ML20078C597
| ML20078C597 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/26/1994 |
| From: | HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML20078C595 | List: |
| References | |
| PROC-941026-01, PROC-941026-1, NUDOCS 9411010105 | |
| Download: ML20078C597 (16) | |
Text
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SOUTH TEXAS PROJECT -
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ELECTRIC GENERATING STATION UNIT 2
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HOUSTON LIGHTING AND POWER COMPANY PUMP AND VALVE INSERVICE TEST PLAN -
REVISION 4 SUPPLEMENT 2 P
Prepared by:
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Date Reviewed by:
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Date' 4
Reviewed by:
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Date Approved by '
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9411010105 941026
""2 PDR ADOCK 05000498 P
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Unit 2 Pump and Valve Rev. 4, Supp. 2 l Inservice Test Plan RR5 Test Requirement IWP-4120 requires the full scale range of each instrument to be three times the reference value or less.
Basis for Relief The Centrifugal Charging Pumps (located in the Mechanical Auxiliary Building) and the Residual Heat Removal Pumps (located in the Reactor Containment Buildir.g) are in areas of high radiation.
For ALARA considerations, the Vibration Monitoring System (located in the Control Room) is used to measure vibration amplitude. The vibration monitoring system is an online system which constantly monitors the machine and provides alarms when alert limits are reached. The full scale range of each instrument is fixed and the above requirement could be exceeded.
Rescaling the instrument to meet the requirements of IWP-4120 for a low reference value would impair the ability of the system to monitor the machine up to the severity limit determined by size, speed and application.
Alternate Testing The Vibration Monitoring System will be used to obtain vibration data for the Residual Heat Removal and Centrifugal Charging Pumps.
The system provides overall readout repeatability within the accuracy limits specified in Table IWP-4110-1 with indication in increments of at least 0.2 mils.
If the Vibration Monitoring System is unavailable, portable vibration indicators will be used as described in RR4.
RR6 Per NRC Letter ST-AE-HL-93298, RR not required.
l 19
Rev. 4 Supp 1
Unit 2 Pump and Valve and Supp. 2 l
Inservice Test Plan RR10 Test Requirement IWP-3400(a) states that an inservice test be run on each pump nominally every 3 months during normal plant operation.
It is also recommended that this test frequency be maintained during shutdown periods if this can reasonably be accomplished.
Basis for Relief STPEGS has three RHR pump trains used only for long-term cooldown events following auxiliary feedwater operation.
The RHR system does serve the LHSI function as they are required to'do in standard not plants.
For these reasons, the STPEGS RHR system is not critical to immediate accident mitigation.
Since the RHR system bas a negligible impact on core damage frequency, less emphasis can be placed on testing the RHR system at (See ST-HL-AE-4544, Risk-Based Evaluation of Technical power.
Specifications.)
Alternate Testing Inservice tests will be run on each pump nominally every 6 months during normal plant operations. This test frequency will be maintained during shutdown periods if it can reasonably be accomplished.
RR-11 Test Requirement IWP-3400(a) states that an inservice test be run on each pump nominally every 3 months during normal plant operation.
It is also recommended that this test frequency be maintained during shutdown periods if this can reasonably be accomplished.
Basis for Relief STPEGS has three CS pump trains used only for protecting containment integrity following a core damage event for other events where radiological release is postulated. Due to the CS's negligible impact on core damage frequency and large early release frequency, less emphasis should be placed on testing.
(See ST-HL-AE-4544, Risk-Based evaluation of Technical Specifications.)
Alternate Testing Inservice tests will be run on each pump nominally every 6 months during normal plant operations.
This test frequency will be maintained during shutdown periods if it can reasonably be accomplished.
21a l
Unit 2 Pump and Valve Rev.
4, Supp. 2 Inservice Test Plan 4
RR-12 System Component Cooling Water Components Component Cooling Water Pumps 2A, 2B, and 2C Component Function Provide cooling water for removal of heat from Engineered Safety Feature Equipment.
Code Requirement IWP-4110 and IWP-4120 for pressure instrumentation accuracy and full-scale range.
Basis for Relief The installed suction pressure gauges for the component cooling water pumps have a range of 160 psig and an accuracy of 0.5%.
The reference values for suction pressure for these pumps have been as low as 21 psig. The ASME Code requires each analog instrument to have a full-scale range 3 times the reference value or less and an accuracy of + 2 percent of full-scale. The installed suction pressure gauges for these component cooling water pumps has a full-scale range greater than 3 times the reference value, but has an accuracy of + 0.5 percent which is more corservative than the Code. The combination of the range and accuracy of the installed suction pressure gauge yielda a reading at least equivalent to the reading achieved from instruments that meet the Code requirements.
The installed suction pressure gauge meets the intent of the Code requirements and yields an acceptable level of quality and safety for testing.
Alternate Testing The permanently installed suction gauges for component cooling water pumps 2A, 2B, and 2C will be used to obtain test measurements for evaluating pump operability.
21b
Rev.
1, Supp. 2 Unit 2 Pump and Valve Inservice Test Plan RR-13 System Essential Cooling Water System Components Essential Cooling Water Screen Wash Booster Pumps 2A, 2B, and 2C Component Function Provide water at high pressure to backwash debris off the traveling screens located at the Essential Cooling Water pump suction inlet from the Essential Cooling Pond.
Code Requirement IWP-4100 and IWP-4120 for pressure instrumentation accuracy and full-scale range.
Basis for Relief The inatalled discharge pressure gauges for the cooling water screen wash booster pumps 2A, 2B, and 2C have a range of 300 psig and an accuracy of 0.5%.
The reference values for discharge pressure for these pumps have been as low as 87 psig. The ASME Code requires each analog instrument to have a full-scale range 3 times the reference value or less and an accuracy of 1 2 percent of full-scale. The installed discharge pressure gauges for these essential cooling vater screen wash booster pumps have a full-scale but has an accuracy range greater than 3 times the reference value, The of 1 0.5 percent which is more conservative than the Code.
combination of the range and accuracy of the installed discharge pressure gauge yields a reading at least equivalent to the reading The achieved from instruments that meet the Code requirements.
installed discharce pressure gauge meets the intent of the Code requirements and yields and acceptable level of quality and safety for testing.
Alternate Testing The permanently installed discharge gauges for essential cooling water screen wash booster pumps 2A, 2B, and 2C will be used to obtain test measurements for evaluating pump operability.
21c
Unit 2 Pump and Valve Rev. 4, Supp.' 2 Inservico Test Plan i
RR-14 System Reactor Makeup Water Components Reactor Makeup Water Pumps 2A and 2B.
Component Function Provide makeup water to the Spent Fuel Fool, Component Cooling Water Surge Tank, and CVCS Boron Blending Tee.
Code Requirement IWP-3100 for varying the resistance of the system until either the measured flowrate or differential pressure equals a corresponding reference value.
Basis for Relief The Reactor Makeup Water Pumps utilize a non-isolatable full flow recirculation loop around the pumps with an additional recirculation line back to the Reactor Makeup Water Storage Tank.
To perform the test, the pump discharge valve downstream of the recirculation lines is closed creating a closed-loop fixed-resistance recirculation flow path.
All pump parameters required by the code except those specifically exempted by other relief requests will be measured.
Alternate Testing Pump testing will be performed using a fixed-resistance flow path.
The measured flowrate and differential pressure will be compared to their respectivo reference values to determine pump operability.
Deviations from the reference values will be compared to the allowed limits and corrective action taken.
(Reference OM-6, Part 5.2 c&d)
I 21d
Unit 2 Pump and Valve Rev.
4, Supp. 2 Inservice Test Plan RR-15 System Chemical and Volume Control Components Centrifugal Charging Pumps 2A and 2B.
Component Function Provide >. rated water from the Volume Control Tank or Reactor Makeup Water Storage Tank to the Reactor Coolant System.
Code Requirement IWP-3100 for varying the resistance of the system until either the measured flowrate or differential pressur'e' equals a corresponding reference value.
Basis for Relief The Centrifugal Charging Pumps utilize a mini-flow recirculation line from the pump discharge to a point upstream of the line leading to the Seal Water Heat Exchanger. To perform the test, the pump discharge valve downstream of the recirculation lines is closed.
Valves in the recirculation line are not designed to perform the function of a throttle valve and therefore are left fully open creating a closed-loop fixed-resistance recirculation flow path.
All Pump parameters required by the code except those specifically exempted by the other relief requests will be measured.
Alternate Testing Pump testing will be performed using a fixed-resistance flow path.
The measured differential pressure will be compared to the allowable ranges given in Table IWP-3100-2 to determine pump operability.
21e
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Unit 2 IST Valve List Page 10 of 72 Component Cooling Water - CC Rev.
4, Supp.'2
-l,
NORM. FAIL TEST ST VALVE ID VALVE FUNCTION CL P&ID GC CAT SIZE TYPE ACT POS.
POS.
REQUIREMENT RR/C C
O CC-0013 CCW to RHR 2A HTX IB Check 2
F05017 E2 AC 16 CK SA NC CV (RR)
ROJ-1 l
L7 CC-0123 CCW to RHR 2B HTX IB Check 2
F05018 E2 AC 16 CK SA NC CV (RR)
ROJ-1 l
LT CC-0183 CCW to RHR 2C HTX IB Check 2
F05019 E2 AC 16 CK SA NC CV (RR)
ROJ-1 l
LT FV-4531 RHR 2A HTX Outlet 3
F05017 G2 B
16 B
AO NC FO Q,R,MT 21 FV-4548 RHR 2B HTX Outlet 3
F05018 G2 B
16 B
AO NC FO Q,R,MT 20 FV-4565 RHR 2C HTX Outlet 3
F05019 G2 B
16 B
AO NC FO Q,R,MT 19 MOV-0049 CCW from RHR 2A IB Isol.
2 F05017 G4 A
16 B
MO NO FAI Q,R,MT 17 17 LT MOV-0129 CCW from RHR 2B IB Isol.
2 F05018 G4 A
16 B
MO NO FAI Q,R,MT 15 16 LT MOV-0189 CCW from RHR 2C IB Isol.
2 F05019 H4 A
16 B
MO NO FAI Q,R,MT 16 16 LT 36 l
Unit 2 IST Valve List Page.15 of 72 Component Cooling Water - CC Rev. 4 Supp. 2
.l,
NORM.
FAIL TEST ST VALVE ID VALVE FUNCTION CL P&ID GC CAT SIZE TYPE ACT POS.
POS.
REQUIREMENT RR/C C
O MOV-0404 CCW from RCP OB Isolation 2
F05021 H1 A
12 B
MO NO FAI Q,R,MT 10 LT FV-4493 CCW from RCP OB Isolation 2
F05021 H1 A
12 B
LT THIS SECTION OF VALVES DELETED 41
Unit 2 IST Valve List Page 16'of 72 Component Cooling Water - CC Rev.
4, Supp. 2.
.l NORM.
FAIL TEST ST VALVE ID VALVE FUNCTION CL P&ID GC CAT SIZE TYPE ACT POS.
POS.
REQUIREMENT RR/C C l )
THIS SECTION OF VALVES DELETED NORM.
FAIL TEST ST VALVE ID VALVE FUNCTION CL P&ID GC CAT SIZE TYPE ACT POS.
POS.
REQUIREMENT RR/C C
O FV-0862 CCW from RCFC 21A,22A OB Isol.
2 F05017 C4 A
8 B
LT FV-0863 CCW from RCFC 21B,22B OB Isol.
2 F05018 C4 A
8 B
LT FV-0864 CCW from RCFC 21C,22C OB Isol.
2 F05019 C4 A
8 B
LT 42 l
4 Unit 2 IST valve List Page 34 of 72_
Essential Cooling Water - EV Rev.
4, Supp. 2 l,*
1 NORM.
FAIL TEST ST VALVE ID VALVE FUNCTION CL P&ID GC CAT SIZE TYPE ACT POS.
POS.
REQUIREMENT RR/C C
O ECW Loop A to Essential EW-0262 CHW Chillers 3
F05038 H6 C
14 CK SA NO CV L--
ECW Loop B to Essential EW-0263 CHW Chillers 3
F05038 F6 C
14 CK SA NO CV ECW Loop C to Essential EW-0264 CHW Chillers 3
F05038 C6 C
14 CK SA NO CV FV-6935 ECW Loop A Drain to ECW Sump 3
F05038 F7 3
Fv-6936 ECW Loop B Drain to ECW Sump 3
F05038 C7 B
FV-6937 ECW Loop C Drain to ECW Sump 3
F05038 A7 B
EWC Self-Cleaning Strainer EW-0403 Emergency Backflush Check 3
F5038 G4 C
6 CK SA NC CV (DI)
RR51 l
EWC Self-Cleaning Strainer EW-0404 Emergency Backflush Check 3
F5038 E4 C
6 CK SA NC CV (DI)
RR51 l
EWC Self-Cleaning Strainer EW-0405 Emergency Backflush Check 3
F5038 B4 C
6 CK SA NC CV (DI)
RR51 l
EW-0370A ECW Pump 1A Discharge Vent 3
F5038 G4 C
3 CK SA NO CV(DI)
RR47 EW-0370B ECW Pump 1B Discharge Vent 3
F5038 E4 C
3 CK SA NO CV(DI)
RR47 EW-0370C ECW Pump IC Discharge Vent 3
F5038 B4 C
3 CK SA NO CV(DI)
RR47 l
ECW Self Cleaning Strainer l
EW-0277 Emergency Backflush 3
F5038 G4 B
6 M
M NC FAI MS ECW Self Cleaning Strainer EW-0278 Emergency Backflush 3
F5038 E4 B
6 M
M NC FAI MS
~~-
ECW Self Cleaning Strainer EW-0279 Emergency Backflush 3
F5038 B4 B
6 M
M NC FAI MS 60
Unit 2 IST Valve List Page 60 of 72-Rev.
4, Supp. 2
.l,
Steam Generator Blowdown - SB NORM.
FAIL TEST ST VALVE ID VALVE FUNCTION CL P&ID GC CAT SIZE TYPE ACT POS.
POS.
REQUIREMENT RR/C C lO THIS SECTION OF VALVES DELETED NORM.
FAIL TEST ST VALVE ID VALVE FUNCTION CL P&ID GC CAT SIZE TYPE ACT POS.
POS.
REQUIREMENT RR/C C
O FV-4153 SG 2A to Flash Tank Isol.
2 F20001 G5 B
4 GT AO NO FC Q,R,MT 32 FV-4152 SG 2B to Flash Tank Isol.
2 F20001 G1 B
4 GT AO NO FC Q,R,MT 31 FV-4151 SG 2C to Flash Tank Isol.
2 F20001 C1 B
4 GT AO NO FC Q,R,MT 33 FV-4150 SG 2D to Flash Tank Isol.
2 F20001 C5 B
l l
86
[
4 Unit 2 IST Valve List Page 61 of 72 l.
Standby Diesel Generator Starting Air - SD Rev. 4,-Supp. 2 N01 FAIL TEST ST VALVE ID VALVE FUNCTION CL P&ID GC CAT 71 2 TYPE ACT PO:
POS.
REQUIREMENT RR/C C
'O DG 21 Right Bank 8041-FV-5435 Cranking Air Valve 3
00108 F2 B
RR40 DG 21 Left Bank 8041-FV-5434 Cranking Air Vsive 3
00108 F3 B
RR40 8041-DG 22 Right Bank 3j FV-SS.15 Cranking Air Valve 00108 F2 B
RR40 DG 22 Left Bank 8041-FV-5534 Cranking Air Valve 3
00108 F3 B
RR40 DG 23 Right Bank 8041-l FV-5635 Cranking Air valve 3
00108 F2 B
RR40 DG 23 Left Bank 8041-FV-5634 Cranking Air valve 3
00108 F3 B
RR40 DG 21 Starting Air Receiver l
SD0003A No. 21 Inlet Check Valve 3
F22546 8F BC 1
CK SA NO Q
DG 21 Starting Air Receiver SD0004A No. 22 Inlet Check Valve 3
F22546 7F BC 1
CK SA NO Q
DG 22 Starting Air Receiver SD0003B No. 23 Inlet Check Valve 3
F22546 SF BC 1
CK SA NO Q
DG 22 Starting Air Receiver SD0004B No. 24 Inlet Check Valve 3
F22546 4F BC 1
CK SAJj40 Q
DG 23 Starting Air Receiver SD0003C No. 25_ Inlet Check Valve 3
F22546 2F BC 1
CK SA NO Q
DG 23 Starting Air Receiver SD0004C No. 26 Inlet Check Valve 3
F22546 IF BC 1
CK SA NO Q
87
Unit 2 Pump and Valve Rev. 4, Supp. 1 Inservice Test Plan and Supp. 2 l
.. RR45 i
Per NRC Letter ST-AE-HL-93298, RR not required.
I RR46 l
Per NRC Letter ST-AE-HL-93298, RR not required.
RR47 (Cold Shutdown Justification)
Test Requirement Exercise check valves for operability at least once every three (3) months.
Basis for Relief Due to plant design, it is not practical to verify by any positive means, either directly or indirectly, the operability of these normally open check valves per the requirements of IWV-3522(a).
The following series check valves are installed in their respective systems with no provisions for independently testing each valve:
CC-0327 and CC-0759 CC-0363 and CC-0757 CC-0321 and CC-0756 CC-0346 and CC-0758 CC-0540 and CC-0541 CC-0402 and CC-0763 CV-0036A and CV-0037A CV-0036B and CV-0037B CV-0036C and CV-0037C CV-0036D and CV-0037D The following valves can not be tested due to the requirement to disable all of the Component Cooling Water system in order to verify valve closure:
CC-0051, CC-0131, AND CC-0191 The following valves are installed in such a way that verifying valve closure is impractical:
RM-0003, RM-0010, and RM-0013 EW-0370A, EW-0370B, and EW-0370C i
EW-0403, EW-0404, and EW-0405 l
Alternate Testing These check valves will be verified operable by disassembling one valve each refueling outage on a rotating basis for inspection-to ensure no degradation has occurred and to provide baseline data for the non-intrusive check valve testing program.
If any check valve selected during any refueling outage shows signs of unacceptable degradation, all other check valves in the sample group will be disassembled and inspected during the refueling outage. The number of valves selected for disassembly each refueling outage will ensure that all valves in any sample group are disassembled and inspected within six years. When approved and sufficient baseline data has been obtained, inspections for operability on these check valves will be performed using non-intrusive methods.
Disassembly and inspection will be used when results of the non-intrusive method is inconclusive or show signs of degradation.
118 l
j
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Unit 2 Pump and Valve Rev.
4, Supp. 2 Inservice Test Plan ROJ-1 (Refueling Outage Frequency Justification)
Applicable Valves 2R202TCC0058: CCW Supply A Train RCFC ICIV 2R202TCC0013: CCW Supply A Train RHR ICIV 2R202TCC0138: CCW Supply B Train RCFC ICIV 2R202TCC0123: CCW Supply B Train RHR ICIV 2R202TCC0198: CCW Supply C Train RCFC ICIV 2R202TCC0183: CCW Supply C Train RHR ICIV Test Requirement OMa Part 10 Section 4.3.2 Exercising Frequency. Check valves shall be 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.
Basis for Deferral (Refueling Outage Justification)
The subject check valves are located inside containment.
Due to the CCW System design, during plant operations and cold shutdowns it is not practical to verify by any positive means, either directly or indirectly, the obturator movement to the closed position per OMa Part 10, 4.3.2.2(a) and 4.3.2.4(a).
Alternate Testing In accordance with OMa Part 10, 4.3.2.2(e) these valves will be exercised each refueling outage in conjunction with the 10CFR50 Appendix J Local Leak Rate Test.
Currently STP has not incorporated OMa Part 10 into its Inservice Test Program; however, past correspondence with NRR (Ref. ST-AE-HL-93298) indicates Code Relief is not required to incorporate a provision of the ASME Section 1989 Edition (including OMa Part 10) which was incorporated by rulemaking on September 8, 1992.
120c
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