ML13333A787
| ML13333A787 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/24/1984 |
| From: | Rosenblum R SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13310B167 | List: |
| References | |
| SO1-V-2.15, NUDOCS 8401270229 | |
| Download: ML13333A787 (76) | |
Text
SAN ON0FRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.15 UNIT 1 REVISION 4 PAGE 1 OF 12 COMPLETE REVISION EFFECTIVE DATE IN-SERVICE TESTING OF VALVES PROGRAM TABLE OF CONTENTS SECTION PAGE 1.0 OBJECTIVE 2
2.0 REFERENCES
2 3.0 PREREQUISITES 3
4.0 PRECAUTIONS 3
5.0 CHECK-OFF LIST(S) 3 6.0 PROCEDURE 3
6.1 Test Interval 3
6.2 Valve Category 3
6.3 Requirements 4
6.4 Corrective Measures
- 9.
6.5 Exceptions 11 6.6 Instrumentation 11 7.0 RECORDS 11 8.0 ATTACHMENTS 12 8.1 Table Information and Explanation of Abbreviations 8.2 System Valve List 8.3 Cold Shutdown Valve Testing Justification Table PAGES CHANGED WITH THIS REVISION: ALL PREPARED BY:
AUTHOR DATE APPROVED BY:
R. M. ROSENBLUM DATE MANAGER, TECHNICAL DDB:0181d/jhm 9401270229 840124 PDR ADOCK 05000206 P
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.15 UNIT 1 REVISION 4 PAGE 2 OF 12 IN-SERVICE TESTING OF VALVES PROGRAM 1.0 OBJECTIVE This procedure defines the requirements for inservice testing of ASME Code Class 1, 2, and 3 valves at San Onofre Unit 1. It is intended that the referenced testing procedures of this program meet the requirements of References 2.1 and 2.2 to the maximum extent practical.
2.0 REFERENCES
2.1 Cross-reference to Licensing Commitment Requirements 2.1.1 American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code,Section XI, 1977 Edition, including Addenda through Winter 1979 2.1.2 Code of Federal Regulations, Title 10, Part 50.55a (paragraphs f,g) dated January 1, 1980 2.1.3 San Onofre Nuclear Generating Station Unit 1 Technical Specifications 2.2 Station Orders 2.2.1 50123-E-12, Calibration and Control of Measuring and Test Equipment used by the Station Engineering Department 2.3 Station Procedures 2.3.1 S01-V-2.14, In-service Testing of Pumps Program 2.3.2 SO1-V-1.12, Containment Penetration Leak Rate Testing 2.3.3 S01-I-2.3, Pressurizer Safety Valve 532 and 533 Pressure Setpoint Check 2.3.4 SO1-I-2.4, Main Steam Safety Valve Pressure Setpoint Check 2.3.5 S01-I-6.64, Crosby Type JO and JB Relief Valve Refueling Preventative Maintenance 2.4 Operating Instructions 2.4.1 501-12.3-15, Turbine Stop Valve Test 2.4 2 SO1-12.4-2, In-service Testing of Valves - Quarterly 2.4.3 SO1-12.7-1, In-service Testing of Valves - Cold Shutdown 2.4.4 S01-12.8-8, In-service Testing of Valves-Refueling Interval 2.4.5 S01-12.9-9, Safety Injection System Check Valve Tests
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.15 UNIT 1 REVISION 4 PAGE 3 OF 12 3.0 PREREQUISITES 3.1 Prior to use of an uncontrolled (pink) copy of this Station Document to perform work, verify that it is current by utilizing one of the following methods:
3.1.1 Checking a controlled copy of any TCNs 3.1.2 Accessing an SCE Document Configuration System (SOCS)
TSO Terminal.
3.1.3 Referencing a current (within one week) Configuration Control Log and associated daily update.
3.1.4 Contacting COM by telephone or through counter inquiry.
3.1.5 Obtaining an uncontrolled (pink) copy of the Station Document from CDM.
3.2 The implementing procedures and Operating Instructions (References 2.3.2 -
2.4.5) shall be.pdated within one month after an approved revision of this procedure is released.
Station Operations and Maintenance Managers shall receive a copy of the approved revision to serve as notification of a revision.
4.0 PRECAT0NS 4.1 The ASME Section XI test requirements (Reference 2.1.1) shall be met to the maximum extent practical.
It is not the intent of this oroceaure to test valves that may place the plant in an unsare condition.
Care should be exercised to insure that no test will be conducted that would violate Technical Specifications or other plant operating contraints.
D 6.0 CH2EK-FFLIT(
6.1 Test interval The valve inservice testing program delineated herein covers a t-?n (10) year interval commencing on January 1, 1973 and.ermina-:ng on January 1, 1988.
6.2 Valve Category Valves are categorized as follows:
6.2.1 Category A -
valves for which seat leakage is limited to a soecific maximum amount in the closed position for fulfillment of their function.
6.2.2 Category B -
valves for which seat leakage in the closed position is inconsequential for fulfillment of their function.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 4 PAGE 4 OF 12 6.0 PROCEDURE (Continued) 6.2.3 Category C - valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves).
6.2.4 Category D - valves which are actuated by an energy source capable of only one operation, such as rupture disks or explosive actuated valves.
NOTE:
Valves covered in this procedure have been placed in one or more of these categories.
When more than one distinguishing category characteristic is applicable, all requirements of each of the individual categories are applicable. Duplication or repetition of common testing requirements is not necessary.
6.3 Recuirements Subsection IWV of Reference 2.1 defines the requirements for inservice testing of Code Class 1, 2 and 3 valves.
Test results are intended to verify valve operational readiness on a continuing basis. Operations Supervisor shall have the responsibility for maintaining the surveillance schedule for all valves.
IST Valve Engineer shall have the IST Programmatic responsibility.
Table III itemizes all valves subject to the test requirements of this procedure including the valve category and test mode.
Following are test requirements for each valve category:
NOTE:
Refer to References (2.3.1-2.4.5) for testing procedures.
6.3.1 Category A and B Valves
.1 TEST FREQUENCY:
Category A and O valves shall be exercised at least once every 3 months, with the exceptions defined below and as noted in Table III.
.2 EXERCISING PROCEDURE Valves shall be exercised to the pcsition required to fulfill their function unless such operation is not practical during plant operation.
If only limited operation is practical during plant operation the valve shall be part-stroke exercised during plant operation and full-stroked during cold shutdown. Valves that cannot be exercised during normal plant operation are specifically identified in Table III and shall be full-stroke exercised during cold shutdown or refueling.
In case of frequent or extended cold shutdowns these valves need not be exercised more often than once every 3 months.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 4 PAGE 5 OF 12 6.0 PROCEDURE (Continued) 6.3.1.2 The necessary valve stem or disk movement shall be established by exercising the valve while observing either an appropriate indicator which signals the required change of valve stem or disk position, or indirect evidence, such as changes in system pressure, flow rate or temperature which reflect stem or disk position.
.3.1 The limiting value of full-stroke time of each power operated valve is specified, where applicable, in Table III.
.3.2 The stroke time of all power-operated valves shall be measured to the nearest tenth second whenever such a valve is full-stroke tested.
.3.3 If an increase in stroke time of 25% or more from the previous test for valves with stroke times greater than ten seconds or 50% or more for valves with stroke times less than or equal to ten seconds is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed.
Valves tested only at cold shutdown or refueling which exhibit an increase in stroke time as specified above, shall be tested each time the plant is in the proper mode.
The valves need not be tested more frequently than once a month. During an extended outage, these valves shall be tested monthly.
Once corrective action is taken, the original test frequency shall be resumed. In any case, any abnormality or erratic action shall be reported.
.4 VALVES 1N REGULAR USE Valves which operate in the :tc se olant ope-ation frequency which wouid -atif"y 7
? exrcisifng requirements of this procedure need not be ad:itionally exercsed, provided that the observations otnerwise recuired for testing are made and analyZed during such ope-ation and
.recorded in the Plant record at intervals -no greater tnan 3 months.
.5 VALVES IN SYSTEMS OUT OF SERV:CE If valves are in a system that is out of service, exercising is not required for such valves except within 30 days prior to the return of the system to service.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 4 PAGE 6 OF 12 6.0 PROCEDURE (Continued) 6.3.1.3.6 FAIL-SAFE VALVES Valves with fail-safe actuators shall be tested by observing the operations of the valves upon loss of actuator power. If these valves cannot be tested once every 3 months, they shall be tested during each cold shutdown; in case of frequent or extended cold shutdowns, these valves need not be tested more often than every 3 months.
6.3.2 CATEGORY C VALVES
.1 SAFETY AND RELIEF VALVE TESTS
.1.1 TEST FREQUENCY Safety and relief valves shall be tested with the following frequencies:
1.1.1 There are 23 safety and relief valves that require testing per IWV-3510. A minimum of seven (7) valves will be tested at each refueling. All valves will be tested in a period of not more than five (5) years (see Reference 2.3.5).
1.1.2 There are two (2) pressurizer relief valves. These will be tested at each refueling shutdown per Technical Specification 4.1.2 (Reference 2.3.3).
1.1.3 There are ten (10) main steam safety valves.
These will be tested at each refueling shutdown per Technical Specification 4.1.2 (Reference 2.3.4).
1.1.4 The scheduling and bookkeeping required for these tests shall be the responsibility of Maintenance.
.1.2 TESTING PROCEDURE Safety and relief valve set poirts will be tested in accordance with ASME Performance Test Code 25.3-1976 (see References 2.3.3, 2.3.4 and 2.3.5).
Bench testing with suitable hydraulic or pneumatic equipment or testing in place with hydraulic or pneumatic assist equipment may be used. Valves so tested are not required to be additionally leak tested in accordance with IWV-3420 (Reference 2.1.1).
.1.3 ADDITIONAL TESTS If any valve in a system fails to function properly during a regular test, additional valves in the system shall be tested as determined by the requirements of Paragraph IWV-3513 of Reference 2.1.1 If any of these additional valves fail to function properly on test, then all valves in the system in this category shall be tested.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 4 PAGE 7 OF 12 6.0 PROCEDURE (Continued) 6.3.2.1.2 CHECK VALVE TESTS
.2.1 TEST FREQUENCY Check valves shall be exercised at least once every 3 months, with the exceptions as defined in paragraph (2.2) below and itemized in Table III.
Check valves are tested in concurrence with Reference 2.3.1 The scheduling of the tests depends on what mode the system has to be in for testing the check valves.
The scheduling and bookkeeping required for these tests will be the responsibility of operations. To determine the operational mode required for valve testing refer to Table III, "Test Mode Column."
.2.2 EXERCISING PROCEDURE Check valves shall be exercised to the position required to fulfill their function unless such cperation is not practical during plant operation.
Normally closed check valves that cannot be operated during normal plant operation are identified in Table II and shall be exercised during cold shutdown or reruelings. In case of frequent cold shutdowns these check valves need not be exercised more often than once every 3 months.
.2.2.1 Normally Open Valves.
Valves normally open during plant operation whose function is to prevent reversed flow, shall be tested in a manner that proves that the disk travels to the seat Promptly on cessation or reversal of flow.
Confirmation that the disk is on its seat shall be by visual ocservation, by observation of aporopr.ate cnessure indications in the system, or by oter.tesit~ve means.
.2.2.2 Normally Closed Valves.
Valves normally closed during plant operation, whose function is to open on reversal of pressure differential, shall be test>d by proving that the disk moves promptly away from tne seat when the closing pressure ciFferential is removed and flow through.the valve is initiated, or a mechanical opening force is applied to the disK.
Confirmation that the disk moves away from the seat shall be by visual observation, by observation o7 substantially free flow through the valve as indicated by appropriate pressure indications in the system, or by other positive means.
This test may be made with or without flow through the valve.
6.3.3 CATEGORY 0 VALVES There are no Category 0 Class 1, 2 or 3 valves at San Onofre Unit 1.
IL SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 4 PAGE 8 OF 12 6.0 PROCEDURE (Continued) 6.3.4 CONTAINMENT ISOLATION VALVES REQUIRING SEAT LEAK TESTS These valves are identified in Table III and shall be tested in accordance with 10CFR50, Appendix J rules at the frequency specified in Reference 2.1.3.
.1 These valves are containment isolation valves and will be tested with a pressure differential in the same direction as when the valve is performing its safety function unless it can be determined that the results from the tests for a pressure applied in a different direction will provide equivalent or more conservative results.
.2 Leakage Rate Analysis.
Leakage rate measurements will be compared with the permissible leakage rates specified by Reference 2.3.
.3 Test Medium.
The test medium used for the leak rate tests will be specified in Reference 2.3.2 for the various valve tests.
6.3.5 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES REQUIRING SEAT LEAK TESTS.
These valves are identified in Table III and shall be tested in accordance to Reference 2.1.1 and 2.1.3.
.1 These valves are reactor ccclant system pressure isolation valves and will be tested with the pressure differential in the same direction as when the valve is performing its function, wit tn.he following exception:
.1.1 Leakage tests involving pressure differentials lower than function pressure differentials are permitted in those types of valves in which service pressure will tend to diminish the overall leakage channel opening,.
as by pressing the disk into or onto the seat with greater force. Gate valves, check valves, and globe-type valves having function pressure differential applied over the seat, are examples of valve applications satisfying this requirement. When leakage tests are made in such cases using pressures lower than function maximum pressure differential, the observed leakage shall be adjusted to function maximum pressure differential value. This adjustmen:
shall be made by calculation appropriate to the test media and the ratio between test and function pressure differential, assuming leakage to be directly proportional to the pressure differential to the one-half power.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 4 PAGE 9 OF 12 6.0 PROCEDURE (Continued)
.2.Leakage Rate Analysis.
Leakage rate measurements shall be compared with previous measurements and with the permissible leakage rates specified in Reference 2.1.3.
.3 Test Medium The test medium used for the leak rate tests will be specified in Reference 2.4.5.
6.3.6 VALVE REPAIR, REPLACEMENT AND MAINTENANCE After a valve or its control system has either been replaced, repaired, or has undergone maintenance that could affect its performance, and prior to the time it is returned to service, it shall be tested as necessary to demonstrate that the performance parameters which could be affected by the replacement, repair, or maintenance are within acceptable limits. Adjustment of stem packing; removal of the bonnet, stem assembly, or actuator; or disconnection of hydraulic or electrical lines are examples of maintenance that could affect valve performance parameters.
6.3.7 CHECK OF VALVE POSITION INDICATOR All valves with remote position indicators shall be visually observed at least every 2 years, to confirm that remote valve indications accurately reflect valve operation.
6.4 Corrective Measures 6.4.1 Category A and B valves.
If a valve fails to exhibit the required change of valve stem or disk position, notify the Shift Supervisor immediately. The valve shall be declared inoperative immediately, and an investigative Maintenance Order shall be initiated to determine corrective action.
NOTE:
It will be the Shift Supervisor's responsibility to determine the technical specification requirements for operability of the affected system.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT I REVISION 4 PAGE 10 OF 12 6.0 PROCEDURE. (Continued) 6.4.1 (Continued)
When corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup. A retest showing acceptable operation shall be run following any required corrective action before the valve is returned to service.
6.4.2 Category C Valves
.1 Safety and relief valves failing to function properly during test shall be repaired or replaced and shall successfully pass a retest before being returned to service.
.2 If a check valve fails to exhibit the required change of disk position, notify the Shift Supervisor immediately. The valve shall be declared inoperative immediately, and an investigative Maintenance Order shall be initiated to determine corrective action.
When corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup. A retest showing acceptable performance shall be run following any required corrective action before the valve is returned to service.
NOTE:
It will be the Shift Supervisor's responsibility to determine the technical specification requirements for operability of the affected system.
6.4.3 Containment Isolation Valves Requiring Seat Leak Tests
.1 Containment Isolation Valves with leakage rates exceeding the permissible leakage rates specified in Reference 2.1.3 shall be evaluated per Reference 2.3.2 6.4.4 Reactor Coolant System Pressure Isolation Valves Requiring Seat Leak Tests
.1 Reactor Coolant System Pressure Isolation Valves with leakage rates exceeding the permissible leakage rates specified in Reference 2.1.3 will be replaced or repaired.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 4 PAGE 11 OF 12 6.0 PROCEDURE (Continued) 6.4.4.2 For valves 6 in. nominal pipe size and larger, if a leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate by 50% or greater, the test frequency shall be doubled; the test will be scheduled to coincide with a cold shutdown until corrective action is taken, at which time the original test frequency will be resumed.
6.5 Exceptions 6.5.1 Any valve which when exercised (cycled) could put the plant in an unsafe condition should not be tested.
Below are examples of the types of valves that are excluded from exercising (cycling) tests during plant operation.
.1 All valves whose failure in a nonconservative position during the cycling test would cause a loss of system function.
.2 All valves whose failure to close during a cycling test would result in a loss of containment integrity.
.3 All valves, which when cycled, could subject a system to pressures in excess of their design pressures.
NOTE:
Valves which fall into the above classifications are identified in Table III and shall be cycled, as practicable, at each cold shutdown or refueling, but not more often than once every three months.
6.6 Instrumentation Instrumentation used shall meet the requirements of Section XI to the maximum extent practical.
Instruments together with their transmitters where used shall be calibrated in accordance with (Reference 2.2.1).
7.0 RECORDS 7.1 Records pertaining to inservice testing of valves shall be maintained in accordance with Aritcle IWV-6000 of Section XI (Reference 2.1.1).
The records shall include as a minimum the following:
7.1.1 A summary listing consisting of a schedule check-off list for valve testing and bookkeeping processes.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 4 PAGE 12 OF 12 7.0 RECORDS (Continued) 7.1.2 Records of tests and examinations.
7.1.3 Preservice tests results and Manufacturer's Functional Test results.
8.0 ATTACHMENTS 8.1 Table Information and Explanation of Abbreviations (7 pages) 8.2 System Valve List (24 pages) 8.3 Cold Shutdown Valve Testing Justification Table (11 pages) 0181d
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 4 PAGE 1 OF 7 ATTACHMENT 8.1 IN-SERVICE VALVE TESTING TABLE INFORMATION PAGE Reactor Coolant System..................................568766-17 1
Reactor Coolant Gas Vent................................568766-17 1
Chemical and Volume Control System.......................568767-21 2
Auxiliary Cooling System................................56876815 5
Residual Heat Removal................................... 5130354-0 7
Safety Injection System.................................568769-15 7
Reactor Cycle Sampling System...........................568770-12 9
Radioactive Waste Disposal System........................568772-23 10 Steam..................................................568773-14 11 Circulating Water System................................568775-24 12 Miscellaneous Water System..............................568776-22 13 Chemical Feed...........................................568777-16 14 Feedwater and Condensate System..........................568779-22 14 Compressed Air..........................................568780-19 16 Air Conditioning........................................568782-20 17 Turbine Cycle Sampling System............................568783-12 18 Post-Accident Containment Hydrogen Monitoring............568784-18 19 Nitrogen System.........................................568784-18 Diesel Fuel Cil-Storage and Supply (Diesel Unit 1)........5169250-2 20 Diesel'Generator Cooling Water System (Diesel Unit 1).
51'9252-1 20 Diesel Starting Air System (Diesel Unit 1) Sheet 1........5159253-2 20 Diesel Starting Air System (Diesel Unit 1) Sheet 2........5169256-1 21 Diesel Fuel Oil-Storage and Supply (Diesel Unit.2)........5169260-2 21 Diesel Generator Cooling Water System (Diesel Unit 2).
5169262-1 21 Diesel Starting Air System (Diesel Unit 2) Sheet 1........5169263-1 21 Diesel Starting Air System (Diesel Unit 2) Sheet 2........51'9266-2 20 Auxiliary Feedwater System..............................359570-0 22 HLligh Radi1ati on Sa:,mpl ing System............................
5:,30-02 a.or:lists the valve identificat_=-ion r u.;-,er --,
Thown on
.~
- i
- 2. P & ID and Coordinates: References t.*
Do.hcntevav oer and its coordinates.
C.
Class: is the ASME classification of the valves.
- 0.
Valve Category: indicates the catagory assigned to tne valve basec on the definitions of iWV-2000.
Where a valve is normally ex27,pt 7rom the testing per IWV-1200, and is in the direct flow,- oath of the syst.:em, his valve is categorized B passive.
Valve size: lists the nominal pipe size of the valve in incnes.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.15 UNIT I REVISION 4 PAGE 2 OF 7 ATTACHMENT 8.1 F.
Valve type: lists the valve design as indicated by the following abbreviations:
GATE GA GLOBE GL CHECK CK SAFETY SV RELIEF RV BUTTERFLY BTF BALL BALL G.
Actuator type: lists the type of the valve actuator as indicated by the following abbreviations:
MOTOR OPERATOR MO AIR OPERATOR AO SOLENOID OPERATOR SO HYDRAULIC OPERATOR HY SELF ACTUATED SA MANUAL M
H.
Valve position: indicates the normal position of the valve during plant operation; either normally open (0) or normally closed (C).
I.
Stroke direction: indicates the direction which an active valve must stroke to perform its safety function. Also, the direction in which the valve will be stroked to satisfy the exercising requirements of IWV-3410 or IWV-3520. This may be specified as open (0), closed (C),
or both (O&C).
J.
Test: lists the test or tests that will be performed for each valve to fulfill the requirements of Subsection IWV. The following tests and abbreviations are used:
Seat Leak Test:
AT Valve will be seat leak tested at least every two (2) years at the appropriate functional differential pressure.
Full Stroke Exercise Test:
BT Valve will be full stroke exercised for operability in the direction necessary to fulfill its safety function.
0
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 4 PAGE 3 OF 7 ATTACHMENT 8.1 J. (Continued)
Partial Exercise Test:
BTP Valve will be part-stroke exercised when full stroke exercising is impractical.
Check Valve Exercise Test:
CVT Check valve will be exercised to the position required to fulfill its function. This functional test will be verified by the operation of the required system.
Check Valve Partial Exercise Test :
CVP Check valve will be part stroke exercised, (i.e. disc moves away from seat) when full stroke exercising is impractical.
Fail Safe Test:
FST All valves with fail safe actuators will be tested to verify proper fail safe operation upon loss of actuator power.
Position Indication Check:
PIT All valves with remote position indicators will be checked at least once every two (2) years to verify that remote valve indications accurately reflect valve position.
Relief Valve Set Point Check:
RVT Relief and safety valve set points will be verified in accordance with IWV-3510.
K.
Test Mode: indicates the frequency at which the above mentioned tests will be performed. The following abbreviations are used:
Cold Shutdown:
CS Valve testing at cold shutdown is valve testing which commences not later than forty-eight (48) hours after cold shutdown and continues until required testing is completed or plant startup, whichever occurs first. Completion of all required valve testing is not a requisite to plantstartup. Valve testing which is not completed during a cold shutdown will be performed during subsequent cold shutdowns to meet the Code specified testing requirements.
No valve will be tested more often than once every 90 days.
NOTE:
During extended outages the valves will be tested every 3 months. Completion of all valve testing during cold shutdown is not required if plant operating conditions will not permit the testing of specific valves.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE'SO1-V-2.15 UNIT 1 REVISION 4 PAGE 4 OF 7 ATTACHMENT 8.1 K.
(Continued)
Normal Operation:
OP Valve tests with this designation will be performed once every three months.
Reactor Refueling:
RR Valve tests with this designation will be conducted at reactor refueling outages.
L.
Max Stroke Time: lists the maximum allowed full-stroke time in seconds for valves requiring test.
M.
Relief Reouest: References the relief requests contained in the Cold Shutdown Valve Testing Justification Table and Valve Relief Requests submitted to the NRC.
N.
Remarks: lists clarification remarks.
0181d
SAN ON UCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 8
PAGE 5 OF 7 IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2, & 3 VALVES SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
STROKE VALVE VALVE VALVE VALVE ACIR.
NORMAL STROKE TEST TIME RELIEF NUMBER COORD. CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECTION TEST MODE (Sec.)
REQUEST REMARKS EXPLANATION OF NOTES NOTES:
- 1.
All motor operated valves fail-as-is and therefore do not require a fail safe test per IWV-3415.
- 2.
The maximum stroke time associated with this valve is an assigned value in pursuant to IWV-3413.
This stroke time is not a protected value and may be changed with approval of the station technical manager.
- 3.
The maximum stroke time associated with this valve is a protected value and cannot be changed without a revision to the safety analysis or the technical specifications.
- 4.
Stroke times specified for this protected valve are minimum and maximum acceptable values in the given stroke direction.
- 5.
Maximum stroke time for this valve will be provided later.
- 6.
This valve is a pressure relief valve and will be tested at the frequency stated in IWV-3511.
- 7.
The pressurizer safety valves arid main steam safety valves shall be tested per Technical Specification Table 4.1.2.
- 8.
The main steam power operated relief valves shall be tested per Technical Specification Table 4.1.2.
- 9.
Any leakage from this valve is monitored during normal operation per Technical Specification 3.1.4 and is collected in the Quench Tank.
- 10.
The seat leakage test for this valve will be performed in accordance with 10CFR50 Appendix J requirements.
The test frequency is specified in the Technical Specification 11.3.1.
This frequency will not exceed each refueling outage.
- 11.
This valve is within a non-safety related system; however, it is used for containment isolation and therefore will receive a seat leakage test in accordance with 10CFR50 Appendix J requirements.
- 12.
This valve is Type A passive and will only receive a seat leakage test.
- 13.
This valve is an RCS pressure isolation valve and will be leak tested per Technical Specification 3.3.5.
- 14.
This valve is tested every 18 months per Technical Specification 4.15.
SAN ONOFRE 1t GENERAlING StAIION INGINrERING PROCEDURE SOl-V-2.15 UNIT 1 REVISION iI PAGE 6 Of 7 ATTACHMENT 8.1 IN-SLRVICE IFSTING PROGRAM ASM-CI.ASS I, 2,
& 3 VALVES SAN ONIRuE NUCIFAR GENERATING STATION UNIT 1 MAX.
STROKE VALVE VALVE VAl VE VAI VI ACIII.
NORMAL SIROKE TES[
IIME REL IEF NUMBER COORD.
CLASS CATEGORY SIZE tYll (VPE POSITION DIRLCTION TEST MODE (Sec.)
REQUEST REMARKS EXVLANAIION OF NOtES (Continued)
NOTES:
- 15.
The Reactor Coiolat, Gas VeIIL System has been inistalled in the plant.
this valve will be Included In the program oice the NtC al)proves the USe Of' the system.
- 16.
this valve is a remliote ly operated hand control valve.
A maximum stroke time is not required for this valve.
17 Per General Design Criteria (GDC)51, these valves are not required to be automatic and will not be seat leak tested.
18 867 a, b, and c assume leak tightness of the Safety Injection System (Technical Specification 4.2.2).
Therefore, these valves will not be seat leak tested.
EXPLANATION Of ABBREVIATIONS GA GATE GE-GLOBE CK CHECK SV SAFETY l(V RELIEF fill BUTTERFLY IAI.L BALL so SOLENOID AD AIR OPERATOR SA SELF ACTUATED
- y.
HYDRAULIC MO MOTOR OPERATOR N
MANUAL AT SEAT LEAK TEST BT FULL STROKE EXERCISE TEST BTP PARTIAL STROKE EXERCISE TEST CVT CHECK VALVE EXERCISE TEST
SAN ON UCLEAR GENERATING STATION INGINEERING PROCEDURE SO1-V-2.15 UNIT REVISION 4 PAGE 7 OF 7 0
AlIACIIMENT 8.1 I N-SI V ICE I ES II NG PROGRAM ASML-CIASS 1, 2,
& 3 VALVES SAN U)NOE NUCLEAR GENERAT ING STAT ION UNIT 1 MAX.
NORMAl/
STROKE VALVE VALVE VAI VL VAIVt.
ACIR.
FAI I 1)
SIROI(F TEST T IME REL IEF NUMBER COORD.
CLASS CATEGORY SIZE IYIPE TYPE POSITION DIRECTION TEST MODE _(Se_.)
REQUEST REMARKS EXPLANATION O ABBRLVIAIIONS (Continued)
CVP PARTIAL CHECK VALVE EXERCISE TEST RVT SAFETY OR RELIEF VALVE TEST PIT POSITION INDICATION CHECK FST FAIL SAFE TEST CS COLD SIIUT DOWN RR REACTOR REFUELING OP NORMAL OPERATION VRR VALVE RELIEF REQUEST 0/0 NORMALLY OPEN/
FAIL OPEN O/C NORMALLY OPEN/
FAIL CLOSED C/o NORMALLY CLOSED/
FAIL OPEN C/C NORMALLY CLOSED/
FAIL CLOSED FAI FAILS AS IS LO LOCKED OPEN LC LOCKED CLOSED Ol81d
SAN NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SOl-V UNIT REVISION 'I PAGE 1 ATTACHMENT 8.2 IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VALVE NORMAL/
STOKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS REACTOR COOLANT SYSTEM P &
ID 568766-17 (includes CC #26)
CV-530 C-2 1
B 2
GL AD 0/0 O&C BT OP 5-0 Notes 2, FST CS 15-C VRR-6 9
B 2
GL AO 0/0 O&C BT OP 5-0 Notes 2, FST CS 15-C VRR-6 9
A 3/4 BALL AD O/C O&C AT RR 5-0 Notes 2, BT OP 5-C 10 FST CS VRR-6 PIT RR CV-533 C-11 2
A 2
BALL AO O/C C
AT RR 20 Notes 2, 10 BT OP FST CS VRR-6 PIT RR CV-534 C-11 2
A 2
BALL AO O/C C
AT RR 10 Notes 2 & 10 BT OP FST OP PIT RR CV-545 B-2 1
B 2
GL AD C/C C
BT CS 5
Notes 2 FST CS
B 2
GL AD C/C C
BT CS 5
Notes 2 FST CS
C 3x6 RV SA C
RVT RR Note 7 PIT RR RV-533 A-3 1
C 3x6 RV SA C
RVT RR Note 7 PIT RR 1"-600-239 C-11 2
AC 1
CK SA C
O&C AT RR Note 10 CVT CS REACTOR COOLANT GAS VENT P & ID # 568766-17 (includes CC #26)
SV-2401 F-8 2
B 3/4 GA SO C/C 0
BT CS 2
Notes 2, 9 FST CS PIT RR See Attachment 8.3
SAN 0 NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S1-V-UNIT REVISION 4 PAGE 2 4
ATTACHMENT 8.2 IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VALVE NORMAL/
STOKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS REACTOR COOLANT GAS VENT P & 10 # 568766-17 (includes CC #26) (Continued)
SV-2402 E-8 3
B 3/4 GA SO C/C 0
BT CS 2
Notes 2, FST CS 9, 15 PIT RR SV-2403 A-7 2
B 3/4 GA SO C/C 0
BT CS 2
Notes 2, FST CS 9, 15 PIT RR SV-2400 A-7 3
B 3/4 GA SO C/C 0
BT CS 2
Notes 2, FST CS 9, 15 PIT RR SV-3401 F-8 2
B 3/4 GA SO C/C 0
BT CS 2
Notes 2, FST CS 9, 15 PIT RR SV-3402 E-8 3
B 3/4 GA SO C/C 0
BT CS 2
Notes 2, FST CS 9, 15 PIT RR SV-3403 B-7 2
B 3/4 GA SO C/C 0
BT CS 2
Notes 2, FST CS 9, 15 PIT RR SV-300 B-7 3
B 3/4 GA SO C/C 0
BT CS 2
Notes 2, FST CS 9, 15 PIT RR CHEMICAL AND VOLUME CONTROL SYSIEM P & ID # 568767-21 (includes CC #18)
CV-202 B-2 1
B 2
GL AO O&C/C C
BT OP Notes 5 FST CS VRR-6 PIT RR CV-203 B-3 1
B 2
GL AO O&C/C C
BT OP Notes 5 FST CS VRR-6 PIT RR CV-204 C-2 1
B 2
GL AO O&C/C C
BT OP Notes 5 FST CS VRR-6 PIT RR CV-276 D-3 2
B 3/4 GL AO 0/0 O&C BT CS 20-0 Note 2 FST CS 20-C PIT RR CV-304 C-2 1
B 2
GL AO O/C 0&C BT CS 100-0 Note 2 FST CS 80-C PIT RR
SAN ONOFR@LEAR GENERATING STAlION ENCINEERING PROCEDURE SO1-V-2.15 UNIT I REVISION 4 PAGE 3 OF 24 ATTACHMENT 8.2 IN-SERVICE ILSI ING PROGRAM ASME-CIASS 1, 2 & 3 VALVES SAN ONOIRE NUCLEAR GENEHAtING STATION UNIT 1 MAX.
VAIVIE NORMAI/
STOKE VALVE VALVE SIZE VALVE ACIR.
FAILED SIROKE TEST TIME RELIEF NUMBER COORD).
CLASS CATEGORY (INC.HIjS)
IYPE 1YPE POS IION
)IRECTION TEST MODE (Sec,)
REQUEST REMARKS CHEMICAL AND VOLUME CONIROL SYSTEM 11 &
1 IL 5681617-21 (incidcs CC #18)
(Continued)
CV-305 C-2 1
B 2
GL AO C/C O&C
[t CS 100-0 Note 2 UST CS 80-C PIT RR CV-334 11-8 2
8 2
GL AO C/O 0
[ti C
.10 D-6 2
B 2
GL AO O/C C
BT OP 5
Note 2 FST OP PIT RR CV-11 D-6 2
B 2
GL AD O/C C
BT OP 5
Note 2 FST OP PIT RR CV-525 A-6 2
A 2
BALL lfY O/C C
AT RB 30 VRR-6 Notes 2, 81 OP 10
A 2
IALL IlY O/C C
AT RB 30 Notes 2, BI OP
& 10
A 3
BALL IIY O/C C
AT RR 20 Notes 2, I
& 10 FST CS PIT RR CV-528 C-11 2
A 3
BALL IlY O/C C
& 10 fST CS PIT RR FCV-1112 I-l 2
B 2
ANGLE AO O/C O&C BTP OP 30-0 Note 2 BT CS 30-C FST CS PIT RR FCV-1115A 11-1 1
B 2
ANGLE AO 0/0 O&C DTP OP 30-0 Note 2 BT CS 15-C FST CS fCV-1115B 11-2 1
I 2
ANGLE AO 0/0 O&C BIP OP 30-0 Note 2 8i CS 15-C
[ST CS
SAN ONOFRO EAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIf 1 REVISION I4 PACE 4 OF 2 ATTACHMENT 8.2 I11-SEWICE TESTING PROGRAM ASMIE-CLASS 1,
2 & 3 VALVES SAN ONOFRE NUCLEAR CENERATING STATION UNIT 1 MAX.
VAtVE NORMAL/
STOKE VALVE VALVE SIZE VALVE ACIR.
FAILED STROKE TEST TIME RELIEF NUMBER COORD.
CLASS CATEGORY (INCIIF)lYP[
TYPE POSilION DIRECIION TEST MODE (Sec.) REQUEST REMARKS CHVMICAL AND VOLUME CONTROL SYSTEM P &
ID 5687671-21 (includes CC #18) (Continued)
FCV-1115C 1-3 1
8 2
ANGLE AO 0/0 O&C BTP OP 30-0 Note 2 Bt CS 15-C EST CS FCV-11150 li-I 1
B 2
GL AO C/C 0
[ST CS FCV-1115E 1-2 1
B 2
GL AO C/C 0
BT CS Notes 2 EST CS&5 FCV-1115F 11-3 1
B 2
GL AO C/C 0
BT CS 30 Note 2 EST CS MOV-18 11-3 2
B I4 GA MO C/FAI 0
T OP 120 Notes 1 PIT RR MOV-19 1I1I.
2 IT 11 GA MO C/FAI 0
BT OP 120 Notes 1 PIT RR MOV/LCV-llOOC D-7 2
11 11 GA MO O/FAI C
BT CS 20 Notes 1 PIT RR PCV-1115A E-I 2
B 2
ANGLE AO 0/0 C
BT CS 40 Note 2 EST CS PIT RR PCV-1115B 1-2 2
B 2
ANGLE AO 0/0 C
T CS 15 Note 2 FST CS PIT RR PCV-1115C F-3 2
It 2
ANGLE AO 0/0 C
ITT CS
'40
- Note 2
RV-289 0-4 2
C 3x'I RV SA C
RVT Note 6 RV-2004 C-3 2
C 3
RV SA C
RVT Note 6 236-4-C42 F-7 2
C I4 CK SA 0
C CVT CS 247-3-C58 F-5 2
C 3
CK SA 0
O&C CVT OP 248-3-C58 C-5 2
C 3
CK SA 0
O&C CVT OP 264-2-C58 F-3 1
c 2
CK SA 0
c CVT CS
SAN ONOFRO LEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 0 PACE 5 Of 24 A1TACIIMLNT 8.2 IN-SERVICE lEST ING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GENERAT ING STAf ION UNIT 1 MAX.
VAI VE NORMA./
STOKE VALVE VALVE SI/I VAlVE ACTR.
FAILED SIROKE TESf TIME RELIEF NUMBER COO1D.
CLASS CATEGORY INCIIIS)IYPI IYPIT P0SITION DIRLCIION TfST MODE (Sec.)
REQUEST REMARKS CHEMICAL AND VOLUME CONIROL SYSTEM P
IDhi68767-2iLicludes CC #1 (Continued) 272-2-C58 F-2 1
C 2
CK SA 0
C CVT CS 280-2-C58
[-1 1
C 2
CK SA 0
C CVT CS 308-2-C58 B-2 1
C 2
CK SA 0
C CVT CS 338-2-C42 F-5 2
C 2
CK SA 0
0 CVI OP 339-2-C42 F-5 2
C 2
CK SA 0
0 CVT OP 354-2-C58 C-2 1
C 2
CK SA C
O&C CVT CS 362-2-CAl D-5 2
C 2
CK SA C
0 CVT CS AUXILIARY COOLING SYSIEM P & 10 )
568768-15 (includes CC &17)
CV-722A H-5 3
B 1 1/2 GL AO O/C C
[T CS 5
Note 2 fST CS PIT RR CV-722B 11-6 3
B 1 1/2 GL AO O/C C
BY CS 5
Note 2 FSI CS PIT RR CV-722C 11-9 3
B 1 1/2 CL AO O/C C
BT CS 5
Note 2 FST CS PIT RR CV-737A C-7 3
n 6
BALL IIy C/O 0
BT OP 15 Note 2 1ST OP PIT RR CV-737D C-7 3
B 6
BALL lY C/o 0
BT OP 15 Note 2 FST OP PIT RR MOV-720A 8-9 3
B 10 GA MO O/FAI 0
BT OP Notes 1, 2 PIT RRH MOV-720B B-7 3
B 10 GA MO C/FAI 0
BT OP Notes 1, 2, PIT RR&5 RV-721A 11-7 3
C
.1/2x1 RV SA C
RVT Note 6 RV-721B 11-8 3
C 1/2xl RV SA C
RVT Note 6 RV-721C 11-9 3
C 1/2xl RV SA C
RVT Note 6 RV-775A E-5 3
C.
lx2 RV SA C
RVT Note 6
SAN ONOIR
- EAR GENERATING SIAT ION ENGINEERING PROCEDURE SO1-V-2.115 UNIT I REVISION 4 PAGE 6 OF12 ATIACIIMENT 8.2 IN-SIRVICII IES[ING PROGRAM ASME-CI.ASS 1, 2 & 3 VALVES SAN ONOfRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VALVE NORMAL/
STOKE VALVE VAlVE SIZE VAlVE ACII.
FAILLI)
SI ROK F TISI TIME RELIEF NUM1ER COORD.
CLASS CATLCORY ( INCIIES]
YPI lYPE POSi ION DIRECT ION luSt MODE LSec.
REQUEST
_REMARKS AUXILIARY COOLING SYSTEM P & ID # 568768-15 iicludes CC 1171 RV-775B E-3 3
RVT Note 6 RV-775C C-6 3
RVT Note 6 RV-775D E-11 3
C IX2 RV SA C
RVT Note 6 RV-775E D-11 3
C lx2 RV SA C
RVT Note 6 RV-775F E-12 3
C lx2 RV SA C
RVr Note 6 RV-775G E-7 3
C lx2 RV SA C
RVI Note 6 RV-775H
[-8 3
C 1x2 RV SA C
RVT Note 6 RV-7751 1-9 3
C lx2 RV SA C
RVT Note 6 RV-787 B-11 3
C 3xi RV SA C
RVI Note 6 TCV-601A L-6 3
B 8
GL AU O&C/O O&C Il OP 120-0 Note 2
[SI OP 415-L PIT RR TCV-601B E-3 3
B 8
CL AU O&C/O O&C Il OP 120-0 Note 2 FS1 0I, 45-C Pit RR 2-647 C-10 3
C 2
CK SA 0
0 CVT CS 2-6417 G-10 3
C CK SA 0
0 CVT CS 703A-8-C32 B-9 3
C 8
CK SA 0
O&C CVT OP 703B-8-C32 C-9 3
C 8
CK SA 0
O&C CVT OP 703C-8-C32 C-9 3
C 8
CK SA 0
O&C CVT Oi 723A-1-1/2-C38A 11-6 3
C 1 1/2 CK SA 0
C CVT CS 723D-1-1/2-C38A 11-8 3
C 1 1/2 CK SA 0
C CVT CS 723C-1-1/2-C38A 11-9 3
C 1 1/2 CK SA O
CVT CS
SAN ONOFS LEAR GENERATING STAlION ENGINEERING PROCEDURE SOl-V-2.15@
UNIf I REVISION 4 PAGE 7 Of 214 ATTACHMENT 8.2 IN-SIRVICE ILSI ING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GINERAlING STAIION UNII 1 MAX.
VAI VI NORMAI./
STOKE VALVE VALVE SI/E VALVE ACIIt.
AI1-1D SItROKE lESt TIME RELIEf NUMBER COORD).
CLASS CAllGORIY (INQIIS)1YP TYPE POSITION DIRECTION TLST MODE (Sec.
REQUEST REMARKS AUXILIARY COOLING SYSIEM P & ID # 568768-15 (inciudes CC #111 741A-1-1/2-C38 11-6 3
C 1-1/2 CK SA C
O&C CVT CS 742A-1-1/2-C38 H--7 3
C 1-1/2 CK SA C
O&C CVI CS 743A-1-1/2-C38 11-8 3
C 1-1/2 CK SA C
O&C CVT CS RESIDUAL HEAT REMOVAL P &
I0 #
51301351-0 IICV-602 D-7 2
B 6
t1F AO C/FAl 0
DIP OP Note BI CS PIT in closed PIT RR position only MOV-813 F-6 1
B 8
GA MO C/FAI 0
& 2 MOV-814 F-7 1
B 8
GA MO C/FAI 0
& 2 MOV-822A C-2 2
B 6
GA MO C/FAI 0
& 2 MOV-8228 C-11 2
B 6
GA MO C/FAI 0
& 2 MOV-833 E-7 1
B 6
GA MO C/FAI O
B CS Notes 1, PIT RR 2 & 5 MOV-831I L-6 1
V 6
CA MO C/FAI 0
B[
& 2 RV-206 C-2 2
C 2-1/2 I(V So C
RVT Note 6 x
4 819A-6-C54 G-6 2
C 6
CK SA 0
O&C CVT CS 819B-6-C54 11-6 2
C 6
CK SA 0
O&C CVT CS SAFETY INJECIION SYS1(M 1
It1 ji j_
8/69-15 (includes CC #331 CV-875A A-9 2
it 3
GL AO C/C 0
& 5 PIT FR CV-8750 C-9 2
V 3
GL AO C/C 0
SAN NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO-V UNIT REVISION 4 PAGE U WATTACHMENT 8.2 IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VALVE NORMAL/
STOKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS SAFETY INJECTION SYSTEM P &
ID 568769-15 (includes.CC #33) (Continued)
HV-851A B-6 2
B 14 GA HY C/FAI 0
BT CS I4 mi Notes 3 PIT RR 45 max
& 4 HV-851B D-6 2
B 14 GA HY C/FAI 0
BT CS 4 min Notes 3 PIT RR 5 max
& 4 HV-853A B-9 2
B 16 GA HY C/FAI 0
BT CS 3 min Notes 3 PIT RR 6 max
&14 HV-853B D-9 2
B 16 GA HY C/FAI 0
BT CS 3 min Notes 3 PIT RR 6 max
& 4 MOV-356 G-2 1
B 2
GA MO C/FAl 0
& 3 MOV-357 F-2 1
B 2
GA MO C/FAI 0
& 3 MOV-358 E-2 1
B 2
GA MO C/FAI 0
& 3 MOV-850A D-2 1
8 6
GA MO C/FAI 0
BT CS 9.5 min Notes 1, 3 PIT RR 11 max
& 4 MOV-850B C-2 1
B 6
CA MO C/FAI 0
BT CS 9.5 min Notes 1, 3 PIT RR 11 max
& 4 MOV-850C B-2 1
B 6
GA MO C/FAI 0
BT CS 9.5 min Notes 1, 3 PIT RR 11 max
& 4 MOV-866A G-1 2
B 4
GA MO C/FAI 0
& 2 MOV-866B G-2 2
B 4
GA MO O/FAt 0
& 2 MOV-880 E-5 2
B 4
GA MO C/FAI 0
& 5 MOV-883 C-13 2
B 8
GA MO O/FAI C
& 5 MOV-LCV-1100B F-9 2
B 4
GA MO C/FAt 0
& 3 SV702A D-3 2
B 3/4 GA SO C/C C
BT OP Notes 5 & 18 SV702B C-2 2
B 3/4 GA SO C/C C
BT OP Notes 5 & 18 SV702C D-3 2
B 3/4 CA SO C/C C
BT OP Notes 5 & 18 SV702D C-2 2
B 3/4 GA SO C/C C
BT OP Notes 5 & 18
SAN ONOO CLEAR CENERATINC STAIION ENGINEERING PROCEDURE SOl-V-2.1 UNIT 1 REVISION I#
PAGE 9 OF 24 ATTACHMENT 8.2 IN-SER VICE TES ING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1
MAX.
VAIVE NORMAL/
SJOKE VALVE VALVE SIZE VALVE ACIR.
FAII1)
SIROKE TESI TIME RELIEF NUMBER COORD.
CLASS CATEGORY INCHES IYPL TYPE POSITION DIR[CT ION TESI MODE (Sec.) REQUEST REMARKS SAFETY INJECTION SYSIEM P &
10 568769-15 includes CC #33)
(Continued)
MOV-LCV-1100D G-9 2
B 11 GA MO C/FAI 0
& 3 RV-868 A-3 2
C 1
RV SA C
RVT Note 6 RV-882 E-5 2
C 1/2xl RV SA C
HVT Note 6 SV-2900 B-6 2
B 3/4 GA SO C/C 0
BT CS 2
Note 2
8 3/4 GA SO C/C 0
Of CS 2
Note 2 FST CS PIT RR 351-4-C42 F-10 2
C 11 CK SA C
0 CVT CS 862A-12-C42 B-11 2
C 12 CK SA C
0 CVP OP VRR-2 CVT 8628-12-C02 0-11 2
C 12 CK SA C
0 CVP OP VRR-2 CVT 863A-6-C34 11-2 2
C 6
CK SA C
O&C CVT RR VRR-3 Must be disassembled and hand stroked 863B-6-C34 11-3 2
C 6
CK SA C
O&C CVT RR VRR-3 Must be disassembled and hand stroked 867A-6-C58 0-2 1
AC 6
CK SA C
AT HR VRR-4 Note 13 867B-6-C58 C-2 1
AC 6
CK SA C
AT HR VRR-4 Note 13 867C-6-C58 13-2 1
AC 6
CK SA C
AT RR VRR-'s Note 13 881-4-C48 F-5 2
C II CK SA C
O&C CVT CS REACIOR CYCLI SAMPLING SYS11M
- 1) 568/70-12 (includes CC #11)
CV-948 0-3 2
A 3/8 6L AO C/C O&C BT OP 20-0 VRR-6 Note 2 FST CS 10-C
SAN ONOIRE BAR GENERATING SIATION B
ENGINEERING PROCEDURE SO1-V-2.1150 UNIT I HEVISION 'I PAGE 10 OF2 ATTACHMENT 8.2 IN-SI RV ICf I fSI ING PROGRAM ASME-CLASS 1,
2 & 3 VALVES SAN ONOIRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VALVE NORMAI /
STOKE VALVE VALVE SI/I VAIVL ACIR.
FAIA. 10 SIROKI I1ST TIME RELIEF NUMBER COURD.
CLASS CATEGORY LINCIS)(YPE TYPL POSIIION DIRC110N TEST MODE Sec.)
REQUEST REMARKS REACTOR CYCLE SAMPI. ING SYSTEM I) &
10j
'flb770-12_LincludsCC All (Continued)
CV-949 F-5 2
A 3/8 GL AO C/C O&C BI OP Notes 2, 5 FSI OP PIT RR CV-951 11-2 2
A 3/8 GL AO C/C O&C Al OH 10-0 VRR-6 Notes 2, III OP 12-C 11 rSr CS CV-953 13-2 2
A 3/8 CL AO C/C O&C AT RR 15-0 VRR-6 Notes 2, BI OP 5-C 11 FST CS CV-955 C-2 2
A 3/8 GL AO C/C O&C At RlR VRR-6 Notes 2, 5, BT OP 11 FSU CS CV-956 C-2 2
A 3/8 GL AO C/C O&C AT RR VRR-6 Notes 2, 5, B
Op 11 FST CS CV-957 C-5 2
A 3/8 GL AO C/C O&C AT RR Notes 2, BY OP 5 &11 FST OP PIT RR CV-962 D-2 2
A 3/8 GL AO C/C O&C Al RR 10-0 VRR-6 Notes 2, RT OP 10-C 11 FST CS CV-992 11-5 2
A 3/11 GL AO C/C O&C AT RR 10-0 Notes 2 BT OP 15-C
& 11 FST OP P I RR CV-2145 E-2 2
B 3/11 GL SO O/C O&C BT oP Notes 2 & 5 FST 01 SV-3302 C-0 2
Notes 2 B1 OP
& 11 FST OP RADIOACTIVE WAS[E DISPOSAL SYSTEMS I'
10 568772-23 CV-102 E-3 2
A 1 1/2 GL AO O/C C
AT RR 5
VRR-6 Notes 2, BY OP 10, 11 FST CS PIT RR
SAN ONOF LEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 14 PAGE 11 OF 2 ATTACIIMENT 8.2 IN-SIICE IESIING PROGRAM ASMIL-CILASS 1, 2 & 3 VALVES SAN ONOIRE NUCLEAR GENERAIING S[ATION UNIT 1 MAX.
VAI VE NORMAL/
STOKE VAI VE VAlVE SIZE VAlVE ACIR.
rAII I)
STROKE TEST TIME RELIEF NUMBLR COR.
CLASS CATEGORY ( INCIES) _ IYPI TYPE POSITION DIRECIION TEST MODE (Sec.)
REQUEST REMARKS RADIOAClIVE WASTE DISPOSAL SYSTEMS P
I
/568772-23 (Continued)
CV-103 E-3 2
A 1 1/2 GL AD O/C C
AT RR 5
Notes 2, 8I OP 10 & 11 rST OP PIT RR CV-lO E-3 2
A 2
GL AO O/C C
AT RR 5
VRR-6 Notes 1, OT OP 10, 11 FS[
A 2
GL AO O/C C
AT RR 5
Notes 2, BI OP 10 & 11 FS[
A 2
CL AO O/C C
AT RR 5
VRR-6 Notes 2, Br OP 10, 11 FST CS PIT RR CV-10 C-2 2
A 2
GL AO O/C C
AT RH 5
Notes 2, BI OP 10 & 11 FST OP PIT RR CV-535 0-3 2
A 1
BALL AO O/C C
AT RR 5
Notes 2, BT OP 10 & 11 FST OP PIT RR CV-536 D-3 2
A I
BALL AO O/C C
AT RR 5
VRR-6 Notes 2, BT OP 10, 11 FS[
B 1
GA So O/C C
Of OP 2
STIAM P
1
- 568//3-111 CV-76 D-I 2
U 11 GL AD C/C 0
BT CS Notes 5 & 8 FST CS CV-77
[-1 2
1 1 CL AO C/C O
BT CS Notes 5 & 8 FST CS CV-18 C-li 2
I II CL AO C/C 0
SAN ONfBLAR ENERAING SAION SENGINEERING PROCEDURE SOR-V-2.1 UNIT 1 ATIACitMENT 8.2 IN-SIRVICE I[SlING PROGRAM ASME-CIASS 1, 2 & 3 VALVES SAN ONORIL NUCLEAR GL.NERAI I NG STAT ION UNIT 1
MAX.
VAIVI NORMAL /
STOKE VALVE VALVE SIZE VAIVE ACIR.
FAILED SIROKE TEST TIME RELIEf NUMBER COORD.
CLASS CAIGORY AINCHES)
_YPE TYPE 10SIT ION DIRICTION TESI MODE (Sec.)
REQUEST REMARKS STEAM P
ID #
568773-111 (Contiiued)
CV-79 F.-1 2
B 11 Gt AO C/C 0
111 CS Notes 5 & 8
[SI CS RV-1
[-4 2
RVI RR Note 7 RV-2 C-11 2
RVT R
Note 7 RV-3 F-4 2
RVI RR Note 7 RV-Q C-1 2
RVt BR Note 7 RV-5 G-4 2
RVI RR Note 7 RV-8 Il-1 2
C 6xl)
RVI RR Note 7 RV-9 G-11 2
RVI RR Note 7 RV-lo B-11 2
RVT RR Note 7 TURBINE STOP (E) 0-6 2
B 24 GA NlY 0/0 C
BT OP Notes 2 TURBINE SlOP (W) E-6 2
It 24 CA IHY 0/0 C
DI OP Notes 2 PIT RR CIRCULATING WAIER SYSIUM P
10 D 5687/-2jI_
iincludes CC 19t CV-100A C-I 2
it CA SO O/C C
u8 OP Notes 2 EST OP&5 POV-5 B-1 3
I 12 Bi M
O&C/FAl O&C BT OP (SWC-380)
POV-6 C-1 3
II 12 Bi M
O&C/FAI O&C UT OP (SWC-379)
POV-11 D-2 3
11 12 BIF M
O&C/FAt 0
BT OP (SWC-381)
SWC-338 D-2 3
C 12 CI SA O&C O&C CVT OP Aix. Saltwater pump discharge check valve
SAN ONO LEAR GENERATING SIATION ENGINEERING PROCEDURE SO1-V-2.1 UNIT 1 REVISION Ii PAGE 13 OF ATTACHiMENT 8.2 IN-SILRVICE IESTING PROGRAM ASMIE-CLASS 1,
2 & 3 VALVES SAN ONOIRE NUCLEAR GENERATING SIATION UNIT 1 MAX.
VAl.VE-NORMAI/
STOKE VALVE VALVE SI/I VALVE ACIR.
FAILLD S IOKE IST TIME RELIEF NUMBER COORD.
CLASS CA1EIOY (INCEIS) IYPL IYPL POSITION DIRECTION iEST MODE (Sec.) REQUEST REMARKS MISCELLANEOUS WAlER SYSTEMS P
ID_1 56876-i22 inciudes CC #29)
CV-82 B-7 2
B 6
BF CS 25 Note 2
B It flf AO C/C U
& 114 CV-11l1 B-6 2
0 6
A 2
CL AU O/C C
AT fR 6
Notes 2 & 10 1
OP FST OP PIf RR CV-515 C-lU 2
A 6
BALL IlY O/C C
[tR CV-516 C-2 A
0 BALL IIY O/C C
BT OP 20 Notes 2, 6
FST OP PIT R
CV-517 F-6 2
I1 6
BALL ItY O/C O&C BT OP
'0-0 Note 2
[ST OP 20-C PIT RR CV-518 L-1 I
6 BALL liY O/C O&C Bt OP 3D-0 Note 2 FST OP 15-C PIT RH CV-537 C-7 2
A 2
BALL AO O/C C
AT OR 15 VRR-6 Notes 2, B1 OP 10 FST CS PIT RR 1-1/2-600-229 E-2 2
C 1-1/2 CK SA C
0 CVT OP 2"-629 D-7 2
A 2
CA M
C AT RR Notes 10
& 12 2"-649 C-1 2
AC 2
CK SA C
AT RB Notes 10
& 12
SAN ON CLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.10 UNIT I REVISION 4 PAGE II OF ATTACHMENT 8.2 IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VAlVE NORMAL/
STOKE VALVE VALVE SIZE VALVE ACIR.
FAIILD STROKE TEST TIME RELIEF NUMBER COORD.
CLASS CATEGORY (INIlS)-IYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS MISCELLANEOUS WATER SYSTEMS P
- 1) #
568776-22 (includes CC
- 29)
(Continued) 6-300-241 H-5 2
C 6
CK SA C
O&C CVT CS 6-300-241 11-5 2
C 6
CK SA C
O&C CVT CS 8-250-271 F-4 2
C 8
CK SA C
0 CVP OP CVT CS CHEMICAL FEED P &
ID
- 568777-16 RV-2000 F-8 2
C 1
RV SA C
RVT Note 6 RV-2001 F-9 2
C 1
RV SA C
RVT Note 6 RV-2002 F-9 2
C 1
RV SA C
RVT Note 6 RV-2003A It-11 2
C 3/4 RV SA C
RVT Note 6 RV-2003B G-11 2
C 3/11 fV SA C
RVT Note 6 SV-600 11-12 2
11 3/4 GL SO C/O 0
BT OP 5
Note 2 FST OP PIT RR SV-601 G-12 2
B 3/4 GL SO C/o 0
BT OP 5
Note 2 FST OP PIT RR 3/4-600-237 G-12 2
C 3/11 CK SA C
0 CVT OP Check Valve for Spray Additive Pump G-200A 3/4-600-237 11-12 2
C 3/11 CK SA C
0 CVT OP Check Valve for Spray Additive Pump G-200B FEEDWATER AND CONDINSAFL SYSILM P
10 568179-22 CV-36 C-7 2
B 3
GL AO C/o C
BT OP Notes 2 FST OP
& 5 CV-37 F-7 2
B 3
GL AU C/o C
BT OP Notes 2 FST OP
& 5
SAN ONOf1R*EAR GENERATING S]AIION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1I REVISION 'I PAGE 15 OF2~
ATTAC1IMENT 8.2 IN-SLRVICE TEST INC PROGRAM ASMI -CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VAtVL NORMAL/
STOKE VALVE VALVE SIZE VAlVE ACI1R.
CAILLED SIROKE TEST T IME RELIEF NUMBER COORD.
CLASS CAIEGORY LINCII[S) TYPE IYPE IOSITION DIRICTION TEST MODE (Sec.) REQUEST REMARKS FEEDWATER AND CONDENSATE SYSTEM P &
If)_ f _
T912-22 (Continued)
CV-100 G-2 2
B 2
CA AO O/C C
BI OP 20 Note 2 FSI OP CV-100B F-I 2
B 3
GA AO O/C C
[I 01' 5
Note 2 CV-142 E-2 2
B 11 CL AO C/C O&C BT CS 30-0 Note 2 Bill' OP 30-C FST CS CV-143 C-2 2
B 4
GL AO C/C O&C DT CS 30-0 Note 2 Bip OP 30-C FST CS CV-li4 D-1 2
1 to GL AO C/C O&C 1
CS 30-0 Note 2 DIP OP 30-C FCV-456 f-2 2
It CA AO 0/0 C
BT CS Notes 2 BiP OP&5 fST CS FCV-457 D-1 2
B GA AO 0/0 C
RI CS 55 Note 2 DIP OP FST CS FCV-458 C-2 2
11 GA AO 0/0 C
BIT CS 35 Note 2 BTP OP FST CS HV-852A B-4 2
B 12 GA IfY O/FAI C
BT CS 3 mima Notes 3 PIT RR 4.5 max
& 4 HV-852B E-11 2
B 12 GA ClY 0/FAI C
BT CS 3 min Notes 3 PIT RR 4.5 max
& 14
SAN ONO CLEAR GENERATING STATION ENGINEERING PROCEDURE SO-V-2.1 S
UNIT 1 REVISION 4 PAGE 16 00 ATTACHMENT 8.2 IN-StiVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VAIVI NORMAL/
STOKE VALVE VALVE SIZI VALVE ACIIt.
FAILED S1ROKE TEST TIME RELIEF NUMBER COORD.
CLASS CATEGORYt(IIES)
YPE TYPE VOSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS FEEDWATER AND CONDENSATE SYSTEM P &
11 568779-22 (Continued)
HV-854A D-4 2
B 1II GA IHY O/fAt C
BT CS 5.5 min
& 4 IIV-854B E-11 2
B 1I GA IHY
/ffAI C
BI CS 5.5 min
& 4 MOV-20 0-1 2
B 10 GA MO O/fAt C
& 5 MOV-21 F-3 2
B 10 CA MO O/FAI C
& 5 MOV-22 C-3 2
B 10 CA MO O/FAt C
& 5 4-600-222 0-2 2
C 4
CK SA C
O&C CVT CS 4-600-222 0-2 2
C 4
CK SA C
O&C CVT CS 4-600-222 E-2 2
C 4
CK SA C
O&C CVT CS 10-600-222 C-2 2
C 10 CK SA 0
C CVT CS 10-600-222 D-2 2
C 10 CK SA 0
C CVT CS 10-600-222 L-3 2
C 10 CK SA 0
C CVT CS 12-600-222 B-4 2
C 12 CK SA 0
O&C CVT CS Verify open during operation 12-600-222 G-11 2
C 12 CK SA 0
O&C CVT CS Verify open during operation COMPRESSED AIR P
& II D#5688-12 SV-125A G-9 2
A 2
CA SO O/C C
AT RR 2
Notes 2, BT OP 10 &11 FST OP PIT RR 1-1/2-600-240
-11 2
AT RR Notes 10
& 11
SAN ONOFR@LEAR GENERATING SIAIION ENGINEERING PROCEDURE SO1-V-2.15 UNIT I REVISION 4 PAGE 17 OF AlTACIIMENT 8.2 IN-SERVICE IESIING PROGRAM ASMIE-CLASS 1,
2 & 3 VALVES SAN UNOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VAl VE NORMAL/
SIOKE VALVE VALVE SI/L VALVE ACIR.
FAILED SIROKE ILSI TIME RELIEF NUMBER
- COORD, CLASS CAIEGORY AINIE[S)IYPE TYPE POSITION I)1HECTION TEST MODE (Sec. I REQUEST REMARKS COMPRESSED AIR P &
ID 568780-19 (ConLiiued) 1-1/2-600-240 0-12 2
AT RR Notes 10
& 1 2-600-150 G-9 2-A 2
GL M
C AT BR Notes 10, 11 & 12 Locked Closed 2-600-240 G-9 2
AC 2
CK SA 0
AT RR Notes 10
& 11 AIR CONDITIONING P &
ID 568782-20 (includes CC #181 CV-10 D-10 2
A 6
BTF AO O/C C
AU RR 25 Notes 2 usT OP PIT RR CV-4O D-9 2
A 2
3 Way AO O/C C
AT RR 5
VRR-6 Notes 2, B1 Op 10 FST CS CV-116 0-9 2
A 6
01f AO C/C C
AT RR 25 VRR-6 Notes 2, BI OP 10 FST CS PIT RR CV-146 F-6 2
A 1
VRR-6 Notes 2, BI OP 10 FST CS PIT RR CV-147 F-6 2
A 1
VRR-6 Notes 2, BT OP 10 FST CS PIT RR CV-2048 1-8 2
B 3/8 GL AO 0/0 O&C OT 01 Notes 2 FST Up&5 CV-2049 F-8 2
11 3/8 GL AO 0/0 O&C BT OP Notes 2 PST Op P
N POV-9 B-10 2
A 211 BTF AO C/C C
AT RR Notes 10
& 12
SAN ONOf LEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.1 UNIT 1 REVISION 14 PAGE 18 OF6 ATTACHMENT 8.2 IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VALVE NORMAL/
STOKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TESF TIME RELIEF NUMBER COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS AIR CONDITIONING P &
ID #
568782-20 (includes CC #18)
(Continued)
POV-9A B-10 2
.A 24 BTF M
C AT R
Locked Closed Notes 10
& 12 POV-10 C-10 2
A 24 BTF AO C/C C
AT RR Notes 16
& 12 POV-1OA C-10 2
A 24 BTF M
C AT RR Locked Closed Notes 10
& 12 SV-1212-8 F-6 2
A 1
Notes 2 BT OP
& 10 FST OP PIT RR SV-1212-9 F-6 2
A 1
Notes 2 BT OP
& 10 FST OP PIT RR TURBINE CYCLE SAMPLING SYSTEM P &
I) 568783-12 SV-119 D-1 2
B 1/14 CA SO O/C C
BT OP 2
Note 2 & 17 FST OP PIT RB SV-120 D-1 2
B 1/i GA SO O/C C
BT OP 2
Note 2 & 17 FST OP PIT RR SV-121 D-2 2
B 1/4 GA SO O/C C
B[
Note2&17 FST OP PIT RR SV-122 D-2 2
B 3/8 GA SO O/C C
01 OP 2
Note2&17 FST OP PIT RR SV-123 0-3 2
B 3/8 GA SO O/C C
BT OP 2
Note2&17 FST OP PIT RR SV-124 D-5 2
B 3/8 GA so 0/C
.1 T
SAN ONOR EAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.115 UNIT I REVISION i PAGE 19 OF 20 AITACHMENT 8.2 I
N-SE1RV ICL I LS II NG PROGRAM ASMt -CLASS I,
2 & 3 VALVES SAN ONOFRL NUCLEAR GLNERATING STATION UNIT 1 MAX.
VALVL NORMAL/
STOKE VALVE VALVE SIZE VAlVE ACIR.
FAILED SIROKE TES[
TIME RELIEF NUMBER COOI).
CLASS CATEGORY (INCIiSL YPE TYPE POSH ION DIRECION TEST MODE ISec.)
REQUEST REMARKS POST ACCIDENT CONIAINMENT HYDROGEN MONITORING P & ID #_ _68184.-18_
includes CC #26)
SV-2004 D-5 2
A 1/2 GL SO O/C C
AT RR 2
Notes 2, Bt UP 10 & 11 FSI OP PIT RR SV-3004 D-6 2
A 1/2 CL SO O/C C
At RR 2
VRR-6 Notes 2, 10, BT OiP 11 FST CS PIT RR
SAN ONOFR EAR GENERATING STATION ENGINEERING PROCEDURE SO-V-2.
UNIT 1 REVISION 4 PAGE 20 OF 214 ATTACHMENT 8.2 IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES 4
SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VALVE NORMAL/
STOKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS NITROGEN SYSTEM P &
ID #
568784-18 (includes CC #26) 3/4-600-142 F-8 2
A 3/4 GL M
C AT RR Notes 10, 11 & 12 3/4-600-142 F-8 2
A 3/4 GL M
C AT RR Notes 10, 11 & 12 DIESEL FUEL OIL -
STORAGE & SUPPLY SYSTEM (DIESEL UNIT 1)
P &
ID 5169250 DFS-309 E-8 3
C 2
CK SA C
O&C CVT OP DFS-308 E-11 3
C 2
CK SA C
O&C CVT OP DIESEL GENERATOR COOLING WATER SYSTEM (DIESEL UNIT 1) P & ID # 5169252 DWS-306 E-3 3
C 1 1/2 CK SA 0
0 CVT OP VRR-1 C
C CVT RR DWS-309 C-3 3
C 8
CK SA 0
0 CVT OP VRR-1 C
C CVT RR DIESEL STARTING AIR SYSTEM (DIESEL UNIT 1)
P & ID #5169256 SV-301 C-4 3
B 3
GA SO C/C 0
BT OP Note 5 FST OP SV-302 G-9 3
B 3
GA SO C/C 0
BT OP Note 5 FST OP SV-304 C-9 3
B 3
GA SO C/C 0
BT OP Note 5 FST OP SV-305 G-4 3
B 3
GA SO C/C 0
BT OP Note 5 FST OP
SAN TNO LEAR GENERATING STATION UNIT IREIVISION IT PACE 21 Of w
ATTACHMENT 8.2 IN-SERVICE ILSIlNG PROGRAM ASML-CLASS 1, 2 & 3 VALVLS SAN ONOIRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VAL VE NORMAL/
STOKE VALVE VALVE SIZE VALVE AClR.
FAILID SIROKE TEST TIME RELIEF NUMBER COORD.
CLASS CATEGORY J INCIES TYPIE TYPE POSITION 1)IRLCTION TEST MODE e
REQUEST REMARKS DIESEL STARTING AIR SYSIEM (DIESEL UNIT I Shoet 1 P &_ID #169253 DSS-357 E-2 3
C 2
CK SA C
O&C CVI OP OSS-358 D-12 3
C 2
UK SA C
O&C CVI UP DSS-305 C-4 3
C 3
CK SA C
0 CV OP USS-306 C-9 3
C 3
CK SA C
0 CV OP DSS-309 G-4 3
C 3
CK SA C
0 CVI OP OSS-310 B-9 3
C 3
CK SA C
0 CV OP DIESEL FUEL OIL -
STORAGE & SUPPLY SYSTEM (DIESEL UNIT 2)
P & ID #5169260 OFN-309 E-8 3
C 2
CK SA C
O&C CVI OP DFN-308 E-11 3
C 2
CK SA C
O&C CVT OP DIESEL GENERATOR COOLING WAlER SYSTEM (DIESEL UNIT 2) P & ID # 5169262 DWN-306 E-3 3
C 1 1/2 CK SA 0
0 CV OP VRR-1 0
C 8
CK SA 0
0 CV Op VRR-1 O
C CVT RR DIESEL AIR STARIING SYSIM (DIISELI UNII?)
P & Il) 15162263 DSN-357 L-2 3
C 2
CK SA C
O&C CVT OP DSN-358 E-11 3
C 2
CK SA C
O&C CVI OP DIESEL AIt SIARIING SYSILM (DIESEL UNII 2)
P &.1_) 1i466 SV-401 C-11 3
D 3
GA SO C/C 0
BT OP Note 5 FST OP SV-402 G-8 3
B 3
GA SO C/C 0
Dr OP Note 5 FSI OP SV-40i C-9 3
B 3
GA SO C/C 0
BT OP Note 5 SST OP SV-U.05 C-1i 3
Bi 3
CA so C/C 0
SAN NUCLEAR CENERAIING STAIION ENGINEERING PROCEDURE 801 UNIT REVISION 'I PAGE 22 ATTACIIMENT 8.2 IN-SIERVICE TESIING PROGRAM ASME-CL.ASS 1, 2 & 3 VALVES SAN ONOIRE NUCLEAR GENERATING STATION UNIT 1
MAX.
VALVL NORMAL/
STOKE VALVE VALVE SIZE VALVE ACIR.
FAILED SIROKE TEST TIME RELIEF NUMBLR COORD.
CLASS CAIEGORYINCS)IYPL YPE POSITION DIRECTION IEST MODE (Sec.)
REQUEST REMARKS DIESEL AIR SIARIING SYSTEM (DIESEL UNIT 2)
P & II) #516926 (Continued)
DSN-305 G-4 3
C 3
CK SA C
0 CVT OP DSN-306 G-9 3
C 3
CK SA C
0 CVT OP DSN 309 C-1I 3
C.
3 CK SA C
0 CVT OP DSN-310 C-9 3
C 3
CK SA C
0 CVT OP AUXILIARY FEEOWAIER SYSIEM P & ID #5159570-0 (includes CC Iti)
CV-113 E-2 2
B 3
GL AO 0/0 O&C BT OP Note 5 FST OP CV-3201 D-2 2
0 3
CL AO C/C 0
1 OP 50 Note 2 FST OP CV-3213 D-6 2
II 3
GL AO C/O O&C BT OP 20 Note 2 FST OP PIT RR FCV-2300 0-9 2
0 3
GL AO 0/0 O&C BT OP 40-0 Note 2 FST CS 20-C PIT FR FCV-2301 0-9 2
B 3
GL AO 0/0 O&C oT OP 40-0 Note 2 EST CS 20-C Pit RR FCV-3300 11-9 2
U 3
GL AO 0/0 O&C ET OP 40-0 Note 2 FST CS 20-0 PIT RR FCV-3301 C-9 2
U 3
GL AO 0/0 O&C BT OP 40-0 Note 2 FST CS 20-0 PIT RR MOV-1202 B-6 2
IU 3
GA MO C/FAl 0
HT OP Notes 1.
U 1/2 GA SO C/O 0
BT OP 2
SAN cO NUCLEAR GENERATING SlAION ENGINEERING PROCEDURE S01 UNIT W
REVISION 4 PACE 23 AlIACIIMENT 8.2 IN-SERVICE IESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VALVE NORMAL/
STOKE VALVE.
VALVE SIZL VAlVE ACIR.
FAIlED SIROKE TEST TIME RELIEF NUMBER COORD.
CLASS CATEGORY (INCIES) TYPE TYPE POSITION DIRECTION TEST MODE (See.) REQUEST REMARKS AUXILIARY FEEDWAIER SYSTEM P & ID #5159570-o (includes CC #14)
(Continued)
SV-3202 E-3 2
B 1/2 GA so 0/0 C
DI OP 2
Note 2 FST OP PIT RR SV-3203 E-3 2
B 1/2 GA SO 0/0 C
BIT OP 2
Note 2 FST OP PIT RR SV-3204 F-3 2
B 1/2 GA so 0/0 C
BT OP 2
Note 2 FST OP PIT RR SV-3205 F-2 2
B 1/2 GA SO C/O 0
Note 2 FST OP Pit RR SV-3211 D-2 2
B 1/2 GA SO C/O 0
BF OP 2
Note 2 FST OP PIT RR SV-3214 0-2 2
a 1/2 CA SO C/O 0
BT OP 2
Note 2 FST OP PIT RR 1-600-229 C-3 2
C I
UK SA C
0 CVT OP 1-600-229 C-3 2
C 1
UK SA C
0 CVT OP 1-600-229 C-6 2
C 1
CK SA C
0 CVT OP 1-600-229 C-6 2
C 1
UK SA C
0 CVT OP 3"-600-222 A-6 2
C 3
CK SA C
0 CVT CS 3"-600-222 0-6 2
C 3
CK SA C
0 CVT CS 3"-1500-219 B-7 2
C 3
CK SA C
0 CVT CS 3"-1500-219 B-7 2
C 3
CK SA C
0 CVT CS 3"-1500-219 B-9 2
C 3
CK SA C
0 CVT CS 3"-1500-219 C-7 2
C 3
CK SA C
0 CVT CS
SAN ON UCLAR GENERAIING STAJION ENGINEERING PROCEDURE SO-V UNIT 1 REVISION 4 PAGE 24 Of*
ATTACHMENT 8.2 IN-SERVICE 1ESIING PROGRAM ASME-CLASS 1, 2 & 3 VALVES SAN ONOrRE NUCLEAR GENERATING STATION UNIT 1 MAX.
VALVE NORMAL/
STOKE VALVE VALVE SIZF VALVE ACrR.
FAILED SIROKE TEST TIME RELIEF NUMBER
- COID, CLASS CATEGORY (INIIS)ljYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS AUXILIARY FEEDWATER SYSTEM P & 10 #5159570:
(includes CC 11f1)
(Continued) 3"-1500-219 C-7 2
C 3
CK SA C
0 CVT CS 3"-1500-219 C-9 2
C 3
CK SA C
0 CVT CS 3"-1500-219 D-7 2
C 3
CK SA C
0 CVT CS 3-1500-219 D-7 2
C 3
CK SA C
0 CVT CS 3"-1500-219 D-9 2
C 3
CK SA C
0 CVT CS HIGH RADIATION SAMPLING SYSTEM P & ID #5159580-0 (includes CC 18)
SV-3303 F-9 2
A 1
Notes 2, BT OP 10 & 11 FST OP PIT RR 3/4-1500-218 F-ll 2
AT BR Notes 10
& 11 0181d
SAN ONOf LEAR GENERATING STATION ENGINEERING PROCEDURE SOI-V-2.15 UNIT I REVISION 4 PAGE 1 OF 1 I*
ATTACHMENT 8.3 COLD SIIUIDOWN VALVE IESTING JUSTIFICATION TABLE SYSTEM P&ID REACTOR COOLANT SYSTEM 568766-17 VALVE VALVE JUSFIl ICAI ION IO1 COLD SIUIDOWN NUMBER COORD.
CLASS CAl.
TESTING FREQUENCY Of VALVES CV-545 B-2 1
B lailure of' valve during operation could cause breach of Reactor Coolant System pressure boundary.
CV-546 C-2 I
B Same as CV-545 l"-600-239 C-11 2
AC this check valve provides containment, isolation for the nitrogen backup supply to the Pressurizer Power Operated Relief Valves and Block Valves. The valve is located inside containment and is not accessible during plant operation.
568766-17 REACTOR COOLANT GAS VENT SV-2401
[-8 1
II Same as CV-Sti SV-2402 F-8 1
is Same as CV-5I5 SV-2403 A-/
1 i
Same as CV-545 SV-2400 A-7 I
0 Same as CV-5115 SV-3401 1-8 1
it Sane as CV-545 SV-3402 E-8 1i1 Same as CV-515 SV-3403 I-1 1
It Same as CV-5115 SV-3011 B-1 1
II Same as CV-545
SAN ONO CLEAR GENERATING STATION ENGINEERING PROCEDURE SO-V-2.15 UNIT 1 REVISION 4 PAGE 2 OF ATTACHMENT 8.3 COLD SiIiDOWN VALVE TESTING JUSTIFICAHION TABLE SYSIEM P&I)
ClIEMICAL AND VOLUME CONTROL SYSTEM 568767-21 VALVE VALVE JUSIIFICAIION FOR COLD ShUTDOWN NUMBER COORiD.
CLASS CAI.
TEStING FREQUENCY OF VALVES CV-276 0-3 2
B Full or partial stroke exercising during plant operation would affect operation Of the seal Water system.
CV-304 C-2 I
a
[tll or lartiaI stroke exercising would affect reactor coolant level during plant operation.
CVr305 C-2 1
B Full or partial Stroke exercising during plant operation would result in thermal shock to the pressurizer spray header.
CV-527 C-3 2
A This valve can be operated full open or full closed only.
Closing this during operation would interrupt RCP seal water return flow and cause relief valve (RV-200,) in tile upstream piping to lift.
CV-528 C-11 2
A Same as CV-527 FCV-1112 B-4 2
A Full Stroke exorcising during plant operation would inhibit charging flow.
FCV-1115A i-1 1
A I'll Stroke exercising Of this valve would interrupt seal water flow to the RCP's and could result in damage to the pump seals.
FCV-1115B 11-2 1
A Same as FCV-1115A FCV-1115C 11-3
.1 A
Same as FCV-1115A FCV-1115D Hi 1
A Partial or full stroke exercising during plant operation would result io excessive Reactor Coolant Pump seal water flow and potential subsequent damage to the pump seals.
FCV-1115E 11-2 1
A Same as FCV-1115D FCV-1115F 11-3 1
A Same as FCV-1115E
SAN ONOF LEAR GENERATING STAIION ENGINEERING PROCEDURE SO-V-2.15 UNIT 1 REVISION It PAGE 3 OF is ATIACHMENT 8.3 COLD SIIUII)OWN VALVI irsi ING JUSifIICAIION TABLE SYSIEM r& ID CHEMICAL AND VOLUME CONTROL SYSTEM VALVE VALVE JUSFIFICAIION FOR COLD S1IUIDOWN NUMBEI COO).
CLASS CAl.
IESIING RU9UENCY OFVALVES MOV/LCV 1100C 0-7 2
CIuSi ii Lhis valve dor ig normal operaLion Would isolate the not'maI Sort iOn Lo the chiailifig ptimps and conseclaiently i oterupt reactor coolant pomp seal flow.
Alternate flow paths would result in overboratiol Of the Reactor Coolant System arid a Plant Shutdown.
PCV-1115A F-1 2
B IliiS valve operaLes Fll open o irIlI closed oly.
Exercising this valve dutr-int) plant operation wouild inhiibi t seal Water flow to the Reactor Coolant Pumps, possibly damaging the pumps.
PCV-1115B F-2 2
B Same as PCV-1115A PCV-1115C f-3 2
B Same as PCV-1115A 236-4-C42 F-7 2
C Ibis valve cannot be stroked during normal operation without interrupt ing flow to the charging pumps suction.
264-2-C58 F-3 1
C This valve cannot be stroked during normal operation without affecting seal injection flow to the Reactor Coolant Pumps.
272-2-C58 F-2 1
C Same as 264-2-C58 280-2-C58 F-I 1
C same as 264-2-C58 308-2-C58 B-2 1
C ilis valve cannot be stroked during normal operation without affecting Reactor Coolant Level Control.
354-2-C58 C-2 1
.C Exercising his valve during normal operation would result in thermal shock to the auixiliary spray header in the pressurizer.
362-2-Cll 0-5 2
C restCing this valve while in operation would require isolation of the seat water return line and stopping both charging pmps causing ioterruation of Reactor Coolant Pump seal water flow.
SAN ONO LEAR GENERATING STATION ENIGINEERING PROCEDURE SO1-V-2. 15 UNIT 1 REVISION If PAGE 4 OF ATTACHMENT 8.3 COLD SIIUTDOWN VALVE TESTING JUSTIFiCATION TABLE SYSTEM P&ID AUXILIARY COOLING SYSTEM 568768-15 VALVE VALVE.
JUSIIFICAION FOR COLD SiUIDOWN NUMBER COORD.
CLASS CAI.
TES1ING FREQUENCY OF VALVES CV-722A 11-5 3
B this valve is full open or full closed only.
Full stroking during normal operation would interrupt cooling water flow to the Reactor Coolant Puimp thermal barrier cooling coils.
CV-7228 11-6 3
B Same as CV-722A CV-722C 11-9 3
B Same as CV-722A 2-617 G-10 3
C Full stroke testing of these check valves cannot be accomplished (2 Valves) during power operation.
these two check valves discharge through a common flowmeter.
Verification or flow through each check valve cannot be accomplished without isolation or one check valve.
The isolation valves for these check valves are located inside containment and therefore are inaccessible during power operation.
Full stroke exercising shall be performed during cold shutdown.
723A-1-1/2-C38A E-1 3
C testing of this valve requires interruption of cooling water to the Reactor Cooling Pump.
723B-1-1/2-C38A [-6 3
.C Same as 723A-1-1/2-C38A 723C-1-1/2-C38A [-8 3
C Same as 723A-1-1/2-C38A 741A-1-1/2-C38 11-3 3
C Testing of this valve requires interruption of cooling water to the Reactor Cooling Pump.
742A-1-1/2-C38 11-6 3
C Same as 741A-1-1/2-C38 743A-1-1/2-C38 11-8 3
C Same as 741A-1-1/2-C38
SANT NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SOl-V-2.
I REVISION t PAGE 5 ATTACHMENT 8.3 COLD SIIUIDOWN VALVE TESTING JUSTIFICAHION TABLE SYSTEM P&ID RESIDUAL hEAT REMOVAL 5130354-0 VALVE VALVE JUSTIFICATION FOR COLD SIUTDOWN NUMBER COOR).
CLASS CAI.
TESTING FREQUENCY OF VALVES HCV-602 D-7 2
B This valve is located inside containment at the lowest level in a high radiation area.
It is inaccessible during plant operation.. The valve has remote position indication of the closed position only.
Thus, there exists no means of verifying valve full stroke action during plant operation.
MOV-813 F-6 1
B This valve cannot be full or partial stroked during normal operation. Opening this valve could subject residual heat removal piping and components to pressure above their design.
MOV-814 F-7 1
B Same as MOV-813 MOV-833 1-7 1
B Same as MOV-813 MOV-834 L-6 1
B Same as MOV-813 819A-6-C54 G-6 2
C Residual heat removal pumps must be run to stroke this valve.
This can only be done during cold shutdown due to system pressure limitations.
819B-6-CS4 11-6 2
C Same as 819A-6-C54
SAN ONO LEAR GENLRATING STAIION ENGINEERING PROCEDURE SO1-V-2.15 UNITW REVISION 4 PAGE 6 OF ATTACHMENT 8.3 COLD SIMIUOWN VALVE TSFINC JUSilICAIION IABLE SYSI LM
.&ID SAFETY INJECTION SYSIEM___
568769-15 VALVE VALVJUiF OR COLD SIFDOWN NUMBER COORD.
CLASS CAI.
TESiING FREQUENCY Of VALVES CV-875A A-9 2
B 111i s va lye cannt be Full or part Stroked during normal plant ope ra t ion.
Opening this valve would cause iinborated f'eedwater to flow into the RWST, diluting its boron concentration.
CV-875B C-9 2
B Same as CV-815A HV-851A B-6 2
A Ixercising this valve during normal operation would disrupt feedwater flow to the steam generator.
IIV-8510 D-6 2
A Same as IIV-851A HV-853A B-9 2
B This valve operates full open or full closed only.
Full stroking during normal plant operations Would cause boron dilution of the RWST.
HV-853B 0-9 2
B Same as IIV-853A MOV-356 G-2 I
B his valve can be operated full open or full closed only.
Opening th is valve during plant operation would disrupt RCP seal water flow.
MOV-351 1-2 1
R Same as MOV-356 MOV-358 F-2 1
U Same as MOV-356 MOV-850A 0-2 1
It Ibis valve cannot be full or part stroke exercised during normal operation since it performs a pressure isolation function.
MOV-850B C-2 1
I Same as MOV-850A MOV-850C B-2 I
Is Same as 10V-80A MOV-866A G-1 2
l ihis valve is located on the discharge line oF the SIS recirculation pliffll)s.
Pumps are normalIly dry and in a Standby valve lineup for post-LOCA recirculation.
Testing during normal plant operation could result in loss of recirculation capabilities.
MOV-8660 G-2 2
B Same as MOV-866A MOV-880 F-5 2
13 Opening this valve during operation would disrupt RCP seal water flow.
MOV/LCV-llUB F-9 2
B full or part stroking of' this valve during normal plant operation would affect reactor coolant level control.
MOV/LCV-1100D G-9 2
B Same as MOV/LCV-1100B SV-2900 136 2
B Same as HV-851A SV-390J0 D-6 2
Bi Sante as IIV-851A I
SAN ONO LEAR GENERATING STAlION
.*ENGINEERING PROCEDURE SO]-V-2 15 UN r1 WREVISION 4
PAGE 7 OF UNIT IATTACIHMENT 8.3 COLD SIIUlDOWN VALVE 1ESTING JUSTIFICATION 1ABLE SYSTEM P&ID SAFETY INJECTION SYSTEM 568769-15 VALVE VALVE JUSIIFICATION FOR COLD SiU IDOWN NUMBER COORD.
CLASS CAl.
TESTING FREQUENCY OF VALVES 351-4-C42 F-10 2
C Ihis valve cannot be full or part stroked during normal plant operation.
Stroking would require opening MOV/LCV-1100B or MOV/LCV-11000 which would affect reactor coolant level control.
881-4-C48 F-5 2
C Same as MOV-880.
SAN ON CLEAR GENERATING SIAHON ENGINEERING PROCEDURE SO1-V-2.1 UNIT 1 W
REVISION 4 PAGE 8 OF ATTACHMENT 8.3 COil) SIl I DOWN VALVE I ES II NG JUSTIFICATION TABLE SYSILEM P&ID STEAM 568773-14 VALVE VAI VI JUS II I CATI ON [0M COL)
SIIU I DOWN NUMBER COORD.
CLASS
(;AI.
--- ILSIING FItEQUENCY OF VALVES CV-76 0-1I 2
- 1)
Ixercising this valve during normal plant operation would dump steam LO the a tinosphe re.
CV-77 F-4 2
B Same as CV-76 CV-78 C-11 2
B Same as CV-76 CV-79 F-4 2
B Same as CV-16
SAN ONO CLEAR GENERATING STATION ENGINEERING PROCEDURE SO-V-2.15 UNIT 1 REVISION 4 PAGE 9 OF ATTACHMENT 8.3 COLD SIIUTDOWN VALVE TESTING JUSTIFICATION TABLE SYSTEM P&ID MISCELLANEOUS WATER SYSTEM 56876-22 VALVE
.VAlVE JUSTIFICATION FOR COLD SHUTDOWN NUMBER
- COORD, CLASS CAL.
TESTING FREQUENCY OF VALVES CV-82 B-7 2
Is lhis valve cannot be full or partially stroked during normal plant operation.
Stroking the valve would cause the RWST to partially drain to the conitainment spray piping and into the containment through a drain in the spray piping.
CV-114 B-6 2
B Same as CV-82 6-300-241 Il-5 2
C This valve cannot be stroke tested during operation due to the potential for Flooding the fire protection or containment spray piping with borated water.
6-300-241 11-5 2
C Same as 6-300-241 8-250-271 F-5 2
C Same as 6-300-241
SAN ONOf LEAR GENERATING SlATION ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 11 PAGE 10 OF ATIACIlMENT 8.3 OLD SilUTDOWN VALVE lESTING JUSTIFICATION 1ABLE SYSTEM PMID fEEDWATER AND CONDENSATE SYSTEM 568779-22 VALVE VALVE JUSI IFICAI 1ON FOR COLD SIIU[UOWN NUMBER COORD.
CLASS CAT.
TESTING FREQUENCY OF VALVES CV-142
[-2 2
B Full stroke exercising during plant operation would disrupt feedwater flow.
CV-143 C-2 2
B Same as CV-142 CV-144 D-1 2
0 Same as CV-142 FCV-456 F-2 2
A Full stroke exercising during plant operation would interrupt feedwater flow to the steam generator.
FCV-457 D-1 2
A Same as FCV-456 FCV-458 C-2 2
A Same as FCV-456 HV-852A 8-4 2
0 This valve operates full open or full closed only.
Full stroking during normal plant operations would cause loss of feedwater to the steam generators.
IIV-852B E-11 2
)
Same as IIV-852A HV-854A B-11 2
B Same as IIV-852A lIV-854B E-11 2
13 Same as IV-852A MOV-20 0-1 2
.0 Same as FCV-456 NOV-21 F-3 2
B Same as FCV-456 MOV-22 C-3 2
Is Same as lCV-456 4-600-222 E-2 2
C Exrcising the Main Feedwater/Steam Generator check valves during normal plant power operation would interfere with the operation of the Steam Generator Level Control System.
4-600-222 D-2 2
C Same as 4-600-222 4-600-222 0-2 2
C Same as 4-600-222 10-600-222 E-3 2
C Full or part stroking of this valve during normal plant operation would interrupt feedwater flow to the steam generator.
10-600-222 0-2 2
C Same as 10-600-222 10-600-222 C-2 2
C Same as 10-600-222 12-600-222 B-4 2
C Same as.10-600-222 12-600-222 G-4 2
C Same as 10-600-222
SAN 0 NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2 UNIT.
REVISION 4 PAGE 11 ATTACHMENT 8.3 COLD SHUTDOWN VALVE TESTING JUSTIFICATION TABLE SYSTEM P&D AUXILIARY FEEDWATER 5159570-0 VALVE VALVE JUSTIFICATION FOR COLD SHUTDOWN NUMBER COORD.
CLASS CAT.
TESTING FREQUENCY OF VALVES FCV-2300 D-9 2
B Failsafe testing of this valve requires removing all power from the control system of one train.
Deenergizing and energizing this control loop requires verification of the bistable setpoints.
This control loop Is normally energized in modes 1 through 5. Relief is requested from quarterly failsafe testing of this valve to reduce the frequency of deenergizing and energizing of the control loop to mimimize degradation of the control loop components. This will be falisafe tested during cold shutdown.
FCV-2301 D-9 2
B Same as FCV-2300 FCV-3300 B-9 2
B Same as FCV 2300 FCV-3301 C-9 2
B Same as FCV 2300 3-600-222 B-6 2
C Testing this valve during normal plant operation would require Injecting cold water into the steam generators. This would result in thermal shock to the steam generators.
3-600-222 D-6 2
C Same as 3-600-222 3-1500-219 B-7 2
C Same as 3-600-222 3-1500-219 B-7 2
C Same as 3-600-222 3-1500-219 B-7 2
C Same as 3-600-222 3-1500-219 B-9 2
C Same as 3-600-222 3-1500-219 C-7 2
C Same as 3-600-222 3-1500-219 C-7 2
C Same as 3-600-222 3-1500-219 C-9 2
C Same as 3-600-222 3-1500-219 D-7 2
C Same as 3-600-222 3-1500-219 D-7 2
C Same as 3-600-222 3-1500-219 D-9 2
C Same as 3-600-222 0181d
PUMP RELIEF REQUEST NO.
1 SYSTEM:
Safety-Related Systems.
COMPONENT:
All pumps in -the program.
CLASS:
2 and 3 FUNCTION:
To provide flow to safety systems.
TEST REQUIREMENT:
The full-scale range of each instrument shall be three times the referenced value or less per IWP-4120.
BASIS FOR RELIEF:
Present instrumentation was specified and installed to comply with the requirements of the 1974 Edition of ASME Section XI which required a full-scale range 4 times the reference value.
ALTERNATE TESTING:
The full-scale range of each instrument shall be 4 times the reference value.
0II
PUMP RELIEF REQUEST NO. 2 SYSTEM:
Diesel Fuel Oil - Storage and Supply COMPONENT:
Diesel Fuel Transfer Pumps G-74A, G-74B, G-75A, G-75B CLASS:
3 FUNCTION:
To provide makeup fuel to diesel generator day tank.
TEST REQUIREMENT:
Measure pump bearing, vibration, and observe lubrication level per Article IWP-3100.
BASIS FOR RELIEF:
The Diesel Fuel Transfer Pumps are submergence type pumps located inside concrete vaults and are not accessible.
Therefore, it is not possible to measure bearing vibration.
The pumps are submerged in diesel fuel.
The diesel fuel provides lubrication for the bearings.
ALTERNATE TESTING:
None
PUMP RELIEF REQUEST NO. 3 SYSTEM:
Safety Injection COMPONENT:
Safety Injection Recirculation Pumps, G-45A, G-45B.
CLASS:
2 FUNCTION:
Pump borated safety injection water from the containment sump through the recirculation heat exchanger for long-term cooling of the core after a LOCA.
TEST REQUIREMENT:
Measurement of in-service test quantities per IWP-3100.
BASIS FOR RELIEF:
Under normal plant conditions these pumps and their discharge piping are dry. There is no provision to fill the sump during power operation. Thus, it is not possible to obtain hydraulic measurements as required by the code.
These pumps are located in the containment sump, in a high radiation area, and are not accessible during operation.
Therefore, it is not possible to take vibration and bearing temperature data.
. ALTERNATE TESTING:
The requirements of Technical Specification 4.2.II.B(3) shall be used in lieu of the Section XI pump testing requirements.
This requires that proper starting of each pump be confirmed by observation of running current demonstrated on a monthly basis.
Every Refueling or once every 2 years, a test requiring the sump to be filled with water and the pump to be run at shut-off head will be accomplished. No vibration or bearing temperature data will be obtained due to the pump being submerged.
PUMP RELIEF REQUEST NO.
4 SYSTEM:
Residual Heat Removal COMPONENT:
Residual heat removal pumps, G-14A, G-14B CLASS:
2 FUNCTION:
These pumps provide flow through the reactor coolant system during the final stage of plant cooldown to cold shutdown.
They also provide flow to remove residual heat to maintain cold shutdown conditions.
TEST REQUIREMENT:
Quarterly testing per Article IWP-3400.
BASIS FOR RELIEF:
During normal plant operation, these pumps can only be tested at minimum recirculation flow afforded by a small three-quarter inch bypass line.
This operating mode might damage the pumps if run long enough to obtain Code specified measurements.
Additionally, the pumps are located at the lowest level of the containment building which is a normally inaccessible high radiation area during plant operation. Thus, it is desirable to test during cold shutdowns when the pumps will normally be in use.
.ALTERNATE TESTING:
Test at cold shutdown.
Test frequency during cold shutdown will be quarterly.
SII
PUMP RELIEF REQUcST NO. 5 SYSTEM:
Feedwater and Condensate COMPONENT:
Feedwater Pumps, G-3A, G-3B CLASS:
2 FUNCTION:
During normal operation, these pumps supply feedwater to the steam generators. During safety injection they provide flow of borated water to the reactor coolant system.
TEST REQUIREMENT:
Measure individual pump flow rate.
BASIS FOR RELIEF:
Both feedwater pumps discharge to a common feedwater header.
From this header, three branch lines (with flow indication) provide feedwater to each of the three steam generators. No flow measuring instrumentation is provided on the individual discharge of each feedpump and, therefore, total flow is measured, rather than individual flow. Alternate testing proposed meets the intent of the Code.
ALTERNATE TESTING:
The total flow rate from both pumps shall be measured.
Additionally, input amps to each pump motor shall be measured.
A ratio of the total flow will be credited to each pump based on the input amps. The flow rate credited to each pump will be evaluated per IWP-3200.
PUMP RELIEF REQUEST NO.
6 SYSTEM:
Safety Injection, Refueling Water, Auxiliary Feedwater COMPONENT:
G-50A, G-50B, G-27N, G-27S, G-20, G-10S CLASS:
2 FUNCTION:
To provide low pressure borated water to the suction of the Feedwater pumps, to provide borated water to the containment spray header, to provide feedwater to steam generator during plant startup and shutdown.
TEST REQUIREMENT:
ASME Section XI requires flow rate to be measured in Table
- IWP-3100-1 of the code.
The pumps referenced in this relief request use a test loop which is a fixed resistance system; therefore, only differential pump head will be measured.
BASIS FOR RELIEF:
Flow instrumentation is not installed in the test loops of these systems. Because the piping test loops are fixed resistance piping systems, the pumps are being tested under the same conditions during each in-service test. Therefore, test results are comparable to reference tests, and the intent of IWP-3000 is being met.
ALTERNATE TESTING:
None
PUMP RELIEF REQUEST NO. 7 SYSTEM:
Saltwater Cooling COMPONENT:
Saltwater Cooling Pumps, G-13A, G-13B, G-13C CLASS:
3 FUNCTION:
To provide saltwater coolant flow to the component cooling water heat exchanoer.
TEST REQUIREMENT:
Measurement of pump bearing vibration and temperature, and observation of pump bearing lubrication level or pressure once every 3 months per Article IWP-3000.
BASIS FOR RELIEF:
The Saltwater Cooling Pumps are submergence type pumps with bearings located under water and inaccessible. Therefore, it is not possible to measure pump bearing vibration or temperature. The pump bearings are cooled and lubricated by fresh water from the Service Water System.
ALTERNATE TESTING:
Once a month., temperature and vibration measurements on the Saltwater Cooling Pump motor thrust bearings will be taken.
Also, once a month, water flow to the pump bearings will be verified in lieu of lubricant level or pressure.
VALVE RELIEF REQUEST NO. 1 SYSTEM:
Diesel Generator Cooling Water System COMPONENT:
DWS-306 DWS-309 DWN-306 DWN-309 CATEGORY:
C CLASS:
No ASME Class Designation FUNCTION:
To prevent backflow through the keep-warm pumps and cooling water pumps.
TEST REQUIREMENTS:
Full-stroke exercise open and closed every three months BASIS FOR RELIEF:
There are no provisions for checking valve closure in the systems.
During refueling, preventative maintenance is performed on the diesel generators. As a part of this maintenance, the check valves will be disassembled and inspected in pairs at every other refueling outage.
W ALTERNATE TESTING:
Stroke open quarterly, disassemble and inspect a pair of check valves at each refueling outage.
VALVE RELIEF REQUEST NO.
2 SYSTEM:
Safety Injection COMPONENT:
862A-12-C42 862B-12-C42 CATEGORY:
C CLASS:
2 FUNCTION:
These valves prevent backflow through the Safety Injection Pumps.
TEST REQUIREMENT:
Full stroke exercise these valves every three months.
BASIS FOR RI TLIEF:
These valves cannot be tested at full design flow without initiating safety injection. The minimum flow calculated to full stroke these valves is 3,500 gpm. The only available flowoath to test these valves is through a 2-inch bypass line.
This line restricts flow to less than the minimum required to full stroke the valves.
These valves are a tilting-disc type without valve caps.
Due to their design, it is imoracticable to disassemble and manually stroke the valve.
A LTER NATE TESTING:
The valves shall be part-stroke exercised quarterly.
VALVE RELIEF REQUEST NO.
3 SYSTEM:
Safety Injection COMPONENT:
863A-6-C34 (check valve) 863B-6-C34 (check valve)
CATEGORY:
C CLASS:
2 FUNCTION:
These valves prevent backflow during operation of the SIS recirculation pumps.
TEST REQUIREMENT:
Exercise valve for operability every three months.
BASIS FOR RELIEF:
These valves are located on the discharge lines from the SIS recirculation pumps. These pumps are located inside containment in a dry sump.
Testing of the valves would require flow in the discharge lines of the pumps to verify proper operation.
This is not practical due to the possibility of filling the suction piping of the Refueling Water Pumps and the Charging Pumps with debris from the sump.
. AL T ERNAT E TESTING:
These check valves will be disassembled and the disks hand-stroked during each refueling outage.
VALVE RELIEF REQUEST NO. 4 SYSTEM:
Safety Iajection COMPONENT:
867A-6-C58 (check valve) 867B-6-C58 (check.valve) 867C-6-C58 (check valve)
CATEGORY:
AC CLASS:
1 FUNCTION:
These valves prevent backflow from the RCS to the SIS.
TEST REQUIREMENT:
Exercise the valves every three months.
BASIS FOR RELIEF:
These valves cannot be tested during operation since they provide isolation of the SIS from the reactor coolant system.
They cannot be tested at cold shutdown due to the requirement that two positive barriers exist between the feedwater system and the RCS (Technical Specification requirement).
This requirement precludes establishing flow through the valve.
ALTERNATE TESTING:
None
VALVE RELIEF REQUEST NO.
5 SYSTEM:
Containment Fire Spray COMPONENT:
CV-92 CATEGORY:
B CLASS:
2 FUNCTION:
This valve, when opened, permits water from the RWST to enter the sphere fire suppression spray header.
TEST REQUIREMENT:
Exercise valve for operability every three months.
BASIS FOR RELIEF:
Exercising this valve while in operation would allow water from the RWST to flow through the fire suppression spray header inside containment. This water would flow over the reactor coolant pumps, residual heat removal pumps and other vital equipment.
Testing at cold shutdowns could allow water accumulated in the piping to run out the spray nozzles since the nozzles are at a lower elevation than portions of the spray piping. As discussed previously, this water would flow over the reactor coolant pump, residual heat removal pumps and other vital equipment.
Thus, it would be necessary to drain and disable the system to allow exercising of the valve.
ALTERNATE TESTING:
Technical Specifications require that this valve, among others, be cycled at least once per 18 months. The valve will be exercised during refueling when the RWST is drained. This requirement provides adequate assurance of proper valve operability.
VALVE RELIEF REQUEST NO. 6 SYSTEM:
Safety-Related Systems COMPONENT:
All power operated valves requiring fail-safe testing located inside containment.
CATEGORY:
A & B CLASS:
1, 2 & 3 FUNCTION:
To regulate flow in safety-related systems.
TEST REQUIREMENTS:
Quarterly test valves with fail-safe actuators by observing the operation of the valves upon loss of actuator power per IWV-3415.
BASIS FOR RELIEF:
The containment is normally inaccessible during power operation.
ALTERNATE TESTING:
Fail-safe testing of valves located inside containment will be performed during cold shutdown.
VALVE RELIEF REQUEST NO.
7 SYSTEM:
Safety-Related Systems COMPONENT:
All power-operated valves with relief to full-stroke test at cold shutdown or refueling.
CATEGORY:
A & B CLASS:
1, 2 & 3 FUNCTION:
To regulate flow in safety-related systems.
TEST REQUIREMENTS:
The requirements of IWV-3417(a), increasing test frequency to once a month when valve stroke time increases more than the specified limit from the previous test.
BASIS FOR RELIEF:
Certain valves can only be full-stroke tested at cold shutdown or during refueling.
To test these valves at the increased frequency specified in IWV-3417(a), would require placing the plant in a cold shutdown or refueling mode just to test these valves.
ALTERNA TE TESTING:
Power-operated valves with relief to test at cold shutdown or refueling which do not meet the requirements of IWV-3417(a) shall be tested each time the plant is in the proper mode.
The valves need not be tested more frequently than once a month.
During extended outages, these valves will be tested monthly.
Once corrective action is taken, the original test frequency shall be resumed.
VALVE RELIEF REQUEST NO. 8 S SYSTEM:
All Systems COMPONENT:
All power-operated valves CATEGORY:
A and B CLASS:
1, 2 and 3 FUNCTION:
N/A TEST REQUIREMENTS:
During surveillance testing, if there is an increase in stroke time of 50% or more from the previous test for valves with stroke times less than or equal to 10 seconds is observed, the test frequency shall be increased to once each month until corrective action is taken.
BASIS FOR RELIEF:
It has been observed through surveillance testing and corrective action that the repeatability of valve stroke times for valves with short stroke times is sporadic and independent of degradation.
ALTERNATE TESTING:
Valves with stroke times of 5 seconds or less with an increase in stroke time of 50% or more shall not have the test frequency increased.
However, if a valve stroke time does exceed its maximum stroke time value, it shall be declared inoperable.
0434j/kdb
VALVE RELIEF REQUEST NO. 9 SYSTEM:
Reactor Coolant System Reactor Coolant Gas Vent System Chemical and Volume Control System Auxiliary Coolant System Residual Heat Removal System Safety Injection System Steam System Miscellaneous Water System Feedwater and Condensate System Auxiliary Feedwater System COMPONENT:
Various valves identified in enclosed Attachment 8.3 to Engineering Procedure SO1-V-2.15 CATEGORY:
As in above Attachment 8.3 CLASS:
As in above Attachment 8.3 FUNCTION:
As in above Attachment 8.3 TEST REQUIREMENT:
Full stroke exercising of the valves on a quarterly basis.
BASIS FOR RELIEF: As in above Attachment 8.3 ALTERNATE TESTING: As in Attachments 8.2 and 8.3 to Engineering Procedure SO1-V-2.15.
ENCLOSURE II OPEN ITEMS & RESPONSES
CHEMICAL AND VOLUME CONTROL SYSTEM
- 1. Open Item How are check valves 247-3-C58 and 248-3-C58 full-stroke exercised quarterly? Provide method and frequency of full stroke exercising.
Response
Referring to P&ID 568767-21, these valves are located on the discharge lines of the North and South charging.pumps respectively. Calculations based on Crane Technical Paper 410 show that a flow of 103 gpm is required to full stroke each valve. To perform a full stroke test on the discharge valve of one pump, the other pump is isolated. Then with one pump running, the discharge flows to the reactor coolant pump seals (three lines) and to Loop A (one line).
As each of these lines is equipped with a flowmeter, a combined flow of 103 gpm can be verified.
- 2. Open Item Licensee to determine if valve 335-2-C42 should be included in the IST program.
Response
Since credit is not taken for the boric acid transfer pumps for accident mitigation or recovery from an accident, this valve is not required to be in the IST program.
- 3. Open Item Licensee to determine if valves 326-2-C42A, 315-2-C42A should be included in the IST program.
Response
Same as in (2) above.
SAFETY INJECTION SYSTEM
- 4. Open Item What alternate tests have been considered for full or partial stroke exercising check valves 867A-6-C58, 867B-6-C58 and 867C-6-C58? Open item for discussion between SCE and NRC.
Response
For reasons identified in Valve Relief Request No. 4, it has been determined unsafe to test these valves either during operation or at cold shutdown. Therefore, these valves are not included in the IST program.
- 5. Open Item Licensee to determine if interim functional test of valves HV-851A and B, HV-852A and B, HV-853A and B, and HV-854A and B satisfies all the requirements of ASME Code,Section XI testing.
Response
The interim functional test does not satisfy ASME code,Section XI requirements for stroke timing and fail safe testing. This test is described in Technical Specification 4.2.3. For reasons identified in Valve Relief Request No. 9, all of the above valves will be exercised at cold shutdown.
-2
- 6. Open Item How is check valve 351-4-C42 full stroke exercised during cold shutdown? Licensee to determine if the reduced flow opens the valve fully or an additional test is required.
Response
Referring to P&ID 568769-15, this valve is located on the common suction header from the refueling water storage tank to the North and South charging pumps. Calculations based on Crane Technical Paper 410 show that 275 pgm flow is required to full stroke this valve. To perform the stroke test, both charging pumps are aligned with the cold leg of the reactor coolant system through valves FCV-1115 0, E and F. Then with both pumps running, the flow is increased to > 275 gpm, as indicated by flow meters located on the charging lines.
For reasons specified in Valve Relief Request No. 9, the stroke test can only be performed during cold shutdown.
- 7. Open Item Check valves 862A-12-C42 and 862B-12-C42 are part stroke exercised quarterly. Licensee to determine a method and frequency for full stroke exercising these valves.
Response
For reasons specified in Valve Relief Request Number 2, it is unsafe and impractical to full stroke exercise these valves.
AUXILIARY COOLANT SYSTEM
- 8. Open Item Licensee to evaluate safety function and if necessary establish a test method and frequency for exercising valves 2-647 (2 valves).
Response
These valves are included in the IST program. Full stroke testing of these valves cannot be accomplished during power operation. The reasons for this, as well as the proposed test method and frequency, are described in Valve Relief Request No. 9.
- 9. Open Item Credit is taken for the operability of the thermal barrier emergency cooling pump. Licensee to evaluate safety function of thermal barrier emergency cooling pump and associated valves.
Response
In past discussions with the NRC staff, credit has been taken for operability of the thermal barrier pump in relation to the following three events: (1) Loss of off-site power (2) Fire in 4 kV room or lube oil reservoir area (3) Station blackout.
However, the thermal barrier pump is considered non-safety related.
Although event (1) is a design basis event, it is of short duration (less than 10 minutes), recovery from which does not require operability of the thermal barrier pump. For event (2), the NRC has permitted use of non-safety-related equipment, such as fire pumps which are not covered by the IST program.
Finally, event (3) is not a design basis event, but continues
-3 as an unresolved safety issue of very low probability.
Therefore, event (3) does not require safety-related equipment to initiate recovery.
For the above reasons, the thermal barrier pump and associated check valves 729C-3-C32, 729D-3-C32 and 729E-3-C32 are not included in the IST program.
FEEDWATER AND CONDENSATE SYSTEM
- 10. Open Item Licensee to evaluate if valves CV-36 and CV-37 can be exercised quarterly.
Response
These valves can, and will, be exercised quarterly. They are included in the IST program.
AUXILIARY FEEDWATER SYSTEM
- 11. Open Item Licensee to determine if check valves 1-600-229 (4 valves) should be included in IST program.
Response
These valves are included in the IST program and will be exercised quarterly.
- 12. Open Item Licensee to determine if fail safe testing of valves FCV-2300, 2301, 3300, 3301 can be performed quarterly.
Response
For reasons explained in Valve Relief Request No. 9, fail safe testing of these valves will be performed at cold shutdown, instead of quarterly.
- 13. Open Item Licensee to determine if valves MOV-1202 and CV-3213 can be exercised quarterly.
Response
These valves will be exercised quarterly. However, as stated in Valve Relief Request No. 9, the associated check valves will be tested only at cold shutdown to avoid injecting cold water into the steam generators (thermal shock).
- 14. Open Item Licensee to determine if valve CV-113 is passive and/or should be included in the IST program.
Response
This valve is included in the IST program and is exercised quarterly.
STEAM SYSTEM
- 15. Open Item Licensee to determine if valves CV-76, 77, 78 and 79 should be included in the IST program, and if so, the testing frequency to be determined.
Response
These valves are included in the IST program. They will be exercised at cold shutdown (see Valve Relief Request No. 9).
-4 MISCELLANEOUS WATER SYSTEMS
- 16. Open Item Licensee to determine if valve 1 1/2-600-229 should be included in the IST program.
Response
This valve is included in the IST program and will be exercised quarterly.
AIR CONDITIONING SYSTEM
- 17. Open Item Licensee to determine if valves CV-146 and CV-147 can be exercised quarterly.
Response
These valves are included in the IST program and will be exercised quarterly. However, since they are located inside the containment, they will be fail safe tested only at cold shutdown (see Valve Relief Request No. 6).
- 18. Open Item Licensee to determine if valves SV-1212-8 and SV-1212-9 can be exercised quarterly.
Response
These valves are included in the IST program and will be exercised quarterly.
PUMPS
- 19. Open Item Licensee to determine if any vibration monitoring on the safety injection recirculation pumps will be performed.
Response
As explained in Pump Relief Request No. 3, it is not practical to take vibration measurements on these pumps.
- 20. Open Item Licensee to consider rewriting Pump Relief Request No. 2 (Rev. 4) and Section 6.4.5.2.3 (Rev. 4) of pump procedure.
Response
After consideration, it is concluded that Section 6.4.5.2.3 meets the intent of the ASME Code. This paragraph has been retained "as is".
Previous Pump Relief Request No. 2 has been deleted, as no such request is considered necessary to implement Section 6.4.5.2.3.
- 21. Open -Item Licensee to determine if San Onofre Unit 1 takes credit for boric acid transfer pumps to provide alternate boration flowpath for accident mitigation.
Response
No such credit is taken for these pumps. Accordingly, they are not included in the IST program.
-5
- 22. Open Item For SI recirculation pumps, motor amperage measurement is utilized as a test alternative, however, no acceptable criterion has been established.
Licensee to establish acceptance criterion for this testing.
Response
The acceptance criterion for motor amperage is:
Acceptable motor amperage < 150 amps.
- 23. Open Item Licensee to determine if valves in the diesel starting air system should be included in the IST program.
Response
These valves have been included in the IST program.
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