ML20034B551
| ML20034B551 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/20/1990 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20034B549 | List: |
| References | |
| PROC-900420, NUDOCS 9004270334 | |
| Download: ML20034B551 (54) | |
Text
a
-(C)-PUMPS:
Safety Injection. Pumps (1A, 18)
SAFETY CLAS$:
2
'l FUNCTION:
To provide emergency core cooling in the event of a break in either the reactor coolant or_
steam system piping.
TEST REQUIREMENT:-
IWP-3100 requires the resistance.of the~ system to be varied until either the measured differential pressure or the measured-flow rate equals--the corresponding reference value.
BASIS FOR RELIEF:
When_ testing these pumps on'line, tO only. flow path available is thru the'ainiflow to the J
FWST.
Flow is limited by an orifice in the 4
miniflow line, which yields a-test point back.
1 on the head curve. =As stated in Generic-1 Letter 89-04, minimum-flow lines are not
-l designed for pump testing purposes.
The. test point.for monitoring pump performance for.
degradation should be in a more stable region j
on the pump performance curve.
Also' the i
amount of time the pump is' run at miniflow should be minimized.
I
~
1 ALTERNATE TESTING:
The Safety Injection-Pumps will be tested-14 1 according to the following program, which is
'i consistent with Generic Letter 89-04._
i Quarterly The Safety-Injection Pumps will be tested-quarterly to verify Technical Specification -
limits on pump operability are met.
Velocity-vibration measurements will.also be taken..The main thrust of this test will be to verify pump operability.
Refuelino Outage During each refueling outage, a code pump test, including velocity vibration measurements, will y
be performed at a test point in the stable region of the performance curve.
Implementation The new testing program (quarterly and 1
refueling) will be_ in. place by the 1990 Unit-2 I
refueling outage and the 1991 Unit 1 refueling:
1
. outage.
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Rev. 14 9004270334 900420 PDR ADOCK 05000369 p
~
(D) PUMPS:
Residual Heat Removal Pumps (IA, 18)
-i SAFETY. CLASS:
2 FUNCTION:
To remove heat energy from the core and Reactor Coolant System during cooldown and refueling operations.
Also,. utilized as part of Safety Injection System and Containment Spray-System during an accident condition.-
TEST REQUIREMENT:
IWP-3100 requires the resistance of the. system to be varied until either the measured differentia 1' pressure or the measured flow rate' equals the corresponding reference value.
BASIS FOR RELIEF:
When. testing these pumps on line, the only flow path available is thru the= miniflow line.. Flow is limited by the miniflow control valve in the.
.line', which yields.a test point,back on the head curve.
Asistated in Generic Letter 89-04, minimum-flow lines are not designed for pump' j
testing purposes. The test point for monitoring pump performance for degradation' should be in a more stable region on the pump.
l performance curve.
Also, the amount of time l
the pump is run at miniflow should be l
minimized, i
ALTERNATE TESTING:
The Residual Heat Removal-Pumps will be' tested H
according to the following program, whichLis
- 14 consistent'with Generic Letter 89-04.
j Quarterly =
l The Residual-Heat Removal Pumps will be tested j
quarterly to verify Technical Specification limits on pump operability are met. Velocity..
i vibration measurements will = also be taken.
The i
main thrust of this test will be to verify pump l
operability.
Refuelina Outaae During each refueling outage, a code pump test, including velocity vibration measurements, will-i be performed at a test point in the stable-i region of the performance uarve..
Implementation I
The new testing program'(quarterly and refueling) will be in place by the.1990 Unit 2 refueling outage and the 1991 Unit 1 refueling outage.
i Rev. 14
(E) PUMPS:
Centrifugal Charging Pump (1A, IB)
SAFETY CLASS:
2 FUNCTION:
To supply reactor coolant inventory in the Volume control Tank or Refueling Water Storage Tank to the reactor coolant system.
TEST REQUIREMENT:
Table IWP-3100-1 requires measuring differential pressure (DP) and flow l rate (Q).
BASIS FOR RELIEF:
When testing these pumps on line, the only flow path available is thru a combination of the normal charging and_the miniflow to the VCT.
The'miniflow is not instrumented for flow.
Flow through the line is assumed to be,at the flow rate corresponding to the orifice design-conditions.
Also, the combination flow paths'-
yield a~ test point back on the head curve.
Thf best' test point back for monitoring pump
'q performance for degradation should be in=a more-stable region on the pump performance curve.
ALTERNATE TESTING:
The Centrifugal Charging Pumps will be tested according to the following program, which is y
consistent with Generic Letter 89-04.l 1
Quarterly The Centrifugal Charging Pumps will be tested j
34; quarterly to verify Technical Specification j
' limits on pump operability are met.
Velocity ~
i vibration measurements will'also be taken.
The main thrust of this test will.belto verify pump' operability.-
Refuelina Out During each eling outage, a code pump test, j
including velocity vibration measurements, will be performed at a test point in the stable region of the performence curve.
Implementation
')
The new testing program (quarterly and refueling) will be in place by the 1990 Unit 2 refueling outage and the 1991 Unit I refueling outage.
Rev. 14 4
e J
1 (F) PUMPS D/G Room Sump Pumps (1A2, 1A3,-182, 183)-
SAFETY CLASS:
3 FUNCTION:
Water removal from Diesel-Generator Rooms:
TEST REQUIREMENT:-
Test' pumps in accordance with Subsection-IWP.
BASIS FOR RELIEF:
The D/G Room Sump Pumps are vertical pumps:
tested by filling the'D/G Room Sump and pumping the-sump down.
No stable system conditions can.
be obtained due to the continuous decrease in l
sump level.
No' suction pressure, flow, bearing temperature, or lubricant level 4 instrumentation is available.
ALTERNATE TESTING:
' The D/G Room Sump 1 Pumps will be tested for-
'l greater than or equal to emergency design flow by:
(1) Filling the sump and recording level._
j
-i (2). Pumping down the sump and recording both-l'I level and pump down time.
An average flow rate'will be determined from-the time it takes to pump a known volume from the sump. ' Pumping down.the sump takes approximately 60 seconds.- An average discharge pressure will be determined and recorded.
The flow rate will be compared with: acceptance I
criteria established per Table-IWP-3100-2.
l The above testing procedure is an interim--
-i method until modifications are made to the.
j system which will' permit full flow testing
~
using a-recirculation loop back to the sump.
14 1 Included in the test loop modification will be 1
direct flow indication and' throttling capability to set either AP or Q.
The i
modifications will be installed by the 1992' j
refueling outages, j
No lubrication level verification is required /
for this pump.
Lubrication is maintained'under our routine preventative maintenance program.
No suction pressure instrumentation is required since this pressure can be. calculated from sump level measurements.
Rev. 14 f
c' l
1 The mechanical condition of.the subject' pumps, will be determined:from. vibration data to be gathered quarterly.
No bearing temperature
-instrumentation-is installed.
ANSI /ASME OM-6.
i will not require bearing temperature'-
- measurements..
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Page No.
2 e
04/11/90 Duke-Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST-TEST-RR STROKE
_ TEST R
DIAGRAM COOR-REQ 1 REQ 2' TIME ALTERNATIVES /-
E i
(SEC)
REMARKS V
't 10 1CA-0007AC C 1592-1.1' B-10' B-ST-Q CA2 RF#
14 ICA-0008 C 1592-1.1 B-11 C MTC-Q 10
~
'C 1592-1.1 C B ST-Q CA2 RF#
14~
ICA-0010 C 1592-1.1 C-05 C MTC-Q 1
10 1CA-0011A C 1592-1.1 B-04 B ST-Q:
RF#
-14' l
CA2 1CA-0012 -
C 1592-1.1 B-03 C MTC-Q-10 1CA-0015A C 1592-1.1 D-03 8 ST-Q_
10 1CA-0018B C 1592-1.1 0-04 B ST-Q 60 ICA-0020AB C 1592-1.1 1-10 B ST-Q ICA-0022 C 1592-1.1 1-10 C MTO-Q-ICA-0026 C 1592-1,1 1-04 C MTO-Q 1CA-0027A C 1592-1.1 J-05 B ST-Q 60
~-
ICA-0031 C 1592-1 1 I-07 C MTO-Q 1CA-0032B C 1592-1.1-J-08 B ST-Q 60.
1CA-0036AB C 1592-1.0 L-10 B ST-Q 60 ICA-0037 B 1592-1.0 K-14 C MTO.C-Q -
CS-CA1 ICA-0038B B 1592-1.0 J-14 B ST-Q 12 ICA-0040B C 1592-1.0 G-14 B ST-Q 60 1CA-0041 B 1592-1.0 H-14 C MTO.C-Q CS-cal-ICA-0042B B 1592-1.0 I-14 B ST-Q 10 ICA-0044B C 1592-1.0 C-11 B ST-Q
'60 ICA-0045 B 1592-1.0 C-09 C MTO,C-Q CS-CA1 ICA-0046B B.1592-l'.0 D-08 B ST-Q 10,-
ICA-0048AB C 1592-1.0 K-08 B ST-Q 60 1CA-0049 B
1592-1.0 H-08 C MTO.C-Q -
CS-CA1 1CA-0050B B 1592-1.0 G-08 B ST-Q 12.
ICA-0052AB C 1592-1.0 K-07 B ST-Q 60.-
ICA-0053 B 1592-1.0 H-07 C MTO.C-Q -
CS-CA1 1CA-0054AC B 1592-1.0 G-07 B ST-Q 12 1CA-0056A C -1592-1.0 C-04 B ST-Q 60_
i 1CA-0057 B 1592-1.0 0-06 C MTO,C-Q CS-CA1 1CA-0058AL B 1592-1.0 D-07 B ST-Q 10 ICA-0060A C 1592-1.0 G-01 B ST-Q 60 ICA-0061 B 1592-1.0 H-01 C MTO.C-Q CS-CA1 1CA-0062A B 1592-1.0 1-01 B ST-Q 10 ICA-0064AB C 1592-1.0 L-04 B ST-Q 60 o
ICA-0065
,B 15.92-1.0 K-01 C MTO.C-Q -
CS-CA1 ICA-0066AC B 1592-1.0 J-01 B ST-Q 12 ICA-0086A C 1592-1.1 C-14 B ST-Q 10 1CA-0116B C 1592-1.1 E-14 B ST-Q 10 1CA-0161C C 1592-1.1 D-08 B ST-Q 10 ICA-0162C C 1592-1.1 D-07 B ST-Q 10 ICA-0165 C 1592-1.1 C-14 C MTO-Q CA1 RF#
ICA-0166 C 1592-1.1 F-14 C MTO-Q CA1 RF#
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Page No.
-5 04/11/90 Duke Power Company.
McGuire Nuclear Station r
PUMP AND VALVE INSERVICE TESTING PROGRAM
^
VALVE CL-FLOW.
FLOW CAT TEST TEST RR STROKE--
TEST R
DIAGRAM COOR REQ 1.
REQ 2' TIME ALTERNATIVES /'
E (SEC)
REMARKS V 2-r i
i
- ' REFUELING WATER 1FW-0001A B 1571-1.0 E-11
B ST-Q-10 i
PASSIVE IFW-0004-B-
1571-1.0 D-08 A LT RF
- i PASSIVE IFW-0005' B 1571-1.0 C-07 AC LT-RF PASSIVE i
1FW-0011-B 1571-1.0 C-02 A LT-RF PASSIVE IFW-0013 B
1571-1,0-D-02 A LT-RF 30-.CS-FW1 1FW-0027A-B 1571-1.0 C-12 B ST-Q CS-FW2-141 1FW-0028.
-B-1571-1.0 B-11 C MTO.C-Q -
10 ' -
IFW-0032B B 1571-1.0 E-11 B
'ST-Q 10 IFW-0033A B 1571-1.0 F-11 B
-~
1FW-0052 E 1571-1.0 I-05 C MTO-Q PASSIVE 1FW-0067 B 1571-1.0 C-01 AC LT-RF s.
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i Page No.
10 04/11/90 4
Duk'e Power Company McGuire Nuclear Station PUMP AND. VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR - STROKE TEST R
DIAGRAM COOR REQ 1 REQ 2 TIME, ALTERNATIVES /-
E-
-(SEC)
' REMARKS' V
- -RESIDUAL HEAT REMOVAL IND-0001B-A-
1561-1.0 1-13 A ST-Q LT-TS 60 --
CS-ND1 PIV' IND-0002AC EAp 1561-1.0 H-13 A ST-Q LT-TS 60 CS-ND1 PIV t
IND-0004B B il561-1.0 E-12 B ST-Q
(
60
'IND-0008 B 1561-1.0 D-08 C MTO.C-Q CS-ND6.
14
=
IND-0014 B 1561-1.0 D-03 B ST-Q
-60 IND-0015B B 1561-1.0 E-03 B ST-Q 10-CS-ND3 1ND-0019A B 1561-1.0 H-12 B ST-Q
'60 CS-ND6 14 j
IND-0023 B 11561-1.0 J-08 C MTO,C-Q IND-0029-B 1561-1.0 J-03 B ST-Q 60 IND-0030A B 1561-1.0 1-03 B ST-Q 10 CS-ND3 IND-0058A B 1561-1.0 K-03 B ST-Q
_ 10 '- 'CS-ND2 1ND-0067B B-1561-1.0 B-09 B ST-Q 10 IND-0068A B 1561-1.0 L-09 -B ST-Q 10 r
1ND-0070 B 1561-1.0 K C MTO.C-Q --
CS-ND4 14 IND-0071 B 1561-1,0-C-04' C
MTO C-Q -
CS-NDS
. 14
)
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Page No.
12 04/11/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE-TESTING PROGRAM VALVE CL FLOW FLOW' CAT TEST TEST RR - STROKE-TEST-
~ R.
DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES /-
'E-
-(SEC)
REMARKS
~V
- SAFETY INJECTION
..CS-nil 11 1NI-0009A B 1562-1.0-H-09 B ST-Q 11 CS-NI1 INI-0010B B 1562-1.0 G-09 B
-ST-Q
=-
CS-N114 14 1NI-0012 B 1562-1.0 G-08' C: -MTO-Q CS-N113 14' INI-0015 A 1562-1.0 K-07 C MTO-Q.
1NI-0017 A 1562-1.0 1-07 C MTO-Q CS-N113 14 1NI-0019 A 1562-1.0 F-07 C MTO-Q CS-N113 14 CS-NI13 >
14-INI-0021 A 1562-1.0 D-07 C MTO-Q 15 1NI-0047A B 1562-2.0 K-05-.A ST-Q LT-RF.
INI-0048 B 1562-2.0 K-03 AC MTC-Q LT-RF-
-NI3
-MT-RF*
1NI-0054A DELETED.
13
]
PIV RF#<
]
1NI-0059'.
A 1562-2.0 D-13 AC MTO.C-Q LT-TS NI4 1NI-0060 A 1562-2.0 D-14 AC MTO.C-Q LT-TS' NI6 PIV RF#
1 INI-0065B DELETED.
13
^
INI-0070 A 1562-2.0 H-13 AC MTO.C-Q LT-TS.
NI4 PIV RF#
INI-0071 A 1562-2.0 H-13 AC-MTO.C-Q LT-TS NI6.
PIV RF#'
-1 r
1NI-0076A DELETED-
_13 l
INI-0081 A 1562-2.1 C-03 AC MTO.C-Q LT-TS NI4 PIV'RF#
l 1N1-0082 A 1562-2,1 C-03 AC MTO.C-Q LT-TS NI6 PIVLRF#.
1NI-0088B DELETED 13 1NI-0093 A 1562-2.1 C-08 AC MTO.C-Q LT-TS:
NI4 PIV RF#
INI-0094 A.
1562-2.1 C-08 AC MTO.C-Q LT-TS NI6
'PIV RF#
INI-0095A B 1562-2.1 F-12 A ST-Q LT-RF 10 INI-0096B B 1562-2.1 E-13 A ST-Q LT-RF
'10 1NI-0100B B 1562-3.0 F-13 B ST-Q
CS-N115 14 1NI-0103A B-1562-3.0 J-14 B ST-Q 10 j
1NI-0114 B 1562-3.0 1-09 C MTO-Q 1NI-0115B B 1562-3.0 H-09 B ST-Q 10 1NI-0116 -
B 1562-3.0 J-09 C HTO.C-Q -
CS-NI16 141 4
1NI-0118A B 1562-3.0 H-07 B ST-Q 10 i
INI-0120B B' 1562-3,0 J A ST-Q LT-RF 10 j
INI-0121A B 1562-3.0 J-06 B ST-Q 10 CS-NIS 1NI-0124 A 1562-3.0 J-03 AC MTO.C-Q LT-TS PIV CS-NI17 14-INI-0125 A 1562-3.0 I-03 AC MTO.C-Q LT-TS PIV.CS-N120 14 1NI-0126 A 1562-3.0 J-02 AC MTO.C-Q -LT-TS PIV CS-N120
-14 3
1NI-0128 A 1562-3,0 1-04 AC MTO.C-Q LT-TS
'PIV CS-N117 14 1NI-0129 A. 1562-3.0.
I-03 AC MTO.C-Q LT-TS PIV CS-NI20 14~
1NI-0134' A 1562-3.0 G-04' -AC MTO.C-Q LT-TS PIV CS-NI20 14 1NI-0135B B 1562-3.0 E-14 B ST-Q 10 1NI-0136B B 1562-3.0 C-14 B ST-Q 10 1NI-0143 B 1562-3.0 F-09 C MTO.C-Q 1NI-0144B B 1562-3,0 G-09
'B ST-Q 10 i
1NI-0147A B 1562-3.0 G-11 B ST-Q 10 CS-NI4 1NI-0148 B 1562-3.0 D-09 C MTO.C-Q -
CS-NI16 14 1NI-0150B B 1562-3.0 E-07 B ST-Q 10. -
'.I Page No.
13 04/11/90 Duke Power Company McGuire Nuclear Station PUMP AND-VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR STROKE TEST R
DIAGRAM COOR '
REQ 1 REQ 2 TIME ALTERNATIVES /
E (SEC)
REMARKS V'
1NI-0152B B 1562-3.0 D-06 B ST-Q-10 CS-NI6 INI-0156 A 1562-3.0 D-03 AC MTO.C-Q LI-TS PIV CS-N117 14 1NI-0157' A 1562-3.0 D-02 AC ~ MTO.C-Q LT-TS
-~
PIV CS-NI17 14' 1NI-0159 A 1562-3.0 B-04 AC MTO.C-Q LT-TS PIV-CS-NI17 14 1NI-0160 A 1562-3,0 B-03 AC MTO.C-Q LT-TS PIV_CS-NI17 14 1NI-0162A' - B 1562-3.1 K B ST-Q 10
_.CS-N17 -
1NI-0165 A 1562-3.1 J-03 AC M10,C-Q LT-TS PIV CS-NI18-14 1NI-0167 A 1562-3.1 J-05 AC MTO.C-Q. LT-TS-PIV CS-N118
-14 1NI-0169 A 1562-3.1 J-06 AC MTO.C-Q LT-TS PIV CS-N118 141 i
1NI-0171 A 1562-3.1 J-07 AC MTO.C-Q LT-TS PIV CS-NI18 14 PIV CS-N119 14 1NI-0173A B 1562-3.1 1-12 B ST-Q 10 CS-NI8 1NI-0175 A 1562-3.1 1-08 AC MTO.C-Q LT-TS 1NI-0176 A 1562-3.1 H-08 AC MTO,C-Q LT-TS PIV CS-NI19 14 I
i INI-0178B B 1562-3.1 F-12 B ST-Q 10 CS-NI9 INI-0180 A 1562-3.1 F-06 AC MTO.C-Q LT-TS PIV CS-N119 14 1NI-0181 A 1562-3.1 D-05 AC MTO.C-Q LT-TS PIV CS-N119-14
{
1NI-0183B B 1562-3,0 G-03 B ST-Q 20 CS-nil 0
-1 INI-0184B B 1562-3.1 D-12 B ST-Q 60
'CS-Nill i-1NI-0185A B 1562-3.1 B-12 B ST-Q 1
60-CS-Nill INI-0332A B 1562-3,0 L B ST-Q 10 1NI-0333B B 1562-3,0 L-12 B - ST-Q 10 1NI-0334B B 1562-3.0 L-11 B ST-Q 10 1NI-0347 A 1562-1.0 I-07 C MTO-Q CS-NI13 14 1NI-0348 A
1562-1.0-F-07 'C MTO-Q CS-NI13 14 i
1NI-0349 A 1562-1.0 D-07 C MTO-Q CS-NI13 14 1NI-0354 A 1562-1.0 K-07 C MTO-Q i
CS-NI13 14-1NI-0430A B 1562-2.0 E-04 B ST-Q 60
-CS-N12 INI-0431B B 1562-2.0 J-04 B ST-Q 60 CS-NI2 1NI-0436 B 1562-2.1 G-11 AC MTC-Q LT-RF NIS MT-RF*
I s
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Page No.
16 04/11/90 Duke Power Company McGuire Nuclear Station l
PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL. FLOW FLOW CAT TEST-TEST RR
. STROKE TEST R
DIAGRAM COOR REQ 1=
REQ 2 TIME ALTERNATIVLS/. - L' (SEC)
REMARKS V
-15 CS-NV3 s
1NV-0002A A 1554-1.2 D-05 B ST-Q
-15 CS-NV3 INV-0007B B 1554-1.2 J-10 B ST-Q 10 CS-NV2' INV-0021A A 1554-1.2 E-03 B ST-Q 2
CS-NV4 1NV-0022 A 1554-l'.2 C-03 C MTO-Q CS-NV5 INV-0024B
'A 1554-1.2 D-06 B ST-Q 2
INV-0025B A' 1554-1.2 D-07
-B-ST-Q-2 1NV-0035A-B 1554-1.2 K B ST-Q 15
'14 1NV-0094AC B 1554-1.1 J-13 B ST-Q
^
10 CS-NV1 INV-0095B B 1554-1.1 H-13 -B ST-Q 10 CS-NV1 INV-0141A B 1554-2.0 B-08 B ST-Q 10 CS-NV7 INV-0142B-B '1554-2.0 B-07 B ST-Q 10 CS-NV7-1NV-0150B B 1554-2.0 F-02 B ST-Q 10 CS-NV12 12 l
1NV-0151A B 1554-2.0 G-02 B ST-Q
.10 CS-NV12 12 INV-0221A B 1554-3.1 H B ST-Q 10 CS-NV9 1NV-0222B B 1554-3.1 1-01 B~
.10
.CS-NV9 INV-0223 B 1554-3.1 1-02 C MTO.C-Q CS-NV15' 14' 1NV-0225 B 1554-3.1 F-05 C MTO.C-Q -
CS-NV14 14 1NV-0227 B 1554-3.1 E-06 C MTO.C-Q INV-0231 B 1554-3.1 F-10 C MTO.C-Q -
CS-NV14
.14 1NV-0233 B 1554-3.1 E-10 C MTO.C-Q INV-0244A B 1554-3.0 K-08 B-ST-Q 10 _ -CS-NV8 107.CS-NV8 INV-0245B B 1554-3.0 K-09 B ST-Q INV-0264 B 1554-3.1 J-10 C MTO-Q
'CS-NV11 INV-0265B B 1554-3.1 J-09 B ST-Q 10 CS-NV13 12 1NV-0411 C 1554-5.0 C-02 C MTO-Q NV4-RF#
12 1NV-0413 C 1554-5.0 B-02 C MTO-Q NV4
,RF#
12 INV-0457A B 1554-1.2 1-07 B ST-Q~
15' INV-0458A B 1554-1.2 J-07 B ST-Q
'15 INV-0459A 15 DELETED-14 i
1NV-0842AC B 1554-1.3 F-02 B-ST-Q 15 INV-0844 E 1554-1.3 F-05 C MTO-Q INV-0849AC B 1554-1.3 F-08 A ST-Q LT-RF 15 INV-1002 B 1554-1.3 F-10 AC MTO.C-Q LT-RF-NV1
,RF INV-1007 B.1554-1.3 F-13 C MTO.C-Q CS-NV6 1NV-1008 B 1554-1.3 F-13 C MTO.C-Q -
.CS-NV61 INV-1009 B 1554-1.3 F-14 C MTO.C-Q -
CS-NV6 1NV-1010 B 1554-1.3 F-14 C MTO.C-Q CS-NV6 1NV-1012C E 1554-1.3 F-12 B'
ST-Q 30 INV-1013C E 1554-1.3 F-12 B ST-Q 30 i
t
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t ii Page No.
21 04/11/90 EDuke. Power Company McGuire Nuclear Station.
i PUMP AND VALVE INSERVICE l
TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST-RR STROKE
- TEST R
DIAGRAM COOR REQ 1 REQ 2 TIME' ALTERNATIVES /
E-(SEC)
REMARKS V,
i
- MAIN STEAM TO AUX. EQUIPMENT 1SA-0005-
'B 1593-1.2
'F-04 C
MTO.C-Q -
14:
ISA-0006-B 1593-1.2 F-04 C MTO,C-Q
' 14' 1SA-0048ABC B 1593-1.2 E-04 B
.ST-Q 50 1SA-0049AB B 1593-1.2 F-02 B ST-Q 50 1
F i
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Page-No.
26 04/11/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE' INSERVICE TESTING PROGRAM-1 VALVE CL-FLOW FLOW CAT TEST TEST RR STROKE TEST R
DIAGRAM COOR REQ 1 REQ 2 TIME ALTERNATIVES /-
E (SEC)
REMARKS V;
DIESEL GENERATOR. STARTING AIR IVG-0061=
C 1609-4.0 K-02 a ST-Q 14 IVG-0062 C 1609-4.0 K-02 B ST-Q 14 IVG-0063 C 1609-4.0 H-02' B ST-Q
-14 IVG-0064 C 1609-4.0 1-02 B ST-Q-14-IVG-0065 C 1609-4.0 E-02 B ST-Q 14' IVG-0066 C'
1609-4.0 F-02 B ST-Q 14 IVG-0067 C 1609-4.0 C-02 B ST-Q 14' IVG-0068
-C 1609-4.0 C-02 B ST-Q-14 i
IVG-0115 C 1609-4.0 K-09' C MTO-Q IVG-0116 C 1609-4.0 H-09 C-MTO-Q IVG-0117-C 1609-4.0 F-09 C MTO-Q-IVG-0118 C 1609-4.0 C-09 C MTO-Q w
r-l J
T a
-~,a
Page No.
28 Duke' Power' Company-McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM l
3 VALVE-CL FLOW FLOW CAT TEST
-TEST RR ' STROKE
- TEST.
R-DIAGRAM COOR REQ 1 REQ 2
-TIME. ALTERNATIVES /~
E 4
(SEC)
REMARKS
- V'.
j i
- CONTAINMENT PURGE VENTILATION IVP-0001B B 1576-1 1-06 A LT-TS
~14.
i IVP-0002A B 1576-l' I-07 A LT-TS.
14
. 1VP-0003B B 1576-1 K-06 A'
LT-TS
- 14
- 1VP-0004A B'^1576-1 K-07 A'
~LT-TS-14 IVP-0006B B 1576-1 E-06A LT-TS 14-IVP-0007A B 1576-1 E-07 A LT-TS 14
~14 1
- 1VP-0008B B 1576-1 D-06 A LT-TS.
l IVP-0009A B 1576-1 D-07 A LT-TS 141 IVP-0010A-B-
1576-1 J-08 A LT-TS
'14 IVk-0011B B '1576-1 J-09 A LT-TS 14' IVP-0012A B 1576-1 1 A.
LT-TS 14 '-
IVP-0013B B 1576-1 I-09 A LT-TS 14 IVP-0015A B 1576-1 F-08 A LT-TS 14 IVP-0016B B 1576-1 F-09 A LT-TS.
14 IVP-0017A B 1576-1 B-07 A LT-TS
- 14 IVP-0018B B 1576-1 B-06 A LT-TS 14 _'
IVP-0019A B 1576-1 B-08 A LT-TS 14 IVP-0020B B 1576-1 B-09 A LT-TS 14 b
(
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I 9
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- Fage No. 33 04/11/90 Duke Power Company McGuire. Nuclear Station PUMP.AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW
. FLOW CAT TEST TEST RR STROKE
-TEST.
R DIAGRAM COOR
' REQ 1 REQ 2 TIME ALTERNATIVES /
E (SEC)-
REMARKS
,V
- LIQUID WASTE RECYCLE 1RL-0001B
-B 1565-1.1 L-11 A ST-Q LT-RF" 10
- 1WL-0002A B '1565-1".1 K-13 A'
ST-Q LT-RF 10 1WL-0024 B 1565-1.1 J-14 AC MTC-Q LT-RF WL2-MT-RF*"
IWL-0039A.
B 1565-1.1
'J-05 A
ST-Q LT-RF 10 IWL-0041B B 1565-1.1 K-05 A ST-Q-LT-RF 10 IWL-0064A B 1565-1.0 J-03 A ST-Q-
.LT-RF 15 t
1WL-0065B B 1565-1.0 K-05 A ST-Q LT-RF 15
.i IWL-0264 B 1565-1.0 J-02 AC LT-RF y
PASSIVE IWL-0321A-B 1565-7.0 H-07 A'
ST-Q LT-RF 15 1
1RL-0322B B 1565-7.0 1-06 A ST-Q LT-RF 15 R
IV 0385 B 1565-7.0 H-07 AC MTC-Q LT-RF WL3 MT-RF*
IWL-0466 DELETED 14
- )
1WL-1301B B.
1565-1.0 G-03 A ST-Q LT-RF 10
~
IWL-1302A A 1565-1.0 E-04 A ST-Q LT-RF 10
=f i
d 1
O
McGUIRE - UNIT 1
- l RELIEF / JUSTIFICATION:
RR-CA2' VALVE:
ICA-8, ICA-10, ICA-12 FLOW DIAGRAM:
MC-1592-1.1 CATEGORY:
C CLASS:
C FUNCTION:
Auxiliary Feedwater Pump Suction check valves to prevent diversion of assured auxiliary feedwater source.
TEST REQUIREMENT:
Full stroke exercise quarterly BASIS:
These valves cannot be tested to.close without contaminating the Auxiliary Feedwater System with raw service water. These valves will not be tested during i
cold shutdown because disassembly is required.
ALTERNATE TESTING:
Valves'will be sample disassembled each refueling:
l outage to verify valve closure capability, i
i i
New Page Revision 14 l
McGUIRE -1 UNIT 1.
RELIEF / JUSTIFICATION:
RR-FW1 (deleted per Rev.' 14; see CS-FW2)
VALVE:
1FW-28 l
i l
M 4
.i.
4 Revision 14 0
i McGUIRE - UNIT 1 k
RELIEF / JUSTIFICATION:
RR-ND1 (Deleted per Rev 14; see CS-ND4)
VALVE:
IND-70 i
l l-1; l
1 I
i l
-t
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1 Revision 14 s
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1
' NcGUIAE - UNIT 1 RELIEF / JUSTIFICATION:
RR-N02 (Deleted per Rev.14; see C$-N05)
VALVE:
IND-71 d
l i
i e
i 6
Revision 14 i
4 9
I McGUIM - IMIT 1 RELIEF / JUSTIFICATION:
RR-NO3 (Deleted per Rev.14; see CS-N06)
VALVE:
IND-8, IND-23 h
. i I
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1 Revision 14
)
e
+
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.~_,F
McGUIRE - WIT 1 RELIEF / JUSTIFICATION:
RR-nil (Deleted par Rev. 14; see CS-NI13)
VALVE:
1NI-15, 1NI-354, 1NI-17, 1NI-347, 1NI-19, 1NI-348, 1NI-21, 1NI-349 q
l t
J t
i Revision 14
~
m
4 5
McGUIRE, - UNIT 1 i
RELIEF /JUST!FICATION:
RR-NI2 (Deleted per Rev.14, see CS-N114) l VALVE:
IN!-12 i
)
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Revision 14-f 4
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McGUIRE - UNIT 1 1
i j
RELIEF / JUSTIFICATION:
RR-NI4
]
VALVE:
1NI-81, 1NI-70, 1NI-59, 2NI FLOW DIAGRAM:
MC-1562-2.0, MC-1562-2.1 q
CATEGORY:
A,C CLASS:
A i
FUNCTION:
Opens on flow from the NI cold leg accumulator to the g4 Reactor Coolant System.
Reactor Coolant Boundary Valve.
I TEST REQUIREMENT:
Full stroke exercise quarterly and leak tested per 14 Technical Specifications.
BASIS:
Valves cannot be full or partial stroked during power operation since the accumulator pressure is $600 psig 1
i and cannot overcome RCS pressure.
Valves will not be 14 i
tested during cold shutdown since disassembly isr required.
Disassembly would render one train of RHR 1
inoperable for an extended time period.
ALTERNATE TESTING:-
Valves will be partial stroked during cold shutdown, but not more often than once per nine months.
Valves will be full stroked at refueling by sample disassembly.
Valves will be leak tested in accordance 34 with Technical Specification 4.4.6.2.2.
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i Revision 14 4
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McGUIRE - UNIT 1 RELIEF / JUSTIFICATION:
RR-NI6 VALVE:
INI-82, 1NI-71, 1NI-60, 1NI-94 FLOW DIAGRAM:
MC-1562-2.0, MC-1562-2.1 CATEGORY:
A,C CLASS:
A FUNCTION:
Open on flow from the cold leg accumulator or the ND 34 system to the Reactor Coolant system.
Roactor Coolant Boundary valve.
TEST REQUIREMENT:
Full stroke exercise quarterly and leak test per 34 Technical Specifications.
BASIS:
Valves cannot be full'or partial stroked during power operation since a driving head to force the valves open does not exist.
Instrumentation is not present to measure the flow through individual valves.. Valves will not be tested during cold shutdown since 34 disassembly is required.
Disassembly would render one train of RHR inoperable for an extended time period.
ALTERNATE TESTING:
Valves will be partial stroked during cold shutdowns on a 9-month frequency and leak tested per Tech Spec 4.4.6.2.2.
The valves will be full stroke 14 exercised at refueling by sample disassembly.
Revision 14
McGUIRE - WIT 1 RELIEF / JUSTIFICATION:
RR-NI7 (Deleted per Rev. 14; see CS-NI15)
VALVE:
- 4 i
Revision 14
McGUIRE - UNIT 1 RELIEF / JUSTIFICATION:
RR-NI8 (Deleted per Rev.14; see CS-N116)
VALVE:
1 I
Revision 14
McGUIRE - UNIT 1 RELIEF / JUSTIFICATION:
F.R-NI9 (Deleted per Rev. 14; see CS-NI17)
VALVE:
1NI-128, 1NI-159, 1NI-160, 1NI-156, 1NI-124, 1NI-157
'l i
i i
Revision 14 l
McGUIRE - IBi!T 1 I
RELIEF / JUSTIFICATION:
RR-nil 0 (Deleted per Rev. 14; see CS-NI18)
VALVE:
1NI-165, 1NI-167, 1NI-169, 1NI-171 i
Revision 14 i
McGUIRE - UNIT 1 RELIEF / JUSTIFICATION:
RR-Nill (Deleted per Rev. 14; see C3 NI19)
VALVE:
1NI-180, 1NI-181, 1NI-175, 1NI-176 v
l 1
Revision 14 4
e
.... - - _.. -._~-
McGUIRE - UNIT 1 RELIEF / JUSTIFICATION!
RR-N112 (Deleted per Rev. 14; see CS-NI20) l l
VALVE:
INI-129, 1NI-125, 1NI-134, 1NI-126 l
i 9
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f 4
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4 Revision 14 1
C McGUIRE
, UNIT 1
[
RELIEF / JUSTIFICATION:
RR-NS1 VALVE:
INS-30, INS-33, INS-16, INS-13, INS-46, INS-41 FLOW DIAGRAM:
MC-1563-1.0 P
CATEG0RY:
C CLASS:
B FUNCTION:
Open on flow from the Containment Spray Pumps TEST REQUIREMENT:
Verify proper valve movement once per three months.
IWV-3522.
BASIS:
Full stroke exercising of these check valves is not practical since there is no external indication of disk movement.
Full stroke exercising would require for the pumps and spray nozzles to be activated which would require a large scale clean up effort.
Valves will not be tested during cold shutdown since 14 disassembly is required, ALTERNATE TESTING:
These valves will be verified to fully c/c1w each refueling by sanple disassembly.
All valves will be 14 partial stroked during cold shutdown, but not more often than once per nine months, and-following disassemoly u
i
)
Revision 14 8
Y
T
' ' ' ~ ' ' ~'
McGUIRE - UNIT 1 RELIEF /JUSTIFICAT10d:
RR-NV2 (Deleted per Rev. 14; see CS-NV14)
VALVE:
INV-225, 1NV-231 l
1 l.
i i
l Revision 14 1
l 1
McGUIRE - UNIT 1 RELIEF / JUSTIFICATION:
RR-NV3 (Deleted per Rev.14; see CS-NV15).
VALVE:
INV-223
=
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I i
i T
Revision 14 i
o
w..
McGUIRE - WIT 1 RELIEF / JUSTIFICATION:
RR-NV4 VALVE:
INV-411, 1NV-413 FLOW DIAGRAM:
MC-1554-5.0 CATEGORY:
C CLASS:
C FUNCTION:
P.otect both units' Boric Acid Tanks from being diluted by water from the NV pump suction. Open to.
14 provide alternate boron path to NV pump suction.
TEST REQUIREMENT:
Full stroke quarterly BASIS:
There is not instrumentation to measure the flowrate through these valves.
The valves do not have any external means of verifying their position. The 14 valves will not be tested during cold shutdown since disassembly is required.
To open INV-411 (Unit 1) or INV-413 (Unit 2) Boric Acid would be injected into the RCS of the respective unit.
At power this would cause a reactor transient, j
ALTERNATE TESTING:
Thes,e valves will be disassembled for inspection.
INV-411 will be inspected during Ur.it I refueling outages and 1NV-413 will be inspected during Unit 2 refuelings.
The valves will be partial stroked during 14 respective unit cold shutdowns, but not more often than once per nine months.
4 Revision 14 1
.a
McGUIRE - WIT 1 i
j RELIEF / JUSTIFICATION:
RR-SA1 (Deleted per Rev. 14)
VALVE:
ISA-3, 1SA-6 i
b a
i f
a F
Revision 14
-r
McGUIRE - UNIT 1 j
RELIEF / JUSTIFICATION:
RR-VB1 VALVE:
IV8-50 FLOW DIAGRAN:
MC-1605-3.1 l
CATEGORY:
A,C CLASS:
B FUNCTION:
Provide containment isolation m
TEST REQUIREMENT:
Verify proper valve movement once per three months.
l BASIS:
1V8-50 is inside containment.
Closure can only be i
verified by a local leak rate test.
To perform a leak test every three months would result in unnecessary radiation exposure.
ALTERNATE TESTING:
Valve will be verified to close by leak test performed 34 in accordance with Appendix J.
J I
i 4
e 4
t Revision 14
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1 McGUIRE - UNIT 1 RELIEF /JUST!FICATION:
RR-VG1 (Deleted per Rev. 14)
VALVE:
1VG-61, IVG-62, IVG-63, IVG-64, IVG-65, IVG-66, IVG-67, IVG-68 9
i
~
Revision 14 i
e i
McGUIRE - UNIT 1 i
?
I RELIEF / JUSTIFICATION:
RR-VP1 (Deleted per Rev. 14)
VALVE:
1VP-18, IVP-2A, IVP-38, IVP-4A, IVP-68, IVP-7A, IVP-88, IVP-9A, IVP-10A, IVP-118, IVP-12A, IVP-138, IVP-15A, IVP-168, IVP-17A, IVP-188, IVP-19A, IVP-208 l
i i
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4 Revision 14 L
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McGUIRE - UNIT 1 RELIEF / JUSTIFICATION:
RR-WL1 (Deleted per Rev. 14)
VALVE:
1WL-466 E
=
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Revision 14 m.
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1 i
McGl' IRE - UNIT 1 RELIEF / JUSTIFICATION:
CS-FW2 i
VALVE:
1FW-28 FLOW DIAGRAM:
MC-1571-1.0 CATEGORY:
C CLASS:
B FUNCTION:
Prevents reverse flow to the FWST and prevents pressurizing the FWST.
1 i
TEST REQUIREMENT:
Full stroke exercise quarterly.
J BASIS:
1FW-28 cannot be full stroked during power operation since the only full flow path is into the RCS by the Residual Heat Removal Pumps (NO).
The NO Pumps cannot overcome RCS pressure.-
j ALTERNATE TESTING:
Valve will be full stroke exercised at cold shutdown l
but not more often than once per nine months, and partial stroked quarterly.
?
1 i
e New Page Revision 14 1
1
~.
McGUIRE - UNIT 1 RELIEF / JUSTIFICATION:
CS-ND4 VALVE:
IND-70 FLOW DIAGRAM:
MC-1561-1.0 CATEGORY:
C CLASS:
8 FUNCTION:
RHR to SI Suction Check TEST REQUIREMENT:
Full stroke exercise quarterly.
BASIS:
IND-70 cannot be full stroked during power operation since the only full flow path is into the RCS and this can only be performed during cold shutdowns.
1N070 cannot be seat leak tested during power operation since the required valve lineup cannot be made without putting 2000 ppe boron water from the RWST into the chemical and volume control pump suction.
Additionally, with the RCS at normal operating i
pressure, the seat leakage cannot be identified.
1 ALTERNATE TESTING:
IND-70 will be full stroke exercised cnd seal leak tested at cold shutdown, but not more often than once per nine months.
IN070 will be partial stroked quarterly.
4 l
New Page Revision 14
McGUIRE - UNIT 1 I
RELIEF / JUSTIFICATION:
CS-N05 VALVE:
IND-71 FLOW DIAGRAM:
MC-1561-1.0 CATEGORY:
C CLASS:
B FUNCTION:
RHR to SI Suction Check TEST REQUIREMENT:
Full stroke exercise quarterly.
BASIS:
Valve cannot be full stroked during power operation since the only full flow path is 'into the RCS and this' can only be done at refueling.
IND-71 cannot be partial stroked during power since the required valve.
lineup would render both trains of safety injection inoperable.
IND71 cannot be leak tested with the RCS at normal operating pressure because the seat leakage cannot be identified.
ALTERNATE TESTING:
Valve will be full stroked at cold shutdown, but not more often tha once per nine months.
l I
l i
4 New Page Revision 14
]
McGUIRE - UNIT 1 4
RELIEF /JUST!FICATION:
CS-ND6 VALVE:
IND-8, IND-23 FLOW DIAGRAM:
MC-1561-1.0 CATEGORY:
C CLASS:
8 FUNCTION:
Prevents reverse flow through the ND Pumps TEST REQUIREMENT:-
Full stroke exercise quarterly.
BASIS:
IND-8 and IND-23 cannot be fully stroked during power operation since the only full flow path is into the RCS and the ND Pumps cannot overcome RCS presure.
The-ND Pump recirc line is not large enough to accomodate full design flow.
ALTERNATE TESTING:
Valves will be full stroke exercised at cold shutdown, but not more often than once per nine months. Valve will be partial stroked quarterly.
i The opposite train valves will be tested closed during quarterly pump testing except when the opposite train of ND is in service.
4 i
l i
New Page J
Revision 14
McGUIRE - UNIT 1 k
i RELIEF / JUSTIFICATION:
CS-NI13 i
VALVE:
IN I-15, 1NI-354, 1NI-17, 1NI-347, 1N I-19, 1N I-348, 1NI-21, 1NI-349 FLOW DIAGRAM:
MC-1562-1.0 i
CATEGORY:
C l
CLASS:
A FUNCTION:
Provides safety injection flow path.
TEST REQUIREMENT:
Full stroke exercise quarterly.
BASIS:
Full or partial stroke during power operation would l
result in. thermal shock to injection nozzles.
ALTERNATE TESTING:
Valve will be full stroked at cold shutdown, but not more often than once per nine months.
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j McGUIRE - UNIT 1 I
RELIEF / JUSTIFICATION:
CS-NI14 4
VALVE:
1NI-12 1
FLOW DIAGRAM:
MC-1562-1.0 CATEGORY:
C CLASS:
B I
FUNCTION:
Provides safety injection flow path
{
TES1 REQUIREMENT:
Full stroke exercise quarterly.
)
i
~
BASIS:
Full or partial stroke during power operation would l
result in thermal shock to injection nozzles.
ALTERNATE TESTING:
Valve will be full stroked at cold shutdown, but not more often than once per nine months.
)
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l New Page Revision 14 P
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McGUIRE - INIT 1
)
RELIEF / JUSTIFICATION:
CS-NI15 a
VALVE:
1NI-101 FLOW DIAGRAM:
MC-1562-3.0 CATEGORY:
C
,j CLASS:
8 FUNCTION:
Opens on flow from FWST to SI.
Checks flow if RHR is supplying SI suction pressure.
1 i
TEST REQUIREMENT:
Full stroke exercise quarterly.
I BASIS:
Valve cannot be full stroked at power since the SI j
pumps cannot overcome RCS pressure.
J ALTERNATE TESTING:
Valve will be partial stroked quarterly and full 1
stroked and leak tested at cold si.utdowns, but not 4
I more often than once every nine months.
i I
k L
i New Page l
Revision 14
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i 1
l I
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i McGLTIRE - UNIT 1-RELIEF / JUSTIFICATION:
CS-NI16 VALVE:
INI-116, 1NI-148 FLOW DIAGRAM:
MC-1562-3.0 4
CATEGORY:
C t
CLASS:
B 1"
FUNCTION:
Opens to flow.from the NI Pump (s). ' Check flow from opposite train..
TEST REQUIREMENT:
Verify proper valve movement once per three months.
BASIS:
Valves cannot be full or partial stroked during power operation since the safety-injection pumps cannot:
overcome RCS pressure.
~
ALTERNATE TESTING:
Valves will be cycled open during cold shutdown, but' not more often than once per nine. months.
Valves will be checked closed quarterly..
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New Page Revision 14 w
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- McGUIRE - UNIT 1 q
s 1
RELIEF / JUSTIFICATION:
CS-NI17-o VALVE:
1NI-128, 1NI-159, 1NI-160, 1NI-156, 1NI-124, 1NI-157 FLOW DIAGRAM:
MC-1562-3.0 CATEGORY:
A, C CLASS:
B FUNCTION:
Open-on flow from the SI pumps to the RCS hot-legs.
Reactor Coolant Boundary valve.
i TEST REQUIREMENT:.
Verify proper valve movement once per three months ~and
- leek test per Technical Specifications.
l BASIS:
Valves cannot be full or partial stroked during power
' operation,since the safety injection pumps cannot discharge into.the RCS at operating pressure; ALTERNATE TESTING:
Valves will be verified to fully cycle during cold shutdown by acoustic emission monitoring, but no more often than,once per nine months.
Valves will be leak tested in accordance with. Tech Spec 4~4.6.2.2.
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l' McGUIRE
'JNIT 1 t
RELIEF / JUSTIFICATION:
CS-N!18 VALVE:
1NI-165, 1NI-167, 1NI-169, 1NI-171 1
-FLOW DIAGRAM:
MC-1562-3.1 CATEGORY:
A,C CLASS:
A FUNCTION:
SI discharge check vaives to RCS cold legs. -Reactor:
q Coolant System Boundary valves.
.{
TEST REQUIREMENT:
Full stroke exercise quarterly and leak test per:
?
Technical Specifications, j
BASIS:
Valves cannot be cycled'during power operation since -
d the SI pumps cannot overcome RCS pressure to permit flow through the valves.
ALTERNATE TESTING:
Valves will be fully cycled during cold shutdown, but not more often than once per:nine months.~ Valves will be leak tested in accordance with Tech Spec 4.4.6.2.2.
- i i
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e i
4 1
New Page Revision 14 1
Ji R v
J' s.s i
.- 1 McGUIRE - UNIT.N n
RELIEF / JUSTIFICATION:
CS-NI19 VALVE:
-1NI-180, 1NI-181, 1NI-175, 1NI-176 f
FLOW DIAGRAM:
MC-1562-3.1 CATEGORY:
'A,C CLASS:-
A FUNCTION:
Opens on flow'from the ND to the RCS.
Reactor Coo.lant Boundary valve.
i TECT REQUIREMENT:
Valve movement once per three months and leak. test per.
Technical Specifications.
BASIS:
ThedischargEpressureoftheNDPumps'isnot
,4 sufficient for opening-the valve to the Reactor Coolant System during power operation.
ALTERNATE TESTING:
Valve will be verified to fully' cycle'during cold i
shutdown by acoustic emission monitoring, but not more often than once per nine months.
Valves'will be leak t
tested in accordance with Technical Specifications.
L l
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New Page Revision 14 e
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{
I
.McGUIRE - UNIT 1-F 1
RELIEF / JUSTIFICATION:
CS-NI20 VALVE:
INI-129,'1NI-125, 1NI-134,'1NI-126 i
FLOW DIAGRAN:
MC-1562-3.0 CATEGORY:
A, C CLASS:
A.
l i
FUNCTION:
Opens on flow from the ND system to the NC' Hot Legs.
i l
Reactor Coolant Boundary Valve.
TEST REQUIREMENT:
Verify proper valve movement once per three months.end 1eak test per Technical Specifications.
BASIS:
N0 pumps do not develop enough ' discharge pressure to
overcome RCS pressure at power' operation..
ALTERNATE TESTING:
Valve will be verified to fully cycle during cold L
shutdown by acoustic emission monitoring. but not more often than once per nine months.
Valves will'be leak j
tested in accordance with Technical Specifications.
l Y
V
, New Page Revision 14 t
(
7,._
McGUIRE - UNIT 1 RELIEF / JUSTIFICATION:
C5-NV10 (Deleted per Rev 14)
VALVE:
INV-459A
- I 1
i I
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Revision 14
McGUIRE a. UNIT 1 RELIEF / JUSTIFICATION:
CS-NV14 VALVE:
INV-225, 1NV-231 FLOW DIAGRAM:
MC-1554-3.1 CATEGORY:
C CLASS:
-B FUNCTION:
Opens on flow from the Centrifugal. Charging. Pump (s).
TEST REQUIREMENT:
Verify proper valve. movement every three montta.
BASIS:
Valve cannot be -fulls stroke' exercised 'during power :
l operation because this-would resultiin an increase'in-the RCS boron inventory and could result in a plant; shutdown.
To fully stroke INV-225 and 1NV-231 the-full centrifugal charging pump flow.would have to go through the valves. - The reactor coolant system.
letdown capacity-would not be enough to maintain volume control tank level.
The additiona1Lflow would have to come-from the refueling water storage tank which has a boron. concentration of.2000 ppe, i
ALTERNATE TESTING:
Valve will be full stroked during cold. shutdown, but
{
not more often than once per nine months,-and partial stroked with normal use.
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McGUIRE - UNIT'1 4
l RELIEF / JUSTIFICATION:
CS-NV15 VALVE:
-1NV-223-FLOW DIAGRAM:
,MC-1554-3.1 CATEGORY:
C 1
?
CLASS:
B g
FUNCTION:
Opens on fiow alignment from FWST.
Closes to ensure sufficient centrifugal charging pump suction pressure-
- when=RHR is used as a suction source.
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TEST REQUIREMENT:
Verify proper valve movement every three months.
BASIS:
Testing of these valve requires opening INV-i?lA or 1NV-2228.
Failure of one of-these valves in the open position aligns the FWST to the suction of the charging pumps =with no means of isolating the flow path.
This would result in an increase in boron-inventory in.the RCS and could result in a plant
- r shutdown.
ALTERNATE TESTING:
Valve will be full stroked and :eak tested during cold shutdown, but not more often than once per nine months.
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