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| document type = TECHNICAL SPECIFICATIONS & TEST REPORTS, TEST/INSPECTION/OPERATING PROCEDURES | | document type = TECHNICAL SPECIFICATIONS & TEST REPORTS, TEST/INSPECTION/OPERATING PROCEDURES | ||
| page count = 90 | | page count = 90 | ||
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4.10 WASH-1400. EVENT V VALVE 1 l i | 4.10 WASH-1400. EVENT V VALVE 1 l i | ||
These valves are designated from a configuration of in-series check valves which provide a boundary between a high-pressure system and a system with a design pressure below that of the normal operating pressure of the high-pressure system. These valves will be leak tested at reduced pressures prior to entering Mode 2 after each refueling and prior to entering Mode 2 whenever the Plant has been in cold shutdown for 72 he or more, and if leakage testing has not been performed in the previous 9 months. Testing of these valves is in accordance with Technical Specification 4.4.6.2.2. | These valves are designated from a configuration of in-series check valves which provide a boundary between a high-pressure system and a system with a design pressure below that of the normal operating pressure of the high-pressure system. These valves will be leak tested at reduced pressures prior to entering Mode 2 after each refueling and prior to entering Mode 2 whenever the Plant has been in cold shutdown for 72 he or more, and if leakage testing has not been performed in the previous 9 months. Testing of these valves is in accordance with Technical Specification 4.4.6.2.2. | ||
4.11 LEAK TESTING MO-8701 AND MO-8702 PGE committed to individually leak test these valves in accordance with the requirements of IWV-3420 in a letter dated May 18, 1984 in response to an NRC request dated March 14, 1984 in SER 180. | 4.11 LEAK TESTING MO-8701 AND MO-8702 PGE committed to individually leak test these valves in accordance with the requirements of IWV-3420 in a {{letter dated|date=May 18, 1984|text=letter dated May 18, 1984}} in response to an NRC request dated March 14, 1984 in SER 180. | ||
4.12 RELIEF REQUESTS Pursuant to the provisions of 10 CFR 50.55a(g)(5)(iii), PGE has deter-mined that conformance with certain ASME Code requirements is impractical and relief from these requirements is necessary. The requests for relief are included in Table 4.1-2 as Item G under Residual Heat Removal System, Item I under Safety Injection System, Item A under Containment Spray System, and Item A under Instrument Air System and in Table 4.1-3 as Item A under Contain?ent Spray System. | 4.12 RELIEF REQUESTS Pursuant to the provisions of 10 CFR 50.55a(g)(5)(iii), PGE has deter-mined that conformance with certain ASME Code requirements is impractical and relief from these requirements is necessary. The requests for relief are included in Table 4.1-2 as Item G under Residual Heat Removal System, Item I under Safety Injection System, Item A under Containment Spray System, and Item A under Instrument Air System and in Table 4.1-3 as Item A under Contain?ent Spray System. | ||
A0W/mc 5834k 4.1-8 | A0W/mc 5834k 4.1-8 |
Latest revision as of 02:27, 5 May 2021
ML20212P879 | |
Person / Time | |
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Site: | Trojan File:Portland General Electric icon.png |
Issue date: | 08/29/1986 |
From: | Kent G, Reinhardt R PORTLAND GENERAL ELECTRIC CO. |
To: | |
Shared Package | |
ML20212P850 | List: |
References | |
PGE-1048, TAC-62727, TAC-62781, NUDOCS 8609030324 | |
Download: ML20212P879 (90) | |
Text
I' PGE-1048 RIvisicn 0 5 * -
4 TROJAN NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES SECOND 10-YEAR INTERVAL by Greg J. Kent Rusty Q. Reinhardt Portland General Electric Company 121 SW Salmon Street Portland OR 97204 0609030324 860329 PDR ADOCK 05000344 PDR p
p
~ ,
I l
TROJAN NUCLEAR PLANT !
PUMP AND VALVE INSERVICE TESTING PROGRAM CONTENTS l
Section Title Page
1.0 INTRODUCTION
. . . . . . . . . . . . . . . . . . . . . 1.0-1 2.0-1 !
2.0 ADMINISTRATIVE CONTROLS . . . . . . . . . . . . . . .
3.0 INSERVICE TESTING OF PUMPS . . . . . . . . . . . . . . 3.1-1 3.1 PUMP
SUMMARY
. . . . . . . . . . . . . . . . . . . . 3.1-1 3.1.1 Reference Values and Tolerances . . . . . . . . . . . 3.1-3 3.1.2 Records . . . . . . . . . . . . . . . . . . . . . . . 3.1-4 3.2 RELIEF REQUESTS FOR PUMPS . . . . . . . . . . . . . . 3.2-1 3.2.1 Service Water System: Pumps P108A, P108B, P108C . . . 3.2-1 3.2.2 Diesel Fuel Oil System: Pumps P144A and P144B . . . . 3.2-2 3.2.3 Feedwater System: Pumps P102A and P102B . . . . . . . 3.2-4 3.2.4 Chemical and Volume Control System: Pumps P205A and P205B . . . . . . . . . . . . . . . . . . . . . . . . 3.2-4 3.2.5 Component Cooling Water System: Pumps 210A, P210B, and P210C . . . . . . . . . . . . . . . . . . . . . . 3.2-5 3.2.6 Chemical and Volume Control System: Pumps P211A and P211B . . . . . . . . . . . . . . . . . . . . . . . . 3.2-6 4.0 INSERVICE TESTING OF VALVES . . . . . . . . . . . . . 4.1-1 4.1 VALVE
SUMMARY
. . . . . . . . . . . . . . . . . . . . 4.1-1 4.2 CATEGORY A AND B VALVES . . . . . . . . . . . . . . . 4.1-4 4.3 CATEGORY C VALVES . . . . . . . . . . . . . . . . . . 4.1-5 4.4 MULTIPLE CATEGORY VALVES . . . . . . . . . . . . . . . 4.1-5 4.5 PASSIVE VALVES . . . . . . . . . . . . . . . . . . . . 4.1-6 4.6 RECORDS . . . . . . . . . . . . . . . . . . . . . . . 4.1-6 4.7 FULL-STROKE EXERCISING . . . . . . . . . . . . . . . . 4.1-6 4.8 PART-STROKE EXERCISING . . . . . . . . . . . . . . . 4.1-6 4.9 CONTAINMENT ISOLATION VALVES . . . . . . . . . . . . . 4.1-7 4.10 WASH-1400, EVENT V VALVES . . . . . . . . . . . . . . 4.1-8 4.11 LEAK TESTING MO-8701 AND MO-8702 . . . . . . . . . . . 4.1-8 4.12 RELIEF REQUESTS. . . . . . . . . . . . . . . . . . . . 4.1-8 i
TABLES 3.1-1 Inservice Testing Program for Pumps . . . . . . . . .
4.1-1 Valve Summary Listing . . . . . . . . . . . . . . . .
4.1-2 Valve Full-Stroke Exercising at Greater than 3-Month Frequency . . . . . . . . . . . . . . . . . .
4.1-3 Valve Part-Stroke Exercising. . . . . . . . . . . . .
i i
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TROJAN NUCLEAR PLANT PUMP AND VALVE INSERVICE TESTING PROGRAM SECOND 10-YEAR INTERVAL
1.0 INTRODUCTION
Title 10, Chapter 1. Ccde of Federal Regulations - Energy, Part 50, Section 50.55a(s) sets forth the requirements for inservice inspection of nuclear power plant components.
The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, is referenced by 10 CFR 50.55a(s) as the standard to be used in developing a program for testing the operational ceadiness of pumps and valves. The Trojan Nuclear Plant ASME Code,Section III, Class 1, 2, and 3 components are committed to design and provision for access to enable the performance of tests for the opera-tional readiness of pumps and valves in accordance with ASME Code,Section II, 1971 edition, and addenda through the winter of 1972. The effective date for commercial operation of Trojan is May 20, 1976. The initial Pump and Valve Inservice Testing (IST) program for Trojan was developed for the first 10 years of commercial operation, which extended through May 20, 1986. The first 10-year test program is described in Topical Report PCE-1022.
This Topical Report describes the second 10-year interval extending through May 20, 1996.
Revisions to the Pump and Valve IST program are required to be made at 120-month intervals to upgrade the program to reflect subsequently approved editions and addenda of ASME Code Section II. Approved editions and addenda are referenced in the effective issue of 10 CFR 50.55a(b)(2).
1.0-1
Successive 120-month intervals are required to meet the standards of the approved edition and addenda in effect 12 months prior to the commence-ment of the applicable 120-month period. The 1985 edition of 10 CFR 50, in effect at that time, required the use of the 1980 edition, winter 1982 addenda of ASME Code Section XI. Paragraph 10 CFR 50.55a(s)(4)(iv) was invoked to write the program to meet the requirements set forth in the subsequent addition and addenda of the Code which was incorporated by reference in the 1986 edition of 10 CFR 50. This program will implement, to the maximum extent possible, the requirements of the 1983 edition, summer 1983 addenda of ASME Code Section XI, Subsections IWP and IWV fcr Pump and Valve IST.
j Certain systems at the Trojan Nuclear Plant are safety-related or are required for safe shutdown, but were not designed to ASME Code, Sec-J tion III, Class 1,'2, or 3 standards (eg, component cooling water, service water, etc). For the Trojen Nuclear Plant, those systems designated Quality Group 1, 2, 3A, and 3B in the Updated Final Safety Analysis Report (UFSAR) are included in the IST program to meet the intent of proving operational readiness of components required to function in the event of an accident.
Subsections IWP and IWV of Section XI of the ASME Code, 1983 edition and addenda through the summer of 1983, give the specific requirements for IST of pumps and valves which are a part of the Trojan Nuclear Plant Pump and Valve IST program. Implementing procedures for the IST program are to comply with these standards. ,
l Those pumps and valves for which conformance with certain provisions of l the approved Code requirements is impractical are identified by relief l
request. These relief requests once approved-by the Nuclece Regulatory l ,
I ' Commission (NRC) will form the basis for the alternative tests to be
- listed herein.
l I
I 1.0-2
T 2.0 ADMINISTRATIVE CONTROLS The IST program for pumps and valves is required by the Trojan Nuclear Plant Technical Specifications, Appendix A to Facility Operating License (FOL) NPF-1. Changes involving additional relief requests from ASME Code Section XI requirements will be submitted to the NRC for approval.
Implementation of this program will be accomplished through Plant proce-dures in accordance with the Nuclear Quality Assurance Program, PGE-8010.
These procedures will identify the specific Plant status, valve lineups, operating steps, and return of valves to a normal lineup to accomplish the required testing at the established frequency. Compliance with the provisions of the testing requirements of ASME Code Section XI, Subsec-tions IWP and IWV, shall be assured by an Inspector as required by Paragraph IWA-2120.
2.0-1
3.0 INSERVICE TESTING OF PUMPS The IST program for pumps is described in Section 3.1. Section 3.2 j provides the alternative testing of specific pumps and the basis for such l test variance.
3.1 PUMP
SUMMARY
l Table 3.1-1 is a complete listing of all pumps to be tested under the Trojan Nuclear Plant Pump and Valve IST program. The listing includes:
(1) The identification number, description, and P&ID location of each pump to be tested; (2) The applicable ASME Code class designation for each pump; (3) The test parameters to be measured for each pump; and (4) The required test frequency for each pump.
Pump design criteria for the Trojan Nuclear Plant are summarized in Section 3.2 and tabulated in Table 3.2-3 of the UFSAR. Pump design code designations used in this program for determining IST requirements are summarized below:
ASME Code Class ASME VIII Designation 1 2 3 Division 1 Trojan Quality Group 1 2 3A 3B Minimum Code ASME III P&V P&V ASME VIII Application Class A Class II Class III Division 1 3.1-1
For clarification, the following notes are pecvided for the pump design code designations used in the previous table:
ASME III: ASME Boiler & Pressure Vessel Code, 1968, Nuclear Vessels plus addenda and code interpretations to the date of purchase award.
For purchase awards on or after July 1, 1971, reference to ASME III should be to ASME Boiler & Pressure Vessel Code, Nuclear Power Plant Components, 1971 edition, plus addenda to the date of purchase award.
P&V: the November 1968 Draft ASME Code for Pumps and Valves plus addenda to the date of purchase award.
ASME VIII means ASME Boiler & Pressure Vessel Code,Section VIII, Pressure Vessels, 1968 edition plus addenda to the date of purchase award. These pumps are to meet the IST requirements for ASME Code Class 3 pumps.
For pumps designed to Quality Group 3(b) operating above 150 psi and 212*F,Section VIII, Division 1 of the ASME Boiler & Pressure Vessel Code was used as a guide in calculating the thickness of the pressure rating parts and in sizing the cover bolting. Below 150 psi and 212*F the manufacturer's standard for service was used.
Abbreviations for measured parameters in Table 3.1-1 are identical to those listed in Article IWP-3000 and are repeated below for convenience:
N = Rotative speed (rpm).
Rotative speed is not required to be measured for pumps directly coupled to motor drivers per Paragraph IWP-4400.
f Pg = Inlet pressure (psig).
Inlet pressure is measured prior to starting the pump and during testing.
3.1-2
f I l
l l
AP = Differential pressure acecrs the pump (psid).
This value is determined by measuring the pump discharge pressure (P ) and subtracting pump inlet pressure (P ).g Q = Pump flow rate (spm).
V = Vibration amplitude (mils).
T = Bearing ter.peraturc (F).
b 3.1.1 REFERENCE VALUES AND TOLERANCES Reference values are to be determined from the results of testing during the IST for each pump and are to be taken from procedures which are readily duplicated for future testing. The reference values and allow-able ranges of IST quantities are specified in Plant procedures. The limits of operability are established according to the criteria set forth in the Trojan Nuclear Plant Technical Specifications, limitations imposed by the Trojan UFSAR, and Paragraph IWP-3210.
After a pump has been repaired in a manner that affects the established reference values, the old reference values are to be reconfirmed or a new set of reference values are to be established within 96 he af ter return-ing the pump to service. Testing to reverify operability will be done in j
accordance with applicable IST procedures, and the reason for changing a set of reference values will be documented.
The criteria for establishing reference values is defined in Para-graph IWP-3110. Administrative control of deviations or revisions to procedures will comply with the Trojan Nuclear Plant Administrative Orders (AOs).
l 3.1-3 l
r 3.1.2 RECORDS All IST records shall be retained for the service lifetime of the pump.
Records shall be readily accessible for review and shall be maintained in accordance with the Trojan Nuclear Plant procedure for the control of Plant records. The records of IST of pumps shall be in accordance with Article IWP-6000.
l 4
3.1-4
TABLE 3.1-1 Sheet 1 of 3 INSERVICE TESTING PROGRAM FOR PUMPS Relief Pump ASME P&ID No. Measures Test Request ID No. Description Code Class (Coordinates) Parameters Frequency Remarks P102 A Auxiliary Feedwater ASME VIII M-213 N. P 1 , AP, V, Tb 3 Konths 3.2.3[a,b]
4 (Turbine) Division 1 (B-7)
P102 B Auxiliary Feedwater ASME VIII M-213 N, P i , AP, V, Tb 3 Months 3.2.3[a,b]
(Diesel) Division 1 (D-7)
P108 A Service Water ASME VIII M-218 P i , AP, Q, V 3 Months 3.2.1[c]
Division 1 (F-7)
P108 B Service Water ASME VIII M-218 P i , AP, Q, V 3 Months 3.2.1[c]
Division 1 (D-7)
P108 C Service Water ASME VIII M-218 P 1 , AP, Q, V 3 Months 3.2.1 ECI Division 1 (D-7)
P144 A Diesel Fuel Oil ASME VIII M-226 P1, AP 3 Months 3.2.2[c]
Division 1 (F-7)
P144 B Diesel Fuel Oil ASME VIII M-226 P i , AP 3 Months 3.2.2[c]
Division 1 (D-7)
P148 A Service Water Booster 3 M-218 P i , AP, Q, V, Td 3 Months [a,b,c]
(C-5)
P148 B Service Water Booster 3 M-218 P,1 AP, Q, V, Tb 3 Months [a,b c]
(C-6)
P148 C Service Water Booster 3 M-218 Pi, AP, Q, V, Tb 3 Months [a,b,c]
(D-5)
P148 D Service Water Booster 3 M-218 P i , AP, Q, V. Tb 3 Months [a,b,c]
(D-6)
TABLE 3.1.-? Sheet 2 of 3 Relief Pump ASME P&ID No. Measures Test Request ID No. Description Code Class (Coordinates) Paramot.ers Frequency Remarks P202 A Residual Heat Removal 2 M-205 P3 , AP, Q, V Tb 3 Months [a,b,c]
, (G-4)
F202 B Residual Heat Removal 2 M-205 Pi , AP, Q V Tb 3 Months [a,b,c]
(D-4)
P203 A Safety Injection 2 M-206 P, i AP,Q,V Tb 3 Months [a,b c]
(B-3)
P203 B Safety Injection 2 N-206 P i , AP, Q, V Tb 3 Months [a,b,ci-(B-3)
P204 A Containment Spray 2 M-207 Pi, AP, Q, V. Tb 3 Months [a,b.cl (G-4)
P204 B Containment Spray 2 M-201 P 1 , AP, Q, V, Tb 3 Months [a,b,c]
(C-4)
P205 A Centrifugal Charging 2 M-202 P i , AP, V. Tb 3 Months 3.2.4[a,b,c]
(C-6) l P205 B Centrifugal Charging 2 M-202 Pl. AP, V, Tb 3 Months 3.2.4[a,b,c]
(B-6)
P210 A Component Cooling Water 3 M-215 P 1 , AP, Q, V, Tb 3 Months 3.2.5(a,b,c]
(G-2)
P210 B Component Cooling Water 3 M-215 Pi, AP, Q. V, Tb 3 Months 3.2.5[a,b,c]
(C-2)
P210 C Component Cooling Water 3 M-215 P i , AP, Q V. Tb 3 Months 3.2.5[a,b,c)
(E-2)
TABLE 3.1-1 Sheet 3 of,3 Rclief Pump ASME P&lD No, Measures Test Request ID No. Description Code Class (Coordinates) Parsmeters Frequency Remarks M-202 P, 3 Months 3.2.6(a,b,c]
P211 A Boric Acid Transfer 3 i fP, V, Tb (C-2)
P211 B Boric Acid Transfer 3 M-202 Pi, AP, V Tb 3 Months 3.2.6[a,b,c]
(C-1)
[c] Lubricant level and/or pressure are to be observed and/or verified to be within manufacturer's tolerances for each individual component. The requirement for observation of lubricant level and/or pressure is to be inco porated into each pump test procedure.
[b] Bearing temperatures are to be measured at least once each year during IST.
[c] Pump speed is fixed; therefore, pump speed will not be measured.
i i
e
3.2 REl.IEF REQUESTS FOR PUMPS The Code of Federal Regulations, 10 CFR 50.55a(g)(5)(iii), states that, "If the licensee has determinei that conformance with certain code requirements is impractical for his facility the licensee shall notify the Commission and submit information to support his determinations."
By interpretation, testing of pitmps which does not conform to the standard test requirements for n.easurement of specific parameters or for the frequency of performance of tests is assumed to be a nonconformance.
This section identifies those ptmps for which the Trojan Nuclear Plant is in nonconformance with the standard test requirements and provides the basis for the relief request an! the provisions for alternate testing of those pumps. Testing for these. pumps will be performed in accordance with the following descriptions.
3.2.1 SERVICE WATER SYSTEM: PUMPS P108A. P108B. P108C Code Class: ASME VIII, Division 1 Function: The service water pumps provide cooling and makeup water for safety-related and non-safety-related equipment and systems.
The pumps are also used for dilution of liquid radwaste during discharge.
Test Requirement: Measure / observe pump inlet pressure, vibration amplitude, bearing temperature, and lubricant.
Basis for Variance: " Instrumentation Not Originally Provided."
ASME VIII pumps at Trojan were not required to be designed for testing for operational readiness as per 10 CFR 50.55a(g).
3.2-1
The pumps are totally submerged inside the Intake Structure. Pump bearings are inaccessible and the instrumentation required for measurement of pump inlet pressure, vibration amplitude, and bearing temperature was not provided in the original system design.
Relief Request: Inlet pressure for these pumps will be determined by measuring the Intake Structure water level.
The pumps are submerged in the Intake Structure and are not accessible for attachment of transducers for displacement measurement of vibration amplitudes during pump operation. The pump motor inboard bearing will be periodically monitored for. vibration amplitude. Motor inboard bearing vibration measurements provide indication of pump shaft alignment and deterioration.
The pump bearing vibration amplitude will not be measured. The pump bearing temperature will not be measured, and the lubricant will not be observed.
3 . 2' . 2 DIESEL FUEL OIL SYSTEM: PUMPS P144A AND P144B Code Class: ASME VIII, Division 1 Function: The diesel oil transfer pumps provide flow of fuel oil from the diesel oil storage tanks to the fuel oil day tanks.
Test Requirement: Measure pump inlet pressure, differential pressure, flow rate, vibration amplitude, bearing temperature, and lubricant. The resistance of the system shall be varied until either the measured differential pressure or the measured flow rate equals the corresponding reference value.
3.2-2
i
~* . l Basic for Variance: "Instrumen.ation Not Originally Provided."
ASME VIII jumps at Trojan were not required to be i designed for testing for operational readiness as per 10 CFR 50.55a(g). Instrumentation was not l provided for measurement of inlet pressure, dif-ferential pressure, and flow rate. No recirculation (test) flow path available to establish reference flow or differential pressuie conditions.
" Accessibility". There pumps are located inside the diesel oil storage tanks. The pumps are inaccessi-ble for measurement of vibration amplitude and bearing temperature.
Relief Request: Pump discharge pressure will be measured while inservice refilling emergency diesel generator (EDG) day tanks.
The inlet pressure will be calculated from diesel oil storage tank level to determine the suction head on the pump. The differential pressure will be taken as the difference between pump discharge pressure and calcu-lated suction pressure. This calculated differential pressure will be monitored as a measure of pump per-formance. The pump flow rate will be calculated from a timed rise in the fuel oil day tank level. Operational readiness will be demonstrated by the pumps ability to supply 20 gym makeup to the EDG day tanks as assumed in the UFSAR. The pumps are enclosed within the diesel oil storage tanks; accessibility is not available for measuring pump vibration amplitude or bearing tempera-ture, and the lubricant cannot be observed.
3.2-3
r 3.2.3 FEEDWATER SYSTEM: PUMPS P102A and P102B Code Class: ASME VIII, Division 1 Function: The auxiliary feedwater (AFW) pumps provide a backup to the normal feedwater pumps to ensure the safety of the Plant and protection of steam generators when the normal fee'dwater pumps are unavailable.
Test Requirement: Measure the flow rate every 3 months.
Basis for Variance: " Instrumentation Not Originally Provided." ASME Section VIII pumps at Trojan were not required to be designed for testing for operational readiness as per 10 CFR 50.55csg). These pumps are tested using a fixed resistance flow path (recirculation flow to the condensate storage tank) since instrumentation was not provided for measurement of flow rate in the flow path.
Relief Request: The inlet pressure, differential pressure, rotative speed, bearing temperature, and vibration amplitude will be measured for each of these pumps. Measurement of these pump parameters will provide evidence to assess the operr.Lional readiness of these pumps. Flow rate can be adequately evaluated from the pump differential pressure measurement since a fixed resistance path is used.
3.2-4 i
F l I
3.2.4 CHEMICAL AND VO!,UME CONTROL SYSTEM: PUMPS P205A and P205B l
Code Class: 2
)
Function: These pumps normally are in service supplying makeup flow to the Reactor Coolant System (RCS) and reactor coolant pumps (RCP) seals. During a Loss-of-Coolant Accident, both of these pumps operate as part of the Safety Injection System (SIS).
Test Requirement: Measure the flow rate every 3 months.
Basis for Variance: " Instrumentation Not Provided." Class 2 pumps at Trojan were not required to be designed for testing for operational readiness as per 10 CFR 50.55a(g).
These pumps are tested using a fixed resistance flow path [ recirculation flow to the refueling water storage tank (RWST)] since instrumentation was not provided for measurement of flow rate.
Relief Request: The inlet pressure, differential pressure, bearing temperature, and vibration amplitude will be measured for each of these pumps. Measurement of these pump parameters will provide evidence to assess the opera-tional readiness of these pumps. Flow rate can be adequately evaluated from the pump differential pressure measurement since a fixed resistance path is used.
3.2.5 COMPONENT COOLING WATER SYSTEM: PUMPS 210A. P210B. and P210C Code Class: 3 Function: Supply and maintain the required cooling water flow to safety-related and other equipment vital to the safe shutdown and normal operation of the Plant. These loads include the RCPs, letdown heat exchanger, residual heat removal (RHR) heat exchangers, and seal water heat exchanger.
3.2-5
F~
e o ,
Test Requirement: The resistance of the system shall be varied until either the measured differential pressure or the measured flow rate equals the corresponding reference value.
Basis for Variance: A set or sets of reference values cannot be estab-lished for either differential pressure or flow in accordance with IWP-3110 due to piping configuration and operating loads supplied by the Component Cooling Water (CCW) System. A recirculation (test) flow path is not available to establish a reference flow rate. Attempts to establish a reference differential pressure or flow rate would require adjusting flow to various critical operating loads which could affect the operability of the inservice equipment. This syst'em is used during all modes of Plant operation, all requiring different minimum cooling flows to the supplied components.
Relief Request: Reference values will be established with respect to the manufacturer's pump curve and allowable ranges specified in accordance with IWP-3210 to monitor pump performance.
Flow and differential pressure will be measured and com-pared to the specified ranges to determine pump opera-tional readiness.
3.2.6 CHEMICAL AND VOLUME CONTROL SYSTEM: PUMPS P211A and P211B Code Class: 3 Function: Normally, one of these pumps is aligned with one boric acid tank and starts on demand from the teactor makeup control system. Emergency boration, the supplying of 4-wt% boric acid 3.2-6
r OO ,
solution to the suction of the charging pumps, can be accomplished by either/or both of these pumps. These pumps are also used to transfer 4-wt% Doric acid solution from the batching tank to the boric acid tanks.
Test Requirement: Measure the flow rate every 3 months.
Basis for Variance: " Instrumentation Not Provided." Class 3 pumps at Trojan were not required to be designed for testing for operational readiness as per 10 CFR 50.55a(g).
These pumps are tested using a fixed resistance flow path (recirculation flow to the boric acid tanks) since instrumentation was not provided for measurement of flow rate.
Relief Request: The inlet pressure, differential pressure, bearing temperature, and vibration amplitude will be measured for each of these pumps. Measurement of these pump parameters will provide evidence to assess the operational readiness of these pumps. Flow rate can be evaluated from the pump differential pressure measurement since a fixed resistance path is used.
3.2-7
o . ,
4.0 INSERVICE TESTING OF VALVES The IST program for valves is described in this section.
4.1 VALVE
SUMMARY
Table 4.1-1 is a complete listing of all valves to be tested under the Trojan Nuclear Plant Pump and Valve IST program. The listing includes:
(1) The identification number, description, P&ID location, and normal position of each valve to be tested; (2) The applicable ASME Code Class designation and Section XI category for each valve; (3) The required tests for each valve; and (4) The required test frequency for each valve.
Valve design criteria for the Trojan Nuclear Plant are summarized in Section 3.2 and tabulated in Table 3.2-3 of the UFSAR. Valve design code designations used in this program for determining IST requirements are summarized below:
ASME Code Class ANSI Designation 1 2 3 B31.1 Trojan Quality Group 1 2 3A 3B Minimum Code ANSI B16.5 P&V P&V Non-Nuclear Application MSS-SP-66 Class II Class III ANSI B31.1 4.1-1
r e O ,
For clarification, the following notes are provided for the pump design code designations used in the previous table:
P&V: means the November 1968 Draft AAME Code for Pumps and Valves plus addenda to date of purchase award.
Valves designated ANSI B31.1 are to meet the IST requirements for ASME Code Clasa 3 valves.
Valves whose test requirements deviate from the standard frequency requirements of Subsection IWV are referenced to their applicable relief request.
Valves which have a limitation on their maximum stroke time in fulfilling their accident function are annotated in the Testing column. The limiting value of full-stroke time is specified in Plant Operating Procedures for implementing the Valve Test program.
The following abbreviations are used in Table 4.1-1:
VALVE DESCRIPTION:
A0 = Air Operated MO = Motor Operated NORMAL POSITION:
C = Closed 0 = Open 4.1-2
TESTING:
ST/0 = Stroke timed for open position.
ST/C = Stroke timed for closed position.
ST/0C = Stroke timed for apen and closed positions.
(blank) = Stroke timing not required.
The test frequency for valves is indicated by one of the following phrases:
(1) Three months implies at least once every 92 days.
l l
(2) cold shutdown implies when the Plant is in or has been in !
Mode 5. In the case of frequent cold shutdowns, the test need not be performed if less than 92 days have elapsed since the last performance of the test. Valve exercising shall commence within 72 he of achieving cold shutdown and continue until all testing is complete or the Plant is ready to return to power.
However, it is not the intent of this program to keep the Plant in cold shutdown in ceder to complete cold shutdown testing.
Exception to the 72-hr rule may be taken and testing started at a later time if an extended shutdown is planned during which all cold shutdown testing will be performed.
t (3) Refueling implies when the Plant has been shut down for a scheduled refueling outage. The schedule for testing of safety and rellei valves has been established to comply with Table IWV-3510-1, based on refueling outage mode changes.
(4) Two years implies valve leak rate tests are required every two years per Paragraph IWV-3422. Typically, these tests are per-formed during each refueling outase with the exception of NO-8701, MO-8702, and -8956 A through D.
4.1-3
Q (5) Five years implies at least once every five years as required by Paragraph IWV-3511. Five years represents the maximum limit ,
between successive tests for all safety valves in the program.
f; l
4.2 CATEGORY A AND B VALVES Preservice testing of new valves which fall under the scope of this program is mandatory. Valves which have been repaired or replaced must be tested prior to being returned to service. Test requirements result- 1 ins from maintenance or replacement of a valve are to be controlled in accordance with Trojan Nuclear Plant Aos and maintenance procedures. I l
i Testing of valves is to be accomplished in accordance with the designated f reference procedure. Administrative control of deviations or revisions l to procedures shall comply with Trojan Nuclear Plant A0s.
- Containment isolation valves are not to be tested for seat leakage rat.e under ASME Code Section II. Seat leakage rate testing and analyses are to comply with Appendix J to 10 CFR 50 for establishing Containment isolation valve integrity. Paragraph 4.9 provides the basis for relief and justification for exemption of seat leakage rate testing from the requirements of ASME Code Section II. The requirements for testing in-series check valves which provide isolation between the RCS and other systems with a lower design pressure are included within the scope of this program for tracking purposes only.
Valves whose test data is outside the tolerance ranges are to be evaluated for corrective action in accordance with Paragraphs IWV-3417 and IWV-3427, with the exception that a 24-he grace period is not allowed before declaring inoperable a valve that is not capable of 4.1-4
- r. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
performing its specified function. Test data outside the established tolerance ranges is to be reported in accordance with the Trojan Nuclear l
. Plant procedure for anomalous indication during periodic curveillance, j l
4.3 CATEGORY C VALVES Preservice testing of new valves which fall under the scope of this program is mandatory. Valves which have been repaired or replaced must be tested prior to being returned to service. T6st requirements result-
. ing from maintenance or replacement of a valve are to be controlled in accordance with Trojan Nuclear Plant A0s and maintenance procedures.
Testing of valves is to be accomplished in accordance with the designated reference procedure. Administrative control of deviations or revisions to procedures shall comply with Trojan Nuclear Plant AOs.
Corrective action for safety and relief valves is to be in accordance with Paragraph IWV-3514. Corrective action for check valves is to be in accordance with Paragraph IWV-3523, with the exception that a 24-hr grace period is not allowed before declaring inoperable a check valve that is not capable of performing its speelfied function.
4.4 MULTIPLE CATEGORY VALVES When a valve has a multiple category classification, such as AC, the test requirements of both categories must be met; however, duplication of testing is not required. Documentation shall meet the requirements of both categories.
4.1-5
r
_ i 4.5 PASSIVE VALVES Passivas valves, as defined in Paragraph IWV-2100(b), will not be exercised, as noted in Table IWV-3700-1. The passive valves which are included in this program are manual valves or check valves which are normally shut during power operation anc are required to be shut to mitigate the consequences of an accident as Containment isolation boundaries. Valves which are normally open and remain open during accident conditions represent passive valves used only for operating convenience or maintenance and are exempted by Paragraph IWV-1200(a).
4.6 RECORDS All inservice inspection records shall be retained for the service lifetime of the valve. Records shall be readily accessible for review and shall be in accordance with Trojan Nuclear Plant procadures for control of Plant records. Records of IST of valves shall be in accordance with Article IWV-6000.
4.7 FULL-STROKE EXERCISING Category A, B, and C active valves that cannot be exercised during Plant operation will be full-stroke exercised during cold shutdowns or refuel-ing outages. Table 4.1-2 lists these valves and includes the basis for why each valve cannot be tested during Plant operation.
i.8 PART-STROKE EXERCISING Category A, B, and C active valves where only limited operation is practical during Plant operation will be part-stroke exercised during Plant operations and full-stroke exercised during cold shutdowns.
Table 4.1-3 lists these valves and includes the basis for why only limited operation is practical during Plant operation.
4.1-6
l i
4.9 CONTAINMENT ISOLATION VALVES These valves provide Containment isolation during reactor operation and/or isolate Containment to prevent release of radioactive products following a design basis accident.
Containment isolation valves are tested for seat leakage under the criteria of Appendix J to 10 CFR 50. These valves are tested and analyzed for seat tightness in accordance with the Trojan Nuclear Plant
" Containment Local Leak Rate Test". This procedure provides for local leak rate testing of valves. The acceptance criteria for allowable leakage rate under Appendix J to 10 CFR 50 varies from the acceptance criteria of Subsection IWV of ASME Code Section XI in that the allowed leakage is based on the total containment leakage rate rather than on individual valve seat leakage criteria. . This test program provides adequate documentation and individual analysis for valves to verify maintenance of Containment integrity. Failure of any valve to provide adequate seat tightness in maintaining Containment integrity will require the same corrective action for repair and replacement of the valve.
Therefore, the 10 CFR 50, Appendix J requirements are adequate in lieu of IWV-3420 requirements. Individual valve leakage rate requirements are assigned and actual leakage rates are compared with previous measurements, which are in compliance with the requirements of IWV-3426 and IWV-3427.
Ihese valves are tested for seat leakage rate during local leakage rate testing in accordance with Appendix J to 10 CFR 50 and will not be tested under this program. Individual valve leakage rate criteria is specified by PGE in accordance with IWV-3426 and corrective actions will be in accordance with IWV-3427.
4.1-7
r
- = . I l
4.10 WASH-1400. EVENT V VALVE 1 l i
These valves are designated from a configuration of in-series check valves which provide a boundary between a high-pressure system and a system with a design pressure below that of the normal operating pressure of the high-pressure system. These valves will be leak tested at reduced pressures prior to entering Mode 2 after each refueling and prior to entering Mode 2 whenever the Plant has been in cold shutdown for 72 he or more, and if leakage testing has not been performed in the previous 9 months. Testing of these valves is in accordance with Technical Specification 4.4.6.2.2.
4.11 LEAK TESTING MO-8701 AND MO-8702 PGE committed to individually leak test these valves in accordance with the requirements of IWV-3420 in a letter dated May 18, 1984 in response to an NRC request dated March 14, 1984 in SER 180.
4.12 RELIEF REQUESTS Pursuant to the provisions of 10 CFR 50.55a(g)(5)(iii), PGE has deter-mined that conformance with certain ASME Code requirements is impractical and relief from these requirements is necessary. The requests for relief are included in Table 4.1-2 as Item G under Residual Heat Removal System, Item I under Safety Injection System, Item A under Containment Spray System, and Item A under Instrument Air System and in Table 4.1-3 as Item A under Contain?ent Spray System.
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TABLE 4.1-1 Sheet 2 of 34 INSERVICE TESTING PROGRAM FOR VALVES i
SYSTEM: Reactor Coolant P&ID NO: M-201, Sheet 2
- ASME j Valve Valve Dwg Code Sect XI Norm Test Frequency I
ID No. Description Loc Class Cat. Pos Exercise Leakage Coments Testing l PCV-455A 3" A0 Globe G-7 1 B C Cold shutdown NA 4.7 ST/OC PCV-456 G-7 C ST/OC l
3 l MO-P000A 3" MO Cate G-7 1 B 0 3 months NA ST/OC MO-8000B C-7 0 ST/OC PSV-8010A 6" Safety G-6 1 C C 5 years NA PSV-8010B G-5 C PSV-8010C G-5 C CV-8025 3/8" AO Clobe G-1 2 A O 3 months 2 years 4.9 ST/C CV-8026 G-2 O ST/C CV-8028 3" AO F-1 2 A O 3 months 2 years 4.9 ST/C Diaphragm CV-8033 3/4" AO F-2 2 A O 3 months 2 years 4.9 ST/C i Diaphragm i 8046 3" Check F-2 2 AC C NA 2 years 4.5 8047 3/4" Check F-2 2 AC C NA 2 years 4.5, 4.9 8079 4" Check D-2 2 C C NA NA 4.5 l 8090A 1/8" Manual E-5 2 A C NA 2 years 4.5,4.9 8090B Needle E-5 C i
i 1
TABLE 4.1-1 Sheet 3 of 34 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Chemical and Volume Control P&ID NO: M-202 ASME Valve Valve Dwg Code Sect XI Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Comments Testing MO-112B 4" MO Cate E-5 2 B O 3 months NA ST/C MO-112C E-5 0 ST/C MO-112D 8" MO Gate C-5 2 B C 3 months NA ST/0 MO-112E C-5 C ST/0 MO-8104 2" MO Globe C-4 2 B C 3 months NA ST/0 MO-8105 3" MO Gate F-7 2 B O 3 months NA ST/C MO-8106 F-7 0 ST/C PSV-8117 3" Safety G-7 2 C C 5 years NA PSV-8118 3/4" Safety E-6 2 C C 5 years NA PSV-8119 2" Safety H-5 2 C C 5 years NA PSV-8120 3" Safety G-6 2 C C 5 years NA PSV-8124 3/4" Safety B-5 2 C C 5 years NA CV-8149A 2" AO Globe F-8 2 A C 3 months 2 years 4.9 ST/C CV-8149B F-7 O ST/C CV-8149C F-7 C ST/C CV-8152 2" AO Globe G-7 2 A O 3 months 2 years 4.9 ST/C j _
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TABLE 4.1-1 Sheet 4 of 34 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Chemical and Volume Control P&ID NO: M-202 i ASME'
, Valve Valve Dwg Code Sect XI Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Conunents Testing 8481A 4" Check C-6 2 C C 3 months NA 4.8 8481B B-6 C 8546 8" Check C-5 2 C C Cold shutdown NA 4.7 4
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TABLE 4.1-1 Sheet 6 of 34 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Residual Heat Removal P&ID NO: M-205 ASME Valve Valve Dwg Code Sect XI Nom Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Coments Testing HCV-606 8" AO F-7 2 B O 3 months NA ST/OC HCV-607 Butterfly D-7 O ST/OC FCV-610 2" MO Clobe H-5 2 B C 3 months NA ST/OC FCV-611 C-5 C ST/OC CV-1782 3/4" AO Clobe H-7 2 B C 3 months NA ST/C CV-1783 B-6 C ST/C MO-8700A 14" MO Cate F-3 2 B O 3 months NA ST/OC MO-8700B E-3 O ST/0C MO-8701 14" MO Cate E-2 1 A C Cold shutdown 2 years 4.7. 4.11 ST/C MO-8702 E-2 C ST/C MO-8703 12" MO Cate B-2 2 B C 3 months NA ST/OC
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PSV-8708 3" Safety E-3 2 C C 5 years NA PSV-8709 3/4" Safety B-3 2 C C 5 years NA MO-8716A 8" MO Cate F-7 2 B O 3 months NA ST/OC i MO-8716B D-7 O ST/OC l 8730A 8" Check F-4 2 C C 3 months NA 4.8
! 8730B D-4 C 1
8736A 8" Check C-2 1 AC C Cold shutdown Cold shutdown 4.7, 4.10 8736B B-2 C and refueling 4 _
I
TABLE 4.1-1 Sheet 7 of 34' INSERVICE TESTING PROCRAft FOR VALVES s
SYSTEM: Residual Heat Removal P&ID NO: M-205 ASME Valve Valve Dwg Code Sect XI Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Conments Testing MO-8804A 8" MO Gate G-7 2 B C Cold shutdown NA 4.7 ST/OC MO-8804B B-7 C ST/OC MO-8809A 8" MO Cate C-7 2 B O Cold shutdown NA 4.7 ST/O ;
MO-8809B C-7 O ST/O MO-8811A 14" MO Cate G-3 2 B C 3 months NA ST/OC j l MO-8811B D-3 C ST/OC l MO-8812 14" MO Cate E-4 2 A O Cold shutdawn 2 years 4.7, 4.9 ST/C i
8818A 6" Check G-8 1 AC C Cold shutdown Cold shutdown 4.7, 4.10 8818B G-8 C and refueling 8818C C-8 C 8818D C-8 C PSV-8856A 2" Safety G-7 2 C C 5 years NA PSV-8856B C-7 C 8958 14" Check E-3 2 C C Refueling NA 4.7 1
9 TABLE 4.1-1 Sheet 8 of 34 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Safety Injection P&ID NO: M-206 ASME Valve Valve Dwg Code Sect KI Noru Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Comments Testing
.MO-8801A 4" MO Cate D-6 2 B C Cold shutdown NA 4.7 ST/O MO-8801B D-6 C ST/O MO-8802A 4" MO Cate B-6 2 B C 3 months NA ST/OC MO-8802B A-6 C ST/OC MO-8806 8" MO Cate C-2 2 B O Cold shutdown NA 4.7 ST/O MD-8807A 6" MO Gate C-2 2 B C 3 months NA ST/OC MO-8807B C-2 C ST/OC MO-8808A 10" MO Cate F-7 1 B O Cold shutdown NA 4.7 ST/OC MO-8808B F-6 O ST/OC MO-8808C F-4 O ST/OC MO-8808D F-3 O ST/OC MO-8813 2" MO Clobe F-2 2 B O Cold shutdown NA 4.7 ST/OC MO-8814 O ST/OC 8815 3" Check E-7 1 C C Cold shutdown NA 4.7 8819A 2" Check D-8 1 AC C Cold shutdown Cold shutdown 4.7, A.10 8819B C-8 C and refueling 8819C C-8 C 8819D C-8 C
TABLE 4.1-1 Sheet 9 of 34 INSERVICE TESTINC PROGRAM FOR VALVES SYSTEM: Safety Injection P&ID NO: M-206 ASME Valve Valve Dwg Code Sect II Norin Test Frequency ID No. Description Loc class Cat. Pos Exercise Leakage Conuments Testing MD-8821A 4" MO Cate B-5 2 B O 3 months NA ST/0 MO-8821B B-5 0 ST/0 NO-8835 4" MO Cate C-6 2 B 0 Cold shutdown NA 4.7 ST/0 PSV-8851 3/4" Safety B-5 2 C C 5 years NA PSV-8852 E-6 C 5 years NA PSV-8853A B-5 C 5 years NA PSV-88538 B-5 C 5 years NA PSV-8S'5A 1" Safety C-7 2 C C 5 years NA PSV-88558 C-6 C PSV-8m55C C-4 C PSV-8855D G-3 C ,
PSV-8858 3/4" Safety B-2 2 C C 5 years NA
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5 TABLE 4.1-1 Sheet 11 of 34 INSERVICE TESTING PROCRAM FOR VALVES
) ID No. Description Loc Class Cat. Pos Exercise Leakage Conunents Testing 8926 8" Check B-2 2 C C 3 months NA 4.8 8956A 10" Check F-7 1 AC C Refueling 2 years 4.7 8956B F-6 C l
8956C F-4 C 8956D F-3 C l
CV-8964 3/4" AO Clobe E-2 2 A C 3 months 2 years 4.9 ST/C l
8968 1" Check H-7 2 AC C NA 2 years 4.5, 4.9 j
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t TABLE 4.1-1 Sheet 12 of 3'4 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Containment Spray P&ID NO: M-207 ASME Valve Valve Dwg Code Sect II Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Coments Testing 2-CCB-9 2" Check E-4 2 C C 3 months NA 2-CCB-9 D-4 C 10-HCB-9 10" Check C-7 2 C C Refueling NA 4.7 10-HCB-9 C-7 C 14-HCB-14 14" Check F-3 2 C C 3 months NA 4.8 14-HCB-14 C-2 C MO-2052A 14" MO Cate F-3 2 B C 3 months NA ST/OC i MO-2052B C-2 C ST/OC MO-2053A 10" MO Cate C-7 2 B C 3 months NA ST/O MO-2053B C-7 C ST/O
]
MO-2056A 2" MO Globe D-4 2 B C 3 months NA ST/O MO-2056B D-4 C ST/O MO-2069A 18" MO Gate D-2 2 B O 3 months NA ST/O
. MO-2069B D-2 O PSV-2078 1-1/2" Safety F-5 2 C C 5 years NA PSV-2084 2" Safety E-5 2 C C 5 years NA i
PSV-2085 2" Safety E-5 2 C C 5 years HA l
~
TABLE 4.1-1 Sheet 13 of 34' INSERVICE TESTINC PROGRAM FOR VALVES SYSTEM: Main Steam P&ID NO: M-208' i
ASME Valve Valve Dwg Code Sect XI Norm Test Frequency l ID No. Description Loc Class Cat. Pos Exercise
- Leakage Comments Testing i
i CV-2210 6" AO Clobe H-3 2 B C Cold shutdown NA 4.7 ST/0C PSV-2211 6" Safety H-3 2 C C 5 yearc NA PSV-2212 H-3 C PSV-2213 H-3 C PSV-2214 H-2 C PSV-2215 H-2 C CV-2216 28" A0 Check H-2 2 BC 0 Cold shutdown NA 4.7 ST/C CV-1451 3" A0 Cate G-2 2 B C 3 months NA ST/0 CV-1452 E-3 C ST/0
- CV-1453 D-3 C ST/0 l CV-1454 C-2 C ST/O i CV-2230 6" A0 Globe F-3 2 B C Cold shutdown NA 4.7 ST/0C PSV-2231 6" Safety F-3 2 C C 5 years NA PSV-2232 F-3 C PSV-2233 F-3 C PSV-2235 F-2 C PSV-2235 F-2 C I
TABLE 4.1-1 Sheet 14 of 34 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Main Steam P&ID NO: M-208 ASME Valve Valve Dwg Code Sect XI Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Conunents Testing CV-2236 28" AO Check F-2 2 BC 0 Cold shutdown NA 4.7 ST/C 1
CV-2250 6" AO Globe D-3 2 B C Cold shutdown NA 4,7 ST/OC I
PSV-2251 6" Safety D-3 2 C C 5 years NA PSV-2252 D-3 C PSV-2253 D-3 C PSV-2254 D-2 C j PSV-2255 D-2 C 28-EBB-1 28" Check C-1 2 C 0 Cold shutdown NA 4.7 28-EBB-1 D-1 4 28-EBB-1 F-1 28-EBB-1 H-1 CV-2256 28" AO Check D-2 2 BC 0 Cold shutdown NA 4.7 ST/C j CV-2270 6" AO Clobe C-3 2 B C Cold shutdown NA 4.7 ST/OC l PSV-2271 6" Safety C-3 2 C C 5 years NA i PSV-2272 C-3 C PSV-2273 C-3 C PSV-2274 C-2 C PSV-2275 C-2 C t
i
TABLE 4.1-1 Sheet 15 of 14 ,
INSERVICE TESTINC PROCRAM FOR VALVES ,
SYSTEM: Main Steam P&ID NO: M-208 ASME l Valve Valve Dwg Code Sect II Norm Test Frequency
! ID No. Description Loc Class Cat. Pos Exercise Leakage Comuments Testing CV-2276 28" A0 Check B-2 2 BC 0 Cold shutdown NA 4.7 ST/C CV-2277 3" A0 Globe C-2 2 B O 3 months NA ST/C l CV-2278 F-2 0 ST/C l CV-2279 D-2 O ST/C CV-2280 B-2 O ST/C
! CV-2294 1" AO Cate E-4 2 B 0 3 months NA ST/C l CV-2295 C-4 0 ST/C l CV-2296 A-4 0 ST/C CV-2297 G-3 0 ST/C 3-EBD-7 3" Check G-2 B31.1 C C 3 months NA 4.7 3-EBD-7 E-3 C l
3-EBD-7 D-3 C 3-EBD-7 C-2 C l
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TABLE 4.1-1 Sheet 16 of 34' INSERVICE TESTING PROGRAM FOR VALVES 4
SYSTEM: Main and Auxiliary Feedwater P&ID NO: M-213, Shtet 1 4
- j Valve Valve Dwg Code Sect II Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Conunents Testing 6-DBD- 5 6" Check C-8 B31.1 C C Cold shutdown NA 4.7 I
6-DBD-5 B-8 6-HBD-43 6" Check B-7 B31.1 C C 3 months NA 6-HBD-43 B-7 C 6-HBD-43 B-7 C 3 months NA 6-HBD-43 B-7 C 6-HFD-7 6" Check C-7 B31.1 C C 3 months NA MO-3045A 6" MO Cate B-7 B31.1 B C 3 months NA ST/0 MO-3045B B-7 C ST/0
! MO-3060B 6" MO C-7 B31.1 B C 3 months NA ST/0 Butterfly i
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TABLE 4.1-1 Sheet 18 of 34 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Auxiliarf Steam P&ID NO: M-214 ASME Valve Valve Dwg Code Sect II Norm Test Frequency
> ID No. Description Loc Class Cat. Pos Exercise Leakage Conenents Testing MO-3071 4" MO Globe B-4 B31.1 B C 3 months NA ST/0 MO-3170 B-4 0 ST/0 l
1 4
4 i
7 i
J i
I
TABLE 4.1-1 Sheet 19 of 34' INSERVICE TESTING PROGRAM FOR VALVES 4
SYSTEi Component Cooling Water P&ID NO: M-215 '
i e
ASME Valve Valve Dwg Code Sect II Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Coauments Testing MO-3210A 12" MO F-8 B31.1 B C 3 months NA ST/0
! MO-3210B Butterfly D-8 C ST/O 4 PSV-3251 2" Safety C-1 B31.1 C C 5 years NA PSV-3263 D-2 C 4
CV-3287 18" AO F-4 B31.1 B O 3 months NA ST/C CV-3288 Butterfly D-4 O ST/C MO-3290 14" MD C-4 2 B O Cold shutdown NA 4.7 ST/0 NO-3291 Butterfly G-4 O ST/O MO-3292 H-4 O ST/O MO-3293 14" MO G-8 B31.1 B C 3 months NA ST/O Butterfly MO-3294 6" MO Cate H-4 B31.1 B O Cold shutdown NA 4.7 ST/C J
1 MO-3295 8" MO D -5 B31.1 B O Cold shutdown NA 4.7 ST/C Butterfly MO-3296 4" MO Cate C-4 B31.1 B O Cold shutdown NA 4.7 ST/C l
MO-3300 6" MO Cate G-6 B31.1 B O Cold shutdown NA 4.7 ST/C i
CV-3303 18" AO E-1 B31.1 B O 3 months WA ST/C CV-3304 Butterfly E-1 0 ST/C MC-3319 8" MO C-6 B31.1 B O Cold shutdown NA 4.7 ST/C Butterfly
l .
TABLE 4.1-1 Sheet 20 of 34 INSERVICE TESTING PROGRAM FOR VALVES
! SYSTEM: Component Cooling Water P&ID NO: M-215 l
l ASME Valve Valve Dwg Code Sect II Norm Test Frequency ID No. DescelPtion Loc Class Cat. Pos Exercise Leakage Conuments Testing MD-3320 4" MO Cate B-6 B31.1 B O Cold shutdown NA 4.7 ST/C PSV-3323A 2" Safety F-7 B31.1 C C 5 years NA PSV-33238 C-7 C MO-3346 14" MO B-4 2 B O Cold shutdown NA 4.7 ST/O Butterfly l
l MO-3347 14" MO B-6 B31.1 B C 3 months WA ST/O Butterfly i
l PSV-3373 2" Safety F-2 B31.1 C C 5 years NA l PSV-3374 D-2 C l PSV-3392 F-2 C l
l 24-HBD-27 24" Check C-3 B31.1 C O 3 months NA 24-HBD-27 F-3 C 24-HBD-27 D-3 C 24-HBD-27 C-3 0 1/2-HBD-65 1/2" Check F-1 B31.1 C C 3 months NA 1/2-HBD-65 D-1 C ,
1-CBD-26 1" check F-1 B31.1 C 0 3 months NA 1-CBD-26 D-1 0 l
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o TABLE 4.1-1 Sheet 23 of 34 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Clean Radioactive Waste P&ID NO: M-220 ASME Valve Valve Dws Code Sect XI Norm Test Frequency ID 50. Description Loc Class Cat. Pos Exercise Leakage Conenents Testing CV-4000 1" AO Globe G-8 2 A 0 3 months 2 years 4.9 ST/C MO-4005 3" MO Cate F-7 2 A O 3 months 2 years 4.9 ST/C CV-4006 3" AO Cate F-7 2 A O 3 months 2 years 4.9 ST/C 1-CBB-1 1" Check G-8 2 AC C NA 2 years 4.5, 4.9 l
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TABLE 4.1-1 Sheet 24 of 34' i
INSERVICE TESTING PROGRAM FOR VALVES OYSTEN: Dirty Radioactive Waste P&ID NO: M-221 .
ASME Valve Valve Dwg Code Sect II Norm Test Frequency J
ID No. Description Loc Class Cat. Pos Exercise Leakage Conenents Testing MO-4180 3" MO Gate H-8 2 A C 3 months 2 years 4.9 ST/C CV-4181 3" A0 Gate H-8 2 A C 3 months 2 years 4.9 ST/C i
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TABLE 4.1-1 Sheet 26 of 34 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Instrument and Service Air P&ID NO: M-223 ASME Valve Valve Dwg Code Sect XI Noun Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Conunents Testing CV-4470 2" A0 Globe D-1 2 A C 3 months 2 years 4.9 ST/C CV-4471 2" A0 Globe F-1 2 A O Refueling 2 years 4.7, 4.9 ST/C 2-HBE-8 2" Check F-1 2 AC 0 Refueling 2 years -4.!, 4.9 2-HBE-9 2" Check D-1 2 AC C NA 2 years 4.5, 4.9 j
TABLE 4.1-1 Sheet 27 of 34' INSERVICE TESTING PROCRAM FOR VALVES-SYSTEM: Diesel Fuel Oil P&ID NO: M-226
, ASME I Valve Valve Dwg Code Sect XI Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Comments Testinr, MO-4903A 3" MO Gate F-5 B31.1 B C 3 months NA ST/O MO-4903B D-5 C ST/O MO-4907A 2" MO Clobe C-6 B31.1 B C 3 months NA ST/D MO-4907B B-6 C ST/O 3-HBD-72 3" Check F-7 B31.1 C C 3 months NA 3-HBD-72 D-7 C i
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l i
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1
TABLE 4.1-1 Sheet 28 of 34 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Spent Fuel Pool Cooling P&ID NO: M-227 ASME Valve Valve Dwg Code Sect XI Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Comments Testing SF-046 8" Cate F-2 2 A C NA 2 years 4.5, 4.9 SF-062 3" Gate E-2 2 A C NA 2 years 4.5, 4.9 4
SF-063 E-2 SF-073 10" Gate B-2 2 A C NA 2 years 4.5, 4.9 SF-074 B-2 C SF-080 8" Gate F-2 2 A C NA 2 years 4.5, 4.9 CV-5075 4" AO Cate A-6 3 B C 3 months NA ST/C CV-5076 A-6 C ST/C
O TABLE 4.1-1 Sheet 29 of*34 INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Makeup Water Treatment P&ID NO: M-228 f
ASME Valve Valve Dwg Code Sect XI Norm Test Frequency ID No. Description Loc Class Cat. Fos Exercise '
Leakage Comments Testing MD-059 3" Manual F-1 2 A C NA 2 years 4.5, 4.9 Cate 3-HCB-3 3" Check F-1 2 AC C NA 2 years 4.5, 4.9 I
l
I 1
- l l
TABLE 4.1-1 Sheet 30 of 34 INSERVICE TESTING PROGRAM FOR VALVES a
f SYSTEM: Sampling P&ID NO: M-231, Sheet 1 ASME Valve Valve Dwg Code Sect XI Norm Test Frequency i ID No. Description Loc Class Cat. Pos Exercise Leakage ' Conunents Testing CV-2809 3/4" AO Globe H-6 2 B O 3 months NA ST/C CV-2811 H-7 0 ST/C CV-2814 H-6 O ST/C CV-2880 H-7 O ST/C MO-5651A 3/4" MO Globe H-4 2 A C 3 months 2 years 4.9 ST/C MO-5651B H-4 C ST/C MO-5651C H-4 C ST/C MO-5651D H-4 C ST/C CV-5652 3/4" AO Globe G-4 2 A C 3 months 2 years 4.9 ST/C MO-5653 3/4" MO Globe H-6 2 A C. 3 months 2 years 4.9 ST/C MO-5654 H-5 C ST/C 4
CV-5655 3/4" AO Globe G-5 2 A C 3 months 2 years 4.9 ST/C MO-5656 3/4" MO Globe H-5 2 A C 3 months 2 years 4.9 ST/C I
CV-5657 3/4" AO Globe G-5 2 A C 3 months 2 years 4.9 ST/C MO-5658 3/4" MO Clobe H-5 2 A C 3 months 2 years 4.9 ST/C CV-5659 3/4" AO Globe G-5 2 A C 3 months 2 years 4.9 ST/C MO-5660 3/4" MO Globe C-6 2 A O 3 months 2 years 4.9 ST/C CV-5661 3/4" AO Globe B-6 2 A O 3 months 2 years 4.9 ST/C
TABLE 4.1-1 Sheet 31 of 34 j INSERVICE TESTING PROCRAM FOR VALVES I
i SYSTEM: Containment Ventilation P&ID NO: M-243 ASME l Valve Valve Dwg Code Sect XI Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Comments Testing SV-5642 3/4" Solenoid F-7 2 A C 3 months 2 years 4.9 ST/C
, SV-5643 E-7 C ST/C 3 MO-5663 1" MO Globe E-7 2 A 0 3 months 2 years 4.9 ST/C MO-5671 E-7 O ST/C MO-5672 E-6 0 ST/C MO-5673 E-7 0 ST/C MO-5674 E-7 C ST/C MO-5675 F-7 C ST/C MO-5676 E-7 C ST/C MO-5677 F-8 C ST/C MO-5678 E-8 C ST/C
! SV-5679 3/4" Solenoid E-7 2 A C 3 months 2 years 4.9 ST/C CV-10001 54" A0 D-2 2 A C Cold shutdown 2 years 4.7, 4.9 ST/C Butterfly ST/C.
I MO-10002 54" MO D-2 2 A C Cold shutdown 2 years 4.7, 4.9 ST/C MO-10003 Butterfly D-7 C ST/C CV-10004 54" AO D-7 2 A C Cold shutdown 2 years 4.7, 4.9- ST/C Butterfly 4
TABLE 4.1-1 Sheet 32 of*34 INSERVICE TESTING PROCRAM FOR VALVES SYSTEM: Contcinment Ventilation P&ID NO: M-243 ASME Valve Valve Dwg Code Sect XI Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Connents Testing MO-10005 8" MO C-2 2 A C 3 months 2 years 4.9 ST/C MO-10006 Butterfly C-2 C ST/C MO-10007 C-2 C ST/C MO-10008 C-2 C ST/C MO-10009 8" MO C-7 2 A C 3 months 2 years 4.9 ST/C.
MO-10010 Butterfly C-7 C ST/C MO-10011 C-7 C ST/C MO-10012 C-7 C ST/C 10610A 3/4" Gate D-7 2 A C NA 2 years 4.5, 4.9 10610B D-7 C 10611A C-7 C 10611B C-7 C
. . - - = - . . . .
d.
TABLE 4.1-1 Sheet 33 of 34 INSERVICE TESTING PROGRAM FOR VALVES I SYSTEM: Chilled Water P&ID NO: M-248 ASME Valve Valve Dwg Code Sect XI Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Comments Testing 1
MO-10013 4" MO B-4 2 A O 3 months 2 years 4.9 ST/C Butterfly CV-10014 4" AO B-4 2 A O 3 months 2 years 4.9 ST/C CV-10015 Butterfly B-4 O ST/C MO-10016 4" MO B-4 2 A O 3 months 2 years 4.9 ST/C Butterfly i
i
TABLE 4.1-1 Sheet 34 of 34' INSERVICE TESTING PROGRAM FOR VALVES SYSTEM: Steam Generator Blowdown P&ID NO: M-348 ASME Valve Valve Dws Code Sect II Norm Test Frequency ID No. Description Loc Class Cat. Pos Exercise Leakage Coments Testing MO-2808 2" MO Cate F-7 2 B O 3 months NA ST/C MO-2810 H-5 O ST/C i
MO-2812 G-7 O ST/C MO-2813 G-6 O ST/C MO-6716 2" MO Globe H-8 2 B O 3 months NA ST/C MO-6717 G-8 0 ST/C MO-6718 G-8 O ST/C MO-6719 F-8 O ST/C i
i l
i i
A0W/mc 5834k i
TABLE 4.1-2 Sheet 1 of 25 FULL-STROKE EXERCISED VALVES The following Category A, B. and C active valves cannot be exercised during Plant operation and will be full-stroke exercised during cold shutdowns as per Paragraphs IWV-3412 and -3522 or during refueling outages as indicated by relief requests.
M-201: Reactor Coolant System A. Vo l.ves : SV-1015A, SV-1015B, SV-1016A, and SV-1016B Category: B Class: 2 Function: These valves are solenoid-operated isolation valves for the reactor vessel head vent lines. They permit venting of the reactor vessel head under abnormal conditions.
Test Requirement: Exercise for operability every three months during Plant operation or during cold shutdown if the valves cannot be exercised during Plant operation.
Basis for
Conclusion:
Operation of these valves while the RCS is under pressure could result in venting primary coolant to the Containment atmosphere.
TABLE 4.1-2 Sheet 2 of 25 Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
B. Valves: 8900A, 8900B, 8900C, 8900D Category: C Class: 1 Function: Each of these check valves prevents backflow from its respective RCS cold les into the boron injection tank (BIT) during normal operation and allows flow from the BIT to the RCS during safety injection.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Exercising these valves would require injec-tion of the contents of the BIT into the RCS.
While the RCS is at normal operating pressure the centrifugal charging pump (CCP) cannot develop check valve design flow.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown at reduced RCS pressures where adequate flow can be obtained.
C. Valves: 8948A, 8948B, 8948C, 8948D Category: AC Class: 1
TABLE 4.1-2 Sheet 3 of 25 Function: Each of these check valves prevents backflow from its respective RCS cold leg and sequentially allows flow from the SIS accumulators, the SIS pump discharge, and the RHR System during safety injection.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Exercising of these valves would require injection of concentrated boric acid into the RCS, causing a power transient that could result in a reactor trip. During power opera-tion, the SIS accumulators, SIS pumps, and RHR pumps cannot overcome RCS pressure to achieve check valve design flow.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown using RHR pump flow.
D. Valves: 8949A, 8949B, 8949C, 8949D Category: AC Class: 1 Function: Each of these check valves prevents backflow from its respective RCS hot leg to the safety injection pump and RHR pump discharge during normal operation and allows flow for hot-leg recirculation during accident conditions.
Test Requirement: Exercise for operability every 3 months.
1 l
TABLE 4.1-2 Sheet 4 ci 25 Basis for
Conclusion:
During power operation the safety injection and RHR System pumps cannot overcome RCS pressure.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
E. Valves: PCV-455A and PCV-456 Category: B 1
Class: 1 Function: These valves prevent reactor pressure from activating the high-pressure reactor trip or from reaching the setpoint of the code safety valves. During periods of reduced RCS temperature (1290*F), these valves are used in the over-pressure mitigation system to prevent brittle fracture.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Testing these valves every 3 months increases the number of times each valve must open against design RCS pressures in excess of 2000 psig, thus deteriorating the valve seat and increasing the likelihood of damaging the valve seat and causing leakage. In addition, these valves are not given credit in the design accident analysis, and since the Plant can operate without them, if they were to fail, they can be adequately isolated by the block valves (MO-8000A and B).
Alternate Testing: These valves will be full-stroke exercised at i
1 cold shutdown.
TABLE 4.1-2 Sheet 5 of 25 M-202: ChemicIl and Volume Control System Valve: 8546 Category: C Class: 2 Function: This check valve prevents backflow of water from the volume control tank (VCT) to the RWST during normal operation arid allows flow from the RWST to the CCP suctions during safe shutdown.
Test Requirement: Exercise for operability every 3 months.
Basis for conclusion: Exercising of this valve would require injection of concentrated boric acid from the RWST into the RCS, causing a power transient which could result in a reactor trip.
Alternate Testing: This valve will be full-stroke exercised for verification of operability during cold shutdown.
TABLE 4.1-2 Sheet 6 of 25 l
1 M-203: Chemical and Volume Control System A. Valves: MO-8100 and MO-8112 Category: A Class: 2 Function: These normally open Containment isolation valves close on a Containment isolation signal to isolate the RCP seal water return.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Failure of either of these valves in a closed pcsition would result in loss of seal leakoff flow.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown when the RCPs are shut down.
B. Valves: MO-8110 and MO-8111 Category: B Class: 2 Function: These series valves isolate CCP recirculation flow path return to the seal water heat exchanger.
Test Requirement: Exercise for operability every 3 months.
TABLE 4.1-2 Sheet 7 of 25 Basis for
Conclusion:
Failure of either of these valves in the closed position renders the recirculation flow path inoperable. A minimum flow rate through the pumps is required to ensure pump cooling.
A safety injection actuation while either valve is in the closed position could cause damage to both trains of high head safety injection if the RCS pressure increases above the discharge head of the CCP.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
M-205: Residual Heat Removal System A. Valves: MO-8701 and MO-8702 Category: A Class: 1 Function: These normally closed series valves connect the suction of 1
the RHR pumps to the RCS Loop 4 hot leg. These valves are interlocked to prevent opening with RCS pressure >425 psig 1 and to automatically close when RCS pressure exceeds 600 psig.
Test Requirement: Exercise for operability every 3 months.
t
TABLE 4.1-2 Sheet 8 of 25 Basis for
Conclusion:
Exercising of.these valves during normal operation would require overriding cf a safety interlock. The potential for overpressuriza-tion of the RNR System and depressurization of the RCS make testing of these valves at normal RCS pressure unsafe.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
B. Valves: 8736A, 8736B Category: AC Class: 1 ,
Function: These check valves prevent backflow from the RCS Loops 2 and 4 hot legs into the RHR System during normal operation.
Test Requirement: Exercise for operability every 3 months.
Basis for Concittsion: During normal operation, the RHR pumps cannot overcome RCS pressure to achieve check valve design flow.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
TABLE 4.1-2 Sheet 9 of 25 C. Valves: MO-8804A and MO-8804B Category: B .
1 Class: 2 Function: These valves are used during RCS cold- and hot-leg recirculation where the RHR pump discharge is aligned to provide flow to the suction of the CCPs and safety injection pumps.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
These valves are interlocked with the safety injection pump recirculation flow isolation valves (MO-8813 and MO-8814) which are exer-cised on a cold shutdown frequency. Cycling these valves during power operation would require defeating the safety interlock.
Alternate Testing: These valves will be full-stroke exercised during cold shutdown with MO-8813 and MO-8814.
D. Valves: MO-8809A and MO-89093 Category: B Class: 2 Function: These valves are aligned to provide RCS cold-leg injection flow from the RHR system.
Test Requirement: Exercise for operability every 3 months.
I
- = .
1 TABLE 4.1-2 Sheet 10 of 25 '
l Basis for
Conclusion:
These valves are required to be in the open position to meet the flow assumptions in the accident analysis. Failure of either of these valves in the closed position or safety injec-tion actuation while in the closed position could result in low head safety injection flow at rate below that assumed in the safety analysis.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
E. Valve: MO-8812 Category: B Class: 2 Function: This no mally open valve is repositioned to isolate the RWST from the RHR pump suction during the accident recirculation phase.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Failure of this valve in the closed position would render the entire RHR System inoperable.
Alternate Testing: This valve will be full-stroke exercised for verification of operability during cold shutdown.
TABLE 4.1-2 Sheet 11 of 25 F. Valves: 8818A, 8818B, 8818C, 8818D Category: AC Class: 1 Function: Each of these check valves prevents backflow from one of the RCS cold legs into the RHR System during normal opera-tion and allows flow from the RHR System into the RCS dur-
- ing cooldown, injection phase and cold-leg recirculation phase of accident mitigation.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
During normal operation, the RHR pumps cannot overcome RCS pressure.
f Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
G. Valve: 8958 -
Category: C Class: 2 runction: This check valve prevents backflow from RHR suction header to the RWST.
Test Requirement: Exercise for operability every 3 months.
l 1
TABLE 4.1-2 Sheet 12 of 25 l l
Basis for
Conclusion:
Exercising this valve requires the RHR pumps drawing suction on the RWST. Operating modes l l
do not allow this because there is no place to store the water unless initiating large scale RWST recirculation (opening manual valve 8735).
However, this is not feasible due to the RHR System operating in a degraded condition.
Cold shutdown is not feasible because the RHR is in circulation to the RCS using the RCS as a suction source. The only fessible Plant condition for which this valve can be exer-cised is during refueling when the RHR System is utilized to fill the refueling cavity.
Relief Request: This valve will be full-stroke exercised during refueling outages when the refueling cavity is being filled.
M-206: Safety Injection System A. Valves: MO-8801A and MO-8801B Category: B Class: 2 Function: These normally closed parallel valves isolate the BIT during normal operation and open on a safety injection actuation to provide high head Emergency Core Cooling System flow to the RCS cold legs from the CCPs.
, TABLE 4.1-2 Sheet 13 of 25 Basis for Ccnclusion: Opening either of these two valves would divert flow from the normal RCS charging and RCP seal injection and flush the contents of the BIT into the RCS. Isolating the BIT inlet valves (normally open MO-8803A and MO-8803B) is not considered feasible should a safety injection actuation occur while testing, since these valvec do not receive a signal to reposition. This condition could result in loss of both trains of high head safety injection and flow less than that assumed in the safety analysis.
Alternate Testing: Full-stroke exercise for verification of operability during cold shutdown.
B. Valves: MO-8806 and MO-8835 Category: B Class: 2 Function: These normally open valves isolate the RWST from the safety injection purap suction (MO-8806) and the cold-leg safety injection into the RCS (MO-8835).
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Failure of either valve in the closed position would render both trains of safety injection pumps inoperable.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
o ,
TABLE 4.1-2 Sheet 14 of 25 C. Valves: MO-8808A, MO-8808B, MO-8808C, MO-8808D Category: B Class: 1 .
Function: These normally open valves provide isolation for the SIS accumulators. The valves are also designed to open on receipt of a safety injection signal.
Test Requirement: Exercise for operability every 3 months.
~
Basis for
Conclusion:
These valves are passive in that, under normal operating conditions, they are open and remain open in performance of their safety function.
The valves have been included in the IST program for testina due to their critical location in a safety-related system and the imposed administrative requirements which require Plant shutdown for failure of one of these valves in a closed position.
Alternate Testing: Exercise for verification of operability during cold shutdown.
D. Valves: MO-8813 and MO-8814 Category: B Class: 2 Function: These normally open series valves isolate the safety injection pump miniflow return flow path to the RWST.
TABLE 4.1-2 Sheet 15 of 25 Basis for
Conclusion:
Failure of either valve in a closed position or safety injection actuation while closed would render the safety injection pumps inoperable. A minimum flow cate through the pumps is required to ensure pump cooling. The miniflow flow path guarantees this minimum flow during the safety injection initiation.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
E. Valve: 8815 Category: C Class: 1 Function: This check valve prevents backflow from the RCS cold legs into the BIT during normal optration and allows CCP high head injection via the BIT during a safety injection.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Exercising of this valve would require injec-tion of the BIT into the RCS. At normal RCS pressure, check valve design flow cannot be achieved.
Alternate Testing: This valve will be full-stroke exercised for verification of operability during cold shutdown, i
I
9 TABLE 4.1-2 Sheet 16 of 25 F. Valves: 8819A, 8819B, 8819C 8819D Category: AC Class: 1 Function: Each of these check valves prevents backflow from its respective RCS loop cold leg and allows flow from the discharge of the safety injection pumps during RCS cold-leg injection and recirculation.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
During power operation, the safety injection pumps cannot overcome RCS pressure to achieve check valve design flow.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
G. Valves: 8905A, 8905B, 8905C, 8905D Category: AC Class: 1 Function: Each of these check valves prevent backflow from its respective RCS loop hot leg and allows flow from the dis-charge of the safety injection pumps during RCS hot-leg recirculation.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
During power operation, the safety injection 1
l pumps cannot overcome RCS precsure to achieve check valve design flow.
TABLE 4.1-2 Sheet 17 of 25 Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
H. Valves: 8922A and 8922B Category: C Class: 2 Function: Check valves 8922A and 8922B are on the discharge of the safety injection pumps downstream of the recirculation return to the RWST and prevent backflow through the respective pump.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
The safety injection pumps cannot overcome RCS pressura during power operation and, as a result, check valve design cannot be achieved.
Alternate Testing: Valves 8922A and 8922B will be full-stroke exercised for verification of operability during .
cold shutdown.
I. Valves: 8956A, 8956B, 8956C, and 8956D Category: AC Class: 1 Function: These normally closed check valves prevent backflow from the RCS into the accumulatora during normal operation.
Test Requirement: Exercise for operability every 3 months.
TABLE 4.1-2 Sheet 18 of 25 Basis for
Conclusion:
During normal operation. the accumulator cannot overc ome RCS pressure. Full-stroke testing is not feasible during cold shutdowns due to limited Plant conditions for testing which require discharging the accumulators into the open reactor vessel during refueling.
Relief Request: These valves will be full-stroke exercised during refueling outages when the reactor pressure vessal is open.
M-207: Containment Spray System A. Valves: 10-HCB-9 (two)
Category: C Class: 2 Function: These check valves prevent backflow of air from the Containment atmosphere through the Containment spray ring header.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
These valves do not have provision for testing under normal conditions. Exercising the valves would require injection of the test medium into the Containment through the spray nozzles with no means available for verifica-tion of flow. Equipment damage and require-ments for extensive cleanup of the Containment would result.
- o. ,
TABLE 4.1-2 Sheet 19 of 25 Relief Request: During refueling outage, these valves will be partially disassembled and the disc will be manually moved through a full stroke. f M-208: Main Steam System l
l A. Valves: CV-2210, CV-2230, CV-2250, and CV-2270 l Category: B Class: 2 Function: These valves prevent reaching the safety valve setpoint during transients and dissipate reactor decay heat to the atmosphere if the main condenser is not available.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Testing these valves every 3 months increases j
the normal number of times each valve opens against a differential pressure, thus deteriorating the valve seat and increasing the likelihood of causing leakage.
Alternate Testing: These valves will be full-stroke exercised during cold shutdova.
B. Valves: CV-2216, CV ' 25 CV 256, CV-2276 Category: BC Class: 2
TABLE 4.1-2 Sheet 20 of 25 Function: These valves provide main steam isolation in each of the respective main steam headers.
l Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Shutting of one of these valves during full-power operation would result in a transient which would lead to a reactor trip and/or a steam dump to atmosphere. Repeated closure of these valves at full power will reduce their reliability. Failure of a valve
- in the closed position would remove its I
respective steam generator from operation.
l Alternate Testing: These valves will be exercised for verification of operability while in startup or hot standby during each reactor shutdown or subsequent startup, except that this test need not be performed more often than once per 92 days.
Operability will be demonstrated by closure within 5 see on a closure activation signal.
C. Valves: 28-EBB-1 (four)
Category: C Class: 2 Function: These check valves perform an accident-related function in that they are required to close in the event of a steam line break in containment in order to prevent blowing down of more than one steam generator to Containment.
Test Requirement: Exercise for operability every 3 months.
~o ,
TABLE 4.1-2 Sheet 21 of 25 I
Basis for
Conclusion:
During normal operation, the main steam pressure cannot be overcome, and as a result the valves cannot be exercised.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during recovery from cold shutdown.
M-213: Main and Auxiliary Feedwater System A. Valves: 2-CCC-CK, 3-DBE-3, 3-EBE-3, and 6-DBD-5 i
i Category: C Class: 2 and ANSI B31.1 Function: These check valves prevent backflow from the main feed lines to the AFW System during normal operation.
Test Requirement: Exercise for operability every 3 nonths.
Basis for
Conclusion:
These valves cannot be exercised during power operation without thermal shocking of the feed system nozzles.
I Alternate Testing: These valves will be full-stroke exercised during ,
1 cold shutdown. j l
B. Valves: 14-EBE-3 (four)
Category: C Class: 2 I
I i
- e 1 TABLE 4.1-2 Sheet 22 of 25 l i
l Function: These check valves prevent backflow from the steam generators into the main feed system.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Shutting of one of these valves during full-power operation would result in a transient which could lead to a reactor trip.
Repeated closure of these valves at full power will reduce their reliability.
Alternate Testing: This valve will be full-strcke exercised during cold shutdown.
M-215: Component Coolina Water System A. Valves: MO-3290, MO-3291, MO-3292, MO-3294, MO-3296, MO-3300, MO-3320. NO-3346 Category: B Class: 2 (MO-3290, MO-3291, MO-3292, MO-3346) and ANSI B31.1 (MO-3294, MO-3296, MO-3300, MO-3320)
Function: These normally open valves are on the supply and return lines of the CCW supply to containment and the RCPs.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Failure of one of these valves in the closed position would result in loss of cooling water to the RCPs.
TABLE 4.1-2 Sheet 23 of 25 Alternate Testing: These vs.lves will be full-stroke exercised for verification of operability at cold shutdown.
B. Valves: MO-3295 and MO-3319 Category: B Class: ANSI B31.1 Function: These are the inlet and outlet isolation valves on the letdown and seal water heat exchangers. The valves are normally open and close on receipt of a Containment isolation signal.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Failure of either of these valves in the closed position would result in loss of cooling water to the RCS letdown and the RCS pump neal water heat exchangers requiring reactor shutdown.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
M-223: Instrument Air System A. Valves: CV-4471 and 2-HBE-8 Category: A and AC, respectively Class: 2
TABLE 4.1-2 Sheet 24 of 25 Function: These normally open series Containment isolation valves are the instrument air supply to pneumatic valves and instrumentation inside Containment. The valves close on receipt of a containment isolation signal.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Failure of either of the instrument air valves in a closed position removes the air supply to the Containment air-operated valves and pneumatic instrumentation. Valve 2-HBE-8 can only be verified shut during leak testing at refueling outages.
Relief Request: CV-4471 will be full-stroke exercised during refuel-ing. Check valve 2-HBE-8 will be full-stroke exer-cised for verification of operability during local leak rate testing per 10 CFR 50, Appendix J.
M-243: Containmont Ventilation System A. Valves: CV-10001, MO-10002, MO-10003, CV-10004 Category: A Class: 2 Function: These valves are the Containment isolation valves for the main Containment purge system.
Test Requiremant: Exercise for operability every 3 months.
-- - - - . . - - . - - - - . _ . - - , - - - - - - - - - , - - , -, -.r--- r-- -
TABLE 4.1-2 Sheet 25 of 25 Basis for conclusion: PGE has committed to maintaining these valves in the closed position during Modes 1, 2, 3, and 4 in response to an NRC concern over Containment purging during normal operation.
Alternate Testing: These valves will be full-stroke exercised during cold shutdown.
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o TABLE 4.1-3 Sheet 1 of 4 PART-STROKE EXERCISED VALVES The following Category A, B, and C active valves, where only limited operation is practical during Plant operation, will be part-stroke exercised during Plant operations and full-stroke exercised during cold shutdowns as per Paragraphs IWV-3412 and -3522.
M-202: Chemical and Volume control System A. Valves: 8481A and 8481B Category: C Class: 2 Function: Each of these check valves is on the discharge of a CCP and prevents backflow.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
During power operation, the charging flow path cannot accommodate full flow except through the BIT, which would require injection of boric acid into the RCS, causing a power transient that could result in a reactor trip.
Alternate Testing: These valves will be part-stroke exercised at power every 3 months and full-stroke exercised at cold shutdown.
.'e
- t e TABLE 4.1-3 Sheet 2 of 4 PART-STROKE EXERCISED VALVES M-205: Residual Heat Removal System A. Valves: 8730A and 8730B Category: C Class: 2 Function: These check valves are on the discharge of the RHR pumps and prevent backflow through their respective pump.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
During power operation, the RHR pumps cannot overcome RCS pressure to achieve check-valve design flow. The only alternate flow path which can accommodate full flow is on recirculation to the RWST. This flow path is unacceptable because it would require repositioning of the RWST return isolation valve, 8735 (normally locked closed), which would render the RHR injection system inoperable.
Alternate Testing: Check valves 8730A and 8730B will be part-stroke exercised on miniflow during power operation and full-stroke exercised during cold shutdown.
o
- e ,
TABLE 4.1-3 Sheet 3 of 4 PART-STROKE EXERCISED VALVES M-206: Safety Injection System A. Valves: 8926 Category: C Class: 2 Function: Check valve 8926 is between the safety injection pumps suction and the RWST and prevents backflow into the REST.
Test Requirement: Exercise for operability every 3 mcnths.
Basis for
Conclusion:
The safety injection pumps cannot overcome RCS pressure during power operation and, as a result, full flow cannot be accommodated.
Alternate Testin5: Check valve 8926 will be part-stroke exercised during power operation and full-stroke exercised for verification of operability during cold snutdown.
M-207: Containment Spray System A. Valves: 14-HCB-14 (two)
Category: C Class: 2
4-
- c ,
TABLE 4.1-3 Sheet 4 of 4 pART-STROKE EXERCISED VALVES Function: These check valves prevent backflow into the RWST from the Containment spray suction header.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Full-stroke exercising of these valves during power operation would require injection of the test medium into the Containment in order to achieve design flow. Equipment damage and requirements for extensive cleanup of the Contain-ment would result. The alternate test method requires initiating check valve design flow using the RHR pump while discharging into the refueling cavity for flood-up in preparation for refueling.
Relief Request: These valves will be part-stroked every 3 months and full-stroke exercised during refueling outages. ,
I i
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