ML20072M904
| ML20072M904 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/25/1983 |
| From: | James Gavula, Kin J, Pickens T NUTECH ENGINEERS, INC. |
| To: | |
| Shared Package | |
| ML20072M885 | List: |
| References | |
| BOS-03-0201, BOS-3-201, NUDOCS 8307150128 | |
| Download: ML20072M904 (120) | |
Text
BOS-03-0201
["'N Y' Revision 1
- 87. 5 3. 201 r-
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INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES PILGRIM NUCLEAR POWER STATION Prepared for:
9 Boston Edison Company Prepared by:
NUTECH Engineers Chicago Prepared y: Issued by:
v- /
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W(Ap =&5 J. W./ Kin T. A. Yickens Projdct Engineer Project Manager Approved b :
M Date: May 25, 1983
- 7. U . G la
- [j [ Engine ing Manager l
l 8307150128 830711 PDR ADOCK 05000293 P PDR
Revision Control Sheet
Title:
Inservice Testing Program for Pumps and Valves Pilgrim Nuclear Power Station n
J. W. Kin ]g [
Senior Engineer (W \
NAME/ TITLE INITIAL A. W. Joslin Consultant II k NAME/ TITLE INITIAL Effective Accuracy Criteria Pace (s) Revision Prepared Check Check iii, iv 1 dlMN 4WI NA-1-1 to 1-2 1 2-1 to 2-21 1 Tables for IST Pump Program 1 .
3-1 to 3-47 1 Tables for IST Y ,
Valve Program 1
@% A WJ BOS-03-0201 11 Revision 1
TABLE OF CONTENTS Page
1.0 INTRODUCTION
.......................................... 1-1 2.0 INSERVICE TESTING PROGRAM FOR PUMPS................... 2-1 2.1 General Information.............................. 2-1 2.1.1 Applicable Code........................ 2-1 2.1.2 Pump Program Table Description......... 2-1 2.1.3 " Inservice Test Ouantities" Columns.... 2-2 2.1.4 Measurement of Inservice Test Ouantities............................. 2-2 2.1.5 Allowable Ranges of Test Ouantities.... 2-3 2.1.6 B e a r i n g Lu b r i c a n t . . . . . . . . . . . . . . . . . . . . . . 2-3 2.1.7 Instrument Accuracy.................... 2-3 2.1.8 Exempted Pumps Within Systems Classified for ISI..................... 2-4 2.2 Relief Requests for Inservice
{ 2.3 Pump Testing Program............................. 2-10 Inservice Pump Testing Program................... 2-22 3.0 INSERVIbE TESTING PROGRAM FOR VALVES.................. 3-1 3.1 General Information.............................. 3-1 3.1.1 Valve Program Table Description........ 3-1 3.1.2 Excess Flow Check Valves . . . . . . . . . . . . . . . 3-5 3.1.3 Valve Numbering........................ 3-5 3.2 Relief Requests for Inservice Valve Testing Program............................ 3-10 3.3 Inservice Valve Testing Program.................. 3-48 b) v BOS-03-0201 iii Revision 1
LIST OF TABLES Table Title Page 2.1-1 Key to Pump Names................................ 2-5 2.1-2 Owner Specified Ranges for Test Ouantities....... 2-6 2.3-1 P u mp I ST L i s t i n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-23 3.1-1 I n s e r v i ce Va l ve Te s t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-6 3.1-2 Test Frequency................................... 3-9 3.3-1 List of Systems.................................. 3-49 3.3-2 Valve IST Program Remarks........................ 3-50 3.3-3 Valve IST Listing................................ -
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BOS-03-0201 iv Revision 1
E
1.0 INTRODUCTION
Revision 1 of the Pilgrim Nuclear Power Station (PNPS)
Unit 1 ASME Inservice Testing Program for Pumps and Valves will be in effect f rom December 8, 1982 through and including December 7, 1992. The period of tinte this revision of the program is effective represents the second 120 month (10 year) inspection interval. This program will be updated prior to the start of the third
~
inspection interval in accordance with the requirements of 10CFR50.55a(g).
The program contained herein outlines the Inservice Testing (IST) requirements for Pilgrim Nuclear Power Station. This program is based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda. All references to IWP or IWV in this document correspond to
[
Subsection IWP or IWV of ASME Section XI, 1980 Edition through the Winter 1980 Addenda unless otherwise noted.
This IST program was developed using the ISI classification boundaries and the following documents:
Title 10, Code of Federal Regulations, ,
Chapter 50.55a(g)
Division 1 Regulatory Guides Standard Review Plan 3.9.6, " Inservice Testing of Pumps and Valves" Division 1 Draft Regulatory Guide and Value/ Impact Statement, " Identification of Valves for Inclusion in Inservice Test Programs" "NRC Staff Guidance for Preparing Pump
() and Valve Testing Programs and Associated BOS-03-0201 1-1 Revision 1 i
Relief Request," January 1978 i (
- Final Safety Analysis Report, Pilgrim l
Nuclear Power Station Technical Specifications, Pilgrim Nuclear Power Station The inservice tests identified in this program will I
verify the operational readiness of pumps and valves whose functions are required for safety. Pumps and valves which function to mitigate the consequences of an accident or to bring the reactor to a stable condition have been included in this program. The IST classification of each pump and valve matches the ISI classification indicated on the P& ids with one exception, pumps and valves in the IST program which are not within the ISI classification boundaries are indicated as non-classed (NC).
O
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BOS-03-0201 1-2 Revision 1
r- 2.0 INSERVICE TESTING PROGRAM FOR PUMPS
()]
2.1 General Information 2.1.1 Applicable Code This Inservice Testing Program for ISI Class 1, 2, 3 and NC Pumps meets the requirements of Subsection IWP of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included in Section 2.2.
2.1.2 Pump Program Table Description The tables in Section 2.3 list all pumps included in the
(]) Pilgrim Nuclear Power Station IST Program. The data contained in these tables identifies all pumps subject to inservice testing, the inservice test quantities, the I inservice testing interval, and any applicable remarks. The column headings in these tables are listed and explained below:
PUMP NUMBER: The pump identification number PUMP NAME: Keys to the pump names are given in Table 2.1-1 CLASS: The ISI classification of the pump -
P&ID: The Bechtel PNPS drawing number for the P&ID COOR: The coordinate location on the P&I6 where the pump appears.
SPEED, INLET PRES, DIFF PRES, FLOW RATE, VIBRATION and BEARING TEMP: Inservice Test Ouantities
, to be measured in accordance with Table
(_). IWP-3100-1 BOS-03-0201 2-1 Revision 1 '
i TEST INTERVAL: The frequency of IST as prescribed in IWP-3400 REMARKS: Remarks in the IST Program are coded as Note 001, Note 002, etc. Any remarks will be listed in the Pump IST Program Remarks.
2.1.3 " Inservice Test Quantities" Columns When the character "Y" appears in a particular test quantity column, that quantity will be measured during inservice testing in accordance with Subsection IWP. If a modified test is planned or if the character "N" appears in a particular test quantity column, a request for relief number will be referenced. Requests for relief are abbreviated RP ___. The actual request for relief is attached to Section 2.2.
2.1.4 Measurement of Inservice Test Ouantities
- Speed: Per IWP-4400, shaft speed measurements are not applicable (NA) for pumps coupled to synchronous or induction type drivers. For variable speed pumps, the pump speed shall be set at the reference speed per IWP-3100.
Inlet Pressure: For pumps taking suction from the Salt Service Water Complex basin, inlet pressure will be calculated (using appropriate density corrections) from a measured tank or basin level. Pumps taking suction from a tank (i.e. SLC Pumps) shall have the tank level recorded and monitored within an acceptance range. All other inlet pressure measurements will be taken using pressure instruments at or near the pump inlet.
O BOS-03-0201 2-2 Revision 1
Differential Pressure: Differential pressure i
() measurements will be calculated f rom inlet and discharge pressure measurements except for the SLC pumps which will use only discharge I
pressure for acceptance evaluations (see RP-7).
Plow Rate: Pump discharge flow rate shall be measured.
Vibration: Pump vibration velocity shall be measured at the designated monitoring point.
Bearing Temperature: Pump bearing temperature (s) shall not be measured (See RP-2).
2.1.5 Allowable Ranges of Test Quantities In accordance with the intent of ASME Code Interpreta-tion XI-1-79-19, owner specified ranges for the test quantities have been determined and are given in Table 2.1-2. Technical justifications are available in FSAR, Technical Specification, plant design documents and startup tests which show that the overall pump performance has not degraded from its intended function if the ranges in Table 2.1-2 are used. In some cases, the performance of a pump may be adequate to fulfill its safety function even though there may be some degradation, as compared to the reference value.
2.1.6 Bearing Lubricant As specified in Table IWP-3100-1, the pump bearing lubricant level, pressure, or flow will be observed during inservice testing.
O BOS-03-0201 2-3 Revision 1
g3 2.1.7 Instrument Accuracy G
A program for investigating instrument accuracies is being initiated. Any deficiencies discovered by this investigations will be resolved to the satisf action of j the commission no later than December 8, 1983 (or no l later than 12 months af ter the expiration of the initial 120 month period) as allowed by 10CFR50. 55a (g )( 4 ) (iv) .
2.1.8 Exempted Pumps Within Systems Classified for ISI The reactor recirculation jet pumps have been exempted from the IST program because Subsection IWP is l applicable to centrifugal and positive displacement ,
pumps only. These pumps have been exempted in accordance with IWP-1100.
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O BOS-03-0201 2-4 Revision 1
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' TABLE 2.1-1 KEY TO PUMP NAMES i
I Pump Name Pump Description RBCCW Reactor Building Closed Cooling l Water System Pumps RHR Residual Heat Removal System Pumps HPCI High Pressure Core Injection System Pump SLC Standby Liquid Control System Pumps i
SSW Salt Service Water System Pumps CS Core Spray System Pumps DOT Diesel Oil Transfer Pumps 4
l BOS-03-0201 2-5 Revision 1 w ,
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$.Y TABLE 2.1-2 mo WW oe OWNER SPECIFIED RANGES FOR TEST OUANTITIES ao M
F* o SYSTEM ACCEPTANCE ALERT REQUIRED ACTION PUMPS RANGE RANGE RANGE
===============================================================================
RBCCW P-202A TDH >_ 98 ft. Note 1 TDH < 98 ft.
P-202B P-202C O=0 Note 2 Note 2 P-202D P-202E V j:_.314 ips .314 ips < V _< .628 ips V> .628 ips P-202F M
1 .
- RHR P-203A Pd > 172 psig, Note 3 Note 1 Pd < 172 psig P-203B P-203C O=4800 gpm Note 2 Note 2 P-203D V ;< .314 ips .314 ips < V ;< .628 ips V> .628 ips HPCI P-205 Pd >_ 1195, Note 3 Note 1 Pd < 1195 psig O=4250 gpm Note 2 Note 2 N=4000 rpm Note 2 Note 2 V J:_ .314 ips .314 ips < V j:_.628 ips V> .628 ips T
O O O
<m TABLE 2.1-2 (Continued) rI mo OWNER SPECIFIED RANGES FOR TEST OUANTITIES rw O I DO SYSTEM g ACCEPTANCE ALERT REOUIRED ACTION Ho PUMPS RANGE RANGE
" RANGE
================================================================================
SLC P-207A Pd=1275 psig, Note 3 Note 2 Note 2 P-207B O ji 39 gpm Note 1 0 < 39 gpm V j:_.314 ips .314 ips < V j:_ .628 ips V> 628 ips SSW w
8 P-208A TDH J; 148 ft. Note 1 TDH < 148 ft.
P-208B P-208C 0=0 Note 2 Note 2 P-208D P-208E V<_.314 ips .314 ips < V _< 628 ips V> .628 ips CS P-215A Pd > 252 psig Note 1 Pd < 252 psig P-215B (P-215A, Note 3) (P-215A)
Pd jL 253 psig Note 2 Pd < 253 psig (P-215B, Note 3) (P-2158)
V <:_.314 ips .314 ips < V;< .628 'ips V > .628 ips
TABLE 2.1-2 (Continued)
OWNER SPECIFIED RANGES FOR TEST OUANTITIES SYMBOLS TDH - Total dynamic head (feet of water)
Pd - Discharge pressure (psig) of tested pump to be used in lieu of differential pressure. See Relief Request RP-7.
O - F low rate (gpm)
V - Vibration Velocity (inches per second, ips)
NOTE 1: The acceptance ranges for the lower limits are based on FSAR requirements. An alert range of .93 times the reference value as defined in Tab,le IWP-3100-2 for pressure or flow rate is not used because the resulting lower alert limits are less than the FSAR requirement.
- g. Values greater than 1.1 times the reference value will
\> be investigated on a per observation basis in accordance with IWP-3220 and IWP-3230(c)(d). Test quantities will be trended to identify at an early stage pump degradation. Trend criteria and the point for increased observation will be established by the owner and specified in the pump record.
NOTE 2: This test quantity, either flow rate or discharge pressure, is the independent variable and is set to a specified value. The dependent variable is measured and compared to the acceptance range. Speed is set to a specified value.
O BOS-03-0201 2-8 Revision 1
TABLE 2.1-2 (Continued)
OWNER SPECIFIED RANGES FOR TEST OUANTITIES NOTE 3: Discharge pressure will be used for the acceptance test. See Relief Request RP-7.
NOTE 4: The acceptance limit of 148 ft of TDH is the shut off head for the SSW pumps and it is based on the SSW pump performance curve given in BECO Purchase Order No.
41964.
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BOS-03-0201 2-9 Revision I
. O SECTION 2.2 RELIEF REQUESTS FOR INSERVICE PUMP TESTING PROGRAM O
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BOS-03-0201 2-10 Revision 1 c------ er-,- - -
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RELIEF REOUEST RP-1 O
PUMP: RBCCW Pumps P-202A, P-202B, P-202C, P-202D, P-202E, P-202F CLASS: 3 FUNCTION: Emergency Equipment Cooling TEST REQUIREMENT: Measure pump flow rate.
BASIS FOR RELIEP: Instrumentation is not installed to measure flow rate. Redesign of the system would be necessary to install flow instrumentation er to utilize portable flow instrumentation. There is no method available to control the flow rates of individual pumps. Shutoff head will provide a repeatable parameter for measuring pump performance. Pumps are not run at shutoff head for more than 60 seconds by procedure.
(]) .
ALTERNATE TESTING: Measure pump shutoff head and total system flow quarterly.
O BOS-03-0201 2-11 Revision 1
() RELIEF REOUEST RP-2 PUMP: Salt Service Water Pumps P-208A, P-2088, P-208C, P-208D, P-208E Standby Liquid Control Pumps P-207A, P-207B High Pressure Coolant Injection Pump P-205 Reactor Building Closed Cooling Water Pumps P-202A, P-202B, P-202C, P-202D, P-202E, P-202F Core Spray Pumps P-215A, P-215B Residual Heat Removal Pumps P-203A, P-203B, P-203C, P-203D CLASS: 2, 3
!Os N
FUNCTION: Emergency Equipment Cooling, Reactor Shutdown Without Control Rods, Emergency Core Cooling.
- TEST REOUIREMENT: Pump vibration and bearing temperature measurements are used to detect changes in the mechanical characteristics of a pump. Regular testng should detect developing problems, thus repairs can be initiated prior to a pump becoming inoperable (i.e.
unable to perform its function). ASME Section XI requires measurenent of vibration amplitude displacement in mils (thousandths of an inch) every three months and f bearing temperature once per year.
BASIS FOR RELIEF: Pilgrim 1 Generating Station proposes an alternate program which is believed to be more 73 comprehensive than that required by Section XI. The kJ proposed program is based on vibration readings measured in velocity units rather than vibration amplitude in BOS-03-0201 2-12 Revision 1
{} RELIEF REQUEST RP-2 (continued) mils displacement. This technique is an i ndus t ry-accepted method which is more sensitive to small changes that are indicative of developing mechanical problems and hence more meaningful. Velocity measurements detect not only high amplitude vibrations that indicate a major mechanical problem, but also the equally harmful low amplitude high f requency vibrations resulting from misalignment, imbalance, or bearing wear that usually go undetected by simple displacement measurements.
In addition, these readings go far beyond the capabilities of a bearing temperature monitoring program. A bearing will be seriously degraded prior to the detection of increased heat at the bearing housing. Quarterly vibration velocity readings will O)
(_ achieve a much higher probability of detecting developing problems than annual bearing temperature readings.
Finally, IWP-3500 requires "three successive readings taken at ten minute intervals that do not vary more than three percent." Meeting this requirement for pumps having no recirculation test loop would be very difficult because the system water temperature, and consequently the lubricant temperature, are expected to drift more than three percent during 20 minutes. Also, the temperature of the lubricating fluid will vary with ambient conditions and make meaningfull data trending impractical.
As described above, a program of bearing temperature trends and the evaluation of the results would in some cases be dif ficult to analyze. Improper interpretation of results could result in unnecessary pump BOS-03-0201 2-13 Revision 1
g- RELIEF REQUEST RP-2 (continued)
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maintenance. In addition, it is impractical to measure bearing temperatures on many of the pumps in the program. Some specific examples are as follows:
- 1. Salt Service Water Pumps: There is no installed instrumentation to measure bearing temperature.
Also, pump bearings are under water and, therefore, inaccessible.
- 2. Standby Liquid Control Pumps: There is no installed instrumentation to measure bearing temperature. Bearings are inaccessible for direct measurement due to the size of the bearing housing and the location of the bearing within the housing. Bearings are in an oil bath which is
(]) inaccessible.
- 3. HPCI Pump: No installed instrumentation to measure bearing temperature. Bearings are inaccesible for direct measurement due to the bearing housing and the location of the bearing within the housing.
Measurement of lube oil temperature is not practical because this lube oil supplies several bearings and control valves and would not necessarily reflect the pump bearing temperature.
- 4. Core Spray Pumps: There is no installed instrumentation to measure bearing temperature.
Bearings are inaccessible for direct measurement due to the size of the bearing housing and the location of the bearing within the housing.
- Bearings are process liquid lubricated.
! BOS-03-0201 2-14 Revision 1
RELIEF REOUEST RP-2 (continued)
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- 5. Residual Heat Removal Pumps: There is no installed instrumentation to measure bearing temperature.
Bearings are inaccessible for direct measurement due to the size of the bearing housing and the location of the hearing within the housing.
l Bearings are process liquid lubricated.
In conclusion, the foregoing reasons demonstrate that the proposed program of vibration measurements is a more practical method of testing which meets the intent of the requirements of the ASME Code.
ALTERNATE TESTING: Pump vibration measurements will be taken in vibration velocity (in/sec). The alert range begins at
.314 in/sec and the required action range begins at .628
() in/sec for all pumps. These values are recommended by IRD Mechanalysis Inc., and correspond to rough and very rough operating conditions, respectively. Similar velocity ranges can be obtained by the Hydraulic Institute Standards, 13th Edition, Figure 66.
Bearing temperature will not be measured.
O BOS-03-0201 2-15 Revision 1
RELIEF REOUEST RP-3 PUMP: Standby Liquid Control Pumps P-207A, P-2078 CLASS: 2 FUNCTION: Provide a method of shutting down the reactor without use of control rods TEST REOUIREMENT: Run pumps for five minutes under stable i
conditions. (Per IWP-3500)
BASIS FOR RELIEF: Standby Liquid Control Pump is tested by pumping demineralized water into a test tank. The tank capacity does not allow operation of the pump for longer than three minutes.
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() ALTERNATE TESTING: Pumps will be run for three minutes.
NOTE: Relief Request RP-2 applies to vibration measurements, and Re.. f Request RP-7 applies to differential pressure measurements for the Standby Liquid Control Pumps.
4 BOS-03-0201 2-16 Revision 1
, . . ~ . . - - _ _- _ _ _ . _ .
RELIEF REOUEST RP-4 O
PUMP: Salt Service Water Pump P-208A, P-208B, P-208C, P-208D, P-208E CLASS: 3 FUNCTION: Emergency Equipment Cooling TEST REOUIREMENT: Measure pump inlet pressure BASIS FOR RELIEF: No instrumentation is installed to measure
' pump inlet pressure.
ALTERNATE TESTING: Tide level will be used to calculate pump inlet pressure.
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BOS-03-0201 2-17 Revision 1
RELIEF REQUEST RP-5 PUMP: Salt Service Water Pumps P-208A, P-2088, P-208C P-208D, P-208E CLASS: 3 FUNCTION: Emergency Equipment Cooling TEST REOUIREMENT: Measure pump flow rate BASIS FOR RELIEF: Instrumentation is not installed to measure individual pump flow rate. Redesign of the system would be necessary to install flow instrumentation. There is no method available to control the flow rates of individual pumps. Shut off head will provide a repeatable parameter for measuring pump performance.
Pumps are not run at shutoff head for more than 60
() seconds by procedure.
ALTERNATE TESTING: Measure pump shutoff head and total system flow quarterly.
l 2
- BOS-03-0201- 2-18 Revision 1
ggg RELIEF REOUEST RP-6 PUMP: Salt Service Water Pumps P-208A, P-208B, P-208C, P-208D, P-208E CLASS: 3 FUNCTION: Emergency Equipment Cooling TEST REOUIREMENT: Measure pump vibration BASIS FOR RELIEF: The pump casing is physically located under water and, therefore, inaccessible.
ALTERNATE TESTING: Measure pump motor vibration at upper bearing per the Hydraulic Instit'ute Standards.
lh NOTE: Relief Request RP-2 applies to vibration measurements for the Salt Service Water Pumps.
O BOS-03-0201 2-19 Revision 1
RELIEF REQUEST RP-7 PUMP: Residual Heat Removal Pumps P-203A, P-203B, P-203C, P-203D High Pressure Coolant Injection Pump P-205 Core Spray Pumps P-215A, P-215B Standby Liquid Control Pumps P-207A, P-207B CLASS: 2 FUNCTION: Emergency Core Cooling, Reactor Shutdown Without Control Rods TEST REOUIREMENT: Differential pressure shall be an inservice test quantity.
O BASIS FOR RELIEF: Discharge pressure will be used when determining acceptable performance instead of differential pressure. Inlet pressure will be controled to ensure repeatability. Use of discharge pressure will simplify the pump acceptance analyses.
i ALTERNATE TESTING: Discharge pressure will be used instead of differential pressure when determining acceptable pump performance.
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i BOS-03-0201 2-20 Revision 1
RELIEF REQUEST RP-8 PUMP: Diesel Oil Transfer Pumps CLASS: NC FUNCTION: Diesel Oil Transfer from Main Storage Tank to Day Tank TEST REOUIREMENT: Inlet pressure, differential pressure, flow rate, vibration, bearing temperature shall be inservice test quantities.
BASIS FOR RELIEF: Discharge pressure or flow rate cannot be controlled to the point of insuring repeatability of the reference test quantity. Pump startup is initiated automatically when the oil level drops below the low level set point in the day tank during the diesel operability tests. When the high level set point is reached the pump shuts off.
Because the mass of the pump housing and impeller are small relative to the connecting pipes, it is the opinion of PNPS that vibration measurements would be highly susceptible to spurious vibrations and therefore meaningless for the prediction of pump degradation.
No instrumentation is installed to measure fluid temperature.
ALTERNATE TESTING: During the diesel operability tests, the refilling of the day tank from the low to high level I set-points will be verified in conjunction with procedure 8. 9.1. This operability test is performed on a monthly basis.
O f BOS-03-0201 2-21 Revision 1
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SECTION 2.3 INSERVICE PUMP TESTING PROGRAM O
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l BOS-03-0201 2-22 Revision 1
O O O gg TABLE 2.5-1 OO BOSTON EDISON COMPANY hfO INSERVICE TESTING fROGtAM
$g ISI CLASS 1,2,3 AND NC PtNPS O I PILGilM NUCLEAR POWER STATION
- 3 o M
wo g Page 1 IST Program Revision 001 12/08/82 INSERVICE TEST OUANTITIES Pump Pump ISI PalD inlet 01ff F1ow Bear Test
..$.:2:0......"=....21*!!.....t9....9??:.....St!!!.....tt:1!.....tt:11....."a!.....!!.%:.....I:2.....la!;.r:a!......"m.^.t.,...
P-202A RBCCW 3 M-215 F-3 NA Y Y Y:RP-1 Y:RP-2 N:RP-2 QUARTERLY P-2028 RBCCW 3 M-215 F-3 NA Y Y Y:RP-1 Y: RP-2 N:RP-2 OtMRTERLY P-202C RBCCW 3 M-215 G-3 NA Y Y Y:RP-l Y:RP-2 N:RP-2 OtRRTERLY P-202D RBCCW 3 M-235 G-5 NA Y Y Y:RP-1 Y:RP-2 N:RP-2 QlARTERLY P-202E R8CCW 3 M-215 G-5 NA Y Y Y:RP-1 Y:RP-2 N:RP-2 OtMRTERLY P-202F R8CCW 3 M-215 F-5 NA Y Y Y:RP-1 Y: RP-2 N:RP-2 N OtRRTERLY 1
M P-203A RHR 2 M-241 K-4 NA Y Y:RP-7 Y Y:RP-2 N:RP-2 OtRRTERLY P-2038 RHR 2 M-241 K-10 NA Y Y:RP-7 Y Y: RP-2 N:RP-2 QlMRTERLY P-203C RHR 2 M-241 J-4 NA Y Y:RP-7 Y Y:RP-2 N:RP-2 QUARTERLY P-2030 RHR 2 M-241 J-10 NA Y Y: RP-7 Y Y:RP-2 N:RP-2 QtMRTERLY P-205 WCl 2 M-244 F-9 Y Y Y Y Y:RP-2 N:RP-2 QUARTERLY P-207A SLC 2 M-249 E-5 NA Y RP-3 Y: RP-3 Y:RP-3 Y:RP-3 N:RP-2 QtRRTERLY P-2078 SLC 2 M-249 F-5 NA ):RP-3 Y:RP-3 Y:RP-3 Y:RP-3 N:RP-2 OtRRTERLY P-208A SSW 3 M-212 B-7 NA Y: RP-4 Y Y:RP-5 Y:RP-6 N:RP-2 QlMRTERLY P-2088 SSW 3 M-212 0-8 NA Y:RP-4 Y Y: RP-5 Y:RP-6 N:RP-2 QtMRTERLY P-208C SSW 3 M-212 8-7 NA Y: RP-4 Y Y: RP-5 Y:RP-6 N:RP-2 OtMRTERLY P-208D SSW 3 M-212 B-6 NA Y:RP-4 Y Y: RP-5 Y:RP-6 N:RP-2 QtRRTERLY P-208E SSW 3 M-212 B-5 NA Y:RP-4 Y Y:RP-5 Y:RP-6 N:RP-2 OtMRTERLY P-215A CS 2 M-242 F-7 NA Y Y:RP-7 Y Y:RP-2 N:RP-2 OtMRTERLY
, P-2158 CS 2 M-242 F-9 NA Y Y: RP-7 Y Y:RP-2 N:RP-2 OtMRI'ERLY P-141A DOT NC M-223 F-6 NA N:RP-8 N:RP-8 N:RP-8 N:RP-8 N:RP-8 MONTHLY P-141B DOT NC M-223 E-6 NA N:RP-8 N:RP-8 N:RP-8 N:RP-8 N:RP-8 M)NTHLY
3.0 INSERVICE TESTING PROGRAM FOR VALVES O
3.1 General Information This Inservice Testing Program for ISI Class 1, 2, 3 and NC Valves meets the requirements of Subsection IWV of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included in Section 3.2 3.1.1 Valve Program Table Description The tables in Section 3.3 list all ISI Class 1, 2, 3 and NC valves that have been assigned valve categories. The tables are arranged by P&ID number, which is given on each page of the tables. Certain valves have not yet been placed on a P&ID. These valves appear toward the end of the tables and bogus P&ID numbers have been assigned to them. The bogus P&ID numbers have the form X-001, X-002, etc.
Valves exempt per IWV-1200 are not listed. The following information is included for each valve:
VALVE NUMBER: The valve identification number.
P&ID COORDINATE: The coordinate location on the P&ID where the valve appears.
CLASS: The ISI Classification of the valve.
VALVE CATEGORY: The category (s ) assigned to the valve based on the definitions of IWV-2200.
Four (4) separate categories are defined in the Code:
(G~h BOS-03-0201 3-1 Revision 1
(~ CATEGORY A - valves for which seat leakage is v) limited to a specific maximum amount in the closed position for fulfillment of their safety function.
CATEGORY B - valves for which a specific amount of leakage in the closed position is not measured but which require stroke testing to verify their ability to fulfill their .
safety function.
CATEGORY C - valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves).
CATEGORY D - valves which are actuated by an energy source capable of only one operation, such as rupture disks or explosive-actuated valves.
({) VALVE SIZE: The nominal pipe size of the valve in inches.
VALVE TYPE: The valve body design as indicated by the following abbreviations:
ANGLE AN BALL BL BUTTERFLY BF CHECK CK GATE GA GLOBE GL NEEDLE ND
- PLUG PG RELIEF RL l
RUPTURE DIAPHRAGM RD SAFETY SV
,s SHEAR SH ks) STOP CHECK SC BOS-03-0201 3-2 Revision 1
SPRING CHECK SK
{
3-WAY 3WY EXPLOSIVE XP ACTUATOR TYPE: The type of valve actuator as indicated by the following abbreviations:
MOTOR OPERATOR MO AIR OPERATOR A SOLENOID OPERATOR S HYDRAULIC OPERATOR H EXPLOSIVE ACTUATOR XP MANUAL s M SELF ACTUATED SA SELF ACTUATED, TESTABLE SAT RUPTURE DISC RD O
- NORMAL POSITION: The normal position of the valve during plant operation. This is specified as follows:
O Normally Open C Normally Closed O/LO Normally Open/ Locked Open O/LC Normally Open/ Locked Closed O/KL Normally Open/ Key Locked O/FO Normally Open/ Fail Open O/FC Normally Open/ Fail Closed l
O/KO Normally Open/ Key Locked and Fail l
Open j C/LO Normally Closed / Locked Open l
C/LC Normally Closed / Locked Closed C/KL Normally Closed / Key Locked C/FO Normally Closed / Fail Open
~BOS-03-0201 3-3 Revision 1 l
C/FC Normally Closed / Fail Closed O C/KC Normally Closed / Key Locked and Fail Closed NE Normally Energized ND Normally De-energized TH Throttled S Valve position determined by other system parameters as in the case of check valves.
Valves with fail-safe positions are indicated as either FO-fail open or FC-fail closed.
TEST: The test (s) that will be performed to fulfill the requirements of Subsection IWV.
The test definitions and abbreviations used are identified in Table 3.1-1.
O TEST FREOUENCY: The frequency at which the above mentioned tests will be performed. Test frequencies are defined in Table 3.1-2.
MAXIMUM STROKE TIME: The limiting value of full stroke time, in secends, for power operated valves in Category A or B.
MAXIMUM LEAKAGE: The maximum leakage allowed during the specified leak test. The abbreviations for the units of measurement are:
C Standard cubic feet per minute F Degrees Fahrenheit O
1 BOS-03-0201 3-4 Revision 1
RELIEF REOUEST: The reference to a relief request in Section 3.2 for valve testing that is considered impractical to implement. Relief requests are also provided to justify valve testing at a frequency other than what is specified in Section XI.
REMARKS: Remarks in the IST Program are coded as Note 001, Note 002, etc. For a complete listing see the Valve IST Program Remarks.
3.1.2 Excess Flow Check Valves Excess flow check valves are tested once per cycle in accordance with Technical Specification Section 4.7.D.
A complete list of excess flow check valves is given in Procedure No. 8.M.3-2. The existing tests and ggg procedures described in Procedure No. 8.M.3-2 are considered adequate, therefore, these valves will not be subject to any ASME test requirements.
3.1.3 Valve Numbering A program is currently underway to revise P&ID's for identification of valves. Some valves listed in Table 3.3-1 may have revisions to numbering. The program will be revised as P&ID's are approved.
O BOS-03-0201 3-5 Revision 1 l
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$. 'f TABLE 3.1-1 l 0o INSERVICE VALVE TESTS
,g 8A i F' TEST TEST NAME TEST DESCRIPTION AT-1 Type C Leak Test Containment isolation valves will be seat leak tested in l accordance with Technical Specification requirements and Appendix J, 10CPR50.
AT-2 Vacuum Breaker Leak The suppression chamber-drywell vacuum breakers will be Test leak tested in accordance with PNPS Technical Specifi- l cation, Section 4.7.A.
AT-3 Safety and Relief Valve Safety and relief valve leakage is continuously Leak Test monitored by the safety and relief valve tailpipe temperature monitor. An alarm at 212*F indicates safety w or relief valve leakage. Refer to PNPS Technical 4 1 Specification, Section 4.6.D.
BT-O Full Stroke Exercise Exercise testing in the open direction, verified by Test to the Open stroke time measurement, will be performed to confirm i Position (IWV-3412 the full stroke capability of each valve. The stroke and 3413) direction tested and timed (open) is based on the direction the valve disk must travel to fulfill a safety function. The maximum allowable stroke time is specified by the owner.
BT-C Full Stroke Exercise Exercise testing in the close direction, verified by Test to the Close stroke time measurement, will be performed to confirm Position (IWV-3412 and the full stroke capability of each valve. The stroke 3413) direction tested and timed (close) is based on the direction the valve disk must travel to fulfill a safety function. The maximum allowable stroke time is specified by the owner. 1
O O O TABLE 3.1-1
<m INSERVICE VALVE TESTS (continued) uYo oY oo TEST TEST NAME TEST DESCRIPTION N
wo BT-OT Full Stroke Exercise Exercise testing in the open direction, verified by Test to the Open stroke time measurement, will be performed to confirm Position (IWV-3412 the full stroke capability of each valve. The stroke and 3413) direction tested and timed (open) is based on the direction the valve disk must travel to fulfill a safety function. The maximum allowable stroke time is specified by Technical Specifications.
BT-CT Full Stroke Exercise Exercise testing in the close direction, verified by Test to the Close stroke time measurement, will be performed to confirm Position (IWV-3412 and the full stroke capability of each valve. The stroke 3413) direction tested and timed (close) is based on the direction the valve disk must travel to fulfill a safety w function. The neximum allowable stroke time is 4 specified by Technical Specifications.
CT-O Check Valve Exercise Check valves will be exercised from the full closed {
Test to the Open to the full open position. Verification of safety l Position (IWV-3412) basis system flow through a check valve shall be !
adequate demonstration that the valve is full open. The stroke direction tested (open) is based on the direction the valve disk must travel to fulfill a safety function. J I'
CT-C Check Valve Exercise Check valves will be exercised from the full open to the Test to the Close full closed positions. The stroke direction tested Position (IWV-3412) (closed) is based on the direction the valve disk must travel to fulfill a safety function.
CT-SP Relief Valve Set Point Relief and safety valve set points will be Verification Test verified in accordance with IWV-3510.
(IWV-3510) i DTR Rupture Disk Test Rupture disks will be tested in accordance with {
(IWV-3620) manufacutrer's instructions, if applicable.
I TABLE 3.1-1
.<m INSERVICE VALVE TESTS (continued) ob oY ao TEST TEST NAME TEST DESCRIPTION N
F* o DTX Explosive Valve Test Explosive valves will be tested accordance with (IWV-3610) IWV-3610.
FST Fail-Safe Test All valves with fail-safe actuators will be tested to (IWV-3415) verify proper fail-safe operation upon loss of actuator power.
PAS Passive Valve Operational checks shall verify the position of passive Operational Check valves before operations are performed and af ter operations are completed. Passive valves are valves that are not required to change position to accomplish their safety function.
w PIT Position Indication All valves stroke timed with posi'. ion indicators will J
& Check (IWV-3300) be checked to verify that remote valve indicators i accurately reflect valve operation.
In the interest of ALARA, any individual valve for which a PIT would require expenditure of greater than or equal to one man-rem will not have a PIT performed. Valves falling under this exemption will be identified prior to test and justification for exemption will be recorded.
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' N TABI 3.1-2 l
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TEST EOUENCY (1) f5 TEST OPERATIONAL FREQUENCY
$.y FREQUENCY CONDITION OF TESTING no nY ao OP Power Operation At least once per 92 days N
Po CS Cold Shutdown See (2) Below e
RR Refueling Tests shall be performed during each reactor refueling but in no case I at intervals greater than two years SP See applicable See applicable relief request relief request SY No operational At least eve ry five years condition limitations per Article IWV-3511.
Applies to CT-SP test.
'w 2Y No operational Eve ry two years (see Article 1 condition limitations IWV-3300). Applies to PIT test.
NA No operational Tests are not required for Category condition limitations B, C, and D passive valves according to IWV-3700. Therefore, test l frequency is not applicable for these valves.
(1) Operational conditions are defined in Technical Specification, Section 2.0.
(2) Inservice valve testing not completed before startup may be completed during the I subsequent cold shutdown. In the case of frequent cold shutdowns, valve testing need not be performed more often than once every three months.
In the case of longer planned cold shutdowns, the testing need not be started within the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limitation. However, in these instances, all valve testing must be completed prior to start-up.
NOTE: It is expected that the required testing will normally be completed in 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> follow-ing cold shutdown. However, completion of all valve testing during cold shutdown is not required if plant operating conditions will not permit the testing of specific valves.
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SECTION 3.2 i
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, RELIEF REQUESTS FOR INSERVICE VALVE TESTING PROGRAM O
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s -- ,.-,,n., , ., , . , , , , ,. , . _ . . ,, . , , , , , , . , . , , , , , , _ , ,
RELIEF REOUEST RV-01
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SYSTEMS: ALL SYSTEMS PENETRATING PRIMARY CONTAINMENT VALVE: Valves subject to Appendix J, Type C leak testing (AT-1).
CATEGORY: A, A/C CLASS: 1, 2, 3, NC FUNCTION: The subject valves perform a containment isolation function as defined in 10CFR50, Appendix J.
TEST REOUIREMENT Corrective action is based on the requirements of IWV-3427.
BASIS FOR RELIEF: The Type C test leakages from all containment
() isolation valves are summed and added to the leakage from all Type B tests. This total leakage is compared to 0.6L p where L p is defined in Technical Specifications Section 4.7.A.b. Along with the above maximum allowable leak rate, no isolation valve leakage can exceed 0.05L to where L to = 0.75L p. The main steam isolation valve leakage cannot exceed 11.5 SCFH (0.192 SCFM).
Comparing the two leakage criteria, the 0.6L p criteria is approximately seven times more restrictive than the
.05L to maximum leakage criteria, when the 0.05L to leakage is summed for all isolation valves.
Given the conservatism of the 0.6L p criteria and the requirements of the 0.05L to criteria, no further ASME test requirements as described in IWV-3427 are necessary to ensure the leakage integrity of the containment G
(_/ isolation valves.
BOS-03-0201 3-11 Revision 1
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RELIEF REQUEST RV-01 (continued) i ALTERNATE TESTING: Containment isolation valves will be tested i in accordance with Technical Specification Section j 4.7.A.
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i BOS-03-0201- 3-12 Revision 1
I RELIEF REQUEST RV-02 O
SYSTEM + RBCCW VALVE: 4009A, 40098, 4002 CATEGORY: A, B CLASS: 3 FUNCTIONt These valves are RBCCW to drywell and the non-safety related component isolation valves.
TEST REOUIREMENT: Exercise valve for operability and measure i
stroke time every quarter.
BASIS FOR RELIEF: Cycling this valve would cause loss of cooling
(} water flow to the recirculation pump lube oil and seal water coolers and drywell coolers. This action could
. result in ' damage to the recirculation pumps. The recirculation pumps are required to be running during normal operation and cold shutdown. Partial stroking is precluded by valve design.
ALTERNATE TESTING: Exercise valve for opertb4 lity and measure stroke time at refueling.
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BOS-03-0201 3-13
, Revision 1 t
RELIEF REOUEST RV-03 SYSTEM: RBCCW VALVE: 40124 CATEGORY: A/C CLASS: 2 FUNCTION: This valve is the recirculation pump seal water outboard check valve.
TEST REOUIREMENTS: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Verification of valve closure can only be accomplished by leak testing, which is performed at refueling.
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ALTERNATE TESTING: Exercise valve for operability at refueling.
O BOS-03-0201 3-14 Revision 1
i RELIEF REQUEST RV-04 O
SYSTEM: COMPRESSED AIR i VALVE: AO-4356 CATEGORY: A CLASS: 2 FUNCTION: This valve is the nitrogen / instrument air to drywell isolation valve.
TEST REOUIREMENT: Exerc'lse valve for operability, observe proper operation of fail-safe mechanism, and measure stroke time every quarter.
(]) BASIS FOR RELIEF: If this valve fails closed during cycling, it would cause a loss of nitrogen / instrument air to the drywell. This would cause a reactor trip due to closure of the inboard MSIVs. Part stroking is precluded by valve design.
ALTERNATE TESTING: Exercise valve for operability, observe proper opeation of fail-safe mechanism, and measure stroke time during cold shutdown.
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BOS-03-0201 3-15. 1 Revision 1
6 RELIEF REQUEST RV-05 I
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SYSTEM: ALL SYSTEMS VALVE: Valves equipped to fail open or closed.
CATEGORY: A, B CLASS: 1, 2, 3, NC FUNCTION: Upon loss of electrical power, the valve must stroke to its fail-safe position.
TEST REOUIREMENT: Solenoid valves which control the air supply to air operated valves and direct solenoid operated valves must stroke to their fail-safe position upon interruption of their electrical supply.
BASIS FOR RELIEF: De-energizing the solenoid valve has the same effect as loss of electrical power. Therefore, stroking the valve from the control room to its fail-safe position constitutes a Fail-Safe Test (FST). No additional testing is necessary.
ALTERNATE TESTING: Normal stroking, to the fail-safe position of valves equipped to fail open or closed constitutes a Fail-Safe Test. No additional testing is necessary.
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0 BOS-03-0201 3-16 Revision 1
RELIEF REQUEST RV-06 SYSTEM: COMPRESSED AIR VALVE: 3"267 CATEGORY: A/C CLASS: 2 FUNCTION: This valve is the instrument air to drywell check valve.
TEST REOUIREMENT: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Verification of valve closure can only be accomplished by leak testing, which is performed at refueling.
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ALTERNATE TESTING: Exercise valve for operability at refueling.
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BOS-03-0201 3-17 Revision 1
RELIEF REQUEST RV-07 SYSTEM: CONTAINMENT ATMOSPHERE CONTROL VALVE: AO-5045A AO-5045G AO-5045B AO-5045H -
AO-5045C AO-5045D AO-5045J AO-5045E AO-5045K AO-5045F CATEGORY: A/C CLASS: NC FUNCTION: These valves are the pressure suppression chamber to drywell vacuum breaker valves which equalize the
(]) pressure between the two volumes when the suppression chamber pressure exceeds the drywell pressure.
TEST REOUIREMENT: Measure valve seat leakage and compare the measured leakage to a specific maximum leakage for each valve (IWV-3426).
BASIS FOR RELIEF: A specific maximum leakage per valve is not applicable to the vacuum breaker valve testing. A pressure decay test is performed on the pressure suppression chamber atmosphere in accordance with Technical Specification Section 4.7.A.4.b on a quarterly basis. This pressure decay test demonstrates the leak tightness of the vacuum breaker valves.
ALTERNATE TESTING: The leak tightness of the pressure suppression chamber to drywell vacuum breakers shall be
() demonstrated in accordance with Technical Specification Section 4.7.A.4.b.
BOS-03-0201 3-18 Revision 1
RELIEF REQUEST RV-08 SYSTEM: CONTAINMENT ATMCSPHERE CONTROL VALVE: CV-5065-10 through 5065-27, CV-5065-31 through 5065-38 CATEGORY: A CLASS: 2 FUNCTION: These valves are the 02 analyzer and H2 analyzer shutoff valves.
TEST REOUIREMENT: Measure and trend stroke time every quarter.
BASIS FOR RELIEF: The O2 analyzer valves are operated in two banks of nine valves each, valves CV-5065-10 through 16,
{]) CV-5065-26 and CV-5065-27 on one bank and valves CV-5065-17 through 25 on the other bank. The H2 analyzer valves are operated in two banks of 4 valves each, valves CV-5065-31, 32, 35 and 36 on one bank and valves CV-5065-33, 34, 37 and 38 on the other bank. Each bank is controlled by a single hand switch and operation of individual valves is not possible. The valves are all 1" air operated gate valves which are required to operate in less than five seconds by Technical Specifications. Stroke times of these vcives vary depending upon air pressure to the valve operators. The valves often stroke too fast (less than one second) to time accurately. Note that valves CV-5065-12 and CV-5065-19 have been removed.
ALTERNATE TESTING: Verify that all valves operate in less than five seconds. No stroke time trending will be
() performed.
BOS-03-0201 3-19 Revision 1
._-_ --. - - - , - ~ , _ . , . - _ _ _ . -
RELIEF REQUEST RV-09 O
SYSTEM: CONTAINMENT ATMOSPHERE CONTROL VALVE: 1"223, 1"223 CATEGORY: A/C CLASS: 2 FUNCTION: These valves serve as containment atmosphere control system containment isolation valves.
TEST REOUIREMENT: Exercise valve for operability quarterly.
BASIS FOR RELIEF: Verficiation of valve closure can only be accomplished by leak testing, which is performed at
(]) refueling.
ALTERNATE TESTING: Exercise valve for operability at refueling.
O BOS-03-0201 3-20 Revision 1
i RELIEF REQUEST RV-10 0 -
SYSTEM: CONTAINMENT ATMOSPHERE CONTROL VALVE: 1"276M3, 1"276M3 CATEGORY: C i
CLASS: NC FUNCTION: These valves prevent back flow from the air accumulators.
)
TEST REQUIREMENT: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Verification of valve closure can only be accomplished by disassembling a portion of the air
(}
supply system. Therefore, exercise tests can only be performed during reactor refueling.
ALTERNATE TESTING: Exercise valve for operability at refueling.
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BOS-03-0201 3-21 Revision 1
RELIEF REQUEST RV-ll SYSTEM: CONTAINMENT ATMOSPHERE CONTROL VALVE: .5"223 CATEGORY: A/C CLASS: NC FUNCTION: This valve serves as the isolation valve for the TIP purge system.
TEST REOUIREMENT: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Verification of valve closure can only be accomplished by leak testing, which is performed at
(~) refueling.
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ALTERNATE TESTING: Exercise valve for operability at refueling.
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! BOS-03-0201 3-22 Revision 1
RELIEF REQUEST RV-12 SYSTEM: RESIDUAL HEAT REMOVAL VALVE: 1001-47, 1001-50 CATEGORY: A CLASS: 1 FUNCTION: These valves are the RHR shutdown cooling suction valves.
TEST REOUIREMENT: Exercise valve for operability and measure stroke time every quarter.
BASIS FOR RELIBF: The valves are interlocked to prevent opening when reactor pressure is greater than 100 psig.
O ALTERNATE TESTING: Exercise valve for operability and measure stroke time during cold shutdown.
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BOS-03-0201 3-23
, Revision 1 L
RELIEF REQUEST RV-13 SYSTEM: RESIDUAL HEAT REMOVAL VALVE: 1001-68A, 1001-68B CATEGORY: C CLASS: 1 FUNCTION: These valves are the low pressure coolant injection check valves.
TEST REOUIREMENT: Exercise valve for operability quarterly.
BASIS FOR RELIEF: Exercising these valves to the open position can only be accomplished by verifying flow to the vessel as exhibited by the ability to maintain the proper vessel temperature. Forward flow through these valves is confirmed during shutdown cooling operations. During a given cold shutdown, only one cooling loop is used.
The other cooling loop is used during the subsequent cold shutdown.
ALTERNATE TESTING: Exercise each valve for operability during every other cold shutdown.
O BOS-03-0201 3-24 Revision 1
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SYSTEM: CORE SPRAY
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VALVE: 1400-9A, 1400-98 CATEGORY: C l CLASS: 1 FUNCTION: These valves are the core spray injection check valves.
TEST REOUIREMENT: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Exercising these valves to the open position.
can only be accomplished by manual manipulation. The termperature in the vicinity of these valves is in
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excess of 150'F for at least 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after achieveing cold shutdown; therefore, the area is not habitable.
Manual manipulation of these valves can only be accomplished during reactor refueling.
ALTERNATE TESTING: Exercise valve for operability at refueling.
O BOS-03-0201 3-25 Revision
RELIEF REQUEST RV-15 SYSTEM: HPCI VALVE: 2301-7 CATEGORY: C CLASS: 1 FUNCTION: This valve is the HPCI injection check valve.
TEST REOUIREMENT: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Testing this valve during normal operation would require injecting cold water into the reactor vessel using the HPCI system. This would result in both
{) a reactivity excursion and thermal shock to the feedwater nozzle and piping. The thermal shock condition can also exist during cold shutdown when the vessel metal temperature is above 212*F.
ALTERNATE TESTING: Exercise valve for operability during reactor refueling.
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BOS-03-0201 3-26 Revision 1
RELIEF REQUEST RV-16 i SYSTEM: HPCI 1 VALVE: HO-1, HO-2 CATEGORY: B CLASS: 2 FUNCTION: These valves are the HPCI turbine throttle valves.
TEST REOUIREMENT: Measure valve stroke time every quarter.
l BASIS FOR RELIEF: The purpose of these valves is to regulate steam to the HPCI Turbine. Operability of these valves are adequately demonstrated by turbine operation. Valve position is steam line pressure dependent and therefore
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will not repeatedly throttle to the same position.
During turbine operation, these valves move in response to control signals.
i ALTERNATE TESTING: Proper response of the valves will be '
verified by performing the HPCI System test.
O BOS-03-0201 3-27 Revision 1
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RELIEF REQUEST RV-17
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SYSTEMS: HPCI VALVE: 2301-34, 2301-45 CATEGORY: C CLASS: 2 FUNCTION: These valves prevent back flow in the HPCI turbine exhaust and exhaust drain lines.
4 TEST REOUIREMENT Exercise valve for operability every quarter.
BASIS FOR RELIEF: Verification of valve closure can only be accomplished by leak testing, which is performed at refueling.
(])
ALTERNATE TESTING: Exercise valve for operability at refueling.
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BOS-03-0201 3-28 Revision 1
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RELIEF REQUEST RV-18 SYSTEMS: RCIC VALVE: 1301-40, 1301-41, 1301-47 CATEGORY: C CLASS: NC FUNCTION: These valves prevent back flow in the RCIC turbine exhaust, vaccum pump discharge and minimum flow by-pass lines.
TEST REOUIREMENT: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Verification of valve closure can only be accomplished by leak testing, which is performed at
{
refueling.
ALTERNATE TESTING: Exercise valve for operability at refueling.
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BOS-03-0201 3-29 Revision 1
RELIEF REQUEST RV-19 SYSTEMS: STANDBY LIQUID CONTROL VALVE: 1101-15, 1101-16 CATEGORY: C, A/C CLASS: 1 FUNCTION: These valves are the SLC inlet check valves.
TEST REOUIREMENT: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Testing valves would require either injection of demineralized water by the Standby Liquid Control System or connection of a test pump to the test
{} connection. Either of these could render the Standby Liquid Control System inoperative. This system is required to be operative during normal operation and cold shutdown.
ALTERNATE TESTING: Exercise valve for operability at refueling.
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BOS-03-0201 3-30 Revision 1
4 i . RELIEF REOUEST RV-20 SYSTEM: CRD Hydraulic VALVE: 302-21A, 302-21B, 302-22 CATEGORY: B i CLASS: 2 j FUNCTION: These valves are the scram discharge volume
- isolation valves.
i TEST REOUIREMENT: Exercise valve for operability, observe proper operation of f ail-safe mechanism, and measure stroke time every quarter.
() BASIS FOR RELIEF: If the valves fail closed during cycling, water accumulates in the scram discharge volume. If more than 39 gallons accumulate, the reactor trips on High Level in the Scram Discharge Volume. Partial stroking is precluded by valve design.
ALTERNATE TESTING: Exercise valve for operability, observe proper operation of f ail-safe mechanism, and measure stroke time during cold shutdown.
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RELIEF REQUEST RV-21 SYSTEM: CRD Hydraulic VALVES: CV-126, CV-127 (typical of 145 each)
CATEGORY: B CLASS: 2 FUNCTION: These valves are the CRD scram inlet and exhaust valves.
TEST REOUIREMENT: Exercise valve for operability, observe proper operation of f ail-safe mechanism, and measure stroke time every quarter.
BASIS FOR RELIEF: These valves operate in coincidence to rapidly insert control rods. Valves will be tested by SCRAM timing control rod drives in accordance with Technical Specification Section 4.3. This requires testing of 50%
of the drives every 16 weeks and 100% every 32 weeks.
Additionally, 100% of the drives are tested each shutdown. Timing of the SCRAM function will be substituted for individual valve times.
ALTERNATE TESTING: SCRAM function timing will be substituted for i individual valve timing. No timing or trending will be performed under control of this program.
BOS-03-0201 3-32 Revision 1
RELIEF REQUEST RV-22 SYSTEM: CRD Hydraulic VALVES: 114, 115, 138 (typical of 145)
CATEGORY: C CLASS: 2 4
FUNCTION: These valves are CRD cooling water check valves.
TEST REOUIREMENT: Exercise for operability every quarter.
BASIS FOR RELIEP: Failure of these valves to seat in the reverse direction would result in the loss of insert drive water flow. They are therefore indirectly tested with each
, rod movement evolution. Valves will be tested in
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accordance with Technical Specification Section 4.3.
ALTERNATE TESTING: Tested per code by meeting Technical Specification Section 4.3. No testing will be performed under control of this program.
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O BOS-03-0201 3-33 Revision 1
RELIEF REQUEST RV-23 SYSTEM: NUCLEAR BOILER VALVES: 203-3A (ADS)* 203-4A 203-3B (ADS)* 203-4B 203-3C (ADS)*
203-3D (ADS)*
CATEGORY: A/C CLASS: 1 FUNCTIONS: The functions of the relief valves are: (1) open upon receipt of an auto depressurization signal to blowdown reactor (for the ADS valves only) and (2) act as a primary system relief valve which can be manually actuated from the control room. A primary system safety valve actuates on high system pressure. ,
TEST REOUIREMENT: Perform leak tests not less than once every two years.
BASIS FOR RELIEF: There are three major concerns associated with safety and relief valve seat leakage: (1) the sizing of the drywell cooling system is based on a limited amount of heat being rejected to the containment atmosphere by the main steam relief valve discharge lines; (2) the suppresion pool temperature will increase slowly if the relief valves leak; and (3) if a safety valve leaks, steam will be vented directly to the drywell atmosphere.
BOS-03-0201 3-34 Revision 1 i
RELIEF REQUEST RV-23 (continued)
Continuous seat leakage indication is provided on these valves by the safety and relief valve tailpipe temperature monitors and acoustic monitors. Excessive leakage is indicated by a control room alarm when the tailpipe temperature monitor exceeds 212*F. No special test to measure seat leakage is planned.
ALTERNATE TESTING: The tailpipe temperature indicator will be used to confirm that the safety and relief valves are leaktight.
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V BOS-03-0201 3-35 Revision 1
RELIEF REQUEST RV-24 SYSTEM: NUCLEAR BOILER VALVES: 203-3A 203-3B 203-3C 203-3D CATEGORY: A/C CLASS: 1 FUNCTION: The functions of the reactor relief valves are (1) open upon receipt of an auto depressurization signal to blowdown reactor (for the ADS valves only) and (2) act as a primary system relief valve which can be manually
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V actuated from the contol room.
, TEST REOUIREMENT: Exercise valves every quarter.
BASIS FOR RELIEF: Relief is requested from the Section XI required testing frequency of once every three months.
Exercising these valves during normal operation would cause primary system pressure spikes and reactor power fluctuations which could lead to a reactor scram. These valves will be exercised once per operating cycle as specified in Technical Specificati.on Section 4.5.E.
In addition, relief is requested from the stroke timing requirements of Section XI. It is impractical to measure stroke times for relief and solenoid valves since the stroke times are on the order of 100 ms. An abrupt change in the turbine bypass valve position will
() verify that the solenoid and relief valves have performed their function.
BOS-03-0201 3-36 Revision 1
. _ _ . _ _. . . . _ = _ _ _ . _ _ _ _ . ._ _ _ _ _ _ _ _ _ . - _ _ . _ . _ ..__ --_.. .._ _________ -
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RELIEF REQUEST RV-24 (continued)
ALTERNATE TESTING: These valves will be exercised at least once l
per operating cycle. The response of these valves will j be verified by observing an abrupt change in the turbine bypass valve po,sition. No stroke times will be f measured.
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l BOS-03-0201 3-37 l Revision 1
RELIEF REQUEST RV-25 O
SYSTEM: NUCLEAR BOILER VALVES: 220-46 220-47 CATEGORY: B CLASS: 1 FUNCTION: These valves are used to vent the reactor vessel head and main steam line "A" during startup.
TEST REQUIREMENT: Exercise and time valves for operability every quarter.
BASIS FOR RELIEF: Exercising one of these valves during normal operation leaves the other valve as the only barrier between the reactor vessel and the drywell sump. Any leakage through the closed valve could potentially pressurize the drywell which is an unnecessary rish for the sole purpose of testing a valve. Finally, operating procedures prohibit operation of these valves'during power operation.
ALTERNATE TESTING: These valves will be full stroke exercised during cold shutdown.,
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BOS-03-0201 3-38 .,
Revision 1 ~
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{} RELIEF REQUEST RV-26 SYSTEM: NUCLEAR BOILER VALVES: 6-58A 6-62A 6-58B 6-62B CATEGORY: A/C -
CLASS: 1 FUNCTION: These valves serve as the feedwater inlet check valves.
TEST REOUIREMENT: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Verification of valve closure can only be
() accomplished by leak testing, which is performed at refueling.
ALTERNATE TESTING: Exercise valve for operability at refueling.
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l BOS-03-0201 3-39 Revision 1 .. .-
i RELIEF REOUEST RV-27 O
SYSTEM: NUCLEAR BOILER VALVES: 1"273M3 (four ADS air accumulator check valves) 84A 85A 84B 85B 84C 85C 84D 85D CATEGORY: C CLASS: 2 FUNCTION: These valves provide isolation for the ADS, inboard MSIV and outboard MSIV air accumulators.
TEST REOUIREMENT: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Verification of valve closure can only be accomplished by disassembling a portion of the air supply system. Therefore, exercise tests can only be performed during reactor refueling.
ALTERNATE TESTING: Exercise valve for operability at refueling.
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I I
-BOS-03-0201 3-40
- Revision 1
- .-. . -, .. . .- .- . _- .-..-,~.
RELIEF REQUEST RV-28 SYSTEM: RECIRCULATION PUMP SEAL WATER VALVES: FO-13A FO-17A FO-13B FO-17B CATEGORY: A/C CLASS: 2 FUNCTION: These valves serve as the recirculation pump seal j water inboard and outboard check valves.
l TEST REOUIREMENT: Exercise valve for operability every quarter.
BASIS FOR RELIEF: Verification of valve closure can only be
() accomplished by leak testing, which is performed at refueling.
ALTERNATE TESTING: Exercise valve for operability at refueling.
O BOS-03-O201 3-41 Revision 1
RELIEF REQUEST RV-29 SYSTEM: TRANSVERSING INCORE PROBE l
VALVES: TIP-BALA TIP-BALC TIP-BALB TIP-BALD CATEGORY: A CLASS: NC FUNCTION: These valves provide containement isolation.
TEST REQUIREMENT: Exercise and time valves for operability every quarter.
BASIS FOR RELIEF: Per Operability Procedure 9.5, each TIP ball g valve is excercised during probe insertion tests every 1000 effective full power reactor hours. After each probe insertion test, the valves are confirmed closed.
These valves are never stroked without confirmation of valve closure, therefore, no timing requirements are necessary to show valve operability.
ALTERNATE TESTING: Verify valve closure coincident with LPRM calibration procedure 9.5. Stroke times will not be measured.
O BOS-03-0201 3-42 Revision 1
RELIEF REQUEST RV-30 SYSTEM: CONTAINMENT ATMOSPHERE CONTROL VALVE: CV-5046, 1"276 CATEGORY: A, A/C CLASS: NC FUNCTION: These valves provide containment isolation.
TEST REOUIREMENT: Exercise or exercise and time valves for operability every quarter.
BASIS FOR RELIEF: Verification of valve closure can only be accomplished by leak testing, which is performed at refueling. Also, there is no means to meausre valve
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closure time for CV-5046.
ALTERNATE TESTING: Exercise valves for operability at refueling. Valve closure time will not be measured for CV-5046.
O BOS-03-0201 3-43 Revision 1
i l
RELIEF REQUEST RV-31 SYSTEM: HPCI VALVE: 2301-39 CATEGORY: C CLASS: 2 FUNCTION: This valve prevents back flow in the HPCI pump suction line.
- TEST REOUIREMENT
- Exercise valve for operability every quarter.
BASIS FOR RELIEF: During the HPCI pump operability tests, water is taken from the condensate storage tank and not the
() suppression pool. Therefore, disc movement cannot be confirmed by flow verification every quarter.
i Different testing methods are now being investigated. Considering the dif ficulty in testing this valve, testing will be deferred to reactor refueling.
ALTERNATE TESTING: Exercise valves for operability at refueling.
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- BOS-03-0201 3-44 Revision 1 . . - - . - ,, - ..
l RELIEF REQUEST RV-32
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SYSTEM: SALT SERVICE WATER VALVE: 3915, 3925 CATEGORY: B CLASS: 2 FUNCTION: These valves isolate the service water system from the screen wash system when LOCA occurs.
TEST REOUIREMENT: Exercise and time valve for operability every quarter.
BASIS FOR RELIEF: When the screen wash pumps are turned off,
() these valves receive a signal to close. There are no position indicator lights to show when the valves have closed after the pumps are tripped, therefore, the stroke times cannot be determined. Proper valve closure is verified by observation of actuator stem position change af ter the screen wash pumps have tripped.
ALTERNATE TESTING: Exercise valves for operability every quarter. Valve closure times will not be measured.
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l BOS-03-0201 3-45 Revision 1
RELIEF REOUEST RV-33 SYSTEM: DIESEL OIL TRANSFER VALVE: AO-4521, AO-4522 CATEGORY: B CLASS: NC FUNCTION: These valves open automatically upon initiation of the diesel oil transfer pumps to allow oil to flow into the day tank.
TEST REOUIREMENT: Exercise and time valve for operability every quarter.
BASIS FOR RELIEF: These valves are not equipped with position
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indicators, therefore, stroke times cannot be obtained. Valve opening is indirectly verified by proper system operation.
ALTERNATE TESTING: Exercise valve for operability every quarter. Valve opening times will not be measured.
O BOS-03-0201 3-46 Revision 1
3 RELIEF REQUEST RV-34 SYSTEM: HPCI VALVE: AO-9313 CATEGORY: B CLASS: 2 FUNCTION: This valve must close so as to isolate the nitrogen rupply system from the turbine exhaust line.
TEST REOUIREMENT: Exercise and time valve for operability every quarter.
BASIS FOR RELIEF: Both AO-9312 and AO-9313 operate in tandem and provide isolation of the nitrogen supply system.
{ AO-9313 is in the IST program because the ISI boundary stops at this valve. There is no direct method fcr confirming that AO-9312 and AO-9313 close. If these valves do not close properly, primary containment pressure will slowly increase. An increase in containment pressure will be detected by the primary containment monitoring system. ALTERNATE TESTING: Valves will be exercised during the HPCI operability tests every quarter. No increase in primary containment pressure following the HPCI operability tests implies that these valves have closed properly. O - BOS-03-0201 3-47 Revision 1
I O SECTION 3.3 INSERVICE VALVE TESTING PROGRAM O - O BOS-03-0201 3-48 Revision 1
TABLE 3.3-1
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LIST OF SYSTEMS INCLUDED IN PNPS VALVE PROGRAM SYSTEM P&ID REV PAGE Salt Service Water M-212 E4 1 RBCCW M-215 E4 2 Compressed Air M-220 ES 4 Diesel Oil Transfer M-223 9 5 Containment Atmosphere Control M-227 E4 6 Post Accident Purge & Vent M-227 E4 14 Radwaste Collection M-232 E4 16 Analyzer M-239 10 17 Residual Heat Removal M-241 E2 19 {} Core Spray HPCI (Sheet 1) M-242 M-243 El 15 24 26 HPCI (Sheet 2) M-244 14 , 28 RCIC M-245 E2 29 Reactor Water Clean-Up M-247 E2 30 Standby Liquid Control M-249 E2 31 CRD Hydraulic M-250 E3 32 Nuclear Boiler M-252 El 33 Recirculation Pump Seal Water X-001 - 37 Transversing In-Core Probe X-002 - 38 Post Accident Sampling X-003 - 39 C-19 Return X-004 - 40 1 l l l BOS-03-0201 3-49 l Revision 1 ,
+ TABLE 3.3-2 [} VALVE IST PROGRAM REMARKS Note-001 Test with Pump Test.
\
Note-002 Rupture discs are non-testable and are therefore exempt per IWV-3620. Note-003 Stroke time is to be determined by owner. Note-004 This valve is typical of 145 valves. Note-005 ADS air accumulator check valve is typical of four valves. Note-006 Inboard MSIV air accumulator check valve is typical of four valves. (~} Note-007 Outboard MSIV air accumulator check valve is typical of four valves. Note-008 One SLC explosive valve is discharged every refueling. Both explosive valves are tested in the course of two refueling cycles. Note-009 TIP explosive valves are tested in accordance with IWV-3610. O BOS-03-0201 3-50 Revision'l
_ _ _ _ _ . . _ _ . . _ _ _ . . _ . __ ._ _ . ._ ._ ~ _ . . _ _ _ _ O O O TABLE 3.5-3 i INSERVICE TESTING PROGtAM BOSTON EDISON COMPANY , ISI CLASS 1,2,3 AND NC VALES P&lD: M-212 REVISION: E4 PILCRIM NtCLEAR POWER STATION Page 1 SYSTEP: Salt Service tentor IST Program Revision 001, 12/08/82 Valve PalD ISI Valve Valve Valve Actuator Normel Test Max Stroke Max Ro ll ef
..W:9tt......S?2t...c!!!!....S*!....S!!:....!!!
3800
......!!et.....te!!!!e2....!!!!....F:n......!!=......!!2*22..."nn!!......"?!!!...
G-8 3 8 18 BF MO O BT-O OP 003 PIT 2Y 3806 G-5 3 B 18 BF MD 0 BT-O OP 003 PIT 2Y 3808 C-6 3 B 12 BF MO O BT-C OP 005 BT-O OP 003 PIT 2Y 3813 C-6 3 8 12 BF PO O 9T-C OP 003 BT-O OP 003 PIT 2Y l 3915 D-4 3 B 6 BF A O/FC BT-C OP FST OP RV-32 ,1 PIT 2Y RV-0 5 i 3925 C-4 3 8 6 BF A O/FC BT-C OP t i FST OP RV-32 PIT 2Y RV-05 38100 C-8 3 C 12 CK SA S CT-C OP 001 CT-O OP 001 38103 C-7 3 C 12 CK SA S CT-C OP 001 CT-O OP 001 38105 C-6 3 C 12 CK SA S CT-C OP 001 CT-0 OP 001 38107 C-6 3 C 12 CK SA S CT-C OP 001 CT-0 OP 001 38109 C-5 3 C 12 CK SA S CT-C OP 001 CT-O OP 001 i 4
l jl)lllll l llllllllllll llll Y 2 . N 2 B . A / . oF M O C N P e0 g/ a2 8 1 ! 2 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 1 1 0 0 0 0 O , S 1 . I 0 . D 0 . E . _ n ! 1 2 2 2 N O o f ! 0 0 0 0 e nV i T s l V V V S R R R _ O B i v e lonR R R a. m a t r g o a x esC 9 P r M P. ! 6 2 0 T !. S . I . e . k . o . t r S !
=
x !. a . M t s nR e : R R 2 R Y R Y R2 RY R2 P Y O2 P Y O 2 P Y O2 P Y O2 P Y P7 P Y P Y P P T O 2 O2 O 2 O2 O O C.. S N . O MA L T EI ! 1 C T C
- T C- T 0 O O O O O C C C0 A A t TT - T - T - T - T - T - T - T - T - -
mV 0 T S I. A B P I TI B P TI BP TI BP T BP I T I BP T I BP T B P I TI B P T CPI T CPI T T C C R C . P N R . 3 E .
- G D W 2 3 N N O 2 le!
oE A P I 3 T s ! S 3, R r! O 0 O C C E A o! C C C C O O S L T B 2, LE N e A E 1 C t. T C L . I S N . - V S r . R AM E L l o . t r S a e O D N l Cm I L t u x M M O M 0 M 0 M D M 0 M D M 0 M O M O M A S S I c !. i P A . e . v s l e A A A A A A A F F A A K a x G G G G G G G B B G G C V e . v ! l ! 2 2 2 2 0 0 a! 6 8 8 1 1 1 1 1 1 8 8 8 V S.. e v!
! A 8 8 8 B 8 8 8 8 8 B C la S..
V 4 I
! C E S ! N 3 3 3 3 3 3 3 3 I ! 3 3 3 N
O S.. I . S D I l 2 4 6 4 7 7 2 2 4 4 2 3 3 V & 2 - - - - - - - - - - E P C D - - R S.. C G H C D E F E D G W C 5 C 1 8 2- R o s M : e t A 8 4 B 4 B A M v t 2 9 9 0 0 0 0 3 4 5 B 2
- E e0 0 0 6 5 0 1 1 6 8 8 8 8 DT law 4 1
0 0 0 0 0 0 0 0 0 0 0 0 l V 4 4
&W .
4 4 4 4 4 4 4 4 4 P S .
'-l:! i
l Y 2 , N 3 8 , A / , O P 8 3 M e0 3 1 1 1 1 1 1 1 1 1 1 O g / 0 0 0 0 0 0 0 0 0 0 C a2 g 0 0 0 0 0 0 0 0 0 0 P 1 N, N O , , S 1 , I 0 , D 0 , E , n 3 1 3 N O o f e g 3 00 T i g - - s i V V S O B i v e l R e e R, R R R m , a g r g 0 g x e 6 o Mag 9 r ; 2 P T 5, 0 S , I , e , k , o , t S 3 r
=
x 1, a , M , t s gP P P P A A P P P P P P R R e g O O T g OO N N OO O O OO R R S N , E O , M V I y CO C0 CO C0 CO 1 C A L T - - - - S S - - - -
@V A A T
nTCC T T T CC P A P A TT T T T T T T O S I, C C C C CC A C R C , 3 P N R , E ,
- G D W g 5 N N O l g I
A P e3 OE3 T L T B S E 3, RA 2, LE r r3 o3 N g g S S C C S S S S A E 1 C , T C U , I S N r , V S R A M o , E L l t ; S a g A A A A A N I C@ 1 L t u g S S M M S S S S A S I c I,, 1 P A e , v g l g K K F F K K K K a g C C B B C C C C V I, e , v 3 5 4 2 la3 V 8 8 1 1 8 8 8 6 S.. e . C v! /
- C C B B C C C A la S..
V 4 l ! C E S
- 3 3 3 5 3 3 3 N I !
O N S. I S D t I l 2 3 3 3 4 5 5 5 6 V a 2 - - - - - - - - E P 5 G G E E F G G C R W . C . 5 C 1 8 2- R o M
- E D T layS P S M
- e 2 5 v2 0 law 4 V
1 0 8 0 1 0 4 1 1 1 0 4 2 1 1 0 4 4 1 1 0 4 7 1 1 0 4 0 2 1 0 4 4 2 1 0 4
O O O TABLE 3.3-3 i lNSERVICE TCSTING PROG 4AM BOSTON EDl SON COMP 4NY ISI CLASS 1,2,3 AND NC VALES P&lD: M-220 REVISION: E5 PlLGilM NLELEAR POWER STATION Page 4 SYSTEM: Compressed Air IST Program Revision 001, 12/08/82 l Valve P&lD ISI Valve Valve Valve Actuator Normal Test Max Stroke Max Rollef
- ..!!".29tc... ...Seet. ..S!!!!. .. .S!!....S !!!... .!x es. .... .!xer.. ...Ce!!!! e2....!!!!.. ..C
- n......!!n.. ....L ed est. ..ats n!!.. ... ."21:2...
A0-4356 D-3 NC A 3 GA A O/FC AT-1 RR RV-01 0.296C BT-C CS R V-04 003 FST CS RV-05 PIT 2Y 3"267 D-3 NC AA: 3 CK SA S AT-1 RR RV-Ot 0.296C I CT-C RR RV-06 I N t 4 b 4 I
O O O T ABL E 3.3-3 INSERVICE TEST lNG PROGtAM B0STON EDl SON COMPANY ISI CLASS 1.2.3 ANO NC VAIXS P&lD: M-223 REVISION: PILGtlM NLCLEAR POWER STATION Page 5 SYSTEM: Olesel Transfer Oli IST Program Revision 001, 12/08/B2 Valve P&lD ISI Valve Valve Valve Actuator Norsel Test Mas Stroke Max Rollet Number Coor Cless Cat Size Tyoe Type Position Test Frea Time Leekage Request Notes AO-4 521 G-5 NC B 1.5 BL A0 C/FO BT-O OP NA RV-33 AO-4522 E-5 NC . B 1.5 BL A0 C/F0 BT-0 OP NA RV-33 I"223 F-5 NC C I CK SA C CT-C OP CT-0 OP la223 E-5 NC C 1 CK SA C CT-C OP CT-O OP FOOT-VAL-A F-7 NC C 2.5 CK SA C CT-C OP CT-O OP FOOT-VAL-B O-7 NC C 2.5 CK SA C CT-C OP CT-0 OP J w d i
O O O TABLE 3.5-3 INSERVICE TESTING PROGRAM BOSTON EDISON COMPANY ISI CLASS 1,2,3 AND NC VALES P&lD: M-227 REVISION: E3 PILGllN NUCLEAR POWER STATION Page 6 SYSTEN: Containment Atmosphere Control IST Program Revision 001, 12/08/82 r Valve P&lD ISI Valve Valve Valve Actuator Norse t Test Max Stroke Max Rollef
.."utzt......ceet.. 91t!!....S!!....S!!!....!rn......!!et.....Pgjjjg,,,,{gg],,,,{gg,,,,,,{jg,,,,,,(gggg,,,Rggg{,,,,,,Ng]pg,,,
X-212A A-7 NC AS 20 CK SA S AT-1 RR 0.296C RV-01 CT-C OP CT-O OP X-212B A-7 NC A/C 20 CK SA S AT-1 RR 0.296C RV-01 CT-C OP CT-O OP A0-5035A E-3 2 A I GL A ONC AT-1 RR 0.296C RV-01
- BT-CT OP 10 FST OP RV-05 PIT 2Y AO-50338 E-2 NC A 4 GA A C6C AT-1 RR 0.296C RV-01 1
- BT-CT OP 10 FST OP RV-05 PIT 2Y l
A0-5033C E-3 2 A I GL A ONC AT-1 RR 0.296C RV-01 RT-CT OP 10 FST OP RV-05 PIT 2Y A0-5035A D-3 2 A 20 BF A CNC AT-1 RR 0.296C RV-01 , BT-CT OP 15 i FST OP RV-05 PIT 2Y i
- A0-5035B D-2 NC A 20 BF A C#C AT-1 RR 0.296C RV-01 l BT-CT OP 15 I
FST OP RV-05 PIT 2Y , A0-5036A C-3 2 A 20 BF A CSC AT-1 RR 0.296C RV-01 1 ! BT-CT 0(* 15
- FST OP RV-05 PIT 2Y f
O O O TABLE 3.5-3 BOSTON EDISON COMPANY INSERVICE TESTING PROCRAM ISI CLASS 1,2,3 AND NC VALVES Page 7 P&lD: M-227 REVISION: E3 PIL(RIM NUCLEAR POWER STATION IST Program Revision 001, 12/08/B2 SYSTEM: Containment Atmosphere Control Norpel Test Max Stroke Max Rollef Valve P&lD ISI Valve Valve Valve Actuator
..hetc......S22r...c!!!!....St!....S!!!....!x22......!xt2.... 5e!!!!es....!!!!....5 23......I!n......Lt* tan...Rggg{,,,,,,Ng{gg,,,
AT-1 RR 0.296C RV-01 A0-50368 C-2 NC A 20 BF A C/FC BT-CT OP 15 FST OP RV-05 PIT 2Y AT-l RR 0.296C RV-01 A0-5040A B-7 2 A 20 BF A C/F0 BT-C OP 003 BT-0 OP 003 FST OP RV-05 PIT 2Y AT-1 RR 0.296C RV-01 A0-50408 -B-7 2 A 20 BF A C/F0 BT-C OP 003 BT-O OP 003 FST OP RV-0 5
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plt 2Y l i AT-1 RR 0.296C RV-01 A0-5041A D-7 NC A 2 GL A C/FC BT-CT OP 10 FST OP RV-05 PIT 2Y A C/FC AT-1 RR 0.296C RV-01 AO-50418 D-8 2 A 2 GL RT-CT OP 10 FST OP RV-05 PIT 2Y A C/FC AT-1 RR 0.296C RV-01 A0-5042A D-7 NC A 20 BF BT-CT OP 15 FST OP RV-05 PIT 2Y C/FC AT-1 RR 0.296C RV-01 A0-5042B D-7 2 A 20 BF A BT-CT OP 15 FST OP RV-05 PIT 2Y
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5-3 TABLE INSERVICE TESTING PROLTtAM BOSTON EDISON COMPANY ISI CLASS 1,2,3 AND NC VALVES PalD: M-227 REVISION: E3 PlLCRIM NUCLEAR POWER STATION Page 8 SYSTEM: Containment Atmosphere Control IST Procram Revision 001, 12/08/82 Valve PalD ISI Valve Valve Valve Actuator Norne t Test Max Stroke Max Ro ll ef .."".:Mr......S?2t...S!a!!....Sa!....SH ....!!er......!!e:.....te!!!!?a....!:21... 2:2......!'::......':a M st...Rggggg],,,,,,Ng]gg . A0-5043A E-6 NC A 2 GL A C/FC AT-1 RR RV-01 0.296C BT-CT OP 10 FST OP RV-05 PIT 2Y AO-50438 E-6 2 A 2 GL A C/FC AT-1 RR 0.296C RV-01 BT-CT OP 10 FST OP RV-05 PIT 2Y AO-5044A F-7 NC A 20 BF A C/FC AT-1 RR 0.296C RV-01 BT-CT OP 15 FST OP RV-05 PIT 2Y AO-50448 F-6 2 A 20 BF A C/FC AT-1 RR 0.296C RV-01 BT-CT OP 15 FST OP RV-05 PIT 2Y A0-5045A C-6 NC A/C 18 CK SAT C AT-2 RR NA RV-07 CT-C OP CT-0 OP PIT 2Y A0-50450 C-6 NC A/C 18 CK SAT C AT-2 RR NA RV-07 CT-C OP CT-0 OP PIT 2Y A0-5045C C-6 NC A/C 18 CK SAT C AT-2 RR NA RV-07 CT-C OP CT-0 OP PIT 2Y
O O TABLE 3.5-3 O INSERVICE TEST. LNG PROGRAM BOSTON EDISON COMPANY ISI CLASS 1,2,3 AND NC VALES P&lD: M-227 REVISION: E3 PILCRIM NtELEAR F0WER STATION Page 9 SYSTEM: Containment Atmosphere Control IST Program Revision 001, 12/08/82 Valve P&lD ISI Valve Valve Valve Actuator Norne l Test Max Stroke Max Rollef
..W:9tc..... 922 .. 9!*!!....S*!....S!!!....!122......!%22.....te!!!!20....!!!!... 5 n......!!n......!!*h*n..."n=51......"212$...
, A0-%4 2 C-6 NC Ar 18 CK SAT C AT-2 RR NA RV-07 i CT-C OP CT-O OP PIT 2Y A0-%45E C-6 tC AM: 18 CK SAT C AT-2 RR NA RV-07 i i CT-C OP CT-0 OP PIT 2Y A0-%45F C-6 NC A/C 18 CK SAT C AT-2 RR NA RV-07 CT-C OP CT-0 OP PIT 2Y A0-%4 % C-6 NC A/C 18 CK SAT C AT-2 RR NA RV-07 CT-C OP CT-O OP PIT 2Y A0-%45H C-6 NC A/C 18 CK SAT C AT-2 RR NA RV-07 CT-C OP CT-0 OP PIT 2Y A0-%45J C-6 NC A/C 18 CK SAT C AT-2 RR NA RV-07 CT-C OP CT-0 OP PIT 2Y .I
,4 %
u/ TABLE 5.3-3 lNSERVICE TESTING PR0mAM BOSTON EDISON COMPANY ISI CLASS 1,2,3 AND NC VALVES P&lD: M-227 REVISION: E3 PILmlM NtELEAR POWER STATION Page 10 SYSTEM: Contalnnent Atmosphere Control IST Frogram Revision 001, 12/08/82 Valve PalD ISI Valve Valve Valve Actuator Norne l Test Max Stroke Max Relief .."etzt......S22 ...S!a$!....Sa!....S!!:.... Iter......!re!.....te5!!!22....!!!!....ttn......!!=......'tabas!..."un!!......"21:2... A0-504'M C-6 PC A/C 18 CK SAT C AT-2 RR NA RV-07 CT-C OP CT-O OP PIT 2Y CV-5046 C-6 PC A 1 GL A C AT-1 RR 0.296C RV-01 BT-C RR NA RV-30 CV-5065-10 B-3 PC A 1 GA A O/FC AT-1 RR 0.296C RV-01 BT-C T OP 5 RV-08 FS1 OP RV-05 PIT 2Y CV-5065-11 B-3 NC A 1 GA A O/FC AT-1 RR 0.296C RV-01 BT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-13 B-3 to A 1 GA A O/FC AT-1 RR 0.296C RV-01 BT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-14 B-3 NC A 1 GA A O/FC AT-1 RR 0.296C RV-01 BT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-15 B-3 tC A 1 GA A O/FC AT-1 RR 0.29fC RV-01 BT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y
b' TABLE 3.3-3 lNSERVICE TESTING PR0fRAM BOSTON EDlSON COMPANY ISI CLASS 1,2,3 AND NC VALVES P&lD: M-227 REVISION: E3 PILGtlM NUCLEAR POWER STATION Page 11 SYSTEM: Containment Atmosphere Control IST Program Revision 001, 12/08/82 f Valve P&lD ISI Valve Valve Valve Actuator Normal Test Max Stroke Max Relief
. .$2tc. ... ..S22c...S!* !!.. . .S* !. . ..S !!!. ...!r e r.... . .!r e!. .. . .Pgs j {j gn,,,,{ gs {,,,,{ { gg,,,,,,{ jg,,,,,,L ggggg,,,gg gs {,,,,,,${ gg,, ,
CV-5065-16 B-3 NC A 1 GA A O/FC AT-1 RR 0.296C RY-01 BT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-17 C-3 2 A 1 GA A O/FC AT-1 RR 0.296C RV-01 BT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-18 C-3 2 A 1 GA A O/FC AT-1 RR 0.296C RV-01 BT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-20 C-3 2 A I GA A O/FC AT-1 RR 0.2960 RV-01 BT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-21 C-3 2 A 1 GA A O/FC AT-1 RR 0.296C RV-01 BT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-22 C-3 2 A 1 GA A O/FC AT-1 RR 0.296C RV-01 BT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y
/- /m) 70 l h
TABLE 3.5-3 V l l lNSERVICE TESTING PRO @AM BOSTON EDISON COMPANY j ISI CLASS 1,2,3 AND NC VALES PalD: M-227 REVISION: E3 PILmlM NUCLEAR POWER STATION Page 12 SYSTEM: Containment Atmosphere Control IST Program Revision 001, 12/08/82 l Valve P&lD ISI Valve Valve Valve Actuator Norml Test Max Stroke Max Relief I ..N.u.m.. be..r. . . . . .C.o.o.
. r. ..C. .l a.s.s . . . . .C.a. t. . . . .S. .i z.e. . .. .T.% o.e.. . . ... .T.l pe. . . ..
...P. os .i..t.i o. n.... .T. e.s.t. . . .F. r eq. . . . . . . . .T. .i m.e.. . . . . . .L. e.ak.a.
...o.e. . . .R.e.q ue.s.t. . . . . .N.o. .t .e.s. . .
CV-5065-23 C-3 2 A 1 GA A ONC AT-1 RR 0.296C RV-01 BT-CT OP 5 R V-08 l FST OP RV-05 PIT 2Y CV-5065-24 C-4 2 A 1 GA A ONC AT-1 RR 0.296C RV-01 BT-CT OP 5 RV-08 j FST OP RV-05 i PIT 2Y CV-5065-25 B-5 2 A 1 GA A 05C AT-1 RR 0.296C RV-01 RT-CT OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-26 8-4 NC A 1 GA A ONC AT-1 RR 0.296C RV-01 BT-CT RV-08 OP 5 FST OP RV-05 PIT 2Y CV- 506 5-27 B-5 NC A 1 GA A OEC AT-1 RR 0.296C RV-01 BT-CT OP 5 R V-03 FST OP RV-05 PIT 2Y 1"223 E-3 2 A/C 1 CK SA S AT-1 RR 0.296C RV-01 CT-C RR R V-09 1"223 E-3 2 A/C 1 CK SA S AT-1 RR 0.296C RV-01 CT-C RR R V-09
. _ _ _ _ _ _ _ _ _ ~
O TABLE O 3-3 O INSERVICE TESTING PRO @AM BOSTON EDISON COMPANY ISI Cl. ASS 1,2,3 AND NC VALVES P&lD: M-227 REVISION: E3 PlL@lM NTLEAR POWER STATION Page 13 SYSTEM: Containment Atmosphere Control IST Program Revision 001, 12/08/82 Valve PalD ISI Valve Valve Valve Actuator Normal Test Max Stroke Max Rollef
..N.um..be.r..... e . .C.o.o.r.
. ..C. .l a..s
. s. .. .C.a.
. t....S..i z.e.....T.l. pe.... ...T.% .pe.. .. . .P.o..s.i. .t.i o.n......T.es.t. ...F.r.9. ... . . .T..i.m.e.... ..L..e.ak.aP....R.9.
. .u.e.s.t. . . . ...N. o.t.e.s. . .
1"276 C-6 NC A/C 1 CK SA S AT-1 RR 0.2960 RV-01 CT-C RR RV-30 I"276M3 B-6 NC C 1 CK SA S CT-C RR RV-10 I"276M3 B-7 NC C 1 CK SA S CT-C RR RV-10 5"223 C-2 NC AA: 5 CK SA S AT-1 RR 0.296C RV-01 CT-C RR RV-1 I t 1 4 1 ? e
r% O
'N ']
TARLE 3-3 N]
~
INSERVICE TESTING PR0mAM BOSTON EDISON COMPANY 151 CLASS I,2,3 AND NC VALVES PalD: M-227 REVISION: E4 PILmlM NtELEAR POWER STATION Page 14 SYSTEM: Post Accident Purge & Vent IST Program Revision 001, 12/08/82 Valve PalD ISI Valve Valve Valve Actuator Norml Test Max Stroke Max Relief ..!!d!c......S?? ...S!a5$....Sa!....S!!!....!rer...... Ires.....Pggj{jpg,,,,{gs{,,,,{gg,,,,,,{jgg,,,,,,Lgagagg,,,Rggs{,,,,,,{jg{g,,, SV-5081 A H-8 tC A 1 GL SO C/LC AT-1 RR 0.296C RV-01 SV- 50818 H-8 FC A 1 GL SO C/LC AT-1 RR 0.296C RV-01 SV- 5082A H-7 FC A 1 GL SO C/LC AT-1 RR 0.296C RV-01 SV-50828 H-7 tC A 1 GL SO C/LC AT-1 RR 0.296C RV-01 SV-5083A C-8 NC A 1 GL SO C/LC AT-1 RR 0.296C RV-01 SV-50838 C-8 NC A 1 GL SO C/LC AT-1 RR 0.296C RV-01 SV-5084A C-8 to A 1 GL SO C/LC AT-1 RR 0.29F RV-01 SV-50848 C-8 to A 1 GL SO C/tc AT-1 RR 0.2960 RV-01 SV-5085A F-4 NC A 1 GL SO C/LC AT-1 RR RV-01 0.296C SV-508S3 F-4 PC A 1 GL SO C/LC AT-1 RR RV-01 0.296C SV-5086A F-4 NC A 1 GL SO C/LC AT-1 RR 0.296C RV-01 SV- 50860 F-4 FC A 1 GL SO C/LC AT-1 RR RV-01 0.296C
TA8LE 'J.3-3 lNSERVICE TESTlHG PRO @AM BOSTON EDISON COMPANY 151 CLASS 1,2,3 AND NC VALES PalD: M-227 REVISION: E4 PILmlM NUCLEAR POWER STATION Page 15 SYSTEM: Post Accident Purge E Vent . IST Program Revision 001, 12/08/82 Valve P&lD If. ~1alve Valve Valve Actuator Normal Test Max Stroke Max Rollef
..httsc......htc.. 91222... 91... 5152....!r82......!r22.....!e:21222....It!!....Es ts......!!n......!!!!!st..."ts n!!......"2122.. .
SV-5087A F-4 NC A 1 GL SO C/LC AT-1 RR 0.296C RV-01 4 SV-5087B F-4 NC A 1 GL SO C/tc AT-1 RR 0.296C RV-01 SV-5088A F-4 NC A 1 GL SO C/LC AT-1 RR 0.296C RV-01 SV-50888 F-4 NC A 1 GL SO C/LC AT-1 RR 0.296C RY-01 4
. _ t .
INSERVICE TESTING FROGRAM BOSTON EDISON C3PANY ISI CLASS 1,2,3 AND NC VALVES P&lD: M-232 REVISION: E4 PILGalM NtELEAR POWER STATION Page 16 SYSTEM: Radweste Collection IST Program Revision 001, 12/08/82 O. l Valvo P&ID ISI Valve Valve Valve Actuator Nornut T4,s t u.w Stroke ( Max Relief J
. . r,
..N.u.m.be.r..... .. .C.o.o.r....C..l a.s . s. ....C.a.t...
. .S..i z.e.....T.%. pe.......T.l.pe. .....P.os.i .. .t.i on...
.. .T.e.s.t....F.r.eo.
. .... ...T..i m..i......- L.e..e'.<a.c.e... R.ec. . .. ue.s.t.. ....M. r.e. 5 *2..
A0-7011A G-6 NC A 2 PG A C/FC AT-1 RR , J.2')(c RV-01 - ,
, 20 j ' ~
~
BT-CT' OP' *
, y l , , - .
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/- 0 5
- 4. FST OP 'f j { t 7'*
- 1 1 PlT 2Y '
4 A0 101 1 G, -6, , (C ( A 2 e, PG A C/FC AT-1 RR - +0,2960 RV-01 i
'( -, " **
g BT-CT OP 2G- < j /
,,, - y FST '
OP '
/;
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,- , p;y, gy . j
- , t .
)S-7017A D-6 to A 2 PG A J C/FD \ AT-1 RR 0.29fc (, RY-01 Y /
1
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/
BT-CT FST OP OP 20 i / RV-05 - e I
., ? - < {' PIT 2Y / <
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/
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, , A0-70178 D-6 NC A 2
- PG A C/FC AT-1 RR / ,
C,216C 'Ry-N \ *j' - [ g
) ,'* '
BT-CT ~ ' OP 20' ,
' t g
fJ . t t
< j UST OP *. Rv-05
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us-TAedE 3-3 f - lNSERvlCE TESTING PR0mAM BOSTON EDISON COMPANY ISI ddSS f,2,3 AND NC VALVES PalD: M-239 REVIS10Hi,10- PILm lM NtELEAR POWER STATION Page 17 SYSTEh: Ana lyzer IST Program Revision 001, 12/08/82 Valve P&lD ISI Valve Valve Valve Actuator Norma l Test Max Stroke Max Rollef
..W:ht..... 922;...S!a!!....Sa!....S!! ....!re!......Irer.....Pggj{jpn,,,,{gg{,,,,{gg,,,,,,Jjgg,,,,,,Lgaggg,,,Rggg{,,,,,,Ng{gg ,
CV-5065-31 0-5 NC A 1 GL A C/LC AT-1 RR 0.296C RV-01 BT-C OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-32 A-5 NC A 1 GL A C/LC AT-1 RR 0.296C RV-Of BT-C OP 5 RV-08 FST OP RV-05 plt 2Y CV-5065-33 B-6 NC A 1 GL A C/LC AT-1 RR 0.296C RV-01 BT-C OP 5 RV-08 FST OP RV-05 PIT 2Y A-6 CV-5065-34 NC A 1 GL A C/LC AT-1 RR 0.296C RV-01 BT-C OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-35 B-5 NC A 1 GL A C/LC AT-1 RR 0.296C RV-01 BT-C OP 5 RV-08 FST OP RV-05 PIT 2Y CV-5065-36 A-5 PC A 1 GL A C/LC AT-1 RR 0.296C RV-01 BT-C OP 5 RV-08 FST OP RV-05 plt 2Y A
, (~q
\' -') N..)
TABLE 3-3 INSERVICE TEST 1NG PR0rnAM B0STON EDlSON COMPANY ISI t;t. ASS 1,2,3 AND NC VALVES P&lD: M-239 REVISION: 10 PILGll4 NLELEAR POWER STATION Page 18 SYSTEM: Ana lyzer IST Procram Revision 001,12 V8/82 Valve PalD ISI Valve Valve Valve Actuator Nornel Test Max Stroke Max Rollet . .N.u.m.be..r..
. ....C.o.
.. or...C..l
. a. s.s....C. .: .t. ..
. .S. .i ze.. ...T.%.pn....
. . .. . .T.y p. e. . ..
.. .P.o.s .i .t.i on. . . .T.e..s.t....F.r.9. . .. . ...
..T. ..i m.e... .....
.L ea.k a.oe....R.e.q . u.e.s.t. . .. . .N.o..t CV-5065-37 B-6 NC A I GL A C/l.C AT-1 RR d.296C RV-01 BT-C OP 5 RV-08 FST OP RV-05 Pli 2Y CV-5065-38 A-6 NC A I GL A C/LC AT-1 RR 0.296C RV-01 BT-C OP 5 RV-08 FST OP RV-05 PIT 7Y
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . _ _ _ _ . _ . _ . . _ _ _ . _ _ _ . _ . _ _ _ _ . . _ . ~ _ . . . . , . . _ _ _ . . _ _ _ _ . . _ _ . . _ _ _ ._ _. .. O TAELE 3.5-3 O O lNSERVICE TESTING PR0mAM BOSTON EDISON COMPANY ISI CLASS 1,2,3 ANO NC VALES P&lD: M-241 REVISION: E2 PILMIM HlCLEAR POWER STATION Page 19 , SYSTEM: Residual Heat Removal IST Proaram Revision 001, 12/08/B2 ! i Valve P&l0 ISI Valve Valve Valve Actuator Normal Test Max Stroke Max Rollef
..?. 2 ...... cut...Et$5... 2!... 51u....!rn......Izu.....tn'!!n....!n!... 5 n......!!n......'t.*.tn...an=5!......t'e!n...
- 1001-2A K-4 2 C 2 CK SA S CT-C CP 001 CT-O OP 001 1001-2B K-10 2 C 2 CK SA S CT-C OP 001 i
CT-O OP 001 1001-2C J-4 2 C 2 CK SA S CT-C OP 001 1 3 CT-O OP 001 1001-2D K-10 2 C 2 CK SA S CT-C OP 001 , CT-0 OP 001 ' i 1001-7A K-6 2 8 18 GA MD 0/KL BT-CT OP 90 $ BT-O OP 90 j' PIT 2Y t j 1001-78 K-7 2 B 18 GA MG 0/KL BT-CT OP 90 BT-O OP 90 PIT 2Y , 1001 PC K-6 2 8 18 GA 2 O/KL BT-CT OP 90 l BT-O OP 90 PIT 2Y 1001-7D K-7 2 B 18 GA m O/KL BT-Ci OP 90 ' , BT-O OP 90 PIT 2Y 1001-16A J-3 2 B 18 GA m C BT-C OP 99 y RT-O OP 99 i PIT 2Y ' I 1001-168 K-Il 2 8 18 GA 90 C BT-C OP 99
- BT-0 OP 99 PIT 2Y
[
TABLE . 3 INSERVICE TEST lNG PR0mAM B0$ TON EDISON COMPANY 150 CLASS 1,2,5 AND NC VALES PalD: M-241 REVISION: E2 PIL@lM NUCLEAR POWER STATION Page 20 SYSTEM: Residual Hoot Removal IST Program Revision 001, 12/08Ml2 , t t. Valve P&lD ISI Valve Valve Valve Actuator Normal Test Max Stroke Max Rollet
..klhr......cert...S!!!!....S!!... 51!!....!!!!......!!!!.....?e5'I'e2....!n!....Crn......!!=......!:l$222..."un'!......'.'?!n...
1001- 8A H-4 2 B 3 GA MO O BT-C OP 20 BT-0 OP 20 PIT 2Y 1001-188 H-10 2 B 3 GA MO O BT-C OP 20 i BT-O OP 20 4 PIT 2Y 1001 19 H-4 2 B 18 GA MO O/KL PAS NA 1001-21 F-11 2 B 4 GA M0 C BT-C OP 20 l PIT 2Y 1001-22A C-2 2 C 1 RL SA C CT-SP 5Y 1001-22B C-12 2 C 1 RL SA C CT-SP 5Y 1001-23A B-5 2 A 10 GA MD C AT-1 RR 0.296C RV-01 I BT-C OP 14 l PIT 2Y I 1001-238 B-9 2 A 10 GA 60 C AT-1 RR 0.296C RV-01 ! BT-C OP 14 j PIT 2Y 100l-26A B-6 NC A 10 GA MD C AT-1 RR 0.296C RV-01 l [ BT-C OP 14 PIT 2Y 1001-268 B-8 IC A 10 GA DO C AT-1 RR 0.296C RV-01 - BT-C OP 14 PIT 2Y 1001-28A C-5 2 A 18 GL MD C AT-1 RR 0.296C RV-01 ! BT-C OP 30 BT-0 OP 30 PIT 2Y I l i
TABLE 3-3 INSERVICE TEST lNG PROMAM B0STON EDlSON COMPANY ISI CLASS 1,2,3 AND NC VALES P&lD: M-241 REVISION: E2 PlL@lM NtCLEAR POWER STATION Page 21 SYSTEM: Residual Heat Removal IST Program Revision 001, 12/08/82 Valve P&lD ISI Valve Valve Valve Actuator Norsel Test Max Stroke Max Rollet
...herc......C25...C !!' t. .. .St !....S ! n.. ..Ir n.... ..It t!. ....tn!!! n....In !....[ tn .. . . ..!!=. . ....!!!$25..." n =$ !. . ....W15. . .
1001-288 D-9 2 A 18 GL MD C AT-1 RR 0.296C RV-01 BT-C OP 30 BT-O OP 30 PIT 2Y 1001-29A D-4 1 A 18 GL MD 0 AT-1 RR 0.296C RV-01 , BT-C OP 003 I , BT-O OP 003 i PIT 2Y [ 1001-298 D-9 I A 18 GL MO O AT-1 RR 0.296C RV-01 BT-C OP 003 BT-0 OP 003 PIT 2Y r 1001-32 F-10 2 B 4 GA MD C BT-C OP 20 I j PIT 2Y l 1001-34A C-3 2 A 12 GA MD C AT-1 RR 0.296C RV-01 i BT-C OP 30 BT-O OP 30 Pli 2Y , 1001-348 C-Il 2 A 12 GA MD C AT-1 RR 0.296C RV-01 BT-C OP 30 BT-0 OP 30 !
\
PIT 2Y l
- 1001-36A D-3 2 B 12 GL MD C BT-C OP 30 j BT-O OP 30 l j PIT 2Y 1
1001-368 D-Il 2 B 12 GL M0 C BT-C OP 30 BT-O OP 30 PIT 2Y ! 4 f f 4 4
O O TABLE $3-3 O INSERVICE TESTING PR0mAM BOSTON EDISON COMPANY ISI CLASS 1,2,3 AND NC VALES P&lD: M-241 REVISION: E2 PIL@lM NUCLEAR POWER STATION Page 22 SYSTEM: Residual Heat Removal IST Program Revision 001, 12/08/82 Valve P&lD ISI Valve Valve Valve Actuator Hornel Test Max Stroke Max Roll ef
..W2:c..... 92:c...S!*!!....E*!....S!!:....!tu......!!n.....te!!!!n....!n!....ttn......!!=......!:$an..."n=!!......W!n... ,
1001-37A D-3 2 A 6 GL MD C AT-1 RR 0.296C RV-01 , BT-C OP 33 PIT 2Y 1001-378 D-11 2 A 6 GL MD C AT-1 RR 0.296C RV-01 BT-C OP 33 PIT 2Y IOOI-43A K-6 2 8 18 GA MD C PAS NA 1001-438 K-8 2 8 18 GA MO C PAS NA LOGI-43C J-6 2 8 18 GA MD C PAS NA 1001-430 J-8 2 B 18 GA 60 C PAS NA 1001-47 F-7 1 A 20 CA M0 C AT-1 RR 0.296C RV-Ol 8T-CT CS 30 RV-12 PIT 2Y 1001-50 E-7 1 A 20 GA 60 C AT-1 RR 0.296C RV-01 BT-CT CS 30 RV-12 4 PIT 2Y 1001-59 A-5 2 C 1 RL SA C CT-SP SY 1001-60 A-6 1 A 4 GA MD C AT-1 RR 0.296C RV-01 1001-63 8-7 I A 4 GA MD C AT-1 RR 0.296C RV-01 1001-67A K-3 2 C 12 CK SA S CT-C OP 001 CT-O OP 001 1001-678 K-10 2 C 12 CK SA S CT-C OP 001 CT-0 OP 001 1001-67C J-3 2 C 12 CK SA S CT-C OP 001 CT-O OP 001
l Y 5 2 . N 2 9, . ,)'~ A P 4 e0 8 2 ,k 0 g/ 1 0 0 1 1 1 0 1 0 C a2 2 0 0 0 0 N O P 1 S 1 . I 0 . D 0 . E . n ! 3 3 N o t ! 1 1 O T i s l en V Y S O B i v e l o n R R R R a. . m . a ; r g s x
- o a t r M a P r T '.
S . I . e . k . o . r 2 t : S I x I. a . M . t s e nP P
- O O P
S P S A N A N P O P O Y 5 T C.. S N . M EIO A L T
!! CO- - O- O
- S S C- C-P S
mVA ATS 0
! T T
!. C C T
C T C A P A P T C T C T C R C P N R 3 E .
- G D W c 3 N N O l a
e C C I A P T S m!! F
/
F
/
3, R A r! S S S C C S S C E. E T o ! N e R 2, LE A E 1 C t. U T IC S N V S r . R E L A M l t o! . S a e A A A A A A I N CmI L t u r S S S A A S S S S I c !. I P A . e . v r l e K K K F L K K L a r C C C B G C C R V e . v ! 5 l ! 2 8 8 a! 1 1 1 6 3 2 2 1 V S.. e . v! a C C C 8 B C C C l la S.. V a v o ! 2 m I ! C E e S a 2 1 1 2 2 2 2 N I ! N: tR G a S.. I e . S H D 02 0 5 I 1 2 l l 1 9 1 1 1 2 7 v l & 2 - - - - - - - - E a P 9 K D D E E J J E R u d . i . 1 s . 4 e . D A 8 3 4 2 R .7 8 8 0 1 0 0 s)' - 0 6 6 6 0 0 1 1 4 M : e 2 - - - 0 0 - -
,('~ 4 M v9 1 1 1 8 8 1 1
- E : 0 0 0 - - 0 0 V D T l
& Y S law V
0 1 0 1 0 1 0 A 0 A 0 1 0 1 S P P S ll' i l illf!ll!! ll l l
4 o* n TABLEY3-3 INSERYICE TEST lNG PROGtAM O , BOSTON EDISON C00PANY ISI CLASS 1,2,3 AND NC VALES P&lD: M-242 REVISION: El PILfRIM NLCLEAR PONER STATION Page 24 SYSTEM: Core Spray IST Program Revision 001, 12/08/82 l Valve P&lD ISI Valvo Valve Valve Actuator Nornet Test Max Stroke Max Relief
..htttc......c2tc...S!!!!....St!... 5152....!!n......!!st.....te!!!n....!!!!... 22s......!!=......'re.tn...han!!......W!!!... '
I400-3A H-7 2 B 18 GA 0 O/KL PAS NA I 1400-38 H-8 2 B 18 GA 2 O/KL PAS NA 003 i 1400-4A C-6 2 B 6 GA MD C BT-C OP 33 ! PIT 2Y 1400-48 C-6 2 8 6 GA E C BT-C OP 33 i Pli 2Y
! 1400-9A D-3 I C 10 CK SA S CT-0 RR i
RV-14 1400-98 B-3 I C 10 CK SA S CT-O RR RV-14 7 1400-13A E-7 2 C 3 SC SA CAO CT-0 OP 1400-13B E-9 2 C 3 SC SA CAO CT-O OP 1400-24A D-5 2 A 10 GA MO O AT-I RR 0.296C RV-01 BT-C OP 12.5 i 4 BT-O OP 12.5 PIT 2Y 1400-24B B-5 2 A 10 GA MO O AT-l RR 0.296C RV-01 , BT-C OP 12.5 BT-O OP 12.5 i PIT 2Y 1400-25A D-4 1 A 10 GA M0 C AT-I RR 0.296C RV-Of BT-C OP 12.5 BT-O OP 12.5 PIT 2Y r
TABLE 3-3 lNSERVICE TESTING PROGRAM BOSTON EDISON COePANY ISI CLASS 1,2,3 AND NC VALVES P&lD: M-242 REVISION: El PILCRIM NLELEAR POWER STATION s Page 25 SYSTEM: Core Spray IST Program Revision 001, 12/08/82 l Valve Pfl0 ISI Valve Valve Valve Actuator Normal Test Max Stroke Max Relief
..he: ......SW....S!!!!....S*I....S!!!....Irn......Irn.... 2:!!'n....!n!... 5tn......!!n... .'re.n!... ann!!......W!n...
1400-25B 8-4 1 A 10 GA M0 C AT-1 RR 0.296C RV-01 BT-C OP 12.5 BT-O OP 12.5 PIT 2Y 1400-35A E-5 2 C 6 m SA S CT-C OP 001 1400-32 E-5 2 C 6 CK SA S CT-C OP 001 1400-36A E-7 2 C 10 CK SA S CT-0 OP 001 1400-36B E-8 2 C 10 CK SA S CT-0 OP 001 1400-100 D-7 2 C 2 CK SA S CT-C OP 001 1400-102 8-7 2 C 2 CK SA S CT-C OP 001 1401-28A E-6 2 C 2 RL SA S CT-SP 5Y 1401-288 C-7 2 C 2 RL SA S CT-SP 5Y 4 i t i ? 5
TABLE 5-3 INSERVICE TEETIC PRO @AM BOSTON EDISON t,uMPANY 151 CLASS 1,2,3 AND NC VALES P&lD: M-243 REVISION: 15 PIL@lM NLELEAR POWER STATION Page 26 SYSTEM: HPCI IST Program Revision 001, 12/08/82 Valve PalD ISI Valve Valve Valve Actuator Norrel Test Max Stroke Max Rollet
..Wer..... 9?? ...S!*!!....Ea!....S!!!....!xer......!xer.....te!!!!ee....!!5!....Bes......!!=......!!aban... San!!......"2122...
2301-3 F-13 2 B 10 GA MD C BT-O OP 22 PIT 2Y 2301-4 D-4 1 A 10 GA MO O AT-1 RR 0.296C RV-01 BT-CT OP 25 BT-O OP 25 PIT 2Y 2301-5 D-6 i A 10 GA MO O AT-1 RR 0.296C RV-01 BT-CT OP 25 BT-O OP 25 l PIT 2Y 2301-6 C-10 2 0 16 GA MO O BT-C OP 30 PIT 2Y l 2301-7 H-5 i C 14 CK SA S CT-O RR RV-15 2301-8 H-5 1 A 14 GA MD C AT-1 RR 0.296C RV-01 l BT-CT OP 25 BT-O OP 25 PIT 2Y 2301-9 H-6 2 B 14 GA MO O BT-O OP 25 PIT 2Y 2301-10 E-6 2 0 10 GL M0 C BT-C OP 22 PIT 2Y 2301-14 F-8 2 B 4 GL M0 C BT-C OP 11 BT-O OP 11 PIT 2Y
_- . . - . - . . .. - -~. i TABLE 3-3 lNSERVICE TESTING PR0mAM BOSTON EDISON COMPANY ISI CLASS 1,2,3 AND NC VALVES P&lD: M-243 REVISION: 15 PlL@lM NtELEAR POWER STATION Page .27 SYSTEM: HPCI IST Program Revision 001, 12/08/B2 Valve P&lD ISI Valve Valve Valve Actuator Noral Test Max Stroke Man Relief ;
- . .hetc. .....Sec...c!!!!.. . .ct!.... Sin... .Ix u......!x u. . ...Pg j jj g,,,,{g j,,,,{g g ,,,,,,{jg,,,,,,L gggg,,,Rg ggj,,,,,,gjgg , ,
l 2301-34 K-5 2 C 2 O( SA S CT-C RR RV-17 l 2301-35 E-9 2 8 16 GA E C BT-CT OP 30 BT-O OP 30 PIT 2Y 2301-36 M-5 2 B 16 CA 2 C BT-CT OP 30 BT-O OP 30 PIT 2Y l 2301-39 M-6 2 C 16 CK SA S CT-O RR RV-31 o 2301-45 J-4 2 C 20 CK SA' S CT-O OP 001 $ CT-C RR RV-17 l 2301-74 J-4 2 C 20 SC SA C/LO CT-0 OP 001 l. A0-29 J-14 2 B 1 GL A0 0/FC BT-C OP 003 t l
; FST OP R V-0 5 L PIT 2Y !
{ A0-9313 K-10 2 B 1 GL A0 C/FC BT-C OP NA RV-34 FST OP RV-05 t PIT 2Y VRV-9066 J-5 2 C 1 RL SA S CT-C OP 001 CT-O OP 001
- CT-SP 5Y
, f i i f
-.- - - _ _ _ _ _ - - e n w ,m
lll1 11 1 Y 8 2 . N 2 8/ OP A . M O e0 g/ 8 2 n 2 0 2 0 0 1 C a2 2 0 0 0 N O P1 S 1 . I 0 . D 0 . E . n ! 6 6 N o f ! 1 1 O T S i is l e
=
2 V V R O v B e R lo h. R R m . a ! r s g x a o ab r M a P ! T !. S I k e . o .. r t S ! N
= A A N
_ x !. _ a . M . t s e t O2 nP Y P Y O 2 P O T 5 S N . E O . M V I
! O O C A L T ! - T - T R R -
A A mV O T S
! T
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T D T C RC F N R 3 E . 5
- G D W N N O n O3 I
T S A P 3, R lm! r! C C C C S E E A o ! L T R 2, E L N e A E 1 E t. T C t . I S N . V S r . R E L A M o . t r S a e A A A N I ICml L t u r H H S S S IS P I c !. A . e v r l V a nGA G A D R D R K C ev lai n0 1 0 1 6 1 6 1 4 V S.. e v ! B D D C la h.. B V 4 I ! C 1 S a 2 2 2 N 2 I ! N O S.. I S D 0 2 1 1 0 0 I l 1 1 1 8 V & 2 - - - - - E P 9 E E E D K R I . 4 C 4 P 2 H . 5
- 0 O
8 9 7 M : e 2 6 6 - M v l 2 - - 1
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O e TMILE 3.5-3 O INSERVICE TESTING PROGtAM B0STON EDlSON COMPANY ISI Ct. ASS 1,2,3 AND NC VALES PalD: M-245 REVISION: E2 PILGtlM NUCLEAR POWER STATION Page 29 SYSTEM: RCIC IST Program Revision 001, 12/08/82 Valve P&lD ISI Valve Valve Valve Actuator Norpel Test Max Stroke Max Rollef
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1301-16 C-6 1 A 3 GA MO O AT-1 RR 0.296C RV-01 BT-CT OP 20 PIT 2Y 1301-17 C-5 i A 3 GA MO O AT-l RR 0.296C RV-01 BT-CT OP 20 PIT 2Y 1301-25 L-8 NC B 6 GA MD C BT-C OP 55 PIT 2Y 1301-40 J-9 NC C 2 CK SA S CT-C RR RV-18 1301-41 J-6 NC C 8 CK SA S CT-C RR RV-18 1301-47 H-8 2 C 2 CK SA S CT-C RR RV-18 ; 1301-49 E-7 1 A 4 GA M0 C AT-1 RR 0.296C RV-01 BT-CT OP 20 PIT 2Y i r
N O C) U TAHLE Y.5-3 INSERVICE TESTING PROGAM BOSTON EDISON COMPANY ISI CLASS 1,2,3 AND NC VALES P&lD: M-247 . REVISION: E2 Pil.@lM NUCLEAR POWER STATION Page, 30 SYSTEM: Reactor Water Clean-Up IST Program Revision 001, 12/08/82 Valve P&lD ISI Valve Valvo Valve Actuator Normal Test Max Stroke Max Rollef
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1201-2 C-2 1 A 6 GA MO O AT-1 RR 0.29fic RV-01 BT-CT OP 25 PIT 2Y 1201-5 C-3 1 A 6 GA MO O AT-1 RR 0.29fic RY-01 BT-CT OP 25 PIT 2Y 1201-80 B-9 I A 4 GL MD 0 AT-1 RR 0.29fic RV-01 BT-CT OP 30 PIT 2Y i o 9
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o TABLL'I.3-3 O lNSERVICE TESTING FH0mAM BOSTON EDISON COMPANY 151 CLASS 1,2,3 AND NC VALES P&lD: M-250 REVISION: E3 PILmlM NtELEAR POWER STATION Page 32 SYSTEM: CRD Hydraulle IST Program Revision 001, 12/08/82 Valve PalD ISI Valve Valve Valve Actuator Nornel Test Max Stroke Max Rollet
..P.ert......S22t...S!*!!....S!!... 5122....!r22......!Ie2.....te!!!!ea....!!!!....B 2... . . .!!::... .. .!!2
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302-21A B-2 2 B RG A 1 O/FC BT-C CS RV-20 003 BT-O CS RV-20 003 FST CS RY-05 PIT 2Y 302-21B B-10 2 'B I RG A O/FC BT-C CS RV-20 003 BT-O CS RV-20 003 FST CS RV-05 PIT 2Y 302-22 D-6 2 B 2 RG A O/FC BT-C CS RV-20 005 BT-0 CS RV-20 003 FST CS RV-05 PIT 2Y CV-126 B-17 2 B 0.5 RG A C/FO BT-C OP RY-21 003,004 BT-O OP RV-21 003 FST OP RV-05 I PIT 2Y CV-127 A-17 2 0 0.5 RG A C/FO BT-C OP RV-21 003.004 BT-0 OP RV-21 003 FST OP RV-05 PIT 2Y RD-132 C-18 2 D 1 RD SA C' DTR SP 002 114 A-18 2 C 0.5 CK SA S CT-C SP RV-22 004 CT-O SP RV-22 115 C-19 2 C 0.5 CK SA S CT-C SP RV-22 004 CT-O SP RV-22 138 C-16 2 C 0.5 CK SA S CT-C SP RV-22 004 CT-O SP RV-22
l o D TAELE q.3-3 O INSERVICE TEST lNG PROGRAM H0STON EDISON CQ4PANY ISI CLASS 1,2,3 AND NC VALES P&lD: M-252 REVISION: El PIL(RIM NUCLEAR POWER STATION Page 33 SYSTEM: Nuclear Boller IST Program Revision 001, 12/08/82 Valve PalD ISI Valve Valve Valve Actuan.- Noriel Test Max Stroke Max Rollef
..Weter......c u t...S!r!!....St!....S!!!....!xn......!xer.....tn!!!n....!!!!... 5 n......!!n......!!P.en... ann!!......h!n...
203-IA C-6 i A 20 GL A ONC AT-1 RR 0.192C RV-01 BT-CT OP 5.5 FST OP RV-05 PIT 2Y 203-IB E-9 I A 20 GL A ONC AT-1 RR 0.192C RV-01 BT-CT OP 5. 5 FST OP RY-05 PIT 2Y 203-IC F-7 I A 20 GL A 05C AT-1 RR 0.192C RV-01 BT-CT OP 5.5 FST OP RV-05 PIT 2Y 203-ID F-7 i A 20 GL A ONC AT-1 RR 0.192C RV-01 BT-CT OP 5.5 ' FST OP RV-05 PIT 2Y 203-2A C-Il I A 20 GL A ONC AT-1 RR 0.192C RV-Ol BT-CT OP 5.5 FST OP RV-05 , PIT 2Y 203-28 E-9 1 A 20 GL A ONC AT-1 RR 0.192C RV-01 BT-CT OP 5.5 FST OP RV-05 PIT 2Y l
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O TAR.E q.3-3 O iNSERYICE TEST lNG PRO @AM BOSTON ED1 SON COMPANY ISI CLASS 1,2,3 AND NC VALES P&lD: M-252 REVISION: El PILCRIM NUCLEAR POWER STATION Page 34 SYSTEM: Nuclear Boller IST Program Revision 001, 12/08/92 , 4 Valve P&lD ISI Valve Valve Valve Actuator Nornel $ Test Max Stroke Max Ro llet
- . 222:......c er t...S!!!$....St!... 5152....!re!......!rn.....Pggj{jg,,,,{g{,,,,Qg,,,,,,((g,,,,,,Lgggg,,,Rggsj ,,, {,4g{g .
205-2C F-7 1 A 20 GL A AT-1 O/FC RR 0.19E RV-01 t BT-CT OP 5. 5 FST OP RV-05 PIT 2Y 203-2D F-7 1 A 20 GL A O/FC AT-1 RR 0.192C RV-Ol BT-CT OP 5.5 FST OP RV-05 i PIT 2Y 203-3A C-7 i A/C 6 RL SA C AT-3 SP I ' 212F RV-23 ; BT-O RR RV-24 003 ! CT-SP SY 203-38 F-7 i AM 6 RL SA C AT-3 SP 212F RV-23 BT-O RR RV-24 003 I CT-SP SY 203-3C F-7 I AM 6 RL SA C AT-3 SP 212F RV-23 BT-O RR RV-24 003 ; CT-SP 5Y 203-30 E-9 I A/C 6 RL SA C AT-3 SP 212F RV-23 i BT-O RR RV-24 003 CT-SP 5( l 203-4A E-8 i A/C 6 RL SA C AT-3 SP 212F RV-23 CT-SP SY 203-48 F-7 I AM 6 RL SA C AT-3 t SP 212F RV-23 CT-SP 5Y i a
o/ TAIL -* .3-3 O INSERVICE TESTING FHC3 TAM BOSTON EDISON COMPANY ISI CLASS 1,2,3 AND NC VALES P&lD: M-252 REVISION: El PILGtlM NtELEAR POWER STATION SYSTEM: Nuclear Boller Page 35 IST Program Revision 001. 12/08/B2 [ Valve PalD ISI Valve Valve Valve Actuator Normal Test Max Stroke Max Rollef
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D-9 1 A 3 5152....!xer......!rn.....tn!!!n....!!!!....t n......!!n......t:P.en..."un!!......W!n... GA M) C AT-1 RR O.296C RV-01 BT-C OP 30 PIT 2Y I 220-2 D-II 1 A 3 GA MD C i AT-1 RR 0.2960 RV-01 l BT-C OP- 30 e PIT 2Y
- 220-44 L-4 A i
1 1 GL A C#C AT-1 RR 0.296C RV-01 BT-C OP 10 FST OP RV-05 PIT 2Y 220-45 L-3 1 A GL A 1 CNC AT-1 RR 0.296C RV-01 BT-C OP 10 - FST OP RV-05 PIT 2Y 220-46 B-4 I B 1 GL A C#C BT-C l CS RV-25 003 l FST CS RV-05 ' Pli 2Y !
- 220-47 B-5 I B l 1 GL A C#C BT-C CS RV-25 003
} FST CS Rv-05 Plf 2Y j 6-58A E-4 1 A/C 12 CK SA S AT-1 RR 0.296C RV-Ot CT-C RR RV-26 6-58B F-4 1 A/C 12 CK SA S AT-1 RR 0.296C RV-01 CT-C RR RV-26 6-62A E-3 1 A/C 12 CK SA S AT-1 RR 0.29dC RV-01 . CT-C RR RV-26 I i 1 I )
s TABL 3-3 INSERvlCE TESTING PROGRAN BOSTON EDISON COEPANY ISI CIASS 1,2,3 AND NC VALES P&lD: M-252 REVISION: El PILGtl4 NUCLEAR POWER STATION - Page 36 SYSTEM: Nuclear Boller IST Program Revision 001, 12/0842 Valve P&lD ISI Valve Valve Valve Actuator Normal Test Max Stroke Max Rollef
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- F-3 1 AA
- 18 m SA S AT-1 RR 0.296C RV-01 CT-C RR RV-26 la276M3 C-7 NC C 1 m SA S CT-C RR RV-27 005 '
84A B-9 NC C 1 m SA S CT-C RR RV-27 8 54 B-1I NC C 1 m SA S CT-C RR RV-27 84B E-9 NC C I CK SA S CT-C RR RV-27 82 E-9 NC C 1 m SA S CT-C KR RV-27 84C F-8 NC C 1 m SA S CT-C RR RV-27 85C F-8 IC C 1 m SA S CT-C RR RV-27 I
, 84D F-8 NC C 1 CK SA S CT-C RR 1 RV-27 .
82 F-8 NC C 1 m SA S CT-C RR RV-27 j r J
TABLE ~3.5-3 i 1NSERVlCE TEST 1NG PR0 MAN ROSTON EDISON COMPANY ISI CLASS 1,2,5 AND NC VALES P&lD: X-001 REVISION: PILMIN NLCLEAR POWER STATION SYSTEM: Recirculation Pump Seal Water Page 37 IST Program Revision 001, 12/08/82 Valve P&lD ISI Velve Valve Valve Actuator Normal Test Max Stroke Max Rollet
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aP.,..R. 9.u.e.s.t. FO-13A - 2 AA: 0.75 m SA S AT-1 RR 0.296C RV-01 CT-C RR RV-28 FO-138 - 2 A/C 0.75 m SA S AT-1 RR 0.296C RV-01 CT-C RR R-28 i FO-17A - 2 A/C 0.75 CK SA S AT-1 RR 0.296C RV-01 , CT-C RR RV-28 FO-17B - 2 A/C 0.75 CK SA S AT-1 RR 0.296C RV-01 CT-C RR RV-28 l I l [ I
O O T ABL'c'3.5-3 INSERvlCE TESTING PROGtAM BOSTON EDISON COMPANY 151 Cl. ASS 1,2,3 AND NC VALES P&lD: X-002 REVISION: PILGtlM NUCLEAR POWER STATION Page 38 SYSTEM: Transwersing in-Core Probe IST Progran Revision 001, 12/08/82 Valve P&lD ISI Valv. Valve Valve Actuator Norgel Test Max Stroke Max Rollef
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TIP-BALA NC A - BL S C AT-1 RR 0.296C RV-01 BT-C OP 5 RV-29 PIT 2Y TIP-BALB - NC A - BL $ C AT-1 RR 0.296C RV-01 BT-C OP 5 RV-29 PIT 2Y l TIP-BALC - E A - BL S C AT-1 RR 0.296C RV-Ol
- BT-C OP 5 RY-29 PIT 2Y TIP-BALD -
NC A - BL S C AT-1 RR 0.296C RV-01 BT-C OP 5 RV-29 Pli 2Y TIP-SHA - NC D - SH XP O DTX SP 007 TIP-SMB - NC D - SH XP O DTX SP 007 TIP-SHC - NC D - SH XP O DTX SP 007 YtP-SM) - NC D - SH XP O DTX SP 007 i 'l i ) l 1 I I 1 I 1 I 4 wn v-v- -
e TABLE 3.5-3 INSERVICE TESTING PR0 MAN BOSTON EDISON CtWPANY ISI CLASS 1,2,3 AND NC VALW.S
.PalD: X-003 REVISION: PlL@lN NLCLEAR POWER STATION Page 39 SYSTEN: Post Accident Sampilng IST Program Revision 001, 12/08/82 Valve PalD ISI Valve Valve Valve Actuator Norral Test New Stroke Max ReIIef
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. .....T..i m..e. ... .....L eak..T....R.9. .ue..s.t... .. .N..o.t.e.s.. .
SV-5065-63 - NC A I GL SO C AT-1 RR 0.296C RV-01 SV-5065-64 - NC A I GL SO C AT-1 RR 0.2960 RV-01 SV-5065-71 - NC A I GL SO C AT-1 RR 0.296C RV-01 SV-5065-72 NC A I GL SO C AT-1 RR 0.296C RV-01 SV-5065-77 - NC A I GL SO C AT-1 RR 0.296C RV-01 SV-5065-78 - NC A 1 GL S0 C AT-1 RR 0.296C RW-01 SV-5065-85 - NC A I GL SO C AT-1 RR 0.296C RV-01 SV-5065 NC A 1 GL SO C AT-1 RR 0.296C RV-01 i i 4 i I l 5 i i l i 1
-s TAELE 3.5-3 INSERVICE TESTING PROGRAM BOSTON EDISON COMPANY ISI Ct. ASS 1,2,5 AND PC VALVES P&lD: X-004 REVISION: PILGtlM NIELEAR POWER STATION Page 40 SYSTEM: C-19 Return IST Program Revision 001, 12/08/82 Valve P&lD ISI Valve Valve Valve Actuator Noren t Test Max Stroke Max Ro llet
.."cB ......c e2;...c!!!!....ca!... 5112....!rer......!rer.....Pggj{jg,,,,Jgg{,,,,[ggg,,,,,,{jgg,,,,,,Lgggagg,,,Rgggg{,,,,,,Ng{gg,,. CV-5065 NC A 1 GL SO C AT-1 RR 0.296C RV-01 CV-5065-92 - E A I GL SO C AT-1 RR 0.296C RV-01 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ .}}