ML20027D934
| ML20027D934 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/04/1982 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20027D928 | List: |
| References | |
| PROC-821104, NUDOCS 8211100404 | |
| Download: ML20027D934 (91) | |
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SEQUOYAH NUCLEAR PLANT ,
UNITS 1 AND 2 Dl t g, PUMP AND VALVE I
INSERVICE TESTING PROGRAM i
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8211100404 821104 PDR ADOCK 05000327 p PDR,
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INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES SEQUOYAH NUCLEAR POWER PLANT 1.0 Introduction Under the provisions of 10CFR50.55a, inservice testing of safety related pumps and valves will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. As specified in 10CFR50.55a(b), the effective edition of Section XI with regard to this program is the 1974 edition through the Summer 1975 Addenda (Unit 1) and '
the 1977 edition through the Summer 1978 Addenda (Unit 2). This program identifies the pump and valve inservice testing that will be performed at the Sequoyah Nuclear Power Plant to comply with the requirements of 10CFR50.55.
Where this text refers to specific paragraphs in Section XI, the paragraphs in the 1977 edition through Summer 1978 Addenda is referenced. Refer to the equivalent paragraph in the 1974 edition through Summer 1975 Addends *when required.
2.0 Pump Inservice Testing Program The pump test program shall be conducted in accordance with Subsection IWP of Section XI of the ASME Boiler and Pressure Vessel Code (applicable edition and Addenda) except for relief requested under the provisions of 10CFR50.55a (g) (5) (iii). Appendix A details the inservice testing progra- for all safety related pumps at Sequoyah Nuclear Plant. Table A in Appendix A lists each pump required to be tested in accordance with IWP-1100 of Section XI i of the Code. Each parameter to be measured as well as specific notes con- '
cerning nonconformance are also listed.
2.1 Pump Testing Frequency Present regulatory policy requires that all safety related pumps installed in water-cooled nuclear power plants be tested in accordance with the ASME Code,Section XI, Subsection IWP. The purpose of these tests is to collect '
data to be used in assessing the operational readiness of pumps during their service life.
There are two reasons for conducting periodic pump testing. The first is to record data for assessing operational readiness and the second is to lubricate those bearings of the prime mover and pump which may lose their oil lubrication film due to lack of operation. In order to properly lubri-cate their bearings, these pumps should be " rolled" or " jogged" for a very short time, in order to supply lubricant to wear surfaces.
Starting and running the pump for the purposes of recording data permits an assessment of operational readiness but also subjects the pump to wear.
In determining the most effective and ef ficient pump test frequency, the benefits of running the pump to record this data must be weighed against the costs in degraded pump integrity and reliability. Pump reliability can be adequately demonstrated (and degradation reduced) by conducting the Section XI pump test quarterly, as is consistent with the operational readiness test for valves as presently endorsed by the ASME Code.
k 2.1 Pump Testing Frequency (continued)
In addition, while the latest NRC-accepted version of the ASME Code calls for monthly testing of safety-related pumps, all subsequent Editions and Addenda, including the next Addenda to be approved by the NRC, call for quarterly pump testing. -
Th'us, Sequoyah will fully test each pump quarterly per Section 21. .
3.0 Valve Inservice Testing Program The valve test program shall be conducted in accordance with Subsection IWV of Section XI of the ASME Boilcr and Pressure Vessel (applicable Edition and Addenda) except for relief requested under the provisions of 1QSFR50.55a (g) (5) (iii). The valve test program is included as Appendix C. The codes
, and symbols used to abbreviate the tables in Appendix C are explained in Appendix B. The Calculated Maximum Allowable Stroke Times and the Maximum Allowable Stroke Times shall not be <1.0 second due to the eye and hand coordination involved in manually operating a stop watch. Valves identified in Appendix C, Remarks, by the word " cycled" are only cycled and not timed since a response time is of no concern (except Diesel Air Start Valves) and i is not specified by the owner.
3.1 Category A Valves Valves for which seat leakage is important may generally be classified as pressure isolation valves (PSIV), containment isolation valves (CIV), or both pressure and containment isolation valves. Containment isolation valves falling within the scope of ASME Section XI are tested in accordance with the Section XI requirements of IWV-3410, Category A with the exception of the seat leakage tests (IWV-3420). The seat leakage testing of these valves
, . meets the intent of Section XI, but the actual test procedures shall be in .
accordance with the 10CFR50, Appendix J, Type C, CIV test program. For valves performing a containment isolation function individual valve leak rates are not in themselves significant. The only pertinent leak rate criteria for CIV's is that the total leak rate for all penetrations and valves be less than 0.60 La. The Sequoyah plapt was designed to perform the Appendix J. Type C tests, not the indiv"idual Category A leak test (i . e . , s ome penetration test connections test more than one valve at a time). Accordingly, all CIV seat leak testing shall be performed in accordance with the require-ments of 10CFR50, Appendix J, Type C, in lieu of the Category A requirements of Section XI.
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3.2 Thermal Relief Valves Many safety related systems, particularly those with heat exchangers, have been provided with relief valves. Some of these relief valves are thermal l relief valves (TRV) of small capacity intended to relieve pressure due to j thermal expansion of fluid in a " bottled-up" condition. Experience has ,
shown that failure.of these valves will not result in failure of a system to fulfill its safety related function. Thus, the thermal relief valve is not safety related and such valves have not been included in the program.
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33 Thermal Relief Check Valves Several penetrations have been fitted with small check valves designed to relieve pressure due to thermal expansion of fluid in the pene-tration. These valves will be leak tested in the closed position per Appendix J (10 CFR 50); however, these valves do not have a safety-related function to open. The reasoning is similar to that for the thermal relief valves in that the only occasion that would require the opening function of these valves is when both CIVs are absolutely tight with zero leakage. On that occasion, the thermally-induced pressure increase will be stablilized since only a minute amount of leakage past any barrier would stabilize the penetration pressure.
Sequoyah views these valves as safety related only in the closed position to provide containment isolation function. These valves are identified Appendix C with TRCV written in Remarks.
3.4 Corrective Action Relief is requested from the corrective action requirements of Paragraph IWV-3417. -3427, and -3523 of Section XI. The requirement for corrective action of components in safety systems is adequately covered in the Limiting Conditions for Operation contained in the present Sequoyah technical specifications.
3.5 Systems out of Service Relief is requested from the requirements for testing valves in systems which are out of service before returning those systems to operating status, per IWV-3416 of Section XI. These testing requirements are adequately covered in the Sequoyah technical specifications and plant procedures.
- 3.6 Emergency Diesel Systems * '
, The inservice operability testing of pumps and valves associated with the emergency diesels, except for the fuel oil transfer pumps and air start valves, are excluded from the enclosed test programs. These components are an integral part of the Emergency Diesel System and are functionally tested by the diesel tests. Thus, the functional operability testing of the pumps and valves is performed at a frequency equal to that required by Section XI for either pumps or valves. Additionally, the failure of a pump or valve to perform its intended function will be identified by the failure of the associated emergency diesel to meet its functional requirements. The fuel oil transfer pumps and air start valves are quarterly tested per ASME Section XI and are included in this submittal. The stroke time of the air start valves cannot be measured as there is no visible valve stem movement or indication. The stroke time is verified as acceptable by verifying the diesel comes up to speed in <10 seconds as required by technical specifications.
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3.7 Fail-Safe Actuators All those valves which have a fail-safe actuator are exercised normally using that actuator. Thus, the fail safe actuator is regularly tested when the valve is tested per IWV-3415.
3.8 Valve Timing and Remote Indication During each full stroke test of a power operated valve, the full stroke time shall be measured, in accordance with Section XI, Article IWV-3413.
In addition, each valve with a remote operator shall be exercised using that operator and position indicator for verification of valve position l
during refueling, but not less than once every two years in accordance with Section XI, Article IWV-3300. Uw .
3.9 Passive Valve These valves, which have no Section XI testing requirement, are valves in safety related systems which are not required to change position in order to accomplish their required safety function. Sequoyah has included as B-Passive all manually operated valves which are required by procedure to s be maintained in their safety related position. Any valves which are locked-open or locked-closed in their safety related position are also con-sidered Category B-Passive. Due to the lack of testing requirements, these valves have been excluded from Appendix C. Therefore, relief is requested from the testing Category E valves per the 1974 Edition through Summer 1975 Addenda on Sequoyah Unit 1.
3.10 Cold Shutdown Testing -
Sequoyah will commence testing as soon as the 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 cold shutdown, and will continue -
until all tests are complete or the plant is ready to return to power. Any testing not completed at one cold shutdown will be performed during any subsequent cold shutdowns that may occur before refueling to meet the Code specified testing frequency. For planned cold shutdowns, where Sequoyah will complete all the valves identified in the IST program for testing in the cold shutdown mode, exception to the above 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> start time may be taken (refueling, etc.) . Therefore, a unit shall not be required to remain in cold shutdown to complete cold shutdown testing provided the testing commenced no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter achieving the cold shutdown condtion.
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APPENDIX A SEQUOYAH PUMP INSERVICE TESTING PROCRAM 1
- _ Summary of Information Provided The pump test table (Table A) provides the following information on
, testing requirements: #
- 1. System
- 2. Drawing on which the pump is depicted *
- 3. Speed
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- 4. Inlet Pressure ~
- 5. Differential Pressure i 6. Flow Rate
- 7. Vibration Amplitude
- 8. Observation of Lube Oil Level / Pressure
- 9. Bearing Temperature '
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, SEQUOYAH NUCLEAR POWER PLANT TABLE A--PUMP TEST PROGRAM Drawing Inlet Differential Flow Vibration Bearing Observe Lube Oil Pump Number Speed Pressure Pressure Rate Amplitude 8 Temperature Level / Pressure n Pi Ap Q V Tb Au,xiliary Feed 47W803-2 Note 1 Q Q Note 2 Q Note 9 Yes Water (Motor)
- Auxiliary Feed 47W803-2 Q Q Q Note 2 Q Note 9 Yes Water (Steam)
Centrifugal 47W811-1 Note 1 Q Q Note 2 Q Q Yes i Charging 47N809-1
- Safety Injection 47W811-1 Note 1 Q Q Q Q Q Yes i System Essential Raw 47W845-5 Note 1 Q. Note 4 Note 4 Note 5 Note 9 Note 3 Y Cooling Water Note 11 w
Component Cooling 47W859-1 Note 1 Q Note 4 Note 4 Q Note 6 Yes Containment Spray 47W812-1 Note 1 Q Q Q Q Note 6 Yes Residual Heat 47W810-1 Note 1 Q Q Q Q Note 10 Yes Removal Diesel Fuel Oil 47W840-1 ..ote 1 Note 12 Note 12 Q Q Note 9 Note 12 Transfer Boric Acid Transfer 47N809-5 Note 1 Q Q Note 2 Q Note 6 Yes k'
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NOTES f
- 1. Synchronous or induction motor driven pumps do not require speed check per IWP-4400.
- 2. Flow rate is not required since this pump is tested in a fixed resistance pathway. Relief is requested from the 1937 Edition through Summer 1978 Addenda for Unit 2 since flow indication is not available. .
- 3. This pump uses water lubricated bearings and thus lubrication level measurements cannot be taken.
- 4. These pumps are not equipped with recirculation / test lines. The nature of the system they feed makes it impossible to specify a particular flow path that can always be repeated. Various components which they feed wild some-times require cooling water and sometimes not. Sequoyah will initially establish an in situ pump curve which establishes the relationship between flow and dif ferential pressure in a band around the pump design point.
Subsequent inservice tests would then compare test data to this curve using the allowable test ranges per IWP3210.
- 5. The pump bearings are inaccessible as the pump is submerged in a pit.
- 6. These pumps have no installed instrumentation to measure bearing temperature.
A bearing cap temperature measurement is not considered indicative of bearing temperature due to temperature gradient caused by operation of space coolers, pump location, etc.
- 7. The Auxiliary ERCW pumps are only required for Sequoyah Unit 1.Section XI testing requirements will be deleted when Sequoyah's Technical Specifications are revised to delete those pumps.
- 8. Vibration amplitude cannot be measured to the +5% accuracy required. The "out of tolerance" accuracy of the Licensee vibration test equipment shall -
be +11%.
- 9. Bearings are cooled by pumped fluid and bearing temperature measurements are not required per ASME XI.
- 10. This is a closed coupled pump and does not have a bearing in the pump and ,
therefore, does not require bearing temperature measurements per ASME XI.
- 11. The inlet pressure is calculated for this pump by measurement of lake level.
- 12. No instrumentation exists to measure inlet or outlet pressure or to determine differential pressure. The pump bearings are lubricated by the pumped fluid; therefore, lube oil level or pressure is not measured.
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_ APPENDIX B l
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EXPLANATION OF CODES AND SYMBOLS USED IN TIIE SEQUOYAH VALVE INSERVICE TESTING PROGRAM This Appendix defines the meaning of all codes and symbols used in the valve i test program presented in Appendix C.
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I TABLE B-1 SYMBOLS USED TO DESIGNATE VALVE TYPE l ,
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! SYMBOL Meaning a i
BUT Butterfly BAL Ball CK Check DIA Diaphragm GA Gate GL Globe -
\ ND Needle AN Angle .
PLG Plug RD Rupture Disk REL Relief SC Stop Check SK Spring Check l
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TABLE B-2 SYMBOLS USED TO DESIGNATE VALVE ACTUATOR TYPE VALVE ACTUATOR TYPES SYMBOL Meaning DIA Diaphragm Air Operator M Manual Operator M0 Motor Operator l
SA Self Actuated -
SO Solenoid Operator -
CYL Cylinder / Hydraulic Operator ,,
RD Rupture Disc i
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e TABLE B-3 SYMBOLS USED TO DESIGNATE VALVE POSITION VALVE, POSITIONS SYMBOL Meaning
- M 0 Open C Closed -
LO Locked Open -
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LC Locked Closed ,
TH Throttled
- Valve position determined by other system parameters as in the case of any check valve.
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SYMBOLS USED TO DESIGNATE TESTING REQUIREMENT CATECORY A OR B VALVES QT-1 Exercise valve (full stroke) for operability every 3 months,,,,
in accordance with Section XI, Article IWV-3411.
QT-2 Exercise valve (part stroke) for opecability every 3 months and full stroke at cold shutdown, in accordance with Section X1, Article IWV-3412(a).
CS These valves have been specifically identified in Appendix D as -
valves which cannot be tested during power operation. These valves shall be full stroke tested during cold shutdowns only, in accordance with Section XI Article IWV-3412(a).
SLT Perform a Seat Leak Test during refueling, but not less than once every 2 years. Leak rate limits will be established by the licensee in accordance with 10CFR50 Appendix J.
-SLTP Perform a Seat Leak Test for pressure isolation function as required by Technical Specifications.
ER Exercise full stroke at refueling only.
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! TABLE B-4 (continued)
SYMBOLS USED TO DESIGNATE TESTING REQUIREMENT f -
CATECORY C VALVES .
i CV-1 Exercise valve (full stroke) for operability every 3 months, in accordance with Section XI, Article IWV-3520. c.,
Exercise valve (part stroke) for operability every 3 months
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CV-2 and full stroke at cold shutdown, in accordance with Section XI, Article IWV-3520.
CS These valves have been specifically identified in Appendix D as valves which cannot be tested during power operation. These ,
valves shall be full stroke tested during cold shutdown only, in accordance with Section XI, Article IWV-3520.
SLT Perform a Seac Leak Test during refueling, but not less than once every 2 years. Leak rate limits will be established by the licensee,in accordance with 10CFR50 Appendix J.
SLTP Perform a Seat Leak Test for pressure isolation function as required by Technical Specifications.
RF Test safety and relief valve setpoints in accordance with Section XI, Article IWV-3510.
ER Exercise at refueling only. -
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TABLE B-4 (continued)
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STMBOLS USED TO DESTCNATE TESTING REQUIREMENT i CATECORY D -
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I RD Operational checks of rupture discs shall be performed in accordance with the manufacturers' reconunendations. The frequency of tests shall be specified by the licensee in accordance with Section XI, Article IW-3620.
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APPENDIX C SEQUOYAH NUCLEAR PLANT VALVE PROGRAM '
l Summary of Information Provided The following Tables use the format referenced in the 1978 "NRC Staff '
Guidance for Preparing Pump and Valve Test Program Descriptions and Associated Relief Requests Pursuant to 10CFR50.55a(g)" to give valve descriptions. The following information is provided:
- 1. System Name and Number -
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- 2. Drawing Number
- 3. Valve Number
- 4. ASME Section XI Classification
- 5. Drawing Coordinates of Valve
- 6. Valve Category Per Section XI, Article IWV-2110
- 7. Valve Size
- 8. Valve Type
- 9. Actuator Type 1
- 10. Normal Position
- 11. Testing Required Per Section XI
- 12. Relief Request Required i
j 13. Alternate Testing i
- 14. Remarks (Including Relief Request Numbers, Specific Valve Data, etc.)
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,, , Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: _ (1) MATN STEAM '- - '
DRAWING NO _ Nil 801-i (~'18)'
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ob > M Ho VALVE M
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Dy hO NUMBER ejh 5 U #"
4o h" >dO M b" b REQUIRED UD Td REMARKS U
@}N A W{ gy$
4 FCV-1-4 C-4 B-ACT 32
'l CA CYL 0 QT-2 MSIV See Table D-1 FCV-1-11 2 E-4 R-VT 32 GA CYL 0 QT-2 MSIV See Table D-1 FCV-1-22' 2 C-4 B-ACT 32 GA CYL 0 QT-2 MSIV See Table D-1 FCV-1-29 2 A-4 B-ACT 32 CA
.I CYL 0 QT-2 MATV See Table D-1 FCV-1-147 2 C-4 B-ACT _2 CL DIA C QT-1 FCV-1-148 2 E-4 B-ACT 2 CL DIA C OT-1 FCV-1-149 2 C-4 B-ACT 2 CL DIA C QT-1 FCV-1-150 2 A /* B-ACT 2 CL DTA C OT-1 PCV-1-5 2 C-2 b ACT 6 GA DIA C CS* Cycled BC PCV-1-12 2 D-2 -ACT 6 CA DIA C CS* Cycled BC PCV-1-23 2 F-2 -ACT 6 CA DIA C CS* Cycled PCV-1-30 2 A-2 bACT 6 CA ' DIA C CS* Cycled 1-512 2 F-3 C 6 REL SA C RF 1-513 2 7-3 C t
6 REL SA C RF -
1-514 2 F3 C 6 SA REL C RF
, _1-s1s 2 F-3 C 6 REL SA C RF -
t l 1-516 2 F-3 c 6 REL SA C RF
[ 1-517 2 D-3 C 6i REL SA C RF t
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Sequoyah Nuclear Plant inservice Valve Testing Pr'ogram
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I SYSTEM: (1) MATM AND REHEAF 5 TEAM -
DRAWING NO: 47W801-1 '(R18) d S '
os > m p wg VALVE NUMBER M
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4$H 25 TESTING $g hw
<uh N" NH N M U REQUIRED U$ R$
WW REMARKS a8u 6 <
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M M B" 1-518 ? D-3 C 6 REL SA C RF
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1-519 2 D-3 C 6 REL SA C RF -
1-520 2 D-3 C 6 REL SA C RF 1-521 2 D-3 C 6 REL SA C RF 1-522 2 C-3 C 6 REL SA C RF 1-523 2 c-3 C 6 REL SA C RF 1-524 2 C-3 C 6 REL SA C RF 1-525 2 C-$ c 6 REL SA C RF 1-526 2 C-3 6 REL SA C
_C RF 1-527 2 A-3 C 6 REL SA C - RF 1-528 2 A-3 C 6 REL SA C RF
'1-529 2 A-3 C 6 REL ~ SA C RF i
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Sequoyah Nuclear Plant inservice Valve Testing Program 1
. - .- . . . 1 j SYSTEMS (1T RTF AM CFNFP ATOWhi ntmow -
DRAWING Nor _ 47W801-2 , (R14) t U W oe 9 a: ,, so j VALVE g 5y $ w w f. m j5 TESTING $h h6
- NUMBER 40 $ 8 M M
H 4$H REQUIRED $ REMARKS wg u
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4' FCV-1-181 ? C-2 B-ACT 2 CL DIA 0 QT-1 FCV-1 -18 2 ? F-2 B-ACT 2 CL DIA 0 OT-1 -
FrV-1-191 2 F-2 B-ACT 2 CL DIA 0 OT-1 Fev-1-184 ? B-2 3-ACT 2 CL DIA 0 OT-1 FrV-1-7 2 C-3 B-ACT 2 AN DIA 0 OT-1 FCV-1-14 2 E-3 B-ACT 2 AN DIA 0 OT-1
- FCV-1-25 ? F-3 B-ACT 2 AN DIA 0 OT-1 l FCV-1-32 2 B-3 B-ACT 2 AN DIA 0 QT-1 i
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Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (1) FE N ATER *' - -
DRAWING NO: 47W803-1 '(R12) -
O u oe de a: H o VALVE m 6$ $ w w 0
m 5 TESTING b "d NUMBER O h REQUIRED Ug REMARKS 8
O s - =8A un n-FrV-1-11 -2 C-3 B-ACT '18 GA ID 0 CS*
FCV-3-47 2 E-3 B-ACT 18 CA Fn O CS* -
FCV-1-87 9 G-3 B-ACT 18 cA FO O CS*
FCV-3-100 2 B-3 B-ACT 18 CA ID 0 CS*
3-508 2 C-2 C 16 CK SA -
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3-509 2 E-2 C 16 CK SA -
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3-510 _2 .C-2 C 16 CK SA -
CS*
3-511 2 B-5 C 16 CK SA -
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Sequoyah Nuclear Plant Inservice Valve Testing Program j -
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SYSTEM: (3) AUXTLTARY FEETTtJATER DRAWING NO: _47W80322 '(R19)
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- U $ $ ca $ ga @ ca jU TESTING dy hd NUMBER N d" #$ 5 UD Td N Nuh id REQUIRED h" >, O M >$ E*
REMARKS U
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3-810 '3 G-4 C 10 CK 'SA CV-1 X Yes See PV-9. Pump Test 3-820 1 F-5 C 6 CK SA -
CV-1 X Yes See PV 3-821 1 F-6 c 6 CK .SA -
CV-1 X Yes See PV-12 3-830 2 F-9 c 4 CK SA -
CV-1 X Yes See PV-12
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1-811 2 E-9 C 4 CK SA -
CV-1 X Ye9 See PV-12 3-832 2 c_o C 4 CK SA -
CV-1 X Yes See PV-12 3-833 2 A-9 C 4 CK SA -
CV-1 X Yes See PV-12 3-861 2 F-10 C 4 CK SA -
CV-1 X Yes See PV-12 3-862 2 E-10 C 4 CK SA -
CV-1 X Yes' See PV-12 3-864 3 c-6 C 6 CK SA -
CV-1 X tes See PV-12 3-871 2 F-9 C 4 CK SA -
CV-1 X Yes See PV-12
- 1-872 2 D-9 C 4 CK SA -
CV-1 Y Yes See PV-12 3-873 ? C-9 c 4 CK SA -
CV-1 X Yes See PV-12 3-874 2 A-o C 4 CK SA -
CV-1 X Yes See PV'12 3-891 1 n-R C 4 CK SA -
CV-1 X Yes See PV-9. Pump Test
%Ro? 3 A-8 C 4 CK SA - CV-1 X Yes See PV-9. Pump Test 3-921 2 C-10 C 4 CK MA -
CV-1 X Yes See PV-12 3-922 2 E-10 C 4 CK SA -
- CV-1 X Yes , See PV-12 *,
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. Sequoyah Nuclear Plant inservice Valve Testing Program ,
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system: DRAWING NO: _ 47W803-2 ..(R19) i I
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Td 5 REQUIRED US !2 $ REMARKS l
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{ 3-812. -3 F-5 C lb CK SA C 'CV-1 Pump Test
) 1-815 3 F-6 C 1h CK SA C CV-1 Pump Test -
- 3-818 3 G-7 C 1 CK SA C CV-1 Pump Tast 3-894 3 A-6 C-ACT 3 CK SA C CV-1 Pump Test 3-895 3 A-6 C-PAS 3 CK SA C NONE 3-923 is closed 4
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Sequoyah Nuclear Plant Inservice Valve Testing Program SYSTEM: (3) AUXILIARY FEEDUATER --
DRAWING NO: 47W803-2 YR19).
l 0 W oe de ct: Ho VALVE p NUMBER M
- U" $ $ ga ga 8u hb TESTING Dy hU o
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LCV-3-171 -3 A-8 B-ACT 4 CL DIA C QT-1 1CV-3-171A 3 B-8 B-ACT 2 CA DIA C OT-1 LCV-3-172 1 F-8 B-ACT 3 CL DIA C , QT-1 TcV-3-173 1 D-8 B-ACT 3 CL DIA C OT-1 TcV-3-174 3 C-8 B-ACT 3 GL DIA C OT-1 1CV-3-175 1 A-8 B-ACT 3 CL DTA C QT-1 3'-805 3 FA c 8 CK SA C CV-1 X Yes See PV-9. Pump Test 3-806 3 F- 6 C 8 CK SA C CV-1 Y Ye= See PV-9. Pumn Test FCV-3-116A 3 F-6 B-ACT 8 CA M0 C QT-1 FCV-3-116B 3 F-6 B-ACT R CA MD C OT-1 FCV-3-126A 3 F-7 B-ACT 8 CA th C OT-1 FCV-3-126R 3 F-7 B-ACT CA Fh C A OT-1 FCV-3-136A 3 C-5 B-ACT 10 CA Fn C OT-1 '
vrV-1-116n 3 C-5 B-ACT 10 CA Fo C OT-1
- FrV-1-174A 3 G-5 B-ACT in CA 10 C OTk rmr 1_17oB 3 C-5 R-Art in CA th c OT-1 frV-1-14R 3 F-8 R-Art CA 4 nTA C QT-1 1CV-3-14RA 3 F-R 2 CA B-ACT '
DTA C OT-1 i '~
e W
C-7
~
2 .
Shquoyah Nuclear Plant inservice Valve Testing Program.
SYSTEM: (3) AUXII.IARY FEEDUATER - ' ~
DRAWING NO: 47W803-2 (R19)-
oe n U
>. .: -e vat.ve m
- 5 g Wg m ga aa g8 TESTInc bE R5 HUMBER Noh >d$A' #$ &5 N UD R$
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@{8-REQUIRED M{ gy REMARKS o <
I.CV-3-15 6 '4 E-8 B-ACT '4 CA ~DIA C QT-1 1.CV-3-156A 1 E-8 B-ACT 2 CA DTA C OT-1 YCV-1-164 3 C-8 B-ACT 4 GA DIA C OT-1 T.CV-3-164A 1 C-8 B-ACT 2 CA DIA C OT-1 -
FCV-1-15 ? B-9 B-ACT 4 CA MO- O QT-1 FCV-1-16 2 A-9 B-ACT 4 CA MO O QT-1 FCV-1-17 3 .B-8 3-ACT 4 GA MO O CS*
TCV-1-18 3 B-8 B-ACT 4' CA MO O CS*
PCV-3-122 3 F 'i B-ACT 4 CA DIA O OT-1 Oveled PCV-3-132 3 F-6 3-ACT 4 CA DIA O QT-1 Cycled O
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- S'equoyaliNuclear Plant InseNice Valve Testing Program I I
f SYSTEM: (70 FTFE PROTECTTON- DRAWING NO: 47W8502 10' ,
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' de b$ 6 0 ww "8u 15 < A W W 3e l -
FCV-26-243 -2 B-3 A-ACT '4 CA MO O QT-1, SLT i AL- t' 26-1296 2 B-3 ,-PAS 4 CK SA -
SLT -
t I
FCV-26-240 2 A-9 A-ACT 4 GA MO O QT-1, SLT AG- i 76-1260 2 A-9 PAS 4 CK SA -
SLT i
FCV-26-241 3 D-7 B-ACT 4 CA MO O QT-1 242 3 D-i B-ACT 4 CA MO O QT-1 244 3 c-2 B-AcT 4 CA MO O QT-1 f I
245 3 C-1 B-ACT 4 CA MO O QT-1 i
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(10) MFATING AND' VENTILATING AIR FLOW DRAWING NO: 47W86611 (R23) m w
06 >* tt:
VALVE m 3$ "y ' y g yy Qg 6 TESTING H 0 NUMBER 4" $1 b hd koh O M m
e $ o "5 REQUIRED 3$ O id $
ww REMARKS "8U < =8A M $"
4 FCV-30-7 -2 C-1 T-ACT 24
' BUT CYL C QT-1, SLT FCV-30-8 2 C-2 A-ACT 24 BUT CYL C QT-1, SLT -
FCV-30-4 2 C-1 A-ACT 24 BUT CYL C QT-1, SLT FrV-1n-10 ? c-2 A-ACT 24 Etrr CYL C OT-1. SLT PcV-10-14 2 E-1 A-AcT 74 BUT CYL C OT-1. SLT FCV-10-15 2 E-2 A-ACT 24 BUT CYL C QT-1. SLT FCV-30-16 2 F-1 A-ACT 24 BUT- CYL C QT-1, SLT FEV-10-17 2 F- 2 A-ACT 24' BUT CYL C QT-1, SLT FCV-30-19 2 G-1 A-ACT 24 BUT CYL C QT-1, SLT FCV-30-20 2 G-2 A-ACT 24 BUT CYL C QT-1, SLT FCV-30-37 2 D-10 A-ACT 10 BUT CYL C QT-1. SLT
- PCy-10-40 ? n-4 A-ACT 10 BUT CYL C OT-1. SLT FCV-30-50 2 C-10 A-ACT 24 BUT CYL C QT-1, SLT FCV-30-51 2 C-10 A-ACT 24 BUT CYL C QT-1. SLT -
FCV-30-52 2 C-10 A-ACT 24 BUT CYL C QT-1 SLT
, FCV-30-53 2 C-10 A-ACT 24 BUT CYL C QT-1, SLT
- FCV-30-56 2 E-9 A-ACT. 24 BUT i
CYL C QT-1. SLT i F'V-30-57 C 2 E-10 A-ACT 24 BUT CYL C QT-1. SLT i -
s C-10
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Sequoyah Nuclear Plant inservice Valve Testing Program
._ ...... - . . . . . . . . . - . - - - - - - - ~ ~
5
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(, SYSTEM: . (101 MFATING ANIT*VENTILATINC AIR FLOW ~
b DRAWING NO: 47W866-i(R23) {
i ob > m ~ p H e
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vcV ~40-9A '? C-9 A-ACT 12 BUT 'CYL 0 QT-1, SLT FCV-30-59 2 G-10 A-ACT 12 BUT CYL 0 QT-1, SLT
{ -
i FcV-30-46' 2 B-4 A-ACT 20 BUT CYL 0 QT-1, SLT '
.FCV-10-47 2 B-5 A-ACT 20 BUT CYL 0 QT-1, SLT FCV 8 2 B-7 A-ACT 20 BUT CYL 0 QT-1. SLT FSV-30-134 2 F-9 A-ACT 3/8 CA SO O QT-1, SLT
- 1'
l ~4 n- 5 71 ? F-4 ACAcT 20 I
REL SA C RF SLT 30-572 2 B-5 ACACT 20 REL SA C RF SLT l 30-573 2 B-7 ACACT 20 REL SA C RF SLT
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- . C-31 +
Se. quoyah Nuclear Plant inservice Valve Testing Program- ---
1 SYSTEM: /111 ATn ent:nTTTNTINr? CHTI.I FD WATER ..
DRAWING NOs _ 47W865-5 . -
0 $
oH w a:
VAINE MBER g $@ $$ w $w 0m MO TESTING s (3
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u 0 < =8S M@M $"
FCV-31C-222 '2 A-7 A-ACT 2 CA DIA O QT-1, SLT
~
FrV-11c-223 2 A-8 A-ACT 2 CA DIA O QT-1, SLT -
FCV-31C-224 2 B-7 A-ACT 2 CA DIA O QT-1. SLT FCV-11c-775 2 B-8 A-ACT 2 CA DIA O QT-1, SLT rev_11r_??o 1 D-7 1-art 2 CA DIA O OT-1. SLT FrV-11r-210 2 D-8 A-ACT 2 CA DIA O QT-1, SLT FCV-31C- 231 2 E-7 A-ACT 2 GA DIA O QT-1. SLT s
FCV-31C-232 2 E-5 A-ACT 2 CA DIA O QT-1, SLT -
AC-31C-752 2 B-8 PAS h SK SA C
'~
SLT TRCV '
11r-?!4 AC- -
2 C-8 PAS 4 SK SA C SLT TRCV AC-11c-715 2 E-8 PAS 4 SK SA C SLT TRCV
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Sequoyah Nuclear Plant inservice Valve Testing Program ,
SYSTEM: (32) COMPPESSED ATR - - -
DRAWING NO: 47W8/8-1 . (R13)
U $
oe > m ~ p no VALVE y 3$ $ w w 0w U TESTING [3 m h3 .
$ > g u S 4
1-FCV-32-80 'l C-9 'A-ACT '2 CA DIA 0 CS*, SLT 1-FCV-32 -102 2 D-9 A-ACT 2 CA DIA 0 CS*, SLT -
1-FCV-32-110 2 A-9 A-ACT 2 CA DIA 0 CS* SLT 1-32-287 2 A-10 ^ ICT 2 CK SA -
CS*, SLT AG-1-32-297 2 C-10 ACT 2 CK SA - CS*, SLT 1-32-377 2 D-10 ^ [CT 2 CK SA -
CS*. ST.T l-32-375 2 -B - 9 A-PAS 2 CA M C ST,T 1-32-285 2 C-4 A-PAS 2 CA M C SLT 1-32-295 2 E-9 A-PAS 2 CA M C SLT 2-FCV-32-81 2 F-9 A-ACT 2 CA DTA 0 CS*, SLT I 2-FCV-32-103 2 E-9 A-ACT 2 CA DIA 0 CS*. SLT 2-FCV-32-111 ~
2 C-9 A-ACT 2 CA ~ DIA O CS*, SLT W
Q C-13 *
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Sequoyah Nuclear Plant inservice Valve Testing Program
~
SYSTEM: (32) COMPFESSED ATR - -
DRAWING NO: 47W845-1 '(R13) i i
N 08 >< M H 0 p VALVE
$ b$ hh 3
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gU i NOMBER
l ;
u " 4 2-32-348 -2 E-10 AC-ACT 2 CK ~SA - CS*, SLT $
2-32-358 2 F-10 \C- A('T 2 CK SA -
CS* . SLT -
l 2-32-387 2 G-10 iC-ACT 2 CK .SA -
CS*, SLT 2-32-341 2 E-9 A-Pas 2 GA M C SLT 2-32-353 2 F-9 A-Pas 2 CA M C SLT 2-32-385 2 G-9 A-Pas 2 GA M C SLT '
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SYSTEM: (43)* SAMFLING * * ' ' * - -
DRAWING NO: '47W625'1 "(R15) f l
es 0 u W m ~
sg VALVE
"*SER gg 5$ $$ u $w @u jO TESTING Dh $s 2@ $E 8
!$6 0 !$ l$ MU
- 8A "E0"' "E jaM BE ""^^"
u 4 B"
rev-41-? "1 C-4 A-ACT l'/ 8 CA 'DIA O QT-1, SLT
~
4 FCV-43-3 2 c-5 A-ACT 1/8 GA DIA o QT-1, SLT - i FCV-43-11 2 c-4 A-ACT 3/8 GA DIA C QT-1, SLT i
i FCV-43-12 I 2 C-5 A-ACT 3/8 CA DTA C QT-1, SLT FCV-43-22 2 F-5 A-ACT 1/8 CA DTA O QT-1, SLT FCV-43-23 2 D-5 A-ACT 3/8 CA DIA O QT-1, SLT e
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SYSTEM: (43) SAMPLING -' - -
.i DRAWING NO: 47W625-2 (Rll) '
d $
ou > m y no 6$ lnN VALVE m i
I.TMBER 3*
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FCV-43-34 '2 C-2 A-ACT 3/8 GA DIA C QT-1, SLT FCV-43-35 2 C-3 A-ACT 3/8 CA DIA C QT-1, SLT -
FCV-43-%', 3 C-8 B-ACT 3/8 0 5
CA DIA OT-1 2
FCV-41-s8 3 C-8 B-ACT 3/8 CA DIA 0 QT-1 t
FCV-43-61 1 C-8 B-ACT 3/8 CA DIA 0 OT-1
- FCV-43-64 3 D-8 B-A CT 1/8 CA DIA 0 QT-1 i
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SYSTEM: (43) SAMPLING - - -
DRAWING NO: 47W625-7 '(R13) 1 0 g VALVE to 2< g$ o 2 8 *M 3 4O N *N kN D3 0 "
NUMBER 23 ja8 sn 6
G >s gg $$ REWIRED hS f REMA ES o < o a J W 3e g
FcV-43-75 <2 D-6 A-ACT 3/8 CA DIA C QT-1, SLT FCV-43-77 2 D-7 A-ACT 3/8 CA DIA C QT-1, SLT .
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! SYSTEM: (43) SAMPLING *' - '
DRAWING NO: 47W625-1$ (R9) 8 -
N OH > K n H O VALVE y 5@ $ u $w $y 8 TESTING dM y
NUMBER mj d M Q$ 4$H d 5 hU o M >H REQUIRED UU N$ REMARKS ag @ M y 1
o C*
4 FCV-43-201 9 F-8
~
A-ACT 3/8 CA DIA 0 QT-1, SLT l FCV-43-202 2 C-9 A-ACT 3/8 CA 0 QT-1, SLT DTA -
FCV-43-207 2 C-10 A-ACT 3/8 CA DIA 0 OT-1. SLT FCV-43-208 2 B-11 A-ACT 3/8 DIA CA 0 QT-1, SLT e
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Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (59) DEMINERALIZED WAThR N CASK DECONTAMINATION DRAWING NO: IdtJR S6-1 (R101 0 $
VALVE in h y@ g gg hg g$ TESTING I! **
MBER d Q g REQUIRED U REMARKS "8U 6 b.4 4 =8 M W so A
4 AC-99-671 2 F-3 PAS ~2 CK 'SA -
~
59-5?? ? F-3 A-PAS 2 CA M LC ST T - 59-529 2 F-3 A-PAS 3/4 BUT M C SLT O
l .
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.i . Ssqubpah Nuclear Plant inservice Valve Testing Program SYSTEM:_ (61) ICE CONDENSER- - --
DRAWING NO:_47W81402 '(R13) .
O OB > (4 s wy 3$ H0 VALVE NOMBER o u $w $w q o,, TESTING D yU REQ m ED Ug REMA'ES 8
U 6 < =8A EM B"
- C FCV-61-192 '2 A-5 A-ACT 4 DIA DIA QE-1,SLT 0
Trv-A1-101 2 A-5 A-ACT 4 DIA DIA 0 QT-1, SLT - 61-533 2 A-5 ^' PAS 3/8 SK SA C SLT TRCV FCV-61-191 2 A-5 A-ACT 4 DIA DIA O QT-1, SLT FCV-61-194 2 A-5 A-ACT 4 DIA DIA O QT-1, SLT 61-680 AL-2 A-5 PAS 3/8 SK SA C SLT TRCV FCV-61-96 2 c-10 A-ACT 2 DIA DIA O QT-1, SLT FCV-61-97 2 G-10 A-ACT 2 DIA DIA AL-O OT-1. SLT 61-692 2 C-10 pas 3/8 SK SA C SLT TRCV FCV-61-110 2 H-10 A-ACT 2 DIA DIA O QT-1, SLT FCV-61-122 2 H-10 A-ACT DIA 2 DIA O QT-1, SLT
\
C-21 -
~ _ ._ -
. . ~ Sequoyah Nuclear Plant inservice Valve Testing Prog [am SYSTEM: (62) CHEMICAL & VOLUME CONTROL SYSTEM 1 1 '(R19)
DRAWING NO: 47W809 U U OH S4 0;
, VALVE M d$ $$ w $w 0m jO TESTING DM p H O hU 2h "$5 0$ $ d$ h$ $h REQUIRED g REMARKS 1 8
u 6 < "8 D-M b"
~
t FCV-62-72 -2 A-5 A-ACT '2 CL DIA C Qi-1,SLT FCV-62-73 2 A-4 A-ACT 2 CL DIA 0 QT-1, SLT -
FCV-62-74 2 A-4 A-ACT 2 CL DIA C QT-1, SLT FCV-6 2- 77 2 A-7 A-ACT 2 CL DIA O QT-1, SLT FCV-62-90 2 D-7 B-ACT 3 CA MO O QT-1 !
FCV-62-91 2 D-8 B-ACT 3 CA M0 O QT-1 FCV-62-98 3 .D-9 B-ACT 2 CA MO O CS*
FCV-62-99 3 D-9 B-ACT 2' CA MO ' O CS*
__LCV-62-135 2 H-10 B-ACT 8 CA MO C CS*
LCV-62-136 2 H-10 B-ACT 8 CA M0 C CS*
i
_ FCV-62-61 2 B-7 A-ACT 4 CA MO O CSA, SLT
?
FCV-62-63 2 B-8 A-ACT 4 CL MO O CS*, SLT FCV-62-132 2 E-10 B-ACT 4 CA MO O CS*
FCV-62-133 2 E-lO B-ACT 4 CA MO O CS*
62-519 2 F-9 C-ACT 3 CK SA C CV-1 Pump Test 62-525 2 H-9 C 4 CK SA C CV-1 X ER See PV-1. Pump Test I 62-532 2 C-9 C 4 CK SA C CV-1 X ER See PV-1, Pump Test 62-649 2 C-9 C 2 REL SA C RF g 3 3
. C-22 ,
Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: __ (62) CHEMICAL & VOLUME CONTROL ~
DRAWING No 47W809-1 (R19) o s a U$ No l$
YALVE y ro ra 8m hO TESTING Il b yN N h $h "
>h h $ REW IRED U g REMARKS "8O 6 4 =8A W M us
- 4 67-662 AC-
. -2 A-3 ACT 2 REL SA C RF, SLT 62-675 2 A-10 C 2 REL SA C RF - 62-636 2 B-6 C 2 REL SA C RF 62-500 2 H-10 C 8 CK SA -
CV-1 X 62-639 ER See PV-2 2 C-7 ' iAS 1/4 SK SA SLT (TRCV)62-523 2 11 - 9 C 2 CK SA -
CV-1 Pump Test 62-530 2 .C-9 C 2 CK SA -
CV-1 62-697' Pump Test-2 E-iG C-ACT 4 CK SA -
CV-1 FCV-62-84 Pump Test 1 B-2 B-ACS 2 CL DIA C CS*
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A L
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Sequoyah Nuclea'r Plant inservice Valve Testing Program
~
SYSTEM: (6 "O SAFETY TN77CTION SYSTEM DRAWING NO: 47W811-1 (R20)- l ee n >.
N a: ~e VALVE y 3$ $$ g $a Qw j 6 TESTING Db hd 1.tMBER ,
gg5 REQUIRED U g REMARKS 8
u 6 e "8A EM D" FCV-63-6 2' F-10 B-ACT '4 CA M0 C QT-1 FCV 63-7 2 F-10 B-ACT 4 CA M0 C QT-1 -
FCV-63-23 2 D-6 A-ACT 3/4 CA DIA 0 QT-1. SLT --
- FCV-63-25 2 A-7 B-ACT 4 CA M0 C QT-1 i
FCV-63-26 2 B-7 B-ACT 4 CA M0 C QT-1 FCV-63-38 2 B-8 B-ACT 1 CL DIA O QT-1 =-
FCV-63-71 2 C-6 A-ACT 3/4 CL DIA C QT-1, SLT FCV-63-84 2 C-B A-ACT 3/4 CL DIA C QT-1, SLT FCV-63-94 2 G-7 B-ACT 8 CA MO O CS*
FCV-63-152 2 D-7 B-ACT 4. CA MO O QT-1 -
FCV-63-153 2 E-7 B-ACT 4 CA M0 0 QT-1 -
.FCV-63-156 2 E-6 B-ACT 4 CA M0 C QT-1
- FCV-63-157 2 D-6 B-AC1 4 CA M0 C QT I FCV-63-172 2 F-5 B-AC7 12 CA MO C CS*
FCV-63-93 2 C-7 B-AC1 8 CA MO O CS*
FCV-63-3 2 D-8 B-AC'l 2 CL MO O CS*
FCV-63-72 2 H-6 B-AC1 18 CA MO C CS*
g ,
Y C-25 -
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e Sequoyah Nuclear Plant inservice Valve Testing Program
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SYSTEM: (63) SAFETY INJECTION SYSTEM -' DRAWING NO: 47W811 0 1 '(R-20)
U W U N M ~ H0 VALVE m 5 =g $ w @y o NUMBER m gS y w
d@$ 4 ,g 5 TESTING $1 b h6
X ER See PV-4 Pump Test 63-524 2 E-8 C 4 CK SA -
CV-1 X ER See PV-13 Pump Test Verifies Clo-63-526 2 D-8 C 4 CV-1 sure.
CK SA -
X ER See PV-13 Pump Test Verifies Cio-AC-63-543 1 F-4 2 CK SA CV-1,SLTP sure.
Ar"r AL-X ER See PV-5 63-545 1 E-4 ACT 2 CK SA - CV-1,SLTP X ER See PV-5 63-547 1 D-4 AbE 2 CK SA CV-1,SLTP X FR See PV-5 AC-63-549 1 E-4 ACT 2 CK SA CV-1,SLTP AC-X ER See PV-5 63-551 1 C-1 ACT 2 CK SA -
CV-1.SLTP X ER See PV-5 i AC-63-553 1 H-3 ACT 7 CK SA -
CV-l.SLTP X See PV-5 ER AC-63-555 1 C-3 ACT 2 CK . CV-1,SLTP SA -
X ER See PV-5 63-53, AC-1 G-2 ACT 2 CK SA - CV-1,SLTP X ER See PV-5 63-558 1 E-3 kFf 6 CK SA -
Cv-1.StTP x ER See Pv-s63-559 1 D-1 kbT 6 CK SA CV-1.SLTP X ER See PV-5 63-560 1 E-1 khi 10 CK SA CS*, SLTP X YES See PV-7 63-561 1 D-2 kbf 10 CK SA CS*, SLTP X YES See PV-7 a 63-562 1 D-3 kEf 10 CK SA CS*, SLTP X YES See PV-7 4
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C-26 ' ' '.nc
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, Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (63) SAFETY TNJECTTON SYSTEM-~ '
DRAWING NO: 47W811-1 (R20) os 0 $
> a: so
. VALVE y U$ $$ m $w $u hU TESTING Db d
' NUMBER g$ 8 N $ 4$6 REQUIRED $
o m 6 REMARKS 2{5 U{$My a8U ,
3 @ g A
1C-63-563 -1 F-2 ACT 10 CK SA -
CS*, SLTP Yes See PV-7 63-581 1 B-7 C 3 CK SA CV-1 X ER See PV 63-586 1 E-1 C 1h CK SA CV-1 X ER See PV-6 63-587 1 D-2 C lb CK SA -
CV-1 X ER See PV-6 63-588 1 D-3 C 1 CK SA CV-1 I
X ER See PV-6 63-5R9 1 E-2 C 1 CK SA CV-1 X ER Seq PV-6 AG-63-622 1 .C- 1 ACT 10 CK SA CV-1, SLTP X Yes See PV-7 63-623 1 C-2 ICT 10 CK SA CV-1, SLTP X Yes See PV-7 Ac-63-624 1 C-3 ACT 10 CK SA -
CV-1, SLTP X at-y,, See PV-7 6%6?S 1 C-3 ACT 10 CK SA -
CV-1, SLTP X Yes See PV-7 au-63-632 1 C-3 ACT 6 CK SA -
CS*, SLTP AL-X Yes See PV-8 63-633 1 C-2 ACT 6 CK . SA -
CS*, SLTP AL-X Yes See PV-8 63-634 1 G-3 ACT 6 CK SA - CSA, SLTP Yes X See PV-8 63-635 1 G-2 ^'ECT 6 CK SA -
CS*, SLTP X Yes See PV-8 63-640 1 F-4 ^'iCT 8 CK SA -
CS*, SLTP X Yes See PV-8 63-641 au-1 F-2 ACT 6 CK SA -
CS*, SLTP X Yes See PV-8 63-643 AU-1 F-4 ACT 8 CK SA -
CS*, SLTP l X Yes See PV-8 63-644 1 D-2 AC- ,
ACT 6 CK SA -
CS*, SLTP X Yeb See PV-8 ,
. C-27 '
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. . . . . _ . . - _ . . . . ~ . . - - -
,, , Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (63) SAFETY INJECTION -SYSTEM- '
DRAWItG NO: _47W811-l }R20)-
O 06 >< CC s VALVE y 3$ $ w w 0m fb TESTING h H 0 U
INJMBER mj d N "
4$H REQUIRED Ug g"$
d u og M >b R REMARKS
]^
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63-602 3 A-1 C 'l REL SA C RF 63-603 3 A-3 C 1 REL SA C RF - 63-604 3 A-4 C 1 REL SA C RF 63-605 3 A-6 C 1 REL SA C RF 63-626 2 G-7 C 2 REL SA C RF 63-627 2 C-7 C 2 REL SA C RF 63-637 2 F-6 C 3/4 REL SA C RF 63-534 2 E-7' C 3/4 REL SA C i RF 63-535 2 D-7 C 3/4 REL SA C RF 63-536 2 D-7 C 3/4 REL SA i
C RF i 63-511 2 D-10 C 3/4 REL SA C RF 63-570 2 B-S C 1 CK SA -
CS*
CV-1 Pump Test 63-528 2 E-8 C 3/4 CK SA -
CV-1 i
I '
Pump Test
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. C-28 '
i l
. Sequoyah Nuclear Plant inservice Valve Testing Program
~
SYSTEM: (67) ESSENTIALRA51COOLINGUdTER DRAWING NO: J47W84f-l '(R16) i N
eH >< a: $
wo VALVE g to $@ g@ g gg gg $ TESTING WMBER EQUIED
$1 b h3 E U g mms a8o 6 h = n.8 E W B" FCV-67-67 '3 C-7 B'ACT
'6 BUT NO
' C OT-1 FCV-67-65 3 C-7 B-PAS 6 BUT MO C NONF -
FCV-67-66 3 C-11 3-ACT 6 BUT M0 C QT-1 FCV-67-68 3 C-11 B-PAS 6 BUT M0 C NONE 67-508A 3 C-11 C-ACT 6 CK SA -
CV-1 DIESEL TEST 508B 3 C-8 C-ACT 6 CK SA -
CV-1 DIESEL TEST 511A 1 C-11 C-PAS 6 CK SA -
NONE 513B 3 C-8 C-PAS 6 CK SA -
NONE S1?A 1 C-10 C-ACT 8 CK SA -
CV-1 DIESEL TEST 512B 3 C-9 C-ACT 8 CK SA -
CV-1 DIESEL TEST 517A 3 C-8 C-ACT 8 CK SA -
CV-1 DIESEL TEST 517B 3 C-10 C-ACT 8 CK SA -
CV-1 DIESEL TEST
. I a -
s C-29' ,
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Sequoyah Nuclear Plant inservice Valve Testing Program .
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, SYSTEM: (67) ESSENTIAL RiW COOUING W'ATER
/ DRAWING NO: _ 47W845-1 IR16) -
1 l
i3 VALVE m yy > x -
N mo
- a u $" w $w $w TESTING 9
NUMBER N O" d d$ 4 o(j 4 N O
[3 m h6 Moh >e N m >e H REQUIRED U$ id $
ag e h5" =y O gg REMARKS
< W g-0-67-669A -3 H-3 C-PAS 24 CK SA h0NE AERCW DELETED 0-67-669B 3 H-3 C-PAS 24 CK SA -
NONE AERCW DELETED j FCV-67-12 3 E-1 B-pas 36 BUT MO O NOM;f, AERCW DELETED i 14 3 D-1 B-PAS 36 BUT MO O NONE AERCW DELETED 360 1 E-2 B-PAS 24 BUT NO O NONE I AERCW DELETED 363 3 E-4 B-PAS 24 BUT H0 O NONE AERCW DELETED h 364 3 E-1 B-PAS 36 ,
BUT MG 0 NONE 365- AERCW DELETED 3 D-i B-PAS 36 ' BUT MO O NONE AERCW DELETED '
366 3 E-3 B-PAS 24 Birr M0 O NONE AERCW DELETED
?67 3 E-3 B-PAS 24 BUT NO O NONE
! AERCW DELETED 67-656A 3 E-2 C-PAS 30 CK SA -
NONE AERCW DELETED 67-656B 3 E-3 C-PAS 30 CK SA -
FONE AERCW DET ETED FCV 361 3 E-2 B-PAS 30 i BUT MO O NONE AERCW DELETED
- FCV-67-362 3 E-3 B-PAS 30 BUT H0 O NONE-AERCW DELETED i
~
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, Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM:_ (67) ESSENTIAL RAW C00bNG' WATER DRAWING NO:_47W845 2 2 }RIS)-
oe13 i u m W VALVE 5@ -o in u $w 0m d TESTING Il b $U j
ah $E l$$
$ $ $$ l$ $~5 RE @ IRED U gj REMARYJ 1 8 o 6 < =8S M W d" l FCV-67-151 '3 C-6 B'-ACT 24
~
BUT MO C IE-1 FCV-67-152 3 C-7 3-ACT 24 BUT MO C QT-1 -
FCV-67-123 3 C-9 B-ACT 24 BUT MO C QT-1 4
1 FCV-67-126 3 E-8 B-ACT 18 BUT M0 C QT-1 FCV-67-125 3 C-8 B-ACT 18 BUT MO C QT-1 FCV-67-126 3 D-7 B-ACT 18 BUT MO C QT-1 FCV-67-147 3 A-6 B-ACT 24 BUT M0 C QT-1 l Frv-67-Al 3 H-10 B-ACT 24 BUT MO O QT-1 FCV-67-82 3 H-9 B-ACT 24 BUT MO O CT-1 FCV-67-127 3 B-10 B-ACT 8 BUT MO O QT-1 FCV-67-128 3 B-10 B-ACT 8 BITT MO O QT-1 -
t FCV-67-146 3 C-7 B-ACT 24 BUT MO O CS*
- __FCV-67-223 3 A-6 24 BUT M0 E-Act C QT-1 FCV-67-424 3 A-9 B-ACT 24 BUT MO O QT-1 -
FCV-67-478 3 B-- 7 B-ACT 24 BUT MO O CS* .
t 4
9 4 e C-31 '
i
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j Sequoyah Nuclear Plant inservice Valve Testing Program l -
SYSTEM: (67) ESSENTIAL RAW COOLING WATER ~
PRAWING HO: 4 N845-3 ER14) -
i o-0 $
9 c: so VALVE to 5$ $ u $u @y j6 TESTING Da y6 j ,1 h $ h g h W IRED U g n$u N
asu =sA 8 < u n ne l
FrV-67-141 'l A-4 'A-ACT '2 GA MO O hT-1,SLT j 67-580D 2 A-3 ^ICT 2 C SA -
CV-1, SLT -
FCV-67-142 _
2 A-4 A-ACT 2 CA MO O QT-1 SLT
- i l FCV-67-298 2 A-4 A-ACT 2 CA MO O QT-1, SLT I
SLT TRCV j FCV-67-138' 2 B-4 A-ACT 2 CA MO O QT-1. SLT 67-580B 2 B-3 ACT 2 CK SA -
CV-1, SLT I FCV-67-119 2 B-4 A-ACT 2' GA MO O QT-1, SLT '
FCV-67-297 2 B-4 A-ACT 2 CA MO O QT-1, SLT l 67-585B 2 B-4 PAS b CK SA -
SLT TRCV FCV-67-133 2 B-4 A-ACT 2 CA MO O QT-1. SLT -
l 67-580C 2 B-3 ^'AC1 2 CK SA - CV-1, SLT FCV-67-134 2 C-4 A-AC1 2 GA MO O QT-1, SLT
- FCV-67-296 2 C-4 A-AC1 2 GA MO O QT-1, SLT - !
^'
67-585C 2 C-4 pat b CK SA -
SLT TRCV.
$ I FcV-67-130 2 C4 A-AC'l 2 CA MO O QT-1, SLT i
67-580A 2 AG-C-3 ? cK ic.i SA -
CV-1. ST.T FCV-67-131 2 C-4 A-AC1 2 CA MO O QT-1, SLT g ..,
C-32 .-
, , Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING NO:_ 47W845-3 (R14) i i
m
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28 a sn M >D gM gly REWIRED 48 g REMARKS 8 6 s
u 4 o A M M se 4 ,
rim-67-?os '2 C-4 A-ACT 2 CA M0 O QT-1, SLT '
67-585A 2 C24 ^' PAS CK SA -
SLT TRCV -
FCV-67-112 2 D-4 A-ACT 6 BUT MO O CS*, SLT FCV-67-111 2 D-4 A-ACT 6 BUT MO O CS*, SLT !
AL-67-575D 2 D-4 PAS h CK SA -
SLT TRCV FCV-67-107 2 D-4 A-ACT 6 BUT MO O CS*, SLT 67-562D 2 D-4 AC CT 6 CK I SA -
CS*. SLT FCV-67-104 2 E*- 4 A-ACT 6 BUT MO O- CS*, SLT FCV-67-103 2 E-4 6 5 A_-ACT BUT MO O CS*, SLT 67-575B AC- i 2 E-4 PAS 4 CK SA -
SLT TRCV FCV-67-99 2 E-4 A-ACE 6
' BUT MO O CS*, SLT 67-562B 2 E-4 A [CT 6 CK '
SA -
CS*. SLT
67-575C 2 F-4 ^' PAS h CK SA -
j FCV-67-91 2 F-4 A-ACT 6
' BUT MO O CS*, SLT 67-562C AC-2 F-4 AcT 6 CK SA -
CS*. SLT FCV-67-88 2 C-4 A-ACT 6 BUT MO O CS*, SLT a
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4 Sequoyah Nuclear Plant inservice Valve Testing Program ;
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SYSTEMt (671 ESSENTTAL R'AW COOLING WATER DRAWING NO: 47W845 '-3 (R14) i E $
0 E< > CC p HO
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NUMBER mh ,c 8 M d" $ REQUIRED Ug 22 U du M >b H REMARKS og u
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FCV-67-87 -2 G-4 A-ACT ~6 BUT 110 0 C$*,SLT 67-575A 2 G-4 PAS 15 CK SA -
SLT TRCV -
FCV-67-83 2 G-4 A-ACT 6 BUT MO O CS*, SLT AC-67-562A 2 G-4 ACT 6 CK SA -
CS* SLT i
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( C-34 -
Sequoyah' Nuclear Plant inservice Valve Testing Program SYSTEM: (67) ESSENTIAL RAW COOLING A'TER DRAWING NO: 147W84$-4 '(R15) o 0
VALVE d =g u m ,
wo pM o ga y @g 6 TESTING Ub hM h % >h h a DN U NN a8U !$ < z8 EM hh" A*
FCV-67-168 3 C-7 3-ACT 1h DIA CA 0 QN-1 FCV-67-170 3 C-9 3-ACT 1 DIA CA 0 QT-1 .
FCV-67-176 3 D-7 B-ACT 1h CA DIA C QT-1 FCV-67-182 3 D-9 B-/.CT 1 GA DIA C QT-1 FCV-67-184 3 D-7 B-ACT lh CA DIA C QT-1 FCV-67-186 3 D-9 B-ACT 1 CA DIA C QT-1 FCV-67-188 3 .E-7 B-ACT 1 CA DIA C QT-1 FCV-67-190 3 E-9 B-ACT 1 CA DIA C QT-1 FCV-67-342 3 G-7 BRACT 2 CA DIA 0 QT-1 FCV-67-344 3 G-9 B-ACT 2- CA DIA C QT-1 FCV-67-346 3 E-8 B-ACT 1 GA DIA 0 QT-1 FCV-67-%8 3 E-9 B-ACT 14 CA ' DIA C QT-1 FCV-67-350 3 E-7 b-ACT lh CA DIA 0 QT-1 FCV-67-352 3 E-9 B-ACT lh CA DIA C QT-1 FCV-67-354 F-7 3_ B-ACT lh CA DIA- 0 QT-1' FCV-67-356 3 F-9 B-ACT 1h CA DIA C QT-1 FCV-67-162 3 B-7 B-ACT 2 CA DIA 0 QT-1 FCV-67-164 3 B-9 B-ACT i
2 CA DIA C QT-1 g l .,
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Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEMt_ (67)ESSENTIALRAWC00LIl[GWATER DRAWING NO: 47W845-5 (R6)-
t U
o > u $
uo VALVE MBER to d =y $$ w w @w l5 TESTING Db y 53 g O g REWIRED U g MRKS 8 0 < =8A EM o $"
4 FCV-67-205 3 G-9 3-ACT '6 BUT M0 O
- QT-1 FCV-67-208 3 G-10 B-ACT 6 BITT HO O QT-1 -
67-723A 3 B-3 C 24 CK SA -
CV-1 Pump Test 67-724A 3 B-3 C 24 CK SA -
CV-1 Pump Test 67-723B 3 D-3 C 24 CK SA -
CV-1 Pump Test 67-724B 3 D-3 C 24 CK SA -
CV-1 Pump Test 67-743A 3 G-3 C 24 CK SA -
CV-1 Pump Test 67-744A 3 c-3
~
C 24' CK SA -
CV-1 Pump T'est 67-743B 3 E-1 C 24 CK SA -
CV-1 Pump Test 67-744B 3 E-3 C 24 CK SA -
CV-1 Pump Test FCV-67-489 3 D-4 B-ACT 24 BUT HO O QT-1 -
FCV-67-492 3 B-4 B-ACT 24 Bttr ' MO O QT-1 e
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- C-37 *
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i SYSTEM:_ (68) REACTOR COOLANT SYSTEM ., ..
DRAWING NO: 4.7W813-1 (R16) i t
(3 9 a:
pung a $ M M hg h TESTING D s Nu O N N U hh ED
@ g g 6 hU REMARKS
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! FCV-68-333 1 B-3 3-ACT 3 GA M0 O
' QT-1 PCV-68-340A 1 B-3 3-ACT 3 CL DIA C CS*
PORV -
PCV-68-332 1 B-3 B-ACT 3 i
GA MO O QT-1
, PCV-68-334 1 B-3 i B-ACT 3 GL DIA C CS*
68-563 PORV 1 A-3 C 6 REL SA C RF 68-564 1 A-4 C 6 REL SA C RF '68-565 l A-- 4 C 6 REL SA C RF
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N Sequoyah Nuclear Plant inservi~ce Valve Testing Program -
1 s.( ~ .. . - -
- SYSTEM: (77) _ WASTE DISPOSAL SYSTEM ,,
DRAWING NO: 47W830-6 ,(R21)
U U oe > a: uo VALVE NUMBER gM d$ $ u u @u 5 TESTING ba p
5 g d h REQUIRED U REMARKS +
asu B < =aA w a ne FCV-68-305 -2 G-6 1-ACT '3/4 CL' DIA 0 QT-1, SLT FCV-63-64 2 B-5 A-ACT 1 GL DIA C QT-1. SLT -
AC-77-868 2 G-6 ACT 1 CK SA - CS*, SLT AC-77-849 2 B-6 ACT 1/4 CK SA - CS*, SLT L '
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-Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM:_ (70) COMPONENT COOLING SYSTEM _
DRAWING NO: _4E859-i (R12)
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,VAINE gy 3$ $ w $y @w j8 TESTING N h6 NUMDER m$
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y p j 70-791 1 F-9 'C '8 CK 'SA -
CV-1 70-538 3 E-3 C 4' REL SA C RF - 70-504 3 E-8 C 16 CK SA -
CV-1 Pump Test 70-504A 3 C-8 C 16 CK SA -
CV-1 Pump Test 70 504B 3 D-8 C 16 CK SA -
CV-1 Pump Test e
9 9
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SYSTEM: (70) COMPONENTCOOLINGSiSid!' ^
DRAWING NO: 47'd8 59-5 R12) -
0 oe >< a: $
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$ $w jU MBER w 0m TESTING DM hd gO $ gg5REQUIRED U g REMA RKS a8o 8 < =8 A NN se FCV-70-66 J E-3 B-ACT 2 AN DIA 0 QT-1 FrV-70-207 3 A-2 3-ACT 10 BUT MO O QT-1 -
FCV-70-197 3 B-6 3-ACT 20 BUT MO O QT-1 FCV-70-198 3 B-6 B-ACT 20 BUT M0 O 1
QT-1 FCV-70-206 3 G-10 B-ACT 10 EUT MO O QT-1 FCV-70-194 3 B-4 B-ACT 20 BUT M0 0 QT-1 FCV-70-193 3 B-4 B-ACT 20 BUT MO O QT-1 FCV-70-208 3 B-1 B-ACT 10' BUT MO O QT-1 FCV-70-1 3 H-6 B-ACT 12 BUT MO C QT-1 FCV-70-11 3 H-5 B-ACT 12 RUT MO O OT-1 E ,
j k C-42 '
t Sequoyah Nuclear Plant inservice Valve Testing Program l SYSTEM:. (70) COMPONENTCOOLINGS[STkN' i DRAllING NO: 4W859-2 (it14) .
d y i
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8 6
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'2 E-9 PAS 'If CK SA -
' TRCV 70-679 2 H-4 ICT 3 CK SA -
CS*, SLT -
4G-
SLT ac- TRCV 70-692 2 G-4 ACT s 6 ' CK SA -
CS*. SLT FCV-70-II3 2 E-3 A-ACT 6 BITT MO O QT-1 SLT i
FCV-70-85 2 D-10 A-ACT 6 BITI MO O QT-1.SLT i
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Sequoyah Nuclear Plant inservice Valve Testing Program 4
SYSTEM:_ (70) COMPONENTCODLINGS[STbM
' ~
i- DRAWING NO:
i _47W859-2 (R14)-
i i to VALVE o" > a g
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REL 'SA C RF, FrV-70-140 SLT 2 G-3 \-ACT 6 BUT MO FCV-70-134 O CS*, SLT 2 H-3 4-ACT 3 GA MO O CS*, SLT FCV-70-89 2 E-9 A-ACT 6 BUT MO O CS*, SLT FCV-70-92 2 E-10 A-ACT 6 BUT MO FCV-70-90 O CS*, SLT ,
2 E-10 A-ACT 6 BUT MO l O CS*, SLT FCV-70-87 2 H-9 A-ACT 3 CA MO O CS*, SLT e
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DRAWING NO: _4Vt/859 5 IR7) -
vAtyt = yg u ya du g Tesn Na bE
- "E" h lE!Of 0 !$ $$ yl **U"
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FCV-70-153 3' F-3 B-ACT 18 BUT M0 C Qi-1 FrV-70-156 3 F-4 3-ACT 18 BUT MO C QT-1 -
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. C-45 - -
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' Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (72) CONTAINMENT SPRAY- SYSTEM ~
DRAWING NO: 47W812-1 ' (Rll)
I 0 $
De > M HD VALVE NUMBER gy *$ 5 $ w $w @w jo~ TESTING p
hy hU 28 d"a d #
U d UDo e m > D" ge$ 2 o "5 REQUIRED $! $
ww REMARKS a8O 6 < "8A gW D*
pC <
i FCV-72-2 i, 'l B-4 A-ACT ~12 CA M0 C QT-1, SLT FCV- 72-21 2 B-10 B-ACT 12 CA MO O QT-1 -
i FCV-72-22 2 D-10 B-ACT 12 CA M0 O QT-1 FCV-72-39 2 D-4 A-ACT 12 CA M0 C QT-1, SLT FCV-72-40 2 E-4 B-ACT 8 CA M0 C CS*
FCV-72-41 2 F-4 B-ACT 8 CA MO
' C CS*
72-528 2 D-7 C 12 CK SA CV-1 72-529 Pumo Test 2 B-1 C 12 CK SA -
CV-1 I Pump Test 72-547 2 D-3 C 12 CK SA -
CV-1 X Yes See PV-10 72-548 2 B-3 C 12 CK SA -
CV-1 X Yes See PV-10
, 72-555 2 F-3 C 8 CK SA -
CV-1 X' Yes See PV-10
- 72-556 2 E-3 C 8 CK '
SA -
CV-1 X Yes
- See PV-10
, FCV-72-13 2 B-7' 3-ACT 2 CA MO C QT-1 FCV-72-34A 2 C-7 3-ACT 2 CA MO C QT-1
- 72-506 2 D-9 C 12 'CK SA -
CV-1 Pmm Tear 72-507 ? R-4 e 19 rY MA PU.1 Pumn Test FCV-72-20 2 B-9 B-ACT 12 CA MO O OT-1 FCV-72-23 2 D-9 B-ACT 12 GA MO O QT-1 a
l .
C-46
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- Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: D41 RESTDUAL NEAT REMOVAI, SYSTEM DRAWING HO 47W81d11 (R11) i 4
0 9 os u m - so var.vs = 5g gg a m 8m TcSTInc beg 25
! !R 9 E
g d b b lg 6 ** "'**
lg h atxAaxs U A
- C vcV-74-1 1 G-3 A-ACT 14 CA M0 C CS*, SLTP
- FCV-74-2 1 C-3 A-ACT 14 CA M0 C CS*, SLTP -
1 FCV-74-3 3 E-9 B-ACT 14 CA MO O QT-1 FCVi-74-16 2 F-4 B-ACT 8 BUT DIA 0 QT-1 l FCV-74-21 2 C-9 3-ACT 14 'CA MO O OT-1 FCV-74-28 2 C-4 3-ACT 8 BUT DIA 0 QT-1 FCV-74-33 2 -E-4 B-ACT 8 GA MO O CS*
, FCV-74-35 2 C-4 B-ACT 8 CA MO CS*
i O FCV-74-12 2 F-6 B-ACT 2 CA MO O OT-1 74-Mia 2 F-7 c B EK SA -
CV-? Pumn Test: see Table D-1 i 74-515 2 C-7 C 8 CK SA -
CV-2 Pumn Test: see Table D-1 *
! FCV-74-24 2 B-6 B-ACT 2 CA ' MO O QT-1 74-505 2 G-3 C 3 REL SA C RF l
l s .
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1 C-47 . ,
Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (771 UARTF nTSPMf7 SYSTEM N DRAWING NO: 47V83021 '(R14) n > e g m we
FCV-77-18 2 B-5 A-ACT 1 DIA DIA 0 QT-1, SLT FCV-77-19 2 B-6 A-ACT 1 DIA DIA 0 QT-1, SLT FCV-77-20 2 C-6 A-ACT 1 DIA DIA C QT-1, SLT l
FCV-77-9 2 D-1 A-ACT 3 DIA DIA 0 QT-1, SLT FCV-77-10 2 E-1 A-ACT 3 DIA DIA 0 QT-1, SLT l
4 4
0 9
M C-48 .
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- C-55 -
3
PV-1 System: Chemical and Volume Control System Valve: 62-525, 62-532 Class: 2 Category: C
< Function: Opens to admit charging pump flow to the boron injection j tank during safety injection. ,
Impractical .
Requirement: Exercise valve at full flow on a quarterly basis, Basis for Relief: The centrifugal charging pumps cannot be run s'. full flag during operation for charging or through the cold leg injection lines due to undesirable temperat are and/rir boron concentration transients. CCP cannot be run at full flow during CSD with Rx vessel head in place due to the inability to letdown that full flow. This would result in a low temperature overpressurization of the RCS.
Alt.
Testing: Test valve at normal charging flow quarterly and verify that it will open to pass at least the minimum design required flow during each refueling.
Frequency for Alt.
Testing: Part stroke quarterly and full stroke at refueling.
3 4
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4 C-56
PV-2 i
System: Chemical and Volume Control System j Valve: 62-504 i Class: 2
, Category: C
- Function
- . Opens to admit flow from refueling water storage tank to the centrifugal charging pumps and closes to prevent .
backflow to RWST during recirculation mode of ECCS.
7
!' Impractical' Requirement: Exercise quarterly at full flow.
Basis for .g Relief: Charging pumps cannot be run at full flow taking suction from the RWST without causing undesirable RCS temperature and/or boron concentration changes resulting in boration and power changes and could result in a plant trip. Full flow cannot be obtained during CSD with Rx vessel head in I place. (See PV-1).
Alt.
Testing: Exercise at full flow at refueling during system performance tests and part stroke at reduced flow during cold shutdown.
Verify valve will backseat quarterly.
l Frequency j for Alt.
Testing: Full stroke once per refueling and part stroke during cold shutdown (but not more of ten than every three months).
Verify valve vill backseat quarterly.
I 1
e i C-57 1
1
, _ _ _____. , _ . , _ . . . , _ , . _ . . , . - . , , - , - _ _ ~ . _ , , , . . - , _ _ _ _ . . . _ , . . . . _ , ,_ . . , . _ _ _ _ . _ . _ . , _ _ _ _ _ _ _ _ , , _ _ . . . _ _
PV-3 System: Safety injection System Valve: 63-502 Class: 2 Category: C Function: Opens to admit flow from RUST to the RHR pumps during safety injection. Closes to prevent flow to RWST Juring -
recirculation mode of ECCS.
Impractical Requirement: Exercise valve quarterly a't full flow.
a.
Basis for Relief: The RHR pumps do not develop sufficient head to pump to the reactor at normal operating' pressures. The pump recirculation flow path does not include this check valve. The refueling cavity dewatering line cannot be used because the valve alignment required to use it results in degrading both trains of RHR. Capabilities of the CVCS letdown system preclude use during cold shutdowns. Backseating of 63-502 during power operations would require closure of FCV-63-1 and inoperability of both trains of low head SIS.
Alt.
Testing: Exercise at refueling outages during system performance tests. Verify check valve backseats (for recirculation ECCS mode) during cold shutdowns.
Frequency -
- for Alt.
Testing: Exercise once per refueling. Backseat during cold shutdown but not more often than every three months.
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C-58 i
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PV-4 Safety Injection System -
System:
Valve: 63-510 Class: B Category: C Function: Opens to admit flow.from RWST to the SIS pumps during safety injection, .
Impractical
- Requirement: Exercise valve quarterly at full flow, Basis for Relief: SIS pumps do not develop sufficient head to pump to the RCS at normal operating pressures and the pump recirculation line will not pass full flow. RCS letdown. capability will not allow pumps to be run at full ~ flow during cold shutdown.
Alt.
Testing: Cycle valve at reduced flow once per quarter during SIS pump test and at full flow once per refueling during system performance test.
Frequency for Alt.
Testing: Part stroke quarterly, full stroke per refueling.
e C-59
a
P_V-1 63-557, 4
System: Safety Injection System 63-547,63-559, 63-549,63-558, 63-545, Valve: 63-551, 63-555,63-553. I 1 LOCA Class: AC i
Category: ' Opens to admit flow from SILOCA, intersystem pumps to RCS dur ng )
Function: and closes to prevent 1mpractical Exercise quarterly at full flow. y
.w Requirement:
come 7 Basis for SIS pumps do not develop sufficient head to overuse of anoth Relief: normal RCS pressure. i t in the RCS.
in an undesirable temperature trans enallow full flow testing Letdown capability will not with reactor head on. h valves Technical Specificat' ion 4.4.6.2.2ation and during requires t ese to be leak tested following valve actu k tested in the last l cold shutdown if they have not been down not leaTherefore, to exceed relief is nine months.
stroking of these valves during cold k shutercising during refueling once per nine months and full stro e ex outages.
ld shutdown, not to i
Valve closure will be verified duringf rmed. coper nine months w exceed once boundary leak test required by 4.4.6.2.2 is per o full stroke Part stroke exercise during coldLeak shutdown as required and Alt. test Testing: exercise during refueling outages.
by Technical Specification 4.4.6.2.2.
Frequency to exceed once per Leak for Alt. Part stroke every cold shutdown not ling outage.
Testing: nine months and full stroke each refueby Technical Specification test at the frequencies required 4.4.6.2.2.
C-60 A
k PV-6 System: Safety Injection System i Valve: 63-581, 63-587,63-588, 63-569,63-566 Class: 1 Catego ry : C Function: Open to admit flow from boron injection tank to the RCS during safety injection. ,
Impractical Requirement: Exercise valve on a quarterly basis at full flow.
l Basis for Relief: RCS letdown capacity will not allow full flow injection.s with the reactor vessel head on. Valve cannot be part stroked without discharging heavily borated water from the boron injection tank to the reactor. This would cause an undesirable temperature and boron concentration transients which could result in a safety injection or dnit trip. If the BlT and injection lines are not flushed completely to the vessel, boron plateout will occur in the non heat-traced portion of the injection lines. The last 4 valves are in parallel and individual branch line flows are only measured during refueling testing since instrumentation is not available to measure the individual branch flows.
Alt.
Testing: Part stroke valve (63-581) during cold shutdown and*'
exercise valve at full flow during refueling during i system performance tests. Part stroke the combination of parallel valves (63-586, 587, 588, 589) during CSD and full stroke them during refueling during system performance tests.
Frequency for Alt. .
Testing: Part stroke valve during cold shutdown (but not more often than every three months), full stroke once per refueling.
i' C-61
T PV-7 System: Safety Injection System Valve: 63-622, 63-623,63-624, 63-625,63-560, 63-561,63-562, 63-563 Class: 1 Category: AC.
Function: Opens to admit flow from cold leg accumulators to the RCS .
during safety injection and closes to prevent intersystem a LOCA.
Impractical Requirement: Exercise quarterly at full flow.
es Basis for relief: These valves cannot be cycled at full flow without removing the fuel from the core, removing the internals package and causing a rapid depressurization of the RCS from above
, 650 psig to atmospheric pressure. This is an unreasonabic burden and could cause damage to the reactor vessel.
Technical Specification 4.4.6.2.2 requires these valves to
' be leak tested following valve actuation and during cold shutdown if they have not been leak tested in the last nine months. Therefore, relief is requested to allow partial stroking of these valves during cold shutdown not to exceed once per nine months.
Valve closure will be verified during cold shutdown not to exceed once per nine months when the pressure isolation boundary leak test required by 4.4.6.2.2 is performed.
Alt.
Testing: Part stroke exercise using SIS or RHR pump during cold
, shutdown not to exceed once per nine months and full stroke i
- exercise during refueling outage. Leak test as required by Technical Specification 4.4.6.2.2.
. Fraquency I
for Alt.
Testing: Part stroke during cold shutdown not to exceed once per nine months and full stroke during refueling outage. Leak test at the frequencies required by Technical Specification 4.4.6.2.2.
t C-62 i
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P V-8 System: Safety Injection System Valve: 63-632, 63-633,63-634, 63-635,63-640, 63-641,63-643, 63-644.
Class: 1 Category: AC Function: Opens to adapt flow from RHR pumps to RCS during LOCA and '
closes to prevent intersystem LOCA.
Impractical Requirement: Exercise quarterly at full flow.
Basis for ==
Relief: RHR pumps do not develop sufficient head to overcome normal RCS pressure. Use of another pump would result in an undesirable temperature transient in the RCS and possible t
I Techncial Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation and during cold shutdown if they have not been leak tested in the last 2
nine months. Therefore, relief is requested to allow full stroking these valves during cold shutdown not to exceed once per nine months.
Valve closure will be verified during cold shutdown not to exceed once per nine months when the pressure isolation boundary leak test required by 4.4.6.2.2 is performed.
1 Alt.
Testing: Full stroke exercise during cold shutdown. Leak test as
- required by Technical Specification 4.4.6.2.2.
Frequency for Alt.
j' Testing: Full stroke exercise during cold shutdown not to exceed once per nine months. Leak test at the frequencies required by Technical Specification 4.4.6.2.2.
1 i
C-63
PV-9 i
System: Auxiliary Feedwater Valve: 3-805, 3-806, 3-810, 3-891, 3-892.
Class: 3 Category: C Function: Opens to admit auxiliary feedwater flow or steam flow to auxiliary feedwater pumps. The first three valves ,
above also closes when the ERCW is aligned to the auxiliary feedwater pump suction.
Impractical Fequirement: Exercise valve quarterly at full flow.
Basis for Relief: Exercising these valves during power operation would result in severe thermal shock to the auxiliary feedwater nozzles and cause SG level transients and a unit trip.
Alt.
Testing: These valves will be part stroked during the associated pump test and full stroked during hot standby not to exceed once per three months. The first three valves will be backseated quarterly.
Frequency for-Alt.
Testing: Part stroke quarterly and full stroke during HSB not to exceed once per quarter. Backseat the first three valves
, quarterly.
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C-64
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PV-10 System: Containment Spray Valve: 72-547, 72-548, 72-555, 72-556 Class: 2 Category: C Function: Opens to admit flow from the containment spray and RHR pumps to the spray headers.
- Impractical Requirement: Exercise quarterly at full flow.
Basis for Relief: Testing these valves with water will deluge the contain=nt.
Testing with air could set off a containment isolation signal .
from high, high containment pressure.
Alt.
Testing: Test with air during spray header nozzle test as required by Technical Specification 4.6.2.1.
Frequency for Alt.
Testing: At least once every five years.
l l
l l
} C-65
PV-ll System: Upper Head Injection System Valve: 87-558, 87-559,87-560, 87-561,87-562, 87-563.
Class: 1 Category: AC Function: Opens to admit upper head injection fluid to reactor vessel during rapid depressurization. .
J Impractical Requirement: Exercising at full flow quarterly.
Basis for Relief: Plant was not designed to allow full flow inservice .,
testing. To test at full flow it would be necessary at minimum to remove all fuel, remove reactor internals, install a temporary impingement plate and drain the reactor coolant cystem. The resultant extended down time due to additional fuel movement, storage problems, water chemistry cleanup and refill operations presents an unbearable operational burden.
Technical Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation and during cold shutdown if they have not been leak tested in the last nine months. Therefore, relief is requested to allow partial stroking of these valves during cold '
shutdown not to exceed once per nine months.
Valve closure will be verified during cold shutdown not to exceed once per nine months when the pressure isolation
. boundary leak test required by 4.4.6.2.2 is performed. .
Alt.
Testing: Part stroke ' exercise during cold shutdown and leak test as
, required by Technical Specification 4.4.6.2.2.
Frequency for Alt.
j Testing: Part stroke every cold shutdown not to exceed once per nine months. Leak test at the frequencies required in Technical Specification 4.4.6.2.2.
e
- C-66
i PV-12 System: Auxiliary Feedvater Valve: 3-820, 3-821, 3-830, 3-831, 3e832, 3-833, 3-861, 3-862, 3-864, 3-871, 3-872, 3-873, 3-874, 3-921, 3-922 Class: 3 Category: C Function: Opens to afmit flow to cream generators, ,
Impractical Requirement: Exercise quarterly at full flow.
Basis for Relief: Exercising these valves during power operation would 4 result in severe thermal shock to tiie auxiliary feedwater nozzles and cause SG 1 eve 1' transients and a unit trip.
These valves are routinely operated during operation of the auxiliary feedwater system during hot standby.
Alt.
s Testing: Full flow will be verified through these checks during HSB not to exceed on.e per quarter.
e sy
(
C-67
' PV-13 i,
System: Safety Infection System Valve: 63-524, 63-526 Class: 2 Category: C Function: Opens to admit flow from SIS pumps to RCS during LOCA.
4 Impractical Requirement: Exercise quarterly at full flow.
Basis for Relief: SIS pumps do not develop sufficient head to pump to the RCS during normal operation.
Alt.
Testing: Part stroke valves during cold shutdown and full stroke
'. exercise valves during refueling. Verify valve closed quarterly during pump test.
Frequency for Alt.
g Testing: Verify closed quarterly, part stroke during cold shutdown not to exceed once per nine months and full stroke during refueling.
i e
G C-68 I
I i
APPENDIX D
_ VALVES TESTED ONLY DURING COLD SHUTDOWN CONDITIONS l
Valves listed in Table D-1 are therein specifically identified by the Licensee av valves which cannot be exercised during power operation, per Section XI, Article IWV-3412(a). The table lists the System, Valve Number and the Basis for Cold Shutdown Testing for each valve listed in Appendix C which is being tested on a cold shutdown frequency. ,
Table D-1 System Valve Basis for Cold Shutdown Testing Main Steam FCV-1-4 Full stroke exercising of these'4alves FCV-1-ll during operation could cause SG level FCV-1-22 transients which could result in a FCV-1-29 plant trip. These valves will be part stroked exercised quarterly and full
- stroked exercised during cold shutdown.
Compressed Air FCV-32-80 Exercising these valves during operations FCV-32-81 results in a loss of control air to con-FCV-32-102 trol valves inside containment and could
- FCV-32-103 result in valves going to their failed FCV-32-110 position and resulting in a unit trip.
4 FCV-32-111 FCV-32-287 1
FCV-32-297
- FCV-32-377
, FCV-32-348 i
FCV-32-358 I FCV-32-387
- Main Steam FCV-1-17 Closing these valves during power oper-FCV-1-18 ation causes a loss of steam to the steam driven auxiliary feedwater pump. Failure in the closed position will result in no i heat sink for the loss of all AC power
! accident.
Chemical and Volume
, Control System FCV-62-84 Exercising these valves during operations l violates the pressurizer spray water tem-t perature differential of 320 F (Technical Specific.ition 3.4.9.2) and would result in a rapid depressurization of the RCS i
and a unit trip and/or safety injection signal.
e D-1 -
Table D-1 (continued)
System Valve Basis for Cnid Shutdown Testing Main Steam PCV-1-5 Opening valve during power operation will PCV ,1-12 cause a steam generator level transient PCV-1-23 which could result in an inadvartent PCV-1-30 safety injection signal and/or plant trip.
Feedwater FCV-3-33 Exercising these valves during power FCV-3-47 operation causes a loss of feedwater to FCV-3-87 the loop they supply. When feedwater flow FCV-3-100 is restored, the resulting SG 1evel shrink
'3-508 could cause a reactor trip.
3-509 .
3-510 3-511 Chemical and FCV-62-61 Exercising valves during operation would Volume Control FCV-62-63 cause loss of seal water return and probab]
System damage to the reactor coolant pump seals.
Chemical and FCV-62-98 Exercising valves during operation results Volume Control FCV-62-99 in isolation of the miniflow path of the System centrifugal charging pumps and could result in pump damage.
Chemical and FCV-62-132 Stroking these valves during power Volume Control FCV-62-133 operation would cause unacceptable boron Systen LCV-62-135 transients causing RCS boration and power LCV-62 -136 transients which could result in a unit trip.
Safety Injection FCV-63-1 Exercising valve during operation results in losing suction from RWST to both trains of residual heat removal.
Saf ety Injection FCV-63-5 Exercising the valve during operation isolates both SIS pump suction lines from the refueling water storage tank.
Safety Injection FCV-63-22 Exercising valve quarterly isolates both System trains of safety injection from their normal flow path to the cold legs.
k D-2
Table D-1 (continued) ,
) System Valve Basis for Cold Shutdown Testing Safety Injection FCV-63-3 Exercising valve during operation results System in isolating the recirculation line to both trains of pumps. If the pumps started without recirculation, severe damage to both pumps could occur. s i Safety Injection Closing or opening these valves during and Residual Heat operations results in the ineperability Removal System FCV-63-172 of the cold leg injection path to provide FCV-74-33 its required flow rate (common mode failure)
FCV-74-35 =
Safety Injection FCV-63-93 Closing these valves during operation 1
System FCV-63-94 results in less than the required number of RHR cold leg injection flow paths operable.
Safety Injection FCV-63-72 These valves are associated with the System FCV-63-73 containment sump and their operation during FCV-63-8 power operation could cause flooding of FCV-63-ll lower containment or would result in inoperability of both trains of low head
- safety injection. FCV-63-8 and -11 are interlocked with FCV-63-72 and -73.
Safety Injection 63-570 Exercising this valve during power System operation could cause unacceptable boron concentration changes in the boron injection tank as the continuous recircu -
lation of the tank would have to be stopped and stratification would occur..
t Safety injection 63-563 These valves are in the residual heat 1 System 63-560 removal rump injection lines and the RHR 63-561 pumps do not develop sufficient head to 63-562 open the valves during operation. Inj ection 63-635 through these lines using another pump 63-633 would result in overpressurization of the 63-632 RHR lines behind the check valves and 63-634 cause an undesirable temperature transient 63-640 in the RCS which would cause a safety 63-641 injection. ,63-643 63-644 D-3
1 Table D-1 (continued)
System Valve Basis for Cold Shutdown Testing Essential Raw FCV-67-146 Failure of these valves in the closed i Cooling Water FCV-67-478 position would result in loss of cooling System to the RCP oil cooler, thermal barriers and seal water llTX.
i Essential Raw FCV-67-83 Exercising valve quarterly causes a loss Cooling Water FCV-67-87 of flow to control rod drive coolers and j System FCV-67-88 reactor coolant pump motor coolers.
- FCV-67-91 i FCV-67-95 FCV-67-96 .
FCV-67-99 FCV-67-103 FCV-67-104 FCV-67-lli FCV-67-107 FCV-67-112 Essential Raw 67-562 A/B/C/D These valves normally pass water to the i Cooling Water control rod drive coolers and the reactor i System coolant pump motor coolers. Exercising i the valve causes a loss of flow to this equipment.
Reactor Coolant PCV-68-340A NRC has requested that the pressurizer System PCV-68-334 PORV's be tested during cold shutdown j rather than during power operation.
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- . Component Cooling FCV-70-1!0 Exercising valve during operation results-System FCV-70-92 in loss of cooling water flow to all 4
FCV-70-89 eight reactor coolant pump oil coolers.
Component Cooling FCV-70-134 Exercising valves during operation
. System FCV-70-87 rer,ults in loss of cooling water flow FCV-70-90 to all four reactor coolant pump thermal I barrier coolers resulting in possible seal failure and loss of a RCP and a unit j trip.
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Table D-1 (rontinued) 4 System Valve Basis for Cold Slyutdown Testing Componect Cooling 70-679 This valve normally passes water to
(
System the thermal barrier coolers. Removal from service for testing will cause a loss of flow to all four TB coolers; thus, introducing the possibility of -
i seal failure on all four reactor coolant pumps and a LOCA or unit trip.
Component Cooling 70-692 This valve normally passes flow to the System reactor coolant pump oil cooler. Removal 1
from service for testing while ECP's are running will result in overheating and subsequent loss of all four RCP's and a unit trip.
Containment Spray FCV-72-40 These valves are interlocked with the System FCV-72-41 containment sump valves. Exercising these valves during operations could result in flooding of lower containment or would i
result in inoperability of both trains of low head safety injection.
Residual Heat FCV-74-1 Valves have interlocks to prevent opening Removal FCV-74-2 them when RCS is above the RHR design temperature and pressure. Exercising valve during operation results in over-j pressurizing RHR.
1 Residual Heat 74-514 These valves cannot be full stroked quar-.
I Removal 74-515 terly since opening HCV-74-34 is a common mode failure alignment. These valves will be part stroked quarterly during j the pump test and full stroked during cold I
shutpown, but not to exceed once per three months. ,
l Reactor Coolant 77-868 Cycling these valves during power operation i System 77-849 shuts down nitrogen supply inside contain-l ment to a number of components and systems. Personnel radiation exposure l and valve inaccessibility also prohibits quarterly exercising of these valves.
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Table D-1 (continued)
System Valve -
Basis for Cold Shutdown Testing Primary Water 81-502 Exercising this valve results in loss System of primary water to the RCP stand pipes and PRT. Personnel radiation exposures and valve inaccessibility also prohibits exercising these valves quarterly. -
Upper Head 87-558/559 Exercising these valves during power Inj ection 87-560/561 operation would necessitate removal of 87-562/563 both trains of Upper Head Injection from service to prevent overpressurization of UHI during the test. The test Elow path would require charging flow to be distrib-uted to the UHI Check valve test lina which would present sever thermal shock problens. Injection of this cold charging flow into the reactor vessel head results in a positive reactivity addition and a power transient will probably result in a unit trip.
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