ML20138H386
| ML20138H386 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/29/1997 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20138H378 | List: |
| References | |
| PROC-970429, TAC-M94530, NUDOCS 9705070160 | |
| Download: ML20138H386 (16) | |
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NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION 1
l THIRD INTERVAL INSERVICE TESTING PROGRAM REVISION 1.2 J
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9705070160 970429 PDR ADOCK 05000298 P
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j COOPER NUCLEAR STATION THIRD INTERVAL-l INSERVICE TESTING PROGRAM TABLE OF CONTENTS l
I 1.
INTRODUCTION PAGE l
A.
Basis for the Program 1
B.
The Third Ten Year Interval 2
C.
Applicable ASME Code 2
D.
IST Program Scope 2
E.
IST Basis Document 3
j F.
Testing Frequency 3
G.
Skid-Mounted Components and Component Subassemblies 3
H.
Program Description 4
11.
TESTING PROGRAM FOR PUMPS l
A.
Description 1
B.
Allowable Ranges of Test Quantities 1
C.
Instrumentation 1
D.
Reference Values 2
l III.
PUMP
SUMMARY
LISTING l
A.
Notations 1
B.
Pump Summary Tables 2
C.
Pump Relief Requests 11 D.
Augmented Pump Relief Requests 19 IV.
TESTING PROGRAM FOR VALVES A.
Description 1
l B.
Cold Shutdown Testing 1
l C.
Limiting Values of Full-Stroke Time 1
D.
Reference Values 2
E.
Instrumentation Requirements 2
i F.
Active / Passive Valves 2
G.
Fail-Safe Testing 3
l-H.
Valve Position Indication Verification 3
I.
Water Sealed Valves 3
J.
Check Valve Testing 4
K.
Relief Valve Testing 4
L.
Vacuum Breaker Testing 5
Revision 1.2 Page i 1
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COOPER NUCLEAR STATION THIRD INTERVAL I
INSERVICE TESTING PROGRAM V.
VALVE
SUMMARY
LISTING PAGE A.
Notations 1
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B.
Valve Summary Tables 4
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C.
Cold Shutdown Justifications 80 i
D.'
Refueling Outage Justifications 94 E.
Valve Relief Requests 117 F.
Augmented Valve Cold Shutdown Justifications 136
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G.
Augmented Valve Refueling Outage Justifications 144 II.
Augmented Valve Relief Requests 151 t.
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i Revision 1.2 Pageii
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COOPER NUCLEAR STATION TIIIRD INTERVAL i
INSERVICE TESTING PROGRAM i
C.
Pump Relief Requests RR No.
Description Notes RP CS, RIIR, IIPCI, RCIC Pumps Suction Pressure 1
RP-02 CS, RIIR, IIPCI, RCIC, SW, and SWB Pumps Instrument 1
Accuracy RP-03 REC Pumps Flowrate Gauge Range 1
RP-04 RCIC Pump / Turbine Speed Measurement Range 1
RP-05 SW Pumps Differential Pressure Notes:
1 Approved by NRC letter dated February 19,1997 (TAC NO. M94530) l t
i Revision 1.2 Section III Page 11 of 21 i
COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE
SUMMARY
TABLES SYSTEM: REACTOR CORE ISOLATION COOLING (RCIC)
P&ID ISI IST VALVE VALVE ACT TEST TEST VALVE CIC P&ID COOR CLASS CAT SIZE TYPE TYPE RQhIT FREQ POS RCIC-CV-21CV 2M3 117 2
C 2
CK-P SA C
PSO Q
RCIC CONDENSATE PUh1P FSO RF DISCIIARGE, ROJ-17 FSC RF RCIC-CV-22CV 2N3 E10 2
C 1 1/2 CK-L SA C
VBT RF RCIC VACUUhl BREAKER. RV-14 RCIC-CV-23CV 2043 E10 2
C i 1/2 CK-L SA C
VBT RF RCIC VACUUh1 BREAKER. RV-14 RCIC-CV-24CV 2M3 E10 2
C I 1/2 CK-L SA C
VBT RF RCIC VACUUh1 BREAKER. RV-14 RCIC-CV-25CV 2m3 E10 2
C 11/2 CK-L SA C
VBT RF RCIC VACUUh1 BREAKER. RV-14 RCIC-CV-26CV 2043 C9 1
A/C 4
CK-S SA O
U-l RF INJECTION CilECK VALVE, CSJ4)2 FSO CS FSC CS PIT 2Y RCIC-h10V-h1015 2041 D6 1
A 3
GT h10 0
U-l RF RCIC STEAh11NBOARD ISOLATION FSC Q
PIT 2Y RCIC-hlOV-51016 2041 D7 1
A 3
GT A10 0
U-l RF RCIC STEAh! OUTBOARD FSC Q
ISOLATION PIT 2Y i
Resision 1.2 Section V Page 50 of 155
COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE
SUMMARY
TABLES SYSTEM: STANDBY GAS TREATMENT (SGT)
VALVE CIC P&lD P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES! DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ SGT-AOV 2037 C7 A
B 10 BTF AO C
FSO Q
SGT UNIT A DISCIIARGE
- DPCV546, FST Q
DIFFERENTIAL PRESSURE PIT 2Y CONTROL SGT-AOV-2037 E7 A
B 10 BTF AO C
FSO Q
SGT UNIT B DISCilARGE DPCV546B FST Q
DIFFERENTIAL PRES 5URE PIT 2Y CONTROL SGT-CV-14CV 2037 C6 A
C 10 CK-D SA C
PSO Q
SGT UNIT A FAN EXIIAUST, FSO CS ACSJ-05 FSC CS SGT-CV-15CV 2037 G6 A
C 10 CK-D SA C
PSO Q
SGT UNIT B FAN EXIIAUST.
Revision 1.2 Section V Page 77 of 155
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COOPER NUCLEAR STATION l
TIlIRD INTERVAL i
INSERVICE TESTING PROGRAM E.
Valve Relief Requests t
i RR No.
Descrintion Notes RV-01 liot Shutdown Component Testing 1
RV-02 CRD-AOV-CV126, CRD-AOV-CV127, and CRD-CV-2 114CV (typical of 137) Exercising By Scram Testing RV-03 CRD-CV-115CV (typical of 137) Testing to the Closed 2
Position RV-04 CRD-CV-138CV (typical of 137) Test Method 2
RV-05 CRD-SOV-SO120, SO121, S0122, and SO123 (Typical 2
of 137) Test Method RV-06 CS-CV-12CV, CS-CV-13CV, CS-CV-14CV, and CS-CV-15CV Testing to the Closed Position l
RV-07 IIPCI-CV-18CV and 19CV Testing to the Closed Position RV-08 IIPCI-SOV-SSV64 and SSV87 Disassembly Testing 3
Frequency RV-09 MS-RV-71 ARV to 71HRV Exercising Testing Frequency 3
RV-10 Excess Flow Check Valves Testing Per Technical 4
Specifications RV-11 RCIC-CV-18CV and 19CV Testing to the Closed Position RV-12 RIIR-CV-18CV,19CV,24CV, and 25CV Testing to the Closed Position RV-13 SW-MOV-MO89A and MO89B Testing Relief 3
l RV-14 IIPCI-CV-24CV, 25CV, 26CV, 27CV, RCIC-CV-22CV, l
23CV, 24CV, and 25CV Testing Relief l
Notes:
i-1 NRC Approval not required (TAC NO. M94530)
Revision 1.2 Section V Page 117 of 155 4
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I COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM i
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- Approved by NRC letter dated February 19,1997 (TAC NO. M94530) 3 Approved for one year by NRC letter dated February 19,1997 (TAC NO.
M94530).
4 Acceptable per OM-10, NRC approval not required (TAC NO. M94530)
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i Revision 1.2 Section V Page 118 of 155
COOPER NUCLEAR STATION TIllRD INTERVAL INSERVICE TESTING PROGRAM RELIEF REQUEST RV-06 VALVE:
CS-CV-12CV, CS-CV-13CV, CS-CV-14CV, and CS-CV-15CV CLASS:
2, A (outboard)
CATEGORY:
C FUNCTION: Core Spray (CS) Loop A and Loop B pressure maintenance check valves from the condensate supply system. These valves open to maintain the Core Spray system solid and close to prevent diversion of core spray How.
REQUIRED OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally TESTS:
every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.
BASIS FOR These valves are normally closed check valves (with two in series). The inboard RELIEF:
valve is essential (safety related). The redundant outboard valve is non-essential.
The valves are the same make and model number and met the same quality assurance requirements at the time they were installed. They open as necessary to keep the CS system in a solid standby condition, which is not a safety function.
When the CS pumps start, these valves close to ensure maximum flow to the reactor. These valves do not perform a function which requires leakage to be limited to a specified amount.
Only one valve is required to close to prevent diversion of flow as determined and documented in accordance with CNS safety classification requirements. However, the current system design does not allow independent testing to ensure both valves have closed. Thus both valves will be tested together. When a CS Pump is started, should both valves fail to close, a relief valve would lift or a pressure sensor would alarm on the condensate supply side of the valves.
ALTERNATE TEST:
The check valves in each loop will be tested closed simultaneously to assess the operational readiness of each pair of valves. Should the acceptance criteria be exceeded, both valves will be declared inoperable until they are repaired or replaced as necessary.
Revision 1.2 Section V Page 125 of 155 m
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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM I
1 RELIEF REQUEST RV-07
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VALVE:
HPCI-CV-18CV and IIPCI-CV-19CV p
. CLASS:
2, A (outboard)
CATEGORY:
C
- FUNCTION: High Pressure Coolant Injection (IIPCI) pressure maintenance check valves from I
the condensate supply system. These valves open to maintain the HPCI system solid and close to prevent diversion of HPCI injection flow, i
REQUIRED OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally j
TESTS:
every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.
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BASIS FOR These valves are normally closed check valves (with two in series), The inboard RELIEF:
valve is essential (safety related). The redundant outboard valve is non-essential.
i The valves are the same make and model number and met the same quality
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}j assurance requirements at the time they were installed. They open as necessary to keep the HPCI system in a solid standby condition, which is not a safety function.
When the HPCI starts, these valves close to ensure maximum flow to the reactor.
1 These valves do not perform a function which requires leakage to be limited to a
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specified amount.
j Only one valve is required to close to prevent diversion of flow as determined and documented in accordance with CNS safety classification requirements. However, I
the current system design does not allow independent testing to ensure both valves have closed. Thus both valves will be tested together. When HPCI is started, i
should both valves fail to close, a relief valve would lift or a pressure sensor would j
alarm on the condensate supply side of the valves.
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ALTERNATE TEST:
The check valves will be tested closed simultaneously to assess the operational l
readiness of the pair of valves. Should the acceptance criteria be exceeded, both j
valves will be declared inoperable until they are repaired or replaced as necessary.
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Revision 1.2 Section V Page 126 of 155 I
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COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAM RELIEF REQUEST RV-11 VALVE:
RCIC-CV-18CV and RCIC-CV-19CV CLASS:
2, A (outboard)
CATEGORY:
C FUNCTION: Reactor Core Isolation Cooling (RCIC) pressure maintenance check valves from the condensate supply system. These valves open to maintain the RCIC system solid and close to prevent diversion of RCIC injection flow.
REQUIRED OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally TESTS:
every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.
BASIS FOR These valves are nonnally closed check valves (with two in series). The inboard RELIEF:
valve is essential (safety related). The redundant outboard valve is non-essential.
The valves are the same make and model number and met the same quality assurance requirements at the time they were installed. They open as necessary to keep the RCIC system in a solid standby condition, which is not a safety function.
I When the RCIC starts, these valves close to ensure maximum flow to the reactor.
l These valves do not perform a function which requires leakage to be limited to a specified amount.
Only one valve is required to close to prevent diversion of flow as determined and l
documented in accordance with CNS safety classification requirements. Ilowever, the current system design does not allow independent testing to ensure both valves have closed. Thus both valves will be tested together. When RCIC is started, should both valves fail to close, a relief valve would lift or a pressure sensor would alarm on the condensate supply side of the valves.
ALTERNATE TEST:
The check valves will be tested closed simultaneously to assess the operational readiness of the valves. Should the acceptance criteria be exceeded, both valves will be declared inoperable until they are repaired or replaced as necessary.
Revision 1.2 Section V Page 131 of 155
COOPER NUCLEAR STATION 1
TIIIRD INTERVAL
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INSERVICE TESTING PROGRAM RELIEF REQUEST RV-12 VALVE:
RIIR-CV-18CV, RIIR-CV-19CV, RIIR-CV-24CV, and RIIR-CV-25CV CLASS:
- 2. A (outboard)
CATEGORY:
C FUNCTION: Residual IIeat Removal (RIIR) Loop A and Loop B pressure maintenance check valves from the condensate supply system. These valves open to maintain the RIIR system solid and close to prevent diversion of LPCI injection flow.
REQUIRED OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally TESTS:
every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.
l BASIS FOR These valves are normally closed check valves (with two in series). The inboard RELIEF:
valve is essential (safety related). The redundant outboard valve is non-essential.
Each pair of valves are the same design and met the same quality assurance requirements at the time they were installed. They open as necessary to keep the RIIR system in a solid standby condition, which is not a safety function. When the RIIR pumps start, these valves close to ensure maximum flow to the reactor.
i These valves do not perform a function which requires leakage to be limited to a specified amount.
Only one valve is required to close to prevent diversion of flow as determined and documented in accordance with CNS safety classification requirements. Ilowever, the current system design does not allow independent testing to ensure both valves have closed. Thus both valves will be tested together. When a RIIR Pump is started, should both valves fail to close, a relief valve would lift or a pressure sensor would alarm on the condensate supply side of the valves.
ALTERNATE TEST:
The check valves in each loop will be tested closed simultaneously to assess the operational readiness of each pair of valves. Should the acceptance criteria be exceeded, both valves will be declared inoperable until they are repaired or replaced as necessary.
Revision 1.2 Section V Page 132 of 155
COOPER NUCLEAR STATION TIllRD INTERVAL INSERVICE TESTING PROGRAM RELIEF REQUEST RV-14 VALVE:
IIPCI-CV-24CV, HPCI-CV-25CV, IIPCI-CV-26CV, HPCI-CV-27CV, RCIC-CV-22CV, RCIC-CV-23CV, RCIC-CV-24CV, and RCIC-CV-25CV CLASS:
2 CATEGORY:
C FUNCTION: IIPCI and RCIC Turbine Exhaust Line Vacuum Breakers open to prevent siphoning suppression pool water into the exhaust line.
REQUIRED OM Part 1, 3.3.2.3(a) requires vacuum relief valves to be individually actuated to TESTS:
verify open and close capability, set pressure, and performance of any pressure and position sensing accessories.
OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.
l BASIS FOR These valves are normally closed check valves with two in series cross connected i
RELIEF:
to two in parallel (Il pattern). The four RCIC valves are lift check valves, and the four HPCI valves are swing check valves. The valves are located in the i
suppression pool free space. In the closed position they prevent steam from the exhaust line entering the free space of the suppression chamber. Either two j
inboard valves or two outboard valves must be closed to perform this function.
Two valves in series provides added assurance that steam will not enter the suppression chamber.
The valves open to prevent siphoning suppression pool water into the exhaust line due to steam condensing when the associated HPCI or RCIC systems are isolated.
Each pair of valves is cross connected to the parallel pair of valves (H pattern) so that a single failure will not prevent the vacuum relief function. These valves are not required to be leak tight and are not equipped with position indication or pressure sensing devices. During power operation the suppression chamber is inerted and inaccessible.
Due to the location and configuration of these valves (located on the open ended turbine exhaust lines) a closure test can not be performed and the inboard check valves are not accessible for a set pressure test. Also due to the configuration, a set pressure test of the two outboard RCIC lift check valves can not be performed.
Revision 1.2 Section V Page 134 of 155
I COOPER NUCLEAR STATION.
TIIIRD INTERVAL INSERVICE TESTING PROGRAM RELIEF REQUEST RV-14 (Continued) i ALTERNATE TEST:
In lieu of the OM-1 and OM-10 requirements, each valve will be disassembled, inspected, and manually exercised open and closed during each refueling outage.
1 In addition, the two outboard IIPCI vacuum relief valves will be set point tested open in place each refueling outage.
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Revision 1.2 Section V Page 135 of 155
COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM AUGMENTED COLD SHUTDOWN JUSTIFICATION ACSJ-05 VALVES:
SGT-CV-14CV and SGT-CV-15CV CLASS:
A CATEGORY:
C REQUIRED TEST:
OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.
FUNCTION: Open to provide flow paths from their respective SGT filter trains. Close to prevent back flow from the operating SGT train discharge.
BASIS FOR DEFERRAL: The acceptance full flowrate for these valves is > 1602 cfm. During plant power operations, system conditions exist that prevent the SGT system from achieving a flowrate of > 1602 cfm. Reactor building differential pressure and back pressure from the Off Gas Dilution Fans act against SGT system pressure restricting SGT system flowrate. Therefore, it is impracticable to perform a full flowrate test of these valves at power operations. These valves are not within the scope of ASME Section XI.
ALTERNATE.
TEST:
A partial open stroke test will be performed on these valves during plant power i
operations on a quarterly frequency. A full flow open test will be performed on these valves during cold shutdown periods. The full flow test shall also satisfy the j
closure exercise requirements of the check valve in the idle train.
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Revision 1.2 Section V Page 143 of 155
4 COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM AUGMENTED REFUELING OUTAGE JUSTIFICATION AROJ-05 VALVE:
SLC-CV-10CV and SLC-CV-11CV i
CLASS:
A CATEGORY:
C FUNCTION: The SLC pump discharge check valves are required to open for sodium pentaborate i
injection (neutron poison) and close to isolate the inservice pump from the adjacent idle pump. The injection of the sodium pentaborate is not a safety function, but l
may be required in emergency situations.
REQUIRED TEST:
OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally a
every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and i
4.3.2.5.
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BASIS FOR PEFERRAL: These pump discharge check valves are located in a segment of piping which is not l
provided with upstream vent / drain connections or pressure connections to facilitate valve closure testing. Additionally, the pumps' positive displacement design does not allow for any appreciable back flow which otherwise may be detected in the pump suction piping. Modification to the system for verification of valve closure i
capability is not practicable nor cost beneficial since no commensurate increase in q
safety would be derived. The only practicable method of valve closure verification is by perfonning radiography (RT) of the seat area. Performing RT on a quarterly or cold shutdown frequency, as opposed to once each refueling, increases personnel radiation exposure due to the presence of a radioactive source. Although j
exposure is low, this is an undesirable ALARA practice. The burden of performing a quarterly RT is not justified based on the previous discussion. These valves are not within the scope of ASME Section XI.
ALTERNATE TEST:
Valve closure capability shall be verified at or prior to each refueling outage by performing radiography on the valve seating area.
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Revision 1.2 Section V Page 149 of 155
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