ML20205R961
| ML20205R961 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/03/1986 |
| From: | Connolly J, Martel R, Sessler G PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | |
| Shared Package | |
| ML20205R954 | List: |
| References | |
| NUDOCS 8606060056 | |
| Download: ML20205R961 (131) | |
Text
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INSERVICE TESTING PROGRAM Rev. I k
l Prepared By:
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J. W. Connolly Da te Staff Engineer,'
Prepared By:
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- Date Station Manager 8606060056 060604 PDR ADOCK 0D000443 E
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INSERVICE If. STING PROGRAM CONTENTS
1.0 INTRODUCTION
2 1.1 General 2
1.2 Codes and Standards 2
1.3 Component Classification 2
2.0 REFERENCES
2 3.0 DEFINITIONS 3
4.0 DEVELOPMENT OF THE INSERVICE TESTING PROGRAM 4
4.1 Pump Selection Basis 4
4.2 Required Pump Testing 4
4.3 Valve Selection Basis 6
4.4 Valve Classification 7
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4.5 Required Valve Testing 8
5.0 TEST PLAN TABLES 10 5.1 Pump Test Requirement Table 10 -
5.2 Valve Test Requirements Legend 12 5.3 Valve Test Requirement Tables 13 6.0 RELIEF REQUESTS 6.1 Valves (V-1 through V-45) 6.2 Pumps (P-1 and P-2) 6.3 General (G-1 through G-5) 7.0 DRAWINGS 8.0 ATTACHMENTS 8.1 Limiting Values of Full Stroke Time 8.2 Flow Measurement Instrumentation Accuracies 8.3 Description of Operational Modes
-1
1.0 INTRODUCTION
1.1 General This test plan describes the Inservice Testing (IST) program to verify the operational readiness of certain Class 1, 2, and 3 pumps and valves and their actuating and position indicating systems. The IST program is administrative 1y controlled by the Seabrook Station Test Control Manual procedures TC 3.1 and TC 3.2.
1.2 Codes and Standards Pursuant to Title 10 of the Code of Federal Regulations, Part 50, Paragraph 50.55(a), the inservice testing requirements for the first inspection interval at Seabrook Station are based on the rules set forth in the 1983 edition of the ASME Boiler and Pressure Code,Section XI, including addenda through Summer 1983, any references to Section XI, or the Code, refer to the above edition and addenda to Section XI, unless stated otherwise. Where conformance with certain code requirements is determined to be impractical, specific relief will be requested as required by 10CFR50.55a (g) (5) (iii). The relief request bases are located in Section 6.0 of this test plan.
As permitted by Paragraph 50.55a (g) (4) (iv), the Owner may elect, for certain components, to meet the requirements as set forth in sub-sequent editions and addenda of the Code which are incorporated by reference in Paragraph (b) of 10CFR50.55a. Any such " upgrading" will be specifically identified by revisions to this document.
1.3 Component Classification The pumps and valves selected for inclusion in the inservice testing program are classified as Class 1, 2, and 3, based on the classifica-tion of the system, or portion of system, in which they are located.
The quality group claasification system for radioactive water /
steam-containing components important to the safety of water-cooled nuclear power plants is established by NRC Regulatory Guide 1.26, in conjunction with 100FR50.55a for Class 2 and 3 and 10CFR50.2v for Class 1.
Fluid system components important to safety are classi-fled in accordance with the ANSI N18.2a-1975, "American National Standard Revision and Addendum to Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants" classification.
This classification system is compatible with the requirements of 10CFR50.2v and NRC Regulatory Guide 1.26, and was submitted as an alternate acceptable method of meeting the intent of 10CFR50.2v and Regulatory Guide 1.26.
2.0 REFERENCES
2.1 Title 10, Code of Federal Regulations, Part 50.
2.2 ASME Boiler and Pressure Vessel Code,Section XI, 1983 edition, including addenda through Summer 1983. Rev. 1
2.3 Reg. Guide 1.26, Rev. 3, Quality Group Classification and Standards For Water, Steam, and Radioactive Waste Containing Componerts of Nuclear Power Planta.
2.4 ANSI Id.2a-1975, "American National Standard Revision and Addendum to Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants."
3.0 DEFINITIONS The following is a list of definitions for various terms used in the Inservice Testing Program.
Active Valve:
Valves which are required to change position to ac:omplish a specific function.
Code:
Refers to ASME Boiler and Pressute Vessel Code,Section XI, 1983 Edition, including addenda through Summer 1983, unless otherwise specified.
Exercising:
The demonstration based on direct or indirect vieual, or other positive indication, that the moving parts of a valve function satisfactorily.
L Inservice Life:
The period of time from installation and acceptance until retired from service.
Inservice Test:
A special test procedure for obtaining information through measurement or observation to determine the operational readiness of a valve or pump.
Maintenance:
Routine valve servicing or work on a valve undertaken to (valves) correct or prevent an abnormal or unsatisfactory con-dition.
Normal Plant The conditions of startup, hot standby, or operation Operation:
within the normal power range, or cooldown and shutdown of the power plant.
Operational The capability of a pump or valve to fulfill its Readit.ess:
function.
Passive Valve:
Valves which are not required to change positions to accomplish a specific function.
Pressure Isola-A valve required to protect a lower pressure system from tion Valve:
accidental pressurization from the Reactor Coolant System. To qualify as a pressure isolation valve, the following conditions must be met:
a.
The low pressure system must be connected to the Reactor Coolant System. Rev. 1
b.
The valve's function is to perform pressure isolation between high pewssure reactor coolant and low pressure systems.
)
c.
The pressure isolation valves are located at a Class 1 to Class 2 boundary.
d.
The piping line must have a diameter greater than one inch nominal pipe size.
Pressure isolation valves are claasified as ASME XI, Category A and AC valves.
Routine Servicing The performance of planned, preventive maintenance (Pumps):
which does not require disassembly of the pump or repla-cement of pump parts, such as changing oil, flushing the cooling system, adjusting packing, adding packing rings,
,r mechanical seal maintenance.
System Resistance: The hydraulic resistance to flow in a system.
4.0 DEVELOPMENT OF THE INSERVICE TESTING PROCRAM 4.1 Pump Selection Basis h
4.1.1 The pumps selected for inclusion in the IST program include Class 1, 2, and 3 centrifugal, and displacement type pumps that are required to perform a specific function in the shutting-down of the reactor or in nitigating the consequences of an accident, and are provided with an emergency power source. See Section 5.1 for the Pump Test Requirement Table.
4.1.2 The followxng Code allowed exclusions apply to pump testing:
a.
Drivers are excluded from the requirements of subsection IWP except where the pump and driver form 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.
4.2 Required Pump Testing 4.2.1 Inservice tests shall be conducted with the pump operating at nominal motor speed.
A series of raference values are determined for quantities listed below, as observed or measured when the equipment is known to be operating correctly. Where plant conditions or design are impractical, a specific request for relief has been included in Section 6.2 of this progam, as required by 10CFR50.55a(g)(5)(iii). Rev. 1 L
l Inservice Test Quanitites Inle t Pressure, Pi Differential Pressure. AP Flow Rate, Q Vibration Amplitude, V Pioper Lubricant Level or Pressure (observed)
Speed N - (if Variable Speed)
In an Inservice Test, these quanitities are measured, observed, and compared with the reference values to. determine if corree-tive action is needed.
When a reference value or set of values may have been affected by replacement, repair, or routine ser-vicing of the pump, a new reference value or set of values shall be determined, or the previous value reconfirmed by an 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.
tP 4.2.2 Each Inservice Test includes the measurement and observation of applicable test quantites.
An inservice test is run on each applicable pump nominally every three months during normal plant operations. This test frequency is maintained during plant shutdown periods, if this can reasonably be accomplished, although this is not mandatory.
If the pump is not tested during plant shutdown, it is tested within one week af ter the plant is returned to normal operation.
Pumps that are operating need not be run or stopped for a spe-cial test, provided the plant tog shows each such pump was operated at reference conditions, and the quantities specified were measured, observed, recorded and analyzed.
4.2.3 Analysis and Corrective Action 4.2.3.1 Analysis All test data is analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> af ter completion of a test. The test quantities are com-pared with the allowable range of quantities listed on file.
In accordance with the Code, 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 NHY in the pump testing procedures.
, Rev. I
4.2.3.2 Corrective Action Corrective action is taken by NHY if the periodically acquired operational data falls into the calculated Alert Range or Required Action Range as specified in the Code. The scope of corrective actions specified in the procedures spans a series of alternatives up to and including a required notification of plant management that a pump's operation data has entered the Required Action Range. The NHY plant management or his designee shall disposition the status of any pump which is operating in the Required Action Range.
4.2.4 Records The following information is maintained by NHY to meet the requirements for inservice testing:
1.
A record for each pump, including the name of the manufac-turer, the model, and the serial or other identification number.
2.
An inservice 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.
3.
Test record giving pertinent information 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 o.e maintained at NHY and accessible for audit.
4.3 Valve Selection Basis 4 3.1 The valves selected for inclusion in the IST program include certain ASME Class 1, 2, and 3 valves (and their actuating and position indicating systems) which are required to perform a specific function in shutting down the reactor to the cold shutdown condition or in mitigating the consequences of an accident.
See Section 5.3 for the Valve Test Requirements Table.
4.3.2 The following valves are exempt from testing under the Code. Rev. 1
r Valves used only for operating convenience (such as manual a.
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 pro-viding cirnals for valva oparation.
4.3.3 The following special testing requirements apply to containment isolation valves:
a.
Containment isolation valves are considered Category A valven.
b.
Valves which perform only a containment isolation function and not a pressure isolation
- function are exempt from the Code leak rate testing. These valves are leak rate tested under the requirements of 10CFR50, Appendix J.
- For a definition of Pressure Isolation Valves, see Section 3.0.
The designation of valves to be tested under the 10CFR50
[
c.
Appendix J program were determined from Table 6.2 - 83 of F
the Seabrook Station FSAR. Currently, this table and the Appendix J 1eak rate testing program have not been endorsed by the NRC.
In the event of future changes to the Appendix J program, this program will also be ammended to reflect the changes.
d.
Individual leakage rates for valves tested in the 10CFR50 Appendix J test program are limited to 0.05 La (maximum allowable leakage).
Individual valves with leakage rates erceeding 0.05 La shall be repaired or replaced.
4.4 Valve Classifiestion 4.4.1 The valves selected for inclusion in the inservice testing program are classified as follows:
a.
Catcgory A - Valvca f a r wh h }.
.wat 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.
Category C - Valves which are self-actuating in response to c.
some system characteristic such as pressure (relief valves) or flow direction (check valves). Rev. 1
d.
Category AC - Valves which function as Category A and Category C as defined above.
4.5 Required Valve Testing 4.5.1 Test Frequency The tests required and their frequencies for the valves designated as Category A, B, and C are listed on the test tables in Section 5.0.
In certain cases, it is not practical to test individual valves at the listed freqsencies, so other frequencies are speelfied on the tables in Section 5.0.
Where a test frequency has been designated at each refueling outage, and cold shutdown a specific request for relief has been included in Section 6.1 of this program.
4.5.2 Systems Inoperable Valves in systems that have been declared inoperable or are not required to be operable, do not need to be exercised in accor-with the normal schedule. These valves, however, must be exer-cised within 30 days of returning the system to service.
4.5.3 Valveswhichoperateatafrequercywhichmeetsorexceedsthef.
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.
4.5.4 Cold Shutdown Cold shutdown testing of valves will be conducted as follows:
1.
Testing will commence as soon as the cold shutdown con-dition is achieved but not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shut-down and continue until complete or the plant is ready to return to power.
Note 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.
b.
Completion of all valve testing is not a prerequisite to return to power.
c.
Any testing not completed during one cold shutdown should be performed during any subsequent cold shutdowns that may cccur be fore refueling to as closely as pousible meet the Code-specified testing frequency. Rev. 1
4 4
i 4
j 4.5.5 Retest l
Valves or their control systems which are replaced, repaired, or have undergone maintenance which could affect their opera-l 4
I tion shall be tested to the extent necessary to demonstrate l
that the performance parameters which could have been affected are within acceptable limits.
i
'l 4.5.6 Valve Position Indicator Verification I
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Valves with remote position indicators shall be observed at least once every two years to verify that valve operation is i
accurately indicated.
4.5.7 Power-Operated Valves Power-operated valves shall be checked for stroke time each time they are full-stroke exercised to meet the requirements of this program.
4.5.8 Fall Safe Actuators When practical, valves with fail-safe actuators shall be testedI for proper actuation upon loss of power each time the valve is exercised to meet the requirements of this program.
If the valve can only be partially stroked during operation, the fall-
]
safe mechanism shall be tested when the valve is full stroke tested during a cold shutdown.
I i
De-energizing the solenoid valves of valves which control the i
air supply to air operated valves and direct solenoid operated l-valves has the same effect as a loss of electrical power or control air. Therefore stroking the valve to its fail-safe l
position constitutes a fall safe test.
j 4.5.9 Paselve Category b and C Valves i
P4ssive Category B and C valves do not have test requirements i
specified in Table IWV-3700-1 of the Code and are not listed in l
Figure 5.3 of this test plan.
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Page 1 of 2 FIGURE 5.1 SEABROOK STATION PUMP TEST REQUIREMENTS TABLE Flow Inlet Differential Pump Vibration Bearing Pump Re sis tance Speed Control Pressure Pressure Flow Measurement Lubrication Tempera ture Frequency Containment Spray Pump CBS-P-9A Fixed Cons tant x
Calculated x
x x
P-2 Quarterly CBS-P-98 Fixed Cons tant x
Ca lcula ted x
x x
P-2 Quarterly R201 dual Heat R moval Pump KH-P-8A Fixed Cons tant x
Ca lcula ted x
x x
P-2 Quarterly CH-P-88 Fixed Cons tant x
Calculated x
x x
P-2 Quarterly Safety Injection Pump SI-P-6A Fixed Constant x
Calculated x
x x
P-2 Quarterly SI-P-6B Fixed Constant x
Calculated x
x x
P-2 Quarterly Service Water Pump SW-P-41A Variable Cons tant Sea Level Calculated x
x n/a P-2 Quarterly SW-P-41B Variable Cons tant Sea Level Calcula ted x
x n/a P-2 Quarterly SU-P-41C Variable Constant Sea Level Calculated x
x n/a P-2 Quarterly SW-P-41D Variable Cons tant Sea Level Calculated x-x n/a P-2 Quarterly Service Wa ter Cosling Tower Pump SW-P-110A Variable Cons tant Tower Level Calculated x
x n/a P-2 Quarterly SW-P-110B Variable Cons tant Tower Level Ca lcula ted x
x n/a P-2 Quarterly Primary Plant Component Cos11ag Pump P11A Variable Constant x
Ca lcula ted x
x x
P-2 Quarterly Coeling Pump P11B Variable Cons tant x
Calculated m x x
x P-2 Quarterly Cooling Pump P11C Variable Cons tant x
Calculated x
x x
P-2 Quarterly Cooling Pump P11D Variable Cons tant x
Ca lcula ted x
x x
P-2 Quarterly Rev. 1
Pcge 2 of 2 FIGURE 5.1 SEABROOK STATION PUMP TEST REQUIREMENT TABLE Flow Inlet Differential Pump Vibration Bearing Pump Resistance Speed Control Pressure Pressure Flow Measurement Lubrication Temperature Frequency Boric Acid Transfer Pump CS-?-3A Fixed Constant x
Calculated x
x n/a P-2 Quarterly CS-P-3B Fixed Constant x
Calculated x
x n/a P-2 Quarterly Centrifigal Chcrging Pump CS-P-2A Fixed Constant x
CalculatcJ x
x x
P-2 Quarterly CS-P-2B Fixed Constant x
Calculated x
x x
P-2 Quarterly h
Diesel Generator
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Fu21 Oil Transfer Pump DC-P-38A Variable Constant x
Calculated x
x n/a P-2 Quarterly DG-P-38B Variable Constant x
Calculated x
x n/a P-2 Quarterly Emergency Feed-Unter Pump FW-P-37B Fixed Constant x
Calculated x
x x
P-2 Quarterly Emergency Feed-Water Pump FW-P-37A Fixed Variable x
Calculated x
x x
P-2 Quarterly
- e, Rev. I
FIGURE 5.2 VALVE TESTING REQUIREMENTS LEGEND Function A - Active; required to change position to accomplish a specific function.
P - Passive; not required to change position to accomplish a specific function.
Category A - Seat leakage is limited to a specific maximum amount in the closed position of fulfillment of valve function.
B - Seat leakage in the closed position is inconsequential for fulfillment of valve function.
C - Self actuating in response to some system characteristics, such as pressures (relief valves) or flow direction (check valves).
Valve Type Leak Test Alternative B - Butterfly valve 1 - Reactor Coolant Pressure Isola 1ation BA - Ball valve valvas shall be tested in accordance C - Check valve with Tech Spec Section 4.4.6.2.2.
G - Cate valve CL - Clobe valve S - Safety / relief valve Exercise Test Requirement SC - Stop check valve I
W - Saunders weir valve Blank - None required 4
D - Diaphram 1 - Exercise every 3 months per IWV-3410.
T - Three way valve 2 - Safety valve setpoints shall be Actuator tested per IWV-3512 in accordance with ASME PTC 25.3-1976.
-- - Self actuated 3 - Exercise every 3 months per IWV-3520 A - Air operator (check valves)
M - Motor operator HA - Manual Exercise Test Relief Requested P - Piston operator (hydraulic)
S - Solenoid operator Blank - No X - Yes Normal Position OC - Normal position is open/ closed Exercise Test Alternative C - Closed 0 - Open 1 - Exercise on reactor shutdown, partial LC - Locked closed stroke every 3 months LO - Locked open 2 - Exercise each cold shutdown T - Throttled 3 - Exercise each refueling
-- - Normal position for safety /
4 - Exercise when system is shut down relief valves is closed Fall Safe Test Requirement Leak Test Requirement
~
X - Yes, test according to 1WV-3415 Blank - None required 1.- Leak test at least every 2 Blank - No years per IWV-3420 2 - Leak test every 2 years Position Indicator Test Requirement 10CFR50 App. J X - Yes, test according to IWV-3300 Leak Test Relief Requested Blank - No Blank - No X - Yes Rev. 1
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VALVE TESTING REQUIREMENTS NOTES 1.
The frequency and quantity of safety valves subject to test at'each refueling outage is in accordance with Section XI, IWV-3500.
2.
Valve full closure time on any closure actuation signal will be verified while in hot-standby during each reactor shutdown except that this verifi-cation need not be determined more than once per 3 months for multiple shutdowns. Shutdown will not be required for the sole purpose of per-forming the full closure test.
As an alternative, the valve will be part stroked every 3 months.
(Relief Request V-1 and V-4.)
3.
N/A l
4.
This valve will be exercised during cold shutdowns since operation of this portion of the feed system will introduce cold water into the steam generator feed nozzles.
(Relief Request V-2 and V-5.)
5.
N/A 6.
N/A l
7.
The valves are required by technical specific.ations to be shut and power removed from their operators during Modes 1, 2, 3.
They will be full-stroke exercised during cold shutdown.
(Relief Roquest V-13.)
8.
Opening this valve during operational modes other than cold shutdown is prohibited by tech specs. This valve will be exercised during cold shut l
downs (Relief Request V-7.)
- l 9.
N/A 10.
This valve is a boundary valve between high pressure RCS piping and adja-cent low pressure systems. As such, it is Category A and/or AC per IWV-2200.
It will be leak tested in accordance with technical specificaticas.
(Relief Request V-10.)
- 11. This valve will be exercised during cold shutdown.
(Relief Request V-II.)
12.
N/A l
13.
Full stroke exercise tests of these valves shall be performed during each l
cold shutdown.
(Relief Request V-12.)
14.
N/A l
(* - Relief Requests refer to relief requested in IST submittal to the NRC.)
Rev. 1
(continued)
VALVE TESTING REQUIREMENTS NOTES
- 15. Quarterly full-stroke exercising this normally closed check valve would require that reactor coolant system pressure be below RHR pump discharge This valve will be verifie:1 as operable during cold shutdowns.
pressure.
(Relief Request V-15.)
1 16.
N/A 17.
N/A 18.
This normally open valve is in the position required for accident con-ditions and, per technical specifications, must remain open during power operations. These valves shall be full-stroke exercised during cold shutdowns. (Relief Request V-14) 19.
Exercising this valve requires flow to the RCS using the safety injection or residual heat removal pumps.
During operation, RCS pressure will be higher than pump discharge pressure. As an alternative, this valve will be exercised at refueling outages.
(Relief Request V-18.)
20.
Exercising this valve requires initiating flow to the RCS using the charging pumps.
If charging flow was directed to the RCS in this manner, it could create a loss of charging flow control during normal operation resulting in pressurizer level changes and possibly a plant trip and cause low-temperature overpressurization of the RCS during cold shutdowns. As an alternative, this valve will be exercised at refueling outages.
(Relief Request V-20.)
21.
This valve cannot be exercised during power operation when charging system is in operation.
It will be exercised at cold shutdowns.
(Relief Request V-21.)
- l 22.
To protect reactor coolant pump seals, flow to them is required at all times during power operation and startup. It will be exercised during cold shutdowns when risk of equipment damage is eliminated by securing the pumps.
(Relief Request V-22.)
23.
N/A 24.
Exercising this valve during power operations could cause a sudden increase in RCS boron inventory.
It will be exercised at cold shutdown when the RCS is already borated to shutdown conditions. (Relief Request V-24.)
25.
N/A l
26.
Exercising these valves could isolate cooling water to many vital com-ponents, in the event a valve were to fail in the closed position. These valves will be exercised during cold shutdown when non-essential loads can be isolated.
(Relief Request V-25.)
(* - Relief Requests refer to relief requested in IST submittal to the NRC)
Rev. 1
-. ~ - -
i (continued)
VALVE TESTING REQUIREMENTS NOTES 27.
N/A l
28.
These valves cannot be exercised withcut the initiation of containment spray flow into the containment building quarterly during power operation or during cold shutdowns. These valves shall be partially disassembled, inspected, and manually exercised on a staggered sampling basis each refueling cutage. (Relief Request V-27.)
29.
This valve cannot be exercised by system flow without substantial amounts of water in the containment sumps being pumped by the spray and RHR pumps.
This valve will be exercised during refueling outages by disassembly and
.[
mechanical exercise on a staggered sampling basis.
(Relief Request V-28.)
30.
This check valve is normally open during plant operation.
Its function is to prevent reverse flow, and shall be tested during cold shutdown.
It is impractical to shut down at three month intervals to perform a full closure test.
(Relief Request V-6.)
- 31. _ Exercising this valve during power operations is impractical and would align the charging pump suctions of the RWST which could cause a sudden increase in the reactor coolant system boron inventory. This valve shall be full-stroke exercised during cold shutdowns. (Relief Request V-26.)
32.
This valve provides a containment isolation function only. Additional exercising of this valve is not practical, and will not improve its leak tightness characteristics. Operability is proven during periodic 10CFR50, App. J, Type C testing.
(Relief Request V-8.)
33.
N/A l
34.
N/A l
35.
N/A 36.
It is impractical to full-stroke exercise these valves on a quarterly basis because these valves are not in the pump test flow path. These valve. can-not be full-stroke exercised during cold shutdowns because there is no flow path back to the RWST. Testing during cold shutdowns would require flow to be established into the RCS where there is no additional volume to add the additional inventory. These valves will be full stroke exercised l
during refueling outages. (Relief Request V-31.)
(* - Relief Requests refer to relief requested in IST submittal to the NRC.)
Rev. 1
(continued) 37.
There is not sufficient flow to full-stroke exercise these valves during the quarterly RHR pump tests because these tests are run on minimum flow a
recirculation. These valves can only be partially stroked during the quar-terly RHR pump tests. These valves shall be full-stroke exercised during j
cold shutdowns.
(Relief Request V-32.)
38.
These valves are required to be open with power removed from the operators during operational modes 1, 2, and 3 by plant Technical Specifications sec-tion 4.5.2 to ensure the operability of this ECCS subsystem. These valves shall be tested during cold shutdowns. (Relief Request V-33.)
39.
There is not sufficient flow to full-stroke exercise these valves during the quarterly SI pump test because theses tests are run on minimum flow recirculation. These valves are partially stroked on a quarterly basis.
These valves cannot be full-stroke exercised during cold shutdowns due to possible low-temperature overpressurization concerns with the RCS.
1 These valves shall be full-stroke exercised during refueling outages.
(Relief Request V-34.)
40.
Exercising these valves per the frequency described in IWV-3520 is not practical. Exercising these valves during plant operation would require initiating flow to the reactor coolant system using the residual heat remo-val pumps. During plant operation, the reactor coolant system pressure will be greater than the residual heat removal pump discharge pressure.
These valves cannot be exercised during cold shutdowns since establishing flow through these valves could result in RHR cooling flow bypassing the reactor core. These valves will be exercised during refueling outages.
1 (Relief Request V-19.)
41.
Full-stroke exercising these valves per the frequency described in IWV-3520 is not practical. Exercising these valves during plant operation would require initiating flow to the RCS using the safety injection pumps.
During plant operation the RCS pressure will be greater than the SI pump discharge pressure. These valves cannot be exercised during cold shutdowns because il pump flow could possibly result in low-temperature overpressuri-1 zation during refueling outages.
(Relief Request V-35.)
42.
Full-stroke exercising these valves on a quarterly basis could cause a loss of pressurizer level control and possibly a plant trip. These valves shall be full stroke exercised during cold shutdowns.
(Relief Request V-36.)
1 1
(* - Relief Requests refer to relief requested in IST submittal to the NRC.)
Rev. 1
(continued) 43.
It is impractical to full-stroke exercise these valves quarterly.
In order to fell-stroke exercise these valves, it is necessary to inject flow through the charging pumps to the High Head Safety Injection flow path.
If charging flow was d;rected to the RCS in this manner it could cause a loss of charging flow control during plant operation resulting in pressurizer level changes and possibly a plant trip. Additionally, charging flow through these valves would also result in the injection of relatively cold water into the RCS possibly resulting n the cold shocking of system com-ponents. During cold shutdowns, the injection of charging flow could result in low-temperature overpressurization of the RCS.
These valves shall be full stroke exercised during refueling outages, j
(Relief Request V-37.)
44.
These valves can only be partially stroked during power operations. There is insufficient flow during charging operations to full-stroke exercise these valves. During the quarterly pump test, flow is directed through the seal water heat exchanger to the suction of the charging pumps. These valves cannot be exercised during cold shutdowns since injection flow from the chargir.g pumps could result in low-temperature overpressurization of the RCS. These valves shall be full-stroke exercised during refueling i
outages.
(Relief Request V-38.)
45.
This normally closed check valve performs its safety function in the closed j
position.
It shall be verified in the closed direction quarterly.
46.
Full-stroke exercising of these valves during power operations requires isolating one train of primary component and could possible isolate cooling water to many vital components. These valves shall be full-stroke exer-cised during cold shutdowns, (Relief Request V-39.)
1 47.
These valves can only be partial stroked during quarterly pump testing.
There is insufficient flow through these valves when the containment spray pump is operated in its test path to the RWST to full-stroke exercise these valves. The necessary flow required to full stroke these valves per the Code requirements would require the initiation of containment spray ficw into the containment which is impractical. These valves shall be partially disassembled, inspected and manually exercised on a staggered sampling j
basis each refueling outage.
(Relief Request V-40.)
48.
Exercising these valves quarterly during power operation would isolate cooling water to the reactor cooling pump bearing oil coolers and motor air coolers possibly damaging the reactor coolant pumps which could affect reactor coolant system circulation.
Full stroke exercising of these valves will be performed during cold shutdowns when the reactor coolant pumps are secured.
(Relief Request V-29.)
1
(* - Relief Requests refer to relief requested in IST submittal to the NRC.)
Rev. 1
(continued)
- 49. These valves are not provided with power operators, therefore, the measuring of stroke time is not measured for these valves.
- 50. During quarterly pump testing of the EFW turbine pump, there is insufficient flow to full-stroke exercise these valves in accordance with the require-ments of the Code. These valves are partially stroked during the quarterly pump test.
T,hese valves shall be full-stroke exercised during plant cool-down to cold shutdown or heatup from cold shutdown when there is sufficient steam available to full-stroke exercise these valves.
(Relief Request V-41.) *
- 51. These valves shall additionally be tested to closed position because they are required to close in the event of a main steam line break.
- 52. These valves cannot be full-stroke exercised quarterly,during power operation, or during cold shutdowns. These valves shall be partially disassembled, inspected and manually exercised on a staggered sampling basis each refueling.
(Relief Request V-42.)
- 53. These valves shall be partially stroked during cold shutdowns.
- 54. Full-stroke exercising these valves on a quarterly basis would increase the risk of placing the plant in a small transient in the event there is a failure of one of the reactor vessel head vent valves.
If one of the vent valves experienced a failure and the reactor head was vented to the pressuri-zer relief tank (PRT) during operation, there would be a pressure drop in the reactor coolant system until the level control system in the pressurizer could respond.
Full-stroke exercising these valves quarterly increases the poten-tial of putting the plant through an excursion to test the system. These valves shall be full-stroke exercised during cold shutdowns to assure valve operability while eliminating risk of a plant transient.(Relief Request V-43.) *
- 55. It is impractical to measure the limiting value of full-stroke time of these valves. The safety function of these valves is to open to support the startup of its respective diesel to provide rated frequency and voltage in less than 10 seconds. Successful startup of each emergency diesel generator within the above specified conditions is dependent upon the proper operation and speed of these valves. Additional Code required full-stroke time measurement of these valves will not increase the assurance that the diesel generators will start as required.
Upon failure of the diesel generators to start as required, corrective action shall be taken to assure proper diesel startup conditions.
(Relief Request V-44.)
- 56. Exercising these valves at any periodic frequency is impractical. The primary function of these valves is to modulate to control the temperature and pres-sure of the cooling water of each emergency diesel generator. Code required full-stroke exercising of these valves would not verify the operability of these valves. Periodic operation of the diesels verifies operability of these valves.
These valves are included in the inservice test program because of their fail-safe function. These valves shall be verified on a quarterly basis that they fail to maximum cooling position upon loss of actuator power.
(Relief Request V-45.)
- 57. These valves shall additionally be full-stroke exercise tested open.
(* - Relief Requests refer to relief requested in IST submittal to the NRC. )
Rev. 1
s
- 1..
6.0 Relief Requests 6.1 Valves
. Rev. 1
l L
Relief Request:
V-1 Valves:
MS-V86, MS-V88, MS-V90, MS-V92 Category:
B Code Class:
2 Function:
Main Steam Isolation (active) i Test Requirements:
IWV-3410 (3 months) 5 ll Basis for Relief:
Full Closure of these valves for the purpose of exercising per IWV-3410 would require plant shutdown.
Alternate Testina: These valves will be partially stroked in accordance with IWV-3410. Valve full closure time will be verified in hot standby during each reactor shutdown except that this veri-fication need not be determined more than once per 3 months for multiple shutdowns.
t Rev. I ww w-t
Relief Request:
V-2 Valves:
FW-V64, FW-V70 Category:
C Code Class:
3 Function:
Prevent backflow to the emergency feed pumps (active)
Test Requirements:
IWV-3520 (3 months) 5 o
Basis for Relief:
Full flow through these valves quarterly during power opera-tions would unnecessarily introduce cold water into the steam generator causing thermal shock to the feed nozzles.
Alternate Testina: These valves will be full-stroke exercise. tested during cold shutdowns with the associated pump operability testing.
e e
i e
i Rev. I
Relief Request:
V-3 (Deleted)
Valves:
Category 1 Code Class:
Function:
Test Requirements:
Basis for Relief:
Alternate Testing:
Rev. 1 t
Relief Request:
V-4 Valves:
FW-V30, FW-V39, FW-V48, FW-V57 Category:
B Code Class:
2 Function:
(Active) feedwater isolation Test Requirements:
IWV-3410 5
Il r.
Basis for Relief:
Full closure of these valves to satisfy the requirements of '
IWV-3410 would require plant shutdown.
Alternate Testing: These valves will be partially stroked in accordance with IWV-3410. Valve full closure time will be verified in hot standby during each reactor shutdown except that this veri-fication need not be determined more than once per 3 months for multiple shutdowns.
Rev. 1
Relief Request:
V-5 Valves:
FW-V76, FW-V82, FW-V88, FW-V94 Category:
C Code Class:
2 Function:
(Active) prevent feedwater backflow Test Requirements:
IWV-3520 (3 months)
- f..
Basis for Reli6f:
Full flow through these valves quarterly during power opera-tions would unnecessarily introduce cold water into the steam generator causing thermal shock to the feed nozzles.
Alternate Testing: These valves will be full-stroke exercise tested during cold shutdowns with the associated pump operability testing.
Rev. 1
N Relief Request:
V-6 Valves:
FW-V330, FW-V331, FW-V332, FW-V333 1
Category:
C Code Class:
2 Function:
(Active) prevent feedwater backflow 4
Test Requirements:
IWV-3520 (3 months) k j
Basis for Relief:
Exercising these valves for closure would require securing the steam generator feedwater system and cause plant shut-i down.
Alternate Testing: Operation of these valves will be verified when entering and/or leaving cold shutdown conditions.
1 i
t i
Rev. 1
- +.. -
---...,-.--..,..~.-,,-,e-,__
,n
Relief Request:
V-7 Valves:
CAP-VI, CAP-V2, CAP-V3, CAP-V4 Category:_
A.
Code Class:
2 Function:
(Active) containment isolation for contain' ment purge supply and exhaust Test Requirements:
IWV-3410 (3 months) s Basis for Relief:
These valves are lock closed containment isolation valves per Technical Specifications Section 3.6.1.7.
It is imprac-tical to open these valves at 3 month intervals and possibly void containment integrity.
Alternate Testing: These valves will be full-stroke exercised during cold shut-downs.
,/
,/
Rev. 1
Relief Request:
V-8 Valves:
SS-V273, CAH-V12 Category:
AC Code Class:
2 Function:
(Active) containment isolation Test Requirements:
IWV-3520 (3 months) l Basis for Relief:
These valves provide a containment isolation function only.
Additional exercising of these valves is not practical, and will not improve the leak tightness characteristics of the valve. Valve operability is proven during periodic 10CFR50 App. J, Type C testing Alternate Testing: None Rev. 1
Relief Request:
V-9 (Deleted)
Valves:
Category:
Code Class:
Function:
Test Requirements:
Basis for Relief:
Alternate Testing:
O Rev. I
Relief Request:
V-10 Valves:
RC-V22, RC-V23, RC-V87, RC-V88, RH-V15, RH-V29, RH-V30, RH-V31, SI-V6, SI-V21, SI-V36, SI-V51, RH-V50, RH-V51, RH-V52, RH-V53, SI-V81, SI-v82, SI-V86, SI-V87, SI-v106, SI-V110, SI-V118, SI-V122, SI-V126, SI-V130, SI-V140, SI-V144, SI-V148, SI-V152, SI-V156, SI-V5, SI-V20, SI-V35, SI-V50 Category:
A/C and A Code Class:
1 Function:
Reactor coolant pressure isolation valve Test Requirements:
IWV-3420 (2 years)
Basis for Relief:
These valves are reactor coolant pressure isolation valves, and will be leak tested in accordance with Technical Specifications Section 4.4.6.2.2.
These valves are Category A per IWV-2200.
Alternate Testing: Each reactor coolant pressure isolation valve shall be demonstrated operable by verifying leakage to be within its limit:
a.
at least once per 18 months; b.
prior to entering Mode 2 whenever the plant has been in cold shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more, and if leakage testing has not been performed in the previous 9 months; prior to returning the valve to service following main-c.
tenance, repair or replacement work on the valve; and d.
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automa-tic or manual action or flow through the valve.
e Rev. 1
Relief Request:
V-11 Valves:
RC-V22, RC-V23, RC-V87, RC-V88 Category:
A Code Class:
1
- Function:
(Active) reactor coolant pressure isolation valve /RHR Pump Saction Valves Test Requirements:
IWV-3410 (3 months) f.
Basis for Relief:
It is impractical to full-stroke exercise these valves during operation when RCS pressure is above 400 psig. These valves have system interlocks which prevent these valves from opening with the RCS pressure above 400 psig to prevent overpressurization of the RHR system piping.
Alternate Testing: These valves will be full-stroke exercised during cold shut-downs.
4 Rev. 1 o
Relief Request:
V-12 Valves:
RC-PCV456A, RC-PCV456B Category:
B Code Class:
1 Function:
(Active) power operated pressurizer relief valves Test Requirements:
IWV-3410 (3 months) 5 I
Basis for Relief:
Full stroke exercising of these valves is impractical during power operation. The safety function of these valves is to protect the reactor vessel and the reactor coolant system
~
from low-temperature overpressurization conditions and shall be exericised prior to initiation of system conditions for which protection is needed.
Alternate Testing:
These valves will be full-stroke exercised at each cold shutdown. Section 4.5.4 of this submittal does not apply to the testing of the cold shutdown valves.
4 I
e 4
Rev. 1
)
I l
Relief Request:
V-13 l
Valves:
RH-V70, RH-V32, SI-V77, SI-V102 Category:
B Code Class:
2 Function:
(Active) isolation valves Test Requirements:
IWV-3410 (3 months) a f.
4 Basis for Relief:
These valves are required by technical specifications to be shut and power to be removed from their operators during Modes 1, 2 and 3 (Technical Specifications Section 4.5.2) to ensure operability of this ECCS subsystem.
Alternate Testing: These valves will be full-stroke exercised.during cold shut-downs.
k e
Rev. 1
Relief Request:
V-14 Valves:
CBS-V47, CBS-V51 and SI-V114 Category:
B Code Class:
2 Function:
(Active) isolation valves Test Requirements:
IWV-3410 (3 months)
Basis for Relief:
These valves are required by technical specifications to be f.
open and power removed from their operators during Modes 1, 2 and 3 (Technical Specifications Section 4.5.2) to ensure operability of these ECCS subsystems.
Alternate Testing: These valves will be full-stroke exercised during cold shut-downs to the closed position.
Rev. 1
4.
Relief Request:.
.v-15 RH-V15, RH-V29, RH-V30, RH-V31 Valves:
o t
Categorg AC f
4
Iode Class:
1
~
F '
Function:
%,'- (Active) reactor coolant pressure boudary isolation valves s
Test Requirements:
1WV-3520 (3 months) i
~-
~
~
- Basis for Relief:
To quarter 1r full-stroke exercise these normally closed check valves to the open position is not practical.
It cwould require the reactor coolant system pressure to be below the RMk pump discharge pressure.
Alternate Testing: The valves will be full-stroke exercised during cold shut-downs.
B t.
N f
e7 v
9 L
l f
' 4~
s v
4 Rev. 1
~
'Ti f
=
s,
= - --, ~ - - - -,..-. - - - -
Relief Request:
V-16 (Deleted)
Valves:
Category:
Code Class:
Function:
Test Requirements:
I P
Basis for Relief:
Alternate Testing:
Rev. 1
Relief Request:
V-17 (Deleted)
Valves:
Category:
Code Class:
Function:
Test Requirements:
h Basis for Relief:
?-
Alternate Testing:
e 4
Rev. 1
i Relief Request:
V-18 Valves:
SI-Vil8, SI-V122, SI-V126, SI-V130, SI-V106, SI-V110, SI-V81, SI-V82, SI-V86, SI-V87 Category:
AC/C Code Class:
I and 2 Function:
(Active) reactor coolant pressure isolaticn valves Test Requirements:
IWV-3520 (3 months) f..
Basis for Relief:
Exercising these valves per the frequency described in IWV-3520 is not practical. Exercising these valves during plant operation would require initiating flow to the reactor coolant system using the safety injection pumps. During plant operation, the reactor coolant pressure will be greater than the safety injection pump discharge pressure.
These valves cannot be exercised during cold shutdowns because SI pump flow could possibly risk low-temperature overpressurization of the RCS.
Alternate Testing: These valves will be full-stroke exercised during refueling outages.
-4
+
Rev. 1
Relief Request:
V-19 Valves:
RH-V50, RH-V51, RH-V52 and RH-V53 Category:
AC Code Class:
1 Function:
(Active) reacter ccolant pressure boundary isolation valves /
RER Hot Leg Injection Test Requirements:
IWV-3520 (3 months)
$r.
Basis for Relief:
Exercising these valves per the frequency described in IWV-3520 is not practical. Exercising these valves during plant operation would require initiating flow to the reactor coolant system using the residual heat removal pumps.
During plant operation, the reactor coolant system pressure will be greater than the residual heat removal pump discharge pressure. These valves cannot be exercised during cold thutdowns because establishing flow through these valves could result in RHR cooling flow bypassing the reac-tor core.
Alternate Testing: These valves will be full-stroke exercised during refueling outages.
I Rev. 1 i
,7----
Relief Request:
V-20 Valves:
SI-V156, SI-V297, SI-V140, SI-V144, SI-V148, SI-v152 Category:
AC/C Code Class:
I and 2 Function:
(Active) reactor coolant pressure boundary isolation / prevent safety injection backflow Test Requirements:
IWV-3520 (3 months) i f.
Basis for Relief:
These valves are normally closed check valves. To exercise these check valves charging flow from the charging pumps must be initiated.
If charging flow was directed to the RCS in this manner, it could cause a loss of charging flow control during plant operatio.s resulting in pressurizer level changes and possibly a plant trip. Charging flow through these valves during plant operation would also result with the injection of relatively cold water into the RCS possibly resulting in the cold shocking of system com-ponents. Charging flow through these valves during cold shutdown could cause low-temperature overpressurization of the RCS.
Alternate Testing: These check valves will be full-stroke exercised open during refueling outages.
Rev. 1
Relief Request:
V-21 Valves:
CS-LCV112B and CS-LCV112C Category:
B Code Class:
2 Function:
(Active) Chemical and Volume Control Tank Suction Isolation Valves Test Requirements:
IWV-3410 (3 months) i-Basis for Relief:
Full stroke exercising these valves quarterly during power operation could result in a loss of charging pump suction.
This could cause a loss of pressurizer level control possibly resulting in a plant trip. Use of the alternate pump suction sources could result with injecting higher con-centrations of boric acids into the RCS.
Alternate Testing: These valves will be exercised at cold shutdowns.
e Rev. 1
I
^
Relief Reque4L.
V-22 Valves:
CS-V167, CS-V168 Category:
A Code Class:
2 Function:
(Active) containment isolation f
Test Requirements:
IWV-3410 (3 months) h..
Basis for Relief:
These valves isolate leakoff flow from the reactor coolant pump #1 seals.
Isolating these valves during power opera-tion and startup could cause damage to the reactor coolant pump seals.
Alternate Testing: Full-stroke exercising of these valves will be performed during cold shutdowns when the reactor coolant pumps are secured.
Rev. 1
Relief Request:
V-23 (Deleted)
Valves:
Category:
Code Class:
Function:
Test Requirements:
s
}
Basis for Relief:
Alternate Testing:
Rev. 1
Relief Request:
V-24 Valves:
RMW-V119, CS-V426, CS-V427 Category:
B and C Code Class:
2 Function:
(Active) prevents back flow Test Requirements:
IWV-3410/IWV-3520 (3 months) 6 F
Basis for Relief:
Exercising these normally closed valves to the open position during power operation could cause a sudden increase in the reactor coolant system boron inventory. These valves supply
' highly concentrated borated water to the suctions of the charging pumps. A rapid addition of this highly con-centrated borated water would add large amounts of negative reactivity to the reactor coolant system possibly causing a plant shutdown.
Alternate Testing: These valves will be full-stroke exercised at cold shut-downs.
t 5
Rev. 1
Relief Request:
V-25 i
Valves:
CC-V447, CC-V448, CC-V426, CC-V427, and CC-V341 Category:
B Code Class:
3 Function:
(Active) primary component cooling water isolation valves Test Requirements:
IWV-3410 (3 months)
>l F
Basis for Relief:
It is impractical to full-stroke exercise these valves quar-terly.. Isolating these valves during power operations could isolate cooling water to several heat-exchangers resulting in overheating of several non-essential systems.
Alternate Testing: These valves will be full-stroke exercised during cold shut-downs when these non-essential cooling loads can be iso-lated.
Rev. I
i Relief Request:
V-26 Valves:
CS-LCVll2D, CS-LCVil2E Category:
B Code Class:
2 Function:
(Active) charging pump suction isolation from the RWST Test Requirements:
IWV-3410 (3 nonths)
E Basis for Relief:
Exercising these valves during power operation would require the charging pump suctions to be aligned with the RWST (refueling water storage tank). -This would cause a sudden increase in the reactor coolant system boron inventory resulting in the addition of large amounts of negative reac-tivity to the RCS possibly causing a plant shutdown.
Alternate Testing: These valves shall be full-stroke exercised during cold shutdowns.
Rev. 1
^
Relief Request:
V-27 Valves:
CBS-V12, CBS-V18 Category:
C, Code Class:
2 Function:
(Active) containment isolation Test Requirements:
IWV-3520 (3 months)
F Basis for Relief:
These valves cannot be exercised without the initiation of containment spray flow into the containment building quar-terly during power operation or during cold shutdowns.
Alternate Testing: These valves shall be partially disassembled, inspected and manually exercised on a staggered sampling basis each refueling outage. At each disassembly, it shall be verified that the disassembled valve is capable of full stroking and that its internals are structurally sound (no loose or corroded parts).
In the event that the disassembled valve's full-stroke capability is in question, both valves in this group shall be disassembled.
Rev. 1
Relief Request:
V-28 Valves:
CBS-V9, CBS-V26, CBS-V25, CBS-V15 Category:
C Code Class:
2 Function:
(Active) prevent backflow to the' containment recirculation sumps Test Requirements:
IWV-3520 (3 months)
P Basis for Relief:
These valves cannot be exercised by system flow with substantial amounts of water in the containment sumps being drawn by the containment spray and residual heat removal
~
pumps.
Alternate Testing: These valves will be par?.ially disassembled, inspected and manually exercised on a staggered sampling basis (one valve in each group) each refueling outage. One group includes CBS-V9 and CBS-V15. The other group includes CBS-V25 and CBS-V26. At each disassembly, it shall be verified that the disassembled valve is capable of full stroking and that its internals are structurally sound (no loose or corroded parts).
In the event that a valve's full-stroke capability is in question, both valves in the respective group shall be disassembled.
i Rev. 1
Relief Request:
V-29 Valves:
CC-V175, CC-V176, CC-V256, CC-v257, CC-v168, CC-V57, CC-V122,CC-V121
-Category:
A Code Class:
2 Function:
(Active) containment isolation Test Requirements:
IWV-3410 (3 months)
Basis for Relief:
Exercising these valves quarterly during power operation would isolate cooling water to the reactor coolant pump 4
bearing oil coolers and motor air coolers possibly damaging the reactor coolant pumps which could affect reactor coolant system circulation.
1 Alternate Testing: Full-stroke exercising of these valves will be performed during cold shutdowns.
i Rev. 1
- - - -, - -, - - - - - - - - - - - ~ -, -, -,
e-
Relief Request:
V-30 (Deleted)
Valves:
Category:
Code Class:
Function:
Test Requirements:
I f-hsis for Relief:
Alternate Testing:
o Rev. 1
Relief Request:
V-31 Valves:
CBS-V55 and CBS-V56 Category:
C
. Code Class:
2 Function:
RHR Suction from the RWST (Active)
Test Requirements:
IWV-3520 (3 months) ll Basis for Relief:
It is impractical to full-stroke exercise these valves on a quarterly basis because these valves are not in the pump test flow path. These valves cannot be exercised during cold shutdowns because there is no flow path back to the RWST. Testing during cold shutdowns would require flow to be established into the RCS where there is no additional volume to add the additional inventory.
Alternate Testing: These valves will be full-stroke exercised during refueling outages.
G Rev. 1
.. ~
Relief Request:
V-32 Valves:
RH-V4 and RH-V40 Category:
C Code Class:
2 Functions (Active) RHR Pump Discharge Check Valves Test Requirements:
IWV-3520 (3 months) 5 A
Basis for Relief:
There is not sufficient flow to full-stroke exercise these valves during quarterly RHR pump tests because these tests are run on minimum flow recirculation. These valves can only be partially stroked during the quarterly RHR pump tests.
Alternate Testing: These valves shall be full-stroke exercised during cold shutdowns.
Rev. 1
Relief Request:
V-33 Valves:
RH-V14 and RH-V26 Category:
B Code Class:
2 Function:
(Active) RHR Cold Leg Isolation Test Requirements:
IWV-3410 (3 months)
Basis for Relief:
These valves are required to be open with power removed from'*
the operators during operational modes 1, 2 and 3 by plant Technical Specifications Section 4.5.2 to ensure the opera-bility of this ECCS subsystem.
Alternate Testing: These valves shall be full-stroke exercised during cold shutdowns.
i I
i Rev. 1 l
Relief Request:
V-34 Valves:
CBS-V48 and CBS-V52 Category:
C Code Class:
2 Function:
(Active) SI pump suction check valves from the RWST Test Requirements:
IWV-3520 (3 months)
T-Basis for Relief:
There is not sufficient flow to full-stroke exercise these valves during the quarterly SI pump tests because these tests are run on minimum flow recirculation. These valves are partially stroked on a quarterly basis. These valves cannot be full-stroke exercised during cold shutdowns due to possible low-temperature overpressurization concerns with the RCS.
Alternate Testing: These valves will be full-stroke exercised during refueling outages.
Rev. 1
Relief Request:
V-35 Valves:
SI-V71 and SI-V96 Category:
C Code Class:
2 Function:
(Active) SI pump discharge check valves Test Requirements:
IWV-3520 v
Basis for Relief:
Full-stroke exercising these valves per the frequency described in IWV-3520 is not practical. Exercising these valves during plant operation would require initiating flow to the RCS using the SI pumps. During plant operation, the RCS pressure will be greater than the residual heat removal pump discharge pressure. These vnives cannot be exercised during cold shutdowns because SI pump flow could possibly result in low-temperature overpressurization of the RCS.
Alternate Testing: These valves shall be full-stroke exercised during refueling outages.
Rev. I
~
Relief Request:
V-36 Valves:
CS-142, CS-143, CS-V149 and CS-V150 Category:
A and B Code Class:
2 Function:
(Active) Charging Isolation Valves / Letdown Containment Isolation Valves
- c I
(
Test Requirements:
IWV-3410 (3 months) 1>
Basis for Relief:
The charging and letdown subsystems of the Chemical and Volume Control System provide pressurizer level control and chemical control of the reactor coolant system. Full-stroke exercising these valves during power operation on a quar-terly basis could cause a loss of pressurizer level control and possibly a plant trip.
Alternate Testing:
These valves shall be full-stroke exercised during cold shutdoens.
G Rev. 1
T d
i -
Relief Request:
V-37 Valves:
CBS-V58 and CBS-V60 Category:
C Code Class:
2 Function:
(Active) Charging Pump Suction Valves from RWST.
?-
f Test Requirements:
IWV-3520 (3 months) 5
'l i
Basis for Relief:
It is impractical to full-stroke exercise these valves quar-terly.
In order to full-stroke exercise these valves, it is necessary to inject flow through the charging pumps to the High Head Safety Injection flow path.
If charging flow was directed to the RCS in this manner, it could cause a loss of charging flow control during plant operation resulting in pressurizer level changes and possibly a plant trip.
Additionally, charging flow through these valves during
.i.
plant operation would also result in the injection of rela-s tively cold water into the RCS possibly resulting in the cold shocking of system components.
During cold shutdowns, the injection of charging flow could result in low-temperature overpressurization of the RCS.
I -
Alternate Testing: These valves shall be full-stroke exercised during refueling outages.
e t
Rev. 1 a
y y
Relief Request:'
V-38 Valves:
CS-V200 and CS-V209 Category:
C Code Class:
2 Function:
(Active) Centrifugal Charging Pump Discharge Check Valves Test Requirements:
IWV-3520 (3 months)
>f T-Basik for Relief:
These valves can only be partially stroked during power operations. There is insufficient flow during charging operations to full-stroke exercise these valves. During the quarterly ch.trging pump test, flow is directed through the seal water heat exchanger to the suction of the pumps.
These valves cannot be exercised during cold shutdowns since injection flow from the charging pumps could result in low-temperature overpressurization of the RCS.
Alternate Testing: These valves shall be full-stroke exercised during refueling outages.
Rev. 1
Relief Request:
V-39 Valves:
CC-TV2271-1, CC-TV2271-2, CC-TV2171-1, CC-TV2171-2 Ca tegory:
B Code Class:
3 Function:
(Active) Primary Component Cooling Water Temperature Control Valves Test Requirements:
IWV-3410 (3 months) 5 h
Basis for Relief:
Full-stroke exercising these valves during power operations requires isolating one train of primary component cooling and could possibly isolate cooling water supply to many vital components.
Alternate Tes ting:
These valves shall be full-stroke exercised during cold shu tdown s.
Relief Request:
V-40 Valves:
CBS-V3 and CBS-V7 Category:
C Code Class:
2 Function:
(Active) Containment Spray Pump Suction Check Valve from the RWST Test Requirements:
IWV-3520 (3 months) s P
Basis for Relief:
These valves can only be partially stroked during quarterly pump testing. There is insufficient flow through these valves when the containment spray pump is operated in its RWST recirculation test path to full-stroke open these valves. The necessary flow required to full-stroke exercise these valves per the Code requirements would require the initiation of containment spray flow into the containment which is impractical.
Alternate Testing: These valves shall be partially disassembled, inspected, and manually exercised on a staggered sampling basis each refueling outage. At each disassembly, it shall be verified that the disassembled valve is capable of full stroking and that its internals are structurally sound (no loose or corroded parts).
In the event that the disassembled valve's full-stroke capability is in question, both valves in this group shall be disassembled.
Rev. 1
Relief Request:
V-41 Valves:
MS-V94 and MS-V96 Category:
C Code Class:
3 Function:
(Active) Full-stroke open to allow system'to supply the-Emergency Feedwater Pump Turbine Test Requirements:
IWV-3520 (3 months)
L n
Basis for Relief:
During quarterly testing of the Emergency Feedwater Turbine Pump (P-37A), there is insufficient flow to full-stroke exercise these valves in accordance with the requirements of the Code. These valves are partially stroked during the quarterly pump test of the pump. Full-stroke exercising these valves would require flowing emergency feedwater to the steam generators which is impractical.
Alternate Testing: These valves shall be full-stroke exercised during plant cooldown to cold shutdown or heat-up from cold shutdown when there is sufficient steam available to full-stroke exercise these valves.
Rev. 1
Relief Request:
V-42 Valves:
SI-V5, SI-V6, SI-V20, SI-V21, SI-V35, SI-V36, SI-V50 and SI-V51 1
Category:
AC poda Class:
1 Function:
(Active) Reactor Coolant Pressure Boundary Isolation Valves Test Requirements:
IWV-3520 (3 months)
F Basis for Relief:
These valves cannot be full-stroke exercised quarterly during power operation because the safety injection accumu-lators have insufficient pressure to flow into the RCS.
Additionally, valves (SI-V5, SI-V20, SI-V35 and SI-V50) can-not be exercised quarterly during power operation because the RHR pumps have insuf ficient pressure to flow into the RCS.
During cold shutdowns, there is not sufficient flow using the RHR pumps to full-stroke exercise these valves (SI-V5, SI-V20, SI-V35 and SI-v30). These valves shall be partially stroked during cold shutdowns.
Also, during cold shutdowns these valves cannot be exercised because the accumulator isolation valves (SI-V3, SI-V17, SI-V32 and SI-V47) are required by the plant technical speci-fications Section 4.5,2 to be closed with power removed from the operators. SI flow from the accumulators could also risk low-temperature overpressurization of the RCS.
Alternate Testing: These valves shall be partially disassembled, inspected and manually exercised on a staggered sampling basis each refueling outage. At each disassembly, it shall be verified that the disassembled valve is capable of full stroking and that its internals are structurally sound (no loose or corroded parts).
In the event that the disassembled valve's full stroke capability is in question, all valves in this group shall be disassembled.
Rev. I
l i;
Relief Request:
V-43 Valves:
RC-V323 and RC-FV2881
~
Category:
B
-Code Class:
2 Function:
(Active) Reactor Vessel Head Vent Valves
' Test Requirements:
IWV-3410 (3 months) 5 l>
Basis for Relief:
Full-stroke exercising these valves on a quarterly basis would increase the risk of placing the' plant in a small transient in the event there' i~s a failure of one of the vent valves.
If one of~the vent valves experienced a failure and the reactor head was vented to the Pressurizer i
Relief Tank (PRT) during operation, there would be a pressure drop in the reactor coolant system until the level control system in the pressurizer could respond.
Full-stroke exercising these valves quarterly increases the potential o.f putting the plant through an excursion to test the system.
2 h,
AlternateTestin[:
These valves shall be full-stroke exercised during cold
[
~
shutdowns to assure valve operability while eliminating the risk of a plant transient.
p 9
/
Rev. 1 e
.q s
J i e
~-
---n
Relief Request:
V-44 Valves:
DGA-FYAS1, DG-FYAS2, DGB-FYASI and DGB-FYAS2 Category:
B Code Class:
3 Function:
(Active) Emergency Diesel Generator Air Start Solenoid Valves Test Requirements:
IWV-3413 Limiting Values of Full Stroke Time IWV-3417 Corrective Action Basis for Relief:
It is impractical to measure the limiting value of full-stroke time of these valves.
The safety function of these valves is to open to support the startup of its respective dieset to provide rated frequency and voltage in less than ten seconds. Successful startup of each emergency diesel generator within the above specified conditions is depen-dent upon the proper operation and speed of these valves.
Additional code required full-stroke time measurement of the valves will not increase the assurance that the diesel generators will start as required. Upon failure of the diesel generators to start as required, corrective action shall be taken to assure proper diesel startup conditions.
These valves shall be full-stroke exercised during required monthly diesel testing.
Alternate Testing:
None i
i Rev. 1
Relief Request:
V-45 Valves:
DG-PV7A1, DG-PV7A2, DG-TCV7A1, DG-TCV7A2, DG-PV7B1, DG-PV7B2, DG-TCV7B1 and DG-TCV7B2 Category:
B Code Claas:
3 Function:
(Active) Emergency Diesel Generator Cooling Water System Temperature and Pressure Control Valves Test Requirements:
IWV-3410 (3 months)
L IWV-3417 Basis for Relief:
Exercising these valves at any periodic frequency is impractical. The primary function of these valves is to modulate to control the pressure and temperature of the cooling water of each emergency diesel generator. Full-stroke exercising these valves would not verify the opera-bility of these valves. Periodic operation of the diesels verifies operability of these valves.
Alternate Tescing:
These valves are included in the inservice test program because of their fail-safe function. These valves shall be verified on a quarterly basis that they fail to the maximum cooling position upon loss of actuator power.
Rev. 1
e s.
'l 6.2 Relief Requests Pumps 9
lo Rev. I
Relief Request:
P-1 Pumps:
CC-P-llA, CC-P-llB, CC-P-llc, CC-P-llD, CS-P-2A, CS-P-2B, DC-P-38A, DC-P-38B, SW-P-110A, SW-P-110B, SI-P-4A, SI-P-4B, CBS-P-9A, CBS-P-9A, CBS-F-9B, RH-P-8A, RH-P-8B Code Class:
2 and 3 Function:
Pumps required to perform a function in shutting down the reactor, or in mitigating the consequences of an accident, and are provided with an emergency power source.
Test Requirements:
IWP-4600 (Accuracy Limits Table IWP-4110-1)
Basis for Relief:
New Hampshire Yankee uses flow measuring instrumentation which meets the acceptable instrument accuracies defined in
- Table IWP-4110-1.
However, tha rotal flow element loop f.
accuracy was calculated from the flow device to the computer' readout providing hard copy log data. The loop accuracies do not meet the instrument accuracies of Table IWP-4110-1, but the instruments are well within the table limits for flow rate (see Attachment 8.2).
Alternate Testing: No additional testing is necessary.
9 Rev. 1 rv v
Relief Request:
P-2 Specific relief is being requested from the subsection IWP-3300 to measure bearing temperatures at least once per year.
Pumps:
All Code Class:
2 and 3 Function:
Pumps required to perform a function in shutting down the reactor or in mitigating the consequences of an accident, and are provided with an emergency power source.
Test Requirements:
Bearing temperatures shall be measured during at least one in-service test each year.
Basis for Relief:
The referenced edition of the Code requires bearing tem-perature to be recorded annually.
It has been L
demenstrated by experience that bearing temperature rise occurs only minutes prior to bearing failure. Therefore, the detection of possible bearing failure by a yearly tem-perature measurement is extremely unlikely.
It requires at least an hour of pump operation to achieve stable bearing temperatures. The small probability of detecting bearing failure by temperature measurement does not justify the additional pump operating time required to obtain the measurements.
J Alternate Testing:
As an alternate, the pump vibration testing will be expanded from 1 to multiple readings in two orthogonal directione.
~
Rev. 1
+i
?-
6.3 Relief Requests General Rev. I
Relief Request:
G-1 Valves:
All 10CFR50 Appendix J Tested Containment Isolation Valves that serve only a containment isolation function.
Category:
A and AC Code Class:
2 Function:
Containment Isolation Test Requirements:
IWV-3421 through IWV-3425 Basis for Relief:
Leak test procedures and requirements for containment iso-lation valves are determined by 10CFR50 Appendix J.
Relief from paragraphs IWV-3421 through 3425 (1983 Edition through Summer 1983 Addenda) presents no safety problem 6
sincetheintentoftheseparagraphsismetbyAppendixJf.
requirements.
Alternate Testing:
All 10CFR50 Appendix J tested valves that serve only a containment isolation function shall be tested in accor-dance with the requirements of Appendix J.
Rev. I
Relief Request:
G-2 Valves:
Solenoid Power Operated Valves Category:
A, B
-Code Class:
1,2,3 Function:
General Test Requirements:
IWV-3300 Basis for Relief:
It is not practical to perform valve position indication verification tests as stated every two years in Subsection IWV-3300. These va!.ves will require disassembly of actuator components to verify operation. The accurate l-visual verification of valve operation is not possible due to the minimal' stem travel and short stroke period. This visual observation would not contribute significantly to the assurance of safe and proper valve operation.
1 Alternate Testing:
Valve open and closed indications shall be verified by monitoring normal system parameters at least once every two years during exercise testing, e.g.,
(flow, tem-perature or pressure).
4 Rev. 1
3 Relief Request:
C-3 Valves:
All Valves Equipped to Fail Safe Category:
A and B Code Class:
1, 2, 3 and valves important to plant safety Function:
Upon loss of actuator power, the valve must stroke to its fail safe position.
Test Requirements:
When practical, valves with fail-safe actuators shall be tested by observing the operation of the valves upon loss of actuator power (IWV-3415).
I r
Basis for Relief:
Solenoid valves which control the air supply to air-operated valves and direct solenoid-operated valves must stroke to their fail safe position upon interruption of-their electric supply. De-energizing the solenoid valve has the same effect as a loss of electrical power or control air. Therefore, stroking the valve from the control switch to its fail-safe position constitutes a fail-safe test.
Alternate Testing:
No additional testing is necessary.
Rev. 1 r
r
. Relief Request:
G-4 Valves:
All rapid acting valves r
Category:
A and B Code Class:
1, 2, and 3 Function:
Rapid acting valves are defined as valves that stroke in two seconds or less.
' Test Requirements:
IWV-3417(a) (Corrective Action) basis for Relief:
Relief from the trending requirements of Section XI L
(Paragraph IWV-3417(a), 1983 Edition through Summer of 1983 Addenda) presents no adverse safety concerns for these valves since variations in stroke times will be affected by slight variations in the response times of the personnel performing the tests.
Alternate Testing:
None Rev. 1
Relief Request:
G-5 Valves:
Power operated valves that cannot be exercised during power operation.
Category:
A and B Code Class:
1, 2 and 3 Function:
Various Test Requirements:
IWV-3417(a) Corrective Action Basis for Relief:
It is impractical to increase the testing frequency for these valves. Strict adherence to this requirement for valves which cannot be exercised during power operations would require that the test frequency be increased to once each month or until corrective action is taken. Exercising these valves would require a plant shutdown or operation under unusual conditions.
Alternate Testing:
The subject valves shall be full-stroke exercised only during cold shutdownsson a frequency determined by the intervals between shutdowns as follows:
A.
For intervals of one month (31 days) or longer, tests will be performed during each shutdown.
B.
For intervals of less than one month (31 days), tests will not be performed unless one month (31 days) has passed since the last shutdown.
Rev. 1
7.0 DRAWINGS 9763-F-202074 Main Steam 9763-F-202076 Emergency Feedwater System 9763-F-202079 Feedwater System 9763-F-202086 Main Turbine And Steam Drains 9763-F-202100 Auxiliary Boiler Steam And Condensate Return 9763-F-202101 Diesel Generator Air Start System 9763-F-202102 Diesel Generator Fuel and Lube Oil 9763-F-202103
' Diesel Generator Cooling Water System 9763-F-202108 Service Air System 9763-F-500037-2 Leak Detection System 9763-F-604131 Fuel Pool and Purge Exhaust System 9763-F-604146 Fire Protection System 9763-F-804958 Floor and Equipment Drain System 9763-F-804978 Sample System-Nuclear-Post Accident 9763-F-804981 Primary Component Cooling Water Loop "A" 9763-F-804982 Primary Component Cooling Water Loop "B" 9763-F-804988 Refueling Cavity Clean Up System 9763-F-804989 Service Air 9763-F-804994 Floor And Equipment Drain System 9763-F-805002 Reactor Coolant System Reactor Vessel 9763-F-805003 Reactor Coolant System Loop Number 1
[
9763-F-805006 Reactor Coolant System Loop Nusber 4 p
9763-F-805007 Reactor Coolant System Pressurizer 9763-F-805008 Residual Heat Removal System 9763-F-805009 Safety Injection System Accumulators 9763-F-805010 Safety Injection System High Head 9763-F-805011 Chemical and Volume Control System / Purification 9763-F-805012 Chemical and Volume control System / Charging 9763-F-805014 Chemical and Volume Control System /Boration 9763-F-805016 Primary Component Cooling Water Loop "B" 9703-F-805018 Primary Component Cooling Water Loop "A" 9763-F-805019 Service Water System Nuclear 9763-F-805020 Gas Service System Nitrogen Nuclear 9763-F-805021 Reactor Water Make Up 9763-F-805022 Combustible Gas Control System 9763-F-805023 Containment Spray System 9763-F-805024 Steam Generator Blowdown 9763-F-805025 Sample System Nuclear 9763-F-805028 Primary Component Cooling Water Loop "B" 9763-F-805029 Primary Component Cooling Water Loop "A" 9763-F-805030 Demineralized Water System Nuclear 9763-F-805033 Service Water System 9763-F-805040 Reactor Coolant Drain Tank Containment 9763-F-805635 Equipment Vent System Hydrogenated Vent Header Rev. I
ATTACHMENT 8.1 LIMITING VALUES OF FULL STROKE TIME (SEC.)
Main Steam P&ID 202074 /202110 Valve Time MS-PV3001 35 MS-PV3002 35 MS-PV3003 35 MS-PV3004 35 MS-V86 5
MS-V88 5
MS-V90 5
MS-V92 5
MS-V127 8
MS-V128 8
5 MS-V204 15 h
MS-V205 15 MS-V206 15 MS-V207 15 MS-V393 7
MS-V394 7
MS-V395 7
Emergency Feedwater P&ID 202076 Valve Time i
FW-FV4214A 16 FW-FV4214B 16 FW-FV4224A 16 FW-FV4224B 16 FW-FV4234A 16 FW-FV4234B 16 FW-FV4244A 16 I
FW-FV4244B 16 Rev. 1 4
r
._t.
l Feedwater System P&ID 202079 Valve Time FW-V30 5
FW-V39 5
FW-V48 5
FW-V57 5
Main Turbine and Steam Drains P&ID 202086 Valve Time MSD-V44 20 MSD-V45 20 MSD-V46 20 MSD-V47 20 Aux Boller and Steam Condensate Return P&ID 202100 Valve Time AS-V175 15 AS-V176 15 Containment Purge P&ID 604131 Valve Time CAP-V1 3
CAP-V2 3
CAP-V3 3
CAP-V4 3
COP-V1 2
COP-V2 2
COP-V3 2
COP-V4 2
CAH-FV6572 1
Call-FV6573 1
CAH-FV6574 1
Rev. 1
Floor Drains' P&ID 804958 Valve Time WLD-FV8330 1
Post Accident Sampling P&ID 804978 Valve Time SS-FV2857 1
Primary Component Cooling - Loop A P&ID 804981 Valve Time CC-V137 30 CC-V145 30 CC-V32 30 Primary Component Cooling - Loop B P&ID 804982 Valve Time CC-V266 30 CC-V272 30 CC-V445' 30 Floor and Equipment Drain P&ID 804994 Valve Time WLD-FV8331 1
Reactor Coolant - Reactor Vessel P&ID 805002 Valve Time RC-FV2881 1
RC-V323 10 Reactor Conlant - Loop 1 P&ID 805003 Valve Time RC-V22 120 RC-V23 120 Rev. 1
Reactor Coolant - Loop 4 P&ID 805006 Valve Time RC-V87 120 RC-V88 120 Reactor Coolant Pressurizer P&ID 805007 Valve Time RC-PCV456A 2
RC-PCV456B 2
FC-V122 10 RC-V124 10 Residual Heat Removal P&ID 805008 Valve Time RH-V14 15 RH-V21 15 RH-V22 15 i
RH-V26 15 E
RH-V32 40 RH-V35 15 RH-V36 15 RH-V70 40 RH-FCV610 10 RH-FCV611 10 RH-V27 10 RH-V28 10 Safety Injection Accumulators P&ID 805009 Valve Time SI-V62 10 SI-V70 10 Rev. 1
i SAFETY INJECTION HIGH HEAD P&ID 805010 Valve Time CBS-V47 15 CBS-VS1 15 CS-V460 15 CS-V461 15
'CS-V475 15 SI-V77 10 SI-V89 10 SI-V90 10 SI-V93 10 SI-V102 10 SI-Vill 15 SI-V112 15 SI-V114 10 CBS-V49 10 CBS-V53 15 SI-V138 10 SI-V139 10 SI-V157 10 SI-V158 10 gJ SI-V160 10 RH-V49 10 SI-V131 10 SI-V134 10 CHEMICAL AND VOLUME CONTROL / PURIFICATION P&ID 805011 Valve Time CS-V142 10 CS-V143 10 CS-V149 10 CS-V150 10 CS-V167 10 i
CS-V168 10
.i Rev. 1 i
-,.._n
--....,n,~
.,,. - - -. - - - -, _..., - -,.,. +. - -,., -,. - -
. =..,
=
J CHEMICAL AND VOLUME CONTROL / CHARGING P&ID 805012 Va lve Time CS-V196 10 CS-V197 10 CS-LCV112B 8
CS-LCV112C 8
1 CHEMICAL AND VOLUME CONTROL /B0 RATION P&ID 805014 i
Valve Time CS-V426 10 4
PRIMARY COMPONENT COOLING - LOOP B P&ID 805016 Valve Time CC-T V2271-1 25 i
CC-T V2271-2 25 E
CC-V447 14 CC-V448 14 PRIMARY COMTONENT COOLING - LOOP A P&ID 805018 Valve Time CC-T V2171-1 25 7
CC-T V2171-2 25 CC-V341 30 CC-V426 14 CC-V427 14 I
Rev. 1 i-
--. _= _.-
SERVICE WATER P&ID 805019 Valve Time SW-V4 56 SW-V5 56 SW-V15 69 SW-V16 50 SW-V17 69 SW-V18 60 SW-V19 69 SW-V20 69 SW-V23 44 SW-V25 44 SW-V34 69 SW-V54 69 SW-V27 69 SW-V56 69 SW-V139 70 SW-V140 70 SW-V74 69 SW-V76 69
[
r-NITROGEN GAS P&ID 805020 Valve Time NG-V13 10 NG-V14 10 NG-FV4609 1
NG-FV4610 1
REACTOR MAKEUP WATER P&ID 805021 Valve Time RMW-V30 10 COMBUSTIBLE GAS CONTROL P&ID 805022 Valve Time CGC-V14 8
CGC-V28 8
Rev. 1
CONTAINMENT SPRAY P&ID 805023 Valve Time CBS-V2 20 CBS-V5 20 CBS-V8 32 CBS-Vil 10 CBS-V14 32 CBS-V17 10 CBS-V31 10 CBS-V32 10 CBS-V33 10 CBS-V38 15 CBS-V43 15 CS-LCV112D 15 CS-LCV112E 15 STEAM GENERATOR BLOWDOWN P&ID 805024 Valve Time SB-V1 10 SB-V3 10 SB-V5 10
[
SB-V7 10 F
SB-V9 10 SB-V10 10 SB-V11 10 SB-V12 10 SAMPLE SYSTEM P&ID 805025 Valve Time RC-FV2830 1
RC-FV2831 1
RC-FV2832 1
RC-FV2833 1
RC-FV2836 1
RC-FV2837 1
RC-FV2840 1
RC-FV2874 1
RC-FV2876 1
Re-FV2894 1
RC-FV2896 1
PRIMARY COMPONENT COOLING P&ID 805028 Valve Time CC-V175 10 CC-V176 10 CC-V256 10 CC-V257 10 Rev. 1 9
o'
PRIMARY COMPONENT COOLING - LOOP A P&ID 805029 Valve Time CC-V168 10 CC-V57 10 CC-V121 10 CC-V122 10 SERVICE WATER P&ID 805033 Valve Time SW-V2 44 SW-V22 44 SW-V29 44 SW-V31 44 L
REACTOR COOLANT DRAIN TANK; CONTAINMENT 9
Va lve Time WLD-V81 10 WLD-V82 10 EQUIPMENT VENTS TIME VG-FV1661 1
VG-FV1712 1
l 1
a Rev. 1 l
I i
c ATTACHMENT 8.2 FLOW MEASUREMENT INSTRUMENT ACCURACIES
(% of Full Scale)
Instrument Loop System Accuracy Accuracy CBS 0.5%
2.2%
CC 0.5%
3.29%
DG 0.5%
2.2%
FW 0.5%
2.0%
SW 0.5%
2.5%
0.5%
3.67.
f' SI 1.0%
2.2%
RH 2.0%
3.0%
Rev. I
ATTACHMENT
8.3 DESCRIPTION
OF OPERATIONAL MODES REACTIVITY
% RATED AVERAGE COOLANT MODE CONDITION, Keff THERMAL POWER
- TEMPERATURE 1.
POWER OPERATION
> 0.99
> 5%
> 350*F 2.
STARTUP
> 0.99
< 5%
> 350'F 3.
HOT STANDBY
< 0.99 0
> 350'F 4.
HOT SHUTDOWN
< 0.99 0
350*F > Tavg
> 200*F 5.
COLD SilUTDOWN
< 0.99 0
< 200'F 6.
REFUELING **
< 0.95 0
< 140'F
- Excluding decay heat.
- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
Rev. 1