ML20234C914
| ML20234C914 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/30/1987 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20234C913 | List: |
| References | |
| PROC-870630, NUDOCS 8707070002 | |
| Download: ML20234C914 (129) | |
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- ABSTRACT, The Inservice Testing I'rogram and Pressure Test Program for Connecticut Yankee were developed in accordance with Subsections IWA, IWP, and IWV of the ASME Boiler and Pressure Vessel Code,Section XI, 1983 Edition, including Addenda through Summer 1983 except where specific relief is requested in accordance with 10CFR 50.55(a)(g)(5)(iii). This program I
applies to the third inspection interval as defined for Inspection Program B in Subsubarticle IWA-2420 of Section XI.
nLJ re83/7651
THIRD INTERVAL INSERVICE TESTING PROGRAM (9
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TABLE OF CONTENTS PAGE 1.0 Introduction 1
2.0 Program Development 3
3.0 Valve Legend 10 4.0 IWP-1 Pump Program 12 q
5.0 IWV-1 IST Valves 17 6.0 IWV-2 Containment Isolation Valves 56 7.0 IWV-3 Valves Not Tested 68 8.0 IWV-4 Pressure Isolation Valves 76 9.0 IWV-5 Safety / Relief Valves 81 10.0 IWP-DG Diesel Aux. Pumps 83 1
fs 11.0 IWV-DG Diesel Aux. Valves 96 12.0 ISI Boundary Drawings 13.0 DG Boundary Drawings l
0) rw83/7651 i
1.0 Introduction l')
j The following subsections provide a listing of the Inservice Testing of Class 1, 2, and 3 pumps and valves at Connecticut Yankee. Also included is the Augmented Inservice Test Program (Diesel Generator Systems).
1.1 Operational Readiness Testing for Pumps There are fourteen (14) pumps at Connecticut Yankee that are required to perform a specific function in shutting down the reactor or to mitigate the consequences of an accident and that are provided with an emergency power source. These pumps are tested on a quarterly basis with parameters measured as required by ASME,Section XI, Article IWP. Relief has been requested in cases where system design or lack of instruments-tion prohibits Connecticut Yankee from complying literally with the code.
Table IWP-1, Connecticut Yankee Inservice Pump Test Program, identifies the pumps to be tested, parameters to be measured, and notes for alternate testing where relief was required.
1.2 Operational Readiness Testing for Valves Tables IWV-1, IWV-2, IWV-3, IWV-4, and IWV-5 include all valves (s
in Connecticut Yankee which are required to be identified under
(
Subsection IWV of ASME Section XI, as further defined in NRC staff guidelines and in meetings with NRC staff reviewers, Connecticut Yankee, and Northeast Utilities personnel.
Most of the valves are presently under surve111ance testing requirements of plant Technical Specifications or adminis-tratively controlled by plant procedures.
In some cases, the-specific requirements of IWV cannot be met due to plant design, operational requirements, or infringement on safety margins.
These situations are noted as required and pertinent relief requests and alternate test schemes are presented.
Valves which cannot be tested while the reactor is at power can, for the most part, be tested during cold shutdowns.
CYAPCO has established a program to commence testing these valves within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown conditions and to continue as time permits on subsequent shutdowns without repeating valve tests until the entire list has been completed.
Leak testing of pressure isolation valves will be conducted to the requirements of IWV-3420.
Relief valve setpoints will be tested in accordance with ASME PTC25.3 - 1976.
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reb 3/7651
.. - All exercising and testing procedures required by Article IWV, O
including schedules and the limiting values of observed para-meters, shall be defined and performed by CYAPCO.
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Locked valves are listed separately. These valves are considered " passive" and,'as such, are not exercised.or tested.
1.3 Augmented Inservice Testing Program The' attached Tables IWP-DG, IWV-DG include all Emergency Diesel j
Generator Auxiliary System pumps and valves in the Raddam Neck Plant whose function is safety-related and are subjected to the periodic tests required by ASME code,Section XI, 1983 Edition, with Addenda through the Summer of 1983 to the. extent possible.
i 1
In some cases, the specific requirements of.IWP and IWV cannot be met due to plant design, operational requirements, or infringement on. safety margins. These situations are noted as required and pertinent Relief Requests are presented.
Boundary dia. grams-of the Fuel Oil, Fresh Water, and Lube Oil Systems were developed and are provided as attachments.
Other references include P&ID 16103-26060, Sheet 2 of 2, "DG Com-
~
pressed Air System".and P&ID 16103-26020, Sheet 1 of 2, "DG Fuel Oil Supply."
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1 1
O re83/7651 2.0 Development of the Inservice Testing Program 2.1 Valve Classification 2.1.1 The valves selected for inclusion in the inservice testing program are. classified as follows:
a.
Category A - Valves for which seat leakage is limited to a specific' maximum amount'in the closed position for. fulfillment of their func-tion.
b.
Category B - Valves for which seat leakage in the closed position is inconsequential for ful-fillment 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:
1 (check valves).
2.2 Valve Selection Bases 2.2.1 The valves selected for inclusion in the IST program include certain Class 1, 2, and 3 valves and their actuating and position indicating systems which are O-required to perform a specific function in shutting down the reactor to the cold shutdown condition or in mitigating the consequences of an accident.
2.2.2 The following valves are exempt from. readiness testing under Section XI:
Valves used only for operating convenience (such a.
as manual vent, drain, instrument, and test valves), valves used for system control (such as pressure-regulating valves), and valves used; only for maintenance.
b.
Valves which are part of external control and protection systems _ responsible for sensing plant:
conditions and providing signals for valve operation.
2.3 Required Valve Testing 2.3.1 The tests required.and their frequencies for the valves designated as; Category A,-B, and C are listed in Table IWV-3700-1. -In certain cases, it is not 3
practical to test individual valves at the listed frequencies, so other frequencies are specified on i
the tables in Section 5.0_through 12.0, Where a test frequency has been designated as each refueling re83/7651 7
outage, a specific request for relief has been pre-t pared as required by 10CFR50.55a(g)(5)(iii). Were a test frequency of.each cold shutdown has been specified, no request for relief is required..
2.3.2 Cold shutdown testing of valves will be conducted as follows:
a.
Testing will commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving the cold shutdown condition, and con-tinue until complete, or the plant is ready.to
. return to power.
b.
Completion of all' valve testing is not a pre--
requisite to return to power.
c.
Any testing not completed during one cold shut-down should be performed during any subsequent cold shutdowns that may occur.before refueling to as closely as possible meet the Code-specified testing frequency.
d.
For planned cold shutdowns, where ample time is available for testing'all the valves identified for the cold shutdown test frequency in the IST program, exceptions to the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may be taken.
2.3.3 Valves or their control systems which are replaced, repaired, or have undergone maintenance which could affect their operation shall be tested to the extent necessary to' demonstrate that the performance para-meters which could have been affected are within acceptable limits.
2.3.4 Valves with remote position indicators shall be observed at least once every two years to verify that i
valve operation is accurately indicated.
2.3.5 Power-operated valves shall be checked for stroke time each time they are full-stroke exercised to meet the requirements of th;s program.
]
2.3.6 Wen practical, valves with fail-safe actuators shall be tested for proper actuation upon loss of power each time the valve is exercised to meet the require-ments of this program.
If the valve can'only be-part-stroke-tested during operation, the fail-safe mechanism shall be tested when the valve is full-stroke tested during a cold shutdown.
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re83/7651 2.3.7 Valves in systems that have been declared inoperable, or are not required to be operable, do not need to be exercised in accordance with the normal schedule.
These valves, however, must be exercised within 30 days of returning the system to service and the test schedule resumed as required by Paragraph-IWV-3416 of the Code.
2.3.8 Valves which operate at a frequency which meets or exceeds the required test frequency need not be additionally exercised to meet the requirements of this program. provided that the required observations-are made, analyzed, and the resultant data recorded at the specified intervals.
2.3.9 The following special testing requirements apply to containment isolation valves:
a.
All containment isolation valves are considered Category A valves.
b.
Valves which perform only a containment isola-tion function and not a pressure isolation func-tion are exempt from Section XI leak rate testing. These valves are leak rate tested under the requirements of 10CFR50, Appendix J.
c.
Valves which perform only a containment isola-tion function and are not rtquired to change position on a containment isolation signal, including normally closed checks valves, are considered passive and are exempt from Section XI operability testing.
r re83/7651
. 2.4 Pump Selection Basis O
2.4.1 The pumps selected for inclusion in the'IST program-include Class 1, 2, and 3 centrifugal and displace-ment type pumps that-are, required to perform a-specific function in the shutting down of the reactor or in mitigating the consequences of an accident and-are provided with an emergascy power source.
2.4.2 The following Code allowed exclusions apply to pump testing:
a.
Drivers are excluded from the requirements of.
Subsection IWP, except where the pump and driver from an integral unit and the pump bearings are in the driver, b.
Class 1, 2, and 3 pumps'that are supplied with emergency power solely for operating convenience are excluded.
2.4.3 All tests and examination procedures required by Sub-section IWP, including schedules, reference values, the location and type of measurement for each of the required test quantities, records of results, and all corrective action taken shall be performed by Connecticut Yankee ISI Engineering.-
2.5 Pump Testing Program 2.5.1 Inservice tests shall be conducted with the pump-operating at nominal motor speed. A series of reference values are determined for quantities listed below, as observed or measured when the equipment is known to be operating correctly.
Inservice Test Ouantities-Inlet Pressure, Pi Discharge Pressure Differential. Pressure, P
Flow Rate, Q Vibration Signature, V Bearing. Temperature Speed N - (if Variable Speed)
Currene (amps)
In place of V (Vibration-Amplitude), CYAPCO will use a Vibration Signature' Analysis program as described in Sectiow 2.5.5.,This program also eliminates the requirement for measuring bearing temperatures 5
annually due to the program's ability to detect be'aring problet at a very early stage.
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~7-In an inservice test, these quantities are remeasured 0
a c > rea ith ** rer re=ce 2 e t e t r 1=-
i 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 j
pump, a new reference value will be established by an j
inservice test run within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after return of
-]
the pump to normal service.
2.5.2 Test Frequency Each inservice test shall include the measurement and
-]
observation of applicable test quantities. An inservice test shall be run on each applicable pump, at a frequency and scope as stated in Table IC-1.
If practicable, this test frequency shall be main-tained during plant shutdown.
If the pump is not tested during plant shutdown, it shall be tested-within one week after the plant is returned to steady i
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, I
recorded, and analyzed.
2.5.3 Analysis and Corrective Action 2.5.3.1 Analysis of test data shall be performed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> following completion of the test. The test quantities shall be com-pared to the ci ovrU e range of quantities f
provided in Table TVP-3100-2 of Subsection IWP. If the ranges cannot be met, reduced range limits, allowing the pump to fulfill i
its function, may be used in lieu of those i
in Table IWP-3100-2. These reduced range limits shall be specified by CYAPCO in-the pump testing procedures. Vibration Signa-i ture Analysis is covered in Section 2.5.5.
2.5.3.2 Corrective action to be taken by CYAPCO in-
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the event that measured test quantities l
fall outside the allowable range shall be as follows:
a)
If deviations fall within the Alert Range, the testing frequency shall be
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doubled until the cause of the devia-
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tion is determined and the condition corrected.
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reb 3/7651 b)
If the deviations fall within the
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Required Action Range, the pump shall-be declared inoperable until'the cause of the deviation is determined and the condition corrected, c)
Corrective action shall'be either-replacement or repair per paragraph IWP-3111 of Section XI, or shall be an-analysis which demonstrates that the condition does not impair pump operability and that the pump will still fulfill its function. When such-an analysis is used, a new set of reference values shall be established.
d)
If, as a result of the analysis, it is suspected that the deviation may be due to the test instruments being out of' calibration, the instruments involved may be recalibrates and the test rerun prior to. declaring the pump-inoperable. This action must be com-pleted within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> of the original test.
2.5.4 Records of Inservice Tests 2.5.4.1 The following information shall be main-tained by CYAPCO to. meet the requirements for inservice testing:-
1)
A record for each pump, including the name of the manufacturer, the model, and the serial ex other identification number.
1
)
2)
An inservice test plan including:
a.
The hydraulic circuit to be used.
._ b.
The location and_ type of measure-ment for each required test-quantity.
c.
The tese quantity reference-values, the limits of P IWP-3100-2),andany'ot$er(Table l
required information.
O re83/7651 3)
Test record giving pertinent informa-
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tion such as test date,-instruments used, results, corrective action-required, and signatures of persons conducting and analyzing the test.
4)
A record of corrective actions'and subsequent inservice tests-verifying operational adequacy.
All inservice test plans and records shall be main-tained at the Connecticut Yankee plant,'and shall be accessible for audit..
2.5.5
~ Vibration Signature Analysis Program -
2.5.5.1 General Procedure Vibration will be monitored at least quarterly using equipment which collects vibration velocity signatures. Overall, vibration velocity (in/sec~RMS) will be compared to the acceptance criteria in Table 2 of Section 4.0.
Reference Velocity shall be the average O
overall velocity determined during an inservice test at reference conditions when the pump is known to be operating accept-ably.
In addition to the above quantitative analysis of overall vibration levels, vibration signatures will be_ reviewed at least quarterly by a knowledgeable person to identify potential bearing degradation or other developing faults. When potential faults are identified, action.as required for a pump in the Alert Range of vibration will be initiated.
The measurement locations to be used for quarterly baseline vibration signature data are established and specified for each pump in the CYAPCO procedures.
O re83/7651 LEGEND FOR VALVE TESTING Exersice valve (full stroke) to verify satisfactory operation Q
per Section XI, IW-3411 and IW-3521.
LT Valves are leak tested per Section XI Article IW-3420.
ILRT -
Containment Isolation Valves are leak tested in conjunction with containment integrated leak test.
LLRT -
Containment Isolation Valves are leak tested in conjunction with Local Leak Rate Testing.
MT Stroke time measurements are taken per Section XI Article IW-3410 for power operated valves.
CV Exercise check valver, to the position required to fulfill their function per Section IW 3521 except as noted in IW 3522.
]
SRV Safety and relief valves are tested in accordance with ASME PTC 25.3-1976.
ET Verify and record valve position before operations are performed and after operations are completed, and verify that valve is locked or sealed.
O re83/7651 CS Exercise valve (full stroke) to verify satisfactory operation i%
at cold shutdown, as noted per Section IW 3416, 3522 and 3412.
RR Exercise valve (full stroke) to verify satisfactory operation
)
during Reactor Refueling Outage based on Relief Request.
PI Visually observe, every two years or less, actua3 valve posi-tion to confirm that remote valve position indications accurately reflect valve operation, IW-3300.
FT Remove actuator power from valves with fail-safe actuators to confirm that the valve travels to its fail-safe position per IW-3415.
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!t1i1i PUMP TEST RELIEF REQUESTS 1.
Charging Pumps Test Requirement - Pump inlet pressure, differential pressure and flow rate will be measured during scheduled tests.
Basis for Relief - Instrumentation for direct measurement of pump inlet pressures is not available. The static pressure and hydrogen head pressure of the volume control tank will be used as the inlet pressure reference. The piping from the volume control tank to the charging pump inlets is a fixed resistance system.
System f3ow rate and differential pressure vary according to requirements of reactor coolant pump seals, make-up, let down, volume control tank level, etc., which makes a test at a referenced flow or differential pressure difficult to achieve. There is no recirculation piping which could be used for such a test.
Alternate Testing CYAPCO will measure all necessary parameters. These will be used to determine a point which will be plotted on the manufacturer's performance curve. The utilization of the manufacturer's perfor-mance curve with offsets showing " alert" and " required action" tolerances is considered a satisfactory technique for evaluating pump test data in this variable resistance system.
2.
Residual Heat Removal Pumps Test Requirement - Measure flow rate and differential pressure during scheduled tests.
Basis for Relief - The quarterly in-service test is conducted using a fixed flow resistance circuit, therefore, measurement of flow rate is not essential for performance of satisfactory tests.
Instruments-tion is not installed to measure inlet pressure to these pumps. An existing pump drain connection has been found not suitable for the inlet pressure gauge connection.
j Alternate Testing - No flow measurement will be made. CYAPCO will determine and reference the RWST level to pump inlet static head to establish inlet pressure.
3.
Auxiliary Feedwater Pumps Test Requirement - Measure flow rate during scheduled tests.
Basis for Relief - The quarterly in-service test is conducted using a fixed flow resistance circuit, therefore, measurement of flow rate is not essential for performance of satisfactory tests, re83/7651 Alternate Testing - No flow measurement will be made.
4.
Low Pressure Safety Injection Pumps Test Requirement - Measure inlet pressure and flow rate during scheduled tests.
Basis for Relief - The quarterly in-service test is conducted using a fixed flow resistance circuit, therefore, measurement of flow rate is not essential for performance of satisfactory tests. Instruments-tion is not installed to measure inlet pressure. An existing pump casing drafn has been found not suitable for the inlet pressure gauge connection.
Alternate Testing - No flow measurement will be made. CYAPCO will determine and reference the RWST level to pump inlet static head to establish inlet pressure.
5.
High Pressure Safety Injection Pumps Test Requirement - Measure flow rate during scheduled tests.
Basis for Relief - The quarterly in-service test is conducted using a fixed flow resistance circuit, therefore, measurement of flow rate is not essential for performance of satisfactory tests.
Alternate Testing - No flow measurement will be made.
6.
Service Water Pumps Test Requirement - Resistance of a system shall be varied until the measured flow rate or differential pressure equals the corresponding reference value.
Basis for Relief - The service water system flow rate varies as river temperature and plant cooling requirements change. These variations, both seasonal and operating, make a test at a referenced flow rate or differential pressure difficult and/or impossible.
Alternate Testing - CYAPCO conducts quarterly in-service tests by using the pump shutoff head (zero flow) as a reference value. River water level relative head is used as pump inlet pressure reference.
7.
,All Pumps Except Charging Pumps Test Requirement - The bearing temperature of all centrifugal pump bearings, and main shaft bearings of reciprocating pumps shall be measured at points selected to be responsive to changes in the temperature of the bearing.
re83/7651
1
- Basis for Relief - Bearing metal' temperature monitoring can be effective in detecting bearing problems. However, no pumps, except the charging pumps, have the permanently installed temperature sensors required to measure bearing metal temperatures; i.e., outer race of anti-friction bearings or babbitt lining of sleeve bearings.
The annual measurement of bearing housing temperature.is far less j
effective in detecting bearing problems than the quarterly perfor-mance of vibration signature analysis being performed by'CYAPCO.
i
.HPSI and LPSI pump bearings are located deep inside the pump o
casing and are surrounded by the oil reservoir. There is no design provision for directly measuring bearing temperatures.
A quarterly check on the lubrication level and. vibration tests is made.
4 Service water pumps have five bearings-primarily shaft steady-o ing bearings.
It is not possible to measure temperatures of the four lower bearings due to pump casing designs. A quarterly check on the lubrication level and vibration tests are done.
The upper bearing temperature of the service water pumps is recorded.
Residual heat removal pumps have no design provision for' direct o
measurement of bearing temperatures and the results of using a handheld pyrometer ere questionable. A quarterly check on lubrication level and vibration tests are done.
Auxiliary feedwater pumps have no design provision for direct o
measurement of bearing temperatures.
Bearings are enclosed in oil reservoir and are not directly accessible. A quarterly check on lubrication level and vibration' tests are done.
Alternate Testing Record and analyze pump vibration as' scheduled. This analysis will provide more meaningful analysis of pump bearing condition than the annual measurement of bearing temperatures.
8.
All Pumps Test Requirement - Measure at least one displacement vibration amplitude during each scheduled test.
Basis fq Relief and Alternate Testing To meet the vibration monitoring of ASME,Section XI Section IWP, exception is taken to the specific vibration requirements of IWP and an alternate, more effective vibration analysis program, as described a
herein, is used. During the scheduled in-service pump test, vibration velocity is measured. Vibration velocity is a function of displace-ment and frequency and is a direct measurement of component condition.
re83/7651 In addition, a supplemental program is performed which er.hances the evaluation of the component condition. This program consists of
\\
signature analysis plotted on plotting paper and retained as a permanent record. These plots are compared to baseline data and to previous data for a continuing evaluation of the condition of the component. The vibration signature consists of an automatic plot of vibration amplitude in velocity versus frequency typically over a frequency range of 0-500 cycles per second.
This supplementalal vibration program analysis approach provides for the early detection of deterioration of pump mechanical con-dition, a determination of the cause of problems, and a more accurate assessment of the vibration severity.
Criteria for evaluation of changes as to cause, severity, and.the establishment of alert and required action ranges shall be specified in the CYAPC0 procedures.
Shown below are the allowable ranges for Vibration Test quantities. The acceptance criteria is based on an ASME publication 76-WA/NE-5 " Suggested Improvements in the Measure-ment of Pump Vibration for Inservice Inspection." This acceptance criteria has been revised by Connecticut Yankee to reflect actual pump vibration data and provides a conservative basis for analysis of pump vibration.
The NRC approved ASME publication 76-WA-NE-5 " Suggested Improve-ments in the Measurement of Pump Vibration for In-Service Inspec-tion," in their safety evaluation of December 29, 1983 and Connecticut O
Yankee has revised this publication to evaluate pump vibration more conservatively in their review of the Inservice Testing Frogram on May 12, 1987.
]
Table 2 Suggested Revision of Table IWP-3100-2 Allowable Ranges for Vibration Test Quantities Test Acceptable Quantity Range Alert Range Required Action Range Wen O f v f.10 in/sec Ohv $.15 in/sec
.15 in/sec <v g v >.3 in/sec v
r
.3 in/see v Wen.10 in/sec < v <
02 v.$.3 in/sec
.3 in/see < v e v >.45 in/sec
- ~
~
.15 in/see
.45 in/sec Wen.15 in/sec <v {
02 v $.45 in/sec 0.45 in/sec (v f v >.75 in/sec v
r
.3 in/sec
.75 in/sec v Wen.3 in/sec < vrg Ohv g.75 in/see
.75 in see (v <
v p 1.0 in/sec
.6 in/see 1.0 in/see Definitions:
v = velocity measured in inches /second, peak v = reference velocity measurement (initial measurement after installation or rework)
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i ~ SYSTEM:
Valves:
RC-SOV-596A, B, C, D, and PR-SOV-552A, B, C, and D j
Basis for Test Frequency:
It is not practical'to exercise these' valves during normal operations. Failure of valve in a nonconservative position could cause a shutdown. Timing the operation of solenoid valves is not.practica1'due-to the speed of operation.
l These valves will be exercised and position indicators checked at cold i
shutdown.
2.
Valves:
PR-A0V-568'and PR-A0V-570 l
l Basis for Cold Shutdoun It is not practical.to exercise:
Tert Frequency these valves during normal opera-tions.
Failure of valve'in a nonconservative position could cause a shutdown.
These valves will'be exercised and O
position indicators checked at cold.
shutdown.
3.
Valves:
PR-A0V-574 and PR-A0V-573 Basis for Test Frequency:
Cycling these' valves at full power would disrupt pressure which could lead to a shutdown'.
These valves will be tested at cold shutdown.
4.
Valves:
RC-MOV-501, 512, 513, 524, 526, 537, 538, and 546 Basis for Test Relief It is not possible to exercise and Test Frequency:
these valves during normal operations. Operation of these valves could cause flow to be lost in'the loop and would isolate a steam generator, causing a plant shutdown and' loss'of a heat sink.
It is also not practical.to exercise these valves at cold shutdown.
Alternate Testing:
These valves will be tested during refueling.'
re83/7651
. _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - 5.
Valves:
RC-CV-545, 509, 523, and 536 O
NOTE:
These valves may not be possible to test due to pipe geometry. A test will be attempted in ?987 outage.
i I
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_ ______ SYSTEM: '
POWER OPERATED RELIEF VALVES AIR ACCUMULATOR' SYSTEM
.O 1.
Valves:
'CA-SOV-752'and CA-SOV-754 Basis for Test Frequency:
These valves are tested in conjunc-tion'with the PORVs..'It is not practical to exercise these valves during normal operation. Failure of-these valves could cause the PORVs to be in~a nonconservative position.-
which could cause a shutdown.
Timing the operation of solenoid valves'is not practical due'to the speed of operation..
These valves'will be tested at cold shutdown.
O 3
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SYSTEM:
SAFETY INJECTION (U
\\
1.
Valves:
SI-CV-103, 107A, 107B, and SI-CV-872A/B Basis for Test Frequency:
Full or partial valve exercising requires that flow be established into the reactor vessel from the refueling water storage tank, using the LPSI pumps.
System pressure downstream of these valves does not allow flow during normal operations.
During cold shutdown, available volume in the reactor vessel is insufficient to accommodate flow required for exercising these
)
valves.
Introduction of RWST water j
to the reactor coolant system requires additional waste liquid processing which is time consuming
-l and delays start-up.
Alternate Testing:
CYAPCO will perform a system flow l
test each refueling to exercise j
these valves. The water will be q
pumped from the RWST to the reactor vessel. The flow will be determined nb by measuring the discharge and 4
suction head. CY will calculate the pump head to find the corresponding
{
flow from the pump curve that i
indicates valve performance.
2.
Valves:
SI-CV-856A/B and SI-CV-862A/B/C/D l
1 Basis for Test Frequency:
In order to full stroke these check l
valves, flow must be established it to the reactor vessel from the refueling water storage tank using the HPSI pumps.
System pressure downstream of these valves does not allow flow during normal operation.
l During cold shutdown, available l
volume in the reactor vessel is insufficient to accommodate flow required for exercising these valves.
Introduction of RWST water I
to the reactor coolant system l
requires additional waste liquid processing which is time consuming and delays start-up.
f n
<J re83/7651
27 -
1 Alternate Testing:
CYAPCO will perform a system flow-
'{~J test each refueling to exercise T
these valves. The water will be pumped from the RWST to'the reactor vessel. The flow will be determined by measuring the discharge and j
suction hesd.' CY will calculate the pump head to find the corresponding flow from the pump curve that irdicates valve performance, j
3.
Valves:
SI-MOV-861A/B/C/D Basis for Test Frequency:
The inability to check the closed integrity of SI-CV-862A/B/C/D prior i
to exercising SI-MOV-861A/B/C/D.
These valves interface'directly with the RCS at operating pressure.
Alternate Testing:
These valves will be full stroked at cold shutdowns.
4.
Valves:
SI-MOV-24 Basis for Test Frequency:
It is not practical to exercise this valve during normal operations or-O cold shutdown.
Failure of valve in
{
a nonconservative position would j
disable the HPSI system, causing a j
plant shutdown and delaying plant 1
start-up.
CYAPCO will exercise this valve during refueling and partially stroke test (one inch of travel) quarterly.
5.
Valve:
SI-MOV-871A/B Basis for Relief and The inability to check the closed Test Frequency:
integrity of the 872A/B valves prior to exercising MOVs 871A/B. These valves interface directly with the RCS at operating pressure. There is no way to perform a leakage test on-these valves. They are welded directly to CD-CV-872A/B.
O re83/7651 J
1.
Alternate Testing:
These valves will only be full stroked at cold shutdowns.
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SYSTEM:
RESIDUAL HEAT REMOVAL SYSTEM i
(~.
1.
Valves:
RH-MOV-23 and RH-MOV-34 Basis for Test Frequency:
.The containment spray system is set up such that opening either-RH-MOV-23 or-34 will initiate flow.
By entering the containment and closing manual valve RHR-V-23A, the valves could be "no' flow"' stroked, but technical specifications 3.11 prevent this, as it would be dis-abling the containment spray system.
These valves.will be exercised during cold shutdowns.
2.
Valve:
RH-MOV-33A/B Basis for Test Frequency:
RH-MOV-33A/B provide a flow path' from the RER system to the charging pump suction header.. Stroking these valves varies the suction header pressure in the charging system and could'cause charging. pump flow oscillations..
()
These valves will be exercised at cold shutdowns.
3.
Valves:
RH-MOV-780'and 781' Basis for Test Frequency:
These valves are interlocked with the reactor coolant system such that operation is not possible unless the 3
RCS pressure is less than.375 psig, j
1 These valves will be exercised during cold shutdowns.
4.
Valves:
RH-MOV-803 and 804 Basis for Test Frequency:
These valves are interlocked with the reactor. coolant system such that operation is not possible unless the RCS pressure is less than 375 poig.
These valves will be exercised at cold shutdowns.
s O
re83/7651-
v.:.
5.
= Valves:
RH-CV-783'and RH-CV-808A 1
j Basis for Relief:
These valves are located in piping
.]
which is.normally drained and do not; function unless water is present in-the containment sump, as.would be
.the case during.a LOCA. :It is not practicable to flood the containment floor and_ sump to hydraulically exercise these valves..'In order to test these. valves'during. refueling,-
it would require that the RHR system be taken out of' service. To take.
the RER system out.of service would
. require the core to be. unloaded.
This.is not practical-to do every..
outage.. Done once every five years.
Alternate Testing:
Both-of the'se valves will be disas -
~
sembled and inspected to determine interior' condition and operability-every five years.oriat'a less.
frequency when.'ever the core is.-
~
unlosded.
RH-CV-783;was disassem -
bled and inspected in February 1979,.
l
.RH-CV-808A in February 1983, and-found to'be.in satisfactory condi-J
\\
tion.
6.
Valves:
RH-CV-788A/B 1
Basis for Test Frequency:
Full flow through these valves'is
.l not;possible except;at cold' shutdown ~~
.at which time 1the system is~in operation.- Part stroking is done monthly.as the pumps are~ tested.~
These valves will be full stroked at-cold shutdowns.
l O
re83/7651
l1{1
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t
1 1 SYSTEM:
CHEMICAL AND VOLUME CONTROL 1.
Valve:
BA-MOV-32 Basis for Test Frequency:
Cycling this valve could potentially cause a highly borated solution to reach the RCS, via the charging system, which is in continuous
-service.
Exercise valve for operability at cold shutdown.
2.
Valve:
LD-MOV-200 Basis for Test Frequency:
Closing this normally open valve to check operability would disrupt letdown flow. This would cause flow / pressure transients in the
]
charging and letdown systems.
j Exercise valve for operability at cold shutdowns.
3.
Valve:
CH-MOV-257 t'
Basis for Test Frequency:
Closing this normally open valve would cause the charging pumps to cavitate. Part stroke testing is not possible (no jog control on i
valve operator).
Exercise valve (full stroke) during cold shutdowns.
4.
Valves:
CH-FCV-110/110A Basis for Test Frequency:
These valves are arranged in paral-I lel flow paths, such that either valve can be utilized to control 1
charging flow to the RCS. The valves are normally open and modu-late to control flow. Exercising-these valves full stroke during' 1
normal operations would cause flow and pressure transients in the charging system.
These valves will be full stroke exercised at cold shutdown.
i O
i i
re63/7651 1
5.
Valve:
BA-CV-320
(
\\
Basis for Test Frequency:
Exercising this valve to the open position must be done by passing j
flow through it and this could j
potentially cause a concentrated j
boric acid solution to reach the reactor via the charging system.
Exercise valve for operability at cold shutdown.
6.
Valve:
BA-MOV-366 3
i Basis for Test Frequency:
Operation of this valve while the l
plant is at power could potentially I
cause a concentrated boric acid solution to reach the reactor via the charging system.
This valve will be exercised at cold shutdowns.
7.
Valve:
BA-CV-372A Basis for Test Frequency:
Operation of this valve while the i
plant is at power could cause boric j
()
acid solution to reach the reactor via the charging system.
This valve will be exercised at cold shutdowns.
8.
Valve:
BA-MOV-373 i
Basis for Test Frequency:
Operation of this valve while the plant is at power could potentially cause boric acid solution to reach the reactor.
Alternate Testing:
This valve will be exercised at cold shutdowns.
i O
r63/7651
_ 40 9.
Valve:
BA-CV-387 Basis for Test Frequency:
Exercising this valve to the open position.must be done by passing j
flow through it.
This could j
potentially cause a concentrated-boric. acid solution to reach the reactor via the charging system.
]
This valve ~will be exercised at cold shutdowns.
i I
- 10. Valve:
DH-MOV-310 Basis for Test Frequency:
DH-MOV-310 is a normally closed valve. This system is.used for-draining the loops, however, this system could be.used for alternate letdown. Exercising this valve could cause overpressurization of the loop drain system.
l This valve will be exercised during cold shutdown.
11.
Valve:
CF-MOV-331 Basis for Test Frequency:
In order to cycle this valve, reactor coolant system pressure must be greater than 100 psig, but less than 1,000 psig. Cycling this valve-at full power will disrupt.RCP seal flow which will result in damaging the #1 seal on the RCPs.
This valve will be exercised at cold shutdown.
i
- 12. Valves:
CH-MOV-311, 312, 313, and 314 Basis for Test Frequency:
Cycling these valves at full power-would disrupt RCP seal flow which could cause a failure of the RCP's
. seals.
These valves will be exercised at cold shutdowns, i
O re83/7651
1 i?
1.j 1
- 13. Valve:
CH-MOV-298 Basis for Test Frequency:
Cycling 'this valve at full -power
would disrupt pressurizer pressure which could lead to a shutdown.
This valve will be exercised'at cold.
shutdown.
14.
Valves:
FH-MOV-578, 535, 522, and 508-l Basis.for Test Frequency The inability to check'the' closed and Relief Request:
. integrity of the FH-CV-296 prior to exercising thes'e MOVs.
These valves ' interface directly with the RCS at operating pressure.
This system is normally used.to' fill l
the RCS, during;- refueling..
.]
These valves will be tested at refueling.
]
- 15. Valves:
DH-MOV-544, 534, 521, and 507.
Basis.for Test Frequency These valves interface directly with 3
and Relief:
the RCS of operating pressure. This system is normally used to drain the RCS during refueling.
These valves will be tested at refueling.
I i
.i 1
lO i
re83/7651
8 2 8 s
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vt R
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SYSTDi:
MAIN STEAM SYSTEM
'O..
1.
Valves:
MS-NRV-11, 21, - 31, and 41' Basis for. Test Frequency:
Failure of valve in a nonconserva--
tive position would cause a-loss of
.j system function.
j These valves will be full stroke tested at cold shutdowns. LValves~
are partially stroked quarterly per 7
technical specifications,.4.9.
)
2.
Valves:
MS-TV-1211-1, 2,-3, and'4 Basis for Test Frequency:
Failure of valve in nonconservative position would cause loss of system' function.
Full strok'e exercise and measure stroke time during cold shutdown.
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, SYSTEM:
FEEDWATER SYSTEM (q
J 1.
Valves:
FW-CV-153 and FW-CV-184 Basis for Test Frequency:
Full or partial stroke testing of these_ valves requires that an i
auxiliary feedpump lue started and flow be established to the steam.
generators.
This test is undesir-able while the reactor isfat power because of the steam generator thermal shock potential. The pumps take suction on the demineralized water storage tank (cold water).
These valves will be exercised at cold shutdown.
2.
Valves:
FW-CV-156-1,
-2,
-3, and -4 q
j Basis for Test Frequency:
Full or partial stroke testing of these valves requires that an auxiliary feedpump be started and flow be established to the steam generators. This test is undesir-
]
able while the reactor is at power
(])
because of_the steam generator
)
thermal shock potential. The pumps take suction on the demineralized water storage tank (cold water).
)
These check valves will be exercised i
at cold shutdowns.
3.
Valves:
FW-FCV-1301-1,
-2, -3, and -4 Basis for Test Frequency:
Failure of. valve in nonconservative position would cause loss of system function.
These valves will be cycled at cold shutdowns.
4.
Valves:
FW-MOV-11, 12, 13, and 14 Basis for Test Frequency:
Failure of.these valves in a close'd or partially closedLeondition would cause loss of system _ function.
Valves cannot be partially stroke tested.
These valves will be cycled at cold
()
shutdowns.
reb 3/7651
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SYSTEM:
SERVICE WATER SYSTEM fsU 1.
Valves:
SW-MOV-1 and 2 Basis for Test Frequency:
These valves control service water cooling to several essential plant loads. Failure of valves in a nonopen position could cause overheating of these loads,
)
resulting in loss of generation.
These valves will be full stroke tested and timed at cold shutdowns.
2.
Valves:
SW-MOV-3 and 4 Basis for Test Frequency:
These valves control service water f
cooling to the component cooling heat exchangers.
Failure of valve in a nonopen position could cause j
overheating, resulting in loss of j
generation.
These valves will be full stroke tested and timed at cold shutdowns.
{}
3.
Valves:
SW-MOV-5 and 6 Basis for Test Frequency:
Stroking there valves requires that the service water system be cross-connected with the component cooling water system to provide emergency flow to the residual heat removal l
heat exchangers. The service water system utilizes water from the Connecticut River. The component cooling water _ system is a closed system containing potentially contaminated water.
Cross-connect-
)
ing could result in releasing nonconforming water to the river and require a major cleanup of system components, which would require that they be taken out of service during the restoration process.
j Alternate Testing:
We propose to exercise these valves each refueling.
L) re83/7651
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S
1 i SYSTEM:
VARIOUS CONTAINMENT ISOLATION 0-1.
Class / Category:
2--A, 2A-C, 1-A, 1-AC Basis for Test Frequency:
This list consists of valves whose 5
safety feature is containment
-isolation. Those containment isolation valves which are used also for pressure isolation are also:
listed under the particular system in which.they operate. Pressure 1
isolation valves are tested in l
accordance with IWV-3420.
Operability testing of these valves
'during normal. plant operation could cause a loss of containment integrity and/or system function if a valve failed in a nonconservative i
position. Present technical-l specifications and associated procedures require both an individual and an integrated leakage rate test for containment isolation valves and penetrations. Procedures also require repair of any valve j
exceeding the. leakage limit. The l
Q sum of leakage from all penetrations
]
v and isolation valves is used to determine an integrated leakage rate which is compared to the maximum allowable leakage rate stated in the technical specifications.
Alternate Testing:
CYAPCO proposes to use existing procedures for leak testing of valves used as containment-isola-tion. Modifications to procedures, as agreed upon by CYAPCO and NRC
]
staff, concerning " Appendix J" tests and exemptions, will be reflected in-l this program. All " active" contain-
.i sert isolation valves are demon-strated operable during cold shut-i down or reactor refueling at least j
once each 18 months, by verifying that all valves actuate on contain-ment isolation signals in accordance j
with plant technical specifications.
l Passive valves do not require exercising.
j O
reb 3/7651
.. _ I SYSTEM: CHARGING RCS v'
2.
' Valves:
Basis for Relief Request:
CYAPCO had previously requested an exemption from the Type C testing requirements of Appendix J for the reactor coolart-charging (P-8)-
Pis previous report was based on the seismic design of.
system piping inside containment and the proposed seismic qualification' of system piping from the isolation valves of Penetration ?-8 to'its water source.
Subsequent evaluations determined such qualification to be a lengthy and costly effort; therefore,.CYAPCO intends to modify Penetration'P-8 to permit Type C testing. In the interim, although Penetration P-8 is not currently Type C tested, the isolation valves in this penetration-3 are exposed to water subjected to containment pressure through the~
vented reactor coolant system during the CILRT.
The valves are exposed to containment pressure in-the direction of accident pressure with the back side of the valves-depressurized.
Further, the portion of the system'outside containment is checked for liquid leakage in accordance with Administrative-Technical Specification 3.14; system leakage is accounted for in off-site dose consequence calculations, per 10CFR100.
Such leak testing provides additional assurance that the potential for significant containment atmosphere leakage through this penetration is ninimized.
O re83/7651
.]
, )
l CYAPCO believes a schedular exemption from the Type C testing requirements'of Appendix J is
{
justified. based on the above
{
information, as well as the long lead time for equipment needed to modify this penetration, the level of design and analysis required, and the need to integrate these modifications with the ultimate resolution of the SEP review of containment isolation valve configurations per 10CFR50,-
Appendix A.
This' approach'is consistent with the ALARA philosophy.
in that it avoids repetitive modifications to the same penetration. The ultimate resolution of-this issue will be accomplished within the framework of the Haddam Neck Plant ISAP.
Reference:
1.
Docket No. 50-213 from J. F.
Opeka to C. I. Grimes, "10CFR50, Appendix J - Request for Exemption," dated March 12, J
1986.
2.
Docket No. 50-213 from J. F.
Opeka to C. I. Grimes, "10CFR50, Appendix J, Revision 1 to 3
Request for Exemption," dated-l July 15, 1986.
l O
re83/7651
! j i
SYSTEM:
SAFETY INJECTION 3.
Valves:
SI-V-860 Basis for Relief Request:
Valve SI-V-860 is a 3" locked close manual gate valve that isolates the 3
cavity fill line. The cavity fill line branches off the high pressure safety injection header inside containment. This valve is not LLRT tested, but is tested during the ILRT in the accident direction with air on the containment side of the valve.
The downstream side of the valve is covered with liquid, but vented during the ILRT. This is consistent with expected post-LOCA conditions because valve SI-V-860 is in a vertical run with liquid trapped above it due to testing of the high pressure safety injection system.
The recent PRA analysis of the penetration resulted in a total risk (due to noncompliance with
(~)
Appendix J) of 0.9 man-rem over the
\\>
life of the plant. Of the total
]
risk, 0.3 man-rem is due to valve SI-V-860 not being tested.
It is
)
assumed that SI-V-860 leaks 5 percent of the containment air volume per day, which is greater than twice the worst measured containment isolation valve as-found i
leakage at the plant. Clearly, the risk due to this untested valve is very small.
Since the ILRT does leak test this valve, the actual risk will be much less than 0.3 man-rem.
CYAPCO believes a schedular exemption from the Type C testing requirements of Appendix J is justified based on the above information as well as the long lead time for equipment needed to modify this penetration, the level of design and analysis required, and the need to integrate these modifications with the ultimate
(~h resolution of the SEP review of q) 2r63/7651
' i containment isolation valve I
f~)
conf f gurations per 10CFR50, Appendix A.
This approach is consistent with the ALARA philosophy j
in that it avoids repetitive modifications to the same j
penetration. The ultimate resolution of this issue will be accomplished within the framework of the Haddam Neck Plant ISAP.
Reference:
1.
Docket No. 50-213 from J. F.
Opeka to C. I. Grimes, "10CFR50, Appendix J - Request for Exemption," dated March 12,
)
1986.
4 2.
Docket No. 50-213 from J. F.
Opeka to C. I. Grimes, "10CFR50, Appendix J, Revision 1 to Request for Exemption," dated July 15, 1986.
(,
\\s reb 3/7651
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1
.79 -
t TESTING REQUIREMENTS FOR PRESSURE ISOLATION, VALVES
.(
I SI-CV-862A/B/C/D - Valves are subjected to type "C" test as containment 1
isolation check valves and a 150#. leakage test for pressure isolation.
]
valves.
1 SI-V-863A/B/C/D - Valves are subjected to a 150# 1eakage test for o
pressure isolation valves and a Type "C" containment isolation check
)
valve.
1 SI-MOV-861A/B/C/D - Each valve is subjected to's 150# 1eak test.
SI-MOV-871A/B and SI-CV-872A/B are velded to one another with no pro-vision for leak testing CD-MOV-871A/B using reactor coolant pressure.
1 During the system hydrotest at startup, SI-MOV-871A/B are open, thus',
subjecting SI-CV872A/B to reactor coolant pressure between 350-375 psig.
Leakage is measured at that time.
i RH-MOV-803,804,780,781 are individually leak tested during the system hydrotest using reactor coolant at 350-375 psig.
FH-MOV-578-535-522-508 piping is designed for reactor coolant tempera-'-
ture and pressure back to charging pumps. No tests are made.
DH-MOV-310,FH-V-311 are individually leak tested at.150# for pressure isolation valves.
re83/7651 FH-CV-296'is subjected to a Type "C" test for containment isolation O-
. valves. Piping is designed for reactor coolant temperature and pressure, back to the charging pumps. No pressure' isolation test is required.
DH-MOV-562,507,521,534,544 and DH-V-502,516,529,539, and 525 are not individually tested.
If leakage occurs, it is cooled by the drain cooler and piped back by way of DH-MOV-310 or DH-V-311 to either the volume control tank or to the primary drain tank, both of which are monitored and alarmed at the main control board. These valves are not required to be tested.
Loop fill and loop drain valves (FH and DH) are listed in Table IWV.
I These valves are not used in bringing the reactor to a safe shutdown condition and are not normally used to mitigate the consequences of an accident, however, these valves (fill only) may be used as backup for small break LOCA. These valves are normally used to fill and/or drain loops during refueling operations.
O re83/7651 TABLE IWV-5 j
,U SAFETY / RELIEF VALVE SETPOINTS Service Valve Number Valve Type Setpoint (Tolerance)
Press. Safety Valve PR-SV-584-3" Safety 2485 1%
Press. Safety Valve PR-SV-585 3" Safety 2535
!1%
Press. Safety Valve PR-SV-586 3" Safety 2585 1%
RWST Recirculation SI-RV-870 1" Relief 1500 11%
Relief to RWST RH-RV-715 3" Relief 500 10 psig A
Service Water to SF HX SW-RV-309 6" Relief 150 3%
U SG No. 1 Main Steam Safety MS-SV-11 6" Safety 985 10 psi l
SG No. 1 Main Steam Safety MS-SV-12 6" Safety 1015 11%
SG No. 1 Main Steam Safety MS-SV-13 6" Safety 1025 11%
}
f SG No. 1 Main Steam Safety MS-SV-14 6" Safety 1035 1%
i SG No. 2 Main Steam Safety MS-SV-21 6" Safety 985 110 psi
{
SG No. 2 Main Steam Safety MS-SV-22 6" Safety 1015 11%
l SG No. 2 Main Steam Safety MS-SV-23 6" Safety 1025 11%
SG No. 2 Main Steam Safety MS-SV-24 6" Safety 1035 11%
SG No. 3 Main Steam Safety MS-SV-31 6" Safety 985
.10 psi SG No. 3 Main Steam Safety MS-SV-32 6" Safety 1015 11%
SG No. 3 Main Steam Safety MS-SV-33 6" Safety 1025 1%
4 SG No. 3 Main Steam Safety MS-SV-34 6" Safety 1035 11%
SG No. 4 Main Steam Safety MS-SV-41 6" Safety 985 10 psi l
l re83/7651 I
i Service Valve' Number
-Valve Type
'Se tpoint ' (Tolerance)
. O SG No. 4 Main Steam Safety
'MS-SV-42 6" Safety
'1015 21%.
SG No.'4 Main Steam Safety MS-SV-43
'6" Safety 1025 1%'
SG No. 4 Main Steam Safety MS-SV-44 6" Safety 1035.-
11%
SV for Aux. Feed Pump "A" MS-SV-1216A
.3" Safety 650
-!!0 psig SV for Aux. Feed Pump "B" MS-SV-1216B 3" Safety 650 110 psig Low Pressure Pressurizer Relief -PR-RV-587 3" Relief 380 110'psig Low Pressure Pressurizer Relief PR-RV-588 3" Relief 380 10 psig SV for Drain Header
'DH-RV-1847 2" Relief 150 3%
I Seal Water Return Line Relief CH-RV-332 3" Relief 140 3%.
Heter Pump Suction Line Relief BA-RV-279
.5" Relief 150-13%
PR-A0V-568 Control Air CA-RV-838A
.25" Relief 100 13%
A PR-A0V-570 Control Air CA-RV-838B
.25" Relief 100 3%
%)
Containment Instrument Air CA-RV-719
.25" Relief 145 10/5 psig i
Containment Instrument Air CA-RV-720
.25" Relief 145 10/5 psig l
Containment Instrument Air CA-RV-721
.25" Relief 145 t0/5 psig Containment Instrument Air CA-RV-829
.5" Relief 170 13 psig SW/ Component Cooling to RHR CC-RV-763A 1.5" Relief 150 3%
SW/ Component Cooling to RHR CC-RV-763B 1.5" Relief 150 13%
Meter Pump Discharge CH-RV-280 1.5" Relief 2735 1%
Loop Pressure Equal. Line*
RC-CV-509 1.5" Relief 200 P.
Loop Pressure Equal. Line*
RC-CV-523 1.5" Relief 200.
P Loop Pressure Equal. Line*
RC-CV-536 1.5" Relief 200 P
Loop Pressure Equal. Line*
RC-CV-545 1.5" Relief 200 P
l i
- This test may not be possible due to pipe geometry. A test will be attempted in 1987 outage, re83/7651
Il l
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- 84 _
i Relief Request #1P Inservice Test Program (IWP)
Emergency Diesel Generator Auxiliary Systems Connecticut Yankee SYSTEM:
Fuel Oil AFFECTED PUMPS:
Engine-driven fuel oil pumps TEST REQUIREMENT:
Per Table IWP-3100-1, measure the speed of variable speed pumps.
~ BASIS FOR RELIEF:
'The above listed pumps are variable speed in'that-they are driven by the diesel engine and, therefore,-' change speed as the diesel does. However, at the time of testing, the diesel will be of a procedurally specified constant load-and speed. Therefore, for the
. purposes of this testing, these pumps are considered constant speed.
ALTERNATE TESTING: The affected pumps and systems will be. monitored during diesel engine operation using procedural specifications to assure satisfactory performance.
j Il O
i 1
i re83/7651 Relief Request //2P
/
Inservice Test Program (IWP)
Emergency Diesel Generator Auxiliary Systems Connecticut Yankee SYSTEM:
Lube 011 AFFECTED PUMPS:
Main lube oil pumps Piston oil pumps Scavenging oil pumps TEST REQUIREMENT:
Per Table IWP-3100-1, measure the speed of variable j
speed pumps.
BASIS FOR RELIEF:
The above listed pumps are variable speed in that they are driven by the diesel engine and, therefore, change speed as the diesel does. However, at the time of testing, the diesel will be a procedurally specified constant load and speed. Therefore, for the i
purposes of this testing, the pumps are considered constant speed.
ALTERNATE TESTING: The affected pumps and systems will be monitored during diesel engine operation using procedural specifications to assure satisfactory performance.
v 1
I i
l fV re83/7651
Relief. Request ll3P
.O, t= ervice teet rre8re- (1"r>
Emergency Diesel Generator Auxiliary Systems Connecticut Yankee U
SYSTEM:
Cooling Water
]
AFFECTED PUMPS:
Cooling water pumps TEST REQUIREMENT:
Per Table IWP-3100-1, measure the. speed of variable-i speed pumps.
BASIS FOR RELIEF:
The above listed pump's'are variable speed in'that they are driven.by the diesel engine and, therefore, change speed as the
)
diesel doee.- However, at the time of testing, the diesel will be a j
procedurally specified constant load and speed. Therefore, for the-1 purposes of this. testing, the pumps are considered constant speed.
j i
-_ ALTERNATE TESTING: The affected pumps and systems will be monitored during diesel engine operation using procedural specifications to assure satisfactory performance.
O i
O' re83/7651 l
__ Relief Request #4P Q,
Inservice Test Program (IWP)
Emergency Diesel Generator Auxiliary Systems Connecticut Yankee SYSTEM:
Fuel Oil AFFECTED PUMPS:
Transfer pumps Engine-driven pumps i
Electric pumps TEST REQUIREMENT:
Per Table IWP-3100-1, measure the following J
quantities:
Inlet pressure (before pump startup and during test)
Differential pressure I
Flow rate Bearing temperature BASIS FOR RELIEF:
At this time, there is no installed in.
. tion to measure any of the above parameters.
i ALTERNATE TESTING: The affected pumps and systems will be monitored during diesel engine operation using procedural specifications to assure satisfactory performance.
O re83/7651
. 88 --
J 1
Relief Request //SP hg Inservice Test Program (IWP)
Emergency Diesel Cenerator Auxiliary Systems Connecticut Yankee SYSTEM:
Lube Oil AFFECTED PUMPS:
Main Lube Oil Pumps Circulating Oil Pumps i
Piston Oil Pumps Turbocharger 011 Pumps Scavenging 011 Pumps TEST REQUIREMENT:
Per Table IWP-3100-1, measure the following quantities:
Inlet pressure (before pump startup and during test)
Differential pressure Flow rate Bearing temperature BASIS FOR RELIEF:
At this time, there is no installed instrumentation to measure any of the above parameters.
ALTERNATE TESTIMG: The affected pumps and systems will be monitored during diesel engine operation using procedural specifications to assure satisfactory performance, o
(
re83/7651
" Relief Request #6P
()'
Emergency Diesel Generator Auxiliary Systems
- Inservice Test Program (IWP)
Connecticut Yankee SYSTEM:
Cooling. Water AFFECTED PUMPS:
Cooling Water Pumps TEST REQUIREMENT:
Per Table IWP-3100-1, measure the following quantities:
Inlet pressure (before pump startup and during test) '
Differential pressure Flow rate Bearing temperature BASIS FOR RELIEF:
At this time, there Lis no installed instrumentation to measure any of the above parameters.
ALTERNATE TESTING: The affected pumps and' systems will be monitored during diesel engine operation using procedural specifications to assure satisfactory performance.
()
l 1
l rdB3/7651 l
l-O i
1 e
m -
Relief Request #7P Inservice Test Program (1WP)
Emergency Diesel Generator Auxiliary Systems Connecticut Yankee SYSTEM:
Fuel Oil
'AFFECTED PUMPS:
Engine-driven fuel oil pumps Electric-driven fuel oil pumps TEST REQUIREMENT:
Per Table IWP-3100-1, measure vibration amplitude.
BASIS FOR RELIEF:
The above listed pumps are mounted to the diesel engine or connected support structures. All meaningful vibration readings will be' overwhelmed by the vibration of the diesel engine itself.
ALTERNATE TESTING: The affected pumps and systems will.be monitored during diesel engine operation using procedural specifications to assure satisfactory performance.
O 1
J
.I l
l i
i re83/7651 j
Relief Request #8P i
Inservice Test Program (1WP) l Emergency Diesel Generator Auxiliary Systems Connecticut Yankee SYSTEM:
Lube Oil AFFECTED PUMPS:
Main lube oil pumps Piston oil pumps Scavenging oil pumps TEST REQUIREMENT:
Per Table IWP-3100-1, measure vibration amplitude.
BASIS FOR RELIEF:
The above listed pumps are mounted to the diesel engine or connected support structures. All meaningful vibration
)
readings will be overwhelmed by the vibration of the diesel engine i
itself.
ALTERNATE TESTING: The affected pumps and systems vill be monitored during diesel engine operation using procedural specifications to assure satisfactory performance.
O re83/7651 Relief Request //9P
' Inservice Test Program (IWP).
Emergency Diesel Generator Auxiliary Systems Connecticut Yankee SYSTEM:
' Cooling Water
'AFFECTED PUMPS:
Cooling water pumps TEST REQUIREMENT:
.Per Table IWP-3100-1, measure vibration amplitude.
BASIS FOR RELIEF:
The above listed pumps are mounted to the diesel engine or connected support structures. All meaningful' vibration readings will be overwhelmed by the vibration of the diesel engine itself.
ALTERNATE TESTING: The'affected pumps.and systems will be monitored during diesel engine operation using prricedural specifications to assure satisfactory performance.
O re83/7651 e
I l Relief Request #10P
('^')
Inservice Test Program (IWP) l Emergency Diesel Generator Auxiliary Systems Connecticut Yankee SYSTEM:
Fuel Oil 1
1 AFFECTED PUMPS:
Transfer pumps j
Engine-driven pumps Electric pumps TEST REQUIREMENT:
Per Table IWP-1300-1, observe proper lubricant level or pressure.
BASIS FOR RELIEF:
The above listed pumps are equipped with sealed bearings and not supplied by observable lubrication systems. Presently, instrumentation does not exist to monitor lubricant level or pressure.
ALTERNATE TESTING: The affected pumps and systems will be monitored during diesel engine operation using procedural specifications to assure satisfactory performance.
O 1
l s
O re83/7651 i
)
.__ __ Relief' Request #11P
'( ).
Inservice. Test Program -(IWP)
Emergency Diesel Generator Auxiliary Systems Connecticut-Yankee SYSTEM:
lube'011 AFFECTED PUMPS:
Main lube oil pumps Circulating oil pumps Piston oil pumps Turbocharger oil. pumps-Scavenging oil pumps TEST REQUIREMENT:
Per Table IWP-1300-1, observe proper lubricant level'
.or pressure.
BASIS FOR RELIEF:
The above listed pumps are' equipped.with sealed
-bearings.and not supplied by observable lubrication systems. Presently, instrumentation does not exist to monitor lubricant level or pressure..
i ALTERNATE TESTING: The affected pumps and systems will,be monitored
.j during diesel engine operation using procedural specifications to assure satisfactory performance.
(
l I
l i
(
1 O
rw83/7651 l
t
1 Reidef Request #12P
[)
Inservice Test Program (IWP)
Emergency Diesel Generator Auxiliary Systems Connecticut Yankee i
SYSTEM:
Cooling Water AFFECTED PUMPS:
Cooling water pumps TEST REQUIREMENT,:
Per Table IWP-1300-1, observe proper lubricant level or pressure.
BASIS FOR RELIEF:
The above listed pumps are equipped with sealed bearings and not supplied by observable lubrication systems.
Presently, instrumentation does not exist to monitor lubricant level or pressure.
ALTERNATE TESTING: The affected pumps and systems will be monitored during diesel engine operation using procedural specifications to assure satisfactory performance.
)
i 1
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re83/7651 I
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- 105 -
SAFETY / RELIEF VALVE SETPOINTS Service Sta. No.
Valve Type
.Setpoint'(Tol.)
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Air Receiver Relief DA-RV-32A
.5" Relief
'220 3%
Air Receiver' Relief DA-RV-33A
.5" Relief 220 13%
Air Receiver Relief DA-RV-34A
.5" Relief 220 13%
Air Receiver Relief DA-RV-35A
.5" Relief 220 3%
Air Receiver Relief DA-RV-36A
.5" Relief 220 13%
Air Receiver Relief DA-RV-37A
.5" Relief
'220 13%
Air Receiver Relief DA-RV-32B
.5" Relief 220 13%
Air Receiver Relief DA-RV-33B
.5" Relief 220 13%
Air Receiver Relief DA-RV-34B
.5" Relief 220 13%
Air Receiver Relief DA-RV-35B
.5" Relief 220 3%
Air Receiver Relief DA-RV-36B
.5" Relief 220 t3%
Air Receiver-Relief DA-RV-37B
.5" Relief 220 3%'
Fuel Oil Relief FO-RV-203A Relief 60 i2 psig Fuel Oil Relief FO-RV-203B Relief 60 12 psig Fuel Oil Relief F0-RV-203C Relief 60 12 psig Fuel Oil Relief FO-RV-203D Relief 60 12 psig Lube Oil Relief DLO-RV-5A
-Relief 40 !2.psig tube Oil Relief DLO-RV-5B Relief 40 2 psig O
re83/7651
- 106 -
Relief Request #1V
(~'
Inservice Test Program (IWV)
N Emergency Diesel Generator Auxiliary Systems Connecticut Yankee SYSTEM:
Starting Air AFFECTED VALVES: DA-ass-1A DA-ASV-2A DA-ARV-3A DA-ARV-4B DA-ASV-1B DA-ARV-4A DA-SOV-133 DA-ASB-2B DA-ARV-3B DA-SOV-134 CATEGORY: B DA-SOV-135 DA-SOV-136 CLASS:
Noncode Class Valves
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TEST REQUIREMENT:
Subarticle IWV-3413(b) - The stroke time of all power-operated valves shall be measured to the nearest second.
RELIEF REQUESTED:
Relief is requested from measuring stroke time of these valves.
BASIS FOR RELIEF:
These valves have no visible operating parts to measure the stroke time by.
There are no system instruments which monitor their operation. Further, the actual stroke time of these valves is very short ( 1 second) and measurement of stroke time would I
provide no realistic information for evaluation of valve condition.
l
()
ALTERNATE TESTING: The valves will be exercised per Art. 3412, and functional operation will be verified by proper starting of the emergency diesel.
('h s/
re83/7651 j
- 107 -
Relief Request #2V
("'
Inservice Test Program (IWV)
Emergency Diesel Generator' Auxiliary Systems Connecticut Yankee SYSTEM:
Starting Air AFFECTED VALVES:
Air start check valves CATEGORY:'C CLASS:
Noncode Class Valves TEST REQUIREMENT:
Per.Subarticle IWV-3522, verify proper operation of valve by visual observation, electrical signal initiated by a position indicating device or by observation of appropriate pressure indications in the system or by other positive means.
RELIEF REQUESTED:
Relief is requested to verify proper operation by-the above methods.
BASIS FOR RELIEF:
These valves lack the instrumentation required to satisfy this requirement.
ALTERNATE TESTING: The air start check valves will be exercised as-specified in Article IWV-3521. Functional operation will be verified by proper starting of the emergency diesel.
O re83/7651
- 10B -
Relief Request #3V
[')
Inservice Test Program (IWV)
Emergency Diesel Generator Auxiliary Systems Connecticut Yankee i
SYSTEM:
Fuel Oil i
AFFECTED VALVES:
FO-SOV-147A FO-S0V-147B CATEGORY: B CLASS:
Noncode Class Valves TEST REQUIREMENT:
Per Subarticle IWV-3413(b) - The stroke time of all
)
power-operated valves shall be measured to the nearest second.
j RELIEF REQUESTED:
Relief is requested from measuring stroke time of these valves.
BASIS FOR RELIEF:
These valves have no visible moving parts to measure the stroke time by.
ALTERNATE TESTING: The valves will be exercised per Art. 3412, and functional operation will be verified by the ability of the fuel oil transfer pumps to maintain fuel oil flow greater than the maximum demand
{
(*/)
of the emergency diesel, j
s_
I j
tv83/7651
_ 109 _
Relief' Request #4V-()
Inservice Test Program (IWV)
. Emergency Diesel Generator Auxiliary Systems i
Connecticut Yankee I
SYSTEM:
' Fuel Oil System / Lube Oil System AFFECTED VALVES:
Fuel 011 Check Valves Lube Oil Check Valves CATEGORY: C i
j CLASS:
Noncode Class Valves i
I TEST REQUIREMENT:
Per Suberticle.IWV-3522, verify proper operation of-valve by visual observation,, electrical signal initiated by a position J
indicating device or by observation'of appropriate pressure indications in the system.or by other positive means.
RELIEF REQUESTED:
Relief'is requested to verify proper operation by-the above methods.
BASIS FOR RELIEF:
These valves lack the instrumentation required to satisfy.this requirement.
ALTERNATE TESTING: The feel oil / lube oil check valves will be exercised O.
as specified in Article IWV-3521.
Functional operation will be verified by proper starting of the emergency diesel.
1 1
1
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re83/7651
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