ML13317B492
| ML13317B492 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/10/1985 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13317B491 | List: |
| References | |
| 0181D, 181D, S01-V-2.15, S1-V-2.15, NUDOCS 8603050119 | |
| Download: ML13317B492 (52) | |
Text
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SOI-V-2.15 UNIT 1 REVISION PAGE 1A OF 52 COMPLETE REVISIO TCN EFFECTIVE DATE 14Y 40 IN-SERVICE TESTING OF VALVES PROGRAM TABLE OF CONTENTS SECTION PAGE 1.0 OBJECTIVE 2
2.0 REFERENCES
2 3.0 PREREQUISITES 2
4.0 PRECAUTIONS 3
5.0 CHECKLIST(S) 3 6.0 PROCEDURE 3
6.1 Test Interval 3
6.2 Valve Category 3
6.3 Requirements 4
6.4 Corrective Measures 10 6.5 Exceptions 11 6.6 Instrumentation 12 7.0 RECORDS 12 ATTACHMENTS 1
Table Information and Explanation of Abbreviations 13 2
System Valve List 20 3
Cold Shutdown Valve Testing Justification Table 44 860305011 0500000206.
PDR ADOCK PDR 0181d QA PROGRAM AFFECTING
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION
/
PAGE 2 OF 52 TCN IN-SERVICE TESTING OF VALVES PROGRAM 1.0 OBJECTIVE 1.1 To define the requirements for in-service 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 Reference 2.5.1 to the maximum extent practical.
2.0 REFERENCES
2.1 Licensing Commitments 2.1.1 Code of Federal Regulations, Title 10, Part 50, Appexdix J 2:1.2 Unit 1 Technical Specifications 2.2 Site Order 2.2.1 S0123-IN-1, In-Service Inspection Program 2.3 Procedure 2.3.1 SO1-V-1.12, Containment Penetration Leak Rate Testing 2.4 Operating Instructions 2.4.1 S01-12.4-2, Operations In-Service of Valve Testing 2.4.2 S01-12.8-8, Refueling Interval In-Service Testing of Valves 2.4.3 S01-12.9-9, Safety Injection System Check Valve Tests 2.5 Other 2.5.1 American Society of Mechanical Engineers (ASME),
Boiler and Pressure Vessel Code,Section XI, 1977 Edition, including Addenda through Winter 1979 3.0 PREREQUISITES 3.1 Prior to use of an uncontrolled (pink) copy of this Site document to perform work, verify that it is current by utilizing one of the following methods:
3.1.1 Check it against a controlled copy and any TCNs; 3.1.2 Access an SCE Document Configuration System (SDCS) TSO Terminal; 3.1.3 Contact CDM by telephone or through counter inquiry; 3-1-3 k
9AO
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT I REVISION 5 PAGE 3 OF 52 TCN 3.0 PREREQUISITES (Continued) 3.1.4 Obtain an uncontrolled (pink) copy of the Site document from CDM; 3.1.5 Reference a current (within one week) Configuration Control Log and associated daily update. '
3.2 The implementing Procedures and Operating Instructions shall be updated 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 PRECAUTIONS 4.1 The ASME Section XI test requirements (Reference 2.5.1) shall be met to the maximum extent practical. It is not the intent of this Procedure to test valves that may place the Plant in-an unsafe condition. Care should be exercised to ensure that no test will be conducted that would violate Technical Specifications or other Plant operating contraints.
4.2 Special care must be exercised to ensure that the allowed test interval is not exceeded. For valves routinely tested at one (1) month or three (3) month intervals, a test interval extension is allowed. This extension shall not exceed twenty-five percent (25%)
of the inspection interval and must not cause any three (3) consecutive surveillance intervals to exceed 3.25 times the specified surveillance interval.
5.0 CHECKLIST(S) 5.1 None 6.0 PROCEDURE 6.1 Test Interval 6.1.1 The valve in-service testing program delineated herein covers a ten (10) year interval commencing on January 1, 1978 and terminating on January 1, 1988.
6.2 Valve Category 6.2.1 Valves are categorized as follows:
.1 Category A - valves for which seat leakage is limited to a specific maximum amount in the closed poston for fulfillment of their function.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 5 PAGE 4 OF 52 TCN 6.0 PROCEDURE (Continued)
.2 Category B -
valves for which seat leakage in the closed position is inconsequential for fulfillmentf their function.
.3 Category C - valves which are self-actuati lg n response to some system characteristic, such as pressure (relief valves) or flow direction (check valves).
.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 Requirements NOTE:
Subsection IWV of Reference 2.5.1 defines the requirements for in-service testing of Code Class 1, 2 and 3 valves.
Test results are intended to verify valve operational readiness on a continuing basis. Operations shall have the responsibility for maintaining the surveillance schedule for all valves except safety/relief valves for which Maintenance shall have responsibility. The IST Coordinator, in the Technical Division, shall have responsibility for maintenance of the IST Program, including this Procedure.
NOTE: itemizes all valves subject to the test requirements of this Procedure including the valve category and test mode.
ggDEger p I MA TAL 6.3.1 Category A and B Valves
.1 Test Frequency: Category A and B valves shall be exercised at least once every (3) months with the exceptions defined below and as noted in Attachment 3.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE S01-V-2.15 UNIT 1 REVISION,/
PAGE 5 OF 52 TCN 6.0 PROCEDURE (Continued) 6.3.1.2 Exercising Procedure
.2.1 Valves shall be exercised to the position re uired to fulfill their function unless such operatiot-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 which cannot be exercised during normal Plant operation are specifically identified in Attachment 3 and shall be full-stroke exercised during cold shutdown or refueling.
.2.2 In the case of frequent or extended cold shutdowns, these valves need not be exercised more often than once every three (3) months.
.2.3 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, flowrate 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.
.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, he original test frequency shall be resumed. In any case, any abnormality or erratic action shall be reported.
NUCLEAR GENERATION SITE ENGINEERING PQCEDURE SO1-V-2.15 UNIT 1 REVISION PAGE 6 OF 52 TCN 6.0 PROCEDURE (Continued) 6.3.1.3.4 Valves in Regular Use
.3.4.1 Valves which operate in the course of Plant 6peration at a frequency which would satisfy the exercising requirements of this Procedure need not be-additionally exercised provided the observations otherwise required for testing are made and analyzed during such operation and recorded in the Plant record at intervals no greater than three (3) months.
.3.5 Valves in Systems Out Of Service
.3.5.1 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.
.3.6 Fail-Safe Valves
.3.6.1 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 three (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 three (3) months.
6.3.2 Category C Valves
.1 Safety and Relief Valve Tests
.1.1 Test Frequency: Safety and relief valves shall be l
tested with the following frequencies:
1.1.1 There are fourteen (14) safety and relief valves which require testing in accordance with Reference 2.5.1, IWV-3510. For refueling intervals of 18 months, a minimum of five (5) valves will be tested at each refueling. All valves will be tested in a period of not more than five (5) years.
1.1.2 There are two (2) pressurizer relief valves. These will be tested at each refueling shutdown in accordance (4
with Technical Specification 4.1.2.
1.1.3 There are ten (10) main steam safety valves. These will be tested at each refueling shutdown In accordance li with Technical Specification 4.1.2.
1.1.4 The scheduling and bookkeeping required for these tests shall be the responsibility of Maintenance.
NUCLEAR GENERATION SITE ENGINEERING P OCEDURE SO1-V-2.15 UNIT 1 REVISION PAGE 7 OF 52 TCN 6.0 PROCEDURE (Continued) 6.3.2.1.2 Testing Procedure
.1.2.1 Safety and relief valve setpoints will be sted in accordance with ASME Performance Test CodetS.3-1976.
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 Reference 2.5.1 IWV-3420.
.1.3 Additional Tests
.1.3.1 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 valves fail to function properly on test, all valves in this categury in the system shall be tested.
.2 Check Valve Tests
.2.1 Test Frequency
.2.1.1 Check valves shall be exercised at least once every three (3) months, with the exceptions defined in step 6.3.2.2.2 and itemized in Attachment 3. The scheduling of the tests depends on what Mode the system has to be in for testing the check valves.
.2.1.2 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 Attachment 3.
.2.2 Exercising Procedure
.2.2.1 Check valves shall be exercised to the position required to fulfill their function unless such operation is not practical during Plant operation.
Normally closed check valves which cannot be operated during normal Plant operation are identified in and shall be exercised during cold. 'i shutdown or refuelings. In case of frequent cold shutdowns, these check valves need not be exercised more often than once every three (3) months.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE 501-V-2.15 UNIT 1 REVISION 5/
PAGE 8 OF 52 TCN ____
O 6.0 PROCEDURE (Continued) 6.3.2.2.2.1 Normally Open Valves: valves normally open during Plant operation, whose function is to prevent vrcversed flow, shall be tested in a manner which j'
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 observation, by observation of appropriate pressure indications in the system or by other positive 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 tested by proving that the disk moves promptly away from the seat when the closing pressure differential is removed and flow through the valve is initiated or a mechanical opening force is applied to the disk.
.2.2.2.1 Confirmation that the disk moves away from the seat shall be by visual observation, by observation of 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 D Valves: There are no Category 0 Class 1, fT 2 or 3 valves.
6.3.4 Containment Isolation Valves Requiring Seat Leak Tests NOTE:
These valves are identified in Attachment 3 and shall be tested in accordance with 10 CFR 50, Appendix J rules at the frequency specified in Reference 2.1.2.
.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 SO1-V-1.12.
.3 Test Medium:
the test medium used for the leak rate tests will be specified in SO1-V-1.12 for the various It valve tests.
NUCLEAR GENERATION SITE ENGINEERING PYQCEDURE SO1-V-2.15 UNIT 1 REVISION PAGE 9 OF 52 TCN 6.0 PROCEDURE (Continued) 6.3.5 Reactor Coolant System Pressure Isolation Valves Requiring Seat Leak Tests NOTE: These valves are identified in Attachment 3 and shall be tested in accordance to Reference 2.1.2 and 2.5.1.
.1 These valves are reactor coolant system pressure isolation valves and will be tested with the pressure differential in the same direction as when the valve is performing its function, with the 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 adjustment shall be made by calculation appropriate to the test media and the ratio between the test and function pressure differential, assuming leakage to be directly proportional to the pressure differential to the one-half power.
.2 Leakage Rate Analysis:
leakage rate measurements shall be compared with previous measurements and with the permissible leakage rates specified in the Technical Specifications.
.3 Test Medium:
the test medium used for the leak rate tests will be specified in S01-12.9-9.
6.3.6 Valve Repair, Replacement and Maintenance
.1 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.hich could be affected by the replacement, repair or aintenance 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.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION PAGE 10 OF 52 TCN 6.0 PROCEDURE (Continued) 6.3.7 Check of Valve Position Indicator
.1 All valves with remote position indicators jhall be visually observed at least every two (2) years to.
confirm that remote valve indications accurately reflect valve operation.
6.4 Corrective Measures 6.4.1 Category A and B Valves
.1 If a valve fails to exhibit the required change of valve stem or disk position, notify the Shift Superintendent 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 Superintendent's responsibility to determine the Technical Specification requirements for operability of the affected system.
.2 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 testing 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 Superintendent immediately. The valve shall be declared inoperative immediately and an investigative Maintenance Order shall be initiated to determine corrective action.
.3 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.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION PAGE 11 OF 52 TCN O
6.0 PROCEDURE (Continued) 6.4.2 (Continued)
NOTE:
It will be the Shift Superintendent'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 the Technical Sspecifications shall be evaluated in accordance with S01-V-1.12.
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 the Technical Specifications will be (r
replaced or repaired.
.2 For 6 inch nominal pipe size valves and larger, if a leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin between the 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 T
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.
Examples of the types of valves that are excluded from exercising (cycling) tests during Plant operation are:
.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 int rity.
.3 All valves, which when cycled, could subjett a system to pressures in excess of their design pressures.
0II
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION PAGE 12 OF 52 TCN 6.0 PROCEDURE (Continued) 6.5.1 (Continued)
NOTE:
Valves which fall into the above 7 classifications are identified and shall be cycled, as practicable, at each cold shutdown or refueling but not more often than once every three (3) months.
6.6 Instrumentation 6.6.1 Instrumentation used shall meet the requirements of Section XI of Refereence 2.5.1 to the maximum extent practical.
Instruments together with their transmitters where used shall be calibrated in accordance with the governing Maintenance Procedures.
7.0 RECORDS 7.1 Records pertaining to in-service testing of valves shall be maintained in accordance with Reference 2.5.1, Article IWV-6000,Section XI.
Operations and Maintenance shall maintain these records for valves delineated by Section 6.3. 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.
7.1.2 Records of tests and examinations.
7.1.3 Preservice tests results and Manufacturer's functional test results.
0181d
MUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 5 PAGE 13 OF 52 ATTACHMENI 1/
TCN TABLE INFORMATION AND EXPLANATION OF ABBREVIATIONS PAGE Reactor Coolant System.....................
20 Reactor Coolant Gas Vent........................................21 Chemical and Volume Control System................................21 Auxiliary Cooling System........................................24 Residual Heat Removal...........................................26 Safety Injection System........................................27 Reactor Cycle Sampling System....................................
29 Radioactive Waste Disposal System................................
30 Steam........................................................... 31 Salt Water Cooling System.......................................32 Miscellaneous Water System.......................................33 Chemical Feed.
34 Feedwater and Condensate System...
5 Compressed Air.................................................
37 Air Conditioning...............................................
37 Turbine Cycle-Sampling System....................................
38 Post-Accident Containment Hydrogen Monitoring......................39 Nitrogen System................................................
39 Diesel Fuel Oil-Storage and Supply (Diesel Unit 1).................39 Diesel Generator Cooling Water System. (Diesel Unit 1)...............39 Diesel Starting Air System (Diesel Unit 1).........................39 Diesel Fuel Oil-Storage and Supply (Diesel Unit 2)..................40 Diesel Generator Cooling Water System (Diesel Unit 2)...............40 Diesel Starting Air System (Diesel Unit 2).........................40 Auxiliary Feedwater System......................................
41 HIigh Radiation Sampling System.................................... 43 A.
Valve Number: lists the valve identification number as shown on the P&ID.
B. P&ID and Coordinates: References the P&ID and the coordinates on which t
A the valve appears.
C. Class: is the ASME classification of the' valves.
D. Valve Category: indicates the catagory assigned to the valve based on the definitions of IWV-2000. Where a valve is normally exempt from the testing per IWV-1200, and is in the direct flow path of the system, this valve is categorized B passive.
E. Valve size: lists the nominal pipe size of the valve in inches.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 5 PAGE 14 OF 52 ATTACHMENT 1/
TCN TABLE INFORMATION AND EXPLANATION OF ABBREVIATIONS (Continued)
F.
Valve type: lists the valve design as indicated by the foliwing abbreviations:
ANGLE ANGLE BALL BALL BUTTERFLY BTF CHECK CK RELIEF RV SAFETY SV 3-WAY 3-WAY G.
Actuator type: lists the type of the valve actuator as indicated by the following abbreviations:
AIR OPERATOR AO HYDRAULIC OPERATOR HY MANUAL M
MOTOR OPERATOR MO SELF ACTUATED SA SOLENOID OPERATOR SO 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.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 5 PAGE 15 OF 52 ATTACHMENJ
'x TCN TABLE INFORMATION AND EXPLANATION OF ABBREVIATIONS (Continued)
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. disk 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 Setpoint Check:
RVT Relief and safety valve setpoints 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 Plant startup. 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 ninety (90) days.
NOTE:
During extended outages the valves will be tested every three (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.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT 1 REVISION 5 PAGE 16 OF 52 ATTACHMENT V TCN f2..
0 TABLE INFORMATION AND EXPLANATION OF ABBREVIATIONS (Continued)
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 Request: references the relief requests contained in the Cold Shutdown Valve Testing Justification Table and ValveRelief Requests submitted to the NRC.
N.
Remarks: lists clarification remarks.
0181d
N GENERATION SITE INGINEE ING PROCEDURE 8014 UNI REVISON 5 PAGE 1 52 ATTACHMW TCN IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT I MAX.
STROKE VALVE VALVE VALVE VALVE ACTR. 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 fall-as-is and therefore do not require a fall safe test per IWV-3415.
- 2.
The maximum stroke time associated with this valve is an assigned value pursuant to IWV-3413.
This stroke time is not a protected value and may be changed with approval of the 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.
- 6.
This valve is a pressure relief valve and will be tested at the frequency stated in IWV-3511.'
- 7.
The pressurizer safety valves and main steam safety valves shall be tested In accordance Technical Specification 4.1.2.
- 8.
The main steam power operated relief valves shall be tested in accordance with Technical Specification 4.1.2.
- 9.
Any leakage from this valve is monitored during normal operation In accordance with 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 10 CFR 50, Appendix J requirements.
The test frequency is specified in the Technical Specification 4.3.1.
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 10 CFR 50, 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 In accordance with Technical Specification 3.3.5.
- 14.
his valve is tested every 18 months in accordance with Technical Specification 4.15.
NOTE: 5 deleted
NUCLEAR GENERATION SITE ENGiNEERINO POUIEDURE SO-V-2.
UNIT REVISION 5 PAGE 18 OF 52 ATTACHMEN.
TCN IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2, & 3 VALVES UNIT 1 MAX.
STROKE VALVE VALVE VALVE VALVE ACTR.
NORMAL STROKE TEST TIME RELIEF NUMBER COORD, CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECTION TEST MODE (Sec.)
REQUEST REMARKS EXPLANATION OF NOTES (Continued)
NOTES:
- 15.
This valve Is a remotely operated hand control valve. A maximum stroke time is not required for this valve.
- 16.
Per General Design Criteria (GDC)57, these valves are not required to be automtic and will not be seat leak tested.
- 17.
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 ANGLE ANGLE GA GATE GL GLOBE CK CHECK SV SAFETY RV RELIEF BTF BUTTERFLY BALL BALL 3-WAY 3-WAY SO SOLENOID AO AIR OPERATOR SA SELF ACTUATED HY HYDRAULIC MO
- PRATOR M
MANUAL AT SEAT LEAK TEST BT FULL STROKE EXERCISE TEST BTP PARTIAL STROKE EXERCISE TEST CVT CHECK VALVE EXERCISE TEST
NUC ENERATION SITE vENGINEERING PROOURE SO1-V REVISION 5 PAGE 19 52 ATTACHMEN-1l...
TCN JN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
NORMAL/
STROKE VALVE VALVE VALVE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER COORD. CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECTION TEST MODE (Sec.)
REQUEST REMARKS EXPLANATION OF ABBREVIATIONS (Continued)
CVP PARTIAL CHECK VALVE EXERCISE TEST RVT SAFETY OR RELIEF VALVE TEST PIT.
POSITION INDICATION CHECK FST FAIL SAFE TEST CS COLD SHUT 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 LOC%0ED OPEN LC
.,CLOSED 0181d
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SOI-V-9 UNIT 1 REVISION 5 PAGE 20 52 ATTACHMELTL TCN 41.~5 IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER MI + COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS REACTOR COOLANT SYSTEM CV-530 5178105/G-2 1
B 2
GL AO 0/0 O&C BT OP 5-0 Notes 2 FST CS 15-C VRR-6
& 9 PIT RR CV-531 5178105/E-2 1
B 2
GL AO 0/0 O&C BT OP 5-0 Notes 2 FST CS 15-C VRR-6
& 9 PIT RR CV-532 5178404/C-10 2
A 3/4 BALL AO O/C O&C AT RR 5-0 Notes 2 BT OP 5-C
& 10 FST CS VRR-6 PIT RR CV-533 5178370/G-9 2
A 2
BALL AO O/C C
AT RR 20 Notes 2 BT OP
& 10 FST CS VRR-6 PIT RR CV-534 5178370/G-7 2
A 2
BALL AO O/C C
AT RR 10 Notes 2 BT OP
& 10 FST OP PIT RR CV-545 5178105/E-2 1
B 2
GL AO C/C C
BT CS 5
Notes 2 FST CS
& 9 PIT RR CV-546 5178105/G-2 1
B 2
GL AO C/C C
BT CS 5
Notes 2 FST CS
& 9 PIT RR GNI-102 5178405/G-2 2
AC 1
CK SA C
O&C AT RR Note 10 CVT CS RV-532 5V 8 O/E-5 1
C 3x6 RV SA C
RVT RR Note 7 PIT RR RV-533 5178105/E-5 1
C 3x6 RV SA C
- See Attachment 3
NUCLEA GENERATiON SITE UNIT 1 TKGINEERIKG 0AOCEDUAE SGI-V-2.15 REVISLON 5 PAGE 21 OF 52 ATTACHftI_
TCN IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS REACTOR COOLANT GAS VENT SV-2401 5178100/C-8 2
8 3/4 GA SO C/C 0
BT CS 2
Notes 2 FST CS
& 91 PIT RR SV-2402 5178100/C-9 3
B 3/4 GA SO C/C 0
BT CS 2
Notes 2 FST CS
& 9 PIT RR SV-2403 5178105/C-9 2
B 3/4 GA SO C/C 0
BT CS 2
Notes 2 FST CS
&9 PIT RR SV-2404 5178105/C-9 3
B 3/4 GA SO C/C 0
BT CS 2
Notes 2 FST CS
& 9 PIT RR SV-3401 5178100/B-8 2
B 3/4 GA SO C/C 0
BT CS 2
Notes 2 FST CS
& 9 PIT RR SV-3402 5178100/B-9 3
B 3/4 GA SO C/C 0
BT CS 2
Notes 2 FST CS
&9 PIT RR SV-3403 5178105/B-9 2
Notes 2 FST CS
& 9 PIT RR SV-3404 5178105/8-10 3
8 3/4 GA SO C/C 0
BT CS 2
Notes 2 FST CS
& 9 PIT RR CHEMICAL AND VOLUME CONTROL SYSTEM CV-202
,1?8130/E-6 1
8 2
CV-203 5178130/F-6
.1 B
FST CS VRR-6 PIT RR CV-204 5178130/F-6 1
B 2
GL AO O&C/C C
BT OP 4
- See Attachment 3
NUC ENERATION SITE ENGINEERING PROdtOURE SO1-V-2 UNIT 1 REVISION 5 PAGE 22 OF 52 ATTACHMENT 7CN IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT I MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER PID + COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS CHEMICAL AND VOLUME CONTROL SYSTEM (Continued)
CV-276 5178111/C-7 2
B 3/4 GL AO 0/0 O&C BT CS 20-0 Note 2 FST CS 20-C PIT RR CV-304 5178135/G-10 1
B 2
GL AO O/C O&C BT CS 100-0 Note 2 FST CS 80-C PIT RR CV-305 5178135/C-10 1
B GL AO C/C O&C BT CS 100-0 Note 2 FST CS 80-C PIT RR CV-334 5178145/G-3 2
B 2
GL AO C/O 0
BT OP 10 Note 2 FST OP PIT RR CV-410 5178136/D-6 2
8 2
GL AD 0/C C
BT OP 5
Note 2 FST OP PIT RR CV-411 5178136/D-9 2
B 2
GL AO O/C C
BT OP 5
Note 2 FST OP PIT RR CV-525 5178130/C-10 2
A 2
BALL HY O/C C
AT RR 30 VRR-6 Notes 2 BT OP
& 10 FST CS PIT RR CV-526 5178140/B-3 2
A 2
BALL HY O/C C
AT RR 30 Notes 2 BT OP
& 10 FST OP PIT RR CV-527 4178t1t/B-11 2
A 3
BALL HY O/C C
& 10 FST CS PIT RR CV-528 5178136/E-10 2
A 3
BALL HY O/C C
& 10 FST CS PIT RR FCV-1112 5178135/G-8 2
B 2
ANGLE AD O/C O&C BTP OP 30-0 Note 2 BT CS 30-C FST CS PIT RR
- See Attachment 3
NUCLEAR GENERATION SITE ENGINElfit PROCEDURE sol-V-2.
UNIT 1 REVISION 5 PAGE 23 OF 52 ATTACH~iajj.
TCN
.2 VN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR. FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD, CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS CHEMICAL AND VOLUME CONTROL SYSTEM (ContInued)
FCV-1115A 5178110/C-5 1
B 2
ANGLE AO 0/0 O&C BTP OP 30-0 Note 2 BT CS 15-C FST CS FCV-1115B 5178110/E-5 1
B 2
ANGLE AO 0/0 O&C BTP OP 30-0 Note 2 BT CS 15-C FST CS FCV-1115C 5178110/H-5 1
B 2
ANGLE AO O/O O&C BTP OP 30-0 Note 2 BT CS 15-C FST CS FCV-1115D 5178110/B-6 1
B 2
GL AO C/C 0
BT CS 35 Note 2 FST CS FCV-1115E 5178110/E-6 1
B 2
GL AO C/C 0
BT CS 40 Note 2 FST CS FCV-1115F 5178110/G-5 1
8 2
CL AO C/C 0
BT CS 30 Note 2 FST CS MOV-18 5178110/8-3 2
B 4
GA MO C/FAI C
& 2 MOV-19 5178110/C-3 2
B 4
GA MO C/FAI 0
& 2 MOV/LCV-5178136/D-4 2
B 4
GA MO O/FAI C
& 2 PCV-1115A 5178111/F-2 2
B 2
ANGLE AO 0/0 C
BT CS 40 Note 2 FST CS PIT RR PCV-1115B "j1/F-6 2
B 2
ANGLE AO 0/0 C
BT CS 15 Note 2 FST CS PIT RR PCV-1115C 5178111/F-9 2
B 2
ANGLE AO 0/0 C
BT CS 40 Note 2 FST CS PIT RR RV-289 5178136/0-9 2
C 3x4 RV SA C
RVT Note 6
- See Attachment 3
NUCLEAR GENERATION SITE UNIT 1 ENGINEERING PROCEDURE 80J-V-2.15 REVISION 5
?AGt 24 OF 52 ATTACH [N.2 TCN IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT I MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NAMBER P&ID + COORD, CLASS CATEGORY NCHESV TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS CHEMICAL AND VOLUME CONTROL SYSTEM (Continued)
RCP-005 5178110/C-9 1
C 2
CK SA 0
C CVT CS RCP-006 5178110/E-9 1
C 2
CK SA 0
C CVT CS RCP-104 5178110/H-9 1
C 2
CK SA 0'
C CVT CS RV-2004 5178111/A-10 2
C 3
RV SA C
RVT Note 6 VCC-002 5178135/G-11 1
C 2
CK SA 0
C CVT CS VCC-003 5178135/G-11 1
C 2
CK SA C
O&C CVT CS VCC-301 5178136/E-4 2
C 4
CK SA 0
C CVT CS VCC-305 5178135/G-5 2
C 3
CK SA
.0 O&C CVT OP VCC-306 5178135/F-6 2
C 3
CK SA 0
0&C CVT OP VCC-331 5178135/E-5 2
C 2
CK SA 0
0 CVT OP VCC-332 5178135/E-4 2
C 2
CK SA 0
0 CVT OP VCC-357 5178136/E-8 2
C 2
CK SA C
0 CVT CS AUXILIARY COOLING SYSTEM CV-722A 5178312/B-3 3
B 1 1/2 CL AO O/C C
BT CS 5
Note 2 FST CS PIT RR CV-722B 5178312/8-5 3
B 1 1/2 GL AD O/C C
BT CS 5
Note 2 FST CS PIT RR CV-722C 8
/B-8 3
B 1-1/2 GL AO O/C C
BT CS 5
Note 2
'%~*vFST Cs PIT RR CV-737A 5178310/C-9 3
B 6
BALL HY C/o BT OP 60 Note 2 FST OP PIT RR CV-7378 5178310/8-9 3
B 6
BALL HY C/o BT OP 60 Note 2 FST OP
- See Attachment 3.
- Substitute
NUCL NERATION SITE ENGJNEEkINC PROCEDURE 801-V-2 UNIT 1 REVISION $
PAGE 25 2
ATTACH N &
TCN.5~
IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS AUXILIARY COOLING SYSTEM (Continued)
MOV-720A 5178310/G-10 3
B 10 CA MO O/FAI 0
& 2 MOV-720B 5178310/E-10 3
B 10 GA MO C/FAI 0
& 2 RV-721A 5178312/B-3 3
C 1/2x1 RV SA C
RVT Note 6 RV-721B 5178312/B-5 3
C 1/2x1 RV SA C
RVT Note 6 RV-721C 5178312/B-8 3
C 1/2x1 RV SA C
RVT Note 6 RV-787 5178310/B-4 3
C 3x4 RV SA RVT Note 6 TCV-601A 5178311/8-3 3
B 8
GL AO O&C/O O&C BT OP 120-0 Note 2 FST OP 45-C PIT RR TCV-601B 5178311/A-3 3
B 8
GL AO O&C/O O&C BT OP 120-0 Note 2 FST OP 45-C PIT RR CCW-011 5178312/B-2 3
C 1 1/2 CK SA 0
C CVT CS CCW-012 5178312/B-7 3
C 1 1/2 CK SA 0
C CVT.
CS CCW-032 5178312/8-7 3
C 1-1/2 CK SA C
O&C CVT CS CCW-035 5178312/B-2 3
C 1-1/2 CK SA C
O&C CVT CS CCW-040 5178312/B-4 3
C 1-1/2 CK.
SA C
0&C CVT CS CCW-071 5178312/F-8 3
C 2
CK SA 0
0 CVT CS 8
CCW-074 5178312/0-8 3
C 2
CK SA 0
0 CVT CS CCW-092 51ti312/B-4 3
C 1 1/2 CK SA 0
C CVT CS CCW-322 5178310/E-5 3
C 8
CK SA 0
O&C CVT OP CCW-323 5178310/F-5 3
C 8
CK SA 0
O&C CVT OP CCW-325 5178310/H-5 3
C 8
CK SA 0
0&C CVT OP
- See Attachment 3
NUCLEAR GENERATION SITE ENGINEERING PWOCEDURE SONV2 UNIT 1 REVISION 5 PAGE 26 OF 52 ATACH t,2 IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD, CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS RESIDUAL HEAT REMOVAL HCV-602 5178130/B-9 2
B 6
BTF AO C/FAl 0
BTP OP 40 Note BT CS PIT In PIT RR closed position only MOV-813 5178130/8-2 1
B 8
GA MO C/FAI 0
& 2 MOV-814 5178130 C-2 1
8 8
CA MO C/FAI 0
& 2 MOV-822A 5178130/B-7 1
B 8
GA MO C/FAI 0
& 2 MOV-822B 5178130/D-7 1
8 8
GA MO C/FAI C
& 2 MOV-833 5178130/C-11 1
B 8
GA MO C/FAI 0
& 2 MOV-834 5178130/C-12 1
B 8
GA MO C/FAI 0
& 2 RHR-013 5178130/D-5 2
C 6
CK SA 0
O&C CVT CS RHR-014 5178130 B-5 2
C 6
CK SA 0
O&C CVT CS RV-206 5178130/A-6 2
C 2-1/2 RV SO C
=-
RVT Note 6 X 4
- See Attachment 3
NUCLEAR GENERATION SITE ENGINEERING PAOCURE S REVISION 5 PAGE 27 OF 52 ATTACHMEN 2 IN-SERVJCZ TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD, CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.)REQUEST REMARKS SAFETY INJECTION SYSTEM CV-875A 5178205/C-10 2
B 3
GL AO C/C 0
BT CS 25 Note 2 FST CS PIT RR CV-875B 5178205/F-10 2
B 3
GL AO C/C 0
BT CS 30 Note 2 FST CS PIT RR HV-851A 5178115/D-6 2
B 14 GA HY C/FAI 0
BT CS 4 min Note 3 PIT RR 5 max
& 4 HV-8518 5178115/G-6 2
B 14 GA HY C/FAI 0
BT CS 4 mln Notes 3 PIT RR 5 max
& 4 HV-853A 5178115/D-4 2
B 16 GA HY C/FAI 0
BT CS 3 min Notes 3 PIT RR 6 max*
4 HV-853B 5178115/G-5 2
B 16 GA HY C/FAI 0
BT CS 3 min Notes 3 PIT RR 6 max
& 4 MOV-356 5178115/G-11 1
B 2
GA MO C/FAI 0
& 3 MOV-357 5178115/F-11 1
B 2
GA MO C/FAI 0
& 3 MOV-358 5178115/D-11 1
B 2
GA MO C/FA 0
& 3 MOV-850A 5178115/G-10.
1 B
6 GA MO C/FAI 0
BT CS 9.5 min Notes 1, 3 PIT RR 11 max
& 4 MOV-850B 5178115/F-10 1
B 6
GA MO C/FAI 0
BT CS 9.5 min Notes 1, 3 PIT RR 11 max
& 4 MOV-850C 15/E-10 1
B 6
GA MO C/FAI 0
BT CS 9.5 R Notes 1, 3 PIT RR 11 "it"
& 4 MOV-866A 5178121/E-8 2
B 4
GA MO C/FAI 0
& 2
- See Attachment 3
NUC ENERATION SITE EAGINRING PROCEDURE UNIT I S01- -0 REVISION 5 PAGE 28 OF 52 ATTACHME L.2 TCN 2N-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD, CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.)jREQUEST REMARKS SAFETY INJECTION SYSTEM (Continued)
MOV-866B 5178121/E-5 2
B 4
GA MO O/FAI 0
& 2 MOV-880 5178120/D-5 2
B
.4 GA MO C/FAl 0
BT CS 25 Note 1 PIT RR MOV-883 5178120/B-9 2
B 8
GA MO O/FAl C
BT CS 350 Note 1 PIT RR MOV/LCV-5178136/G-3 2
B 4
GA MO C/FAI 0
& 3 MOV/LCV-5178136/G-3 2
B 4
GA MO C/FAI 0
BT CS
& 3 RV-868 5178115/B-9 2
C 1
RV SA C
RVT Note 6 RV-882 5178120/C-5 2
C 1/2x1 RV SA C
RVT Note 6 SV-702A 5178115/C-8 2
B 3/4 GA SO C/C C
BT OP 2
Note 18 SV-702B 5178115/D-10 2
B 3/4 GA SO C/C C
BT OP 2
Note 18 SV-702C 5178115/C-8 2
B 3/4 GA SO C/C C
BT OP 2
Note 18 SV-702D 5178115/E-10 2
B 3/4 GA SO C/C C
BT OP 2
Note 18 SV-2900 5178115/D-6 2
B 3/4 GA SO C/C 0
BT CS 2
Note 2 FST CS PIT RR SV-3900 5178115/H-6 2
B 3/4 GA SO C/C 0
BT CS 2
/F-8 2
C 6
CK SA C
O&C CVT RR sbe sembled and hand stroked
- See Attachment 3
NUCLEAR GENERATION SITE ENGINEERING WdCDURE S01-V-2.15 UNIT 1 REVISION 5 PAGE 29 OF 52 ATTACHMENT,2 TCN 55 JN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR. FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD.
CLASS CATEGORY IINCHES) TYPE TYPE POSITION DIRECTION TEST MODE _Sec.
1REQUEST REMARKS SAFETY INJECTION SYSTEM (Continued)
CRS-009 5178121/F-5 2
C 6
CK SA C
O&C CVT RR VRR-3 Must be disas sembled and hand stroked RCP-337 5178110/H-3 2
C 4
CK SA, C
O&C CVT CS SIS-003 5178115/G-10 1
AC 6
CK SA C
AT RR VRR-4 Note 13 SIS-004 5178115/E-10 1
AC 6
CK SA C
AT RR VRR-4 Note 13 SIS-010 5178115/F-10 1
AC 6
CK SA C
AT RR VRR-4 Note 13 SIS-303 5178115/G-3 2
C 12 CK SA C
0 CVP OP VRR-2 CVT SIS-304 5178115/C-3 2
C 12 CK SA C
0 CVP OP VRR-2 CVT VCC-388 5178136/G-2 2
C 4
CK SA C
0 CVT CS REACTOR CYCLE SAMPLING SYSTEM CV-948 5178150/F-3 2
A 3/8 GL AO C/C C
BT OP VRR-6 Note 2 FST CS 10
- CV-949 5178150/F-7 2
A 3/8 GL AO C/C C
BT OP 12 Note 2 FST OP PIT RR CV-951 5178150/B-3 2
A 3/8 GL AO C/C C
.& 11 FST CS CV-953
/C-3 2
A 3/8 GL AO C/C C
& 11 FST tS CV-955 5178150/E-3 2
A 3/8 GL AO C/C C
AT RR 8
VRR-6 Notes 2 BT OP
& 11 FST CS See Attachment 3 This valve Is out of service Indefinitely and therefore, not being tested.
If it is returned to service in the future, It will be tested to the requirements shown.
NUCL GENtRATION SITE
-NGINEERING PROCEDURE SO1-V UNIT 1 REVISION 5 PAGE 30 52 ATTACHMVT,2 TCN
- 0 itN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD, CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS REACTOR CYCLE SAMPLING SYSTEM (ContInued)
CV-956 5178150/D-3 2
A 3/8 GL AO C/C C
AT RR 20 VRR-6 Notes 2 BT OP
& 11 FST CS CV-957 5178150/E-6 2
A 3/8 GL AO C/C C
AT RR 25 Notes 2 BT OP
& 11 FST OP PIT RR CV-962 5178150/E-3 2
A 3/8 GL AO C/C C
& 11 FST CS CV-992 5178150/8-7 2
A 3/8 GL AO C/C C
& 11 FST OP PIT RR CV-2145 5178150/E-11 2
B 3/4 CL SO 0/C O&C BT OP 3-0 Note 2 FST OP 5-C SV-3302 5178150/C-5 2
A 3/8 GA SO O/C O&C AT RR 2-0 Notes 2 BT OP 5-C
& 11 FST OP RADIOACTIVE WASTE DISPOSAL SYSTEMS CV-102 5178158/G-9 2
A 1 1/2 GL AO O/C C
AT RR 5
VRR-6 Notes 2, BT OP 10 & 11 FST CS PIT RR CV-103 5178158/G-10 2
A 1 1/2 GL AO O/C C
AT RR 5
Notes 2, BT OP 10 & 11 FST OP PIT RR CV-104 5178158/F-9 2
A 2
GL AO O/C C
AT
.RR 5
6 Notes 1, BT OP 10, 11 FST CS PIT RR CHANGED
HUCL GENERATION SITE ENGINEERING PROCEDURE SO1-V-2 REVISION 5 PAGE 31 OF 52 ATTACHM NT/ 2 TCN 4N-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD, CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS RADIOACTIVE WASTE DISPOSAL SYSTEMS (ContInued)
CV-105 5178158/F-10 2
A 2
GL AO O/C C
AT RR 5
Notes 2, BT OP 10 & 11 FST OP PIT RR CV-106 5178158/D-9 2
A 2
GL AO O/C C
AT RR 5
VRR-6 Notes 2, BT OP 10 & 11 FST CS PIT RR CV-107 5178158/D-10 2
A 2
GL AO O/C C
AT RR 5
Notes 2, BT OP 10 & 11 FST OP PIT RR CV-535 5178158/C-10 2
A 1
BALL AO O/C C
AT RR 5
Notes 2, BT OP 10 & 11 FST OP PIT RR CV-536 5178158/C-9 2
A 1
BALL AO O/C C
AT RR 5
VRR-6 Notes 2, BT OP 10 & 11 FST CS PIT RR SV-99 5178170/D-11 2
B 1
GA SO O/C C
BT OP 2
STEAM CV-76 5178225/B-9 2
B 4
GL AO C/C 0
BT CS 30 Note 8 FST CS CV-77 5178225/0-9 2
B 4
GL AO C/C 0
/B-10 2
B 4
GL AO C/C 0
BT Cs 30 Note 8 FST CS CV-79 5178225/0-10 2
B 4
GL AO C/C 0
- See Attachment 3
NUCLEAR GENERATION SITE UNIT 1 ENGINEERING PROCEDURE SOI-V-2.15 REVISION 5
?AGE 32 OF 52 ATTACHM LNP2 TCN IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR. FAILED STROKE TEST TIME R UES RF NUMBER P&ID + COORD.
CLASS CATEGORY (INPCHES I TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST
-REMARKS STEAM (Continued)
RV-1 5178225/G-6 2
RVT RR Note 7 RV-2 5178225/C-6 2
RVT RR Note 7 RV-3 5178225/G-6 2
RVT RR Note 7 RV-4 5178225/C-6 2
RVT RR Note 7 RV-5 5178225/G-7 2
RVT RR Note 7 RV-6 5178225/C-7 2
RVT RR Note 7 RV-7 5178225/G-7 2
RVT RR Note 7 RV-8 5178225/G-8 2
RVT RR Note 7 RV-9 5178225/C-8 2
RVT RR Note 7 RV-10 5178225/G-8 2
RVT RR Note 7 PV-1650 5178226/B-9 2
B 24 GA HY 0/0 C
BT OP 2
Note 2 PIT RR PV-1651 5178226/F-9 2
B 24 GA HY 0/0 C
BT OP 2
Note 2 PIT RR SALT WATER COOLING SYSTEM SWC-338 5178350/C-5 3
C 12 CK SA O&C O&C CVT OP Aux.
Saltwater pump dis charge check So 381 17350/E 56 3
B 12 BTF M
OkCFAl Q
BT OP 6W!C 300 s175350/Hfi 5 a
18T i
iF Mee
+
zaft ST OP SWC-381 5178350/E-6 3
B 12 BTF M
0&C/FAI 0
BT OP
NUC*GENERATION SITE UNIT 1 ENGINEERING PROCEDURE S1-V-.
REVISION 5 PAGE 33 OF 52 ATTACHM NV7 TCN IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS SALT WATER COOLING SYSTEM (Continued)
SWC-382 5178350/G-5 3
C 12 CK SA O&C CVT OP Discharge Check Valve SWC-383 5178350/E-5 3
C 12 CK SA O&C CVT OP Discharge Check MISCELLANEOUS WATER SYSTEMS Valve CV-82 5178120/F-3 2
B 6
BTF AO C/O 0
BT CS 25 Note 2 FST CS PIT RR CV-92 5178120/0-3 2
B 4
BTF AO C/C 0
& 14 CV-114 5178120/F-2 2
B 6
BTF AO C/O 0
BT CS 30 Note 2 FST CS PIT RR CV-115 5178381/B-6 2
A 2
GL AO 0/C C
AT RR 6
Notes 2 BT OP
& 10 FST OP PIT RR CV-515 5178320/D-7 2
A 6
BALL HY 0/C C
BT OP 60 Note 2 FST OP PIT RR 60 CV-516 5178320/C-8 2
A 6
BALL NY O/C C
BT OP Notes 2 FST OP
& 6 PIT RR CV-517 3178120/E-5 2
8 6
BALL HY 0/C O&C BT OP 200-0 Note 2 FST OP 200-C PIT RR CV-518 508 O/F-5 2
B 6
BALL NY O/C O&C BT OP 300-6 Note 2 FST OP 300-C PIT RR CRS-301 5178120/B-9 2
C 8
CK SA C
0 CVP OP CVT CS
- See Attachment 3
NUC GENERATION SITE ENGINEERING PhOCEbURE SOG-V-2 UNIT 1 REViSION 5
?AGE 34 OF 52 ATTACHMf NV2 TCN t
IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD, CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS MISCELLANEOUS WATER SYSTEMS (Continued)
CRS-304 5178120/F-8 2
C 6
CK SA C
O&C CVT CS CRS-305 5178120/H-8 2
C 6
CK SA C
O&C CVT CS CV-537 5178381/8-5 2
A 2
BALL AO 0/C C
AT RR 15 VRR-6 Notes 2 BT OP
& 10 FST.
CS PIT RR CRS-341 5178120/D-4 2
A 2
GA M
C AT RR Notes 10
& 12 CRS-020 5178120/D-2 2
AC 2
CK SA C
AT RR Notes 10 12 CHEMICAL FEED RV-2000 5178125/B-3 2
C 1
RV SA C
RVT Note 6 RV-2001 5178125/B-3 2
C 1
RV SA C
RVT Note 6 RV-2002 5178125/B-4 2
C 1
RV SA C
RVT Note 6 RV-2003A 5178125/F-8 2
C 3/4 RV SA C
RVT Note 6 RV-2003B 5178125/D-8 2
C 3/4 RV SA C
RVT Note 6 SV-600 5178125/H-10 2
B 3/4 GL SO C/o 0
BT OP 5
Note 2 FST OP PIT RR SV-601 5178125/F-9 2
B 3/4 GL SO C/o 0
BT OP 5
$D/F-9 2
C 3/4 CK SA C
0 CVT OP Check Valve for Spray Additive Pump G-200B
- See Attachment 3
NUO GENERATION SITE m
ENGINEERING PROCEDURE SOJ-V UNIT 1 REV3SION 5 PAGE 35 OF 50 ATTACHtgN /2 T.CN
'J - _
IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.)_REQUEST REMARKS CHEMICAL FEED (Continued)
SHA-306 5178125/H-9 2
C 3/4 CK SA C
0 CVT OP Check Valve for Spray Additive Pump G-200A FEEDWATER AND CONDENSATE SYSTEM CV-36 5178205/B-10 2
B 3
GL AD C/o C
BT OP 240 Note 2 FST OP CV-37 5178205/G-10 2
B 3
GL AD C/O C
BT OP 240 Note 2 FST OP CV-100 5178206/C-3 2
B 2
ANGLE AD O/C C
BT OP 20 Note 2 FST OP CV-100A 5178206/C-2 2
B 2
GA SO O/C C
BT OP 20 Note 2 FST OP CV-100B 5178206/C-3 2
B 3
GA AO O/C C
BT OP 5
Note 2 FST OP CV-142 5178206/F-8 2
B 4
GA AD C/C O&C BT CS 30-0 Note 2 BTP OP 30-C FST CS CV-143 5178206/B-8 2
B 4
GA AO C/C O&C BT CS 30-0 Note 2 BTP OP 30-C FST CS CV-144 5178206/D-8 2
B 4
CA AD C/C O&C BT CS 30-0 Note 2 BTP OP 30-C FST CS FCV-456
/0-8 2
B 8
GA AD 0/0 C
BT CS 50 Note 2 BTP OP FST CS FCV-457 5178206/E-8 2
B 8
GA AO 0/0 C
BT CS 55 Note 2 BTP OP FST CS FCV-458 5178206/C-8 2
B 8
GA AD 0/0 C
- See Attachment 3
NUCOLE GENERATION SITE ENGINEERING PROCEDURE SOl-V-2 UNIT 1 REVISION 5 PAGE 36 OF 52 ATTACHKEW2 TCN E.7 IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD, CLASS CATEGORY (INCHES) TYPE TYPE POSIT40N DIRECTION TEST MODE (Sec.) REQUEST REMARKS FEEDWATER AND CONDENSATE SYSTEM (Continued)
FWS-345 5178206/0-8 2
C 10 CK SA 0
C CVT CS FWS-346 5178206/E-8 2
C 10 CK SA 0
C CVT CS FWS-378 5178206/D-8 2
C 4
CK SA C
O&C CVT CS FWS-379 5178206/F-8 2
C 4
CK SA C
O&C CVT CS FWS-398 5178206/C-8 2
C 10 CK SA 0
C CVT CS FWS-417 5178206/8-8 2
C 4
CK SA C
O&C CVT CS FWS-438 5178205/C-5 2
C 12 CK SA 0
O&C CVT CS Verity open during operation FWS-439 5178205/G-5 2
C 12 CK SA 0
O&C CVT CS Verity open during operation HV-852A 5178205/C-6 2
B 12 GA HY 0/FAI C
BT CS 3 min Notes 3 PIT RR 4.5 max
& 4 HV-852B 5178205/0-6 2
8 12 GA HY 0/FAI C
BT CS 3 min Notes 3 PIT RR 4.5 max
& 4 HV-854A 5178205/C-3 2
B 14 GA' HY O/FAI C
BT CS 5.5 min
& 4 HV-854B 5178205/0-3 2
B 14 GA HY O/FAI C
BT CS 5.5 min
& 4 MOV-20 5176206/E-7 2
B 10 GA MO O/FAI C
BT CS 90 Note 1 PIT RR MOV-21 51?6206/0-7 2
8 10 GA MO O/FAh C
BT CS 90 Note 1 PIT RR MOV-22 5178206/C-7 2
B 10 GA MO O/FA C
.*See Attachment 3
UN GENERATION SITE ENGINEERING PROCEDURE S31-V REVISION 5 PAG 30 52 ATTACHMENT TCN MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR. FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD, CLASS CATEGORY (INCHES) TYPE TYPE POSITION DRECTION TEST MODE (Sec-REQUEST REMARKS COMPRESSED AIR SV-125A 5178442/D-10 2
A 2
GA SO O/C C
AT RR 2
Notes 2, jt BT OP 10 & 11 FST OP PIT RR ISA-001 5178449/F-2 2
AT RR Notes 10
& 11 ISA-016 5178442/D-11 2
AC 2
CK SA 0
AT RR Notes 10 fl
& 11 ISA-539 5178442/D-10 2
A 2
GL M
C AT RR Notes 10 11 & 12 locked closed ISA-955 5178444/E-10 2
AT RR Notes 10 Io
& 11 AIR CONDITIONING CV-10 5178601/E-3 2
A 6
BTF AO O/C C
AT RR 25 Notes 2 BT OP
& 10 FST OP PIT RR CV-40 5178600/C-11 2
A 2
3 Way AO O/C C
AT RR 5
VRR-6 Notes 2 BT OP
& 10 FST CS CV-116 5178600/B-11 2
A 6
BTF AO C/C AT RR 25 VRR-6 Notes 2 BT OP
& 10 FST CS PIT RR CV-146 5178600/D-11 2
A 1
GL AO O/C O&C AT RR 2-0 VRR-6 Notes 2 BT OP 5-C
& 10 FST CS PIT RR CV-147 00/D-2 2
A 1
GL AO O/C O&C AT RR 2-0 Notes 2 BT OP 5-C,
& 10 FST CS PIT RR CV-2048 5178601/G-5
.2 B
3/8 GL AO 0/0 O&C BT OP 2-0 Note 2*
FST OP 2-C
- Position indication is not available and testing will not be conducted until a valid test technique is developed.
STIop
UC#ENERAT ION SITE ENGINEERING PROCEDURE SO1-V REVISION 5 PAGE 38 52 ATTACHM TP MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR. FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS AIR CONDITIONING (Continued)
CV-2049 5178601/F-5 2
B 3/8 GL AD 0/0 0&C BT OP 2-0 Note 2*
FST OP 2-C CVS-301 5178601/B-4 2
A 24 BTF M
C AT RR Locked Closed Notes 10
& 12 CVS-313 5178601/D-6 2
A 24 BTF M
C AT RR Locked Closed Notes 10
& 12 POV-9 5178601/C-3 2
A 24 BTF AO C/C C
AT RR Notes 10
& 12 POV-10 5178601/0-6 2
A 24 BTF AO C/C C
AT RR Notes 10
& 12 SV-1212-8 5178601/F-3 2
A 1
Notes 2 BT OP
& 10 FST OP PIT RR SV-1212-9 5178601/G-3 2
A 1
Notes 2 BT OP
& 10 FST OP PIT RR TURBINE CYCLE SAMPLING SYSTEM SV-119 5178260/F-2 2
B 1/4 GA SO O/C C
BT OP 2
Notes 2 FST OP
& 17 PIT RR SV-120 5178260/F-3 2
B 1/4 GA SO O/C C
BT OP 2
Notes 2 FST OP
.5178260/F-4 2
B 1/4 GA SO O/C C
BT OP 2
Notes 2 FST OP
& 17 PIT RR SV-122 51t8260/F-5 2
B 3/8 GA so 0/C C
BT OP 2
Notes 2 FST OP
- Position Indication Is not available and testing will not be conducted until a valid test technique is developed.
S73,0 A#
TIME~ PovIPED
NUNI NEATO SITE9 N
o ENGINEERING PROCEDURE SO V T
REVISION 5 PAGE 39 52 ATTACHMENT/1 TCN MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR. FAILED STR3KE TEST TIME RELIEF NUMBER P&ID + COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTJ0N TEST MODE (See, L REQUEST REMARKS TURBINE CYCLE SAMPLING SYSTEM (Continued)
SV-123 5178260/F-5 2
Notes 2 FST OP
& 17 PIT RR SV-124 5178260/F-6 2
B 3/8 GA SO O/C C
BT OP 2
Notes 2 )
FST OP
& 17 PIT RR POST-ACCIDENT CONTAINMENT HYDROGEN MONITORING SV-2004 5178402/F-5 2
A 1/2 GL SO O/C C
AT RR 2
Notes 2, BT OP 10 & 11 FST OP PIT RR SV-3004 5178405/H-2 2
A 1/2 GL SO O/C C
AT RR 2
VRR-6 Notes 2, BT OP 10 & 11 FST CS PIT RR NITROGEN SYSTEM GNI-001 5178405/C-2 2
A 3/4 GL M
C AT RR Notes 10, 11 & 12 GNI-336 5178400/B-6 2
A 3/4 GL M
C AT RR Notes 10, 11 & 12 DIESEL FUEL OIL -
STORAGE & SUPPLY SYSTEM (DIESEL UNIT 1)
DFS-309 5178800/E-11 3
C 2
CK SA C.
0&C CVT OP DFS-308 5178800/E-8 3
C 2
CK SA C
O&C CVT OP DIESEL GENERATOR COOLING WATER SYSTEM (DIESEL UNIT 11 DWS-306 5178810/E-3 3
C 1 1/2 CK SA 0
0 CVT OP VRR-1 C
C CVT RR DWS-309 S
0U1O/C-4 3
C 8
CK SA 0
0 CVT OP C
C CVT RR DIESEL STARTING AIR SYSTEM (DIESEL UNIT 1)
SV-301 5178816/C-4 3
B 3
GA SO C/C 0
BT OP 2
FST OP
NUC GENEAAT ION SI TE UNIT ZNT GINEEIRING PROCEDURE SoliV REVISION 5 PAGE 40 52 ATTACHMf,.l TCN 5_6 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD.
CLASS CATEGORY (INCHESV TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) RECUEST EMARKS DIESEL STARTING AIR SYSTEM (DIESEL UNIT 1)
(Continued)
SV-302 5178816/G-9 3
B 3
GA SO C/C 0
BT OP 2
FST OP SV-304 5178816/C-9 3
8 3
GA SO C/C 0
BT OP 2
FST OP SV-305 5178816/G-4 3
B 3
GA SO C/C 0
BT OP 2
FST OP DSS-357 5178815/E-2 3
C 2
CK SA C
O&C CVT OP DSS-358 5178815/D-12 3
C 2
CK SA C
O&C CVT OP DSS-305 5178816/C-4 3
C 3
CK SA C
0 CVT OP DSS-306 5178816/C-9 3
C 3
CK SA C
0 CYT OP DSS-309 5178816/G-4 3
C 3
CK SA C
0 CVT OP DSS-310 5178816/G-9 3
C 3
CK SA C
0 CVT OP DIESEL FUEL OIL -
STORAGE & SUPPLY SYSTEM (DIESEL UNIT 2)
DFN-308 5178830/E-11 3
C 2
CK SA C
O&C CVT OP DFN-309 5178830/E-8 3
C 2
CK SA C
O&C CVT OP DIESEL GENERATOR COOLING WATER SYSTEM (DIESEL UNIT 2)
DWN-306 5178840/E-3 3
C 1 1/2 CK SA 0
0 CVT OP VRR-1 0
C CVT RR DWN-309 5178840/D-4 3
C 5178 CK SA 0
0 CVT OP VRR-1 0
C CVT RR DIESEL AIR STARTING SYSTEM (DIESEL UNIT 2)
SV-401 5178846/C-4 3
B 3
GA SO C/C 0
BT OP 2
FST OP SV-402
/C-9 3
B 3
GA SO C/C 0
BT OP 2
FST Op SV-404 5178846/C-9 3
B 3
CA SO C/C 0
BT OP 2
FST OP SV-405 5178846/G-4 3
B 3
FST OP
NUC*
GENERATION SITE ENGINEERING PROCEDURE UNIT SO1-V REVISION 5 PAGE 41 OF 52 ATTACHM NT/1 7CN MAX VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR.
FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD.
CLASS CATEGORY (INCHESQ TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS DIESEL AIR STARTING SYSTEM (DIESEL UNIT 21 (Continued)
DSN-305 5178846/0-4 3
C 3
CK SA C
0 CVT OP DSN-306 5178846/0-9 3
C 3
CK SA C
0 CVT OP DSN 309 5178846/C-4 3
C 3
CK SA C
0 CVT OP DSN-310 5178846/C-9 3
C 3
CK SA C
0 CVT OP DSN-357 5178845/E-1 3
C 2
CK SA C
O&C CVT OP DSN-358 5178845/E-12 3
C 2
CK SA C
O&C CYT OP AUXILIARY FEEDWATER SYSTEM CV-113 5178221/E-3 2
8 3
ANGLE AO O/FAI O&C BT OP 120 OP CV-3201 5178221/E-6 2
8 3
CA AO C/C 0
BT OP 50 Note 2 FST OP CV-3213 5178220/H-6 2
B 3
GA AO C/O O&C BT OP 20 Note 2 FST OP PIT RR FCV-2300 5178220/H-10 2
B 3
GA AO 0/0 O&C BT OP 40-0 Note 2 FST CS 20-C PIT RR FCV-2301 5178220/D-10 2
B 3
GA AO 0/0 O&C BT OP 40-0 0
Note 2 FST CS 20-C PIT RR FCV-3300 5178220/C-10 2
8 3
GA AO 0/0 O&C BT OP 40-0 Note 2 FST CS 20-0 PIT RR FCV-3301 5178220/E-10 2
B 3
GA AO 0/0 0&C BT OP 40-0 a
Note 2 FST CS 20-0 PIT RR MOV-1202 8-6 2
B 3
GA MO C/FAI 0
& 2 SV-3200 5178221/D-6 2
B 1/2 CA SO C/o 0
BT OP 2
- See Attachment 3
NU ENERATION SITE ENGINEERING PO UNI ENIERN ROCEDURE SO0 REVISION 5 PAGE 42 52 ATTACHMEN/
TCN VALVE NORMAL/
STROK VALVE VALVE SIZE VALVE ACTR. FAILED STROKE ONST TIME RE
CLASS CATEGORY (INCHES) TYPE-TYPE
-POSITION -DIRECTION TEST MODE I Sec. 1 REQUEST REMARKS AUXILIARY FEEDWATER SYSTEM (Continued)
SV-3202 5178221/D-10 2
B 1/2 GA so 0/0 C
BT OP 2
Note 2 FST OP PIT RR SV-3203 5178221/C-10 2
B 1/2 GA so 0/0 C
BT OP 2
Note 2 FST OP PIT RR SV-3204 5178221/B-10 2
B 1/2 CA so 0/0 C
BT OP 2
Note 2 FST OP PIT RR SV-3205 5178221/E-11 2
B 1/2 GA So C/O BT OP 2
Note 2 FST OP PIT RR SV-3211 5178221/G-5 2
B 1/2 CA SO C/O C
BT OP 2
Note 2 FST OP PIT RR SV-3214 5178221/F-6 2
B 1/2 GA SO C/o C
BT OP 2
Note 2 FST OP PIT RR AFW-303 5178220/G-5 2
C 3
CK SA C
0 CVT CS AFW-304 5178220/C-5 2
C 3
CK SA C
0 CVT CS AFW-309 5178220/G-8 2
C 3
CK SA C
0 CVT CS AFW-310 5178220/F-8 2
C 3
CK SA C
0 CVT CS AFW-312 5178220/C-8 2
C 3
CK SA C
0 CVT CS AFW-317 5178220/1-7 2
C 3
CK SA C
0 CVT CS AFW-318 5178220/C-7 2
C 3
CK SA C
0 CVT CS AFW-320 5178220/C-6 2
C 3
CK SA C
0 CVT CS AFW-321 5
8SRO/H-11 2
C 3
CK SA C
0 CVT CS AFW-322 5178220/F-11 2
C 3
CK SA C
0 CVT
-CS AFW-324 5178220/C-11 2
C 3
CK SA C
0 CVT CS AFW-332 5178220/D-3 2
C 1
CK SA C
0 CVT OP
- See Attachment 3
NUCGENERATION SITE UNIT S
ENGINEERING PROCEDURE SO1-V*2 REVISION 5 PAGE 43 OF 52 ATTACHM N /2 TCN 7
IN-SERVICE TESTING PROGRAM ASME-CLASS 1, 2 & 3 VALVES UNIT 1 MAX.
VALVE NORMAL/
STROKE VALVE VALVE SIZE VALVE ACTR. FAILED STROKE TEST TIME RELIEF NUMBER P&ID + COORD.
CLASS CATEGORY (INCHES) TYPE TYPE POSITION DIRECTION TEST MODE (Sec.) REQUEST REMARKS AUXILIARY FEEDWATER SYSTEM (Continued)
AFW-335 5178220/F-3 2
C 1
CK SA C
0 CVT OP AFW-339 5178220/E-3 2
C 1
CK SA C
0 CVT OP AFW-340 5178220/E-3 2
C 1
CK SA C
0 CVT OP HIGH RADIATION SAMPLING SYSTEM SV-3303 5178950/F-9 2
A 1
GL SO C/C OC FST AT 2
Notes 2, PIT BT 10 & 11 OP RR PAS-004 5178950/F-10 2
AT RR Notes 10 11 0181d
NUCO GENERATION SITE
/(OTE:
L UNIT 1 M
NGINEERING PROCEDUAE SOI-V-2.15 PiE014D' REVISION PAGE 44 OF 52 fj~p-Mr-0ATTACHMEW COLD SHUTDOWN VALVE TEST9NC JUSTiFICATION TABLE SYSTEM REACTOR COOLANT SYSTEM VALVE VALVE JUSTIFICATION FOR COLD SHUTDOWN NUMBER P&ID COORD-CLASS CAT TESTING FREQUENCY OF VALVES CV-545 5178105/E-2 1
B Failure of valve during operation could cause breach of Reactor Coolant System pressure boundary.
CV-546 5178105/0-2 B
Same as CV-545 GNI-102 5178405/G-2 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.
REACTOR COOLANT GAS VENT SV-2401 5178100/C-8 1
B Same as CV-545 SV-2402 5178100/0-9 1
B Same as CV-545 SV-2403 5178105/C-9 1
B Same as CV-545 SV-2404 5178105/C-9 1
B Same as CV-545 SV-3401 5178100/B-8 1
B Same as CV-545 SV-3402 5178100/B-9 1
B Same as CV-545 SV-3403 5178105/B-9 1
8 Same as CV-545 SV-3404 5178105/8-10 1
B Same as CV-545 CV-276 5178111/C-7 2
B Full or partial stroke exercising during Plant operation would affect operation of the seal water system.
CV-304 5178154j
- 10 1
B Full or partial stroke exercising would affect reao
'ant level during Plant operation.
CV-305 5178135/G-10 1
B Full or partial stroke exercising during Plant operation would result In thermal shock to the pressurizer spray header.
NUCLEAR GENERAtION SITE UNIT I ENGONEERING PROCEDURE O8J-V-2.15 REVISION 5 PAGE! 45 OF 52 ATTACHMENT,3/
TCN COLD SHUTDOWN VALVE TESTING JUSTIFICATION TABLE SYSTEM CHEMICAL AND VOLUME CONTROL SYSTEM VALVE VALVE JUSTIFICATION FOR COLD SHUTDOWN NUMBER P&ID + COORD.
CLASS
- CAT,
-TESTING FREQUENCY OF VALVES CV-527 5178111/B-11 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-2004) In the upstream piping to lift.
CV-528 5178136/E-10 2
A Same as CV-527 FCV-1112 5178135/G-8 2
A Full stroke exercising during Plant operation would inhibit charging flow.
FCV-1115A 5178110/C-5 1
A Full stroke exercising of this valve would interrupt seal water flow to the RCPs and could result in damage to the pump seals.
FCV-11158 5178110/E-5 1
A Same as FCV-1115A FCV-1115C 5178110/H-5 1
A Same as FCV-1115A FCV-1115D 5178110/B-6 1
A Partial or full stroke exercising during plant operation would result in excessive Resotor Coolant Pump seal water flow and potential subsequent damage to the pump seals.
FCV-1115E 5178110/E-6 1
A Same as FCV-1115D FCV-1115F 5178110/G-5 1
A Same as FCV-1115E MOV/LCV 5178136/D-4 2
B Closing this valve during normal operation would isolate the normal 1100OC suction to the charging pumps and consequently Interupt reactor coolant pump seal flow. Alternate flow paths would result In overboration of the Reactor.Coolant System and a Plant shutdown.
PCV-1115A 5178111/F-2 2
B This valve operates full open or full closed only. Exercising this valve during plant operation would inhibit seal water flow to the Reactor Coolant pumps possibly damaging the pumps.
PCV-1115 8
$1 "6
2 B
Same as PCV-1115A PCV-1115C 5178111/F-9 2
B Same as PCV-1115A VCC-301 5178136/E-4 2
C This valve cannot be stroked during normal operation without interrupting flow to the charging pumps suction.
NUCLEAR ENERATION SITE ENGINEERING PROCEDURE SO1-V-2.15 UNIT I REVJSION 5 PAGE 46 OF 52 ATTACHMENT 3 TCN 00 COLD SHUTDOWN VALVE TESTING JUSTIFICATION TABLE SYSTEM CHEMICAL AND VOLUME CONTROL SYSTEM VALVE VALVE JUSTIFICATION FOR COLD SHUTDOWN NUMBER M&ID + COORD.
CLASS CAT.
-TESTING FREUENCY OF VALVES RCP-104 5178110/E-8 1
C This valve cannot be stroked during normal operation without affecting seal Injection flow to the Reactor Coolant pumps.
RCP-006 5178110/E-9 1
C Same as RCP-104.
RCP-005 5178110/C-9 1
C Same as RCP-1O*.
VCC-002 5178135/C-11 1
C This valve cannot be stroked during normal operation without affectIng Reactor Coolant Level Control.
VCC-003 5178135/G-11 1
C Exercising this valve during normal operation would result in thermal shock to the auxiI lary spray header In the pressurizer.
VCC-357 5178136/E-8 2
C Testing this valve while In operation would require isolation of the seal water return l ine and stopping both charging pumps causing Interrupt ion of Reactor Coolant pump seal water flow.
CV-722A 5178312/B-3 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 pump thermal barrier cooling coils.
CV-7228 5178312/B-6 3
B Same as CV-722A.
CV-722C 5178312/B-B 3
B Same as CV-722A.
CCW-071 5178312/G-8 3
C Full stroke testing of these check valves cannot be accompilshed during power operation.
These two check valves discharge through a CCW-074 5178312/F-8 common flowmeter.
Verification of flow through each check valve cannot be accomplished without Isolation of one check valve.
The Isolation valves for these check valves are located Inside containment and therefore are Inaccessible during powroperation.
FullI stroke exercising shal I be performed during @@Idtulitdowm.
CCW-011 5178312/B-2 3
C Testing of this'valve requires Interruption of cooling wiate r to the Reactor Coollng pump.
CCW-092 5178312/1-4 3
C Sane as CCW-O0l.
NtflW'GENERATION SITE' UNIT 1 ENGINEERING PROCEDURE Sol.-V REVISION 5 PAGE 47 OF 52 ATTACHMEU 3 TCN COLD SHUTDOWN VALVE TESTING JUSTIFICATION TABLE SYSTEM CHEMICAL AND VOLUME CONTROL SYSTEM VALVE VALVE JUST IFI CATIION FOR COLD SHUTDOWN NUMBER M&ID + COORD.
CLASS
- CAT, TESTING FREQUENCY OF VALVES CCW-012 5178312/B-7 3
C Same as CCW-011.
CCW-035 5178312/B-2 3
C Testing of this valve requires interruption of cooling water to the Reactor Cooling pump.
CCW-040 5178312/8-4 3
C Same as CCW-035.
CCW-032 5178312/B-7 3
C Same as CCW-035.
HCV-602 5178130/B-9 2
a 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 5178130/B-2 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 5178130/C-2 1
B Same as MOV-813.
MOV-833 5178130/C-11 1
B Same as MOV-813.
MOV-834 5178130/C-12 1
8 Same as MOV-813.
RHR-014 517Et*/0m'-
.2 C
Residual heat removal pumps must be run to stroke two VWLY.
This can only be done during cold shutdown due to system '04tibre limitations.
RHR-013 5178130/D-5 2
C Same as RHR-014.
NUCLEAR GENERATION SITE UNIT 1 ENGINEERING PROCEDUAt SOl-V-2.15 REVISION 5 PAGE 48 OF 52 ATTACHMEN TCN COLD SHUTDOWN VALVE TESTING JUSTIFICATION TABLE SYSTEM SAFETY INJECTION SYSTEM NUMBER PID + COORD CLASS VALVE JUSTIFICATION FOR COLD SHUTDOWN CATBER PI_ __ _RCLAS__AT.TESTING FREQUENCY OF VALVES CV-875A 5178205/C-10 2
B This valve cannot be full or part stroked during normal Plant operation. Opening this valve would cause unborated feedwater to flow into the RWST diluting its boron concentration.
CV-875B 5178205/F-10 2
B Same as CV-875A.
HV-851A 5178115/D-6 2
A Exercising this valve during normal operation would disrupt feedwater flow to the steam generator.
HV-851B 5178115/G-6 2
A Same as HV-851A.
HV-853A 5178115/D-4 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 5178115/G-5 2
B Same as HV-853A.
MOV-356 5178115/0-11 1
B This valve can be operated fulS open or full closed only. Opening this valve during Plant operation would disrupt RCP seal water flow.
MOV-357 5178115/F-11 1
B Same as MOV-356.
MOV-358 5178115/D-11 1
B Same as MOV-356.
MOV-850A 5178115/0-10 1
B This valve cannot be full or part stroke exercised during normal operation since it performs a pressure isolation function.
MOV-8508 5178115/F-10 1
B Same as MOV-850A.
MOV-850C 5178115/E-10 1
B Same as MOV-850A.
MOV-866A 5178121/E-8 2
B This valve is located on the discharge line of the SIS recirculation pumps.
Pumps are normaily dry and in a standby valve IIneup for post-LOCA recirculation, Testing during normal Plant operation could result In loss of recirculation capabilities.
MOV-866B 5178121l/E-5 2
B Same as MOV-866A.
MOV-880 5178120/D-5 2
B Opening this valve during operation would disrupt RCP seal water flow.
MOV/LCV-5178136/G-3 2
B Full or part stroking o" this valve during normal Plant operation 11008 would affect reactor coolant level control.
NU GENERAtION SITE ENGINEERING PROCEDURE SOI-V-2.15 UNIT REViSION 5 PAGE 49 OF 52 ATTACHMEN 3/
TON COLD SHUTDOWN VALVE TESTING JUSTIFICATION TABLE SYSTEM SAFETY INJECTION SYSTEM VALVE VALVE JUSTIFICATION FOR COLD SHUTDOWN NUMBER MID
- COORD,
-CAT, TESTING FREQUENCY OF VALVES MOV/LCV-5178136/0-3 2
B Same as MOV/LCV-11OOB 11000 SV-2900 5178115/0-6 2
B Same as HV-851A.
SV-3900 5178115/H-6 2
B Same as HV-851A.
VCC-388 2
C This valve cannot be full or part stroked during normal plant operation. Stroking would require opening MOV/LCV-11008 or MOV/LCV-1100D which would affect reactor coolant level control.
RCP-337 2
C Same as MOV-880.
CV-76 5178225/B-9 2
B Exercising this valve during normal Plant operation would dump steam to the atmosphere.
CV-78 5178225/G-9 2
B Same as CV-76.
CV-78 5178225/0-10 2
8 Same as CV-76.
CV-79 5178225/G-10 2
B Same as CV-76.
CV-82 5178120/F-3 2
B This valve cannot be full or partially stroked during normal Plant operation. Stroking the valve would cause the RWST to partially drain to the containment spray piping and Into Containment through a drain In the spray piping.
CV-114 5178120/F-2 2
B Same as CV-82.
CRS-304 517Stbbtif-2 C
This valve cannot be stroke tested during operatio0 10 the potential for fJoodng the fire protection or containment spray piping with bora'ted water.
CRS-305 5178120/H-8 2
C Same as CRS-304.
CRS-301 5178120/B-9 2
C Same as CRS-304.
NUI ENERATION SiTE UNIT 1 ENGINEERING.PROCEDURE S01-V REVISION 5 PAGE 50 OF 52 ATTACHMENT 3 TCN COLD SHUTDOWN VALVE TESTING JUSTIFICATION TABLE SYSTEM FEEDWATER AND CONDENSATE SYSTEM NUMBER PAVID + COORD.
CLASS V
E JUSTIF50ATION FOR COLD SHUTDOWN NDCTESTING FREQUENCY OF VALVES CV-142 5178206/F-8 2
B Full stroke exercising during Plant operation would disrupt feedwater flow.
CV-143 5178206/B-8 2
B Same as CV-142.
CV-144i 5178206/D-8 2
B Same as CV-142.
FCV-456 5178206/G-8 2
A Full stroke exercising during Plant operation would interrupt feedwater flow to the steam generator.
FCV-457 5178206/E-8 2
A Same as FCV-456.
FCV-458 5178206/C-8 2
A Same as FCV-456.
HV-852A 5178205/C-6 2
B This valve operates full open or full closed only. Full stroking during normal Plant operations would cause loss of feedwater to the steam generators.
HV-852B 5178205/G-6 2
B Same as HV-852A.
HV-854A 5178205/C-3 2
B Same as HV-852A.
HV-854B 5178205/G-3 2
B Same as HV-852A.
MOV-20 5178206/E-7 2
a Same as FCV-456.
MOV-21 5178206/G-7 2
B Same as FCV-456.
MOV-22 5178206/C-7 2
B Same as FCV-456.
FWS-378 5178207/D-8 2
C Exercising the Main Feedwater/Steam Generator check valves during normal Plant power operation would interfere with the operation of the Steam Generator Level Control System.
FWS-379 51?8206/P-6 2
C Same as FWS-378.
FWS-417 51?
8 2
C Same as FWS-378.
FWS-398 5178206/C-8 2
C Full or part stroking of this valve during normal Plant operation would Interrupt feedwater flow to the steam generator.
FWS-345 5178206/c-8 2
C Same as FWS-398.
FWS-346 5178206/E-8 2
C Same as FWS-398.
-V UNIT 1 GENGINEERING PROCEDURE S01-V-2.15 REVISION PAGE 51 OF 52 ATTACHMENT TCN COLD SHUTDOWN VALVE TESTING JUSTIFICATION TABLE SYSTEM AUXILIARY FEEDWATER SYSTEM VALVE VALVE JUSTIFICATION FOR COLD SHUTDOWN NUMBER PAITD + COORD-CLASS
- CAT, TESTING FREQUENCY OF VALVES FWS-438 5178205/C-5 2
C Same as FWS-398.
FWS-439 5178205/G-5 2
C Same as FWS-398.
FCV-2300 5178220/H-TO 2
B Fail-safe testing of this valve requires removing air 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 fall-safe testing of this vaive to reduce the frequency of deenergizing and energizing of the control loop to mimimize degradation of the control loop components. This will be fail-safe tested during cold shutdown.
FCV-2301 5178220/D-10 2
B Same as FCV-2300.
FCV-3300 5178220/C-10 2
B Same as FCV-2300.
FCV-3301 5178220/E-10 2
B Same as FCV-2300.
AFW-303 5178220/G-5 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.
AFW-304 5178220/C-5 2
C Same as AFW-303.
AFW-317 5178220/B-7 2
C Same as AFW-303.
AFW-324 5178220/C-11 2
C Same as.AFW-303.
AFW-318 5178220/C-7 2
C Same as AFW-303.
AFW-322 517220/F-11 2
C Same as AFW-303.
AFW-320
,i9 c,6 2
C Same as AFW-303.
AFW-321 5178220/H-11 2
C Same as AFW-303.
AFW-312 5178220/C-8 2
C Same as AFW-303.
NUCLO GENERATION SITE SO UNIT 1 ENGINEERING POCEDURE V
REVISION 5 PAGE 52 OF 52 ATTACHMENT 3/,
TCN COLD SHUTDOWN VALVE TESTING JUSTIFICATION TABLE SYSTEM AUXILIARY FEEDWATER VALVE VALVE JUSTIFICATION FOR COLD SHUTDOWN NUMBER MID + COORD CLASS
- CAT, TESTING FREQUENCY OF VALVES AFW-310 5178220/F-8 2
C Same as AFW-303.
AFW-309 5178220/G-8 2
c Same as AFW-303.
0181d