ML19305A350
| ML19305A350 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/28/1979 |
| From: | NORTHEAST UTILITIES |
| To: | |
| Shared Package | |
| ML19305A348 | List: |
| References | |
| NUDOCS 7903130383 | |
| Download: ML19305A350 (55) | |
Text
.
MILLSTONE NUCLEAR POWER STATION Uf1IT NO. 1 IflSERVICE INSPECTION & TEST PROGRAF 1 FOR PUMPS, VALVES AflD PRESSURE TESTS FOR THE 20 MONTH PERIOD MAY 28, 1979 TO DECEf1BER 28, 1980 7903130383 Feisruary 28, 1979
PUf1P IN-SERVICE TESTING 1.
Scope This program describes the procedures for in-service testing of pumps to meet the requirements of Section XI of the ASME Code, subsection IWP, "In-service Testing of Pumps in Nuclear Power Plants."
In-service testing is required for all class 1, 2 and 3 pumps (both centrifugal and displacement types) that are provided with an emergency power source. Drivers are excluded except when the pump and driver fom an integral unit and the pump bearings are in the driver.
All tests and examination procedures required by Subsection IWP including schedules, reference values, the location and type of measurement for each of the required test quantities, records of the results, and all corrective action taken shall be defined and perfomed by NNEC0 for Millstone Unit No. 1.
2.
Test Procedure In-service tests shall be conducted with the pump operating at naminal motor speed.
A series of reference values are detemined for quantities listed below, as observed or measured when the equipment is known to be operating correctly.
In-service Test Quantities Inlet Pressure, Pi Differential Pressure, A P Flow Rate, Q Vibration Signature, V Proper Lubricant Level or Pressure Bearing Temperature, Tb In an in-service test these quantities are remeasared and campared with the reference values to detemine if corrective action is needed. When a reference value or set of values may have been affected by replacement, repair or routine servicing of the pump, a new reference value or set of values shall be detemined or the previous value reconfimed by an in-service test run within 4 days af ter retum of the pump to nomal service.
3.
Test Frequency Each in-service test shall include the measurement and observation of applicable test quantities.
Bearing temperature shall be measured durinc at least one in-service test each year. An in-service test shall be run on each applicable pump, at a frequency and scope as stated in Table IWP.
If possible, this test frequency shall be maintained during plant shut-down, but in that most of the pumps run only during power operation, such as in the Condensate and Feed System, testing will _ be limited during this time period.
If the pump is not tested during plant shutdown,
. it shall be tested within one week af ter the plant is returned to steady state operation.
Pumps that are operating need not be run or stopped for a special test, provided the plant log shows each such pump was operated at reference conditions and the quantities specified were measured, observed, recorded and analyzed.
4.
Analysis and Corrective Action All test data shall be analyzed within 4 days after completion of a test.
The test quantities are cmpared with the allowable range of quantities listed in Table IWP-3100-2 of subsection IWP.
If the ranges cannot be met, reduced range limits allowing the pump to fulfill its function may be used in lieu of those in Table IWP-3100-2. These reduced range limits shall be specified by NNEC0 in the pump testing procedures.
The corrective action to be taken by NNECO if the periodically acquired operational data falls into the calculated Alert Range or Required Action Range shall be specified in NNEC0 procedures.
The scope of corrective actions specified in the NNEC0 procedures shall span a series of alter-natives up to and including a required notification of plant management that a pump's operation data has entered the Required Action Range. The NNEC0 plant management shall disposition the status of any pump which is operating in the Required Action Range.
The following information shall be maintained by Millstone to meet the requirements for in-service testing:
A record for each pump including the name of the manufacturer, the model, and the serial or other identification number.
An in-service test plan including:
(a) the hydraulic circuit to be used.
(b) the location and type of measurement for each required test quantity.
(c) the test quantity reference values, the limits of Pj and Tb (Table IWP-3100-2) and any other required information.
Test record giving ptrtinent information such as test date, instru-ments used, results, corrective action required, and signatures of persons conducting and analyzing the test.
A record of corrective action and subsequent in-service test ver-ifying operational adequacy. All in-service test plans and reco ds shall be maintained at the Millstone Unit No.1 plant, and shall be accessible for audit.
Additional information on pump testing records can be found in the
" Documentation and Reports" section of this manual.
. 5.
Vibration Signature Analysis Program General Procedure The in-service pump test, when required, will include vibration signature data of velocity anplitude (inches per second) vs. frequency (0-200 Hj or 0-500 H )-
z The measurements are made using a mounted vibration sensor which inter-faces with a renotely located vibration spectrum analyzer.
The vibration signature data is recorded by means of an X-Y plotter.
The measurement locations to be used for monthly and baseline vibration signature data are established and specified for each pump in the NNECO procedures.
Data _ Evaluation & Analysis The periodically acquired pump vibration signature data shall be canpared to the baseline reference values. The evaluation of pump performance and the establishnent of an Alert Range and a Required Action Range shall be determined by changes in vibration signature peaks which is of greater sensitivity than overall vibration amplitude.
The exact criteria used shall be specified in NNECO procedures.
In general, vibration signature peaks which increase by 6 db and remain between.05 inches per second and
.5 inches per second will be considered in the Alert Range, and the Re-quired Action Range will require a +6 db increase in a signature peak which subsequently exceeds.5 inches per second.
TABLE IWP OPERATIONAL READINESS TESTING FOR PUMPS e
MOTOR INIfr DIITERDTTIAL VIBRATION W BRICATIOi BEARIIG TEST RNP CURRENT MM PRESSURE PRESSURE FUM SIGaWRE LEVEL UFPERAWRE NUCY IPCI M8-75A X
1800 X
X X
X X
tbte 1 Monthly M8-75B X
1800 X
X X
X X
tbte 1 benthly M8-75C X
1800 X
X X
X X
tbte 1 Monthly M8-75D X
1800 X
X X
X X
tbte 1 bbnthly (bre Spray M8-74A X
3570 X
X X
X X
tbte 1 Mmthly M8-74B X
3570 X
X X
X X
tbte 1 Pbnthly Peactor Peod (WCI)
M2-10A X
3580 X
X X
X X
X Fbnthly See Note 8 M2-10B X
3580 X
X X
X X
X obn M2-10C X
3580 X
X X
X X
X Mon t Otzidensate Booster (BCI)
M2-7A X
1780 X
X Note 2 F
X X
Pbnthly M2-7B X
1780 X
X ibte 2 X
X X
Fbnthly M2-7 0 X
1780 X
X Note 2 X
X X
Monthly (bidensate (nCI)
M2-6A X
1185 X
X tbte 2 X
X tbte 1 Monthly M2-6B X
1185 x
X wtc 2 X
X tbte 1 Monthly M2-6C X
1185 X
X Note 2 X
X Note 1 Monthly Dnertjency (bodensate Trans.
M7-28 1780 X
X tete 3 X
X tbte 7 Quarterly Service Water M4-7A X
1180 Sea Level Note 4 X
X Note 1 Mon thly M4-7B X
1180 Sea Icvel Note 4 X
X tbte 1 Monthly M4-7C X
1180 Sea IcVel tbte 4 X
X tbte 1 Pbnthly M4-7D X
1180 Sea Level Note 4 X
X Note 1 Monthly anergericy Service Water M4-13A X
1800 Sea Invel Pbte 5 X
X X
tbte 1 Planp ard Flow Wst Quarterly t*4-13B X
1800 Sea Icvel tbte 5 x
X X
tbte 1 Purp ard Flow Wst Quarterly M4-13C X
1800 Sea Icvel tbte 5 x
X X
!bte 1 Ptrp ard Flow Test Quarterly M4-130 X
1800 Sea IcVel tbte 5 x
X X
tbte 1 Ptsp and Flow Wst Quarterly Standby Ligaid (bntrol 1102A 420 Tank le ml ibte 6 x
X X
N/A bbnthly 1102B 420 Tank level tbte 6 X
X X
N/A Monthly Reactor Buildirg (XM M4-10A X
1775 X
X X
X Monthly See Note 8 M4-10B X
1775 X
X X
X Monthly Secondary (IM M4-15A 1800 X
X X
X Fbnthly See Note 8 M4-15B 1800 X
X X
X Monthly
@ These Ptsnps Not Safety-Related, For Information Only 4
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fl0TES TABLE IWP 1.
Bearing temperatures of these pumps cannot be taken due to the configuration of the bearing housings.
2.
Although flow measurement devices are installed at various locations within the Condensate and Feed systems, the instrumentation is set up to measure header or system flow rates. flomally, all three Condensate and Condensate Booster pumps are running in conjunction with two out of three feed pumps.
Because more than one pump is operating, individual pump flows cannot be derived.
During steady state operation, plant operators rely on system pressure instrumen-tation and pump motor current to determine individual pump per-fomance.
There is technically no need to instrument individual pumps on a multi-pump balanced system such as this.
The operational readiness of these pumps will be detemined by measurement of the parameters shown in Table IWP.
3.
Plant surveillance procedure 625.1 requires the Emergency Condensate Transfer Pump M-728 to be tested quarterly. This test requires the pump to deliver 3600 gpm against a system head of 214 ft. with a pump discharge gauge reading of 104 psig.
4.
Service water pumps M4-7A, B, C and D are operated in parallel with other pumps and dischamed to a common header. flo instrumentation exists for inlet pressure. Pump dischage pressure and motor current will be recorded.
5.
flo instnamentation exists for inlet pressure for emergency service water pumps M-13A, B, C, D.
Plant surveillance procedure 623.2 re-quires that these pumps be tested quarterly. The test requires that each pump shall deliver at least 2500 gpm against a system head of at least 446 ft. with pump discharge pressure of 189 psig.
6.
The Standby Liquid Control Pumps 1102A, B are positive displacment pumps. These pumps are tested nonthly by measuring the time re-quired to pump a measured amount into a test tank and recording pump dischame pressure.
7.
The mergency condensate transfer pump nust be operated in an open hydraulic circuit and will not run long enough to stablize bearing tmperatures.
8.
In nomally operating systems, the running pumps will be tested.
Idle pumps will be tested as they are rotated into service.
Conden-sate & Condensate Booster pumps are normally all running. Feed pumps are run two at a time, and rotated quarterly.
6
a VALVE Ih-SERVICE TESTING 1.
Scope This program describes the procedure for in-service testing of valves to meet the requirements of Section XI of the ASME Code, Subsection IWV, "In-service Testing of Valves in Nuclear Power Plants."
In-service testing is required for all Class 1, 2 and 3 valves which fall in the categories defined below regardless of type of actuation (manual, power, or self-actuated).
Where distinguishing characteristics fran more than one category are applicable, combinations or categories shall be used (e.g., AC) and those valves shall be tested such that all the require-ments of each category are met.
Valves used for operating convenience only such as manual vent, drain, instrument and test valves, and valves used for maintenance only do not require in-service testing. The following categories of valves are subject to in-service testing.
(a) Category A--Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function.
(b) Category B--Valves for which seat leakage in the closed position is inconsequential for fulfillment of their function.
(c) Category C--Valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves).
(d ) Category D--Valves which are actuated by an energy source capable-of only one operation, such as rupture disks or explosive actuated valves.
(e) Category E--Valves which are normally locked (or sealed) open or locked (or sealed) closed to fulfill their function.
All test and examination procedures required by subsection IW, including schedules and the limiting valves of observed parameters shall be defined and performed by NNEC0 for the Millstone Unit No.1 plant.
Tables IW-1 and IW-2 specify the testing frequency and parameters measured or observed for each valve covered by this program. Where exce?tions to the Code are necessary due to design or operating considerations, they are so noted.
Table IW-1 is a listing of all plant valves in the In-Service Testing (IST) Program and shows valve characteristics and test parameters. This table also notes where the requirements of the Code, Subsection IW, cannot be met and a testing alternative for those cases.
Table IWV-2 is a listing of safety / relief valve setpoints and setpoint tolerances.
2.
Test Procedures (a) Category A and Category B Valves All Category A and B valves shall be exercised at least once every three months except as noted in Table IWV-1.
Valves operating at a frequency of at least once every three months to support normal plant operations need not be tested provided required observations are made and analyzed. Where practical, valves with f ail safe actuators shall be tested by observing the operation of these valves upon loss of actuator power.
If valves are in a system that is out of service, exercising is not required for such valves except immediately prior to the return of the systs to service.
If a valve fails to change position upon testing, corrective action shall be initiated immediately.
If the condition is not, or cannot be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the valve shall be declared inoperative.
A retest showing acceptable operation shall be run following any required corrective action before the valve is returned to service.
Category "A" valves are leak rate tested as containment isolation valves in conjunction with the containment leak rate test either individual leak rate tested or if no test connections are present, as part of the containment integrated leak test.
All valves with remote position indicators, which are inaccessible for direct observation during plant operation, shall be visually observed at the same (or greater) frequency as scheduled refueling outages, to verify that rmote valve indications accurately reflect valve operation.
(b) Category C Valves Safety valve and relief valve tests shall be conducted at the end of each time period as defined in ASME Section XI, Table IWV-3510-1. All testing shall be done in accordance with ASME PTC 25.3-1976.
See Table IWV-2 for setpoints.
Check valves shall be exercised at least once every three months or as indicated.
Exceptions are noted where system design or plant safety considerations prevail.
(c) Category D Valves One of the two charges in explosively actuated valves shall be fired and replaced every operating cycle with charges from the same batch being tested, in compliance with Section 4.4 of the Millstone Tech Specs.
(d) Category E Valves There are no regular testing requirements for Category E valves.
Operational checks with appropriate record entries shall be made to verify that each valve is locked or sealed, as applicable.
3.
Records A system of documentation defining all test and examination procedures, including test schedules, limiting values for parameters, test results and corrective actions shall be maintained at the Millstone Unit No.1 plant.
Preoperational tests, if any exist for the Millstone Unit No.1 plant, and examination results and manufacturers functional test results shall be in-cluded in the documentation.
All in-service test documentation shall be made readily accessible to authorized persons for testing or auditing purposes.
The manual section on Documentation and Reports discusses valve testing records.
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25202 - 26032 Sh. 2 Feedwater Coolant Injection 1-MW-90 2E Suction from Cond. Storage Tank 20 GA H
LO ET 1-FCX-1 2C Relief Valve 3
REL SRV 1-FCX-2 2E FWCI Suction 16 GA H
LO ET 1-FCX-3 2E FWCI Pump Suction 16 GA H
LO ET 1-FCX-4 2C Pump Discharge Check 14 CV C
CV 1-FCX-5 28 Pump Discharge Valve 14 GA M0 C
Q MT 90 sec.
1-FCX-6 2E Pump Discharge to Condenser "A" 12 GA H
LO ET 1-FCX-7 2E Pump Discharge to Condenser "B" 12 GA H
LO ET 1-CN-2A 2C Condensate pp 1A Disch. Check 20 CK 0
CV X
1-CN-2B 2C Condensate pp 1B Disch. Check 20 CK 0
CV X
1-CN-2C 2C Condensate pp 1C Disch. Check 20 CK 0
CV X
1-CN-58 2B SJAE Minimum Flow FCV-2-4 16 GL A0 C
Q X
1-CN-60 2E FCV-2-4 Bypass SJAE 14 GA M0 LC ET Power Removed 1-CN-30A 2C Condensate Booster ppa Disch. Check 20 CK 0
CV X
1-CN-30B 2C Condensate Booster ppb Disch Check 20 CK 0
CV X
1-CN-30C 2C Condensate Booster ppC Disch. Check 20 CK 0
CV X
1-CN-701 2B Supply to Recombiner Condenser 6
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25202 - 26032 Sh. 2 Feedwater Coclant Injection (Cont'd) 1-FW-2A 2C RFP 1^ Discharge Check 18 CK 0
CV X
CS 1-FW-2B 2C RFP IB Discharge Check 18 CK 0
CV X
CS 1-FW-2C 2C RFP IC Discharge Check 18 CK 0
CV X
CS 1-FW-4A 2B FW Control Valve 5A Stop 14 GA MO 0
0 X
1-FW-4B 2B FW Control Valve 5B Stop 14 GA M0 0
Q X
1-FW-5A 2B FW Control Valve SA 12 GL A0 0
Q X
1-FW-5B 2B FW Control Valve SB 12 GL A0 0
Q X
1-FW-9A 1AC Outside Containment Cneck 18 CK 0
CV LT 1-FW-9B 1AC Outside Containment Check 18 CK 0
CV LT 1-FW-10A 1AC Inside Containment Check 18 CK 0-CV LT 1-FW-10B 1AC Inside Containment Check 18 CK 0
CV LT 1 -F W-5C 2B FW Control Valve SC 4
GL A0 C
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RELIEF REQUEST BASIS System: Feedwater Coolant Injection System 1.
Valves:
1-CN-2A,28,2C, 1-CN-10A,3 08,30C,
1-FW-2A,28, 2C Category:
C Class:
2 Function:
Pump discharge check valves Test Requirement:
Exercise for closing upon reversal or cessation of flow every three months.
Basis for Relicf:
These valves are in nornal service and are exercised as pumps are routinely rotated.
Each individual valve will not be exercised every three months.
Collectively, all valves will be exercised within a six month period.
Alternate Testing:
NNEC0 believes these valves are being properly demonstrated for occupational readiness and wishes to continue to exercise then as pumps are rotated in service.
2.
Valve:
1-CN-58 Category:
B Class:
2 Function:
Steam jet air ejector minimum flow control Test Requirenent:
Exercise valve for operability every three months.
Basis for Relief:
To exercise this valve during operations would re-quire disrupting condersate flow by by-passing to the main condenser.
This valve is closed by a FWCI signal, is a system isolation valve, and is not in the FWCI flow path.
Alternate Testing:
Exercise valve during cold shutdowns, not to exceed once every three months.
3.
Valves:
1-FW-4A,4B,5A,5B,5C Category:
B Class:
2 Function:
These valves control and regulate feedwater flow to the reactor.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
Exercising these valves during operation would interrupt normal balanced flow to the reactor causing reactor water level fluctuations.
Alternate Testing:
These valves will be exercised during cold shutdowns, not to exceed once every three months.
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CK C
LT CV X
RR 25202 - 26032 Sh. 4 Control Rod Drive Hydraulic 302-19A 2B Air Valves from Reac. Prot.
1 GL SOL C
Q X
RR 302-19B 2B Air Valves from Reac. Prot.
I GL SOL C
Q X
RR 302-20A 2B Air Valves from Reac. Prot.
1 GL SOL C
Q X
RR 302-20B 2B Air Valves from Reac. Prot.
1 GL SOL C
Q X
RR 302-23 2C Scram Discharge Volume Relief
.75 REL SRV 305-114*
.75 CK 0
CV X
RR 305-115*
2C Chanjing Water Supply to Scram
.5 CK 0
CV X
RR 305-120*
2B HCU Withdraw to Exhaust
.5 GA SOL C.
Q 305-123*
2B HCU Insert from Drive Water
.5 GA SOL C
Q 305-126*
2B Scram Insert 1
GL A0 C
Q X
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2B Scram Withdraw
.75 GL A0 C
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RR 305-138*
2C Cooling Water to HCU
.5 CK 0
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- Refers t o one of 145 units 4
RELIEF REQUEST BASIS System: Control Rod Hydraulic System 1.
Valves:
1-HS-4, 1-HS-5 Category:
A, AC Class:
1 Function:
Inner and outer containment isolation valves Tor head spray.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
These normally closed valves have no safety related functions and are listed as containment isolation valves only. These valves are opened to admit water to cool the head and upper reactor internals before removal of the closare head.
Alternate Testing:
Exercise for operability at refueling.
Now being leak tested as containment isolation valves.
2.
Valves:
302-19A,19B, 302-20A,20B Category:
B Class:
2 Function:
Air valves from reactor protection system.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
These valves are solenoid operated thus cannot be partstroked. Full stroking could cause an unsched-uled reactor trip. These valves are operated 145 times each refueling as part of control rod testing.
Alternate Testing:
These valves will be exercised each refueling.
3.
Valves:
305-114,115,126,127 Category:
B,C Class:
2 Function:
Control valves for scram operation of control rods in each of 145 units.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
These valves cannot be part stroked because of their construction.
They cannot be exercised at cold shutdown because of system interlocks. The cold shutdown mode switch prohibits the withdrawal of control rods.
Alternate Testing:
Exercise for operability at reactor refueling.
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Q MT 90 sec.
1-CS-2B 2B Core Spray B Pump Suction 12 GA tt0 0
Q
?1T 90 sec.
1-CS-3A 2C Pump A Discharge Check 10 CK C
CV 1-CS-3B 2C Pump B Discharge Check 10 CK C
CV 1-CS-4A 2B Admission Valve 10 GA M0 0
Q MT 10 sec. open -
20 sec. close 1-CS-4B 2B Admission Valve 10 GA fl0 0
Q MT 10 sec open -
20 sec. close 1-CS-SA 1A Admission Valve 10 GA M0 C
Q f1T 10 sec open -
20 sec. close 1-CS-5B 1A Admission Valve 10 GA M0 C
Q MT 10 sec. open -
20 sec. close LT X
1-CS-6A IC Pump Discharge to Vessel 10 CK C
CV X
RR 5 yr. cycle 1-CS-6B IC Pump Discharge to Vessel 10 CK C
CV X
RR 5 yr. cycle 1-CS-7A 1E System Discharge Shutoff 10 GA LO ET 1-CS-78 1E Systen Discharge Shutoff 10 GA LO ET 6
RELIEF REQUEST BASIS System:
Emergency Core Cooling System (Core Spray and LPCI) 1.
Valves:
Core Spray 1-CS-6A,6B LPCI 1-LP-11A Category:
C Class:
1 Function:
Inside containment check valves.
Test Requirement:
Exercise normally closed valves to open position every three months.
Basis for Relief:
There is no design provision for manually exercising these valves and stroking with system flow requires that water be pumped into the reactor vessel.
This is not possible at power, because of pressure differences and thermal-hydraulic consid-erations.
Alternate Testing:
These valves will be exercised at cold shutdowns on a rotating basis which includes 1-LP-11A.
By drawing the reactor water level down, it will be possible to stroke one of the three ECCS admission check valves (1-LP-11A,1-CS-6A,1-CS-68) by flooding up through each valves respective flow path.
However, it will not be possible to perform more than one valve test each shutdown because of the limited operating volume in the reactor vessel.
All of the valves will be tested within a five year period under the most conservative conditions.
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REL SRV 1-CS-18B 2C Low Pressure Relief 2
REL SRV 1-CS-21A 2B Test Line to Torus 6
GA MO Q
MT 35 sec.
1-CS-21B 28 Test Line to Torus 6
GA M0 Q
MT 35 sec.
1-MW-91A 2E Suction from Condensate Tank 12 GA LC ET 1-MW-91B 2E Suction from Condensate Tank 12 GA LC ET 25202 - 26032 Turbine Building Secondary Closed Cooling Water 1-SC-2A 3C Pump Discharge Check 10 CK o/c CV 1-SC-2B 3C Pump Discharge Check 10 CK o/c CV 25202 - 26032 Sh. 5 Low Pressure Coolant Injection 1-LP-1A 2E System Suction Shutoff 20 BFLY H
LO ET 1-LP-1B 2E System Suction Shutoff 20 BFLY H
LO ET 1-LP-2A 2B Pump A Suction Valve 18 GA M0 0
Q MT 120 sec.
1-LP-2B 2B Pump A Suction Valve 18 GA M0 0
Q MT 120 sec.
1-LP-2C 2B Pump C Suction Valve 18 GA M0 O
Q MT 120 sec.
1-LP-2D 2B Pump D Suction Valve 18 GA M0 O
Q MT 120 sec.
8
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.S2 NE EE Nd 22 25202 - 26032 Sh. 5 Low Pressure Coolant Injection (Cont'd) 1-LP-3A 2C Pump A Discharge Check 12 CK C
CV 1-LP-3B 2C Pump B Discharge Check 12 CK C
CV 1-LP-3C 2C Pump C Dischame Chet-12 CK C
CV 1-LP-3D 2C Pump D Discharge Check 12 CK C
CV 1-LP-4A 2E Pump A Discharge Valve 12 GA H
LO ET 1-LP-4B 2E Pump B Discha me Valve 12 GA H
LO ET 1-LP-4C 2E Pump C Dischame Valve 12 GA H
LO ET 1-LP-4D 2E Pump D Discharge Valve 12 GA H
LO ET 1-LP-5A 2E Heat Exchanger A Inlet 12 GA H
LO ET 1-LP-5B 2E Heat Exchanger B Inlet 12 GA H
LO ET 1-LP-6A 2E Heat Exchanger A Outlet 12 GA H
LO ET 1-LP-6B 2E Heat Exchanger B Outlet 12 GA H
LO ET 1-LP-7A 2B Heat Exchanger Bypass 18 GA MO 0
Q MT 40 sec.
1-LP-7B 2B Heat Exchanger Bypass 18 GA M0 0
Q MT 40 sec.
1-LP-9A 2BC Outboard Stop,LPC I to Recirc. Loop 18 GL MO 0
Q Stop MT 40 sec.
CK CV 1-LP-9B 2BC Outboard Stop, LPC I to Ret irc. Loop 18 GL M0 0
Q Stop MT 40 sec.
CK CV 1-LP-10A 1A Inboard Stop, LPC I to Recirc. Loop 18 GL M0 C
Q MT 18 sec, open -
40 sec. close LT X
9
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W 25202 - 26032 Sh. 5 Low Pressure Coolant Injection (Cont'd) 1-LP-10B 1A Inboard Stop, LPCI to Recirc. Loop 18 GT M0 C
Q MT 18 sec. open -
40 sec. close LT X
1-LP-11A IC Inside Check 18 CK C
CV X
5 yr.
1-LP-11B 1C Inside Check 18 CK C
CV X
CS 1-LP-12A 2E System Discharge Shutoff 18 GA H
LO ET 1-LP-12B 2E System Discharge Shutoff 18 GA H
L0 ET 1-LP-13A 2B Outboard Stop to Torus Spray 6
GT M0 C
Q MT 60 sec.
1-LP-13B 2B Outboard Stop to Torus Spray 6
GT M0 C
Q MT 60 sec.
1-LP-14A 2B Inboard Stop to Torus Spray 6
GL M0 C
Q MT 60 sec.
1-LP-14B 2B Inboard Stop to Torus Spray 6
GL M0 C
Q MT 60 sec.
1-LP-15A 2B Outboard Stop to Containment Spray 10 GL M0 C
Q MT 60 sec.
1-LP-15B 2B Outboard Stop to Containment Spray 10 GL M0 C
Q MT 60 sec.
1-LP-16A 2B Inboard Stop to Containment Spray 10 GA M0 C
Q MT 60 sec.
1-LP-16B 2B Inboard Stop to Containment Spray 10 GA M0 C
Q MT 60 sec.
1-LP.-26A 2B Minimum Flow Bypass to Torus 3
GT M0 0
Q MT l
40 sec.
1-LP-26B 2B Minimum Flow Bypass to Torus 3
GT MO 0
Q MT 40 sec.
10
RELIEF REQUEST BASIS System:
Low Pressure Coolart Injection 1.
Valve:
1-LP-11B Category:
C Class:
1 Function:
Inside containment check valve in LPCI system to reactor recirculation loop.
Test Requirement:
Exercise normally closed valve to open position every three months.
Basis for Relief:
There is no provision for manual ona ation of this valve.
Hydraulic stroking requires pumping water into the reactor vessel.
Because of pressure differentials this cannot be done while vessel is pressurized.
Alternate Testing-NNEC0 will exercise this valve whenever the reactor is in the shutdown cooling phase of operations as this valve is in the shutdown flow path.
Shutdown cooling normally occurs at refueling but may occur at cold shutdowns.
11
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ER ME dd Md uu Low Pressure Coolant Injection (Cont'd) 25202 - 26032 Sh. 5 1-LP-32A 2C fiain Line Relief 2.5 REL SRV 1-LP-32B 2C Main Line Relief 2.5 REL SRV 1-LP-43A 2B Outbcard Stop Test Line to Torus 10 GT M0 C
Q MT 40 sec.
1-LP-43B 2B Outboard Stop Test Line to Torus 10 GT M0 C
Q MT 40 sec.
1-LP-44A 2B Inboard Stop Test Line to Torus 10 GL M0 C
Q MT 40 sec.
1-LP-44B 2B Inboard Stop Test Line to Torus 10 GL M0 C
Q MT 40 sec.
Standby Liquid Control 25202 - 26032 Sh. 7 1-SL-1 2E Combined Pump Suction 2.5 GA H
LO ET 1-SL-2A 2E Pump Suction 1.5 GA H
LO.
ET 1-SL-2B 2E Pump Suction 1.5 GA H
LO ET 1-SL-3A 2C Pump Discharge Check 1.5 CK CV 1-SL-3B 2C Pump Dischange Check 1.5 CK CV 1-SL-4A 2E Pump Discharge 1.5 GA H
LO ET 1-SL-4B 2E Pump Discharge 1.5 GA H
LO ET 1-SL-5A 2D Squib Valve 1.5 Shear RR 1-SL-5B 2D Squib Valve 1.5 Shea r RR 1-SL-6 2E Combined Discharge 1.5 GA H
LO ET 1-SL-7 1AC' Combined Discharge Check 1.5 CK C
CV X
RR LT X
ILRT 1-SL-8 1AC Combined Discharge Check 1.5 CK C
CV X
RR LT X
ILDT 12
RELIEF REQUEST BASIS System:
Valve:
1-SL-7,8 Category:
AC Class:
1 Function:
Canbined discharge checks inside and outside drywell.
Test Requirement:
Exercise normally closed valves to open position every three months.
Basis for Relief:
There is no provision for manual operation of these valves.
Hydraulic stroking requires pumping into the reactor vessel and the operation of a squib valve. There are no test connections at present by which an individual valve leak late test could be performed.
Alternate Testing:
These check valves will be exercised each refueling as the standby liquid system is tested by pumping into the reactor. Leak tightness of these valves is checked during containment integrated leak rate tests.
13
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>M uu Standby Liquid Control 25202 - 26032 Sh. 7 (Cont'd)
I 1-SL-9 2E Canbined Discharge 1.5 GA H
LO ET 1-SL-22A 2C Discharge Relief 1.5 REL SRV 1-SL-22B 2C Discharge Relief 1.5 REL SRV Main Steam 25202 - 26032 Sh. 1 1-MS-1A 1A Stop Inside Containment 20 GL A0 0
Q MT 3 to 5 sec. to close LT X
1-MS-1B 1A Stop Inside Containment 20 GL A0 0
Q MT 3 to 5 sec. to close LT X
LLRT CIV 1-MS-IC 1A Stop Inside Containment 20 GL A0 0
Q MT 3 to 5 sec. to close LT X
LLRT CIV 1-MS-ID 1A Stop Inside Containment 20 GL A0 0
Q MT 3 to 5 sec. to close LT X
LLRT CIV 1-MS-2A 1A Stop Outside Containment 20 GL A0 0
Q MT 3 to 5 sec to close LT X
LLRT CIV 1-MS-28 1A Stop Outside Containment 20 GL A0 0
Q MT 3 to 5 sec. to close LT X
LLP.T CIV 14
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me an 3
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W m2 NE dd Nd Main Steam 25202 - 26032 (Cont'd )
Sh. 1 1-MS-2C 1A Stop Outside Containment 20 GL A0 0
Q MT 3 to 5 sec. to close LT X
LLRT CIV 1-MS-2D 1A Stop Outside Containment 20 GL A0 0
Q MT 3-5 LT X
LLRT CIV 1-f1S-3 A 1C Relief - Electro - flechanical 6
REL SRV 1-MS-3B 1C Relief - Electro - Mechanical 6
REL SRV 1-MS-3C IC Relief - Electro - Mechanical 6
REL SRV 1-M S-3D IC Relief - Electro - fiechanical 6
REL SRV 1-MS-3E 1C Relief - Electro - Mechanical 6
REL SRV 1-MS-3F IC Relief - Electro - Mechanical 6
REL SRV 1-MS-5 1A Upstream Drain Header Stop 2
GT M0 C
Q MT 35 sec.
LT 1-MS-6 1A Upstream Drain Header Stop 2
GT M0 C
Q MT 35 sec.
LT 15
RELIEF REQUEST BASIS System: Main Steam 1.
Valves:
1-MS-1A,1B,1C,1D,2A,28,2C,2D Category:
A Class:
1 Function:
Main steam stop valves inside and outside containment.
Test Requirement:
Seat leakage tests.
Basis for Relief:
NNEC0 proposes a continuation of a 25 psig test pressure for the main steam isolation valves. This exemption was requested from the NRC in a letter of Novembe r 14, 1976 with arguments in favor of such exemptions summarized in NRC letter of March 3,1977.
Alternate Testing:
Test at 25 psig.
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Isolation Condenser 25202 - 26032 Sh. 8 1-1C-1 1A Steam Isolation Valve 14 GA M0 0
Q
~
MT 24 sec.
LT CIV 1-1C-2 1A Steam Isolation Valve 14 GA M0 0
Q MT 24 sec.
w LT CIV 1-1C-3 1A Condensate Return Valve 10 GA M0 C
Q MT 19 sec.
/
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LT CIV E
1-1C-4 1A Condensate Return Valve 10 GA MO 0
Q g
MT 19 sec.
LT CIV I
1-1C-6 2A Steam Vent
.75 CON A0 0
Q MT 5 sec.
LT CIV 1-1C-7 2A Steam Vent
.75 CON A0 0
Q MT 5 sec.
LT CIV 1-1C-10 3B Make-up to Condenser Shell 3
GL M0 C
Q MT 30 sec.
1-1 1
3C Make-up Check 3
CK CV X
RP, f
=
1-1C-12 3E Make-up Stop 3
GT L0 ET u,.
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RELIEF REQUEST BASIS System:
Isolation Cendenser 1.
Valve:
1-1C-11 Category:
C Class:
3 Function:
Reverse flow check in makeup line to isolation condenser.
Test Requirement:
Exercise closed valve to open position every three months.
Basis for Relief:
Exercising this valve requires flow into the isolation condenser.
Operating water level must be lowered to allow for additional water to be pumped to shell. Lower water level reduces the safety margin of this component.
Alternate Testing:
Exercise this valve at reactor refueling.
18
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M ER NE Nd R
>z ou Service Water 25202 - 26032 Sh. 10 1-SW-1A 3C Pump A Discharge Check 20 CK CV 1-SW-1B 3C Pump B Discharge Check 20 CK CV 1-SW-1C 3C Pump C Discharge Check 20 CK CV 1-SW-1D 3C Pump D Discharge Check 20 CK CV 1-SW-9 3B Isolation Valve to Turbine Bldg.
20 GA l10 0
Q X
1-SW-99 3B Emergency Diesel Gen. Cooling 6
GL A0 C
Q MT 30 sec.
E.mergency Service Water 25202 - 26032 Sh. 5 1-LPC-1A 3C ESW Pump A Discharge Check 10 CK CV 1-LPC-1B 3C ESW Pump B Discharge Check 10 CK CV 1-LPC-1C 3C ESW Pump C Discharge Check 10 CK CV 1-LPC-1D 3C ESW Pump D Discharge Check 10 CK CV 1-LPC-2A 3E ESW Pump A Discharge 10 GA LO.
ET 1-LPC-2B 3E ESW Pump B Discharge 10 GA LO ET 1-LPC-2C 3E ESW Pump C Discharge 10 GA LO ET 1-LPC-2D 3E ESW Pump D Discharge 10 GA LO ET 1-LPC-3A 3E ESW to Hx Inlet Stop 14 GA L0 ET 1-LPC-3B 3E ESW to Hx Inlet Stop 14 GA LO ET 1-LPC-4A 3B Heat Exchanger Discharge 12 GL f10 C
Q MT 1-LPC-4B 3B Heat Exchanger Discharge 12 GL l10 C
Q
! MT 19
RELIEF REQUEST BASIS System:
Valve:
1-SW-9 Category:
B Class:
3 Function:
Service Water stop to turbine building closed cooling water heat exchangers.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
This valve is in the sole flow path of service water to the TBCCW heat exchangers.
If this valve failed in the closed position, many balance of plant components, necessary for continuing operation, would be forced out of service. There-by causing a plant shutdown.
Alternate Testing:
This valve goes closed upon loss of normal power and is exercised in conjunction with that test each refueling.
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Reactor Building Closed Cooling Water 25202 - 26032 Sh. 11 1-RC-2A 3C Pump Discharge Check 14 CK CV 1-RC-2B 3C Pump Discharge Check 14 CK CV 1-RC-6 3AC Header Inlet Check 6
CK CV X
RR LT X
1-RC-15 3A Header Outlet Stop 6
GA M0 0
Q X
LT X
1-RC-39 3B Shutdown Heat Exchanger Cooling Discharge 12 GL M0 C
Q X
Fuel Pool Cooling 25202 - 26032 Sh. 3 1-FP-3A 3C FP Pump Discharge Check "A" 6
CK CV 1-FP-3B 3C FP Pump Discharge Check "B" 6
CK CV Shutdown Cooling 25202 - 26032 Sh. 13 1-50-1 1A Suction Isolation 14 GA M0 C
Q X
LT 1 -SD-2A 1A Shutdown Pump A Suction 12 GA M0 C
Q X.
LT 21
RELIEF REQUEST BASIS Systen: Reactor Building Closed Cooling Water 1.
Valves:
1-RC-6,15 Category:
AC, A Class:
3 Function:
Ir.let and outlet valves on drywell header.
Test Requirement:
Exercise for operability every three menths and leak test as containment isolation valves.
Basis for Relief:
These normally open valves can be exercised only during refueling, as flow disruption, even during cold shutdowns, could cause overheating of dry-well equipment.
Even though both valves are Category A, there is no provision for local leak rate testing to verify containment integrity.
This system is a closed system, not exposed to containment a tmosphere.
Alternate Testing:
None 2.
Valve:
1-RC-39 Category:
B Class:
3 Function:
Stop valve in RBCCW system discharge from shut-down heat exchangers.
Test Raquirement:
Exercise for operability every three months.
Basis for Relief:
Shutdown heat exchanger " laid up" between operations and operates as necessary to retain temperature at specified conditions during cold shutdowns.
Alternate Testing:
Exercise for operability at cold shutdowns. Not to exceed once every three months.
22
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6 oQ Q
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gR gg n
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EM MB GB MH M
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>E uu Shutdown Cooling 25202 - 26032 (Cont'd) Sh.13 1-SD-2B 1A Shutdown Pump B Suction 12 GA M0 C
Q X
LT 1-SD-3A 2C Pump Discharge Check 10 CK CV X
CS 1-SD-3B 2C Pump Discharge Check 10 CK CV X
CS 1 -SD-4 A 1A Heat Exchanger Discharge 10 GL M0 C
Q X
LT 1-SD-4B 1A Heat Exchanger Discharge 10 GL M0 C
Q X
LT 1-SD-5 1A Discharge Isolation 12 GA M0 C
Q X
LT Reactor Cleanup
. 25202. 26032 Sh. 1 1-CU-2 1A Supply to CU System Inside Drywell 8
GA M0 0
Q MT 18 sec.
LT 1-CU-2A 1A Bypass to 1-CI-2
.5 GA A0 C
Q MT 10 sec.
LT 1-CU-3 1A Aux. Pump Bypass 8
GA M0 0
Q MT 18 sec.
LT I
23
m RELIEF REQUEST BASIS System:
Shutdown Cooling System 1.
Valves:
1-SD-1,2A,2B,4A,4B,5 Category:
A Class:
1 Function:
Isolation valves for the shutdown cooling system which operates to cool reactor water when the temperature and pressure in the reactor reach the point at which the main condenser can no longer be used as a heat sink following reactor shutdown.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
This system is held in " wet layup" until such time as it is desired to be operated. The system operates as necessary to retain temperature at specified conditions during cold shutdown.
A'i cernate Testing:
Exercise for operability at cold shutdowns not to exceed once every three months.
2.
Valves:
1-SD-3A,3B Category:
C Class:
2 Function:
Pump discharge check valves.
Test Requirement:
Exercise for opening for system requirements every three months.
Basis for Relief:
System is in " wet layup" and does not operate except at cold shutdowns.
System recirculates reactor coolant only and has limited make-up capabilities.
Alternate Testing:
Exercise for operability at cold shutdowns, not to exceed once every three months.
24
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d 8
5 0
e4 wd 3
Q du
- C 5
DE Eg w
g2 38 3
e ts 38 m-M E2 NE ME Nd uu U
Reactor Cleanup 25202 - 26032 Sh. 1 (Cont'd) 1-CU-5 1A Aux. Pump Suction 8
GA M0 C
Q MT 18 sec.
LT 1-CU-28 1A Regen. Hx Discharge 8
GA M0 O
Q MT 18 sec.
LT 1-CU-29 1AC Regen. Hx Discharge Check Inside 8
"K 0
CV X
Drywell LT X
Atmospheric Control 25202 - 26032 Sh. 12 1-AC-2A 2AC Vacuum Relief From Sec. Contain.c 20 CK CV LT 1-AC-2B 2AC Vacuum Relief From Sec. Containment 20 CR CV LT 1-AC-3A 2AC Vacuum Relief From Sec. Containment 20 BFLY A0 Q
MT 10 sec.
LT 1-AC-3B 2AC Vacuum Relier Fron Sec. Containment 20 BFLY A0 Q
MT 10 sec.
LT 1-AC-4 2A Purge Air Supply 18 BFLY A0 C
Q MT 10 sec.
LT 1-AC-5 2A Purge Air to Drywell 18 BFLY A0 C
Q MT 10 sec.
LT 25
~
RELIEF REQUEST BASIS System: Reactor Water Clean-up 1.
Valve:
1-CU-29 Category:
AC Class:
1 Function:
Inside drywell check valve in cleanup water return to reactor vessel.
Test Requirement:
Exercise for operability and test for leakage as containment isolation valve.
Basis for Relief:
This valve is considered to be a containment isolation valve only in that it is in normal system operation and has a minimal safety function in closing.
NNECO presently seat leak tests the outer isolation valve 1-CU-28.
There are no provisions for leak testing of 1-CU-29 or to check the closing operability of this valve.
Alternate Testing:
No alternative exercising or leak seat testing is proposed for 1-CU-29.
26
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a R
s s
s e
et m
md Q
dE N
DU 55 2l w
g N
g R
EM MB dB ds gg M
ER d5 dd Ud
>z ou 5
Atmospheric Control 25202 - 26032 Sh. 12 (Cont'd) 1-AC-6 2A Purge Air to Drywell 10 BFLY A0 C
Q MT 10 sec.
LT 1-AC-7 2A Drywell Vent 18 BFLY A0 C
Q MT 10 sec.
LT 1-AC-8 2A Drywell Vent to Main Exhaust 18 BFLY A0 C
Q MT 10 sec.
LT 1-AC-9 2A Drywell Vent Bypass 2
BFLY A0 C
Q MT 15 sec.
LT 1-AC-10 2A Standby Gas Treatment Inlet 12 BFLY A0 Q
MT 10 sec.
LT 1-AC-11 2A Torus Vent 18 BFLY A0 C
Q MT 10 sec.
LT 1-AC-12 2A Torus Vent Bypass 2
BFLY A0 C
Q MT 15 sec.
LT 1-AC-17 2A N2 Purge Isolation 6
BFLY A0 C
Q MT LT 1-SS-3 2A Drywell Drain Valve Outside Cont.
2 GA A0 C
LT 1-Si 4 2A Drywell Drain Valve Outside Cont.
2 GA A0 C
LT Drywell Equip. Drain Valve Outside Cont.
2 GA A0 C
LT 1-SS-13 2A 1-SS-14 2A Drywell Equip. Drain Valve Outside Cont.
2 GA A0 C
LT 27
~
LEGEND FOR VALVE TESTING Q
- Exercise valve (full stroke) for operability every (3) months LT
- Valves are Icak tested per Section XI Article lWV-3420 LTT - Valves are locally leak tested at containment test pressure.
LLRT - Valves are leak tested in conjunction with containment inte-grated lead test.
- Stroke time measurements are taken and compared to the stroke time limiting value per Section XI Article IWV 3410 CV
- Exercise check valves to the position required to fulfill their function every (3) months SRV - Safety and relief valves are tested per Section XI Article IWV-3510 DT
- Test category D valves per Section X1 Article lWV-3600 ET
- Verify and record valve position before operations are performed and after operations are completed, and verify that valve is locked or sealed.
- Exercise valve for operability every cold shutdown RR
- Exercise valve for operability every reactor refueling 28
TABLE IWV-2 SAFETY / RELIEF VALVE SETPOINTS Service Sta. No.
Valve iype Set Point (Tol.)
CRD Scram Volume Relief 302-23 3/4" R-V 1285 (+15, -50)
Core Spray Low Pressure Relief 1-CS-18A 2" R-V 375 (+15, -5) 1-CS-188 2" R-V 375 (+15, -5)
LPCI flain Line Relief 1-LP-32A 2 1/2 R-V 400 (+10, -5) 1-LP-32B 2 1/2 R-V 400 (+10 -5)
Standby Liquid Control Pump Disc.
1-SL-22A 1 1/2 R-V 1400 (+25, -20)
Relief 1-SL-22B 1 1/2 R-V 1400 (+25, -20) flain Steam Electro-pneumatic Relief 1-MS-3A 6" SRV 1095 (+1%)
1-MS-3B 6" SRV 1125 (T1%)
1-MS-3C 6" SRV 1125 (T1%)
1-MS-3D 6" SRV 1110 (T1%)
1-MS-3E 6" SRV 1125 (T1%)
1-MS-3F 6" SRV 1125 (T %)
1 FWCI Condenser Transfer Relief 1-FCX-1 3" R-V 275 (+10)
(V7-156) 29
SYSTEM PRESSURE TESTS Articles IWA-5000, IWB-5000, IWC-5000, and IWD-5000 discuss the requirements of system pressure tests for Classes 1, 2, and 3 components.
Table BCD-5000 presents the system pressure test requirements for the Millstone components and notes departures from code where it was deemed necessary.
Test requirements for open-ended lines such as suction lines from storage tanks, and which receive static tests,are not addressed in the table.
In that NNECO and NUSCO Quality Assurance personnel will be witnessing these tests or auditing the test results, exception to IWA-2120 concerning the authorized inspector will be taker.
The location of check valves in several systems that penetrate the primary containment preclude the Class 1 pressure test boundary from extending outward beyond the first of such valves, usually located inside containnent even though the Class change boundary is outside containment.
In these cases, the Class 1 leakage and pressure test boundary would be the inside check valve.
Con.ersely, pressure tests of Class 2 systems, which are outside containment, would have to be bounded at a stop valve which may er may not be the Class 1/ Class 2 boundary.
Precautions must be taken in view of the differences that exist in Class 1/
Class 2 test pressures to prevent overpressurization of the Class 1 components.
The following systems are affected:
System Class 1 Boundary Class 2 Boundary Feedwater 1-FW-11A/B HP Heater Discharge Isolation Valves Standby Liquia Control 1-SL-8 1-SL-6 Core Spray 1-CS-6A/B l-CS-SA/B LPCI l-LP-11A/B l-LP-10A/B Reactor Cleanup Return 1-CU-29 CRD Return Penetration (Dormant from cap at Cap penetration to RPV)
Reference Boundary Diagram, Figure 1 1
TABLE BCD-5000 SYSTEM PRESSURE TESTS Test Code Test System Pressure Pressure Remarks I
CLASS 1 Reactor Coolant Pressure Boundary System Leakage Test 1000 1000 In Compliance With Code System Pressure Test 1080 6 200*F 1080 @ 200 F Note 1 CLASS 2 Main Steam 1563 1563 In Complianca With Code CRD System 1563 1563 Note 2 Standby Liquid Control System 1350 1350 In Compliance Pith Code Condensate /FWCI 210*
288 Note 3 Condensate Storage & Transfer i 100*
100 In Compliance With Code (FWCI)
Condensate Booster System (FWCI) 665 665 In Compliance With Code Feedwater/FWCI I 2875 2875 Note 4 LPCI 200*
200 In Compliance With Code Core Spray 260*
260 In Compliance With Code Shutdown Cooling 135*
135 In Compliance With Code Isolation Condenser 1375 1563 Note 5 CLASS 3 Secondary Closed Cooling Water 165 165 System Service Water 45*
165 Note 6 Emergency Service Water 330 330
.In compliance With code Fuel Pool Cooling System 190*
220
' Note 7 RBCCW 80*
165 Note 8
- Test pressure to be obtained by operating the system pump at shutoff head allowing some recirculation for cooling.
The exact pressure will depend on specific test conditions.
Hydro testing will be conducted at temperatures meeting fracture toughness criteria applicable to the ferritic materials f rom which the system components are constructed.
9 2
s TABLE BCD-5000 NOTES 1.
The nominal operating pressure for the RCPB is 1000 psig.
2.
Test pressure may be limited by CRD mechanism seal leakage.
3.
The system maximum operating pressure (condensate pump shutoff head).is 210 psig.
Leakage past valve seats in this system's large gate valves would preclude a test pump's ability to achieve the additional 78 psi to reach the code test pressure. Normal operating pressure for this system is 150 psig.
4.
Feedwater/FWCI system piping and components between the feedpump discharge isolation valves and the maintenance stops downstream of the HP heaters will be pressure tested to 2875 psig, in compliance with Code.
Piping between the HP heater stops and the reactor vessel connot be tested at this pressure because of the double check valve arrangement at the con-tainment penetration and lower test pressure of the reactor coolant pressure boundary components (1080 psig versus 2875 psig).
This piping will be observed for leakage during system operation.
The Class 1 portion is volumetrically examined per category B-J.
Feedwater system piping between the feedpumps and the discharge isolation valves will be pressure tested with the condensate booster /FWCI system.
5.
The isolation condenser system will be pressure tested at 1375 psig to be compatible with current surveillance testing requirements.
6.
The service water system has been redesigned and now operates at a much lower pressure than previously. A pump shutoff head test is considered satisfactory for this system as taking it out of service,for a code pressure test is impractical due to essential cooling functions that must be administered for the reactor building closed cooling water system. This system provides cooling for the spent fuel pool and reactor shutdown cooling systems via the RBCCW System.
7.
The spent fuel cooling system will be tested at 190 psig, 30 psi less than the Code required test pressure. Due to the essential cooling functions of this system, removing it from service for the length of time required for a code pressure test would be impractical.
8.
The RBCCW system is another system which provides an essential cooling function and cannot be removed from service.
This system cools the spent fuel pool and reactor shutdown cooling heat exchangers.
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PROPOSED SCIIEDULE OF PRESSURE TfSTS I
FIRST TEN-YEAR INTERVAL SUBSEOUENT TEf;-YEAR INTERVALS Third First Second Third 40 Months 40 Months 4 0 Months 40 Months CLASS 1 Reactor Coolant Pressure Boundary X
X CLASS 2 Non-Exempt Systems Core Spray
- LPCI*
Isolation Cundenser*
X X
Exempt Systems CRD X
X SLBC*
X X
FWCI Condensate Shutdown Cooling
- X X
REQUIRED 100% IN TEN-YEARS -- 25%-33% PER 40 MONTIIS CLASS 3 Secondary Cooling X
Emergency Service Water X
Puel Pool Cooling X
RBCCW X
REQUIRED 100% EACH INTERVAL -- 25%-33% EACil 40 MONTilS VISUAL 100% EACH 40 MONTilS
- SEE IWC-522 0 (c)
"For components that are not required to function during reactor operation, the system test pressure shall not be less than 100% of the pressure developed during the conduct of a periodic system inservice test."
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