ML20101R172
| ML20101R172 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/11/1992 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20101R167 | List: |
| References | |
| PROC-920611, NUDOCS 9207150253 | |
| Download: ML20101R172 (194) | |
Text
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i' 2nd Intervat IST Program vot. I tevision 01 ENGINEERING DEPARTMENT PERFORMANCE ENGINEERING INSERVICE INSPECTION PLAN (ISI Plan)
Volume I Second Ten-Year y! clear Interval Pump and Valve Inservwe Testina Procram Preparedby!'[l D../
M) ~ #i 6 //* 7 Peter Seniuk Fate 7ff..lR/JiL,~6<1 e n - n.
Qualified Reviewer
'( 10C FR50. 59 )
Date Reviewod by:-
d-//~f/-
Jrfa Barron Date
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Approved-by: 8E.b c Y, [/s
'bote O //-92 Erd aba
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Cover Sheet 920?150253 920709
. PDR _ADOCK 05n0^346 P.
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- t 2nd Interval l$f Program vot. I tevision 01 TUMP AND VALVE INSERVICE TESTING PROGRAM
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2nd Intervel !$f Program Vol. I tevision 01 s
I PUMP AND VALVE INSER7 ICE TESTING PROGRAM FOR DAVIS-BESSE NUCLEL
.0WER STATION SECTION I INTRODUCTION n
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2rd interval 157 Program Ve!. 1 Reviston 01 I.
INTRODUCTION
-I.1 GENERAL 1
This document presents the program for inservice testing (IST) of pumps and valves at the Davis-Besse Nuclear Power Station in compliance with the requirements of 10 CFR 50.55a.
According to 10 CFR 50. 55a (g) (4) (ii), following completion of the first 120-month inspection. interval, successive 120-month inspection intervals shall comply with the requirements of the latest edition and addenda of the American Society of Mechanical Engineers (ASME)
Code incorporated by reference in paragraph (b) of 10 CFR 50.55a 12 months prior to the. start of the 120-month inspection interval.
The second 120-month inspection interval for the Davis-Besse Nuclear ~ Power Station start date was September 21, 1990.
This start date for the second 120-month inspection interval was in compliance with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1986 Edition.
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2nd intervet 151 Program vol. i Revision 01 I.2 Basig NRC Reculations Code of Federal-Regulations 10CFR50.55a(g) (4) (ii) establishes the applicable edition and addenda of Section XI of the ASME Boiler and Pressure Vessel Code to be used for each successive inservice inspection interval for a nuclear power plant.
This paragraph states:
" Inservice examinations of components, inservice tests to verify operational readina.s of pumps and valves whose function is required for safety, and system
-pressure-tests, conducted d ing successive 120-month inspection intervals shall comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section 12 months prior to the start of the 120-month inspection interval, subject'to the limitations and modifications listed in paragraph (b) of this section."
The latest edition of ASME Secticn XI referenced in paragraph (b) of 10CFR50.55a is_the 1986 Edition and accordingly the second 10-year IST program for DBNPS shall' comply with 1986 Edition of ASME Section XI.
In additi n to the reference Code edition and addenda, this-program has been prepared in compliance with NRC guidance contained in " Guidance for Preparing Pump and Valve Testing Program Descriptions and Associated-Relief Requests Pursuant to 10CFR50.55a(g)" and the guidance contained in Generic Letter 89-04.
These three dccuments provide the basis for.
selection of components, test requirements, relief requests, and format.
I.3-scope The Pump and Valve Inservice Testing Program provides testing requirements _for-all safety-related pumps and valves.
Safety-related: components are.those required by either Eposition or movement to:
a) shut-down the reactor to the safe shutdown condition *
- b). maintain the reactor in the safo-shutdown condition
- c) mitigate the consequences-of an accident-
- Safe reactor-shutdown for the Dhvis-Besse Nuclear Power Station.is defined in Section 7.4.1 of'the USAR as that station condition-in which1the reactor is 1.0 percent subcritical-and the reactor coolant system temperature and pressure are in_the normal: operating range.-
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2rd Itstervat !$f Progrm vol. i Revision 01 Safety-related systems and components include both ASME Code Class 1, 2,
and-3 as well as non-class systems and components if they are safety-related.
The construction permit for Davis-Besse Nuclear Power Station was issued on March 24, 1971.
I.3.1 Criteria 12r Safe Shutdown CgnditionsSection XI, IWV 1100 Scope addresses equipment to be tested as ".. required to perform a specific function in shutting down a reactor to the cold shutdown condition, in mitigating the consequences of an accident or in providing overpressure protection."
Davis-Besse Power Station defines shutting down the reactor per Section 7.4.1 of the USAR as that station condition in which the reactor is 1.0 percent subcritical and the reactor coolant system temperature and pressure are in the normal operating range.
Per Davis-Besse Technical Specifications this condition is defined as Mode 3,
Hot Standby.
A Cold Shutdown condition is not required to shut down the reactor.
This is based on the above conditions which is part of the licensing basis for the Davis-Besse Nuclear Power Station.
I.4 Auomented Components Plant test procedures, manufacturer's recommendations, and the Davis-Besse Technical Specifications may require testing of additional pumps and valves not within the scope of Section XI testing, as defined above.
These additional test requirements are not addressed by this program.
I.5 General Procram Concent Section XI requires quarterly testing of all components t
unless it is imp:actical to do so.
This program specifies quarterly testing of pumps and valves unless it has been determined that such testing would:
1.
-Be impractical due to system or component design.
2.
Render a safety-related system inoperable for an extended length of timee 3.
Cause a reactor scram or turbine trip.
4.
Require significant devj ations from normal operations.
5.
Require entry into inaccessible plant areas.
6.
Increase the possibility of an inter-system LOCA.
Excluded from exercising during normal operations are all valves which, if exercised, could place the plant in an I-4 9
o tr<f Interval !$f Program vol, t tevision 01 unsafe condition.
Cases where valve exercising could q
compromise plant safety include:
1.
All valves whose failure in a nonconservativa position during the cycling test would cause a loss of system function will not be exercised.
Valves in this categorv would typically include all non-redundant valves in lines such as single discharge i,
line from the Borated Water Storage Tank.
Other i
valves muy fall into this category under certain system configurations or plant operating modes.
For example, when one train of a redundant system such as I
ECCS is inoparable, non-redundant valves in the remaining train will not be stroked. since their failure in the closed position would cause a loss of total system funct'.on.
2.
All valves, whose failure to close during a cycling test would result in a loss of containment integrity will not Le tested.
Valves in this category would typically include all valves in containment
,u peactrations where the redundant valve is open.
2 3.
All valves, which when cycled, could subject a system to pressures in excess of their design pressures.
It f
is assumed for purpose of a cycling test, that one or more of the upstream check valves has failed unless
=
positive methods are available for determining the pressure or lack thereof on the high pressure side of the valve to be cycled.
Valves in this category
-3 would typically include the isolation valves of the residual heat removal / shutdown cooling system and, in l
some cases certain ECCS valves, q
d Each component excluded from quarterly testing has been analyzed
]i to determine when appropriate testing may be performed.
If exercising of a valve is not practical during plant operation, the I
Code allows part-stroke exercising during normal plant operation, I
and full-stroke exercising at cold shutdown.
Since the Code allows testing at cold shutdown, this program does g-j not request relief for those valves for which testing is delayed l'
until cold shutdown.
The Valve IST Program does provide a justification for the delay of testing until cold shutdown.
These justifications are prepared in a format similar to relief requests, and are included following the Valve Test Tables for each r estem.
Where it has been determined f it is impractical to comply with Code requirements, 10 CFR 50.5 s
,a) requires that a relief request be submitted to the Nba.
NRC Generic Letter 89-04 provides preapproval for several Code alternative test requirements.
The Generic Letter states that if a component is I-5
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2nd Interval ist H ogram vol. I anuon ot i
tested consistent with the positions taken in Attachment 1 of Generic Letter 89-04 as alternatives to the Code requirements, it should be noted in the IST program and approval is granted through the Generic Letter.
Since the Generic Letter grants preapproval er Code alternative test requirements, this program does not
.e.,uest relief for those alternatives addressed uy the Generic s'cte r.
l This program does provide a justification for the nood to apply the preapproved Code alternative test requirements.
These justifications are prepared in a format similar to relief requests, and are included in the program following the component test tables.
Where it has been determined that testing is not practical during plant operation, or at cold shutdown, and is not addressed by NRC Generic-Letter 89-04, a specific relief request has been prepared.
Each relief requent provides justification for not performing the Code required testing, and provides appropriate alternative testing.
In. addition-to specific relief requests, general relief requests which avirosa specific Code requirements found to be impractical for this site have been prepared.
Because of the general nature i
of th,se relief requests, and-the number of components involved, they are presented in separate sections and are no' repeated in the individual system sections.
Cold Shutdcwn and Refueling as used in this test program' includes mode changes going into and coming out of plant Technical Specifications defined modes 5 and 6.
Because of unique system operating conditions, it will be necessary to perform some tests during mode change.
For example, a steam driven turbine scheduled for testing at cold shutdown cannot be tested during mode 5 when there is no steam available.
In this case, testing will be performed duxing a modo change when sufficient steam is available.
I.6 oroanization The Pump and Valve Inservice Testing ' 'ogram is organized into three independent sections, each of #4ch can be removed from the Program for review.
Section I presenta the general program commitment basis and the cor.;eptual frameworP. used in developing the Program Plan.
Section II deals specifically with the Pump Test Program, and-Section III deals specifically 41th the Valve Test. Program.
-Sections II and III are formatted in a mantier to aid review.
Each section summarizes the basis and cancepts usedsto formulate the Pump and Valv2 Testing Program.
PJmp testing requirements are single Pump Test Table attached to Section II.
summarized ir a Valve test raiuirements aro summarized-in Valve Test Tables attached to Se tion III.
The Valve Test Tables are arranged into separr'4 attachments for each system.
Where quarterly testing has I-6
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N Inter..t ist prov e vot. I n ev m on 01 been found to be impractical, a justification for delay of test to cold shutdown, a Generic Letter 89-04 justification or a relief request, is provided following the appropriate Pump or Valve Test Tabico.
I.7 RfFINITIONS The terms below, when used in the Inservice Testing Program, are defined as follows:
Quarterly:
An interval of 92 days for testing components which can be tested during normal plant operation.
. Cold Shutdown:
Testing delayed until cold shutdown will commence as soon as cold shutdown condition is achieved, but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after achieving cold shutdown.
Testing will continue until all tests are complete or the plant is ready to return to power.
Completion of testing is not a prerequisite to return to power, and any testing not completed at one cold shutdown will be performed during nubsequent cold shutdowns before the refueling outage.
No cold shutdown testing will be performed on any components tested less than 92 days prior to achieving cold shutdown.
The 48-hour interval will not hold for planned cold shutdowns where all required testing will be completed.
In addition, all components which have testing delayed to cold shutdown will be tested during each refueling unless the component has been tested during the previous three months.
Cold Shutdown testing includes testing performed during Plant Operating Modes between Normal Operation and Technical Specification defined Cold shutdown conditions.
Refueling:
Testing delayed to refueling will be performed during the normal scheduled refueling shutdown before returning to power operation.
Refueling testing includes testing performed during plant operating modes between normal and Technical Specification defined refueling conditions.
Period:
Category C safety and relief valves (INV-3511), Category D explosive actuated valves (IWV-3610), and Category D rupture I-7 l
tre interval llt Program Vol. I Aevision 01 disks (IWV-3620) are periodically tested, as defaned in the appropriate Code cections.
pressure Isolation:
Valves which act as an isolation boundary between the high-pressure reactor coolant system and a system having a lower operating or design pressure, and designated as pressure isolation valves in Table 3.4-2 of the plant Technical Specifications.
Containment Isolation: Any valve which performs a containment isolation function and is included in the Appendix J, Type C, local leak rate test program.
Active:
Any valve which is required to change position to accomplish its safety-related functions.
All valves not designated as possive LPAS) on the valve test tables are cons:.dered to be active valves.
passive:
Any valve which is not required to change position to accomplish a specific function and for which t!t Code does not requite operability testing.
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l 2rd Intervat l$1 Program Vol. I tevision 01 PUMP AND VALVE INSERVICE TESTI!1G PROGRAM FOR DAVIS-BESSE NUCLEAR POWER STATIO!!
SECTION II PUMP IST PROGRAM s
II-1
2nd intervet 157 Program vol. I tevision 01 PUMP IST PROGRAM II.1 INTRODUCTION This section presents the program for inservice testing Power Station,y related pumps at the Davis-Besse Nuclear (IST) of safet in compliance with the requirements of 10 CFR 50.55a.
This program has been prepared to the requirements of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code,Section XI, Subsection IWP, 1986 Edition for ASME Class 1, 2,
and 3 pumps that are required to perform a specific function in shutting down a reactor or in mitigating the consequences of an accident, and that are provided with an emergency power source.
II.2 Concept The pump test program has been developed to detect and monitor safety-related pump degradation.
The Program addresses all pumps that are required to perform a specsfic function in shutting down a reactor or in mitigating the consequences of an accident, and that are provided with in emergency power source.
This program specifies either Section XI or alternative testing, as appropriate, for *21 pumps that perform a safety-related function.
Pumps have been selected for inclusion in the test program based on a review of all plant systems.
This review identified those systems performing safety-related functions.
Each safety-related system was then analyzed to determine which pumps are essential to the safety-related operation of the system and if they are powered from an emergency power source.
All pumps that fit these criteria were analyzed to determine whether Section XI testing can be performed on a quarterly basis and if all re@ ired test parameters could be measured in compliance with the Code.
Where it was determined that a delay of test is required or Code test requirements could not be implemented either a Generic Letter 89-04 justification or a relief request is provided following the pump test tables.
II.3 Code Interpretations A number of items in Subsection IWP of the Code are subject to interpretation.
The interpretations of a number of general items encountered in preparing the pump test program are provided belows II.3.1 Pumn Test Data Analysis - Reauired Action Rance
@antities, quires that the measured and observed IWP-6000 re limits and acceptance criteria be included in the test procedure.
This data will be used following completion of pump testing to II-2
2nd Irsterval 151 Program vol. I tevision 01 determine if the test data is within the Required h'
Action Range of Table IWP-3100-2.
When the data is P
determined to be within the required action range, the effect on Technical Specification operability of the pump will be assessed and any applicable Technical Specification Action statement time starts.
If required due to repair or replacement, then new reference value shall be determined.
New reference values shall be documentation in the Pump and Valve Basis Document.
II.3.2 Pumo Retests to Verifv Operability If pump test data fall in the Required Action Range
-and the pump has been declared inoperable under any applicable Technical Specification Action Statement, the provision of IWP-3230(d) may be applied.
As an alternative to repair or replacement the test instruments may be recalibrated and the test rerun.
.If the pump passes the retest it will be declared operable.
If the pump fails the retest the pump remains inoperable and the Technical Specification Action Statement requirements remain in effect.
II.3.3 NRC Information Notices & Bulletins NRC issued Information Notices and Bulletins relatina to pumps were reviewed and incorporated, as applicable.
II.4 Generic Letter 89-04 Justification PRC Generic Letter 89-04 provides approval of several ASME Code alternative test requirements providing the Pump and Valve programs are consistent with the positions taken in of the Generic Letter.
The' Generic Letter states.that these preapproved alternatives to the Code should be identified for each applicable pump in the pump test program.
This program identifies these pumps by referencing Generic Letter 89-04 justifications.
These f
justificationa provide the basis for the need to use the Generic Letter alternative testing and reference the applicable Generic Letter approved alternative.
II.5 rumo Procram Relief Recuests Where Code specified test requirements cannot be' met or
(
testing must be delayed to cold shutdown or refueling outages the NRC requires that a relief request be provided, t
This program provides a relief request for each pump test requirements found to be impractical and/or testing delayed II-3 1
e 2nd intervet l$f Progree vot. I nevision et to cold shutdown or refueling outages.
II.6
. umn Test Recorda p
A system of records for pump inservice testing will be maintained at the site in accordance with IWP-6000 of Section XI.
II.7 GENERAL RELIEF REOUESTS_FOR PUMPS
.This section rewests relief from specific reW irements of Section XI found to be impractical for this site.
Since they are general in nature and pertain to a number of components, this section requests general relief as presented below.
General Relief Request:
Nene II.8 PUMP LIST Pumps included in this program are as followst ASME Class 1, 2, and-3 Pumps P&ID Drawing No. of System No.
Pumps Service Water M-041 A 3
' Auxiliary Feedwater M-006 D 2
LMakeup.
M-031 C 2
- Boric Acid Transfer-M-045 C 2
Decay ~ Heat.
M-033--B, C 2
Component Cooling Water M-036 A 3
Containment Spray M-034-2
'High-Pressure Injection LM-033 A.
2 D. G.-Fuel Oil' Transfer M-017 A-2 m
i r
.II-4
2nd interval lif Pregram vol. I tevision 01 11.9 PUMP TEST TABLE HOMENCLATURE The following abbreviations have been used in the Pump Test Tables:
Leaend for Headinas Pump I.D. Number
- Unique pump identification number ASME Class
- Classification as determined for Section XI Drawing Number & COORD.
- Piping and Instrumentation drawing number and location on drawing where pump is shown.
Relief Request
- Applicable relief request numbers are indicated with a "RP" prefix.
Reference Notes
- Hotes are located following the last Pump Test Table.
Leaend for Pumn Parameters Pi - Inlet pressure (psig) or tank level (feet)
Po - Outlet preasure (poig) dP - Differential pressure dP = Po - Pi (psid)
Q
- Flow rate (gpm)
Vd - Vibration Displacement (mil)
Vv - Vibration Velocity (inch /sec)
N-
- Speed (rpm)-
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- Lubricant level or pressure RP - Pump relief request Leaend for Freauency of Test Q
- Quarterly CS - Cold Shutdown R
. Refueling-NA - Not Applicable
- Test deleted, See Relief Request II-5
2iti intervet lli Progree Vol. I 1
sevision 01 PUMP AND VALVE INSERVICE TESTING PROGRAM FOR DAVIS-BESSE NUCLEAR POWER STATIO!!
SECTION II ATTACHMENT 1:
PUMP TEST TABLE AND RELIEF REQUESTS FOR SAFETY-RELATED PUMPS II-1-1 u
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l 2rd Interval lli Program vol, l Revision 01 PUMP TEST TABLE NOTES ASME Class 1, 2,
and 3 The Pump Test List identifies the test parameters to be measured or observed, and the test frequencies.
Notes 1 through 6 refer to am lifications of the Code requirements and are further discucsed be ow 1.
On a pump with constant speed drive, speed is not measured, since the test will be performed at nominal motor nameplate speed, as required by Section XI, IWP-3100.
2.
Inlet pressure is to be calculated from the inlet liquid level.
3.
Bearing temperature measurement is not required (IWP-4310),
since bearings are in the pump fluid flow path, such that they are completely immersed in and lubricated by the pumped fluid.
4.
Pump lubricant level or pressure is not observed because of bearing lubrication design.
Pump motor lubrication is observed in lieu of pump lubricant level or pressure.
5.
Flow rate will be measured by measuring increase in day tank level versus time when the transfer pumps are in operation.
6.
Neither pump nor notor lubricant level, pressure, or bearing temperatures can be observed since the pump and motor contain sealed bearings such that they are completely immersed in the fluid being pumped.
Bearing temperature measurement is not required (IWP-4310).
7.
Neither pump nor motor lubricant level, pressure, or bearing temperatures can be observed since the pump and motor contain sealed bearings. Bearing temperature moasurement is not required (IWP-4310).
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1 Pnd Intervet ist Prearne vol. I eevision 01 PUMP RELIEF REQUEST RP-1 5
PUMPS:
All pumps except the Service Water and DG Puel Oil Transfer.
CLASS:
2 and 3 TEST REQUIREMENTStIWp-3000 requires a bearing temperature measurement at least once a year.
BASIS FOR RELIEFt The once-a-year temperature measurement will not provide significant information about pump conditions.
Industry experience has shown that bearing temperature changes caused by degrading bearings occur only after major degradation-has occurred at the pump.
Prior to this, the vibration measurement would provide the necessary information to warn the operator of an impending malfunction.
The long running time required to achieve temperatt*n stability could result in increased maintenance and repair.
Deletion of this measurement will not have significant effect on evaluating: pump test results since other required test parameters are being measured..
ALTERNATE TESTING Pump differential pressure, flow, and vibration (as applicable) will be used to monitor pump performance.
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sv4 Interval IST Program vot. I tevision 01 PUMP RELIEF REQUEST RP-2 SYSTEM:
Service Water PUMPt P3-1, P3-2, P3-3 CLASS:
3 FUNCTION:
Provide Cooling Water to Safety-Related Equipment.
TEST REQUIREMENTStIWP-3100-2 specifies acceptable, alert, and required action ranges for pump head versus flow rate testing.
BASIS FOR RELIEF: Due to climatic conditions the service water system experiences a wide variation in water temperature.
The syctem flow instrumentation is not designed to compensate for temperature variations.
Because of the variation of water temperature, the use of the Code required acceptable, alert, and required action ranges of Table IWP-3100-2 could result in unnecessary pump maintenance and repair.
Alert and re@ ired action levels will be defined as the function of differential pressure data points with Ranges For Test Parameters, Table 5.2-2b, ASME OM CODE-1990.
ASME OM 1990 Code limits-are more restrictive than-code limits of 1986,Section XI, IWP 3100-2.
Table 5.2-2b has no required alert level for high differential pressure.
These higher values reflect a general consensus that test failures resulting from higher reference value are hydraulic measurements caused by instrument fluctuations.
Pump hydraulic performance is not expected to improve hence high alert or high re wired action levels are ineffectual in predicting pump degradation.
However the high required action level is given to ensure instrumentation problems will be resolved.
Lower alert level and low required action are more conservative than 1986 ASME Code,Section XI, hence this will ensure a more conservative acceptance criteria preventing any degradation of overall pump performance from being masked.
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l 2rd Intervat 15f Progree vol, i tevision 01 4
ALTERNATE TFSTING Alert levels and required action levels shall be defined per ASME OM-1990 Code, Section ISTB 5.2 and Table ISTB 5.2-2b, Ranges For Test Parameters.
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2nd Inte, vet f$f Program vol. I tevision 01 PUMP RELIEF REQUEST RP-3 SYSTEM:
Service Water PUMP:
P3-1, P3-2, P3-3 CLASS:
3 FUNCTION:
Provide cooling water to safety-related equipment.
TEST REQUIREMENT: IWP-4500 specifies measuring displacement vibration amplitude at a pump bearing housing or its structural support, provided the pump is not separated from its support by a resilient mounting.
BASIS FOR RELIEF:
These pumps are submerged in a pit, being vertically mounted, wet pit, turbine-type, centrifugal pumps.
They are inaccessible for measuring vibration amplitude at the pump bearing.
Vibration monitoring is required by measurement of a specific displacement parameter for each pump in the program as defined per ASME, 1986 Edition,Section XI.
The industry consensus among manufacturers of vibration monitoring equipment is that vibration velocity, rather than displacement, is a more useful indicator for evaluating degradation in pumps whose speed exceeds 600 rpm.
Thesa pumps operate at approximately 1200 rpm. Additionally, the ASME OM-1990 Code recognizes thht for this type of pump, vibration measurements taken at the upper motor bearing housing provide the best data.
Such measurements shall be taken in-three orthogonal directions, one of which is parallel to the shaft.
ALTERNATE TESTING:The vibration velocity shall be evaluated at the upper motor bearing housing.
Alert levels and required action-levels shall be defined per ASME OM-1990 Code, Section ISTB 4.6.4(b) and Table l
l ISTB 5.2-2(a), Ranges for Test Parameters.
These test parameters are more conservative than ASME 1986 Code, hence an acceptable level of l
quality and safety is still demonstrated.
L II-1-6 4
p-2rd intervel IST Program vet. I tevision 01 PUMP RELIEF REQUEST RP-4 SYSTEM:
Service Water PUMP:
P3-1, P3-2, P3-3 CLASS:
3 FUNCTION:
Provide cooling water to safety-related equipment.
TEST REQUIREMENT: IWP-3100 requires that each measured test quantity be compared to the reference value of the same quantity.
Any deviations determined shall be compared to the limits given in Table IWP-3100-2.
BASIS FOR RELIEF: This system does not have installed pump test lines and system operating conditions will not allow adjusting system resistance without-signiffcant impact on plant operations.
These are variable resistance systems that are in continuous operation during all modes of plant operation.
Depending on plant operating conditions and climatic conditions, the cooling requirements range from minimum cooling loads to 100 percent with many of the loads automatically placed in operation in response to Aocal temperature requirements.
Because of these normal operating requirements, it is not possible to specify a reference test flow path or flow rate that can be repeated for each test.
ALTERNATE TESTING: Pump performance curves, giving reference values for vibration and differential pressure as functions of flow, have been established between 6000 gpm ana 10500 gpm.
These ranges reflect normal and accident conditions.
Measurements of vibration and differential pressure at six flow data points were obtained for each pump, then plotted to compile the pump performance reference value curves.
.Then the parameter alert levels and required action levels as defined per Pump Relief Requese. RP-2 and Relief Request RP-3 were superimposed.
These curves serve as the basis for required action to ensure pump degradation is identified.
During pump testing the flow shall be established within the domain of the reference curve, then vibration and differential pressure shall be measured'and recorded.. Pump performance will be considered II-1-7
2nd Interval Itt Program vol. I tevision 01 acceptable if parameter values fall within the regions bounded by the defined alert end action level curves, rather than a specific value.
When the demand for service water is low, actual test flow may be increased.
In the event that plant conditions do not allow increasing service water 1.1.owrates above 6000 gpm, then pump performance shall be evaluated against the manufacturer's pump curve, based upon ASME OM-1990 Code, Table 5.2-2(b), Ranges for Test Parameters. Flow rate measurements in the 6000 to 10500 gpm range have validated the manufacturer's pump curves in that range. It is therefore expected the nunufacture's pump curves would be valid at lower flow rates.
Vibration shall be evaluated using the lowest flow data point on the vibration velocity reference curve described above.
These curves will serve as the basis for alert and required-actions to ensure pump degradation is identified.
II-1-8 I
2rd Interval ist Program vol. I Revision 01 PUMP RELIEF REQUEST RP-5 SYSTEM Diesel Fuel 011 Transfer PUMPS P195-1, P195-2 CLASS 3
FUNCTION:
Transfer diesel fuel cil from the Emergency Diesel Generator (EDG) Fuel Oil Storage Tanks to the EDG Day tanks.
TEST REQUIREMENT: Measure nump test inlet pressure, differential pressure and flow rate in accordance with the
~
requirements of IWP-3100 and pump test duration requirements of IWP-3500.
BASIS FOR RELIEF: The diesel fuel oil transfer pump. discharge plenum is bolted to the manhole cover on top of the EDG Fuel Storage Tank, being submerged inside the tank.
These pumps are low flow, rated at 10 gpm. They automatically start on low EDG Day Tank level af seven feet, approximately 5050 gallons, then automatically shut off at seven and one-half feet, this corresponds to approximately 250 gallons pumped.
This safety feature maintains a minimum level as required per Technical Specification 3.8.1.
An EDG Fuel Oil Storage Tank has a capacity of approximately 40,000 gallons.
The EDG Day Tanks have a capacity of-6000 gallons.
EDG Day tank can be cross connected to each other, this allows one EDG transfer pump to serve both diesels.
Each EDG Day tank has the capability of emergency fill from the 100,000 gallon fuel oil storage tank.
EDG fuel design flow is 4.5 gpm, therefore each day tank can last approximately 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />.
This time period is sufficient to allow offsite fuel oil delivery service directly to the day tanks.
None of the pumps have installed-instrumentation to measure either flow or discharge pressure.
ressurecannotbevaried,efbieflow there Dischar e so ation valves.
The only poss are no measurement.is by measuring EDG Day Tank volume over time.
Error in measuring this volume is dependent on fuel oil temperature and a limited change in level indication because the EDG Day II-1-9
'tr l
2nd Interval ll! Program vol. !
Revision 01 Tank has an large upper circular section.
Flow rate is dependent upon EDG ruel Oil Storage Tank level and fuel oil viscosity which varies with environmental temperature conditions.
There are i
no recirculation nor designed drainage pathway.
1 To dato no maintenance has been required for these canned rotor pumps.
Pumps have successfully started and delivered fuel oil upon demand.
The latest flow test indicates pump design flowrates are being met.
To' perform section XI testing would require extensive plant modifications.
Performance of ASME Section XI testing requirements without major modification to plant structure is impractical.
ALTERNATE TESTING Pump flow functional test is performed each month as required per Technical Specification 4.8.1.1.2.
Pumps are observed to start with a corresponding increans level in the EDG Day Tank.
Pump flow rate tests are performed each refueling.
A predetermined oil level abcVe the transfer pump will be set. Flow rate is cotained by measuring a change in EDG Day Tunk level over time.
A EDG Day Tank level change of approximately 150 gallons or more shall be timed to determine flow rate.
There are no means of obtaining differential pressure, nor the ability P.o throttle flow.
Flow rate will be calculated from a known increasu in EDG Day Tank level.
Pump suction pressure shall be precet by fuel oil level adjustment.
Pump discharge is consistent since there are no throttle valves.
Based upon these conditions pump flow rates should be repeatable and capable of predicting pump degradation.
A low required action-range of less than C gpm will be used in lieu Table 3100-2.
Based upon engineering judgment the developed range in lieu of Table 3100-2 is required because of error from fuel temperature viscosities, error in EDG Fuel 011 Storage Tank level measurement, and error in EDG Day Tank measurement.
This range will ensure EDG transfer pumps do not degrade below required design system flow regatrements.
Pump flow rates will be trended for 09 gradation.
l-II-1-10 l
1
. ~.. -
. - ~.
.. -... ~. ~. -.,.
2rd Intervat ist Program Voi. I tevision 01 i
No alert levels shall be specified sir.ca tnis is a refueling test, hence required action will be preformed if pump flow rate is determined to bc outside the acceptabla range.
1 Periodically, the EDG Fuel 011 Storage Tank are drained, cleaned, and filled with fresh oil.
The EDG Day Tank are also drained, cleaned and inspected.
At those times a long term pump duration test is possibla.
The transfer pump will be required to consecutively pump 1000 gallons of fuel from the Emergency Diesel Generator Fuel Oil Storage Tank to the EDG Day Tank.
Flow rate will be measured and evaluated for degradation.
i 3
i 5
+
II-1-ll i:
l;
i 2nd Intervat logram vol. I tevisica 01 PUMP RELIEF REQUEST RP-6 SYSTEMr Dias.el Generator Fuel Oil Transfer PUMP 1 P195-1, P195-2 CLASS 3
FUNCTION:
Transfot diesel fuel oil from the Emergency Diasel Generator (ED3) Fuel oil Storage tanks to the EDG Day Tank.
TEST REQUIRIMENT: Hondu,re pump vibration in accordance with IWP-3100.
BASIS FOR RELIEFt The Diesel fuel Oil Transfer Pumps are submersible motor driven, canned, centrifugal pumps.
Both the pump and motor are submersed in f
an underground tank and are not accessible for vibt.ition measurements.
ALTERNATE TESTING Pump flow rate will be monitored and trended as defined per pump relief request RP-5.
4 II 1-12
2nd Interval ist progres vol. I Revision 01 PUMP RELIEF REQUEST RP-7 PUMPS:
All Pumps CLASS 2 and 3 TEST REQUIREMENTS ASME 1986 Edition Section XI, Table IWP-3100-2 requires measuremen,t of displacement for the vibration test quantities.
T BASIS FOR 52LIEFt Vibration is determined by measurement of a spscific displacement parameter for each pump in t.h6 program as defined per ASME, 1986 Edition, Sec*. en XI.
Above 600 rpm, displacement has been da'cermined as a poor indicator of pump performance.
All inservice test program pumps are centrifugal: type with motor speed greater than 600 rpms.
Presently in some pumps displacement readings are not repeatable.
Therefore for vibration the velocity quantities shall be evaluated in lieu of displacement quantities.
ASME OM-1990 Code Section ISTB 4.6.4 and ISTB Table 5.2-2a regulres more than one vibration point to monitor, hence more. test data is required.
Therefore an acceptable level of quality and safety _is still.present.
ALTERNATE TESTING:If an engineering evaluation indicates that velocity is a more appropriate indicator for
. pump degradation, then velocity shall be used in_
lieu of displacement.
.These velocity quantities shall meet the alert' levels and required action levels as dafined per ASME OM-1990 Code, Section ISTB 4.6.4 and Table ISTB 5.2-2a, Ranges For Test Parameters.
II-1-13
2id Interval !!f Program Vol. I tevision 01 PLMP filf 1 ABLE DAvil M 15! WUCLEAR Pt%(R PLAh!
DoctM(b1 t!Vil104: 1 PUMP LIST MEAtuafD PARAmtitR$
3 tutti : Dlf. :
- Lutt, t
SYSTEM PtMP P&lD COORD.: CLA$$8 REllff SPl[D Pit $$. : PRit$.
FLOW VilaAflow : ftMP.
a 8E2JElf W
Pl s 0 :
V 1
L AUMEfR
................,s..........
..........................s...
SERVICE WATER P3 1 M 041A G2 3
RP 2,3,4 (1) 0(2) 0 0
0 (3)
(4) 0 P3 2 M 041A G5 (1) 0(2) 0 0
0 (3)
(4) 0 P3 3 M 041A G9 (1)
O(2) 0 0
0 (3)
(4) 0 0
0 AuxlLIARY P14 1 M 0060 G9 3 RP 1 0
0 0
0 0
0 0
WATER P14 2 M 002 J6 0
0 0
0 0
0 MArtuP P371 M-031C tB 3 SP 1 (1) 0 0
0 0
0 0
0 0
P37 2 M 031C M9 (1) 0 0
0 1
0 (7) 0 60Ric Atl0 P38 1 M 045 J4 3 RP 1,7 (1) 0(2) 0 0
0 (7) 0 1RAktFIR P38 2 M 045 K3 (1)
O(2) 0 0
0 0
DECAT MEAT P42-1 M 0338 G9 2 RP 1 (t) 0 0
0 0
0 0
0 0
REMOVAk P42 2 f* 033C F8 (1) 0 0
0 0
0 COMPOWEssi P43 1 M 036A 04 3 R F>.1 (1) 0 0
0 0
0 0
0 0
COOLING WATER P43 2 M-036%
J4 (1) 0 0
0 P43 3 M 036A G4 (1) 0 0
0 3
0 0
0 0
CONTLINMENT P56 1 M 034 0 10 2 RP 1 (1) 0 0
0 0
0 0
$ PRAY P56 2 M 034 B 10 (1) 0 0
0 0
0 0
0 MIGH PRESSURE P54 1 M-033A M7 2 RP 1 (1) 0 0
0 0
0 0
thJECilosa 438 2 M 033A E7 (1) 0 0
0 0
0 0
0(5)
(6)
DG FUEL CIL P195 1 M 017A C4 3 RP 5,6 (1) 0 0(5)
(6)
TRAWSFER P195 2 M 017A C-7 (1) 0 11 2 1 l
-.. -. - - - - -.. = - ~ ~, ~, -..
... ~..., ~.
I t
h A.
1 2rd Intef vet 111 Program vet, t sevision 01 i
h l
PUMP AND VALVE INSERVICE TESTING PROGRAM TOR i
DAVIS-BESSE NUCLEAR POWER STATION I
'SECTION III t
VALVE IST PROGRAM i
i a
?
k
- i. :
4
/
III c, 2
2rd interval llt Program vol, I tevision 01 III.
VALVE IST PROGRAM III.1 1HTRODUCTION This section p'Jesents the program for inservice testing of valves at the Davis-Besse Nuclear Power Station, in compliance with the requirements of 10 CFR 50.55a.
This program has been prepared to the requirements of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code,Section XI, Subsection INV, 1986 Edition for safety-related valves which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident or in providing overpressure protection.
III.2 Concent The valve test program has been developed to verify the operability of safety-related systems.
The program addresses those valves whose operability and/or position are essential to safety-releted system operation and Section XI valve testing will be performed to verify valve operability.
The program specifies either Section XI or alternate testing, as appropriate, for those valves which perform a safety related function.
Valves have been selected for inclusion in the test program based on a review of all plant systems.
This review identified those systems performing safety-related functions.
Each safety-related system was analyzed to determine which valves are essential to the safety-related operation of the system.
These valves were then investigated to determine whether Section XI testing could be performed during normal operation.
Those valves for which quarterly testing was determined to be inappropriate were analyzed further to determine if cold shutdown testing was possible.
The ASME code allows a delay in testing until cold shutdown for those valves that are not practical to operate during plant operation.
If cold shutdown testing was determined to be possible then justifications for delay of tests to cold shutdown are provided fol'owing the appropriate valve test tables.
Where it is not practical to comply with Code requirements, a review of Attachment 1 to NRC Generic Letter 89-04 has been performed.
If the component can be tested consistent with the positions taken in,
justifications describing the need to perform the preapproved alternate testing are provided following the appropriate valve test tables.
Relief requests describing appropriate alternative testing, III-2
2nd Intervet 181 Program vol. I tevision 01 and justifying exclusion from section XI testing for
-valves which cannot be tested quarterly or during cold shutdown and which are not specifically preapproved by to NRC Generic Letter 89-04 are provided following the appropriate valve test tables.
III.3 Code Interoretations A number of items in Subsection IWV of the Code are subject to interpretation.
The interpretations of a number of general items encountered in preparing the Valve Test Program are provided below III.3.1 Relief Valves The code requires testing of pressure relief valves in accordance with ASME/ ANSI OH 1981.
The relief valves designated for test are only those which perform a system pressure relief function.
Thermal relief valves, whose only function is to protect components or piping from thermal expansion
.are not considered to be safety-related and are.not addressed in the program.
Where a relief valve performs both a system and a thermal relief function it has been included in the program. Thermal relief valves which also perform a containment isolation function are included in the program for Appendix J, Type C, testing only.
III.3.;
E.assive Valven The Code excludes valves used only for operating convenience and/or maintenance from. testing.
Also, the Code defines passive valves but specifies no operability test requirements.
This program defines as passive any manual or power operated valve that does not have to change position, but that does perform either a containment isolation or pressure isolation function.
Passive containmant and. pressure isolation valves have been included for seat leak testing only.
All valves not designated as passive are considered to be active valves.
-III.3.3 System Test Valves Valves included in a system to align the.
system for testing are included for section XI testing if their position is critical-to safety-related system. operation.
The s
-system analysis postulates that the system III L
2rd Interval 181 Program vol. l 8evition 01 is aligned to a test modo configuration when the actuation signal occurs.
All valve including those used only for testing, s~
.h must respond to the actuation aignal, are included in the test program.
III.3.-
Pressure and ricy control Valves The code excludou valves which perform prescure or flow control functions.
This program excludes them unless they also perform a system safety-related response function, such as automatic closure on system actuation.
The program addresses these valves by specifying testing of the safety-related function and excluding the normal pressure or flow control functions.
III.3.5 Automatic Power ODerated Valves Power-operated valves which receive an automatic signal on system actuation are included in the program.
These valves may be included as passive valves, if appropriate.
III.3.6 Remote Power Operated Valves The program includes power operated valves activated by remote switches if they are required to change position to align a system for safety-related operation, related system operation, terminate safetyinment isolation capability or provide conta for mitigating the consequences of an accident.
III.3.7 Normal yg. Safetv-Related System Operation valves in systems which have both normal and safety-related operating modes are included in the program, only if they perform a safety-related function.
Valves which provide normal system operation control and whose position has no effect on safety-related operation are excluded from the program.
III.3.8 Dual-Fungtion Valves Valves which provide more than one function are tested for their safety-related function only.
Valves with multiple safety-related functions are tested for each function.
An III-4
.re in.ervei m troer vei. I te.tston 00 example is the Pilot Operated Relief Valve, (PORV) that open and close in response to either an automatic or remote manual signal, and also act as relief valves.
Both are cafety-rcLated functions, and testing for both functions is included in the program.
III.3.9 Simple Check Valven Simple check valves are tested to verify operability in the safety-related flow directionds).
Normally closed simple check valves which must open are tested to verify full opening with forward flow.
Normally open simple check valves which must close on loss of flow are tested to verify closure on loss of forward flow.
Normally closed simple check valves which remain closed on system actuations are tested to verify that the valves are closed.- Normally open simple check valves which are required to remain open are tested to verify full-flow in the forward direction.
Simple check valves which are required to cycle open and closed are tested to verify fall opening with forward flow and closure on loss of forward flow.
This interpretation is consistent with Items 1 and 3 of Attachment 1 to NRC Generic Letter 09-04.
A check valve's full stroke open position may be verified by passing the design flow rate through the valve.
A check valve reverse flow is tested in a manner that proves the disk travels to the seat promptly on cessation or reversal of flow.
Full forward flow or reverse flow can be verified by showing for a measured flow or other appropriate system parameters through the valve is such that the valve could only be fully open or closed.
Full forward flow can be verified by using a mechanical exerciser which can be observed to move through a full utroke.
Reverse flow can be verified by using a mechanical exerciser which can be observed to move through a partial movement or the disk travel to the valve seat.
Full forward flow or reverse can be verified by partial disassembly of the valve and manually moving the disk through a full stroke.
Following partial disassembly test III-5
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ - _ _ _ ~
trd Interval 181 Progree vol. I a,vis6on 01 a full or partial forward flow verification test will occur.
III.3.10 Manual Steo Check Valves Manual stop check valves are tested to verify operability in the safety-related flow direction (s).
If the manual operator is withdrawn, the valve operates as a simple check in the forward flow direction and is tested as a simple check.
Reverse flow closure is verified as a simple chock, if possible, or by use of the manual operator.
III.3.11 Testable Check Valves check valves equipped with a manual exerciser will be tested as a simple check or by exercising ucing the manual exercising device.
Check valves equipped with a power operator installed for the solo purpose of exercising the valve to verify operability will be tested as a simple check or by use of the power operator.
III.3.12 Power Or3 rated Ston Che.gk Valves power operated stop check valve testing is based on the function of the operator.
If the valve operator is always withdrcwn and the valve operates as a simple check valve, except during maintenance, the valve is tested as a simple check.
If the operator is normally withdrawn such that-the valve operates as a simpia check in the forward direction and the operator provides positive closure, sit is tested as a simple check in the forward direction and exercised closed using the operator.
In addition to exercising, the operator will be timed and failed as appropriate.
III.3.13 Pumo Discharae ' Check ' Valves As a minimt'in, pump discharge-check valves will be forward flow exercised..In addition, reverse flow closure will be verified when failure of the valve to close could result in a substantial reduction of system flow, such a potential exists with
. parallel pumps connected to common suction and discharge headers.
If the check valve
-on the idle pump fails to close a III-6
7,-.
(9 2nd Interval Ist Program vol. I tevision 01 significant amount of system flow could be diverted back through the idle pump to the suction header.
III.3.14 Chggk Valve Full / Partial Stroke In so.mo cases, full design flow through a check valve requires less than full mechanical valve movement.
As used in this program, the ter-full-stroke refers to either the ability of the valve to pass-design flow rate or full mechanical stroking.
Forward flow full-stroke operability testing will be by any method that verifies the valve capable of passing design flow or full mechanical stroking.
Any test that verifies less than full design flow capability or full mechanical stroking is considered as a partial-stroke test.
This interpretation is consistent with item 1 of Attachment 1 to NRC Generic Letter 89-04.
III.3.15 Cateoorv AC (Containment Isolation Valve)
Leak Testing All valves specified for Appendix J, Type C, local leak rate testing are included in the Program as Category A and C valves.
Appendix J, Type C, local leak rate testing fulfills the intent of Articles IhV-3420 through IWV-3425 and will be performed in lieu of Section XI testing.- Analysis of leakage rates and corrective action requirements of INV-3426 and IWV-3427(a) will be performed.
Compliance to IWV-3427(b is impractical and not required for Appendi)x J testing as established in Generic Letter:89-04, Attachment 1.
The Program reflects the current list of valves receiving Appendix;J, Type C, testing.
Any future change to that-list will be incorporated into the Program.
This interpretation has been preapproved by Item
'10 of Attachment 1 to NRC Generic Letter 89-04.
III.3.16 Catecorv AC'(Pressure Isolation) Valve Operability Testino Reactor coolant. system pressere isolation valves will be demonstrated opereble in:
accordance with plant Technical Specifications 4.4.6.2.2 it lieu of the III-7
2nd intervet 15T Program voi. I tevision 00 requirements of IWV-3420 as follows:
Each reactor coolant system pressure isolation valve specified in Table 3.4-2 shall be demonstrated operable pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated operable by verifying leakage to be within the allowable leakage criteria of 1.0 gal / min with an upper limit of the maximum-allowable leakage in Table 3.4-2; and the measured leak rate for a given test cannot reduce the difference between the results of the previous test and the maximum allowable leakage specified in Table 3.4.2 by more than 50 percent:
a.
After each refueling outage.
b.
Whenever the plant has oeen 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, and c.
Prior to returning tha valve to service following maintenance, repair or replacement work on the valve.
Per the Reactor Safety Study, WASH 1400 Event V Considerations, CF30, CF31, DH76, and DH77 will be leak tested prior to Reactor Startup if forward flow through these valves was identified.
Any change to the list of pressure isolation valves referred to in Technical Spccificat 'ns will automatically be incorporated into tne program.
This interpretation is consistent with Item 4 of Attachment. 1 to NRC Generic Letter 89-04.
III.3.17 Locked Valves This program classifies as locked valves only those which are physically restrained from movement (i.e., chain and padlock), or sealed (i.e., wire and seal) in position at the local hand switch and/or hand wheel.
Remote hand indicator switches, located in the control room, can cycle these locked valves under administrative controls.
III.3.18 Valve position Indicator Verification III-8
2rt interval 15i Program vol. I tevision 01 IWV-3300 requires that all valves with remote position indicators shall be observed at least once every two years to verify that valve operation is accurately indicated.
It is the intent of this program that such verification will be performed on all valves which have remote position indicators.
III.3.19 Valve Stroke Direction Valves will be stroked and timed in their safety-related directions (s).
For example, a motor-operated valve whose safety-related operation is to close on system actuation will be exercised and timed closed.
If the valve must operate in both directions for safety-related system operations, it will be exercised and timed in both directions.
III.3.20 Valve Fail-Safe Directions Valves will be tested to verify operability of tne fail-safe operator in the direction that the valve travels to perform its safety-related fun: tion.
Valves equipped with fail-safe operators for convenience only and which uo not have to change position on loss of power for adequate safety-related operation will not be fail-safe tested.
III.3.21 Temperature Interlocked Valves Valves which open and close in response to local temperature controls will not be tested unless they are-interlocked to system i
operation.
For example, temperature interlocked valves on local area heat exchangers will not be tested unless they are interlocked to go open/ closed on system actuation for safety-related operation.
III.3.22 Containment Entry Entry into the containment structule during normal operation or cold shutdown is strictly regulated by plant operating procedures.
Because of environmental and As-Low-As-Reasonably-Achievable (ALARA) considerations, entry is made only for tasks that are absolutely necessary for plant operation, and dtration inside the containment is limited to as-short-as-possible.
Because of this, valve testing III-9
2nd Interval 151 Program vot. I tevision 01 that would require entry into containment to perform special testing is limited to only those absolutely essential for safe plant operation and all others are delayed until refueling.
III.3.23 Puro leal Coolina, and Lubrication Valvqn Valves in pump seal water, cooling water and lubrication lines which are an integral part of the pump design and which are effectively verified operable during pump operation or testing are not addressed in the program.
Acceptable pump operation or testing verifies adequate operability of pump seal, cooling and lubrication path valves.
III.3.24 Pressurizer Power Operated Relief Valve (PORV) Block Valve The pressurizer PORV block valves will be operability tested quarterly to code Requirements.
III.3.25 Racid-Actino Valve Stroke Timina Power operatsd valves with normal stroke times of two seconds or less are defined as Rapid-Acting valves.
These valves will have a maximum limiting value of full-stroke time of two seconds.
Any measured full-stroke time of two seconds or less verifies operability.
If the measured valve full-stroke time exceeds two seconds the valve is declared inoperable and corrective action is taken in accordance with IWV-3417(b).
This interpretation has been preapproved by Item 6 of Attachment 1 to NRC Generic Letter 89-04.
III.3.26 Power Operated Valve Limitina Values of Full-Stroke Time For power operated valves the Code requires that (a) Limiting values of full-stroke times shall be specified (IWV-3413(a)), (b)
Valve stroke times'shall be measured to (at least) the nearest second (IWV-3413(b)) and (c) If the stroke time increases by 50% or more from the previous test, then the test frequency shall be increased to once each-month until corrective action is taken (IWV-3417(a)).
Paragraph IWV-3417 (b) specifies corrective actions that must be taken. With III-10 1
I' 2nd Interval 157 Progen vol. I Revision 01 reference to (c) above, measuring changes in stroke times from a reference value as opposed to measuring changes from the previous test is an acceptable alternative.
(
Reference:
NRC Generic Letter No. 89-04 April 3,
1989).
The purpose of limiting values of full-stroke time is to establish a value for taking action on a degraded valve before the valve reaches the point where there is a high probability of valve failure due to valve degradation.
The limiting value of full-stroke time for each valve is based on a reference value of full-stroke time for each valve when it is known to be in good mechanical condition and operating acceptable.
The reference value can be e single measurement or, better still, the average of a number of measurements.
The limiting value shall be a reasonable deviation from the reference value.
Neither the Code nor the NRC have provided any specific requirements or guidelines for establishing an appropriate deviatl+'i, except that the limiting value of full-stroke time be a reasonable value and based on each valve size, and the actuator type.
Toledo Edison is adopting component oriented maximum valve stroke times for these valves based upon the criteria below; a.
Motor-operated valves will be limited to 1.5 times baseline.
b.
Air-operated valves with a stroke time baseline less than 10 seconds will be limited to 3.0 times baseline.
c.
Air-operated valves with a ten second or-greater baseline will be limited to twice baseline.
After the limiting values of stroke times have been established they will be compared to Technical Specifications and Updated Safety Analysis Report (USAR) values.
Where the limiting values are less than those of Technical Specifications, they will be used.
If Technical Specification or USAR maximums are less than the calculated values, the Technical Specification or USAR maximum will III-11 l
l
s 2rd Interval 157 Program Voi, j Revision 01 be used.
In no case will the limiting value of full-stroke time be greater than Technical Specification or USAR stroke times.
This interpretation is consistent with Item 5 of Attachment 1 to NRC Generic Letter 89-04.
III.3.27 Submittal of Limitino Values of Stroke TIER The NRC requires that limiting values of power operated valve-stroke times be included in the program submittal.
Because of repair, maintenance,_ modification, etc.
limiting values of stroke time will change.
If limiting values are-included in the program and the program is approved by the NRC, any subsequent chtnge to limiting stroke times would require a program revision.
In order to avoid unnecessary-program revision for Code allowed changes to limiting values of stroke time, a listing of limiting values of stroke times has been prepared. - If-required-due to repair or replacement, then.new reference value shall be determined.
New reference values shall be documentation in the Pump and Valve Basis Document.
III.3.28 Pump Minimum Flow Line Block Valves Stroke-testing of pump minimum flow line block valves depends on valve usage and configuration.
Normally open motor operated line block valves ~that are not required to close (i.e.,
remain open-for all modes of operation) are passive and are excluded from testing.- Normally open individual minimum flow line power operated block valves which are normallyselcaed and open on pump start or normally open and h_e required to close
~ hall be stroke tested quarterly.
If the s
individual minimum flow lines tie into a single discharge line with a normally open power-operated valve, such that failure of the valve in the closed position could stop minimum flow from'all pumps, valve stroke testing will be delayed.
'III.3.29 Check Valve Disassembly Item 2 of Attachment 1-to NRC Generic-Letter 89-04 preapproves the use of valve disassembly and visual inspection as an alternative for check valves where it has III-12 l
b
4 2nd Interval Itf Progrern Vol.1 eevision el been determined that testing is impractical.
A sampling plan is used for groups of check valves which are identical (i.e.in same manufacturer, type, size, etc.)
construction and for which the system operating environment is the same.
The group size has been limited to a maximum of four valves per group, such that each valve shall be disassembled at least once every six years.
The sampling plan selects-one valve from each group for disassembly during each refueling outage.
If the selected valve passes inspection, a second valve is selected for disassembly at the next refueling, etc. until the group has.been completed or until such time that sufficient inspections have been performed to-justify an alternate sampling plan.
For-those cases where disassembly indicates that there are no valve problems, a new relief request may
-?
be prepared to perform less frequent inspections.
Failure of the selected valve to pass inspection will initiate additional valve disassembly as specified by the appropriate Program relief request.
'The samplezdisassembly and inspection program includes verification that the valve is capable of full-stroke operation and visual. inspection for worn or corroded parts.
For valves with hinge pins in the valve body, full-stroke operability is verified by-manually exercising the valve For valves with through L complete cycle.
hinge pins in the removable bonnet, such that the valve internals are removed-from direct
-the valve body during disassembly,ility.by verification =of full-stroke operab manually exercising is not possible.
For these valves, full-stroke operability determination will be.by visual inspection of-valve internals for evidence of wear, binding,-etc., and by stringent valve-reassembly. procedures. At a minimum a partial-forward flow test shall occur af ter reassembly.
III.3.30 Pumo Discharae Header Train Isolation Block Valves
.Where safety-related pumps discharge to a common-header with header power operated III-13 E
l-
2nd interval 151 Program Vol. I tevision 01 block valves, valve testing depends on valve safety-related function and system operating modes.
If the valves are relied upon to provide train separation (i.e., close one or more valves to establish-independent pump flow paths) the valves are stroke tested.
If the valves are for alignment purposes only (i.e., substituting an installed spare
- pump :.n place of a normally aligned pump) the valves are for operating convenience and have been excluded from the program. HIf the-valves require testing, an analysis was performed to determine if stroking would place the plant in an degraded condition (i.e.,
isolation of ECCS required flow-path).
If a degraded condition or extended testing time could exceed the Technical Specifications Action Statement, then testing would be delayed. These specific conditions are identified per Cold Shutdown Justifications or Relief Requests.
III.3.31 Technical Specification /Unanalyzed Condition Analysis Iach' stroke tested valve has been analyzed.
to determine if stroking the valve would violate plant Technical Specification requirements or place the plant in an degraded condition.
For example, if Technical Specifications requires that two independent flow paths be available during normal operatinn-and testing could-exceed the Technical Specification Action Statement then testing would be delayed. In addition, if failure of"a-valve in a nonconservative
. position during testLwould place-the plant in an unanalyzed configuration-(i.e., reduce ECCS flow to below minimum required flow rates) then. testing will be delayed.
~III.3.32 Valve Test Data Analysis - Limitino Value of Stroke Time The. valve stroke time test data will be reviewed immediately,upon completion of test to determine if the-individual valve
-limiting value of stroke time has been exceeded.
If the valve stroke time data exceeds the limiting value, the effect on-
-Technical Specification-operability will be assessed:immediately and actions taken as
-appropriate.
III-14
2nd InteNat l$f Program Vol. I tevision 01
'III.3.33 Valve Inocerability - ELfect on System QRgrpbility There are a number of valves in the test program whose failure to pass section XI test requirements may not affect safety-related system operability.
For example, a normally closed power operated pump test line valve which fails in the closed position would not prevent the system from performing its safety-related operating function (s).
When a valve fails to passSection XI test criteria an analysis will be performed.to determine what offect valve inoperability has on system operability.
If system operability is affected, the plant Technical Specificaulons provide the system operability requirements.
This analysis will be performed without delay upon valve failure and, if-system operability is affected then the action statement to the applicable LCO-shall be met. If valve failure does not affect safety-related system operability the valve will be-declared inoperable and valve retest and/or appropriate corrective action initiated.
III.3.34 Valve Retests to Verifv Ooerability If a valve failed.to passSection XI test criteria and the valve has been declared inoperable a valve retest may be performed.
If the valve passes the retest it will be declared operable.
If the valve fails the retest then corrective action shall occur.or the applicable action statements of.the Technical Specification or the applicable ASME Section XI will be met.
III.3.35 NRC Infe mation Notices and Bulletins NRC issued Information Notices and Bulletins relating to valves were reviewed and incorporated, as applicable.
III.4 Cold Shutdown Justification The ? referenced code (dition allows delay of testing to cold shutdown-when testing quarterly during normal operation is not practical.
Even though a relief request is not necessary, the NRC requests that a III-15
2rc Interval IST Program vol. I nevision 01 justification for delay of testing to cold shutdown condition be provided.
This program rovides a cold shutdown justification for each valve where testing is delayed to cold shutdown.
III.5 Generic Letter 89-04 Justifications NRC Generic Letter 89-04 provides approval of several ASME Code alternative test requirements providing the Pump and Valve test programs are consistent with the positions taken in Attachment 1 of the Generic Letter, The Generic Letter states that these preapproved alternatives to the code should be identified for each applicable valve in the valve test program.
This program identifies these valves by referencing Generic Letter 89-04 justifications.
These justifications provide the basis for the need to use the Generic Letter alternative testing and reference the applicable Generic Letter preapproved alternative.
III.6 Relief Reauests Where Code specified test requirements cannot be met or testing must be delayed to refueling outages the NRC requires that a relief request be provided.
This program provides a relief request for each valve which cannot be tested in compliance with Code test requirement-and/or testing is delayed to refueling outages.
III.7 Valve Test Records A system of records of valve inservice testing will be maintained at the site in accordance with IWV-6000 of Section XI.
III-16
I.
2nt* Interval I$f Progrwa Vol. I Revision 01
.III.8 GENERAL RELIEF REQUESTS FOR VALVES This sect' ion requests relief from specific requirements
'of Section XI found to be imp'Jactical for this site.
Since they are general in nature and pertain to a number of components, this section requests general relief as presented below:
General. Relief Request:
VG-1 Components:
Valves tested at cold shutdown Category:
A, B, C Code Requirements: IWV-3417 states that when corrective action is recuired as a result of tests mada during cold shutdown, the condition shall be corrected before startup.
A retese showint; acceptable operation shall be run following any required corrective action before the valve is returned to service.
~ Basis for Relief:
The plant technical specifications provide the system ~ operability requirements for plant startup and mode changes.
The failure of a valve to passSection XI test requirements may not affect system operability or prevent the system from performing its safety-related function (s).
For example, failure of a normally closed power operated valve in a pump test line to open does not affect system operability and does not prever.t the system from. performing its safety-related function (s).
Alternate Testing: When a valve failsSection XI test criteria during cold shutdown testing an analysis-will be performed to determine if the test failure results in system inoperability or would prevent the system from performing its safety-related function (s) with the failure present.
If the analysis _ determines a valve test failure does not cause system to be inoperable then the plant may startup providing corrective action is being-or will be performed on the valve.
A retest showing acceptable operation shall be run following any required corrective action before the valve is returned to service.
c III-17 l
2rd Interva.
..f Program Vot. I tevision 01 General Relief Request:
VG-2 Component:
Pressure Isolation Valves Code Requirements: Section XI Category A valves will be leak tested to the requirements of IRV-3420.
Category:
A, AC Basis for Relief:
Technical Specification Section 3.4.6.2 defines the limiting condition for operation and Section 4.4.6.2.2 defines the surveillance requirements for pressure isolation valves as follows:
"Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-2 shall be individually demonstrated operable by verifying leakage testing (or equivalent) to be within its limit' prior to entering Mode 2:
a.
After each refueling outage-
~b.
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, and c.
Prior to returning the valve to service following maintenance,-repair, or replacement work on the valve."
Leakage rates are defined.per Table 3.4-2, Notes.
Alternate Testing: The as defined surveillance' testing will be performed-to meet Technical Specifications.
If leakage is greater >than described above then repair or replacement shall be performed to restore the component to an acceptable condition.
This action is equivalent to IWV-3420 requirem.9nts.- To address the Reactor Safety Study, WASH 1400 Event V Considerations, CF30, CF31, DH76, and DH77 will be leak tested prior tc Reactor Startup when a differential pressure of 100 PSID or less has occurred across any of these check valves.
III-18
?
e 2nd Intervet 157 Program Vol. I Revision 01 Gene: 21 Relief.
VG-3
- Request:
Components.
Valves required to shutdown the reactor to cold shutdown condition.
- Code Requirements: The Scope of ASME,-Section XI, Subsection IWV 1100 provides the rules and requirements for inservice testing to assess operational readiness of certain Class 1, 2,
and 3 valves in light water cooled nuclear power plants, which are required to perform a specific function in shutting down a reactor to the cold shutdown. condition, in mitigating the consequences of an accident or in providing overpressure protection.
- Category:
A,B,C,D ~
Basis for Relief:
Davis-Besse Power Station defines shutting down the reactor per Section 7.4.1 of the USAR as that station condition in which the reactor is 1.0 percent subcritical and the reactor coolant system temperature and pressure are in the normal operating range.
Per Davis-Besse
- Technical Specification this condition is defined as. Mode 3, Hot Standby.
A Cold
' Shutdown condition is not required to shutdown thelreactor.
The licensing basis for safe shutdown is hot standby.-
Alternate Testing: No alternate testing is required.
Present Inservice Testing program is limited to those systems and components to reach a safe shutdown condition. 'This condition is defined as Mode 3, Hot Standby per Section 1.0, Definitions for Technical Specifications. Those systems and components required to reach a Cold Shutdown conditions are addressed in an augmented valve test program.
III-19 i
i?
2nd Interval tst Program vol. I Revision 01 III.9.
VALVE DRAWING LISI ASME Class 1, 2,
and 3 Systems System P&ID No.
Reactor Coolant M-030 A M-040 A M-040 B Core Flood M-033 B M-034 Containment Spray M-034 Decay Heat M-033.A-M-033 B M-033 C M-042 C D G-Air Start M-017 B High_ Pressure Injection M-033 A Makeup.
M-031 A M-031 B M-031 C M-045 OS-002 Main Steam M-003 A M-003 C M-007 A M-007 B Feedwater M-006 D-M-007 B Auxiliary Feedwater M-006 D M-007 B-Service Water M-006 D M-031 C M-041 A
-M-041 B M-041 C ComponentLCooling Water M-036 A M-036 B M-036 C M-040 D Containment Vacuum Relief M-029-B Containment Purge M-029 E Containment-Hydrogen Control M-029 B M-029 D Aux.-Bldg. Radwaste, Fuel Handling and-Access Control-AreaLHVAC M-028 B Nitrogen. Supply M-019 M-036 Demineralized Water M-010 C M-036 A sample M-007 A M-040 A Borated Water M-033 A III-20
2nd Intervet ist Program vol. 1
- evision 01 Instrument Air M-015 A Station Air M-015 D M-034
- Station Drainage M-046 Gaseous Radioactive Waste M-038 B M-038 C Auxiliary Steam-M-003 C III-21
2nd Interval ist Program Vol. 1 Revision 01 III.10 VALVE TEST TABLE NOMENCLATURE The following abbreviations have been used in the Valve Test Tables:
Leaend for Valve Catecorieg Cateaory Descriotion A
Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function.
Valves for which seat leakage in the closed B
position is inconsequential for fulfillment of their function.
Valves which are self-actuating in response to sone C
system characteristic.
Valves which are actuated by an energy source D
capable of only one operations, such as rupture disks or explosive-actuated valves.
AC Valves which are both Category A and C.
BC Valves which are both Category B and C.
Leaend of Valve Tvoe Three Way Angle Valve TW AN BF- -
Butterfly Valve TR Thermal Relief Spring Check Ball Valve SK BL Plug Check Valve PG CK
~
DA Diaphragm Valve RG Regulating Gate Valve RD Rupture Disk GT Vacuum Relief Globe Valve VR GL Manual Testable RL Safety or Pressure Relief Valve-MK Stop Check Valve Check SC Power Operated Needle TK ND Testable Check Leaend of Valve Actuator Tvoq AO Air Operated SA Self Actuating SO Solenoid EM -
Electro-Mech Manual HO Hydraulic MA Motor Operated MO III-22
- t 2nd Interval 15T Program Vol. I nevision 01 Leoend of Valve Positions:
Normal. Fail, or Safety-Related Locked Closed' AI As Is LC Closed LO Locked Open C-Locked Throttled
.open LT 0
O/C -
Open or Closed Leaend for Frecuency of Test Quarterly Q
Refueling R
Per ANSI /ASME OM-1-1981 T
- i 2 Years Cold Shutdown C
Leoend for Valve Testina Recuirements TO-
- Stroke and Time Open TC
- Stroke and Time Closed FO
- Fail Safe Test Open FC
- Fail Safe Test Closed
' SR
- Relief Valves VR
- Vacuum Relief; Valves-LJ
- Leak Test per Appendix J, Type C (Cont e ing.cnt Isolation)
--Leak Test per Section XI (Pressure Isolation)
-LC.
- Leak-Test per both Appendix J, Type C, and Section XI PI
- Remote Position Indicator Verification FF
- Check Valve Forward Flow Closure Verification RF-
-- Check Valve Reverse Flow Closure Verification MK
- Testable Check Valve with Manual Exerciser TK
- Testable Check Valve with Power Operated Exerciser SO-
- Stroke Open Without Timing-SC
- Stroke Closed Without Timing RD
- Rupture Disk PAS. - Passive Valve PQRM'-LPartial-stroke test exercised quarterly.
Valve disassembled during refueling and manual stroke test exercised.
RM' Valve disassembled during refueling and manual-stroke tost exercised.
-PQR - Partial-stroke test: exercised quarterly and full-stroke test exercised-during: refueling.
PQCS - Partial-stroke test exercised quarterly and full-stroke test exercis~ed during cold shutdown.
- Partial-stroke test exercised during cold shutdown and full-stroke test exercised during refueling.
PCRM - Partial-stroke test exercised at cold shutdown.
Valve disassembled during refueling and manual stroke test exercised.
III-23
4 i
2rd Irterval ili Program 49l. l tevision 01 i
Lecend for Valve Table Headinos Unique valve identification number.
VALVE No.
Category of valve as defined-in IWV-2200, and CAT. & CL.
ASME Class as determined for Section XI Piping and instrumentation drawing (P&ID)
DRAWING NOf&
L COORD.
number, and location on P&ID where valve is
-~
shown.
' Nominal pipe size diameter'of the valve, and SIZE-<YPE type of. valve (i.e.,_ check, globe, gate).
Type of valve actuator (i.e.,
motor, air) and ACT. TYPE &
FAIL POS.
position to which the-valve travels upon a_.
loss-of-actuator-power or air.
Normal-position of valve, and valve position &
-POS. NORMAL S..R.
OP..
when it performs its safety related (i.e.,
open, closed or open/ closed) - function.
Secti'on XI valve test requirements.
- CODE; TEST
' REQ.
. C.S.
OR RELIEFL
- -Reference-number of a cold shutdown-t
. REQUEST justification or: relief request which are located following.the valve test tables for each system.
- - Cold Shutdown or alternate testing which is C.S.'OR=
ALTERNATE TEST being performed in. lieu of Code specified quarterlyntesting.
A'brief description of valve function, and'&
DESCRIPTION.
NOTES
. applicable notes.
~
~
Revision Number..
REV. NO.
t v
III-24 Y
h v-
2rd Intervat I$1 Progrm Vol. I Revision 01 Valve Subsystem Index System' Subsection Number Auxiliary Feedwater III-1-1 Auxiliary Steam III-1-2 Borated Water Storage III-1-3 Component Cooling Water III-1-4 Containment Hydrogen Control III-1-5 Containment-Purge III-1-6 Containment Spray IIT_ 1-7 Containment Vacuum Relief III-1-5 Core Flood III-1-9 Decay Heat-Removal III-1-10 Demineralised Water III-1-11 Diesel Generator Air Start III-1-12 Feedwater III-1-13
-Gaseous-Radioactive' Waste III-1-14 High Pressure Injection-III-1-15 HVAC-Radwaste, Fuel Handling, III-1-16
& Access Control Area Instrument Air III-1-17 Main Steam III-1-18 Makeup III-1-3' Nitrogen- __
III-1-2s Reactor Coolant III-1-21
-Sample III-1-22 Service Water III-1-23 Station Air III-1-24
- Station Drains III-1-25 m
III-25
2rd Interval IST Progrcm vol. I fevision 01 VALVE TEST TABLE TOLEDO E0!$0m COMF A4Y Ds.Vis BES$t huCLE AR POWit PLAh!
A f,Llany FFroyAT,LR, STSYtM:
A l VALVE l. CAT.lDWG,h0.l SIZE l ACT. l PCs.l CODE l C.S. OR l C.S. CA i
OESCalPfl0N lCMG.l
[ No.
l 1 l l & l TYPE l koam.) Test l REl.i t F l AutRNAtt l
l l
l l CL.j COORD.ITYPEl
& ( & l REQ.l REcutti l TEST l
h0TES l
1 l
l l
l l Fall l 54 l l
40.
l PteFORMtD l
l l
1 I
I i
l Pos. I ce-l 1
i i
l i
AF1 C
M 0060 SA C
RF-Q CS 1 RF C CST to AFW pum suction 3
G6 CK hA C/C FF-Q tine che:k valve.
AF2 C
M 0360 8
SA C
RF-Q CS 1 RF C CST to AFW psrp suction 3
J4 CK hA O/C FF-Q tine check valve.
AFl$
C M 004c 2
SA C
FF-Q
- FW ptry min flow Line g.10 CK h4 0
c.hect valve.
AF16 C
M-0060 2
SA C
FF-Q AFW puno min. flow Line J.10 CK hA 0
ch'eck valve.
AFtv
.C M 0060 6
SA 0
FF-Q AFW pum discharge line 3
c 11 CK hA 0
check valve-AF20 C
M-0040 6
SA 0
FF.Q AFW puro discharge line 3
J 11 CK NA 0
AF39 C
M 0078 6
SA C
FF-Q RV-1 PCS AFW to SG injection
.4 2
B 12 CK NA 0/C RF-Q Cs 2 RF-C line check valve.
AF43 C
M 0078 6
$A C
FF-Q RV 1 Pl$
64 CK hA 0/C RF-Q CS 2 RF C line cheer. valve.
AF49 C
_ M Octo 6
SA C
RF-Q Cs 2 RF C Motor driven FW punp 3
C-6 CK NA C
discharge to AFW sys, line check valve.-
AF52 C
M 0060 6
SA C
as-Q Cs 2 RF-C Motor detven FW purp 3
06 CK NA C
discharge to AFW sys.
tine check valve.
AF63 C
M 0060 1
SA 0/C RF-Q Cs 3 RF-C AFP 1 cooling water 3
G8 CK 0/C FF-Q recirculation to AFP 1 suction.
AF68 C
M-0060 1
SA 0/C RF-Q Cs.3 RF C AFP 2 cooling water 3
g.6 CK 0/L FF-Q recircutation to AFP2 suction.
111-1-1 1 l
l l
' 2nd Intervat 151 Proerse'vol..I' Revision 01 VALVE TE57 TABLE TOLEDO E0lSou COMPANY DAvil BESSE WUCLEAR POWER PtAbt
-$Y$iEM: AdvltlaRY FEE 0 WATER lVALVEj' CAT.l!aWG.h0.lSICEl Act.l PCs.] CCOE{
C.5-CR.!
C.S. OR l
OESCRIPfl0N lCMG.}
l ha.
l j.
l 4 l TYPE { h0RM.l TEST \\ REllEF l ALTERmAtt
]
l l
1-l Ct. I COORD. I type l & 1 1 REQ. I nacuEsr l test i
ustEs t
l l
l:
l l-Fall l SR l
}
Wo.
] FERFotNJ l
l l
1 I
I i
- 1. PCs. I OP.
l l
1 l
l l
AF72 C
M 0078 6
sA C
H-Q Rv 1 PCs AFW pur discharge 1
5 10 CK hA 0/C RF-Q CS 2 RF-C cross tie Line check valve.
AF73 C
M 0078 6
SA 0
FF-Q Rv 1 PCs AFW pu r discharge 3'
A8 CK h4 0
Crossatie Iine check valve.
AF74 C
M 0078 6
SA 0
FF-Q RV 1 PCs AFW puro discharge 3
A7 CK hA 0
cross tie line check valve.
AF75 C
H 0078 6
SA C
FF-Q Rv 1 PCS AFW pum discharge 3
85 CK hA 0/C RF-Q Cs 2 RF C cross tie line check
}
v.tve.
AF599 5
M 0078 6
M0 L0 TC-Q AFW to sG line block 2
8-2 GT Al C
Pl.f valve.
AF608 s
M 007B 6
MO to TC-Q AFW to SG line block 2
B 13 Gt' Al C
PI T valve.
AF3869-
.B M 0078 6
Mo C'
To-Q AFW pump discharge line 3
A-8 GT At 0/C TC-Q isolation valve, PI-Y
.AF3879 s
M-0078 6
MO O
10-0 AFW pump discharge I e 3
A-10 GT At 0/C TC-Q isosttlon valve.
Pl.Y LU38/1 B
M 0075 6
M0 C
70-0 AFW pum discharge tine 3
A7 GT Al C/C TC-Q isolation valve.
PI-Y AF3872 8
M 0078 6
MO 0
10 0 AFW purp discharge Line 3
A-5 GT At 0/C TC+0 isolation valve.
Pl-i AF4979 C
M 0060 1X1
.SA C
SR-T -
AFW pum cooler line 3
H9 Rt Wa O
rellet valve.
!!!-1-1 2 I
,1nd intoevol 151 Program vol. I Revision 01 VALVE TEST TABLE TOLEDO Edison COMPAhY DavlS SESSE NUCLEAR Powlt PLAhi SYSTEM: AU11LIARY FEEDWATEP jVALVEl CAT.l DWG. ko.l $1ZE l ACT.] F'C3.l C00El C.S. OR {
C.S. OR l
DESCRIP110N lCnG.}
l NO.
l 8 l l & } ifPEl kORM.l 1ESTl kELIEF
} AltithATE l
4 l
l
-l l CL.l COORD. l TYPE l & l 1 j REQ. l RE00EST l TEST l
hofES l
l l
l l
l l FAIL l SR l l
h0.
l PERFCRMED l
l l
l l
l l
l P05.l OP.
}
l l
l
{
j AF4980 C
M 0060 1x1 SA C
tt T AFW pwp cooter line 3
K6 RL hA 0
relief valve.
AF6451 5
M 00M 4
SO O
T0 0 Rv i 70 0 AFW grp discharge flow 3
J 12 CT 0
0 F0 0 RV-2 FO-Q controt valve.
AF6452 5
M 0060 4
SO O
70-0 Rv 2 1040 AFW pwp discharge flow 3
G 12 GT 0
0 F0 c Rv-2 FO o control valve.
(
~
!!! 1 1 3
2nd Intervet lli Program Vol. I Revision 01 RELIEF REQUEST RV-1 SYSTEM:
AUXILIARY FEEDPUMP VALVE (s): _
AF39,_AF43, A'/2, AF73, AF74, AF75 CATEGORY:-
C CLASS:
3 FUNCTION:
Motor Driven Feedwater pump and Auxiliary Feedwater Pump Discharge to the Steam Gerierator Li'.e Check Valves.
-ASME SECTION XI-QUARTERLY TEST REQUIREMENTS:
Verify forward flow operability.
BASIS FOR RELIEF: The Auxiliary Feedwater nozzles spray water directly onto the tubes at the upoer_end of the OTSG.
Injecting this relatively cold water during plant operation causes severe thermal stresses in the-0TSG and may also lead to moisture carryover in the steam, damaging the main turbine.
The consequences of these effects make it undesirable to forward flow test-the listed check valves quarterly.
The-cavitating venturis installed in the Auxiliary Feedwater lines limit the maximum flow to a hot, pressurized steam generator by inducing sonic, two-phase flow through the
- venturi.
Full flow at-the reduced back pressure existing during-cold shutdown conditions causes violent cavitation in the
-venturi.
The resulting severe vibration and pipe movement behavior, similar to the-affects-of water hammer, could result in extensive damage to the piping-and pipe supports.-This problem is-avoided by temporarily replacing each venturi'with a full-flow spool piece.
However, the length of time required.and the wear on the affected systems resulting from this maintenance activity make it impractical to do this more frequently _than on a refueling Linterval.
' ALTERNATE TESTING:
Valves will be partial' flow tested at cold shutdown with cavitating vaaturis installed.
III-1-1-4
~
-.w.,
2nd Interval IST Program Vol. l Revision 01 Valves will be full-flow tested at each refueling with the cavitating venturis replaced-with spool pieces.
\\'
F III-1-1-5
2rd Intervet lli Program Vol. I tevision 01 RELIEF REQUEST RV-2 SYSTEM:
AUXILIARY FEEDWATER VALVE (s):
AF6451, AF6452 CATEGORY:
B CLASS:
3 FUNCTION:
Auxiliary Feedwater Pump Discharge to Steam Generator Line Flow Control Valves.
-ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Exercise, time, and fail position.
BASIS FOR RELIEF:
These are Target Rock solenoid operated valves with position indication from linear variable differential position transmitters.
Valve actuator is a closed cylinder containing the upper valve stem, a solenoid positioner, and stem position string instrumentation.
Valve position is not directly observed.
Valve stroke time is dependent on system flow rates.
Stroke time is measured from open signal till a predetermined output voltage from the linear-variable differential position transmitter indicates the valve is full open.
~
' ALTERNATE TESTING:- Valves will-be timed and fail tested parterly.
Stroke times will be obtained indirectly using output voltage from the linear variable differential position transmitter at no system 1 flow.
Position indication and fail safe position will be verified using system flow each quarter.
III-1-1-6
2nd Intervet IST Program Vol. I nevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-1 SYSTEM:
AUXILIARY FEEDWATER VALVE (s):
AF1, AF2 CATEGORY:
C CLASS:
3 FUNCTION:
Condensate Storage Tank to Auxiliary Feedwater Pump Suction Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Verify reverse flow closure.
COLD SHUTDOWN TEST JUSTIFICATION: There are two possible methods which could be used to verify reverse flow testing. First the use of Service Water as a pressure source against the check valve which is not acceptable due to_ water chemistry. Second using a demineralized water source with pressure or flow instrumentation to verify reverse flow closure. Reverse flow testing would require extensive lineups and test-conditions hence causing the respective Aux Feedpump inoperabilitv time period to exceed the Technical Specifir tion Action Statement.
This would be in viol..cion of Technical Specification 3.7.1.2 which requires the operability of the Auxiliary Feedwater system.
QUARTERLY PARTIAL STROKE TESTING:
N/A COLD SHUTDOWN TESTING:
These valves will be reverse flow tested using an external source of demineralized water-and instrumentation to verify reverse flow.
III-1-1-7
2nd interval 181 Program vol. I Revision 01 COLD SHUTDOWN TEST JUSTIFICA"'ON CS-2 SYSTEM:
AUXILIARY FEEDPUMP VALVE (s):
AF39, AF43, AF49, AFS2, AF72, AF75 CATEGORY:
C CLASS:
3 FUNCTION:
Steam Driven Auxiliary Feedwater Pump and Motor Driven Feedwater Pump Discharge to steam Generator Line Check Valves.
ASME SECTION XI QUARTERLY' TEST REQUIREMENTS:
Verify reverse flow operability.
COLD SHUTDOWN TEST JUSTIFICATION: The only way to verify reforse f.ow operability could exceed the present action statement time limit for the Auxiliary feed system.
A demineralized water source, valve lineupu, and pressure or flow instrumentation would be required to verify no reverse flow for each check valve. Reverse flow testing would require extensive lineups and test conditions hence cauaing the respective Aux Feedpump inoperability time pariod to exceed the Technical Specification Action Statement.
This would be in violation of Technical Specification 3.7.1.2 which requires the operabi.lity of the Auxiliary Feedwater system.
During normal daily power operation, plant operators on their rounds will verify no reverse flow by physically touching the auxiliary feed pump discharge piping to ensure no reverse flow from the steam system.
QUARTERLY PARTIAL STROKE TESTING:
N/A COLD SHUTDOWN TESTING:
Thes'e' valves will be reverse flow tested using an external source of demineralized water and instrumentation to verify reverse j
flow.
III-1-1-8 I
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2nd Intervat IST Program vol, hq; Revision 01.
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L
-COLD. SHUTDOWN TEST JUSTIFICATION-CS-3 4
SYSTEM:'
AUXILIARY!FEEDPUMP
' VALVE (s):
AF63, AF68
- t; CATEGORY:
C
-CLASS:-
- 3:
i Provides_ return flow path 1for auxiliary FUNCTION:
feedwater pump _ cooling water recirculation to the pump suction.
Prevents inadvertent
' challenges to Auxiliary Feedwater pump cooler line relief-valve (s) when-service water is aligned.
ASME'SECTION'XI QUARTERLY TEST:
- REQUIREMENTS:--Verifyfreverse flow operability.
-COLD, SHUTDOWN TEST' JUSTIFICATION:'..The only way to verify reverse flow--
Loperability could; exceed the present action
- statement time limit' forothe Auxiliary. feed system?
A"deminerall.ed water source,~ valve lineups, Land; pressure or' flow instrumentation-Lwould be'. required to verify no reverse flow
~
-for eachLcheck. valve.-Reverse flow testing-would require-extensive lineups and test-conditions hence causing the respective Aux
-FeedpumpEinoperability-_ time. period'to-exceed-sthe Technical: Specification' Action: Statements.-
- This would-beLin violation of Technical o
- Specification;3=.7.1.2<whichirequirestthe-
- operabilityxof;the; Auxiliary Feedwaterl system.
l sQUARTERLY.PARTIALL
. STROKE-TESTING:)
LN/A-
- COLD;SHUTDOWNi ETESTING:n Thesetvalves will be' reverse? flow-tested i
cusing :an external. source of demineralized
-water and instrumentation _to verify reverse iflow.
1
'III-1-1-9 f.
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i 2nd Interval lli Progree "ot. l tevistin 01 VALVI filt TAtti TOLED0 (DISDN COePAWY l
DAvil Sillt NUCLEAR PWER Plaaf
$YlffN AUXfLIAff lifAM lVALytl CAT. l DWG. No. l $1Zt l ACf. l Pos. l CODE l C.S. Ok l C.S. OR l
DistelP11t*
lCnG.l l NO.
l 4 l l 8 l TYPtl NDPM.) filfl RELiff l ALittkAff l
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l PitfotMED l
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l Pos l Op.
l l
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l A1274 C
M+003C 6
SA C
Rf 0 kval if t A$ to AFW purp turbine 3
F4 CK NA C
line check valve.
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l 2nd intervet ist Program vol. I eevision 01 RELIEF REQUEST RV-1 SYSTEM:
AUXILIARY STEAM VALVE (s):
AS274 CATEGORY:
C CLASS:
3 TUNCTION:
6uxiliary Steam to Auxiliary Feedwater Turbir.o Test Line Check Valve.
..sHE SECTION XI QUARTERLY TEST REQUIREMENT:
Verify reverse flow closure.
BASIS FOR RELIEF:
The only time this line is open is during modes 4, 5,
and 6 for test purposen.
During normal operation the inline manual isolation valve AS273 is maintained closed.
The valvo provides the boundary between the class 3 Auxiliary Feedwater System and the non-class Auxiliary Steam System.
The only safety-related function for this valve is to remain closed on loss of Auxiliary Steam System integrity.
ALTtRNATE TESTING:
Valve reverse flow closure will be verified each time the isolation valve has been opened and the valve is exercised, but not more than a frequency of once every 92 days.
III-1-2-2 I
l
b d Interval lli Prcgree vel. I 8evision 01 VALyt Ill! 1AB'(
10LEDO (DISCm COMPakt (AVil Sttst WUCLEAR POWit P. Ant
$YlfEM lf attD W4 tit ST14 3 l VALVI l CA1,l DWG. 40. l 5121 l ACf.( P0t.l CTEl C.t. OR \\
C.S. OR l
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SW26 C
M 033A 3
$A 0/C 4F 0 Return line to telt A.13 CK WA C
Illa 1 3 1 i
2rd intervat 151 Program vet. l teviston 01 VALVE tt$1 1ASLt t0Lf00 (0110h COMPAht CAvis Stsst kuCtt AR POWit PL4ht St$ttM: C P M*Ent Cootth WAtta lv4Lvfl CAT.lDWG.40.l$1ZEl Act. l Pos. l Cot t i C.S. ca l C.5. OR l
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CC17 C
M 036A 16 54 0/C FF-Q C$+2 PGC1 CCW PJT discMarse line 3
05 Cr h4 C/C af-Q Cs 7 RF C check valve.
CC18
- 36A 16
$A 0/C 8F-Q CS 8 PGCS CCW p>v discharge Line 3
95 CK kA 0/C aF-Q C5 7 RF C check valve.
CC19 C
M 036A 16 SA 0/C FF-Q Ct 6 PQC$
CCW pJP discharge line 3
- F C check valve.
CC127 C
M 0364 1.5 SA C/C RF-Q C5 11 RF C Mateup pa r 1 1 non*
3 G3 SC ha O/C FF-Q C5 t3 PQCS entential isolation check valve.
CC128 C
M 0368 1.5 SA D/:
nF-Q Cs.11 ar C usteup pem 1 2 non-3 C.A SC NA 0/C FF-Q C$ 13 PQCS essential isolation check valve.
CC129 C
M+0368 1.5 SA 0/C FF-Q CCW cooting return f rom 3
[3 SC kA 0
Makeup Pu v 1 to CCW Lotp 1.
CC133 C
N 0368 1.5 SA 0/C FF-Q CCW cooltre return f rca 3
(5
$C NA 0
Makeup Pa m 2 tu CCW Loop 2.
CC148 C
M-0368
.5 5A 0/C FF-Q seartog cooling water 3
J.9
$C hA 0
intet to Decay Heat Purm 1 1.
CC149 C
M 0368
.5 SA 0/C FF-Q Bearing cooling water 3
w.9
$C NA 0
intet to pecay Meat Pam 1 2.
CC151 C
M 0368
.75 SA 0/C FF-Q 8 earing cooting mater 3
J7 SC NA 0
outset from Decay Meat punp 1 1.
CC153 C
M 0368
.5 SA 0/C 77 0 Bearing cooling water 3
N8
$C h4 0
outlet from Decay Meat Ptsy 1 2.
I11 1 6-1
2nd Intervat ist Program Vol. I e visto.. Di VALVE 1851 TABLE 10tIDO 10180N CCMPANY CAV!s Bisst kVCLEAR POWER PLANT sist[M COMPOAENT t00LIWC battt l WAlvt l CAT.lDwo.ko.l512tl Act, l Pos. j Ctct l C.S. Da l C.S. Da etstalpflon lCac.l l Wo. l 1 l 4
l & l ttPtl WORM.l fist l Rit!!F l Attit4Att l
l l
l l CL.l C00PD.l71Ptl 8 l &
l At0.l Rtout$1 l 1tst l
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l l
l l
l l FAIL l 58 l l
h0.
l PERF08MID l
l l
1 I
I l
l eos. I De. l 1
l l
l l
CC183 C
M 0400 1.5 54 0
RF 0 Rv'1 RF '
CCW intet to its Pu o 3
J3 sC h4 C
thermet barrier line check volve.
CC256 C
M 0368 1.5 sA 0/C
.C3 sC 4A 0
f or Makeup Ptro 1 CC263 C
M 0368 1.5 SA 0/C f7 0 Cs 13 Pots (CW ci9 ting f rom Loop 2 3
C5 SC NA 0
f or Mehw Ptre 2.
CC283 C
M 0400 1.$
SA 0
Rf 0 tv 1 af R CCW Intet to RCs Ptro 3
J4
((
NA C
thermat barrier line check valve.
CC383 -
C M.0400 1.5 SA 0
ar.o eV 1 RF a CCW intet to RCs Purp 3
- J.4 CK NA C
thermal bartter iine check valve.
CC483 C
M 0400 1.5 sa o
ar o av.1 at a CCW intet to RCs Ptre 3
J4 CK NA C
thermal barrier line check valve.
CC$32 C
M 036A 20 SA C
at-Q CS 6 RF C CCW pro dl6 charge header 3
79 CK NA C
isolation check volve.
CC$33 C-M 036A 20 sA 0
AF 0 CS 6 RF C CCW psp discharge heeder 3
M.9 CK NA C
isolation check valve.
CC1328 8
M 036C 3
MO o
TC.0 CCW Intet to CRDC tooster 3
G.14 GT Al.
C
-Pl.Y pro block valve.
CC1338 8
M 036C 3
MO 0-TC C CCW intet to CRDC Booster 3
G 11 GT Al C
Pl.Y prp block valve.
CC1407A A
M 036C 12 Mo 0
TC 0 Cs 2 TC C CCW return from Letdown 2
A 11 8F Al C
LJ R Cooters Ctmt. 1sotation l-Pl Y valve.
CC1407B A
M 036C 12 Mo 0
1C 0 CS 2 TC C CCW return from Letdown 2
A 13 SF Al C
LJ R Cooters Ctmt. Isolation Pl.Y valve.
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l l
111 1-4 2 l
1 l
l 1
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2nd Intervet lif Progree Vot. I pevision 01
%ALyt 1881 1ABLE 70LtDO (Dil0N COMPAkt DAvil Bisti kJCLEAR POWit PLAki sf5ftM COMPowlti C00LlWG W4 Tit l VALVE l CA1. l DWG. h0. l $121 l ACT,l POS.l C00tl C.$. Op l C.S. OR l
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CC1409 8
M 036C 4
Mo C/0 7C 0 Cl 10 1C C CCW to inlet of the 3
67 GT C
PI f Letdown Cooler CC1410 B
M 036C 4
Mo C/D TC 0 C5 10 TC C CCW to intet of the 3
07 C1 C
PI Y Letoown Cooler CC1411A A
M 036C 12 Mo 0
TC 0 C1 2 TC C CCW to Lttdown Cooiets 2
E.7 Bf Al C
tJ a Ctat. Istdatinn volve.
Pl.T
~
CC14115 A
M 036C 12 M0 0
TC 0 C5 2 TC C CCW to tetdown Coolers 2
F7 BF Al C
LJ 4 Ctat. Isolation valve.
P! Y CC1460 0
M 03CA 1.5 A0 0
TC 0 C5 1 fC C CCW to hon sofety related 3
F 11 GL C
C FC 0 C$ 1 FC C loads isoletion vahe.
P! V CC1467 8
M 0368 18 A0 C
88 SF 0
0 F0 0 isolation velve.
Pl Y CC1469 8
M 0368 16 Art C
70 0 DH Ms CCW outlet line 3
A9 BF 0
0 F0 0 isolation valve, PI Y CC1471 B
M 0368 6
A0 C
70 0 DG Jacket cooling water 3
t6 BF 0
0 70 0 un CCW outlet line PI Y isolation valve.
CC1474 8
M 0364 6
AC C
fo o 00 jacket cooling water 3
G8 BF 0
0 f00 MX CCW vuttet line Pl.Y isolation valve.
CC1495 s
M 036A 16 A0 0
TC 0 CCW to non sofety related 3
M 11 BF C
C FC 0 teacs isoletion valve.
Pl*1 CC1567A A
M 036C 3
M0 O
TC 0 C5 3 TC C CCW intet to CAD cooling 2
C 12 GT Al C
tJ R Ctet. isolation valve.
Pl V lil 1 4 3
ind interssi llt Progrwn vol. I levision 01 4Atyt list 14tti 10LEDO (DI$0m COMPAh1 Cavil 5 Ell! WJCLtAt Powtt PLAh!
$YltlM C P P04thf C(ollkG watit lv4 Lyt l CA1. l DWG. h0. l 5121 l Act. l PCs l Cott l C. S. (;a l C.$. 04 l
Ctstelttite lCyG.)
l Wo.
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l aig. l t t avi gt l ttst l
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I I
I I
I I
CC5098 8
M 0368 12 Mo C
1C 0 Cl 5 fC C Letom Cooter return to 3
B.5 Ct Al C
PI v Ctw tine block valve.
Y 111-1 6 5
... _ ~. _. -. -....
.m r
2nd Interval 151 Progree vol. l aevision 01 i
COLD SHUTDOWN TEST JUSTIFICATION CS-1 t
SYSTEMt COMPollENT C00LI!1G WATER VALVE (s)*
CC1460 CATEGORY:
B c-CLASS 3
I FUNCTIolit CCW to Honessentini Loads Isolation Valve.
i-ASME SECTION XI QUARTERLY TEST REQUIREMENTS!
Exercise, time, and fail.
COLD SHUTDOW!i TEST JUSTIFICATION: Exercising this valve closed during normal operation isolates Component cooling Water flow to the Makeup pump gear and pump lube oil coolers.
At least one makeup pump is in normal operation.
Isolation of cooling water to the operating pump for more than a few minutes could result in extensive damage to the pump.
QUARTERLY PARTIAL STROKE TESTI!1G1 Valve full-strokes on initiation and cannot be part-stroke exercised.
COLD-SHUTDOWil TESTING:
Exercise, time, and fail when the makeup pumps are secured.
E f
III-1-4-6
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2rd interval ist Progtem vet, I testaloa 01 COLD SHUTDOW!1 TEST JUSTIFICATIO!1 CS-2 SYSTEM:
COMPONE!1T COOLI!1G WATER VALVE (s):
CC1407A, CC1407B, CC1411A, CC1411B CATEGORY:
A CLASS 2
FUNCTION:
Inlet and outlet Component Cooling Water Containment Isolation Valves.
ASME SECTIO!1 XI QUARTERLY TEST REQUIREMENTS:
Exercise and time.
COLD SHUTDOWN TEST JUSTIFICATION: These are the containment isolation valves for the Reactor Coolant System pump motor, seal cooler and bearing coolers lines.
A loss of cooling water for more than a few minutes could result 'in extensive damage to the reactor coolant pumps.
Plant Technical Specification 3.4.1.1 requires the reactor coolant pumps and associated support equipment to be operable when the plant is in modes 1 and 2.
QUARTERLY PARTIAL STROKE TESTING:
Valves full-stroke on initiation and cannot be part-stroke exercised.
COLD SHUTDOWN TEGII!1G Exercise and time at cold shutdown when all
~
reactor coolant pumps are secured.
III-1-4-7
~ _. - -
~. - - -.,,. -.
frd Interval ist Program Vol. I neviston 01 i
COLD SHUTDOWN TEST JUSTIFICATION CS-3 SYSTEM COMPONENT COOLING WATER VALVE (s):
.CC1567A, CC1567B CATEGORY:
A CLASS:
2 FUNCTION:
Component Cooling Water to Control Rod Drives Containment Isolation Valves.
i ASME SECTION XI QUARTERLY TEST
-REQUIREMENTS. Exercise and time.
{
-COLD SHUTDOWN TEST J
JUSTIFICATION: These are containment isolation valves in-the cooling line to the control rod drive mechanisms.. A loss of cooling water for more than a few minutes could result in extensive damage to the control rod drive mechaninms, plant operating procedure requires that these valves be maintained open during normal operation.
QUARTERLY PARTIAL STROKE TESTING:
Valves full-stroke on initiation and i
cannot be part-stroke exercised.
t COLD-SHUTDOWN TESTING:
Exercise and time.
t i
III-1-4-8
- -._. ~
)
2rd interval l$1 Program Vol. I tevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-4 SYSTEM:
COMPONENT COOLING WATER
" VALVE (s):
CC4100, CC4200, CC4300, CC4400 CATEGORY:
B l
CLASS:
3 FUNCTION:
CCW Outlet from RCP Pump Thnrmal Barrier Heat Exchanger Outlet Valves.
ASME SECTION XI QUARTERLY TEST
- REQUIREMENTS Exercise and time.
1 COLD SHUTDOWN TEST JUSTIPICATION: Exercising these valves closed during normal operation terminates cooling water to the reactor coolant pump thermal barriers.
A loss of cooling water to the thermal barriers for more than a few minutes could result in extensive damage to the reactcr coolant pumps.
Plant Technical Specification 3.4.1.1 requires the reactor coolant pumps and associated support equipment to be operable when the plant is in modes 1 and 2.
QUARTERLY-PARTIAL STROKE TESTING:
Valves full-stroke on initiation and cannot_be part-stroke exercised.
COLD SHUTDOWN TESTING:
-Exercise and time at cold shutdown when the associated reactor coolant pump is secured.-
III-1-4-9 I
n..
2rd Interval 151 Program vol. I a.claion 01 COLD SHUTDOWN TEST JUSTIFICATION CS-S d
SYSTEM:
COMpONE!Pr COOLING WATER VALVE (s):
CC5097, CCSO98 CATEGORY:
B CLASS:
3 FUNCTION:
CCW Containtaent Header Return Line Isolation valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Exercise and time.
COLD SHUTDOWN TEST JUSTIFICATION: These vaPies are in the return line from the CCW containment header.
Normally.one valve is open to the operating CCW return header.
The other valvu is closed to the non-operating CCW return header.
If the open valve is exercised closed, cooling water to the RCS pumps is terminated.
Termination of cooling water to the RCS pumps for more than a few minutes could result in extensive damage to the RCS pumps.
The only way to exercise these valves without terminating flow to the RCS pump would be to establish flow to the normal standby return header and exercise the open valve in the normal operating return line closed.
This test procedure would violate train separation criteria and could place the plant in an unanalyzed condition.
QUARTERLY PARTIAL STROKE TESTING:
Valves full-stroke on initiation and cannot be part-stroke exercised.
COLD SHUTDOWN TESTING:
Exercise and time.
III-1-4-10
\\
2rd treterval ist Program vol. I I
tevision 01 dOLD SHUTDOWN TEST JUSTIFICATION CS-6 SYSTEM:
COMPONENT COOLING WATER VALVE (s):
CC532, CC533 CATEGORY:
C CLASS:
3 FUNCTION:
CCW Pump Discharge Header Isolation Check Valves.
~
ASME SECTION XI QUARTERLY TEST PEQUIREMENTS:
Verify reverse flow closure.
COLD SHUTDOWN TEST JUSTIFICATION: These valves provide trai.. separation from the essential CCW supply hea ers to the common supply header for non-essential CCW loads.
To verify reverse flow closure during normal 7
operation would require realignment of the normal operating essential loop, standby essential loop, and nonessential normal operating headers.
Realignment of these loops and headers during normal operation could result in system operational transient and could result in a forced plant shutdown.
QUARTERLY PARTIAL STROKE TESTING:
N/A COLD SHUTDOWN TESTING:
Verify reverse flow closure.
III-1-4-ll
2rd interval !$f Program vol. I Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-7 SYSTEM COMPONENT COOLING WATER i
VALVE (s) :
CC17, CC18, CC19 I
CATEGORY:
C I
CLASS:
3 FUNCTION:
Component Cooling Water Pump Discharge Line Check Valves.
ASME'SECTION XI QUARTERLY TEST REQUIREMENT:
Verify reverse flow closure of each pump discharge valve quarterly.
BASIS FOR RELIEF:
All three CCW pumps are connected to a common header.
The header is normally aligned such that two pumps are aligned to one essential loop, with one pump normally in operation to supply normal operating loads.
The second pump is an installed spare and only started to replace the normally operating pump.
The third pump is aligned to the second essential loop and is normally in a standby mode.
To test all three pump discharge check valves for reverse flow closure would require swapping the running component cooling water loop. The step change in cooling water temperature when flow is initiated in the previously idle-loop can result in damagc to the operating Reactor Coolant Pump - (RCP) seals.
Since Technical Specifications 3.4.1.1 requires the RCPs to be operable when the plant is in Modes 1.and 2, damage to RCP seals'would necessitate a plant shutdown.
This system configuration could also violate train separation criteria and could place the system in an unanalyzed condition.
QUARTERLY PARTIAL' STROKE TESTING:
Reverse flow closure verification will be performed quarterly when the respective CCW pump-is aligned -eus the standby or p
spare pump.
Reverse-flow closure verification will be' performed if a running CCW pump has been stopped, the
'III-1-4-12 L
i i'~
--... -....=.. _,.
2nd interval Isf Program vot. !
8evision 01 respective check valve has not been i
tested within 92' days, and can be tested without cross tying essential headers.
COLD SHUTDOWN TESTING:
Reverse flow verification will be performed at each cold shutdown if not performed within 92 days.
4 b
III-1-4-13 1
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2nd intervat ist Proorwa vu. I tevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-8 SYSTEM:
COMPONENT COOLING WATER VALVE (s):
CC17, CC18, CC19 CATEGORY:
C CLASS:
3 FUNCTION:
Component Cooling "ater Pump Discharge Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Verify forward flow operability.
COLD SHUTDOWN TEST JUSTIFICATION: The only way to verify full-flow operability is by operating the associated Component Cooling Water pump at full design flow rate.
The system is normally in operation supplying cooling water to normally operating equipment.
System flow rate during normal operation is dependent on plant-operating and climatic conditions.
If the system flow rate is adjusted to full design flow to verify full-flow operability of these check valves, normal operation of the system would be disrupted and could-cause system transients severe enough to result in a system trip or automatic isolation of cooling water to normally operating-equipment and could result in accelerated equipment degradation or equipment damage.
QUARTERLY PART STROKE TESTING:
Valves are partial forward flow test by normal system operation and during quarterly pump testing.
COLD SHUTDOWN TESTING:
Valves will-be partial forward flow tested quarterly and a full-flow test performed at cold shutdown.
9 III-1-4-14
__~
. _ _. ~~
2rd Intervat 111 Program vol. I sevisico 01 COLD SHUTDOWN TEST JUSTIFICATION CS-9 SYSTEM:
COMPONENT COOLING WATER VALVE (s) :
CC5095, CC5096 CATEGORY:
B CLASS:
3 FUNCTION:
CCW Non-Essential Supply Line Isolation Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS: -Exercise and time.
COLD SHUTDOWN TEST JUSTIFICATION: These valves are in the supply line from the CCW Pump discharge header.
Normally one valve is open to the operating CCW non-essential header.
The other valve is closed to the non-operating CCW non-essential header.
If the open valve is exercised closed, cooling water to the'RCS pumps is terminated.
Termination of cooling water to the RCS pumpse for more than-a few minutes could result in extensive damage to the RCS pumps.
The only way to exercise these valves without terminating flow to the RCS pump would be to establish flow to supply header and exercise the normal standby he normal operating supply the open valve in t
-line closed.
This test procedure would violate train separation criteria and could place the plant in an unanalyzed condition.
QUARTERLY PARTIAL STROKE TESTING:
Valves full-stroke on initiation and
=cannot be-part-stroke exercised.
COLD SHUTDOWN TESTING:-
Exercise-and time.
1 III-1-4-15
frd Interval ist Program vol. I nevis6on 01 COLD SHUTDOWN TEST JUSTIFICATION CS-10 SYSTEM:
COMPONENT COOLING WATER VALVE (s):
CC1409, CC1410 CATEGORY:
B CLASS:
3 FUNCTION:
CCW Inlet Isolation Valve to the Letdown Heat Exchanger (s).
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Exercise and time.
f COLD SHUTDOWN TEST JUSTIFICATION: Exercising these valves closed during normal operation could cause loss of letdown flow since these valves are interlocked with their respective letdown cooler inlet isolation valve.
Cycling these valves would cause excessive thermal cycling and shock degradation of the letdown cooler heat exchanger.
Loss of letdown flow may cause High pressurizer level and per Technical Specification 3.4.4.
result in a plant shutdown.
QUARTERLY PARTIAL STROKE TESTING:
Valves full-stroke on initiation and cannot be partial-stroke exercised.
COLD SHUTDOY.
TESTING:
Exercise and time.
III-1-4-16
2nd Interval ll? Program Vol. I nevtilon 01 COLD SHUTDOWN TEST JUSTIFICATION CS-11 SYSTEM:
COMPONENT COOLING WATER VALVE (s):
CCl27, CC128 CATEGORY:
B CLASS:
3 FUNCTION:
Isolates non-essential oiping from the essential supply for Makeup pump cooling.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify Reverse flow operability.
COLD SHUTDOWN TEST JUSTIFICATION: Reverse flow testing these valves during normal operation requires swapping the running component cooling water loop. The step change in cooling water temperature when flow in initiated in the previously idle loop can result in damnge to the operating Reactor Coolant Pump (RCP) seals.
Since Technical Specifications 3.4.1.1 rdquires the RCPn to be operable when the plant 142 ir Modes 1 and 2, damage to RCP seals vould necessitate a plant shutdown.
In addition tests t.mo constraints could violated Technical Specificat ;n 3.1. 2. 4 action statement.
QUARTERLY PARTIAL
~
STROKE TESTING:
N/A COLD SHUTDOWN TESTING:
Reverse flow test.
III-1-4-17
2rd lettervel 111 Progree Vol. I sevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-12 SYSTEM:
COMPONENT COOLING WATER VALVE (s):
Cr2645, CC2649 CATEGORY:
B CLASS:
3 FUNCTION:
Isolates non-essential piping from the essential supply.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Exercised and time.
COLD SHUTDOWN TEST JUSTIFICATION: Exercising these valves during normal operation requires swapping the running component cooling water loop. The step change in cooling water temperature when flow-is initiated'in:the previously idle loop can result'in damage to the operating Reactor Coolant Pump (RCP) - seals.
Since Technical Specifications 3.4.1.1 requires the RCPs to be operable when the plant is in Modes 1 and 2, damage to RCP-seals would necessitate a plant shutdown.
QUARTERLY-PARTIAL STROKE TESTING:
N/A COLD SHUTDOWN
-TESTING:
Exercise and time.
III-1-4-18
2rd Interval l$t Program vol. I revision at COLD SHUTDOWN TEST JUSTIFICATION CS-13 SYSTEM COMPONENT COOLING WATER VALVE (s):
CCl27, CC128, CC256, CC263 CATEGORY:
B CLASS :
3 FUNCTION:
Non-essential (CC127, CC128) and essential (CC256, CC263) cooling water supply to Makeup pumps.
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Verify forward flow operability.
COLD SHUTDOWN TEST JUSTIFICATION: These valves supply cooling water in a redundant parallel path to the makeu pump bearing and gear oil systems.
Norma ly, non essential component water cooling will suppl both pumps.
Upon SFAS level 4,
non-essentia side cooling will be iso.ated and only the l
essential side will be available.
To test both non-essential and essential valves each quarter would require independent isolation of each parallel path.
This would be critical to a running pump because if forward flow failure occurred then pump damage would occur.
QUARTERLY PART STROKE TESTING: Valves will be partial forward flow verified as a set when non-essential and essential cooling is supplied in parallel.
The non-essential valves will be full forward flow verified when the essential cooling side is not in service.
COLD SHUTDOWN TESTING:
Full-flow test performed at cold shutdown.
III-1-4-19
U 2nd Intervat Ilf Program Vol. I Aevision 01 RELIEF REQUEST RV-1 SYSTEMI-COMPONENT COOLING WATER I
VJ LVE(s) t CC183, CC283, CC383, CC483 CATEGORY:
C C' ASS:
3 Ft1NCTION t -
CCW Inlet to RCS Thermal Barrier Heat E
Exchanger Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Verify reverse flow closure.
BASIS FOR RELIEF:
These tests cannot be performed quarterly during power operation because the system is in operation and cannot be isolated.
Also,-those valves are inside containment.
These tests involve an excessive amount of time and personnel exposure to hazardous environments, potential delay of plant startup, and are too complex to be performed during cold shutdown. These valves will.be scheduled for refueling outages.
ALTERNATE TESTING:
Reverse 1 flow closure will be verified during refueling.
9 h
a T
III-1-4-20 g
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2nd Intereal l$t Program Vol. I tevision 01 VALVE 1887 1ABLE-TOLEDO t0llow COMPAhf C Avil St$it WUCLE AR POWit PL AWT SY$11Mt CONtalNMENT pytt0CEN CONie0L l VA(41 l CAT. l DWG. Wo. j $1?* 8 ACf.l FOS l COCEl C.S. DR l C.$. OR l
Ot sCt !> f ic-4 lCMG.l l 40.
l & l l &
TYttl hDRM l tt$1l k!LlEF l A(itthAlt l
j l
{
l Ct.l C0040.lTfril 4 l & l REQ. l #E0Vist l ttst j
hofts l
l l
l l
l l
l Fall l $4 l l
41.
l FERIORPID l
j l
l l
l l
l P05.l 07 j j
l l
l l
CV124 AC M 0298 1
1A C
FF 0 Ctmt. gas anattier return 2
G9 CK NA 0/C RF-Q AV 1 8F t Ctet isotation valve.
LJ t Forward flom verified by inst. operation.
CV125 AC M 0298 1
$A C
FF 0 Ctet, gas analtier return i
2 H 10 CK hA 0/C 47 0 AV 1 AF t Ctet. isolation velve.
LJ t Forward flow vertfled by inst, operation.
CV186 C
M 0290 2
$A C
FF-Q M2 dilution blower 3
Fait CK 44 0
discharge line check valve.
Cvi87 C
M 0290 2
SA C
FF-Q M2 dilution blower 3:
G 11 CK WA 0
discharge line chect valve.
CV209 AC M 0290 4
SA C
FF 0 M2 dilution blower 2
G9 CE kA 0/C 47 0 RV 1 RF t discharge line Ctst.
LJ R isolation valve.
CV210 AC M 0290 4
$A C
77 0 M2 dilution blower 2
C9 CE
%A -
0/C RF 0 RV 1 RF 4 discharge line Ctat.
tJ t isolation valve.
CV343 A
M 029s 8
MA LC pas Ctmt. Leak test line 2
G4 GT hA C
LJ t Ctmt. isolation valve, CV3876 C
M 029D 1 x 1.5 $A C
st f H2 dilution blower 3
G 12 RL
. h4 0
moisture separator relief valve.
CV3877 C
M 0290 1 X 1.5 (A C
st f H2 dilution blower 3
P 12 RL kA 0
moisture separator retlef valve.
CV5010A A
M 0299 1
M0 C
TC 4 Ctat. N2 analiter semple 2
G5 BL AI 0/C
-10 0 tine Ctet, isolation LJ t
- valve, PI Y lil 151 m
r w,
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n
2rus Interval llt Pf ogram vol. I nAlbt Illi 1A8Lt TOLEDO EDISON C W Ahi Cavls ptstli muCttAt powtt P(Ah!
$flitMt @ fAINufht WYt*0r,tw cateot l VALVE l CA1.lt>wG.b0.l Sill l Act. l F05. l C;01 l C.S. Da l C.$, 05 l
D E $t t l 8110h lCaG.l l
40.
l & l l & l l'Pt j h0Ru.! Tllt j tritti l Altitheft j
l l
l l CL.j COORD.l TYPE l 5 l &
l RtQ. l t t 0Ul$i l fiff l
40!t $
l l
l l
l l
l FAIL l $t l l
hD.
l titf0RutD i
l l
l l
l l
! POS. l CP-l l
l l
l CV50100 4
m 0298 1
mo C
10 0 Ctet. *2 analiser samte 2
w4 BL Al C/C 10 0 ttre Ctet. isolatton LJ 4 valve.
PI V cv5010C A
M 029s 1
No C
TC 0 Ctet, n2 anatiser samle 2
E9 BL At 0/C 10 0 line Ctmt. isolation LJ t valve.
Pl f Cv50100 A
m 0298 1
40 C
1C 0 Ctet. e2 analiser samle 2
G 11 8L At 0/C to-Q tine Ctet. I solat ion LJ R valve.
Pl Y Cv5010t A
m 0298 1.5 mo C
TC-Q Ctet. M2 analiser samle 2
". 11 CA Al 0/C 10-Q line Ctmt. isolation LJ t vetve.
Pl*Y a
tv5011A A
m 0298 1
Mo C
1C 0 Ctat. n2 enet t ner samte 2
G3 BL At 0/C 10 0 line Ctat. isolation LJ t valve.
PI Y CV50118 A
M 029B 1
M0 C
TC-Q Ctmt. M2 anaitser sagte 2
H5 SL At 0/C T0 0 tine Ctat. isolation LJ't valve PI Y tv5011C A
M 0298 i
Mo C
1C-Q Ctat. H2 enaliser samle 2
F 11 SL At 0/C 10-Q tine Ctet. isolation LJ t valve.
Pl Y CY50110 A
M 0298 1
Mo C
TC-Q Ctmt. M2 analiser samte 2
F9 BL Al 0/C 70 0 line Ctmt. isolation LJ*t valve.
PI f 111 1 5 2
2nd IntOrv8L l$i Protf M tfol. I tevision 01 v4 Lyt it$1 1ABLt 10Lt00 10l$0W COMPAWf DAVil ttltt WUCLEAR Powtt PLANT St$ttMt COWf athMtWt NYet00tW COWit0L jVALVIl cat.l DA h0.l $12t l ACT.l F01. l C001 l C.S. 04 l C.$. 04 j
tittelPfl0W jCnG.l l Wo._l 4 l 4
l 8 l tvPtl WoaM l ttstl attitt l ALitaWAtt l
l l
}
l Ct.l C03RD. l ffPE l 4 i &
l Bl3.l REwt St {
litt l
W0ftl l
j l
l l
l l 8Allj SR l l
WO.
l FLAF0amto l
j l
l 1
1 I
I PDA. I OP.
I I
I i
l 1
Cv5011t A
M-0298 1.5 MD C
TC+0 Ctat. W2 analiser samte 2
H.11-DA At 0/C 10 0 line Ctet. isolation LJ t valve.
Pl.T tv503T A
M 0290 4
Mo -
C TC 3 n2 purge Ctet, isotation 2
N.4 '
$F At 0/C 10 0 valve.
LJ t Plaf Cv5038 A
M 0290 4
M0 C
1C 9 N2 pu se Ctet, lac ration 2
W.4 SF At 0/C 10 0 valvw.
j LJ t
?l ?
CV5065 A
M 0290 4
Mo C
TC 0 W2 dilution Ctat.
2 G.10 Bf At 0/C 10 0 Isolation valve.
LJ t Pl.Y Cv5090-A M 0290 4
Mo C
TC o W2 dilution Ctmt.
2 G.10 8F At 0/C 10 0 isolation valve.
LJ t Pl.V e
!!! 1-5 3 I
i
2nd Interval 151 Program vol. I sevision et RELIEF REQUEST RV-1 SYSTEM:
CONTAINMENT HYDROGEN CONTROL VALVE (s):
CV124, CV125, CV209, CV210 CATEGORY:
AC CLASS:
2 FUNCTION:
Containment. solation Check Valves.
f ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Ver*l'/ reverse-flow closure.
BASIS FOR RELIEFt The only method available to verify tsverse-flow closure is by valv9 leak test during Appendix J, Type C, testing at refueling.
ALTERNATE TESTING:
Reverse-flow closure will be verified during Appendix J, Type C, testing at refueling.
III-1-5-4
2rd Intervat 151 Prosene vol. I
?+ vision 01 VAlvt 1851 TABLE 10LtDo (Dit0N COMPAWY DAvil Bill! WgCLE AR POWit PL ANT
$1sttN CONTAthutNT PURCE l VALVE l CAT.l DWG. NO.] slll l ACT,l POS.l COCE l C. S. C't l
C.S. OR j
ct$Ct!Pfl0W l C4.l l
h0.
l 4 l 1
l 4 l ffPCl 404W.l 1tStl t!LitF j ALitt4Aff
}
l l
l l Ct.l C00eo.lftPEl & l &
l tio l ttoutst j tr$f j
otti l
)
l l
l l
l Fi l $4 j j
NO.
) PitFotutD
{
j
}
l l
l 1
i Pos. I OP.
l I
I l
l l
CV$004 0
M 029E 42 A0 J
fC.0 Penetration room suroly
)
F 12 tl C
C FC 0 line isolation volve.
PI-Y CV$005 A
N 0298 48 A0 C
tt c CS 1 fC C Ctet, purge supply Ctet.
2
(*11 BF C
C FC 0 C$ 1 FC C isolation valve.
LJ R PI Y Cv5006 A
N 0298 48 A0 C
TC 0 Cs.1 tC C Ctat. purge supply Ctet.
2 f.11 BF C
C FC 0 C$ 1 FC C isolation volve.
LJ*R PI i Cv5007 A
M 029E 48 AD C
TC 9 Cs.1 fC C Ctet. purse enheust *tet.
2 G5-BF C
C FC 0 C* 1 FC C isolation volve.
LJ R Pl*Y Cv5008 A-M 029E 46 A0 C
TC-Q CS 1 TC C Ctet. surge exhaust Ctet.
2 C 4-BF C
C FC 0 CS 1 FC C iscattion volve.
LJ=R Pl.V
-Cv5009 M 029E 42 A0 0
TC-Q Penetration room exhaust 3
G4 BF C
C FC-Q line isol.clon valve.
Pl*1 CV5016 B
M 0298 42 A0 0
TC-Q Penetration tcon supply 3
G.12 BF C
C FC-Q tine isolation vmlve.
Pl.T l
Cv5021 t
M 0298 42 A0 0
TC-Q Penetration room exhaust l
3 G4 BF C
C FC-Q line isolation volve.
P'.Y 111-1 6 1
t 1 :-
i 2nd intervet 18f Program Vol. I i
aevision et COLD SHUTDOWN TEST. JUSTIFICATION l
CS-1 SYSTEM:
CONTAINMENT PURGE
= VALVE (s)t-CV5005, CV5006, CV5007, CV5008 l
CATEGORY:
. A CLASS!
2 l
FUNCTION:
Containment Purge Inlet (CV5005, CV5006)- and Exhaust (CV5007, CV5008). Containment Isolation valves.
- QUARTERLY TEST REQUIREMENTS
Exercise, time and fail.
- COLD SHUTDOWN TEST i
JUSTIFICATION: Valves are required'to be closed and d?-
energized during plant operating modes 1, 2,
3 and 4 by plant Technical Specification I
.3.6.1.7.
Valves are maintained normally
- closed to isolate direct flow paths from the
! containment-atmosphere to the outside atmosphere.
Valves may be opened during normal operation to purge the containment' 4
atmosphere if personnel access into the I
containment-is required.- Accumulated time for any purge supply and/or exhaust valve to be open is limited to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> or less for the preceding 365 days.
These valves are not to be open in Modes 1, 2,.3, or 4 as committed
~
to the NRC.
QUARTERLY PARTML=
STROKE TESTING; Valves full-stroke.on initiation and cannot be yart-stroke. exercised.
COLD SHUTDOWN
- TESTING:
Exercise, time 1and' fail.
.t
-III-1-6-2 i
V 3
l r
i l'
'i ~
'y
- 4
.; w. -
,,+a
.--.,-..,-,~..~-.----,,.--,-,..nn,,-,.--an-~--,
It.
I 2nd interW
- ?f-bgram Vol. I Revision 01 VALVE TE$f TABLE totEDO EDis0N COMPANY CAvis 6 ESSE NUCLEAR POWER PLANT SY$ TEM: CONTAtkNEWT SPRAY lVALV1l CAT.] OWG. No.l $IZE l ACT.l P05.l CODE l C.S. Da l C.S. OR l
DESCRIPfl04 lCMG.l
.l NO.
l & l l & l TYPE l h0RM.l TEST l SkLIEF l ALTEthAli l
l l
l-l CL l COORD.lfYPEl l & l 9EQ.l AEQUElf l TEST l
h01E5 l
}
I I
i 1
i Fall I s a i I
60.
I PEucaato I
i l
l l
l l Pos.l OP.
l l
l l
l
]
CS9 C
M 03A 8
SA C
FF-Q C5 pro dischar; w
2 99 CC h4 0/C RF-Q CS 1 RF C check valve.
C$10 e
M 034 8
sA C
FF o es pro dischargs line 2
0-V CE NA O/C RF-Q CS 1 RF C check valve.
CS17 A
M 034 8
MA C
PAS Cs pro test Line Ctmt.
2 36 GL NA C
LJ R isolation velve.
Pen. P25.
CS18 A
M 034 8
MA C
PAS C5 pnp test Line Ctmt.
2 C6 GL hA C
LJ t isolation valve.
Pen. P26.
CS33 A
M 034 8
MA LC pas Cs pro test line Ctmt.
2 A6 G1 NA C
LJ R isolation valve.
Pen. P25.
CS36 A
M 034 8
MA LC PAS CS pep test line Ctmt.
2 C6 GT hA C
LJ R isolation valve.
Pen. P26, C$1530 A
M 034 8
M0 C
70 0 CS pro discharge Line 2
07 GL At 0/C TC-Q Ctmt. Isotation valve.
LJ R Pen. P26.
PI Y C$1531 A
M 034 8
V
~
T0 o Cs pum d scharge tine 2
B7 CL n>
TC-Q Ctet. $$olation valve.
?Jt Pen. P2'.
vt f 111 1 7-1 i
2nd intervet t$i Program Vol. I nevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-1 5YSTEM:
CONTAINMENT SPRAY VALVE (S):
CS9, CS10 CATEGORY:
C CLASS *.
2 FUNCTION:
Containment Spray Pump Discharge Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verifv reverse flow closure.
COLD SHUTDOWN TEST JUSTIFICATION: To verify reverse flow closure of these valves downstream inline manual maintenance valves must be closed and an external source of water injected into the system through downstream line taps and test instrumentation installed on the system. To do this test during normal operation would disable one train of the containment spray system for an extended period of time, contrary to Technical Specification 3.6.2.1.
m. '.
ERLY 'T ST 8 M TE TESTING: N/A S :.3 SHUTDOWN TESTING:
Verify reverse flow closure.
III-1-7-2
2nd Intervat IST Program vot. !
Revision 01 VALVE TE.T 1ABLE TOLEDO E0l$0N COMPANY CAvt$ 8E55E NUCLEAR POWER PLANT SYSTEM: COWTAthMENT vatt0M #ELIEF l VALVE l CAT.)DWG.NO.] SIZE l ACT.l P05. l C00E l C.S. OR l C.S. OR l
DESCRIPfl04 lCHC.l l h0.
l & j l & l TYPE l MnRM.l Test l RELIEF l ALTERhATE l
l l
l l CL.l-COORD.l TYPE l &
l &
l REG. l REQUE51 l TElf j
hofE5 l
l l
l l
l l 'Alll 5R l l
h0.
l PERFORMED l
l l
l i
i l
l MS. I OP-1 I
I I
I I
CV5070 A
M 0298 8
M0 O
- C-Q Ctmt. vacuum breaker 2
B5 BF Al C
LJ R isolation valve.
PI Y Cv5071 A
M 0298 8
MO O
YC-Q Ctmt. vacuan breaker 2
B5 SF Al C
LJ R isolation valve.
P!-Y Cv5072 A
M 0299 8
M0 O
TC-Q Ctet. vacuum breaker 2
B5 8F Al C
LJ R isolation valve.
PI Y CV5073 A
M 0298 8
MO O
TC-4 Ctmt. vacuum breaker 2
85 67 Al C
LJ R isolation valve, PI Y CV1074 A
M 0?96 8
Mo 0
YC-Q Ctmt, vacuum breaker 2
85 SF Al C
LJ R isolation valve, PI Y s
CV5075 A
M 0298 8
MO O
100 Ctat. vacuum breaker 2
B5 SF Al C
LJ R isolation valve, Pt Y CV5076 A
M 0298 8
MO O
TC-Q Ctmt, vacutsn breaker 2
B5 BF At C
LJ R isolation valve.
Pl Y CV5077 A
M 0299 8
MO O
TC o Ctmt. vacuum breaker 2
B5 SF Al C
LJ R isolation valve.
PI-Y CV5078 A
M 0298 8
MO O
TC-Q Ctmt. vac u breaker 2
s5 SF Al C
LJ R isolation valve.
P! Y CV5079 A
M 0299 8
M0 O
TC-Q Ctmt. vacum breaker 2
85 BF Al C
LJ R isolation valve.
Pl.Y til 1 8 1
I l
2rtd Intervot ist Program vol. I Revision 01 VALVE TEST TABLE tc/s00 C0150N CCMPANY DAvts 5 ESSE NUCLEAR POWER PL AWT SYtfEM: CoutA!NMENT VACUUM eELIEF
]_ VALVE l CAT.lDWG.h0.]512El ACf.l POS,l C00fl C.S. OR l C.$. OR l
CESCRIPi!ON lCNC.l l ko. ] & l l & l ffPt j h0RM.l TEST l REttEF l ALTERNATE l
l l
l l CL.l CCXRD. l TYPE l 4 l &
l REo.l RioufSt l TEST l
40fES l
l l
l l
l l Fall l SR l j
NO.
l PERFORMCD l
l l
l l
l j
l POS.l OP.
l l
l l
l j
CV5080 AC M 0298 8
SA C
VR-T CS 1 VR f Ctmt. vacuum relief 2
B5 CK NA 0/C RF-o Rv 1 RF-R valve. set point LJ-R verified as a relief valve.
Cv5081 AC M 0298 8
SA C
VR 7 C5-1 va f Ctmt. vacuan ret lef 2-B5 CK NA 0/C RF-Q av 1 RF R valve. set point LJ R verified as a relief valve.
Cv5082 AC M-0298 8
SA C
VR Y C$+1 VR f Ctet, vacuun ret tet 2
B5 CK h4 0/C RF.o av.1 RF R vatve set point LJ R verified as a relief valve.
VR f CS 1 VR T Ctat, vacuun relief 2
B-5 CK NA 0/C RF-o Rv 1 RF R valve. Set point L,J R verified as a reilef valve.
Cv5084 AC M 0298 8
sA C
VR.t CS 1 VR 1 Ctmt. vacuun relief 2
85 CK hA 0/C RF-o
~4V-1 48-P valve. Set point (J-R verified as a relief valve.
Cv5085 AC
.M-0298 8
SA C.
VR.T CS 1 VR t Ctmt. vacuan relief 2-B.5 CK hA O/C RF-Q RV 1 RF R valve. Set point LJ R verified as a relief valve.
Cv5086 AC M-0298 8
SA C
VR f C$*1 VR T Ctmt. Vacuum relief 2
85 CK NA O/C RF-Q RV 1 RF R valve. set point LJ R verified as a relief valve.
Cv5087 AC M 0298 8
SA C
VR T CS 1 VR*T Ctat. vacuun relief 2
85 CK NA 0/C RF.o Rv 1 RF R vatve. Set point LJ.R verified as a relief valve.
111-1 8 2
1 i
1 2rd Intervat 15i &rogram Vat. I Revision 01 VALVE TEST TABLE TOLEDO EDISON COMPANY CAVIS BES$$ NUCt(AR POWER PLANT 1
SYSTEM: CONietWENT v4CUUM #ElliF lVAlvtl CAT.lDWG.NO.l$1ZEl ACT.l PO$.l CODE l C.S. OR l C.S. OR l
DESCRIPfl04 lCMG.l l.No.
l & l 1
l
& l TYPE l NORM.l TESI l RELIEF l ALTEthATE j
l l
l l CL.'l COORD. l TYPE l 1 l 8 l REQ. ] REQUEST l Test l
NofE5 l
l
_l l
l l
l Fall l $R l l
NO.
l PERFDEMED l
l l
l l
l l
l PO$.l OP.
l l
l l
l l
CV5088 AC M 0298 8
SA C
VR 1 Cs.1 VR T Ctmt vacutse relief 2
65 CK NA 0/C RF o RV-1 AF 4 valve. Set point LJ.R verified as a rellet valve.
CV5089 AC M 0299 8
SA C
VR.i CS+1 VR T Ctat. vacuum relief 2
B5-CK hA 0/C RF.Q RV 1 RF R valve. $et point LJ+R verified as a relief valve.
!!!.1 8-3
2rd Interval IST Program Voi, I tevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-1 SYSTEM:
CONTAINMENT VACUUM RELIEF
-VALVE (s ) :.
CV5080 THRU CV5089 CATEGORY:
AC CLASS:
2 FUNCTION:
Containment Vacuum Relief Containmert Isolation Check Valves.
ASME SECTION'XI QUARTERLY TEST REQUIREMENTS:
Within every 6 month period operability test shall be performed per ANSI /ASME OM-1-1981 cection 1.3.4.3.a COLD SHUTDOWN TEST JUSTIFICATION:.To perform operability test of these valves will require personnel to enter the= annulus.
This area is located between the containment
-vessel and shjeld building.
The annulus is a locked high radiation area that contains high neutron fields. To do this test during normal operation would violate ALARA concerns.
COLD. SHUTDOWN TESTING:
Manual stroke open and close to ensure opsrability.
III-1-8-4
J 2nd Intervat IST Program Vol. I tevision 01 RV-1 SYSTEM:
CONTAINMENT VACUUM RELIEF VALVE (s):
CV5080 THRU CV5089 CATEGORY:
AC CIASS:
2 FUNCTION:
Containment Vacuum Relief Containment Isolation Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify reverse-flow closure.
BASIS FOR RELIEF:
The only method available to verify reverse-flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.
ALTERNATE TESTING:
Reverse-flow closure will be verified during Appendix J, Type C, testing at refueling.
l III-1-8-5 l
2nd Interval IST Program vol. I Revision 01 bALVE TEST TABLE 10tE00 D ISON COMPANY DAVIS BESSE WuCLEAR POWER PLAhi SYSTEM CORE FLOCO l VALVE l CAT. ] DWG. h0. l SIZE l ACT.l POS.l C00El C.S. OR l C.S. OR l
CESCRIPfloh lCMG.)
l ko.
l- & l 5
l 4 l TYPE l h0RM.l TEST l RELIEF l ALTERNATE l
l l
l l CL.l COORD. l iYFE l &
l 4 l AEO.l RECOEST l TEST l
hofES l
l
.l-l l
l l FAIL l SR l l
NO.
j PERFORMED l
l l
1-1 I
i l Pos. I OP.
l l
l l
l l
l CF1A B
M 034 14 M0 O
T3 0 CS 1 f0 C Core Flood tank to RCS 2
J3 GT At 0/C TC-Q CS 1 TC C line block valve.
PI Y CF13 8
M 034 14 Mo o
to o CS 1 70 C Core Flood tank to RCS 2
J8 GT At 0/C TC-Q CS.1 TC C line block valve.
PI Y CF2A A
M 034 1
M0 LC TC-Q Core Flood Tank drain 2
J.i CL Al C
LJ-R Ctet. isolation valve.
PI Y Pen. P47A.
CF28 A
M 034 1
MO LC TC 0 Core Flood Tank drain 2
J6 GL-Al C
LJ R Ctmt. isolation valve.
P! Y Pen. P47A.
CF5A A
M 034 1
M0 LC PAS Core Flood tank vent line 2
G-4 CL Al C
LJ R Ctmt. isolation valve.
PI V Pen. P478.
CF5B A
M 034 1
M0 LC PAS Core Flood Tank vent line 2
G6 GL Al C
LJ R Ctet. Isolation valve.
Pl.Y Pen. P478.'
CF7A
.C M 034 1x2 SA C
SR T Core Flood Tank safety 2
G-3 RL NA 0
relief valve.
' CF79 C
M 034 1x2 SA C
SR T Core Flood tahk safety 2
G8 RL MA 0
relief valve.
CF15 AC M 034 1
SA ~
C RF-Q Rv 1 RF R hitrogen and HPl Core 2
G3 SC WA C
LJ-R Flood Tank till line Ctmt, isolation valve.
Pen. P44A.
CF16 AC M 034 1
SA C
RF-Q RV 1 RF R Nitrogen and HP! Core 2
G9 JSC NA=
C LJ+R Flood Tank fill line Ctmt. Isolation valve.
Pen. P71C.
F23 C
M-0338.
14 SA C
FF-o RV 2 PCS Core Flood tank discharge 1
B3 CK kA 0
!!!-1 9 1
2rtd Intervat l$f Program Vol. I Revision 01 VALVE TEST T ABLE 10LEDO EDISON CCMPANY C AVIS BESSE NUCLE AR POWER PL ANT SYSTEMI COPE Florm l VALVE l CAT. } CWG, NO. l 512E { Act.l P05. l CCCE l C.S. OR l C.S. OR l
CESCRIPf!Ce lCHO.l l
NO.
l &
}-
l & [ TYPE l NORM.l TElfl RELIEF l ALTERhATE l
5 l
l l
l CL.l CmRD. l TYPE l &
l &
l REQ. } RE3UEST l TEST l
h0TES l
l l
l l
l l Fall l 5R l l
h0.
l PERFORMED l
l l
1 1
I I
l P05. I OP.
I l
i i
I i
CF29 C
M 0338 14 sA C
FF-Q RV 2 PC$
Core Flood Tant discha*ge 1
81 CK NA 0
CF30 AC M 0338 14 sA C
FF c Rv.2 PCS Core Flood tank /tPl
~
1 B3 CK WA 0/C RF-Q VG-2 RF C injection corron line LP R VG 2 LP C check valve. See Sections lit.3.16.
CF31 AC M 0338 14 sA C
FF o Rv 2 PCS Core Flood Tank /LPI 1
62 CK NA 0/C RF-Q v0 2 RF C injection ecmon line LP-R VG 2 LP C check valve. See Sections
!!I.3.16.
CF1541 A
M 034 1
A0 0/C TC-Q hitrogen and HPI Core 2
E 10 CL C
C FC-Q Flood tank fitt Line LJ R Ctmt, isolation valve, PI-Y Pen. P44A.
CF1542 A
M 034 1
A0 C
TC-Q Core Flood tank vent tine 2
E 11 GT C
C FC C Ctmt. isolation valve.
(J R Pen. P478.
Pl Y CF1544 A
M 034 1
A0 0/C TC-Q Nitrogen and HPI Core 2
G-10 GL C
C FC-Q Flood tank fitt Line LJ R Ctmt. isolation valve, Pl.Y Pen. P71C.
CF1545 A
M 034 1
A0 0/C TC o Core Flood tank vent Line 2
F 10 GL C
C FC-Q Ctmt. isolation valve.
LJ R Pen. P47A.
PI Y lli 1-9-2
4
-2nd Interval IST Program Vol. I tevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-1
-SYSTEM:
CORE FLOOD VALVE (s):
CFIA, CFlB CATEGORY:
B
-CLASS:
2 FUNCTION:
Core Flood Tank to RCS Line Block Valves.
ASME SECTION XI
. QUARTERLY '4'EST
-REQUIREMENIS:--
Exercise and time.
. COLD SHUTDOWN TEST-
~ JUSTIFICATION:
Each Core Flood Tank isolation valve
~
opens automatically and is interlocked against closing whenever the Reactor Cociant System pressure exceeds 800 psig.
To close these valves at power would cause one Core-Flood train required by Technical Specification 4.5.1.a to be inoperable.
QUARTERLY PARTIAL STROKE TESTING:
-N/A COLD SHUTDOWN TESTING:
Exercise and time.
III-1-9-3
2nd Intervat ist Program vol. 1
[
I Revision 01 RELIEF; REQUEST RV-1 SYSTEM:
CORE FLOOD
. VALVE (s):
CF15, CF16 CATEGORY:
AC CLASS:
2 ft.'NCTION :
Nitrogen and Core Flood Tank Fill Line Containment Isolation Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify reverse-flow closure.
-BASIS FOR RELIEF:
The only method available to verify reverse-flow closure is by valve leak testing during Appendix J, Type C, testing.at refueling.
ALTERNATE TESTING:
Reverse-flow closure will be verified during Appendix J, Type C, testing at refueling.
III-1-9-4 1
1
2nd Interval IST Program Vol. I Revision 01 RELIEF REQUEST RV-2
-SYSTEM:
CORE FLOOD VALVE (s):
CF28, CF29, CF30, CF31 CATEGORY:
C CLASS:
1 FUNCTION:-
Core Flood Tank Discharge Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:. Verify forward. flow operability.
BASIS-FOR RELIEF: The Core Flood Tanks are isolated-from the RCS by-these normally. closed check valves.
Each Core Flood Tank is charged with a nitrogen blanket at approximately 600 psig.
-This-pressure is insufficient during operation to inject into the RCS.
If these-vtives were to-be exercised at-cold-shutdown, the contents of the tanks would be dumped into the RCS-at the charged pressure which would interfere with RCS depressurization, inventory control, boron-control, could result in overpressurization: of the. RCS and introduce
.l the possibility of brittle fracture.
)
It is impractical'ta attempt to pass design flow rate -through these valves. - Estimated-design flow: rate is 3750-pound, mass per second. -This mass flow rate could destroy or damage core internals.-
Core flood--tank check valves are-tested with
~teactor: vessel-head removed.
Core flood tank pressure is adjusted to approximately 60-psig as determined per refueling. canal level to ensure a repeatable test condition. Core flood tankx isolation' valves are cycled open.
Flow-
- rate (core. flood tank level change)-and valve differential pressures are recorded. !This
. flow rate and dif ferential: pressure is
^
. correlated to-the design flow rate.: -This alternative test would provide an acceptable-level of. quality and safety.
ALTERNATE TESTING: 'These valves will be forward flow tested.
at refueling when-the-reactor vessel head.is removed and the core flood tanks can be dumped
'into the; refueling canal.- Valve differential pressure--and level change is measured during-III-1-9-5
2nd Interval tst Program vot. I Revision 01 the dump test to verify that the valves passes a defined flow rate.
Because accident flow rates can no'. be achieved, test flow rate and differential pressure are measured and correlated to verify flow is greater than or equal to the design base accident flow condition.
A partial forward flow test at cold shutdown will be performed for CF28, CF29, CF30, and CF31 using Core Flood Tank inventory at reduced Core Flood Tank and RCS pressure.
A supplementary partial forward flow test at cold shutdown could also be performed for CF30 and CF31 using the normal Decay Heat removal system.
III-1-9-6
2nd Intervat l$1 Progreen vol. I Revision 01 VALVE TEST TABLE TOLEDO EDISON COMPAWY DAvlS 8E$sE NUCLE AR POWER PL ANT
$f$ TEM: DECAV NEAT DEMg(R l
l VALVE l CAI.l.DWG.No.l SIZE l ACT. l Pos.j.C00El C.S. OR I C.S. OR l
CESCRIPf!ON lCMG.}
l No.-
] & l l & l TYPE l NORM.l TEST l RELIEF l ALTERNATE l
l l
l l CL l COORD. l TYPE l 8 l 8 l
REQ.' l REQUEST l TES1 l
h0TES l
l
)
l l
l l
j FAIL l SR l l
NO.
l PERFORMED l
l l
l l
l 1
1 PCs. l OP.
l l
l l
l l
Ou1A 8
M 0338 10 Mo
.to TC-Q Cs 4 TC C Meat enchanger discharge 2
86 ut AI -
0/C 10-0 Cs 4 To C t ir,e block vatve-P!-Y DN18 8
M 0338 10 M0 to TC-Q C$ 4 tC C Heat exchanger discharge 2
06 GT Al O/C T0 0 CS 4 10 C tine block valve.
PI Y DH7A 8
M 033A 14 M0 LO TC-Q Cs-6 TC C BwST to OH ptsp suction 2
0 11 GT At 0/C PI Y l }r.e block valve.
Ow78.
8 M 033A 14 MO so TC-Q Cs 6 TC C swst to Du map extlan 2
0 10 GT At 0/C PI-Y tine block valve.
SHgA 8
M 033C 14 Mo C
To-Q Rv 1 To R Ch/LMs1 Ctmt. swp block 2
K3 GT AI 0/C TC-Q Rv 1 TC R valve.
PI-Y CH98 8
M-0338 14 Mo C
To o kv-1 70-R DH/LHs! Ctmt, strip block 2.
K6 GT Al 0/C TC-Q Rv 1 TC R valve.
PI Y OH11 8
M 0338 12 Mo C
To-Q Cs-1 To C RCs letdown to DN sys.
.1 H-3 GT At 0/C TC-Q Cs-1 TC C line block valve.
PI Y
~
-ON12-8 M 0338 12 na C
70-0 Cs 1 -
70 C RCS tetdown to OH sys.
1 H2 GT At 0/C
.tc.Q Cs.1 tC C line block valve.
PI Y
'0H13A 8
M 033C 6
Ao C
TC-Q Heat exchanger bypass 2
F 10 SF C
C FC-Q flow controt valve.
PI Y CH138 8
M 0338 6
A0 C
TC+Q Heat exchanger bypass 2
G-12--
SF C.
C FC-Q flew control valve.
PI V OH14A B
M*033C 10 A0 LO 10-Q Heat exchanger cuttet 2
C9 SF 0
0 FO-Q flow control valve, PI-Y
!!I 1-10-1
t 2rtd Interval IST Program Vol. I Revision 01 VALVE TEST TABLE 10LE00 EDISON CCM ANY DAVIS SESSE NUCLEAR POWER PLANT
' SYSTEM: DEC O hE'8T RE MYAL l VALVE l
'AT.l DWG, No.l SIZE l ACT.l POS.l CODE l C.S. OR l C.S. OR l
OESCRIPfl0N lCMG.l l
NO.
! &.l l & l TYPE l kORMl TEST l RELIEF l ALTERhATE l
4 l
g l
l CL. l C00RO.-l TYPE l 8 l 6 l REQ. l RE M ST l TEST l
notes l
l
.l l
l l
l FAIL l SR-l l
h0.
l PERFORME0 l
l l
l l
I i
i POS. I OP.
1 I
I I
I I
DN148
-8 M 0338 10 AO Lo to o seat exchanger outlet 2
E 11 BF 0
0 FO-Q flow control valve.
PI Y ON42 C
M 033C 10 SA 0/C FF c on pump discharge line 2
F8 CK WA 0
DH43 C
M 0338 to SA O/C FF-o on pe p discharge line 2
C-10 CK h4 0
CH63 8
M 0338 4
Mo C
8 12 GT At 0/C TC-Q suction line block valve.
PI-Y
'JH64 8
M 0338 4-Mo C
70 0 OH supply to HPl pm p 2
C9 GT At 0/C TC-o suction tine block vetva.
PI-Y ON76 AC - M 0338 10 SA LO/C FF-Q CS 3 FF-C on injection to Reactor 1-B3 SC hA 0/C RF-Q VG 2 RF C Vesset line che:k valve.
LP R LP C See Sections 111.3.16.
OnT7 AC.. M 0338 10 SA LO/C FF-0 CS 3 FF C DH injection to Reactor 1-02 SC NA 0/C RF-Q VG 2 RF C Vessel line check valve.
vR LP C See Sections 111.3.16 DHS1 C
M 033A-14 SA-0/C FF-Q CS 7-PQCS BWST to DN pwp suction 2
N-10 CK NA 0
line check valve.
DM82 C
M 033A 14
- SA 0/C FF o CS.7 PQCS BWST to DN pw p suction 2
F-11 CK NA 0
line check valve.
DH87
'A-M 0338-8 MA LC PAS Ctmt, isolatten valve.
-2
~ 0-6 GI NA C
LJ-R Pen. P49 DHS$
A-M 0338 8
MA LC PAS Ctmt. Isolation valve.
2 05 GI NA C
LJ R Pen. P49.
.DH125 C
n 033C 8
SA LO/C FF o CS 2 FF C DH train cross tie line 2
09
- SC NA O/C RF-Q CS-2 RF-C check valve.
!!! 1 10 2
l
'2rts intorvol 1st Program vol.' 1 Revision 01 VALVE TEST TASLE t'x,E00 EDi$0N COMPANY DAYll Bis $f NUCLEAR POWER PLANT SYSTEM: QtCAY NEAT REMOVAL J
.lvAtvtl car.lowa.u0.lsizei ACt. l Pos. I Coor i C.s. CR l c.s. OR l
cesCRiPr:0=
1 cmc.l
-- l NO.. l & l 8
l & l TYPE l h0AM l Test l a!LitF l ALTE#hAtt l
l l
l l Ct.l c00Ro.lTYPrI &
] & I RrQ. I P Qutsi i test i
i.0tes l
l l
l l
l l FAIL l $R l l
h0.
l PERFORMED l
l l
l l
l l
l POS ]
Op.
l l
l l
l l
DM126 C
M 033C 8
SA C
FF-Q C5 2 FF C OM train cross-tie line 2
D9 CK NA 0/C Rf-Q CS 2 RF-C check valve.
DH127 C
M 0338 8
sA LO/C FF-Q Cs 2 FF C DM train cross *ie line 2
7 11 SC NA 0/C RF-Q CS-2 RF C check valve.
DM128 C
M 0330 sA C
ff-Q Cs 2 FF C DM train cross tle line 2
F 1' -
CK NA O/C RF-Q C$ 2 RF C check valve.
DH830 3
M 033C 8
M0 LC 70-Q DM train cross tie sine 2
D-9 GT Al C/C TC-Q block valve.
P! Y Dn631 8
M 0338 8
M0 LC 70-0 DN train cross tie Line 2
- F-1) '
GT At 0/C TC-Q block valve.
PI Y DN1508 C
'M 0338
.75 x 1 SA C
SR f DM pufp suction line 2
J7 RL NA 0
relief valve.
D:11509 C
M 033C
.75 x 1 SA C
sR.i on p g suction Line 2
H RL NA 0
relief valve.
CH1517 8
M 0335
.12 Mo C
70-Q DH pum suction line 2
G6 GT AI 0/C TC.Q block valve.
PI Y ON1518 8
M-033C 12 Mo C
to-Q OH punp suction iine 2
F3 Cf At 0/C TC-Q block valve.
Pl.Y DH1529 C
M 0338 1.5 x 2 SA C
sR.?
CH p g discharge line 2
D-8 RL NA 0
relief valve.
DH1550 C
M 0338 1.5 x 2 sA C
sR.T DN pump discharge line 2
A-11 RL NA 0
relief valve.
DH2733 B
M 0338 18 Mo LO TC-Q Swsf to DM pump suction
_2 J8 GT At 0/C 70 0 line block valve, P!-Y i
fil-1 10 3 1
2nd Intervat 157 Program vol. I Revision 01 VALvt ifst TABLE Tott00 Edit 0N CCMPANY CAVIS 81511 NUCLEAR power PLAh!
SYSTEM: DECAY WEAT REMOVAL
- jVALVEl CAT.]DWG,No.l SIZE l ACT.] POS. { CODE l C.S. OR l C.S. 04 l
DESCRIPflC4 lCMG.l l No.
l & ]
1 l & l TYPE l h0RM.l TEST l REllEF l ALTERkAf?
]
l l
l l CL.l COORD.l TYPE l 4 l 1 l REQ.{ Rf00E57 l ftSt j
hofE5 l
l l
l l
l l FAIL l S4 l l
No.
l PERFORwED l
l l
l.
[
'l l
l POS.l OP.
l l
l l
l l
On27)4 s
M-033C 18 M0 Lo TC-Q SwSt to DH pum suction 2
H-6 GT At 0/C 10-Q line block valve.
1 PI Y ON2735 A
M 0338 1.5 M0 LC 10-0 C5 5 to-C Aux, spray line Ctet.
1 A4 GT AI 0/C TC 0 CS 5 fC C isolation valve.
LC-R LC R Pen. P74C.
Pl*Y DH2736 A
M 033B 1.5 M0 LC To o ts 5 To C Aux. spray line Ctat.
-2 e5 GL At 0/C TC-Q CS 5 ft C isolation vatve.
LC R LC-R Pen. P74C.
PI Y ON4849 C
M 0338 4x6 5A C
54 f RCS tetdown Line rettef 2
N5 R L' NA 0
valve.
111 1 10 4 l.'
_.. =
, ~,,
2nd Interval lli Program vol. I 9evision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-1 SYSTEM:
DECAY HEAT VALVE (s):
DH11, DH12 CATEGORY:
B CLASS :-
1 FUNCTION:- RCS'to Decay Heat System Isolation Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Exercise and time.
COLD SHUTDOWN TEST
' JUSTIFICATION: These valves isolate the low pressure Decay Heat System from the high pressure-RCS.
They are incerlocked to prevent opening when RCS pressure is greater than 301 psig and automatically close before RCS pressure exceeds 301 psig.
QUARTERLY PARTIAL STROKE TESTING:
N/A COLD SHUTDOWN TESTING:_
Exercise and time.
III-1-10-5
2nd Interval Iti Program vol, I Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-2 SYSTEM:
DECAY HEAT VALVE (s):
DH125, DH126, DH127, DH128 CATEGORY:
C a
CLASS:
2 FUNCTION:
Decay Heat System Train Cross-Connect Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS: Verify forward flow operability.
Verify reverse flow closure.
COLD SHUTDOWN TEST
'[
JUSTIFICATION: In order to verify forward flow operability it is necessary to establish flow through the cross-connect line and to-measure the flow
. rate.
This test would required cross connecting-both essential lines.
In order to verify reverse flow the standby Decay Heat Pump must be isolated.
These test conditions are unanalyzed and would violate T.S.
3.5.2.b.
since both redundant trains would be inoperable.
DH125 and DH126, or DH127 and DH128 will be reverse flow tested in series as one valve since there are no means to individually test these.
QUARTERLY PARTIAL STROKE TESTING:
N/A COLD SHUTDOWN Forward flow operability will be verified TESTING:
at cold shutdown when flow through the cross-connect line can be initiated and the flow rate into the Reactor Coolant System measured.
Reverse flow closure will be verified during cold shutdown when the redundant Decay Heat Pump can be isolated.
III-1-10-6 l
2nd Intervat IST Program vot. I tevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-3 SYSTEM:
DECAY HEAT VALVE (s):
DH76, DH77 CATEGORY:
AC CLASS:
1 FUNCTION:
Decay Heat to Reactor Coolant System Hot Leg Injection Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Verify forward flow operability.
COLD SHUTDOWN TEST JUSTIFICATION: The only possible way to verify full flow operability of these check valves is by using the Decay Heat pumps to inject into tl7' RCS.
During normal operation the Decay Heat pumps cannot overcome RCS operating-pressure.
QUARTERLY PARTIAL STROKE TESTING:
N/A COLD SHUTDOWN These valves will be forward flow operability TESTING:
tested with flow from the Decay Heat pumps.
The design flow rate through each valve will be verified.
III-1-10-7
2rd interval l$f Program vol. I tevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-4 SYSTEM:
DECAY HEAT VALVE (s):
DHlA, DHlB CATEGORY:
B CLASS:
2 FUNCTION:
Decay Heat Pump Discharge to RCS Isolation Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Exercise and time.
COLD SHUTDOWN TEST JUSTIFICATION: During normal operation these valves are aligned to their accident position which is open.
To close these valves for testing purposes unnecessarily places the plant in an unsafe condition.
If these valves did not reopen following testing, it would render that portion of Low Pressure Safety Injection inoperable.
QUARTERLY PARTIAL STROKE TESTING:
N/A COLD SHUTDOWN TESTING:
Exercise and time.
III-1-10-8
9'i -
1
^;3
~
t my
,a 2nd intervat l$f Progree vol; I Revision 01 COLD; SHUTDOWN TEST JUSTIFICATION CS-5
- SYSTEM:.
DECAY HEAT-VALVE (s):
DH2735,:DH2736 e
fCATEGORY:fA;
~ ~
m 1 CLASS:1
'11(DH2735) 2 (DH2736)
. i FUNCTION:-: Decay-. Heat Auxiliary-Spray _Line Isolation Valves.
c 3
'ASME SECTION-XI:
-QUARTERLY TEST-REQUIREMENTS - Exercise and1 time.
-COLDLSHUTDOWN TEST-JUSTIFICATION:iThese valves-~ provide a boundary between the lhigh pressure.RCS and the-low pressure Decay-i Heat System.. There are no design provisions
'to-measurefline pressure-between the two
- valves.
If.-either valve is exercised.and the
- other valve' fails to provide.a leak tight _
- boundary, the~10w pressure Decay Heat System s
could: be overpressurized or if: the inline
- valve:was--inadvertently opened during testing,
' l an' inter-system-loss-of-coolant accident could-E
-occur.
QUARTERLY-:-PARTIAL'
! STROKE 1 TESTING.
- Partialistroke. exercising is precluded
.for-the same reasons astfull-stroke 3+,
=
exercising.
COLDiSHUTDOWN-1 TESTING:.
- Exercisel and -time.-
a O
u, s
i[ '
g'
+4 L-p
.III-1-10-9 h
m n*
b e'
of
,m-c---7 i+
-saa.-y4e ed i-4 e
n-n
-se,-m-
+-u.i-t m3.-+ge'+E 6f-M,*'
--w1eies 7-+7 4
-wv b e+ d*4+
4e4ew 'er
- 8
\\
s 2nd Intervat ist Program vol. I Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-6
' SYSTEM: -
DECAY HEAT VALVE (s) :
DH7A, DH7B CATEGORY:-
B-CLASS:
2 FUNCTION:
BWST Outlet Header Isolation Valves.
'ASME SECTION XI-QUARTERLY TEST
- REQUIREMENT:
Exercise and time.
COLD SHUTDOWN TEST-JUSTIFICATION: -Exercising thesn valves closed during normal operation isolates Borated Water Storage Tank flow path to one train of the High Pressure-Spray, and Makeup Systems. -Blockkng'ntainment Injection, Low Pressure Injection Co the BWST flow path to one train of these four safety-related systems during normal operation.could place the_ plant in-an unanalyzed condition.
~
These systems are required by Technical Specifications and with-closing DH7A or DH7B causes-one train of these systems to be inoperable.
1 4
~ QUARTERLY PARTIAL STROKE TESTING:
Valves full-stroke on initiation and cannot be_ partial-stroke exercised.
. COLD SHUTDOWN-
' TESTING:-
' Exercise and time.
III-1-10-10 l
l l
2nd Intervat lli Program Vol. I tevision 01 4
COLD SHUTDOWN TEST JUSTIFICATION CS-7 SYSTEM:
DECAY HEAT REMOVAL VALVE (s):
DH81, DH82 CATEGORY:
B CLASS:
2
}
FUNCTION:
BWST to DH/LPI pump and Co!ntainment Spray Pumps Suction Line Check Valves ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Verify forward flow operability.
COLD SHUTDOWN TEST JUSTIFICATION: DH81 and DHB2 are suction check valves to both the Decay Heat pump and the Conta.inment Spray pump.
A flow rate of 4300 gpm is required to verify full open.
Total flow requirement is 3000 gpm for the Decay Heat pump and 1300 gpm for the Containment Spray pump.
To obtain 4300 gpm through the check valves both the Decay Heat pump and Containment Spray pump must be run at the same time.
An increased risk for equipment damage or system inoperability may occur due to the complications of multiple pump test lineups and emergency restoration actions.
This abnormal test condition makes both pumps on the same train inoperable.
Partial flow is observed through these check valves for both the Containment Spray pump quarterly test and Decay Heat pump quarterly test.
QUARTERLY PARTIAL STROKE TESTING: Partial forward flow test during the Decay Heat Pump quarterly test.
COLD SHUTDOWN TESTING:
Full forward flow test.
III-1-10~11
t 2rd INerval lli Program Vol. I nev6ston 01 RELIEF REQUEST RV-1 SYSTEM:
DECAY HEAT REMOVAL VALVE (s) :
DH9A, DH9B CATEGORY:
B CLASS:
2 FUNCTION:
Decay Heat /LHI Containment Sump Block Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS: Exercise and time.
BASIG FOR RELIEF: DH9A and DH9B are the emergency sump isolation valves providing suction to the low pressure injection (LPI)/ decay heat (DH) pumps and containment spray (CS) pumps during the recirculation phase following a postulated a loss of coolant accident.
The LPI/DH pump and CS pumps suctions are also connected to the borated water storage tank (BWST) via the normally open BWST isolation valves DH7A and DH7B.
During normal operation, DH9A and DH9B are deenergized in the closed position to address 10 CFR 50 Appendix R fire protection concerns.
DH9A and DH9B are also interlocked with DH7A and DH7B and BWST level.
On low-low BWST level, the interlock permits the operator to open DH9A and DH9B.
Once these valves begin to open the interlock signals DH7A and DH7B to close.
Cycling of DH9A and DH9B to accomplish the required Code testing during-normal plant operation'would require isolation of the BWST, the source of emergency cooling system water, defeating the interlocks to permit opening of DH9A and DH9B, and reenergization of power to DH9A and DH9B contrary to fire protection commitments.
Closure of DH7A and DH7B to isolate the BWST would also place additional reliance on these valves to open on a safety actuation signal should a LOCA occur during this evolution.
This is not the normal plant configuratior, assumed as an initial condition in the safety analysis.
Cycling of DH9A or DH9B would introduce water into the containment emergency sump since the downstream decay heat system-piping is-f:'.1 of water even if the BWST is isolated.
Consequently, DH9A and DH9B can only be tested when blank flanges can be installed in the containment III-1-10-12 l
. - ~.
2rd interval IST Program Vol. I tevision 01 sump upstream of DH9A and DH98 to prevent water from the e
decay heat-piping from flowing into the sump when the valves are opened.
Even at that, the water trapped between the valves and the flanges will drain into the sump when the flanges are removed.
Blank flanges cannot be installed during normal plant operation because the containment emergency sung is inaccessible and installation of a flange would render the affected emergency core cooling train inoperable.
Even during cold -netdown, installation of the flanges, and restoring the sump to operational readiness and filling and-venting drained sections of piping, a significant burden to accomplish during a non presentsrefuelirg outage cold shutdown.
The emergency sump debris screen.4 must be removed.
The sump is a contaminated area.
Removal of the flanges and-draining of the water trap *3d between the flanges and the valves provides addition i
opportunity for personnel contamination.
These factors in combination with the need to defeat interlocks, the pressures of time associated with non-refueling outage cold shutdowns.-and risk associated with potential errors as identified in NRC Information Notice 91-22 Log Number are significant li(abilities 1-2453 dated March 19; 1991) when compared with the minimal benefits of performing
. testing during cold shutdown.
The ASME Code Section XI requirements for testing of
.0H9A and'DH9B have not changed from the 1977 Edition with addenda through summer of 1978, the basis for the first ten year interval IST program.
Nor has the burden associated with testing DH9A and DH9B at cold shutdown.
In the evaluation of the first ten year interval IST program,-the NRC concluded that the benefit to be gained by testing-DH9A and DH9B at cold'chutdown does not warrant the burden and this same relief request for testing during ref".eling was' approved for the first 10-year interval by NRC letter to Toledo Edison dated May la, 1984-(Log Numner 1521).
ALTERNATE
' TESTING:
Exercise and time each refueling.
III-1-10-13
2nd Intervet ist Program Vol. I tevision 01 VALVI Test TABLE TOLEDO EDisoM COMPANY Davis SEsst wuCLEAR POWER PLAtt sYstt42 Dful=ER AtitED WATER I vAtvt l Cat. oWo. no.1 size I Act, i Pos. I Ccet i C.s. on l C.s. on I
cesCalPilou lCac.)
-l me. I sI a
i sl TYPE l noam.1 test I attigt l AtteauAtt i
s l
l l
l Ct. I Ceono. l TYPt I a i a t sto. I stoutst I test l
worts l
l l
l l
l l FAlt I s a 1 i
wo.
I Pteroaato l
l l
l l
l 1
I PCs. l OP.
l l
l l
l l
CV2643 s
M 036A 1
A0 0/C TC-0 DW make s to CCW surge 3
Call CL C
C FC 0 fank line isolation PI Y volve.
DW6&31A - A M-010C 4
A3 0
tC o DW s e ty line Ctat.
2 K.5 Gt C
C FC 9 isolation valve.
LJ R PI Y DW68316 A
M 010C 4
A0 0
TC c CW s a ty Line Ctat.
2 K4 Gt C
C FC-Q isolation valve.
LJ R PI Y 111-1 11-1 l
i 2nd Intervst ist Program Vol. I Revision 01 I
VALVE TEST TA8LE TOLED0 EDISCN CCMPANY DAVIS BESSE NUCLEAR POWER PLANT SYSTEM: DIESEL CENERATOR AIR START l VALVE l CA1.lDWG.No.l SIZE l ACT.l PCs. l CODE l C. S. OR l
- .$. OR l
DESCRIPfl0N lCMG.l l No. l & l l 4 l TYPE l NORM.l TEST l RELIEF l ALTERNAff l
l l
j l CL, l C00RD. l TYPE l 8 l 8 l REO.l REQUEST l TE$f l
NofE5 l
l l
l l
l l Fall l $R l l
NO.
l PERFORMED l
l l
l l
l l
l P05.l OP.
l l
l l
l l
042 C
M 0178 1.5 5A C
RF-Q Reley air valve relief J CC C
flow path for DA63.
DA3 C
M 0178 1.5 SA C
RF.o Rete air valve relief G 10 CK C
flow path for DA62.
DA10 C
M 0178 1.5 sA C
RF o Relay air valve relief E 10 CK C
flow path for 0461 0411 C
M 0178 1.5 SA C
RF-Q Reley air valve relief C-10 CK C
flow path for DA60.
DA24 C
M 0178
. 75 SA 0/C RF-Q DG sir start compressor 1
3 C5 CK NA C
to air receiver tank line check valve.
DA25 C
M-0178
. 75 SA 0/C RF-Q DG air start compressor 3
G5 CK NA C
to air receiver tank line check valve.
DA38 C
M 0178 75 SA O/C RF-Q DG air start compressor 3
E-5 CK NA C
to air receiver tant line check valve.
DA39 C
M 0178
. 75 5A 0/C RF-Q DG air start compressor 3 --
J-$
' TK NA C
to air receiver tank line check vetve.
DA1135 C
M 0178
. 75 x.75 sA C
sR.T Air start receiver tank 3
C6 RL NA 0
retlef valve.
DA1138 C
M 0178
.75X.75 - SA C
SR T Air start ree?'ver tank 3
D*6 RL NA 0
relief valve.
041141 C
M 0178
. 75 x. 75 SA C
SR.T Air start receiver tank 3
G6 RL NA 0
retlef valve.
DA1144 C
M 0178
. 75x. 75 SA C
sR.T Air start receiver tank 3
M6 RL NA 0
relief valve.
50 C
70 0 RV-1 S0-0 DG air start line JA1147A 5
M 0178 D-10 Gi C.
O solenoid valve.
111 1-12 1
2rd let0rv01 lit Program Vol. I tevision 01 VALVI illt hhl 10ttD0 (DlWw Cte* ANY DAvil+Billt WUCLI AR PCWit PL Ah!
Sf$ttut 9,((1[ U tkitatC1 Alt Stott lVALVIl CA1.lDWG.h0.lll!!l ACf.l POS.l CIE l C. E. (*
l C. S. On l
tticattt!Ou lCwc.l l
40.
l & l 8
l 4 l TYPtl kDem. l Illtj ttLill l AltithAll l
l l
l l CL.l C00RD.lffPtl L
l &
l tie.l ttout ti l ttst l
h0fts l
l l
l l
l l FAllj 1*t l
l ko.
l llif0tutD l
l l
l l
l l
1 Pos. l OP.
l l
l l
l l
k
$0 C
10 0 kV 1
$3 0 DG elr start line 0411479 8
N 0173 t 10 Gt C
0 solenoid velve.
to C
10 0 tv 1
$0 0 DG eir start line
~
CA1148A 3
u 0178 m 10 C1 C
0 totenoid velve.
$0 C
10 0 av.1 50 0 DC ele start (Ine CA11488 B
M 0178
=*
c J 10 Gt C
0 setenoid valve.
-l 111 1 12 2 l
)
1 i
Y fnd Interval 181 Program vol, I tevtston 01 RELIEF REQUEST RV-1 SYSTEMt DIESEL GENERATOR AIR START VALVEt.
DA1147A, DAll47B, DA1148A, DA1148B CATEGORY:
B 1
CLASS:
FUNCTICN '
Diesel Generator Air Start Solenoid Valves.
1 ASME-SECTION-XI QUARTERLY TEST REQUIREMENTSt-Measure stroke time.
BASIS'FOR RELIEF.
These are three-way solenoid valves mounted on the Diesel Generator (DG) skid mounted package.
They are in the DG air start line between the Air Receiver Tanks and the Air Start Manifolds.
Since each generator has two tanks and two manifolds, the DG may start on air supplied by either;or both tanks.- The diesel generator test procedure verifies operability of each of these valves independently _on an alternating basis by isolating-one air start header and starting the DG from one header at a time.
Strokentime~cannot be measured because there are no position indicators and visual observation is not'possible due?torvalve" design.
The DG start test is' performed more frequently than required by Section XI so that actual valve testing criteria-it more limiting
- .7, than Section XI_ requirements.
ALTERNATE TESTING:
These valvos.will be tested as:part of the diesel generator air start-test.-
Diesel generator' starting will be used to' verity-valve' operability.
s
~
III-l'12-3 4
i a
m 4
4
(
4-yWe y-ywby py w w-r wg ry e e ' y
,sy g - age t-
-*M T
?7PTP-T'*"
49t*-*'**"T'**-W"-f*W "t*T'WFT'T'TT'W "T*'W-T -
Sk'v'N'T
-*T*FWT*t
$"'9-'T' T
PWT
- P#~7-' ' * * *Y'
2rd Interval lli Program Vol. I levision 01 VALVE ftsf TABLt 10LtD0 (DISON COMPANY cavil 8(t$t NUCLEAR PG4R PLAuf ist$ttM FitDWAftt l VALVE l CAT.l OWG. NO.l SIZE l ACf. l P05.l CODIl C.S. OR l C.S. OR l
Ot$CalPfl0N lCMG.l l
WO.
l 8 l l 8 j ffPE l N004.] filfl ttLitF l ALittuAft l
l l
l l CL.l COORD. l TYPE l 4 l &
j lie.l tt0UClf l filf l
toits l
l l
l l
l l FAIL l $t l l
Wo.
l PitFORMED l
l l
l l
l l
l POS.l OP, l
l l
l l
l FW167 C
M 0073 18 EA 0
- F 0 Cl 1 Af C FW Line check velve.
t*11 CK NA C
FW1$6 t'
M 0073 18 SA 0
nF 0 C'*1 IF C FW line check velve.
t3 CK NA C
+
FW601 3
M 0073 18 M0 O
TC 0 CS 2 TC C FW Ctat. Isoletion volve.
2 E2 Gt Al C
PI f FW612 8
M 0073 18 M0 O
TC 0 Cl 2 fC C FW Ctat. Isoletion velve.
2 E 12 GT Al C
Pl f
$P6A B
- T7I 16 A0 0
'it 0 CS 2 TC C FW to $G main flow
+4 Au C
C PI f control velve.
SP68 8
M 0078 16 A0 0
IC 4 Ct.2 TC.C FW to SG main flow E9 AM C
C Pl.f control volve.
$PTA B
M 0073 6
A0 0
TC 4 CS 3 TC C FW to 50 line start e M4 GL C
C PI f flew control velve.
$PTB B
M 0075 6
A0 0
TC 0 Cs 3 TC C FW to $4 lite start e N9 GL C
C Pl f flow control valve.
Ill 1 13 1
tre intervet ist prose n vot I Revillon 01 COLD SHUTDOWN TEST JUSTIFICATION CS-1 SYSTEMt FEEDWATER
. VALVE (s):
FW147, FW156 CATEGORY:
C CLASS:
FUNCTION:
Feedwater to Steam Generator Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify reverse flow closure.
COLD SHUTDOWN TEST JUSTIFICATION: Verification of reverse flow closure requires termination of feedwater flow to the associated steam generator.
Termination of feedwater flow to.a steam generator during normal operation is not possible.
QUARTERLY PARTIAL STROKE TESTINGt N/t COLD SHUTDOWN TESTING:
Verify reverse flow closure.
Y 1
TII-1-13-2 i
1 2rd Interval l$f Program Vol. l Revision 01 COLD SHUTDOWN TEST JUSTIFICATION l
i CS-2 SYSTEHf FEEDWATER j
VALVE (s)t FW601, FW612, SP6A, SP6B CATEGORY:
B (SP6A, SP6B)
CLASSI 2 (FW601, FW612)
FUNCTION:
Feedwater cc.ntainment Isolation (FW601, FW612) and Main Cantrol (SP6A, SP6B) valves.
I ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Exercise and time (FW601, FW612)
Exercise, time and fail (SP6A, SP6B)
COLD SHUTDOWN TEST JUSTIFICATION: Exercising these valves closed during normal operation would result in a loss of feedwater to the associated Steam Generator.
Isolation of Feedwater flow during normal operation is not possible.
QUARTERLY PARTIAL STROKE TESTING:
Valves full stroke on initiation and cannot be partial-stroke exercised.
COLD SHUTDOWN TESTING:
Exercise and time (FW601, FW612).
Exercise and time (SP6A, SP6B).
III-1-13-3 i
i l
I a-
-wt-'
g e
4 1'h-em-M rer.wev.,
,=-e*mer 4meen rw r-rv M
-+pr
<-e
'-+-,-t---M'----
+
'u r-g 7->r-9-rg-;r--ywWr-d u
2rd intervet 181 Program Vol. I tevision 01 COLD SHUTDOPN TEST JUSTIFICATION CS-3 SYSTEM FEEDWATER VALVE (s) :
SP7A, SP7B CATEGORYt.
B CLASSt FUNCTION:
Feedwater to Steam Generator Startup Control Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Exercise,. u..
and fail.
COLD SHUTDOWN TEST JUSTIFICATION: These valt.V ete e. M ytved open during normal operation % gn b'-Matur flow is above 15% of unit full load.
4xercising the valves closed at unit loads abreve 15%. causes a system operating transiunt which could result in a
-forced plant shu.down.
QUARTERLY PARTIAL STROKE TESTINGt. Valves full stroke closs on safety initiation and cannot be partial-stroke exercised.
COLD SHUTDOWN TESTING Exercise and time.
III-1-13-4
.i
2rts lotorvat 151 Program vol. I tevision 01 bALV( fit! TABLE toitp0 E0ilDb COMPAt:Y DAvil Bilst wuCLtat Po.ift PLAki
$flitMs tatt1't D AD10ACflVf Watti lVALVIl CAT. l DWQ. 40. l Sllt j ACf.l Pol.l COCE l C.S. OR l C.$. 04 l
OtStaletION lCMG.I l WO.
l 4 l l & l TYPE l 40tN.} 1t51 l AttitF l ALitth4ft l
l l
l l CL.l C00RD.lffPtl 8 l 4 l Rio.l tt0Vist l TElf l
hotti l
l l
l l
l l Fall l SA l l
hD.
j PitFDAMED l
l l
l l
l l
l PO$.l OP.
l l
l l
l l
WC1823 M 038B 1
A0 0/C 1C 0 WG Decay tank inlet 3
t 10.
CA C
C F r. 0 line isolation valve.
Pl 1 WG1824 5
M 0384 1
A0 0/C TC 0 WG Decay fank intet 3
E9 CA C
C fC 9 line isolation valve, Pl f itG1825 9
M.038B 1
A0 0/C TC-Q WG Decay tank intet 3
tali DA C
C FC 0 line teotation valve.
Pj f WG1826 B
M 0180 1
A0 0/C tc.d WG Decay fank intet 3
f.12
. CA C
C FC 0 line isolation valve.
Pl.Y WG1827 I
M 0388 i
A0 0/C TC 0 WG Decar Tank inlet 3
1 13 DA C
C FC 0 line isolation valve.
Pl+f WG1b28 8
M 0388 1
A0 0/C TC 0 WG Decay tank inlet 3
(*14 CA C
C FC 0 line isolation valve.
Pl Y WG1829 C
M 0388 1.5x2
$A C
SR f WG Decay Tank relief 3
t 10 RL NA 0
valve.
WG1831' C
M 0388 1.5X2 5A C
st T WG Deay tank rettef 3
t 11 RL NA 0
valva.
WG1833 C
M 0388 1.$x2 SA C
sa f -
WG Decay tank retlef 3
(*13 RL hA 0
salve.
WG181s 8
M 038C 1
- A0 0/C 1C.0 WG Decay tank outlet 3
02 DA C
C FC 0 line foolation valve.
- PI V WC1836 8
M 035C - 1 A0 0/C TC.0 WG Decay tank outlet 3
G3-DA C
C FC 0 line isolation valve.
PI i 111 1 14 1
2rus Intervet lli Program vol, I tevisitun 01 VALVi 1111 1ABLE fotfD0 (DISON COMPANY DAVil Still WUCit At Powlt PLANT Silf!N Calf 001 eADICJtifvt WAlft lVALVtl CAT.lDWG.h0.lSittl ACf.l P05.l C00fj C.S. De l C,$. De l
DttCalPfl04 lCMG.)
l NO.
l 4 l l & l 1YPEl h084.l filfl a!Litt l ALilahaft l
l l
l l CL. l COORD.1TVPtl 4 l & l et0.l AIQuilf l ftli l
notts l
l l
l l
l l fall l SR l l
h0.
l Pfaf0eMED l
l l
l l
l l
l P05.l OP.
l l
l l
l l
wc1837 8
M 038C 1
A0 0/C TC+Q WG Decay tank outlet
-3 C4 CA C
C FC-Q tine isolation volve.
Pl.Y WC1838 s
M 038C i
A0 0/C TC 0 WG Decey fan 6 outlet 3
G5 DA C
C fC 9 line isoattion velve.
PI f WG1839 8
M 038C 1
A0 0/C TC 0 WG Decay fant outlet 3
G6 DA C
C (C+0 line toolation valve, Pl Y WG1840 B
N 038C 1
A0 0/C TC-Q WG Decay fant outlet 3
G.T DA C
C FC-Q tine isolation volve.
Pl Y I
111*1 14 2
-n
2nd Interval ist Program vol. I Revision 01 VALyt 14$1 TABLE TOLIDO LDISON CCMPANY Cavil Sttst wuCLEAR Powit PLAuf
$v$ttui HICH Pettstet IWJEct10![
j i
I jVALVtl CAT.l DWG, WO. l $12t l ACT.l POS.l C00tl C.$. OR l C.S. OR l
DESCRIPflow lCkG.l l NO.
l 4 l l & l ffPtl kOPM.l fill l Attl[F l AltfRhAft l
l l
l l CL. l COORD. l TYPE l
& l & { Rta.l Rtoutli j filf l
hofft l
l l
l l
l l FAIL l SR l l
No.
l PERFORMto l
l l
l 1
1 I
1 Pos. I OP.
I I
I I
i 1
NP2A B
M 033A 2.5 M0 C
70 0 HPl to RCs injection Line 2
E3 CL At 0/C TC 0 isolation valve.
P! Y HP28 5
M 033A 2.5 MO C
10 0 HPt to RCl injection Line 2
f3 GL At 0/C TC-Q isolation volve.
1 PI Y NP2C 9
M 033A 2.5 MO C
10 0 NPI to RCS telection line 2
M3 CL Al C/C TC 0 isolation valve.
Pl*V HP2D B
M 033A 2.5 MO C
70 0 MPI to RC5 injection line 2
J3 GL Al C/C TC 0 isolation valve, PI Y HP10 C
m 033A 6
SA 0/C fr 0 Rv 2 POR Bw$1 to HPl pg suction 2
H9 CK h4 0/C RF-Q CS 1 RF C line check valve.
HP11 C
M 033A 6
1A O/C 77 0 RV 2 POR sws1 to MPI pg suction 2
E 11 CK h4 0/C RF 9 C$ 1 RF C L ine check valve.
HP22 C
M 033A 4
54 C
F7 0 Rv 2 Pct MPI pg discharge Line 2
p6 CK NA 0
check velve.
NP23 C
M 033A' A
$A C
FF 0 RV 2 PCR HPl prp discharge line 2
E6 CK NA 0
check volve.
MP31 BC M 033A 1.5 5A LO/C FF 0 HPl p g mln. flow line 2.
06 5C Mo 0/C TC 0 stop check valve.
SA Lo/C FF 0 HPI pro min. flow line l
2 K6
$C MO 0/C TC-Q stop check valve.
Pl Y HP33 C
M 033A 3
5A C
FF-Q MPI pro min, flow line lx 2
06 CK NA 0
check velve.
l MP48' C
M 033A 2.5 SA LD/C FF 0 RV 1 FF.R NP!/Mu p g feed a bleed 1
M*2
$C h4 0
to RC$ injection Line manuel stop check estve.
111 1 15 1
2nd Intervet ilt Program vol. I tevtston 01 Valvt 1[$1 1Att!
tdt (D0 (Di$0W CCMPANY CeVil 6tl$t WVCitat POWit PLANT
$YlfEM: El1W Pittsvet INJftflog lVAlvtl cat.lDwG.ko.l$12tl ACf.j P01.l Ctt! l C.s. 02 l C.S. OR l
CEtCalPilom lCuG.l l
WO.
l & l l 4 l TYPt l h0AM.) ttlil Attiti l AlttthAft l
l l
l l CL.l COORD.ltyttl &
l 4 l tro.l ttDutst l ttst j
hotts l
l
.l l
l l
l Fall l 84 l l
h0.
l Pitf0kMID l
l l
l l
l l
l #05. I OP.
I l
l I
I I
MP69 C.
M 033A 2.$
SA LO/C Ff 0 tv 1 77 t MPI/Mu ptro feed & bleed 1
J.2 SC h4 0
to AC5 infection Line manuel st 9 check vetve.
MP$0 C
M 033A 2.$
SA C
77 0 tv 1 ff t MPl/Mu pump feed & bleed 1
M2' C(
h4 O/C to 805 injection line check valve.
MPS1 C
M 033A 2.5-SA C
ff 0 tv.1 iF 4 MPI/Mu pt.rp feod & btend 1
JZ CC
-hA 0
to RC$ injection line check valve.
NP56 C
M 033A 2.5 5A LO/C ff.0 av 1 Pot NPliMu puv feed & bleed 1
f.2 SC h4 0
to RCS inj. Line manuel stop check velve, Part stroke tested quarterly by normat makeup flow.
HP$7-C M 033A 2.5 5A to/0 FF 0 kv 1 FF 8 NPl/Mu ptre feed & bleed 1
(*2
$C NA 0
to its inj. Line manuel stop cP :n velve.
8:
HP58 C
M 033A ' 2.$
5A C
et-Q tv 1 Pot npt/Mu pump feed & bleed 1
F.2 CK ha o
to RCS injection line check valve. Port stroke tested quarterly by normat makeup flow.
NP$9 C
M 033A 2.5 1A 0
FF-0 av 1 fr t NPl/Mu pro feed & bleed 1
(+2 CK NA 0
to RC$ in). tine manuel stop check volve.
HP102 C
M 033A
.5 5A 0/C FF 0 HPI 1 AC tube ott prp 3
C1 CE '
kA 0/C RF-Q discharge volve.
MP10$
C M 033A
.5 ~
SA 0/C Ff 0 HPI 2 AC Lube eli pwp 3
.B2 CK kA 0/C _ R7 0 discher9e valve.
hP202 C
M 033A SA 0/C tr G r.Pl 1 DC tubc ont pep 3
C1 Cr hA 0/C RF 0 discheroe volve.
111 1 1$ 2
2rms intervat Ilf Program vol. I teritton 01 v4 Lyt 1811 1ABLt 10LtDO EDISDN CCmFAhf DAvil Bilit WVCLtaa POWit PLAki
$1&ftMt PlGW PPES$Utt INJEC QQ3 l VALVE l CAT.lDWG.h0.lll![ l ACT.l P05. l Cott l C.$. ca l C.S. ca l
ct$talPtton l Cg l l
NO.
l & l l & l 146 l Wo&M.l tt$f l #[L!tf l AtttthAf[
l
)
l l
l CL. l COORD.lf7Ptl 8 l &
{ ktQ. l t[Qutit l Illi l
h01tl l
l l
l l
l l Fall l $*R l
l k0.
l Pt8FotMt0 l
l l
1 I
I I
l P05. I c*.
I I
I I
I I
MP205 c
M 0334
.5 SA c/C ff 0 kP1 2 DC tute et L prp 3
82 CK kA 0/C 87 0 discharge valve.
HP1510 C
M 03$A 1.5x1.5 SA C
sa.1 api pro swetion line 2
n.8 RL h4 0
reitef valve, HP1511 C
M 0334 1.581.5 5A C
sa.1 po l prp suc t i on l i ne 2
f8 RL h4 0
relief talve.
111 1 15 3
2rd Irsterval lif Pro 0'** Vol I tevision 01 COLD SifUTDOWN TEST JUSTIFICATIO!!
CS-1 SYSTEM:
IIIGil PRESSURE I!!JECTIOli VALVE (s):
HP10, !!P11 CATEGORY:
C CLASS:
2 FUl4CTIOlit flPI Pump Inlet Line Check Valves.
ASME SECTIOli XI QUARTERLY Tr.ST REQUIREMENTS:
Verify reverse flow closure.
COLD SilUTDOWN TEST JUSTIFICATIOll To verify reverso flow closure requires isolation of one Borated Water Storage Tank header.
Isolation of a Borated Water Storage Tank header isolates the normal flow paths to one loop of the liigh Pressure Injection, Decay Heat, Makeup, and Containment spray Systems The extended period of time required for system isolation and testing would violate Technical Specification 3.5.2 action statements.
QUARTERLY PARTIAL STROKE TESTIliG N/A COLD SHUTDOWii TESTI!1G Verify reverse flow closure.
III-1-15-4
2rd iritervsl l$f Program vol. I nevision 01 RELIEF REQUEST RV-1 SYSTEM:
IIIGH PRESSURE INJECTION VALVE (s):
HP48, HP49, !!P50, it P 51, !!P 5 6, ilP57, HP58, ilP59 CATEGORY:
C CLASS:
1 FUNCTION:
!!PI to RCS Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Verify forward flow operability.
BASIS FOR RELIEF:
Verification of forward flow operability can only be performed by injecting HPI pump flow directly into the Reactor Coolant System.
The llPI pumps have insufficient head to overcome normal RCS operating pressure for a full or partial flow test.
Verification of full design flow rate cannot be done at cold shutdown due to back pressure from the RCS and potential for low temperature over-pressurization of the RCS.
Verification of full flow operability can only be done at refueling with the RCS depressurized.
ALTERNATE TESTING:
Forward flow operability will be verified by full flow testing at refueling.
HPS6 and HP58, normal makeup injection line will be partial forward rlow tested each quarter.
III-1-15-5
2nd intervat ist Prottwo Vol. I levision 01 RELIEF REQUEST RV-2 SYSTEM:
HIGH PRESSURE INJECTION VALVE (S) :
HP10, HPil, HP22, HP23 CATEGORY:
C CLASS 2
FUNCTION:
High Pressure Injection Pump Suction and Discharge Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS Verify forward flow operability.
BASIS FOR RELIEFt The-only possible way to verify forward flow operability during normal operation is by flow measurement during quarterly pump testing through an flow orificed,-
three-inch pump test recirculation line back to the Borated Water Storage Tank.
The pump test flow rate is approximately 290 gpm.
The design accident flow rate for these valves is approximately 600 gpm.
the only flow path that can be used to perform a full flow test would inject HPI pump flow directly into the Reactor Coolant System.
Full flow testing can only be done at refueling (see RV-1).-
ALTERNATE TESTING:
The valves will be partial forward flow operability verified-quarterly during pump testing and full forward flow tested at refueling with the RCS depressurized, s
III-1-15-6
trd Intervel lif Progema Vol. I levision 01 VALVE fflf TABLE 10ttDo (0llow C n#Auf Cavil lillt WUCLEAR Powit PLA47 STlftp ty,4,c.e ANalf t. #UEL usu0tlet & acctll couteot atta l VALVE l CA1.l OWQ. No.l l!!! l ACf. l Pol. l CCCI l C.S. OR j C.$. 08 l
tilC#lPfl0W lCuG.l l ko. l & l l & l fvPE l WORN.) ftlil ttL!!F l AlfithAft l
]
]
l l CL.l COORD. l ffPt l & l &
l tie.l ttoutti l fist l
hofft l
l l
l l
l l FAIL l $t l l
Wo.
l Pte FoeptD l
l l
l l
l l
l Pol ]
OP.
l l
l l
l l
NV$439 8
M*0288 12 mo o
TC 4 uvaC isolation velvr.
3 m.$
87 Al C
PI Y Wy3440 0
M 0288 36 No o
TC 0 MV4C lg)l$ tion valve.
3 N$
BF Al C
Pl Y WV5441 M*0288 20 M0 0
1C 0 Mv4C isolation valve.
3 M*6 SF Al C
Pl*T Mv5442 B
M 0288 20 mo 0
fC 0 Hv&C isolation velve.
3 M7 BF At C
Pl*Y i
l l
til 1*16 1
- ~ _.,
_. ~ _ -. _ _ _ _
1 2nd Interval llt Progres Vol. 1 tevision 01 VALVI filf TABLE 70ttD0 (Di$on COM*Auf CAVIS bf tt! WUCLIAR PCMt PLAbf Stif tMs !Nitetssfut att l VALVf l CAT. l CWG. 40. l Sllt l ACf.l PO$.l CCEI l C.S. OR l C.$. OR l
OtSCtlPfl0N lCMG.l l
NO.
l & l l & l ffPt l 40tm.l filfl ttLitF l ALitthaft l
l l
l l CL.l COORD.lffPtl 4 j &
l tto. l tt0Utst l ffsf l
=0fts l
l l
l l
l l Fall l $t l l
No.
l Pit FC8Mt0 l
l l
l l
l l
l Pos.l OP.
l l
l l
l l
l lA501 AC u 015A 1
SA 0
- F.0 ty.1 SF.A 14 to Ctat, isolatice 2
F*3 CK un C
LJ+R LJ t valve.
IA2011 A
m 015A T
A0 0
F2 GT C
C FC 0 valve.
LJ t Pl*Y i
Ill 11T 1 t
l l.
l
2nd Intervat ist progran voi, i eevision et RELIEF REQUEST RV-1 SYSTEM:
INSTRUMENT AIR VALVE (s):
IA501 l
CATEGORY:
]
CLASS 2
TUNCTIONt Instrument Air Supply Containment Isolation Check Valve.
i ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify reverse-flow closure.
BASIS FOR RELIEF The only method available to verify reverse-flow closure is by valve leak testing during Appendix J, Type C, testing.at refueling.
ALTERNATE TESTING:
Reverse-flow closure will be verified during Appendix J, Type C, testing at refueling.
III-1-17-2
'i y
e-<
- ew.p
i frd interval 151 Progrwa vot. I tevision 01 WAlvt f($1 1ABLE 10Ltbo (OttCW COMrAhY r
Davis Stitt WuCLt At PCWit PLAht
$t$1(Mt Malu titAM 4...................
l VALyt l CA1.lDWG.h0.lS1!!l ACf.l Pos.l C00t l C.5. 04 l C.S. De l
DiscalPfl04 lChG.l j No. l 1l l & j ttPtl NoeM.l 1811 j ttLitt j AlttRNAft l
l l
l l Ct.l C00a0.lffPt] & l & 1 tio. l Itauf51 l ttli l
Notti l
l l
l l
l l Fall l St l l
NO.
l Pit f otut0 l
l l
1 l
l l
1 P05. I CP-I i
l 1
I I
I Cl11 A.
9 M 007A 8
A0 C
f0 0 C$ 2 to C M5 atmosserte vent C7 AW C
0/C 1C 0 C$ 2 1C C volve.
IC-Q Cs 2 FC C Pl s IC$110 B
M 0078 8
A0 C
10 0 C$ 2 10 C
>$ etmospheric vent 2
C9 AW C
0/c tC-Q Cl 2 TC+C valve.
CC 0 CS 2 IC C PI V MS100 BC ta 003A 36 A0 0
1C-Q C$n TC C MS isoletion volve.
2 F7 SC SA C
M 003A 2
A0 C
TC-Q Cs 7 tC-C Ms isolation volve bypass 2
F7 CL C
C FC-Q CS 7 FC C line isolation vatyc.
PI f M5101 8C M 003A 36 A0 0
1C 0 Cs 5 es C
>$ isolation valve.
2 C7 SC SA C
'Ml101 1 3
M 003A 2
Ao C
TC 9 Cs.7 tC C Ms isoletion volve bypass 2
C7 GL C
C PC 0 C5 7 FC C tine taotation volve.
Pl Y M1104 -
8 M 003C 6
M0 C
10 0 Mt to A7W turbine line 2 =-
t5 GT At 0/C TC-Q block volve.
Pl f M5106A B
M 003C 6
M0 O
TC 0 MS so l'W tv bine 2
F6 Gt At 0/C T0 0 cross d e line block PI V volve.
i M5107 B
M 003C 6
M0 C
10 0 MS to AFW turbine line l
2 -'
.t9 GT At 0/C 1C 0 btock.*stve.
I. -
Pl*f M5107A B
M 003C 6
M0 O
TC 0 Mt to AfW turbine 2
F8 GT Al 0/C 10 0 cross tie line block l
Pl Y.
volve.
Ill 1 18 1
_ ~ - -
2rd Intervat l$1 Protese Vol. I tevisite 01 v&Lvt itst TAstr 10 LIDO IDi$0W COMPAbf CAVI$-8ttli WUCLEAR POWit PLAht
$Ylftus MA!w titAM l VAWE l cat.l C'WG. WD.l $1!1 l Act.l POS.l COL E l C.S. Of l C.$. OR l
CISCtlPfl04 lCaG.{
l WO.
l 4 l l & l tYPt l WDRM.l tilt] AtLitt l Attifhaft l
l l
l l CL.l CCotD.[Tittl &
l & J ato. l troutSt l tilt l
Nettl l
l l
l l
l l FAIL l lt l l
h0.
l PitPCD ED l
l l
l l
l l
l Pos. I OP.
l l
l l
1 I
MS209 C
M 003A 36 SA 0
- F 0 Cl 1
- F C Ms non return check F6 CK hA C
valve.
Mll10 C
M 003A 36 5A 0
RF 0 Cl 1 af C M5 non return check C.6 CE 4A C
valve.
Ms375 B
M 003A 1.5 Ao C
TC 0 CS 4 TC C Ms trap warnup drain 2
0 10 GT C
C PC 0 Cl 4 FC C tine isolation valve.
Pl Y m1394 8
M 003A 1.5 A0 C
TC 0 Cl 4 1C C Ms trap.ame drain 2
0 10 Gt C
C PC 9 CS 4
- C C line isolation valve.
P! Y M1603 3
M 0075 4
Mo C
TC 0 Cl 6 1C C SG blowdown line 2
M1 GT Al C
Pl.Y isolation valve.
M5611 8
M 007B 4
M0 C
TC 9 CS 6 TC C SG blowdown line 2-M.12 GT Al C
PI t isolation valve.
M5726 C
M 003C 6
SA C
F.$
CK NA 0/C RF 0 GL 1 QM line check valve.
M$727 C
M 003C
-6
$A C
F9 CK hA O/C RF-Q GL 1 RM line check valve.
M5734 C
M 003C 6
5A C
F.5 CE NA 0/C RF 0 CS 3 RF C cross tie line check valve.
MST35 c.
M 003C 6
$A C
FF-Q Ms to AFW pwp turbine 3
F9 CK h4 0/C RF 0 Cs 3 RF C cross.tte Line check valve.
Ms58894 s
M 003C 4
A0 C
10 0 AFW pwp turbine steam 3
G.4 GT 0
0 70 0 aamission valve.
Pl Y Ms58898 5
M 003c 4
A0 C
70 0 AFW pwp turbine steam 3
G9 GT C
0 F0 0 admission valve.
PI V
!!! 1 18 2
fral Intervol 15f Program vol. I tevision 01 VAlvt till TABLt 1
tottDO [Di$0N COMPANY JAvil 8tllt WUCLEA8 PO.tk PLAht
$YlttM: MatW titAM lVALVfl CA1.lOWG.h0.l$128l ACf.l POS.j C00tl C.S. 02 l C.$. OR l
CtlCRIPfl0N lCpC.l l Wo.
l 4 l l & l TVPtl h0aM.l tttil AttitF l ALillhaft l
l l
l l CL.l C00aD.ltvPtl &
l &
l Rio.l ttoutst l ttsi l
hotts l
l l
l l
l l fall l 58 l l
a0.
l Pit 60AMED l
l l
l l
l 1
i Pos. 1 07 I I
I I
l l
i SP17At C
M 007A 6x6
$A C
$4 1 Ms safety retief valve.
2 A*7 RL hA 0
SPl7A2 C
M 007A 6x6 sA C
52 1 M5 safe *y relief valve.
2 B+7 RL NA 0
$P17A3 C
M 007A 6s6
$A t
St+1 M$ safety relief valve, 2
05 RL NA 0
- e'?A4 C
M 007A 6x6 5A C
52 1 M$ saf ety ret tet valve.
2 A*6
- RL h4 0
$P17A5 C
M 007A 6x6 SA C
SR f MS safety relief valve.
2 B.6 tL NA 0
P
$P17A6 C
M 007A 6x6
$A C
staf M$ safety rollet valve.
2 A6 RL hA 0
-SP17A7 C
M 007A 6xe (A
C 52 1 Mt safety retlef valve.
2 06 RL NA -
0 SP17A8 C
M 007A 6x6 SA C
52 1 M5 safety relief valve.
2 05 RL NA 0
SP17A9 C
M 007A 6x6. SA C
st 1 Ms safety relief valve.
2 A5 RL.
hA 0
SP1781 C
M 007A 6x6
$A C
$R f M1 safety relief valve.
2 A9 RL NA 0
$P1752 C
M 007A 6x6 la C
st f MS safety relief valve.
2 89 RL NA 0
SP1783
.C M 007A 6*6 54 C
$4 1 MS safety rettef valve.
2 0 10 at.
h4 0
SP1784 -
C M 007A 6x6
$A C
$2 1 M$ safety rettet valve.
2 A*10 RL hA 0
SP1785 C
M 007A 6x6 SA C
.st.1 Ms safety retlef valve.
2 89 RL kA
-O 111+1 18 3
2rto Interval 151 Program Vol. I tevtston 01 VALVE It$1 1ABLE 10' tD0 (D i f,04 COMP Au f CAvl$. Bit $t WUCLIAR POWit PLAh!
$Y$ttNi MAlW Sff'A4 I
lVAlvti CAT.l M. 40. l $12E l ' ACf. l Pos. ) GCCI l C.S. ot l C.S. On l
CE $Ca t Pf lDN lCMG.l l k3.
& l 1
l 4 l ffPtj h044.j ft$1 l ttLitt l ALitthAtt l
l j
l l CL. l COORD. l f f PE l &
l & l #EQ.l RIQUl$f l Itst l
woft$
l l
l l
l l
l Fall l $.t l l
No.
l PitfotMID l
l l
l
.l l
j l PO$. l OP.
l l
l l
l l
$P1TI6 C
M.007A 6X6
$A C
$2 1 M5 safety retlef valve.
2 A.9 RL h4 0
$P17p?
C M.007A 6X6
$A C
St.1 M5 safety rettef valve.
2 89 RL h4 0
t
$P1788 C
M.007A 6X6
$A C
$2 1 M$ safety relief valve.
2 0+10 AL NA 0
$P1799 C
M.007A 6X6
$A C
$4 1 M$ safety rettef valve.
2 A.10 AL hA 0
V r
i t
l l
111 1-18 4 l
2rd Intervat llt Progree vol. I Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-2 SYSTEM MAIN STEAM VALVE (s):
iCS11A, ICS11B CATEGORY:
D CLASS:
2 FUNCTION:
Main Steam Atmospheric Vent Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Exercise, time, and fail.
COLD SHUTDOWN TEST JUSTIFICATION: Exercising these valves during normal operation would cause a decrease in main steam line pressure and would cause a pressure transient.
Failure in an ooen position would result in.a plant shutdown due to a mismatch between feedwater P.nd main Pteam flow.
QUARTERLY PARTIAL STROKE TESTING:
N/A COLD SHUTDOWN TESTING:
Exercise, time, and fail.
III-1-18-6
2nd Interval 111 Program vol, I tevision 01 COLD SHUTDOWN TEST JUSJIFICATION CS-3 SYSTEMI MAIN STEAM VALVE (s):
MS734, MS735 CATEGORY:
C CLASS:
3 FUNCT20N Maintains integrity of AFPT steam supply system.
Prevents normal auxiliary steam source from reverse flow and entering the backup auxiliary steam supply source.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify reverse flow closure.
COLD SHUTDOWN TEST JUSTIFICATION: Quarterly reverse flow testing is inaccurate because the test isolation valves leak by.
Extended time for testing could exceed Technical Specification 3.7.1.2 action statement (s), Two independent steam generator auxiliary feedwater pumps and associated paths.
Testing these valves at power is dangerous since normal system pressure and temperature is approxinately 870 psig and 590 degrees respectively.
QUARTERLY PARTIAL STROhE TESTING:
N/A COLD SHUTDOWN TESTING:
Verify reverse flow closure.
III-1-18-7
=
2rd Intervat llt Progren vol. I tevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-4 SYSTEM HAIN STEAM VALVE (s):
MS375, MS394 CATEGORY:
B CLASS:
2 TUNCTION:
Main Steam Trap Waru Up Line Isolation valves.
ASHE SECTION XI QUARTERLY TEST REQUIREMENTSt Exercise, time and fail.
COLD SHUTDOWN TEST JUSTIFICATION: These valves are in the Main Steam trap warm up drain lines and are maintained closed during normal operation.
Valves are only open during plant startup to drain condensed steam from the Main Steam traps.
Opening these valves with normal operating steam conditions would result in extensive damage to the downstream line pipe which is not designed for high temperature and pressure steam flow.
If the valves failed to reclose, the plant would be forced to shutdown.
QUARTERLY PART STROKE TESTING:
Valves full stroke on initiation and cannot be part stroke exercised.
COLD SHUTDOWN TESTING:
Exercise, t l,a, fail.
III-1-18-8
l 2nd interven lif Progree vol, j tevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-5 SYSTEMI MAIN STEAM VALVE (s)*
MS100, MS101 CATEGORY:
BC CLASSI 2
FGNCTION:
ASME SECTION XI QUARTERLY TEST REQUIREMENTS Exercise, time, and fail.
COLD SHUTDOWN TEST JUSTIFICATION Exercising these valves during normal operation isolates one line of steam flow to the turbine which would cause a severe pressure transient in the Main Steam lines, resulting in a forced plant shutdown. Reducing power level sufficiently to perform testing without causing a transient would significantly impact plant operations.
The valves are air operated, balanced-disc stop check talves set in opposition to normal flow direction.
The air o in the open position.perator holds the valve On receipt of a close signal, the operator releases the disk which is forced closed by' steam flow.
The valves
-are not designed for repeated full design flow closure and valve degradation may occur upon repeated-closure.
QUARTERLY PART STROKE TESTING:
The valves are equipped with slow close 10 percent partial closure test function.
If the valve were to exceed the 10 percent closure point, they may be forced closed by the steam flow which would result in a forced plant shutdown and could cause valve damage.
ALTERNATE TESTING:
Valves will be full stroke exercised,.
timed, and failed each time the plant is in hot shutdown, unless the valve has been tested in the prior three month period.
III-1-18-9
2rd interval lli Program L.,
Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-7 SYSTEM MAIN STEAM VALVE (s):
MS100-1, MS101-1 CATEGORY:
B CLASS:
2 ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Exercise, timo, and fail.
COLD '"lUTDOWN TEST JUSTIFICATIONt These valves are interlocked with the Main Steam isolation valves and cannot be opened when the Main Steam isolation valveu are open during normal operation.
QUARTERLY PART STROKE TESTING:
Valves are full-stroke on initiation and cannot be partial-stroke exercised.
COLD SHUTDOWN TESTINGt Exercise, time, and fail.
III-1-18-11 0
2nd Intervel 181 Proprom vol. I tevision 01 GENERIC LETTER 89-04 JUSTIFICATION GL-1 SYSTEM:
MAIN STEAM VALVE (s)t MS726, MS727 CATEGORY:
C CLASS:
3 FUNCTION Main Steam to Auxiliary Feedwater Pump Turbine Line Check Valves.
ASME SECTION XI
. QUARTERLY TEST REQUIREMENTS Verify reverse flow closure.
BASIS FOR RELIEF:
Ther6 are no system design provisions for verification of reverse flow closure.
ALTERNATE TESTING:
Forward flow operability is verified quarter 19 during auxiliary feedwater pump testing.
In addition, one valve will be disassembled, inspected and manually full-stroke exercised each refueling consistent with Item 2 of Attachment 1 to NRC Generic Letter 89-04.
Full forward flow testing will occur after inspection and reassembly is completed.
III-1-18-12 i
1 l
2ral intorvat l$1 Program vet.1 l
Sevision 01 v4 Lyt illt TABLE 10LEDO (0110W C34PANY DAVil BIS $1 huCitAt PCtJER PLANT SYSftM mf.1[yP l VALVE l CAT. l DWG. k0. l 512t l ACf. l POS. l C001 l C.S. OR l C.S. OR l
CtlCf!Pfl64 lCMG.l l
WD.
l & l 4
l & l TTFEl hDRM.l tt$1l ttLitf l AtitthAft l
l l
l l CL.l C00aD. l TVPt l & l &
j REQ.i Atout St j ttst l
hotts l
l l
l l
l l Fall l la l l
h0.
l Pitf0AMt0 l
l l
l l
1 I
i Pos. I OP.
I i
1 1
1 1
MU1A B
M 31A 2.5 M3 0/C 10 0 Cl 1 f0 C tetdown toont isolation 2
84 GT 0/C fC-Q CS 1 fC C valve.
PI Y Mutt 8
M 31A 2.$
MO 0/C 70 0 C$ 1 10 C Letoown cooter tsotetion 2
A2 GT 0/C TC-Q CS 1 1C C valve.
PI Y Mu2A A
M 031A 2.5 M0 0
tC 0 C51 TC C Letdown Line Ctet.
2 B.4 Gt At 0/C 10 0 C$ 1 70 C isolation valve.
LJ R Pl*1 Mu28 8
M 314 2.5 M0 0/C 10 0 CS.1 10 C Letoown cooler isolation 2
A2 GT 0
PI-Y valve.
Mu3 A
M 031A 2.5 A0 0
TC-Q C$ 1 fC C Letoowo line Ctet.
2 85 GT C
O/C 70 0 CS 1 70 C isolation valve.
FC=0 Cs 1 FC C tJ R Pl.Y Mull B
M 031A 2.5x3x2, MO 0
TC o 3 way valve to align 3
N.11 TW Al C
Pl Y letdown to MU system or radweste system.
MU12A C
M 31A 2.5 Mo 0/C to o Cs.1 to C Mateup fliter isolation 3
J8 GT 0
PI Y valve.
Mu128 C
M 31A 2.5 M0 0/C 70 0 Cs.1 to C Make up filter isolation 3
t8 GT 0
PI Y valve Mu23 8
M 045 2
A0 0
10 0 BAT pmp discharge Line 3
F4 GL 0
0 flow controt valve.
'MU33 A~
M 0318 1
RC puno seat return line 2
87 GL C
C FC-Q C1 4 FC C Ctat. isolation valve.
LJ t PI Y Mu40 B
M 031A 2.5 Mo C
70 4 BAT p rp to Mu f ank line 3
K 10 GT At 0
PI Y block valve.
Ill.1 1f 1
Revision 01 VALVE ?f,T TAl([
TOLEDO EDisch COMPAh1 DAVIS 8FS$E NUCLEAR power PLAhi SYSTEM: MArfUo
..... s l val.VE l CAT.]DwG.h0.l$12El ACT.l POS.l CODE l C.S. OR \\
C.S. OR l
OESCRIPTION l CMG.l
_l NO.
l 8 l l & l TYPE \\ NORM.l Test l RELIEF l ALTERNATE l
l l
l l CL. \\ COORD. l TYPE l 8 l &
l REQ. 1 REQUEST l TEST
\\
NOTES l
j l
l l
l FAIL l 5R l l
s'.
l PERFORMED l
l
]
(
l l
l l PCS.l OP.
l l
l l
l l
MU594 A
M-0318 1
M0 O
TC-Q CS 4 TC C RC pump seat return Line 2
8-2 GL Al C
LJ R Ctmt. isolation valve.
PI-Y MU599 m
M 0318 1
M0 O
TC-Q CS 4 TC C RC puro seat return line 2
C3 GL Al C
LJ R Ctet, isotation valve.
PI Y MU59C A
M 0318 1
M0 O
TC-Q CS 4 TC C RC puro seat return line 2
D-3 GL Al C
LJ R Ctmt. isolation valve.
PI-V MU590 4
M 0318 1
Mo 0
TC-Q C5 4 TC-C RC puro seat retum line 2
E3 GL Al C
- JR Ctr t. isolation valve.
PI Y MU66A A
M 0318 1.5 A0 0
TC-Q CS 4 TC-C RC pwp seat supply line 2
K5 GL C
C FC-Q CS 4 FC C Ctet. isolation vatve.
LJ R P! Y MU668 A
M 0318 1.5 A0 0
TC-Q CS-4 TC C RC pump seat supply line 2
J-5 CL C
C FC-Q CS 4 FC C Ctmt. isolation valve.
~
LJ R P!-Y MU66c A
M 0318 1.5 A0 0
TC-Q CS 4 TC C RC puno seat swoly line 2
H5 GL C
C FC-Q CS 4 FC C Ctmt, isolation valve.
LJ R PI Y MU660 A
M 0318 1.5 A0 0
TC-Q Cs 4 TC C RC purp seat supply line 2
F5 CL C
C FC-Q CS 4 FC C Ctmt. isolation valve.
L,J R
..Y MU160 C
M 031A 3
SA O/C FF-Q CS 6 FF-C DAT pwp to MU tank Line 3-K-6 CK kA 0
MU169 C
M 031C 2
ss C
RF-Q Cs 2 RF C MU to RCs inj. tine check 2
H2 CK NA O/C FF-Q Rv-2 PQR valve. Normat makeup and feed & bleed.
!!! 1 19 2
2ral intorvat ist Program Vol. I Revision 01 VALVE TE$f TABLE TOLEDO EDl50N CCNPANY CAVi$ 8 ESSE NUCLEAR P& ER PLANT SYST(M3 WAKEUP l VALVE l CAT.]OWG.No.]$12El ACT.l POS l CCOEl C.S. OR l C.S. OR l
DESCRIPfl0N lCHG.l l
WO.
l & l 4
l & l TYPE l h0RM.] TEST l RELIEF l ALTER 4 ATE l
l l
l l CL.l COORD. l TYPE l &
l &
l REQ.} REQUE$f j TEST l
N0ft$
l l
l l
l l
l Fall l $R j l
NO.
l PERFORMED l
l l
.I l
I i
i P05.l OP.
l l
l l
}
j MU176 C
M 031A 1
SA O/C FF-Q CS 6 FF C BAT per to 40 fank tine 3
N6 CK NA 0
MU181 C
M 031C 3-SA 0/C FF o CS 6 FF C Bat pro to MU Tank line 3
A5 CK hA 0
check vatve.
MU196 C
M 031C 2.5 SA 0/C FF o RV A PQCs MU p p discharge line 3
H.6 CK h4 O/C RF o CS 7 RF R check valve.
MU197 C
M 031C 2.5
$A 0/C FF-Q ev 4 PQC5 MU pwp discharge line 3
E6 CK NA O/C RF-Q CS 7 RF R check valve.
MU204 C
M 031C 1
SA 0/C FF-Q CS 10 FF-C MU pump min, flow line 3
G7 CK NA 0/C RF o CS 7 RF C check vatve.
MdA7 C
M 031C 1
SA 0/C FF-Q CS 10 FF C MU pw p min, flow Line 3
F7 CK NA 0/C RF o CS 7 RF-C check valve.
MU242 AC M 0318 1.5 sa O
RF o Av.1 RF.R RC pro seat supply t ine 2
K4 SC NA C
LJ R Ctmt. Isolation valve.
Mu243 AC M 0318 1.5
-SA 0
RF 0 RV 1 RF R RC puno seal supply line 2
J4
$C NA C
LJ R Ctat. isolation vcalve.
MU244 AC M 0318 1.5
$A
.O RF-o Av 1 RF-R RC pwp seat supply line 2
ti 4
$C NA C
(J R Ctmt. isolation valve.
.MU245 AC M-0318 1.5 sA 0
RF o av 1 RF-R RC pwip seat supply line 2
F-4 sc NA C
LJ R Ctmt, isolation valve.
MU346-C M-045 2
SA 0/C 77 0 BAT puro discharge line 3
M*4 CK NA 0/C RF o check valve.
MU347 C
M 045 1.5 SA 0/C FF.o BAT pump discharge line
.3 M2 CK NA 0/C RF.o check valve.
MU350 C
M 045 2
SA 0/C FF-o CS 6 FF C BAT puro discharge line
-3 M2 CK NA 0
MJ361 C
M 045 2
SA 0/C FF-o Cs-6 FF C BAT pwp discharge line 3
E4 CK NA 0
til 1-19 3
1 g _.
2nd Interval l$f Program vol. i Revision 01 VALVE TEST TABLE TOLEDO EDISON COMPANY OAvis BESSE NUCLEAR POWER PLANT SYliEMt MAKEUP l VALVE j CAT.l DWG. No.l SIZE l ACT l P0S.j CODE l C.S. OR l C.S. M l
DESCRIPit0N l CM.l l
NO.
l 8 l 5
l 8 l TYPE l_ NORM.l TEST l RELIEF l ALTERNATE l
l l
l l CL,l COORD. l TYPE l 5 l 4 l REQ. l REQUEST j TE51 l
NOTES l
l l
l l
l l FAIL l SR l l
NO.
l PERFORMED l
l l
l l
l l
j POS. l OP.
l l
l l
l l
MUM 3 C
0$ 002
.5 SA 0/C FF-Q Aus gsar oil rerervoir 3
B 59 CK 0
outtet eneck for Makeup Pumr 1-1 MU384 C
05 002
.5 SA 0/C FF.o Aus gear ott reservoir 3
H.59 CK 0
outlet check for Makeuw Pump 1 2 MU423 C
0$-002
.5 SA 0/C FF-Q Cs.11 FF C Makeup p g 1 aux geer 3-0 58 CK 0/C RF-Q AC tube oil pi.rp.
MU424 C
0s.002
.5 SA 0/C FF 0 CS 11 FF C Makeup p.pp 2 awa gear 3
N-58 CK 0/C RF-Q AC Lube oil puno.
MU800 C
M 031C 2.5 -
SA C
RF o Cs 5 RF C Alternate MU to RCs inJ.
2 E-2 CK 0
FF o av 3 FF.R tine check valve. Att feed & bleed.
MU1893 C
M 031C 6x8 SA C
SR f MU Tank to MU pump 3
0 11 RL NA 0
suction line system r?llef valve.
MU3971 B
M 031C 3x4x3 MO C
10-0 Cs.8 10 C 3 way valve to ation Mu
-3 G 11 TW At 0
Pl.Y pump to SwSi or Makeup Tank. Open position is atigned to Makeup Tann.
MU6405 B
M-031C 3x4K3 M0 C
10 0 Cs 8 10 C 3 way valve to align Mu 3
E.10 TW At 0
Pl.Y pi.np to swst or Makeup Tank. Open position is aligned to Makeup Tank.
MU6408 s
M.031C 2
Mo o
TC o CS 9 TC C MU p g discharge header 3
G-6 Gi Al C
Pl.Y train isolation block valve.
MU6409 B
M 031C 2
' MO O
TC-Q CS 9 TC C MU p g discharge header 3
F.6
' Al C
PI-Y train isolation block valve.
MU6419 B
M 031C 2
M0 C
!0-0 Feed & bleed tine block 3
E4 CL At 0
Pl Y valve.
!!!-1+19 4
l-,:
2nd Interval IST Program Vol. !
Revision 01 VALVE.Ttli TA8LE TOLEDO EDISON COMPANY CAvis 8 ESSE hUCLE AR POWER PL Ah!
SY$ttM MM
OtScalvflow lCnc.l l No. l 4 l l 4 l 1YPEl h0RM.l TEST l AELIEF l alt (RNATE l
4 l
l l
l CL.l COORD.l TYPE l
& l 5 l #EQ. l REQUEST l TEST l
hofE5 l
l l
l l
l l Fall l 5R l l
h0.
l PERFORMED l
l l
1 I
I I
1 Pos. I Ca.
I I
I I
I I
Mu6420 8
M 031C 2.5 M0 C
70-0 Cs 3 To C Feed & oteed Iine etock 3
J4 GT At 0
Pl Y valve.
WJ6421 A
M 031C 2.5 Mo C
10 0 Feed & bleed line Ctmt.
2 E3 GL At 0/C TC-Q isolation valve.
LJ R PI-Y MU6422 A
M 031C 2.5 Mo o
T0-0 CS 3 TC C horr.at Mu to RCS t tne 2
H3 GT.
Al O/C TC-Q Cs 3 to C Ctmt. Isoaltion valve.
LJ R PI Y 2
III 1 19 5
2rd intervat l$f Program Voi. I a vision 01 COLD SMUTDOWN TEST JUSTIFICATION CS-1 SYSTEM:
MAKEUP VALVE (s):
MU1A, MU1B, MU2A, MU2B, MU3, MU12A, MU12B CATEGORY:
A CLASS:
2
- FUNCTION:
RCS Letdown Line Containment Isolation Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Exercise and time (MU1A, MU1B, MU2A, MU28, MU12A, MU12B).
Exercise, tima and fail (MU3).
COLD SMUTDOWN TEST JUSTIFICATION: These valves are in the normal letdown line
'from the RCS.
Exercising during normal operatjen.would disrupt normal RCS letdown flow which would impair the capability of the MU system to provide the proper boration ratio.
Failure of each valve in the closed position coincident with normal Makeup flow could result in a manual reactor trip due to high RCS pressurizer level.
-QUARTERLY PARTIAL.
' STROKE TESTING:
Valves full-stroke on actuation and cannot be partial-stroke exercised.
COLD SMUTDOWN TESTING:
Exercise and. time (MUlA, MU1B, MU2A, MU2B MU12A, MU12B).
Exercise, time and fail (MU3).
L I
III-1-19-6
2rd Interval 111 Program vol, I levision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-2 SYSTEM:
MAKEUP VALVE ( s) :'
MU169 CATEGORY:
C CLASS:
2 FUNCTION:
Makeup to RCS Injection Line Check Valve.
ASME SECTION-XI QUARTERLY TEST REQUIREMENTS:
Verify reverse flow closure.
COLD SHUTDOWN TEST JUSTIFICATION: This valve is in the normal makeup line to t' e Reactor Coolant System.
To verify reverse flow closure requires termination.of the normal makeup flow.
Termination of normal makeup flow during normal operation would impair the capability of the makeup system to provide the-proper boration ratio or result in low pressurizer level and violation of Technical Specification-3.4.4.
In addition, isolation of all makeup flow would be required, causing thermal shock to high pressure injection nozzle thermal sleeve.
QUARTERLY PART STROKE TESTING:- N/A COLD SHUTDOWN TESTING:
-Verify reverse flow closure.
III-1-19-7 l~
fU 2nd Interval IST Program Vol. I J
Revision 01 g-F
' COLD SHUTDOWN TEST JUSTIFICATION 1
CS-3
-SYSTEM:
MAKEUP 1 VALVE (s):'
.MU6420, MU6422 CATEGORY:
A (MU6422)
BJ(MU6420)
CLASS:
2-(MU6422) 3-(MU6420)-
FUNCTION:-
Normal 1 Makeup Lineito RCS Bypass Valve
-(MU6420) and Containment Isolation Valve
. ( MU6 4 2 2 )'.
ASME SECTION'XI
- QUARTERLY-TEST;
-REQUIREMENTS:
Exerciso_and; time.
COLD' S HUTDOWN ! TEST-1' iJUSTIFICATION: MUr6422 is the' block' valve to the normal
-makeup flow to the-RCS.-
MU-6420 is the bypass valve'-around MU 32, RCS Makeup Control Valve.
s
~ Exercising normally~ closed MU 6420:open would-bypassEthis normal Pressurizer level control-
. valve and inject: full makeup flow into the
]
iRCS. ;This full makeup flow would. result in an i
. undesirable condition and may.cause high r
~
= pressurizer level per Technical Specification
- 3. 4. 4 '. : { Exercising MU 6422 would terminate
. normal-makeup flow to the RCS which again -
would~ violate minimum. pressurizer levels per
- Technical ~ Specification :3. 4. 4.. - In addition,
- closing.MU 6422 would isolate all makeup = flow
- causing thermal-Jahock; degradation of.the high
- pressure-injection nozzle.-
Failure of?the-
-valveDin-the-closed position coincident.with normal letdown:would1 result.in.a plant
. shutdown.
- QU ARTERLY 1 PARTIAL ~
STROKE-TESTING:-
Valves full-stroke on-initiation and cannot.be partial-stroke-exercised.
1 COLD SHUTDOWN'
- TESTING
- s Exercise andltime.
III-1-19-8 K
l'
^
A mJ, w,,
e r
2nd intervet 151 Program Vol. I lavision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-4 SYSTEM:
MAKEUP VALVE (s) -
MU38, MU59A, MU59B, MU59C, MU59D, MU66A, MU66B,-MU66C, MU66D CATEGORY:
A CLASS:
2 FUNCTION:
RC Pump Seal Supply (MU66A,B,C D) and Return (MU38, MU66A,B,C,D) Line Conta1nment Isolation Valves.
ASME SECTION QUARTERLY TEST REQUIREMENTS:
Exercise and time (MU59 A, B, C, D).
Exercise, time and fail (MU38, MU66A, B, C, D).
-l COLD SHUTDOWN TEST JUSTIFICATION: Exercising these valves during normal operation or at cold shutdown when the RCS is pressurized results in a loss of normal seal water to the RCS pump seals.
If seal water is terminated, reactor coolant ~is forced from the high pressure RCS into the seals.
Reactor coolant normally contains a high particulate matter concentration which is carried with the reactor coolant in leakage and contaminates the seals and may.cause extensive damage to the seals.
-QUARTERLY PARTIAL '
Valves full-stroke on initiation and STROKE TESTING: L cannot be partial-stroke tested.
COLD SHUTDOWN
-TESTING:
Exercise, time and fail (as appropriate).
i l
III-1-19-9 i
l
2nd Intervat 117 Program vol, l Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-5 SYSTEM:
MAKEUP VALVE (s) :
MU800 CATEGORY:
C CLASS:
2 FUNCTION:
Alternate Makeupfto RCS Injection Line Check Valve.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify reverse flow closure.
COLD SNUTDOWN TEST JUSTIFICATION: Reverse flow testing MU800 during normal operation requires installing a portable pressure source (hydrostatic test pump) at MU801.
The back-to-back High Pressure Injection nozzle check valves, HP48 and HP50 located in Containment, form the only boundary between this open vent connection and full RCS pressure and temperature.
The potential for a loss of coolant by this path exists, which could result in a plant shutdown, and poses a danger to test personnel. Additionally, the test lineup renders that train of the Makeup system inoperable, making it unavailable for
. Feed and Bleed.
QUARTERLY PART STROKE TESTING:
N/A COLD SHUTDOWN TESTING:
Verify reverse flow closure.
III-1-19-10 l
i
I 2rd intervet 157 Program vol. I Revision 01 I
I COLD SHUTDOWN TEST JUSTIFICATION CS-7 SYSTEM:
MAKEUP VALVE (s):
MU196, MU197, MU204, MU207 CATEGORY:
C CLASS:
3 FUNCTION:
Makeup Pump Discharge Check Valves (MU196, MU197).
Makeup Pump Minimum Flow Line Check Valves (MU204, MU207).
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify reverde flcw closure.
COLD SHUTDOWN TEST JUSTIFICATION: The only way to verify reverse flow closure involves closing pump suction line manual valves MU190 and MU191. This action will make the respective Makeup pump inoperable.
Technical Specification 3.1.2.4 requires two operable Makeup pumps.
In addition proper test controls are not present when a makeup pump is in service.
If either suction valve is closed with the other makeup pump in normal operation and the idle pump check valves fail to close, or leaks excessively, the pump seals and low pressure pump inlet piping will be overpressurized.
Exposing the pump seals and low pressure pump suction piping to normal makeup pump discharge pressure could cause extensive damage to the makeup pum seals and low pressure pump suction pi ing.
QUARTERLY PART STROKE TESTING: N/A COLD SHUTDOWN TESTING:
Verify reverse flow closure.
III-1-19-12 l
2nd interval tST Prograrn vol. I Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-8 SYSTEM:
MAKEUP VALVE (s):
MU3971, MU6405 CATEGORY:
B CLASS:
3 FUNCTION:
Three way valves for normal Makeup pump suction supply from the Makeup Storage Tank, when open pump suction swaps to the BWST.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Exercise and time.
COLD SHUTDOWN TEST JUSTIFICATION: MU3971 and MU6405 are in the closed position which allows the Makeup Pump to take suction on the Makeup Tank.
To cycle these valves would allow the Makeup Pumps to take suction on the BWST.
This would cause cold highly borated water to enter as normal makeup flow to the RCS.
This makeup flow would result in an undesirable condition and would cause a power reduction transient. In addition this cold water would cause thermal shock degradation of the high pressure injection nozzle and possible damage to RCP seals.
Failure of the valves in the closed position (return to the Makeup Tank) would result in a plant shutdown.
QUARTERLY PARTIAL STROKE TESTING:N/A s
COLD SHUTDOWN
-TESTING:
Exercise and time.
III-1-19-13 1
2nd intervet ist Program vol. i Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-9 SYSTEM:
MAKEUP VALVE (s):
MU6408, MU6409 CATEGORY:
A CLASS:
2 FUNCTION:
Cross connect lines for Makeup Trains.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Exercise and time.
COLD SHUTDOWN TEST JUSTIFICATION:
MU6408 and MU6409 are cross connect lines for !!akeup Pump 1-1 or 1-2 to RCP seal and Makeup Train 2 or 1 flow path.
Exercising MU6408 or MU6409 would terminate normal makeup flow to the RCS which would violata minimum pressurizer levels per Technical Specification 3.4.4.
In addition, closing s
MU6408 or MU6409 would isolate all makeup flow causing thermal shock degradation of the high pressure injection nozzle.
Failure of the valve in the closed position coincident with normal letdown could result in a plant shutdown.
r QUARTERLY PARTIAL e
STROKE TESTING:
N/A COLD SHUTDOWN TESTING:
Exercise and time.
III-1-19-14
2nd Interval l$i Program Vol, I Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-10 SYSTEM:
MAKEUP VALVE (s) :
MU204, MU207 CATEGORY:
C CLASS:
3 FUNCTION:
Makeup Pump Minimum Flow Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify forward flow operability.
COLD SHUTDOWN TEST JUSTIFICATION:
Forward flow operability of these valves cannot be verified by line flow rate due to lack of installed instrumentation.
Flow rate can only be obtained by using the Borated Water Storage Tank as the makeup pump supply and measuring a known volume increase over time in the Makeup Tank.
QUARTERLY PARTIAL STROKE TESTING:
None.
COLD SHUTDOWN Verified full forward flow at cold shutdown by verifying the check valve opens to pass design flow.
III-1-19-15
2nd Intersal lli Prograre vol, I Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-ll SYSTEM:
MAKEUP VALVE (s):
MU423, MU424 CATEGORY:
C CLASS:
3 FUNCTION:
Makeup Pump Auxiliary Gear AC Lube Oil Pump.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify forward flow operability.
COLD SHUTDOWN TEST JUSTIFICATION:
The AC lube oil pump provide prestarting oil to the makeup pump speed increaser.
After the makeup reaches running speed a gear driven pump provide lubrication and the AC lube oil pump is shutdown.
This pump is interlocked to auto start if aux gear lube oil pressure decreases.
To verify forward flow would require stopping the makeup pump.
QUARTERLY PARTIAL STROKE TESTING:
If makeup pump is stopped, then prior to starting, forward flow will be verified by observing the AC oil pump starts and nominal downstream oil pressure is achieved.
COLD SHUTDOWN Verified full forward flow at cold shutdown by verifying the nominal downstrer.m. oil pressure is achieved.
III-1-19-16
~,
2rd intervat ist Program vol. I nevision 01 RELIEF REQUEST RV-1 SYSTEM:
MAKEUP VALVE (s):
MU242, MU243, MU244, MU245 CATEGORY:
AC CLASS:
2 FUNCTION:
RCS Pump Seal Supply Line Containment l
Isolation Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify reverse flow closure.
BASIS FOR RELIEF:
The only method available to verify reverse flow closure la by valve leak testing during Appendix J, Type C, testing at refueling.
ALTERNATE TESTING:
Reverse flow closure will be verified during Appendix J, Type C, testing at refueling.
III-1-19-17 l
l l
L.
1 2nd Interval !$f Program vol. I Revision 01 RELIEF REQUEST RV-2 SYSTEM:-
MAKEUP VALVE (s):
MU169 CATEGORY:
C CLASS:
2
- FUNCTION:
Normal Makeup To RCS Line Check Valve.
-ASME SECTION-XI QUARTERLY TEST REQUIREMENTS:
Verify forward flow operability.
' BASIS-FOR RELIEF:-
During normal operation makeup flow to the RCS is automatically regulated in response to RCS conditions by upstream flow control valve MU32.
To. inject full flow into the RC5 during normal operation would result in und'sirable RCS boron e
concentrations, system temperature and level transients and could result in thermal shock to the high pressure injection nozzle thermal sleeve.
In
-addition, the MU pumps are incapable of overcoming RCS operating conditions sufficiently to inject full feed and bleed design flow rate.
The Makeup pumps cannot be run at full feed and bleed flow rate at cold shutdown with the reactor vessel head in place due to the inability to letdown that full flow.- This could result in a low temperature overpressurization of the RCS.
ALTERNATE-TESTING:
This valve will1be partial-stroke exercised quarterly utilizing normal
-makeup flow and full-stroke exercised at refueling outages by verifying that the valve opens to pass full forward flow
. rate.
III-1-19-18
2nd Interval l$f Program Vol. I Aevision 01 RELIEF REQUEST RV-3 SYSTEM:
MAKEUP VALVE (s):
MU800 CATEGORY:
C CLASS:
2 FUNCTION:
MU to RCS Feed and Bleed Line Check Valve.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:' Verify-forward flow operability, i
BASIS FOR RELIEF:
This line is isolated during all modes of operation except during the MU system feed and bleed mode of oporation.
To test the valve by injecting makeup flow into the RCS during normal operation would result in undesirable RCS boron concentrations, system temperature and i
level transients and coald result in thermal-shock to the hign pressure injoction nozzle thermal sleeve.
In addition, the MU pumps are incapable of overcoming RCS operating conditions sufficiently to inject full feed and bleed design flow rate.
The Makeup pumps cannot be run at full feed and bleed flow rate-at cold shutdown with the reactor head in place due to-the inability.to letdown that full flow.
This would result.in a low temperature overpressurization of the RCS.
ALTERNATE TESTING:
This valve will-be full-stroke exercised during refueling outages by verifying that the valve opens to pass full forward flow rate.
III-1-19-19 t
2nd intervat IST Program vol, i Revision 01 RELIEF REQUEST RV-4 SYSTEM:
MAKEUP VALVE (s):
MU196, MU197 CATEGORY:
C CLASS:
3 FUNCTION:
Makeup Pump Discharge Line Check Valves.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify forward flow operability.
BASIS FOR RELIEF:
During normal operation makeup flow to the RCS is automatically regulated in response to RCS conditions by upstream flow-control valve MU32.
To inject full flow into the RCS during normal operation would result in undesirable RCS boron concentrations, system-temperature and level transients and could result in thermal shock to the high pressure injection nozzle thermal sleeve In addition, the MU pumps are incapable of overcoming RCS operating conditions sufficiently to Inject full feed and bleed design flow rate.
The Makeup pumps cannot be run at full feed and bleed flow rate at cold shutdown with the reactor vessel head in place.due to the inability to letdcwn-that full flow.
This could result-in a low temperature overpressurization of the RCS.
ALTERNATE TESTING:
These valves will be partial-stroke exercised quarterly utilizing normal makeup flow and full-stroke exercised at refueling outages by verifying that the
-valve opens to pass design flow.
III-1-19-20
1 2rci Interval IST Program 001. I Revision 01 VALVE TEST TABLE TOLEDO EDISON COMPANY DAVIS +6 ESSE NUCLE AR PouCR PLANT SYSTEM! NITR00 Elf l VALVE l CAT. l DWG. h0. l SIZE l' ACT. l Pos.} CODE} C.S. 04 l C.S. OR
}
CESCRIPit0N l C4.l l No.
l & l l & l TYPE l h0R4.l TEST l RELIEF l ALTEthAtt l
l l
l l CL.l COORD.l TYPE l &
l &
l REQ.l REQUEST l TEST l
NOTES l
l 1
l l
l l
l FAIL l SR l l
h0.
l PERFORMED l
l l
1 1
I I
I POS. l CP.
i l
l l
l 1
NN58 AC M 019 1
SA 0
RF-Q PV 1 RF*R Nitrogen supply to 2
B3 CK h4 C
LJ.R Pressuriser Quench tank Ctet. Isolation valve.
)
Pen. P448.
i WW236 A
M 019 1
A0 0
TC-Q Nitrogen suroty to 2
B5 GT C
C FC-Q Pressurizer Quench Tank LJ 2 Ctmt, isolation valve.
PI Y Pen. P448.
NW1002 C
M 019 3/8 SA 0
RF-Q CS 1 RF C Electrical penetration 3
E2 CK NA C
supply to PCP1CX hh1004 M 019 3/8 SA
.0 RF-Q CS 1 RF C Electricot penetration 3
E2 CK kA C
supply to P8P1DX NN1006 C
M 019 3/8 SA 0
RF-Q CS 1 RFaC Electrical penetration 3
'E2 CK NA C
supply to P8L1EX NN1008 C
M 019 3/8 SA 0
RF-Q CS 1 RF C Electrical penetration 3
F2 CK NA C
supply to P4tigx NM1010 C
M 019 3/8 SA 0
RF-Q CS 1 RF C Electrical penetration 3
F2 CK NA C
supply to PSC2DX NN1012 C
M 019 3/8 SA 0
RF-Q CS 1 RF-C Electrical penetration 3
F2 CK NA C
supply to PCL2EX WN1014 C
M 019 3/8 SA 0
RF-Q CS 1 RF C Electrical penetration 3
G2 CK NA C
supply to PCL2FX
.NN1016 C
M 019 3/8 SA 0
RF-Q CS 1 RF C Electricat penetration 3
.G2 CK NA C
supply to PCL2GX kW1018 C
M 019
~3/8 SA 0
RF*Q CS-)
RF*C Electrical penetration 3-G2 CK NA C
supply to P1P38X NN1020 C
'M 019 3/8 SA 0
RF-Q CS 1 RF-C Electrical penetration 3
G-2 CK NA C
supply to PAL 30X NN1022 C
M 019 3/8 SA 0
RF-Q CS 1 RF-C Electricat penetration 3
G2 CK NA C
supply to PAC 3EX tiI 1 20 1
(.-'
~
2nd intervat IST Program vol. l-Revision 01 VALVE TEST TAett TOLEDO EDISON COMPANY davit SESSE NUCLEAR POWER PLANT
- SYSTEMI NITROGEN l VALVE l CAT.lDWG.'No.lSt!El ACT.l POS.l CODE l C.S. OR l C.S. OR l
DESCRIPil0N l CMG.l.
- l No.-l 4
l-
.l 8 l TYPE l NORM.l TEST l' RELIEF l ALTERNAtt l
4 l
l
.' l l CL. l ; Cocco. l TYPE 'l l & l REO.l Atoutti l TEST
'l Notts l
l l
l l
l l Fall l $R l l
NO.
l PERFORMED l
l l
l-l
'l l
l P05 1 OP-1 I
I I
I I
NN1054 C
M 019 3/
SA-0 RF 0 CS 1 RF C Electrical penetration 3
A 14 CK h4 C
s p ly to PAP 1PX l
NN1056 C
N 019-3/8 SA 0
AF 0 CS 1 RF C Electrical penetration
-3 A 14 CK NA -
C s w ty to PtP1RX.
NW1058 C-M 019-
- 3/8 SA 0
RF 0 CS 1 RF C Electrical penetration 3.
3 14 CK NA C
supply to PIC2LX NN1060-C, M-019 3/8 SA
-0 RF 0 CS 1 RF-C Electrical penetration
'3 5 14 -
CK :
NA C
.@ ply to P1P2MX NN1062
-C M 019
~3/8-SA 0
AF-0 CS*1 RF C Electrical penetration
,3.
F414:
CK NA C
supply to PAL 2NX
. NN1064 ~
-C M 019 3/8 SA 0
RF 0 C$ 1 RF-C Electrical penetration
-3 0 14
~ CK
. hA C
sumty to PAP 2PX
- WN1066 C
' M 019.
3/8 -
54 0
'RF 0 CS 1 RF C Electrical penetration 3
C 14
CK NA -~
C-s@ ply to PBC3PX NN1068 -
C M 019 3/8 5A 0
RF-O'
'CS-1 RF C Electrical penetration I
3
' C-14 '- - CK NA C
supply to PsL30X
- j NN1070
.C-
' M 019 '
3/8-SA '
0
' AF 0 -
CS 1 RF-C Electrical' penetration 3-C 14 CK NA-
'C supply to PCP4NX
- NN1072 C
' N 019 -
-3/8 sA :
0-RF 0 CS 1 RF C Electrical penetration 3-
'C 14 CK NA C.
supply to PCP4PX NW1074'
- C.
-M 019 3/8'--
SA RF-0 Cs 1 RF-C Electricat penetration L3:
C+14'--
CK.
NA.
C supply to PCP40X -.
j
-: l NN1076 C
'M 019 13/8 SA
.O RF 0 -
CS 1
. RF C Electrical penetration.
ll 3
. 0 14 ~
CK NA.
C' supply to P3L4SX
= NN1078:
'C-M 019 3/8 SA 0
RF-Q-CS 1 RF-C
. Electrical penetration.-
3 0 14 -
CK NA C
supply to PCCATX NN1080
- C-M 019' 3/8 -
$A =
0 RF 0 Cs-1
- RF C
-Electriest penetration t
~3' D 141 CK-NA C
s@pty to PCC4UX L,
111 1 20 3 b
l f:
L,.
l :-
p z
u L
I.
}
2nd Intervat IST Program vot. I Revision 01 VALVE TEST TABLE TOLEDO EDISON CCptPANY davis 8 ESSE NUCLEAR POWER PLANT SYSTEM: g1Rggg3 l VALVE l CAT. l DWG. NO. l SIZE l ACT,l POS,l CCDE l C.S. OR l C.S. OR
]
DESCRIPfl0N lCMG.}
l h0.
l & l 4
l 4 l TYPE l NOR4.l TEST l RELIEF j ALTERNATE l
j l
l
~ l l
l
_l FAIL l $4 l l
No.
l PERFORMED l
l l
l CL.l COORD. l TYPE l (
l & l REQ.l REQUEST l TEST l
NOTES l
l l
l 1
1 I
l POS.l OP.
l l
l l
l l
NN1082 C
M 019 3/8 SA 0
RF-Q CS 1 RF C Electrical penetration 3
D 14 CK NA C
sely to PCC4VX NN1084 t
M 019 3/8-SA 0
RF-Q CS 1 RF C Electrical penetration 3
E 14 CK NA C
s c ly to PCL4WX NN1086 C
M 019 3/8 SA 0
RF-0 CS 1 RF C Electrical penetratico 3
E-14 CK -
NA C
supply to PCP5NX NN1088 C
M 019 3/8 SA-0 RF 0 CS 1 RF C Electrical penetration 3
E 14 CK NA C
supply to PCP5PX NN1090 C
M 019 3/8 SA 0
kF-Q CS-1 RF-C Electrical penetration 3
E 14 CK NA C
supply to PCP$ux NN1092 C
M 019 3/8 SA 0
RF-0 CS 1 RF C Electricot penetration 3
f.14 CX NA C
s W ty to PCC$fx NN1094 C-M 019 3/8 SA 0
RF-0 CS 1 RF C Electrical penetration 3
F-14 CE kA C
supp:y to PCC5UX NN1096 C
M 019 3/8 SA 0
RF 0 CS*1 RF C Electrical penetration 3
F.14 CK-NA C
supply to PCC5VX
!!! 1-20-4
2nd Interval 151 Program Vol. I nevision 01 l
COLD SNUTDOWN TEST JUSTIFICATION CS-1 SYSTEM:
NITROGEN VALVE:
East Side Electrical Penetratica Check Valves NN1002, NN1004, NN100A. L2008, N!i1010, NN1012, NN1014, NN1616, NN1018, NN1020, NN1022, NN1024, NN1026, NN1028, NN1030, NN1032, NN1034, NN1036, NN1038, NN1040, NN1042, NN1044, NN1046 3-West Side Electrical Penetration Check Valves NN1050, NN1052. NN1054, NN1056, NN1058, NN1060, NN1062, NN1064, NN1066, NN1068, NN1070, NN1072, NN1074, NN1076, NN1078, NN1080, NN1082, NN1084, NN1086, NN1088, NN1090, NN1092, NN1094, NN1096 CATEGORY:
C CLASS:
2 FUNCTION:
H.trogen Check Valves Supply to Containment Electrical Penetrations.
ASME SECTION V.I QUARTERLY TEST REQUIREMENTS:
Verify reverse-flow closure.
COLD SNUTDOWN TEST JUSTIFICATION: To perform operability test of these valves will require personnel to enter the annulus.
This area is located between the containment vessel and shield building.
The annulus is a locked high radiation area that contains high neutron fields. To do this test during normal operation would violate ALARA concerns.
' COLD SHUTDOWN Verify reverse flow closure.
TESTING:
.g III-1-20-5 I
l
2nd Interval Ili Program vot. I Revision 01 RELIEF REQUEST RV-1 SYSTEM:
NITROGEN VALVE:
NN58 CATEGORY:
AC k
\\
CLASS:
2 FUNCTION:
Nitrogen System Containment Isolation Check Valve.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify reverse-flow closure.
BASIS FOR RELIEF:
The only method available to verify 9
reverse-flow closure is by valve leak
\\
testing during Appendix J, Type C, testing at refueling.
ALTERNATE TESTING:
Reverse-flow closure wi.12 be verified during Appendix J, Type C, testing at refueling.
III-1-20-6 I
2rt:$ Interval l$1 Program Vol. I Revision 01 VALVE TEST 1ABLE 10LE00 E0l$0N CCv4 PANT Davis SE55E kUCLEAR power plani SYSTEM: REActee COOLANT l V AL"E l CAT. l DWG, No. l $12E l ACT,l P05. l COCEl C.$. OR l C.S. OR l
DE SCR IPi!ON CMC.l l ko. l 1 l 4
l 1 l TYPE l NORt l Test l REll!F l ALTERhATE l
4 l
l l
l CL.l COORD. l TYPE l 4
l &
l REQ. l REQUEST l YEst j
h01Es l
j l
l l
l l Fall l 5R l l
h0.
l PERf0RMED l
l l
l l
l l
l POS.l CP.
l l
l l
l l
RC2A SC M 030A 2.5x4 EM C
70-Q RV 1 50 #
Electicat ty controt ted 1
43 Gi SA 0/C TC-Q RV-1 SC R pilot vatve operated FC-Q RV 1 FC R relief valve.fPORV)
P!-Y RV 1 RC10 8
M 030A 2.5 M0 O
TC-Q C5 1 TC C Press, spray line block 1
C9 Gt Al C
PI Y valve.
RC11 8
M 030A 2.5 M0 O
TO-Q
- ress. PORV tine block 1
83 ct At 0/C TC-Q
- valve, PI-Y RC13A C
M 030A 4x6 sA C
'sR-1 Press. safety retlef 1
87 RL kA 0
valve.
RC138 C
M 030A 4x6 SA C
SR 't Press safety relief 1
85 RL kA 0
vatve.
RC51 C
M 030A 1,5 SA C
FF-Q Cs 2 FF-C Decay Heat sys. Aun.
1 C9 CK kA 0
spray to Press. line check valve.
RC113 AC M 040A 2
SA 0/C RF-Q Rv 2 RF-R i r t as, Quench T ank intet 2
73 CK-NA C
LJ R tine Ctmt, isolation valve, Pen. P41 RC200 8
M 030A 1
Mc C
70 0 Cs 3 70 C Press. vent line block 1
83 "Y
Pl Y RC229A A
M 040A 3
A0 0
TC-Q Press. Quench Tank 2
H4 GL C
C FC-Q cooling line Ctat.
LJ R isolation valve.
PI Y Pen. P48.
RC229s A
M 040A 3
A0 0
TC-Q Press. Quench tank 2
H3 CL C
C FC-Q cooling Line Ctet.
LJ R isolation valve.
PI-Y Pen. P48.
!!!-1 21 1
2nd interval l$i Program L 1
Revision 01 VALVE TEST TABLE
[
l TOLEDO EDISON COMPAhY DAvil 9 ESSE huCLEAR POWER #LAki SYSTEM: REactot Cootakt l VALVE l CAT.lDwG.No.l SIZE l ACT.l POS.l C00E l C.S. OR l C.S. OR l
CESCRIPfl0N lCMG,l l
h0.
l 4 l l & l TYPE l h0RM.l TEST RELIEF l ALTEthATE l
l l
l l CL.l COORD.jTYPEl & l 8 l REQ. l REQUEST l TEST l
hofES l
l l
l l
l l Fall l S-R l
l NO.
l PERFM MED l
l l
l l
l l
l POS.l OP.
l l
l l
l l
RC232 A
M 040A 2
A0 0
TC-Q Press. Quench tank 2
74 CT C
C 8C-Q coolinQ line Ctmt.
LJ R isolation valve.
PI Y Pen. P41.
RC239A 8
M 030A 1
MO C
70-0 Press vent line block 1
B3 GT At 0
Pl Y valve.
RC24CA A
M 030A 1
MO 0/C TC-Q RCS samte header 1
82 CT At 4
LJ R Ctmt. Isolation velve.
Pl Y Pen. P1.
RC2408 A
M 030A 1
Fa 0/C TC-Q RCS sample header 2
61 GT Al C
LJ R Ctmt. Isolation valve.
Pl.Y Pen. Pl.
RC1719A A
M-040A 3
A0 0
K.7 CA C
C FC-Q Ctmt. isolation valve.
LJ R Pen. P16.
Pl Y RC17198 A
M 040A 3
A0 0
K8 DA C
C FC-Q Ctmt. isolation valve.
LJ R Pen. P16.
PI V RC1773A A
M 040t 3
A0 0
C-10 DA C
C FC-Q Ctet. Isolation valve.
LJ R Pen. P32.
PI Y RC17738 A
M 040A 3
A0 0
0 10 DA C
C FC-Q Ctmt, isolation valve.
LJ.R Pen. P32.
PI Y RC4608A 8
M 030A 1
50 C
T0-Q CS 4 10-C Post Accident RCS toop 1
0 11 CT C
O/C TC-Q CS 4 TC C vent valve.
111 1 21 2
2nd Interval i$i Program Vet, i Revision 01 VALVE TEST TABL(
TOLEDO EDISOM COMPAhY DAVIS BE$$f NUCLEAR PowtR PLAhi
$YSTEM: RCACTOR COOL ANT l VALVE l CAT.lDWG.NO.lSilEl ACT.l P05. l C00El C.S. OR l C.S. OR l
CESCRIPfl0N lCM".l
) 40.
l & l l & l TYPE l h0RM.l TEST l RELIEF l ALTEthATE l
l l
l l CL.l COORD.l TYPE l 1 l &
l REQ. ! REQutST l TEST l
h0TES l
l l
l l
l l Fall l 5R l l
40.
} PERFORMED l
l l
l l
l l
l POS.l OP.
l l
l l
l l
RC46088 8
M 030A 1
to C
70 0 Cs 4 10 C Post Accident RC$ loop 1
D.11 GT C
O/C TC-Q C$ 4 TC C vent valve.
FC-Q C$*4 FC C PI-)
RC4610A 8
M 030A 1
50 C
To-Q CS 4 10-C Post Accident RCS toop i
E2 GT C
O/C TC-Q C5 4 TC C vent valve.
FC.Q CS 4 FC C Pl 1 RC46108 8
'M-030A 1
50 C
fo-o Cs 4 To C Post Accioent RCS toop 1
G2 GT C
0/C TC-Q C5 4 TC-C vent valve.
FC-Q C$ 4 FC C PI Y 111 1 21 3
l 2nd Intervet IST Program vol. 1 Revisto 01 COLD SHUTDOWN TEST JUSTIFICATION CS-1 SYSTEM:
REACTOR COOLANT VALVE (s):
RC10 CATEGORY:
B CLASS:
1 FUNCTION:
RC Pressurizer Spray Line Block Valve.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Exercise and time.
COLD SHUTDOWN TEST JUSTIFICATION:
Failure of this valve in the closed position during normal operation would result in los of normal pressurizer control function and could result in a forced plant shutdown.
QUARTERLY PARTIAL STROKE TESTING:
Valve full-strokes on actuation and cannot be partial-stroke exercised.
COLD SHUTDOWN TESTING:
Exercise and time.
III-1-21-4
I' 2nd Interval IST Prograra vol, I Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-2 SYSTEM:
REACTOR COOLANT VALVE (s):
RC51 CATEGORY:
C CLASS:
1 FUNCTION:
RC Pressurizer Auxiliary Spray Line Check Valve.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify forward flow operability.
COLD SHUTDOWN TEST JUSTIFICATION:
The only way to verify forward flow operability is by injecting Decay Heat System flow into the RCS pressurizer.
The Decay Heat System pumps lack sufficient head to overcome RCS operating pressure and inject flow into the Pressurizer.
QUARTERLY. PARTIAL STROKE TESTING:
N/A COLD SHUTDOWN TESTING:
Verify forward flow operability.
III-1-21-5 l
1
h trd Intstvet 151 Prostwa vol, I tevistwe 01 COLD SHUTDOWN TEST JUSTIFICATION CS-3 SYL: #'"4 REACTOR COOLANT VALVE (s)
RC200 CATEGORY B
CLASS:
1 FUNCTION:
Pressurizer Vent Line Block Valve.
ASME SECTION XI QUARTERLY TEST REQUIREMENTSt exercise and time.
COLD SHUTDOWN TEST JUSTT42 CATION:
This valve is the second normally closed boundary valve between the Reactor Coolant System and the low pressure Gaseous Radwaste System. It is maintained closed during normal operation to maintain Reactor Coolant System Integrity. The only time this valve is opened is during startup to vent the pressurizer.
If the valve is exercised during normal operation and fails in the open position a single upstream valve provides Reactor Coolant System integrity and the plant will be forced to shutdown.
QUARTER.
?ARTIAL STROKE 1.
FING:
Valve full-stroke on initiation and can not be partial-stroke exercised.
TESTING:
Exercise, time, and fail.
III-1-21-6 I
l
2nd Interval 151 Progran vol, i Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-4 SYSTEMI REACTOR COOLANT VALVE (s)
RC4608A, RC4608B, RC4610A, RC4610B CATEGORY:
B CLASS:
1 FUNCTION!
Post Accident RCS Loop Vent Valves ASME SECTION XI QUARTERLY TEST REQUIREMENTS!
Exercise, time and fall.
COLD SHUTDOWN TEST JUSTIFICATION:
These post-accident RCS loop vent valves are Valcor solenoid operated valves with magnetic position switches integral to the valve.
This valve design is susceptible to line pressure surges and will open if subjected to a pressure surges.
If the valves are cycled at
)
system,rossure the closed volve may be forced open and could result in a significant RCS leak.
COLD SHUTDOWN TESTING:
These valves will be full-stroke exercised, time, fail, and flow path verified operable at cold shutdown.
Position indication is indirectly determined by verification of flow.
III-1-21-7 I
frd interval lli Program vol. I 8evision 01 RELIEF REQUEST RV-1 SYSTEM:
REACTOR COOLANT VALVE (s) :
RC2A CATEGORY:
BC CLASS 1
FUNCTION:
pressurizer Power Operated Relief Valve.
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Exercised, time, and fail BASIS FOR RELIEF:
Full stroking and timing cannot be visually verified or measured on this valve since St-valve mechanisms are internal.
Only indication in the control room is the pilot valve position ligh'c which does not indicate true pilot valve or PORV valve position but only the open/close demand signal.
Acoustic monitors provide flow indication, however these are independent of the valve.
The fail position for this valve is closed.
This occurs upon loss of power to the e
solenoid pilot valve, being the normal means to close the valve.
System testing at normal pressure and temperature cannot occur since this would cause a large pressure drop in the RCS hence causing a pressure transient with a posWible Low Pressure Reactor Protection Trip.
Valve testing with the PORV Block Valve (RC 11) closed cannot occur since system pressure is the motive force for 3
opening the valve.
Valve testing cannot occur at cold shutdown because the correct conditions for the testing may not be present.
Testing can only occur during a defined RCS pressure band to ensure the valve has sufficient motive force to stroke open, to limit any RCS system pressure transient, and to limit generation of radwaste.
L III-1-21-8 i
t L
J
2rd Interval ist Program vol. f Revision 01 ALTERNATE TESTING:
Valve will be fully stroked at refueling per DD-SP-03366, Pressuriter Powered Operated Relief Valve Cycle Test.
This test will measure acceptable flow through the PORV by timing the pressure drop from defined and repeatable conditions.
If i
valve fails to completely open then the time for pressure decrease would increase.
A reference value will be defined based upon a pressure change over a time period.
Acceptance criteria based upon j
this reference value will be defined and results trended to identify valve degradation.
Channel 7alibration of PORV setpoint occa:s every refueling per Channel
~
Calibration of 58A-ISPRCO2B2, RCS Pressure to RPS Channel 1.
Present setpoint as allowed by Technical Specification is less than 2355 psig.
This test verifies the solenoid associated with RC2A will energize at the system setpoint.
III-1-21-9
'y y-e e-reye
- m F-
+4 s
-gr-T
- '"T-
2nd Intervet 18f Program vol. I Revision 01 RELIEF REQUEST RV-2 SYSTEMt REACTOR COOLANT VALVE (s):
RC113 CATEGORY:
AC CLASS:
2 l
FUNCTION:
Prissurizer Quench Tank Inlet Line Cont 61nment Isolation Check Valvet. ~
ASME SECTION XI QUARTERLY TEST REQUIREMENT:
Verify reverse flow closure.
BASIS FOR RELIEF:
The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C, testing at refuellng.
ALTERNATE TESTING:
Reverse flow closure will be verified during Appendix J, Type C, testing at refueling.
1-III-1-21-10
.~
.,e e..e,
2nd Interval llt program vol. I teviston 01 v4Lvt tilf TABLE TOLIDO (DISON COMPANY Cavil 6tllt muCLIAt POWtt plant
$15f tut }Au811 l VALyt l CAT.l D4.. Wo.l $121 l ACT. l Pol. l C:Of l C.S. OR l C.$. OR l
OttCalPfl04 lCHO.l l Wo. l & l 4
l 8 l TYtt l h0AM.] flli l RELiff l ALittsAtt l
4 l
l l
l CL.l COORD. l ff7f l &
l &
l Rio. l tt9Utli l tilf l
N0fts l
l l
l l
l l FAIL l $t l l
No.
l PitFDPMfD l
l l
1 I
l l
I Pos. I OP.
I i
1 1
I I
$$235A A
M 040A 1
A0 0/C TC 0 ovench tank vepor serptt 2
E6 CL C
C FC 0 timt. Isolation velve.
LJ*t PI Y 152358 A
M 040A 1
A0 0/C TC 0 Quench tank vapor seaple 2
t3 GL C
C PC 0 Ctet. tooletion velve.
LJ t PI Y
$1598 8
M 00TA
.75 A0 0
it-Q 50 sancte Line Ctet.
2 M3 GL C
C, FC 0 Isolation volve.
Pl*Y 55607 8
M 007A
. 75 A0 0
TC 0 to septe line Ctmt.
2 M9 CL C
C FC 0 (solation velve.
PI Y 111 1 22 1
2rd Interval l$1 Program Vol. t tevision 01 l
I VALvt Illt 1Allt 10L100 (Dil0m COMPANT DAvil Billt hJCLEAR Posit PLAh!
$Y$1(Mt itivlti Watta lVALVIl CA1.l DWG. h0.l $121 l AC1. l P0l. l C00t l C.S. OA l C.S. OR l
CittRIPit0h jCMO.l l
h0.
l 4 l l 5 l 11Ptj hoeW.l tilf l titlEF l AtttthAlt l
4 l
l l
l CL.l CoctD. j titt l 1 l &
l 810. l ttoutti l Illi l
hotts l
l l
l l
l l Fall l lR l l
h0.
l FIRFORMED l
l l
I I
l l
1 POS. I OP-1 I
I I
I I
SW17 C
M 041A 20 SA 0
FF-Q Cl 2 P005 sw pro discharge line 3
03 CK h4 0/C RF-Q Cl 4 PQC$
SW18 C
M 0414 20 SA 0
FF-Q C5 2 PQC5 Sd pro discharge line 3
G 10 CK h4 O/C AF-Q Cl 4 PQCl check vatve.
$W19 C
M 041A 20 SA 0
FF-Q Cl 2 PQC8 sw pn discharge line 3
G7 CK h4 0/C BF-Q Cl 4 PQC5 check valve.
)
$wST C
M 041A 20 SA 0
- F-Q Cl 1 RF C teturn f run cooling 3
A7 CK 44 C
water NX. to $d Line check valve.
$W1356 B
M 041C 8
A0 0
to-Q Ctet. Air Cooter return 2
C2 BL 0
0/C TC-Q to sw line isolation FO-Q valve.
PI Y 5W13$7 8
M 041C 8
A0 0
10 0 Ctet. Air Cooter return 2
C9 BL 0
0/C 1C-Q to SW line isoettion FO-Q valve.
PI V o
5W1358 e
M 041C 8
Ao C
)- Q Ctmt Air Cooter return 2
C5 BL 0
0/C TC-Q to SW tine isolation FO D valve.
PI Y 5W1366 8
M 041C 8
MO O
10 0 SW supply to Ctat. Air 3
M5 SL At 0/C TC-Q Cooters line isolation Pl Y valve.
SW1367 9
M 041C 8
MO O
10 0 SW supply to Ctmt. Air 3
M 12 BL At 0/C TC-Q Cooters line isolation Pl*Y valve.
sW1368 8
M 041C 8
MO O
10 0 SW supply to Ctst. Air 3
M8 t '.
At 0/C TC-Q Coolers Line isolation PI V valve.
SW1379 B
M 041A 4
MO 0/C 10-0 SW u m strainer blowdown 3
M4 G1 At 0
line block valve.
111-1 23 1
trd Intervet lit Program vot. I tevision 01 v&LVE tt$1 1ABLE 10Lt00 (Dilow Compawr C Avil ltlit WuCLE AR POWit PL AN1 lilt [Ms (LRylti Watta lVALVIl CAT.lDWG.N0.l$!!!l ACT.l P01.l CJCI l C.S. OR l C.S. Da l
t t st e lpt !Das lCao.j l
h0.
l & l l
& l tif't l hCau.l ttgij stLitt l Ai,t t e g at t l
t l
l l
l CL.l C00eD. l TYPt l &
l &
l 810. l tt0Vilf l filt l
h0ft3 l
l l
l l
l l FAIL l $4 l l
h0.
l Pitf0PmtD l
l l
l l
l l
} PC's.l OP.
l l
j l
l l
6W1380 6
M 041A 4
M3 0/C 10-Q SW p.ro s t r a i ner tet owdown 3
M 11 GT Al 0
L ine bloc k vetve.
$W1381 I
M 041A MO 0/C 10 0 tw puno strainer blowdown 3
M*7 Cf At 0
(tne block vetve.
$W1382 8
M*041C 6
Mc C
10 0
$W to Arw p.rp suction 3
J4 BF At 0
PI Y time block velve.
$W1383 8
M 041C 6
M0 C
10 0 tw t o Af w pac suc t ion 3
K.9 SF At 0
Pl Y L ine block velve.
SW1395 4
M 041A 20 MO 0
tC-Q C1 5 PGCl SW surely to nonestention 3
0 10 sp Al C
Pl Y corporents L ine isolation velve.
$W1399 8
M 041A 20 M0 C
TC-Q C$ 5 PQCl SW supply to nonessential 3
08 SF Al C
Pl.Y cesponents line isolation valve.
SW1424 8
M 041B 16 A0 0/C 10 0 C13 PQCS CCW MX SW outlet Line 3
C7 BF 0
0 F0 0 tenerature control Pl Y valve.
$W1429 8
M 0418 16 A0 0/C 10 0 C5 3 PQCS CCW Mx SW outlet line 3
C9 at 0
0 70 o tenperature contron Pl.T velve.
SW1434 3
M+0418 16 A0 0/C 10 0 CS 3 PQCS CCW mt SW outlet line 3
C.11 er 0
0 F0 0 terperature control Pl.1 velve.
SW2927 8
M 041B 1.5 Mo C
10 0 Control tocen Emerg. Cond.
3 F7 GT At 0
PI Y SW supply Line isolation valve.
SW?928 s
M 0418 1.5 M3 C
10 0 Control toom Emers. Cord.
3 G 11 Cf Al O
Pt Y SW S4 ply Line isolation valve.
111 1 23 2 e
2rt$ Interval 161 Program Vol. I Revillon 01 VALil 1($1 1ABLE IDLEDO EDi&ON CCMFAkT CAVll lllli NUCLIAR POWit PLAhl
$f$1(Mt 1[PVitt W411t lVALVtl CAT. l DWG. k0. l $l21 l ACf.l PO$.l WJt j C.$. OR l C.S. OR l
OtSCtlPfl04 lC4.)
l No. l 8 l 4
l & l ffP( l NORM.l t!$fl t(Liti l Alt (84Aff l
8 l
l l
l CL. l C00AD. l f fPE l 4 l &
l REo, l tt0 Wilt j ttSt l
hott$
l l
l l
j j
l FA!Ll $4 l l
h0.
l PltFDAM(D l
l l
l l
l l
l Po$. 1 0*.
I I
l l
l l
$W2929 8
M 041C 20 NO 0/C 10 0 SW discha*ge to Inteke 3
A*4
$F At 0/C TC 9 Structure isolation Pl.Y
- valve,
$w2930 M 041C-30 M0 0/C 10 0 SW discherse to intake 3
A*$
$F At 0/C TC 9 Forebay Isoaltion Pl.Y valve.
$W2931 3
M 041C 30 MO 0/C TC 9 SW discharge to coolics 3
A*6 tf Al C
PI f Tower Makeup line block valve.
$W2932 8
M 041C 30 MO C/C TC 9
$W discharge to 3
A.8 et Al C
PI Y Cottection 004 Litw block valve.
$w3962 C
M 041A 6X8 SA C
St*T SW supply header relief 3
E.$
kL h4 0
volve.
$W3963 C
Ma041A 6X8
$A C
St.?
$W s @ ly header relief 3
E 10 RL NA 0
valve.
$W5067 8
M 041C 1
MO 0
10 0
$W to M2 Dilyt{on $lowgr 3-J8 GT At 0
Pl.Y tine isolation valve.
$W5068 8
M 0418 1
MO O.
10 0 SW to H2 Oltution 8 tower 3
J.4 GT At 0
Pl.Y Line isolation valve.
i 111 1+23 3
I 2nd Intervat lli Program vol. I tevisim 01 COLD SKUTDOWN TEST JUSTIFICATION CS-1 SYSTEM SERVICE UATER VALVE (s):
SW57 CATEGORY:
C CLASS 3
FUNCTION:
Return from Cooling Water Heat Exchangers to Service Water Line Check Valve.
ASME SECTION XI QUARTERLY TEST REQUIREMENTSt Verify reverse flow closure.
COLD SHUTDOWN TEST JUSTIFICATION: To verify reverse flow closure during normal operation would require isolating the cooling watoc heat exchangers.
The cooling water heat exchangers are in service during normal operation to remove heat from the turbine condenser.
Isolation of the cooling water heat exchangers during normal operation could result in a turbine trip and forced plant shutdown.
QUARTERLY PARTIAL STROKE TESTINGt N/A COLD SHUTDOWN TESTINGt Verify reverse flow closure.
III-1-23-4 1
,.w...
i
2M intervat lif Program vol.1 Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-2 SYSTEM:
SERVICE WATER VALVE (s):
SW17, SW18, SW19 CATEGORY:
C CLASS:
3 FUNCTION:
Forward flow operability is required to provide full opening of the check valve.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Verify forward ficw.
COLD SHUTDOWN TEST JUSTIFICATION: Quarterly full forward flow testing cannot occur because plant condition does not allow the full forward flow rate conditions.
Full forward flow condition would require the essential inservice heat exchanger (component cooling water) flow to be increase beyond the normal temperature control set point.
This excessive flow would cause excessive heat removal-from equipment being serviced by this heat exchanger. In previous operation the RCP seal have been damaged when these conditions were present.
This and other normal operating heat exchangers could result in temperature transients which could result in e damage or a forced plant shutdown.quipment QUARTERLY PARTIAL STROKE TESTING:
Valves will be partial forward flow tested quarterly.
COLD SHUTDOWN TESTING:
Verify full forward flow.
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III-1-23-5
2rd Intervel llt Progree vol, I tevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-3 SYSTEMt SERVICE WATER VALVE (s):
SW1424, SW1429, SW1434 CATEGORY:
B CLASS:
3 FUNCTION:
These valves modulate to control the service water (SW) flow rate through the component cooling water (CCW) heat exchangers to control CCW system temperature.
Valves are designed to fail full-open on loss of air or open upon a safety system actuation.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS:
Time open and fail open.
COLD SHUTDOWN TEST JUSTIFICATION: These SW control valves control CCW cooling water loop tamperature.
To cycle the inservice valve at power could cause a temperature disturbance, hence potential damage to the running reactor coolant pump seals.
Stroke test of the inservice valve during normal operation would require swapping the running CCW loop.
This too could cause a temperature disturbance and therefore potential damagc to the reactor coolant pumps seals causing a plant shutdown.
Plant Technical Specification 3.4.1.1 requires the reactor coolant pumps and associated support equipment to be operable when the plant is in modes 1 and 2.
QUARTERLY PARTIAL STROKE TESTINGtValves will be stroke tested quarterly if not required to modulate for control of component cooling temperature. If valve is removed from service and has not been tested within the past 92 days then prior to return to service the valve will be stroke tested.
COLD SHUTDOWN Valves will be timed open and failed open if TESTING not done so within the last 92 days.
III-1-23-6
2nd Intervet ist Progree vol. I Revision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-4 SYSTEM:
. SERVICE WATER VALVE (s) _
SW17, SW18, SW19 CATEGORY:
.C CLASS t -
3 FUNCTION:
Service Water Pump Discharge Check Valves.
ASME SECTION XI l
QUARTERLY-TEST REQUIREMENT:
Verify reverse flow closure.
I COLD SHUTDOWN TEST
-JUSTIFICATION: During-normal operation two__of the three Service Water pumps are in operation, The third pump is an installed spare.
The two trains are isolated from each other by
-normally closed manual cross-tie valves.
One 7
of the three pumps supplies cooling to
= nonessential-loads. This pump will-automat-ically align to essential loads when required.
One pump is aligned to essential loads.
To i
perform. reverse flow closure verification on all three pump discharge check valves-during normal operation would require realigning both the manual cross-tie header valves and essential loads. -Realignment of the loads during normal operation could result in temperature and pressure transients-which could result in equipment damage or a. forced plant shutdewn.
. QUARTERLY-PARTIAL STROKE-TESTING Reverse flow closure verification will be performed parterly when the respective SW-pump is aligned as the' standby'or spare pump.
Reverse. flow closure verification Wlll be performed if'a running SW-pump _has been stopped, the respective check valve has not-been tested within 92 days and can be tested without: cross tying essentkal headers.
~ ~ COLD SHUTDOWN L-
' TESTING:
Reverse flow verification will be preformed.at each cold shutdown if not e
preformed-within 92 days.
III-1-23-7
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2nd intervet 1$1 Program vol. I tevision 01 COLD SHUTDOWN TEST JUSTIFICATION CS-5 SYSTEMI SERVICE WATER VALVE (s):
SW1399, SW1395 CATEGORY B
CLASS 3
FUNCTION:
These valves provide isolation from the essential to non-essential header upon Safety Feature' Actuation System Level 2.
The non essential header supplies the Turbine Plant Cooling Water System.
ASME SECTION XI QUARTERLY TEST REQUIREMENTS Time open and closed.
COLD SHUTDOWN TEST JUSTIFICATION: These SW valves will close to maintain essential side integrity by isolating the non-essential cooling water loop.
To cycle the inservice valve at power would cause a tem erature disturbance to the secondary side equ pment, hence potential damage to secondary equ pment. If valve failed in closed position then this would result in tempc.:ature transients causing equipment damage and a forced plant shutdown.
QUARTERLY PARTIAL STROKE TESTINGtIf the valve is not supplying the non-essential header then the valve will be stroked each quarter.
COLD SHUTDOWN If the valve is supplying the non-essential header then the valves will be timed closed if not done so within the last 92 days.
III-1-23-8
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2nd Interval 18f Program Vol. I tevision 01 RELIEF REQUEST RV-1 l
SYSTEMt STATION AIR VAGVE(s):
SA502 CATEGORY:
AC CLASS:
2 FUNCTION:
Station Air Containment Isolation Check Valve.
ASME SECTION XI 5
QUARTERLY TEST REQUIREMENTS:
Verify reverse-flow closure.
BASIS FOR RELIEF:
The only method available to verify reverse-flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.
ALTERNATE - TESTING:
Reverse-flow closure will be verified during Appendix J, Type C, testing at refueling.
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III-1-24-2 a
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