine B1dg. 3.1.52.2 Alternate Testing The valves vill be full-stroke tested for operability at each cold shutdown. 3.1.53 Test Requirement 2 Exercise the valves for operability at least once every three (3) months. 3.1.53.1 Basis for Relief Cycling these valves can result in the automatic isolation of all service water to the turbine building on a high flow signal. With the unit at rated load, this could cause the turbine to trip and/or damage major components of the secondary systems. 3.1.53.2 Alter nate Testing The valves vill be full-stroke tested for operability at each cold shutdown. 3.1.54 Test Requirement Exercise the valves fcr operability at least once every three (3) months. 3.1.54.1 Basis for Relief Cycling these valves causes pressure and flow variations in the CCW system which result in the automatic isolation of CCW to reactor coolant pump's thermal barriers and oil coolers. If flow to the RCP's thermal barriers and oil coolers is not quickly re-established the reactor would trip because the RCP's would have to be shutdown to prevent damage to the bearings and/or seals. 3-104 Revision 2
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4 4- , . W 3.1.54.2 Alternate Testing The valves will be full-stroke tested for operab'ility at each cold shutdown. g A t e . i
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