CP-202100150, (CPNPP) Units 1 & 2 - Inservice Testing Plan for Pumps & Valves Third Interval, Revision 4
ML21082A299 | |
Person / Time | |
---|---|
Site: | Comanche Peak ![]() |
Issue date: | 03/23/2021 |
From: | Hicks J Luminant |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
CP-202100150, TXX-21062 | |
Download: ML21082A299 (210) | |
Text
{{#Wiki_filter:I! Jack C. Hicks Manager, Regulatory Affairs Comanche Peak Nuclear Power Plant (Vistra Operations Company LLC) Luminant P.O. Box 1002 6322 North FM 56 Glen Rose , TX 76043 T 254.897 .6725 CP-202100150 TXX-21062 March 23, 2021 U. S. Nuclear Regulatory Commission Ref 10 CFR 50.55a ATIN: Document Control Desk Washington, DC 20555-0001
Subject:
Comanche Peak Nuclear Power Plant (CPNPP) Docket Nos. 50-445 and 50-446 CPNPP UNITS 1 & 2 INSERVICE TESTING PLAN FOR PUMPS & VALVES THIRD INTERVAL, REVISION 4
Dear Sir or Madam:
Pursuant to 10 CFR 50.55a, Vistra Operations Company LLC (Vistra OpCo) the operator of Comanche Peak Nuclear Power Plant Units 1 and 2 (herein referred to as CPNPP), herewith submits CPNPP Units 1 and 2 Inservice Testing Plan for Pumps and Valves, Third Interval, Revision 4 "For Information Only." The start date of the third interval of the Inservice Testing Plan for CPNPP, Units 1 and 2 is August 3, 2013 with an end date of August 2, 2023. Revision 4 was effective March 23, 2021 . This communication contains no new commitments regarding CPNPP Units 1 and 2. Should you have any questions, please contact Garry Struble at (254) 897-6628 or garry.struble@luminant.com.
TXX-21062 Page 2 of2 Sincerely,
Enclosure:
CPNPP Inservice Testing Plan, Third Interval, Revision 4 c (email) - Scott Morris, Region IV [Scott.Morris@nrc.gov] (CLO) Dennis Galvin, NRR [Dennis.Galvin@nrc.gov] John Ellegood, Senior Resident Inspector, CPNPP Uohn.Ellegood@nrc.gov] Neil Day, Resident Inspector, CPNPP [Neil.Day@nrc.gov]
COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 & 2 INSERVICE TESTING PLAN FOR PUMPS & VALVES THIRD INTERVAL ADDRESS: COMANCHE PEAK NUCLEAR POWER PLANT 6322 NORTH FM 56 GLEN ROSE, TEXAS 76043 COMMERCIAL DATES: UNIT 1 -AUGUST 13, 1990 UNIT 2 -AUGUST 3, 1993
CPNPP/IST COMANCHE PEAK NUCLEAR POWER PLANT INSERVICE TESTING PLAN FOR PUMPS & VALVES THIRD INTERVAL EFFECTIVE LISTING FOR SECTIONS, TABLES, AND FIGURES BELOW IS A LEGEND FOR THE EFFECTIVE LISTING OF SECTIONS, TABLES, AND FIGURES: Revision 0 August 3, 2013 Revision 1 February 24, 2014 Revision 2 February 26, 2015 Revision 3 October 31, 2019 Revision 4 March 23, 2021 CPNPP/IST EL-1 Revision 4
CPNPP/IST Table of Contents Revision 3 Section 1 Revision 0 Section 2 Revision 3 Table O Revision 0 Section 3 Revision 0 Valve Table Index Revision 4 Table 1 Revision 4 Table 2 Revision 4 Table 3 Revision 4 Table 4 Revision 4 Table 5 Revision 4 Table 6 Revision 4 Table 7 Revision 4 Table 8 Revision 4 Table 9 Revision 0 Table 10 Revision 4 Table 11 Revision 4 Table 12 Revision 0 Table 13 Revision 4 Table 14 Revision 4 Table 15 Revision 0 Table 16 Revision 3 Table 17 Revision 4 Table 18 Revision 4 Table 19 Revision 4 Appendix A Revision 4 EL-1 Revision 4 EL-2 Revision 4 Description of Changes Revision 4 EL-2 Revision 4 CPNPP/IST
CPNPP/IST Plan TABLE OF CONTENTS Page 1.0 GENERAL INFORMATION ......................................................................................... 1-1 1.1 lntroduction ...................................................................................................... 1-1 1.2 Code Edition and Addenda ............................................................................. 1-1 1.3 Dates of Test Interval ...................................................................................... 1-1 1.4 Approval Status ............................................................................................... 1-2 1.5 References ...................................................................................................... 1-3 2.0 INSERVICE PUMP TESTING PLAN .......................................................................... 2-1 2.1 Pump Testing Code .........................................................................................2-1 2.2 Scope ..............................................................................................................2-1 2.3 Pump Testing Table Format.. .......................................................................... 2-1 TABLE 0- INSERVICE PUMP TESTING PLAN 3.0 INSERVICE VALVE TESTING PLAN ......................................................................... 3-1 3.1 Valve Testing Code ......................................................................................... 3-1 3.2 Scope ..............................................................................................................3-1 3.3 Valve Testing Table Format ............................................................................3-2 3.4 References ...................................................................................................... 3-5 VALVE TABLE INDEX TABLE 1 -AUXILIARY FEEDWATER TABLE 2 - COMPONENT COOLING WATER TABLE 3 - CHILLED WATER (SAFETY & NON-SAFETY) TABLE 4 - CHEMICAL AND VOLUME CONTROL TABLE 5 - CONTAINMENT SPRAY TABLE 6- DEMINERALIZED & REACTOR MAKEUP WATER TABLE 7 - DIESEL GENERATOR AUXILIARIES TABLE 8 - FEEDWATER TABLE 9- MAIN STEAM TABLE 10- REACTOR COOLANT TABLE 11 - RESIDUAL HEAT REMOVAL TABLE 12 - SPENT FUEL POOL COOLING TABLE 13 - SAFETY INJECTION TABLE 14- SERVICE WATER TABLE 15 - VENTILATION (CONTROL ROOM AIR CONDITIONING) TABLE 16 - VENTS & DRAINS TABLE 17- MISCELLANEOUS CONTAINMENT ISOLATION VALVES TABLE 18- SAFETY & RELIEF VALVES TABLE 19- MOTOR OPERATED VALVES APPENDIX A RISK INFORMED RELIEF REQUEST FOR PUMPS AND VALVES ........................ A-1 RELIEF REQUEST FOR SAFEGUARDS PUMPS .................................................... P-1 RELIEF REQUEST FOR INSERVICE TEST FREQUENCY ..................................... T-1 RELIEF REQUEST FOR MOVs ................................................................................ V-1 COMANCHE PEAK- UNITS 1 AND 2 Rev. 3
CPNPP/IST Plan COMANCHE PEAK NUCLEAR POWER PLANT UNIT 1 & 2 INSERVICE TESTING PLAN FOR PUMPS & VALVES THIRD INTERVAL 1.0 GENERAL INFORMATION 1.1 Introduction lnservice Testing Plan for Pumps & Valves, hereafter referred to as the 1ST Plan, has been prepared to summarize the test program for certain pumps and valves pursuant to the requirements of the Code of Federal Regulations, 10CFR50.55a(f)(4); and as modified by Relief Request A-1, "Request for Alternative from 10CFR50.55a(f)(4)(i) and (ii) for lnservice Testing Frequency Under 10CFR50.55a(a)(3)(i)", and by the Nuclear Regulator Commission (NRC) Safety Evaluation Report (SER) on the CPNPP RI-IST Program. This testing plan is applicable to CPNPP Units 1 & 2. The content and distribution of the 1ST Plan are controlled and users are cautioned to verify the control status of their copy prior to use. To obtain a copy of this document, contact Distribution Control at the Main Document Control Center. An electronic copy can be accessed via CPNPP Electronic License Basis Documents (CPNPP ELBD). 1.2 Code Edition and Addenda This 1ST Plan meets the requirements of the ASME OM Code 2004 Edition through 2006 Addenda, except in specifically identified instances where an alternative to the Code requirements is proposed or where it has been determined that conformance with certain Code requirements is impractical. In these instances, a request for relief from the Code requirement(s), including proposed alternatives to the requirement(s), has been prepared for Nuclear Regulatory Commission review and approval pursuant to 10CFR50.55a(a)(3) or (f)(5). See Section 2.0, "lnservice Pump Testing Plan", and Section 3.0, "lnservice Valve Testing Plan" for a more detailed discussion of Code edition. 1.3 Dates of Test Interval Implementation of the 1989 Edition 1ST Plan was completed on CPN PP Unit 1 before that unit was returned to power following the third refueling outage. This superceded the original Unit 1 lnservice Testing Plan for Pumps and Valves developed for the first inspection interval. The original Unit 1 1ST Plan was implemented per the requirements of the 1986 Edition of Section XI. This 1989 Edition 1ST Plan constituted an update of the original Unit 1 1ST Plan to a later approved Code edition as allowed by 10CFR50.55a(f)(4)(iv) and as approved by the NRC staff. This 1ST Plan was to remain in effect for Unit 1 for the 120 month interval following the date of the Unit 1 commercial operation (August 13, 1990). An exemption from regulation 10CFR50.55a(f)(4)(ii) to the ten year test interval for Unit 1 was granted by the NRC on June 21, 1995. The extension allowed Unit 1 to remain under the 1989 Edition until the conclusion of the ten year test interval for Unit 2 (August 3, 2003). COMANCHE PEAK- UNITS 1 AND 2 1-1 Rev. 0
CPNPP/IST Plan This 1ST Plan was in effect for Unit 2 for the 120 month interval following the date of the Unit 2 commercial operation (August 3, 1993 to August 2, 2003). The 1ST Plan for Unit 1 and 2 first interval end date was extended from August 2, 2003 to not later than August 2, 2004 (see TXX-03075, dated April 11, 2003). The risk informed inservice testing (RI-IST) was approved by the NRG on August 14, 1998 (Reference 10). The RI-IST Program was incorporated in the first interval program plan Rev. 15, and was implemented on December 4, 2000. The start date 1ST Plan second interval for Unit 1 and 2 was August 3, 2004, and the end date for the second interval is August 2, 2013 (see TXX-04134). The current start date of the third interval 1ST Plan for Unit 1 and Unit 2 is August 3, 2013, and the end date for the third interval is August 2, 2023. 1 .4 Approval Status The first interval 1ST Plan was submitted to the NRG staff on July 2, 1992 via TXX-92302 requesting:
- 1. Approval to update the Unit 1 1ST program to the requirements of the 1989 Edition of ASME Section XI as described in this 1ST Plan;
- 2. Approval of a proposed schedule for phasing in the implementation of this 1ST Plan for Unit 1; and,
- 3. Approval of the Relief Requests contained in Appendix A of this 1ST Plan for use in the testing of Unit 1 and Unit 2.
Relief Request A-1 and V-8 were submitted to the NRG for final approval Via TXX-98153. These relief requests allowed for risk informing 1ST. By safety evaluation dated January 29, 1993 for Unit 1 and NUREG-0797, Supplemental Safety Evaluation Report (SSER) No. 26 dated February, 1993 for Unit 2, the NRG staff granted the following approvals.
- 1. Approval to update the Unit 1 1ST program to the requirements of the 1989 Edition of ASME Section XI and approval to test Unit 2 to the requirements of the Code. (Approval had not specifically been requested to test Unit 2 to the requirements of the 1989 Code since regulation 10CFR50.55a already seemed to permit it; approval was granted nonetheless.)
- 2. Approval of the schedule described in Section 1.3 above for phasing in the implementation of this 1ST Plan for Unit 1.
- 3. Approval of the Relief Requests contained in Appendix A of this 1ST Plan for use in the testing of Unit 1 and Unit 2 with the exception of Relief Request VS which was denied. (See Appendix A for specific information.)
COMANCHE PEAK - UNITS 1 AND 2 1-2 Rev. 0
CPNPP/IST Plan As pointed out in the safety evaluation and SSER, the NRC staff review of this 1ST Plan did not include verification that all pumps and valves within the scope of 10CFR50.55a and ASME Section XI (Now ASME OM Code) are contained in the 1ST program. Additionally, for the components included in the 1ST program, all applicable testing requirements were not verified. 1.5 References
- 1. Code of Federal Regulations, 10CFR50.55a, "Codes and Standards".
- 2. ASME OM Code 2004 Edition, through 2006 Addenda "Code for Operation and Maintenance of Nuclear Power Plants".
- 3. USNRC Generic Letter No. 89-04, "Guidance on Developing Acceptable lnservice Testing Programs", April 3, 1989.
- 4. USN RC, "Minutes of the Public Meetings on Generic Letter 89-04",
October 25, 1989.
- 5. USNRC Staff Guidance Letter, "NRC Staff Guidance for Complying with Certain Provisions of 10CFR50.55a(g), lnservice Inspection Requirements", November 1976.
- 6. USN RC Staff Guidance Letter, "NRC Staff Guidance for Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests Pursuant to 10CFR50.55a(g)", January 1978.
- 7. NUREG-0800, "USNRC Standard Review Plan", July 1981. (Section 3.9.6, lnservice Testing of Pumps and Valves)
- 8. Karassik, Igor J., et al. Pump Handbook, second edition. New York:
McGraw-Hill Book Company, 1986.
- 9. NUREG-1482, Revision 1 "Guidelines for lnservice Testing at Nuclear Power Plants".
- 10. USN RC Letter dated August 14, 1998, "Approval of Risk-Informed lnservice Testing (RI-IST) Program for Comanche Peak Steam Electric Station, Unit 1 and 2" (TAC NOS. M94165, MA94166, MA1972, and MA 1973). (Relief Request A-1.)
COMANCHE PEAK- UNITS 1 AND 2 1-3 Rev. 0
CPNPP/IST Plan 2.0 INSERVICE PUMP TESTING PLAN 2.1 Scope The scope of the lnservice Pump Testing Plan is derived from the requirements of ASME OM Code 2004 Edition through 2006 Addenda, as modified by 10CFR50.55a(f)(4). As modified by Risk Informed 1ST Program Plan and previously NRC approved by Relief Request A-1. The pumps selected for inclusion in this testing plan are that ASME Class 1, 2 and 3 pumps which are provided with an emergency power source and are: a) Required in shutting down a reactor to the safe shutdown condition, or b) Required in maintaining the safe shutdown condition, or c) Required in mitigating the consequences of an accident. Excluded from this testing plan are: a) Drivers, except where the pump and driver form an integral unit and the pump bearings are in the driver, and b) Pumps that are supplied with emergency power solely for operating convenience. c) Skid mounted pumps that are tested as part of the major components and are justified to be adequately tested. The pumps in the scope of this testing plan are described in the CPNPP Final Safety Analysis Report (FSAR), Section 3.9N.3.2 and 3.9B.3.2, "Pump and Valve Operability Assurance" and are tabulated in FSAR Tables 3.9N-9 and 3.9B-8, "Active Pumps". This similar listing of pumps can be found in Table 0 of this 1ST Plan. 2.2 Pump Testing Table Format Detailed information and testing requirements for the pumps included in this 1ST Plan are summarized in Table 0. The guidance presented in References 1.5.2, 1.5.8 and 1.5.9 was used to the greatest extent possible in formatting this table. Following is a discussion of the types of information presented in Table 0.
- 1. Pump Identification - The pump identification field includes the pump name (system name) and pump number. The pump name is the common noun name for the pump and conveys some sense of the pump function. The pump number is a unique identifier applied to each pump. Pumps are listed in Table 0 in alphabetical order by system name. See Flow Diagram M1-0200, "Mechanical Symbols and Notes", for a discussion of pump numbering conventions and abbreviations. The pump names and COMANCHE PEAK - UNITS 1 AND 2 2-1 Rev. 3
CPNPP/IST Plan pump numbers shown in Table O are the same names and numbers used on the respective flow diagrams to identify the pumps.
- 2. Flow Diagram Number - The flow diagram number field indicates on which drawing the pump may be found. The flow diagram numbers are prefixed by "M1" to indicate a Unit 1 drawing and by "M2" to indicate a Unit 2 drawing. The suffix (if any) indicates the drawing sheet number.
- 3. Code Class - The code class field indicates the ASME Boiler and Pressure Vessel Code, Section Ill classification for the pump.
- 4. Pump Type - The pump type field indicates the classification of the pump.
The pumps are classified for the purpose of determining the Code required test parameters to be measured as well as for determining the Code limits for those test parameters. The pump classifications are taken from the Code itself. Two basic pump classifications are used: centrifugal and positive displacement. Centrifugal pumps are further classified by the pump/driver arrangement and positive displacement pumps are further classified by the mechanical construction of the machine. The pump type acronyms are listed below along with their meanings. C/DC (Centrifugal pump direct coupled to its driver): This is the most common centrifugal pump arrangement in which the pump and driver are mounted independent of each other (usually horizontally) and are connected by a flexible coupling. In this pump type, the pump and driver bearings are separate. CNLS (Centrifugal vertical line shaft pump): This arrangement is a special case of the direct coupled centrifugal pump. As the name suggests, the pump and driver are arranged vertically. However, unlike the typical direct coupled centrifugal pump, the vertical line shaft pump has a pumping element suspended at the end of a very long line shaft and has bearings which are inaccessible. Also, the vertical line shaft pump shares bearings with the driver in that the motor thrust bearing also acts as a thrust bearing for the pump. C/DC/VLS (Centrifugal vertical line shaft direct coupled): This arrangement is also a special case of a vertically arranged pump. This pump has a short pump shaft, and has an accessible inboard bearing housing near the coupling end of the pump; the pump shaft and suction areas are inaccessible due to being submerged. C/CC (Centrifugal pump close coupled to its driver): In this arrangement, no coupling is provided and the pump and driver form an integral unit. The pumping element is attached directly to the motor shaft and the pump bearings are actually the motor bearings. Orientation may be either horizontal or vertical. COMANCHE PEAK- UNITS 1 AND 2 2-2 Rev. 3
CPNPP/IST Plan PD/RECIP (Reciprocating positive displacement pump): This is a positive displacement pump in which fluid is moved by a back and forth motion of the pressure-producing member(s). The output from a reciprocating pump will be pulsating and flow through the pump is controlled by integral check valves. (There are no reciprocating pumps in the CPNPP 1ST Plan.) PD/ROT (Rotary positive displacement pump): This is a positive displacement pump in which fluid is moved by a rotating motion of the pressure-producing member(s). The output from a rotary pump is non-pulsating and flow through the pump is controlled by the geometry of the pump casing and rotor(s).
- 5. Test Parameters - The test parameters field indicates those quantities which the Code requires to be established or determined at each inservice test. The test parameters include speed, discharge pressure, differential pressure, flow rate and bearing vibration. Vibration is further classified as pump bearing vibration and driver bearing vibration. Not all test parameters are applicable to all pumps. Rather, the parameters to be established or determined for any pump are dependent on the pump type and are specified per the requirements of ASME OM Code 2004 Edition, through 2006 Addenda, Subsection ISTB. In Table 0, Code required test parameters are indicated with an "X". Test parameters which are not applicable to a particular pump are indicated "N/A". Required test parameters for which relief is requested are indicated by a footnote with the specific Relief Request number. (All pump and valve relief requests are contained in Appendix A of this 1ST Plan.)
- 6. Test Schedule - The test schedule field indicates the frequency of inservice tests for each pump in the RI-IST Plan. High Safety Significant pumps for which fluid inventory is normally provided are tested nominally every three months per the requirements of ASME OM Code 2004 Edition, through 2006 Addenda, Subsection ISTB-3400, and are indicated in Table Oby "3 MO". High Safety Significant pumps lacking required fluid inventory (e.g., pumps in dry sumps) are tested at least once every two years per the requirements of ASME OM Code 2004 Edition, through 2006 Addenda, Subsection ISTB-3400, and are indicated in Table Oby "2 YR".
Low Safety Significant pumps are tested nominally every six years (on a staggered test basis) unless indicated otherwise per the requirements of Relief Request A-1, and are indicated in Table Oby "6 YR". A (Group A pump test): Testing for pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations as defined by ISTB-5121, 5221 and Table ISTB-3000-1. B (Group B pump test): Testing for pumps in standby systems that are not operated routinely except for testing as defined by ISTB-5122, 5322 and Table ISTB-3000-1. COMANCHE PEAK- UNITS 1 AND 2 2-3 Rev. 3
CPNPP/IST Plan CPT (Comprehensive pump test): Testing for pumps as defined by ISTB-5123, 5223, 5323 and Table ISTB-3000-1. When a Group A test is required, a comprehensive test may be substituted. When a Group B test is required, a Group A or comprehensive test may be substituted. A preservice test may be substituted for any inservice test. As allowed by ASME OM Code edition 2004 through 2006 addenda, Subsection ISTB-5000. Pump Curves may be used for testing where it is impractical to adjust a centrifugal or vertical line shaft pump to a specific reference value as allowed by OMN-16 Rev. 1 of the 2012 Edition of the ASME OM Code supplemented by Figure 1 of OMN-16 that is in the 2006 Addendum of the OM Code.
- 7. Footnotes - Footnotes containing additional pump testing information are located at the back of Table O and are referenced in Table O by the footnote number in parentheses.
COMANCHE PEAK - UNITS 1 AND 2 2-4 Rev. 3
() TABLE O - INSERVICE PUMP TESTING PLAN 0 s:
)>
PAGE 1 OF 7 z Test Parameters () I Pump Driver m Flow Code Risk Pump Discharge Differential Flow Bearing Bearing Test "U Pump Identification Diagram Class Ranking Type Speed Pressure Pressure Rate Vib. Vib. Schedule m
)>
Auxiliaiy Feedwater (Motor Driven) C z CP1-AFAPMD-01 M1-0206-01 3 HIGH C/DC N/A N/A X X X N/A 3 MO/A
-I 2YR/CPT (f)
_,,_ CP1-AFAPMD-02 M1-0206-01 3 HIGH C/DC N/A NIA X X X N/A 3 MO/A
)> 2YR/CPT z CP2-AFAPMD-01 M2-0206-01 3 HIGH C/DC N/A N/A X X X N/A 3 MO/A 0
2YR CPT N CP2-AFAPMD-02 M2-0206-01 3 HIGH C/DC N/A N/A X X X N/A 3 MO/A 2YR CPT ()
"U z
Auxiliaiy Feedwater (Turbine Driven) "U "U (f) CP1-AFAPTD-01 M1-0206-01 3 HIGH C/DC X N/A X X X N/A 3 MO/B -I 2 YR/CPT "U CP2-AFAPTD-01 M2-0206-01 3 HIGH C/DC X N/A X X X NIA 3 MO/B w 2YR/CPT Component Cooling Water CP1-CCAPCC-01 M1-0229-A 3 HIGH C/DC N/A N/A X X X N/A 3 MO/A 2 YR/CPT CP1-CCAPCC-02 M1-0229-B 3 HIGH C/DC NIA N/A X X X N/A 3 MO/A 2 YR/CPT CP2-CCAPCC-01 M2-0229 3 HIGH C/DC N/A NIA X X X NIA 3 MO/A 2 YR/CPT CP2-CCAPCC-02 M2-0229 3 HIGH C/DC N/A NIA X X X NIA 3 MO/A 2YR/CPT Chilled Water (Safety)
- o (D
CP1-CHAPCP-05 M1-0311 3 HIGH C/DC N/A N/A X X X N/A 3 MO/A ~ 2 YR/CPT 0
0 TABLE O - INSERVICE PUMP TESTING PLAN 0
~ PAGE 2 of? )>
z Test Parameters 0 I Pump Driver m Flow Code Risk Pump Discharge Differential Flow Bearing Bearing Test
-0 Pump Identification Diagram Class Ranking Type Speed Pressure Pressure Rate Vib. Vib. Schedule m )> ;,;;; CP1-CHAPCP-06 M1-0311 3 HIGH C/DC N/A N/A X X X N/A 3MO/A 2YR/CPT C
z CP2-CHAPCP-05 M2-0311 3 HIGH C/DC N/A N/A X X X N/A 3MO/A
-f 2YR/CPT Cf) ...... CP2-CHAPCP-06 M2-0311 3 HIGH C/DC N/A N/A X X X N/A 3MO/A 2YR/CPT )>
z 0 Centrifugal Charging N TBX-CSAPCH-01 M1-0255-01 2 HIGH C/DC N/A N/A X X X N/A 3 MO/A 0
-0 2YR/CPT z TBX-CSAPCH-02 M1-0255-01 2 HIGH C/DC N/A N/A X X X N/A 3 MO/A -0 2YR/CPT -0 Cf)
TCX-CSAPCH-01 M2-0254 2 HIGH C/DC N/A N/A X X X N/A 3MO/A
-f 2YR/CPT -0 TCX-CSAPCH-02 M2-0254 2 HIGH C/DC N/A N/A X X X N/A 3MO/A ru
- J 2YR/CPT Boric Acid Transfer TBX-CSAPBA-01 M1-0257 3 LOW C/CC N/A N/A X X N/A X 6YR/A (1) 6 YR/CPT TBX-CSAPBA-02 M1-0257 3 LOW C/CC N/A N/A X X N/A X 6YR/A (1) 6 YR/CPT TCX-CSAPBA-01 M1-0257 3 LOW C/CC N/A NIA X X N/A X 6YR/A (1) 6YR/CPT TCX-CSAPBA-02 M1-0257 3 LOW C/CC N/A NIA X X NIA X 6YR/A (1) 6 YR/CPT Containment S[Jray
- o CD CP1-CTAPCS-01 M1-0232 2 LOW C/DC N/A N/A X X X NIA 6 YR/B
- < (1) 6 YR/CPT 0
0 TABLE O - INSERVICE PUMP TESTING PLAN 0 s;: PAGE 3 of7
)>
z Test Parameters 0 I Pump Driver m Flow Code Risk Pump Discharge Differential Flow Bearing Bearing Test
""O Pump Identification Diagram Class Ranking Type Speed Pressure Pressure Rate Vib. Vib. Schedule m )> ;,;: CP1-CTAPCS-02 M1-0232 2 LOW C/DC N/A NIA X X X N/A 6YR/B (1) 6YR/CPT C
z CP1-CTAPCS-03 M1-0232 2 LOW C/DC N/A N/A X X X N/A 6YR/B
-! (1) 6YR/CPT (J) ....,. CP1-CTAPCS-04 M1-0232 2 LOW C/DC N/A NIA X X X N/A 6YR/B (1) 6YR/CPT )>
z CP2-CTAPCS-01 M2-0232 2 LOW C/DC NIA NIA X X X NIA 6YR/B 0 (1) 6YR/CPT N CP2-CTAPCS-02 M2-0232 2 LOW C/DC N/A N/A X X X N/A 6YR/B (1) 6YR/CPT 0 CP2-CTAPCS-03 M2-0232 2 LOW C/DC N/A N/A X X X N/A 6YR/B ""O (1) 6YR/CPT z
""O CP2-CTAPCS-04 M2-0232 2 LOW C/DC N/A NIA X X X N/A 6YR/B ""O (1) 6YR/CPT (/) ""O Reactor Makeu~ Water 0)
- J CP1-DDAPRM-01 M1-0241-01 3 LOW(1) C/DC N/A N/A X X X N/A 4 1/2YR/A 4 1/2 YR/CPT CPX-DDAPRM-01 M1-0241-01 3 LOW(1) C/DC N/A NIA X X X N/A 41/2 YR/A 4 1/2 YR/CPT CP2-DDAPRM-01 M2-0241 3 LOW(1) C/DC N/A N/A X X X N/A 4 1/2YR/A 41/2 YR/CPT Fuel Oil Transfer CP1-DOAPFT-01 M1-0215-F (3) LOW PD/ROT N/A X N/A X X N/A 6YR/B (1) 6YR/CPT CP1-DOAPFT-02 M1-0215-F (3) LOW PD/ROT N/A X N/A X X N/A 6YR/B (1) 6YR/CPT CP1-DOAPFT-03 M1-0215-G (3) LOW PD/ROT N/A X N/A X X N/A 6YR/B
- 0 (1) 6 YR/CPT (D
0
0 TABLE O - INSERVICE PUMP TESTING PLAN 0
~ PAGE4of7 )>
z Test Parameters 0 I Pump Driver m Flow Code Risk Pump Discharge Differential Flow Bearing Bearing Test
-u Pump Identification Diagram Class Ranking Type Speed Pressure Pressure Rate Vib. Vib. Schedule m )> ;;:,;; CP1-DOAPFT-04 M1-0215-G (3) LOW PD/ROT N/A X N/A X X N/A 6YR/B (1) 6YR/CPT C
z CP2-DOAPFT-01 M2-0215-F (3) LOW PD/ROT N/A X NIA X X N/A 6 YR/B
=i
(/) (1) 6YR/CPT CP2-DOAPFT-02 M2-0215-F (3) LOW PD/ROT N/A X N/A X X NIA 6 YR/B (1) 6YR/CPT
)>
z CP2-DOAPFT-03 M2-0215-G (3) LOW PD/ROT N/A X N/A X X N/A 6YR/B 0 (1) 6YR/CPT N CP2-DOAPFT-04 M2-0215-G (3) LOW PD/ROT NIA X NIA X X N/A 6 YR/B (1) 6YR/CPT 0
-u z
Residual Heat Removal -u
-u 2 X X(4) X(4) 3 MO/A (/)
TBX-RHAPRH-01 M1-0260 HIGH C/DC N/A N/A X
-I 2YR/CPT -u TBX-RHAPRH-02 M1-0260 2 HIGH C/DC NIA N/A X X X(4) X(4) 3 MO/A DJ 2YR/CPT :::J TCX-RHAPRH-01 M2-0260 2 HIGH C/DC N/A NIA X X X(4) X(4) 3 MO/A 2YR/CPT TCX-RHAPRH-02 M2-0260 2 HIGH C/DC N/A N/A X X X(4) X(4) 3 MO/A 2YR/CPT Spent Fuel Pool Cooling CPX-SFAPSF-01 M1-0235 3 LOW(1) C/DC NIA N/A X X X N/A 3YR/A 3YR/CPT CPX-SFAPSF-02 M1-0235 3 LOW(1) C/DC N/A N/A X X X NIA 3YR/A 3 YR/CPT Safety Injection
- 0 CD TBX-SIAPSl-01 M1-0263-A 2 HIGH C/DC N/A N/A X X X N/A 3 MO/B
- < 2YR/CPT 0
0 TABLE O - INSERVICE PUMP TESTING PLAN 0
$ PAGE 5 of7 )>
z Test Parameters 0 I Pump Driver m Flow Code Risk Pump Discharge Differential Flow Bearing Bearing Test 7J Pump Identification Diagram Class Ranking Type Speed Pressure Pressure Rate Vib. Vib. Schedule m
)> ;;,;; TBX-SIAPSl-02 M1-0263-A 2 HIGH C/DC NIA NIA X X X NIA 3 MO/B C 2 YR CPT z TCX-SIAPSl-01 M2-0262 2 HIGH C/DC N/A NIA X X X NIA 3MO/B =i (J) 2YR/CPT
_,_ TCX-SIAPSl-02 M2-0262 2 HIGH C/DC N/A N/A X X X N/A 3MO/B
)> 2YR/CPT z
0 Service Water N CP1-SWAPSW-01 M1-0233 3 HIGH CNLS N/A N/A X X N/A X 3 MO/A 0 2YR/CPT 7J z CP1-SWAPSW-02 M1-0233 3 HIGH CNLS N/A N/A X X N/A X 3MO/A 7J 2 YR/CPT 7J CP2-SWAPSW-01 M2-0233 (/) 3 HIGH CNLS N/A N/A X X NIA X 3 MO/A 2 YR/CPT 7J CP2-SWAPSW-02 M2-0233 3 HIGH CNLS N/A N/A X X NIA X 3 MO/A iii" 2YR/CPT :J Safeguards Building Floor Drain Pump (5) CP1-WPAPSS-01 M1-0236 3 LOW(1) C/DCNLS N/A N/A X X X N/A 6YR/A 6YR/CPT CP1-WPAPSS-02 M1-0236 3 LOW(1) C/DCNLS NIA NIA X X X NIA 6YR/A 6 YR/CPT CP1-WPAPSS-03 M1-0236 3 LOW(1) C/DCNLS N/A N/A X X X N/A 6YR/A 6YR/CPT CP1-WPAPSS-04 M1-0236 3 LOW(1) C/DCNLS N/A N/A X X X N/A 6YR/A 6YR/CPT CP2-WPAPSS-01 M2-0236 3 LOW(1) C/DCNLS N/A N/A X X X N/A 6YR/A 6YR/CPT
- o CD CP2-WPAPSS-02 M2-0236 3 LOW(1) C/DCNLS N/A N/A X X X N/A 6YR/A
-
- 6YR/CPT 0
0 TABLE O - INSERVICE PUMP TESTING PLAN 0
- s;:: PAGE 6 of?
)>
z Test Parameters 0 I Pump Driver m Flow Code Risk Pump Discharge Differential Flow Bearing Bearing Test
""'CJ Pump Identification Diagram Class Ranking Type Speed Pressure Pressure Rate Vib. Vib. Schedule m )> ?\ CP2-WPAPSS-03 M2-0236 3 LOW(1) CIDCNLS NIA NIA X X X NIA 6YRIA 6YR/CPT C
z CP2-WPAPSS-04 M2-0236 3 LOW(1) CIDCNLS NIA NIA X X X NIA 6YRIA
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(/) 6YRICPT
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z 0 N 0
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- J
- 0
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0 TABLE O - INSERVICE PUMP TESTING PLAN 0
~ PAGE 7 of7 )>
z NOTES 0 I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the pumps within the specified group.
-0 ~
- 2. Not Used.
/\
- 3. The Fuel Oil Transfer Pumps were not commercially available as ASME BPV Code, Section 111, Class 3; however, the normal commercial design was upgraded to C "equivalent" ASME Section 111, Class 3 quality requirements through seismic testing, qualification, and documentation.
z
--i 4. The Residual Heat Removal Pumps were close coupled and all bearings were in the driver (motor); therefore, the driver was monitored for vibration. The pumps were
(/)
....,. modified to a direct coupled design and one set of radial bearings were installed in the pumps. The thrust bearing is still in the driver; therefore, it is prudent to take vibration at two points on the pump and five points on the driver. )>
z 5. Refer to Relief Request P-1 in Appendix "A". 0 N 0
-0 z -0 -0
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0
CPNPP/IST Plan 3.0 INSERVICE VALVE TESTING PLAN 3.1 Scope The scope of the In service Valve Testing Plan is derived from the requirements of ASME OM Code 2004 Edition through 2006 Addenda, Subsection ISTC, Appendix I and Appendix II as modified by 10CFR50.55a(f)(4) and the Risk Informed 1ST Program Plan as allowed by previously NRC approved, Relief Request A-1. The valves selected for inclusion in this testing plan are those active or passive ASME Class 1, 2 and 3 valves and pressure relief devices (and their actuating and position indicating systems) which are required to perform a specific function: a) In shutting down a reactor to the safe shutdown condition, or b) In maintaining the safe shutdown condition, or c) In mitigating the consequences of an accident. Excluded from this testing plan are: a) Valves used only for operating convenience such as vent, drain, instrument and test valves, or b) Valves used only for system control, such as pressure regulating valves, or c) Valves used only for system or component maintenance. d) Skid mounted valves which are tested as part of the major component. e) Category A and Category 8 Safety and Relief Valves are excluded from the requirements of ISTC-3700 and ISTC-3500, valve testing requirements. Further, the valve actuating system test scope does not include external control and protection systems responsible for sensing plant conditions and providing signals for valve operation. The active valves and pressure relief devices in the scope of this testing plan are described in the CPNPP Final Safety Analysis Report (FSAR), Sections 3.9N.3.2 and 3.98.3.2, "Pump and Valve Operability Assurance", and are tabulated in FSAR Tables 3.9N-10 and 3.98-10, "Active Valves". ASME Code Class 2 and 3 pressure relief devices that only protect systems/components that perform a safety function as described above are not tabulated in FSAR Tables 3.9N-10 and 3.98-10. These valves will continue to be tested within the required test interval of 10 years during the third interval. Consistent with the philosophy discussed in Reference 1, these specific thermal relief valves do not require the two additional valve tests following as-found set-pressure determination failures. However, if COMANCHE PEAK - UNITS 1 AND 2 3-1 Rev. 0
CPNPP/1ST Plan performance data indicates that more frequent testing is needed to assure valve function, then the testing frequency should be modified. In lieu of tests, valve replacement may be performed as an alternative to testing. This philosophy only applies to thermal relief valves whose only function is to protect systems/ components that have a safety function. These valves are identified in the 1ST Plan by having a safety function position listing of "N/A". The passive valves and pressure relief devices in the scope of this testing p!an were identified by review and are those valves and pressure relief devices which perform a nuclear safety function but are not active and for which leakage testing or position indicator testing is required. A listing of the above described active and passive valves and pressure relief devices can be found in Tables 1 through 19 of this 1ST Plan. 3.2 Valve Testing Table Format Detailed information and testing requirements for the valves included in this 1ST Plan are summarized in Tables 1 through 19. A separate table has been prepared for each plant system which contains valves in the scope of the plan. The tables are arranged in alphabetical order by system name: Auxiliary Feedwater Table 1 Component Cooling Water Table 2 Chilled Water (Safety & Non-Safety) Table 3 Chemical and Volume Control Table 4 Containment Spray Table 5 Demineralized and Reactor Makeup Water Table 6 Diesel Generator Auxiliaries Table , Feedwater T abl~ S Main Steam Table 9 Reactor Coolant Table 10 Residual Heat Removal Table 11 Spent Fuel Pool Cooling Table 12 Safety Injection Table 13 Service Water Table 14 Ventilation (Control Room Air Conditioning) Table 15 COMANCHE PEAK - UNITS 1 AND 2 3-2 Rev. 0
CPNPP/lST Plan Vents and Drains Table 111 Miscellaneous Containment Isolation Valves Table 17 Safety & Relief Valves Table 18 Motor Operated Valves fable 19 The guidance in References 1.5.2. 1.5.8 and 1.5.9 was used to the greatest extent possible in formatting the tables. Following is a discussion of the types of information presented in the tables.
- 1. Valve Groups - Valves are grouped by system. safety significance, vatve type, actuator type, manufacturer, model number. Each group has a unique Group Number to facilitate the implementation of the risk informed lnservice Test Program.
- 2. Valve Identification - Valve identification includes the valve number field and a brief description of the valve safety function (in the Remarks field).
In each table, the valves are arranged in numerical order by the four digrt location number which forms the root of each valve number. See Flow Diagram M1-0200, "Mechanical Symbols and Notes", for a discussion of valve numbering conventions and abbreviations. The valve numbers shown in Tables 1 through 19 are the same numbers used on the respective flow diagrams to identify the valves. For valves which exist in both Unit 1 and Unit 2 and for which the test requirements are the same. the unit designator prefixes have been dropped from the valve numbers in the tables. The valve numbers in this case should be understood to be prefixed by "1" (or CP1) and "2 {or CP2), as approprrate. If a valve is in a common system, exists in one unit only, is numbered differently between units or has different test requirements between units, then the unit designator is shown.
- 3. Flow Diagram Number - The flow diagram number field indicates on which drawing the valve may be found. The flow diagram numbers are prefixed by "M1" to indicate a Unit 1 drawing and by "M2" to indicate a Unit 2 drawing. The suffix (if any) indicates the drawing sheet number. Drawing coordinates are indicated in parentheses below the flow diagram number for ease in locating a valve.
- 4. Risk Ranking - A valve will either be ranked as High or Low Safety Significant. This was determined through the CPNPP Individual Plant Examination utilizing Probability Risk Assessment techniques and through the RI-IST Expert Panel.
- 5. Size - The size field indicates the nominal valve size in inches.
COMANCHE PEAK - UNITS 1 AND 2 3-3 Rev. 0
CPNPP/IST Plan
- 6. Code Class - The code class field indicates the ASME Boiler and Pressure Vessel Code, Section Ill classification for the valve.
- 7. Category - The category field indicates the classification of the valve according to characteristics described in 2004 Edition through 2006 Addenda, Subsection ISTC-1300. See the Valve Table Index at the end of this section for a listing of valve categories and their meanings.
- 8. Function - The function field indicates the manner in which a valve accomplishes its required safety function(s). "A" denotes an active valve and "P" denotes a passive valve with the terms defined as follows:
Active valves - valves which are required to change obturator position to accomplish their required safety function(s). Passive valves - valves which maintain obturator position and are not required to change obturator position to accomplish their required safety function(s). Obturator - valve closure member (disk, gate, plug, ball, etc.)
- 9. Safety Function Position - The safety function position field indicates the position (open or closed) to which a valve must move or remain in to accomplish its required safety function(s). The open and closed positions are indicated by "O" and "C" respectively.
- 10. Test Parameters/Schedule - The test parameters/schedule field denotes the Code test requirements and test frequencies for valves in the 1ST Plan.
The test parameters include leak test, exercise test, fail-safe test and position indicator test. Not all test parameters are applicable to all valves. Rather, the parameters to be tested for any valve are dependent on the valve/actuator type, category, and function. Valves which have both an open and closed safety function position and for which the test requirements or frequencies are different in the two positions, have their open and closed test requirements identified separately. Test parameters which are not applicable to a particular valve are indicated "N/A". Check valves are exercise tested in both the open and closed direction regardless of safety function position or valve safety significance. Non-safety function exercise tests for high safety significant check valves shall be performed at least once every two years. Non-safety function exercise tests for low safety significant check valves shall be performed at the frequency specified in Relief Request A-1. Required test parameters or test frequencies for which relief is requested are indicated by the specific Relief Request number. (All pump and valve relief requests are contained in Appendix A of this 1ST Plan.) In cases where the performance of a valve full-stroke exercise test is limited to cold shutdowns or refueling outages, a table footnote is provided which justifies COMANCHE PEAK - UNITS 1 AND 2 3-4 Rev.a
CPNPP/IST Plan this determination. See the Valve Table Index at the end of this section for a listing of test parameter and schedule acronyms and their meanings.
- 11. Footnotes - Footnotes containing additional valve testing information are located at the back of each system valve table and are referenced in the tables by the footnote number in parentheses.
3.3 References
- 1. NUREG/CP-0152, "Proceedings of the Fourth NRC/ASME Symposium on Valve and Pump Testing", July 15-18, 1996, pages 38-19 through 38-21.
- 2. NUREG-1482, Rev. 1, "Guidelines for lnservice Testing at Nuclear Power Plants".
- 3. USN RC Letter dated August 14, 1998, "Approval of Risk Informed lnservice Testing (RI-IST) Program for Comanche Peak Steam Electric Station, Unit 1 and 2" (TAC NOS. M94165, MA94166, MA1972, and MA 1973). (Relief Request A-1.)
COMANCHE PEAK - UNITS 1 AND 2 3-5 Rev. 0
0 VALVE TABLE INDEX (Page 1 of 4) 0
~ )> VALVE TYPES ACTUATOR TYPES VALVE FUNCTIONS z
0 AN - Angle AO -Air Operator A-Active I m BA- Ball HO - Hydraulic Operator P - Passive
""O m BF - Butterfly MA - Manual Operator )> ;::,;;: CK- Check MO - Motor Operator SAFETY FUNCTION POSITIONS C
DA - Diaphragm SA - Self Actuated 0 - Open z GA- Gate SO - Solenoid Operator C- Closed
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PL - Plug z RE- Relief 0 N SCK - Stop Check SF - Safety 0
""O VB - Vacuum Breaker z ""O VALVE CATEGORIES -- ""O (J) ""O Category A - Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their ru
- i required safety function(s).
Category B - Valves for which seat leakage in the closed position is inconsequential for fulfillment of their required safety function(s). Category C - Valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves), for fulfillment of their required safety function(s). Category D - Valves which are actuated by an energy source capable of only one operation, such as rupture disks or explosively actuated valves, for fulfillment of their required safety function(s). (There are no Category D valves or pressure relief devices in the CPNPP RI-IST Plan.) Note: Seat tightness determination is performed as part of the performance test for Category C pressure relief devices (SRV) and may be performed as a method of close exercise test for check valves (CV). However, pressure
- o relief devices and check valves are further classified as Category A only if there is a safety analysis criteria CD existing for valve seat leakage such as for pressure relief devices or check valves performing containment
.t,.. isolation functions or reactor coolant system pressure isolation functions .
0 VALVE TABLE INDEX (Page 2 of 4) 0 ~ TEST PARAMETERS )> z 0 I Leak Test m ""CJ m LT - Leak test Category A valve (other than containment isolation valves) per the requirements of ASME OM Code )>
- ,
- ;: 2004 Edition through 2006 Addenda, Subsection ISTC-3630.
C LTJ - Leak test Category A containment isolation valve per the requirements of ASME OM Code 2004 Edition through z =i 2006 Addenda, Subsection ISTC-3620. (J) )> Exercise Test z 0 I\.) MT - Exercise power operated Category A or B valve full-stroke to its safety function position(s) and measure stroke time per the requirements of ASME OM Code 2004 Edition through 2006 Addenda, Subsection ISTC-3510. 0
""CJ ET - Exercise Category A or B valve full-stroke to its safety function position(s) per the requirements of ASME OM Code z ""CJ 2004 Edition through 2006 Addenda, Subsection ISTC-3510. ""CJ (J)
DT- Diagnostic testing determines the cause or mechanism associated with failure, degradation, or performance -I
""CJ anomaly of a motor operated valve per the requirements of OMN-1 Rev. 1 (Relief Request V-1). ru CV- Exercise Category C check valve full-stroke to its safety function position(s) per the requirements of ASME OM Code 2004 Edition through 2006 Addenda, Subsection ISTC-3510.
CVD- Disassemble Category C check valve to verify operability per the requirements of ASME OM Code 2004 Edition through 2006 Addenda, Subsection ISTC-5220. PS- Exercise Category A or B valve or Category C check valve part-stroke towards its safety function position(s) per the requirements of ASME OM Code 2004 Edition through 2006 Addenda. Part-stroke close exercising is not applicable to check valves except upon disassembly and inspection as practicable. SRV- Performance test Category C safety, relief or vacuum breaker valve per the requirements of ASME OM Code 2004 Edition through 2006 Addenda, Subsection ISTC-5230 and Appendix I.
0 VALVE TABLE INDEX (Page 3 of 4) 0
~ TEST PARAMETERS (Continued) z 0
I DD- Dual direction test/verification shall be performed in accordance with ASME OM Code 2004 Edition through 2006 m
-u Addenda, Subsection ISTC-5220. Frequency is determined by relief request A-1 or Appendix II, Check Valve m Condition Monitoring as applicable.
Fail Safe Test C z
-, FO - Fail safe test Category A or B valve in the open direction per the requirements of ASME OM Code 2004 Edition,
(/) through 2006 Addenda, Subsection ISTC-3560. z FC- Fail safe test Category A or B valve in the closed direction per the requirements of ASME OM Code 2004 Edition, 0 N through 2006 Addenda, Subsection ISTC-3560. Position Indicator Test 0
-u z
PIT - Test Category A, B, C or D valve position indication per ASME OM Code 2004 Edition, through 2006 Addenda,
-u -u Subsection ISTC-3700. (/) -u TEST SCHEDULES 0) 3MO- Perform exercise test (and fail safe test, if applicable) nominally every three months.
CS- Perform exercise test (and fail safe test, if applicable) during each cold shutdown outage (A plant shutdown during which the plant reaches the Cold Shutdown condition as defined by Technical Specifications). Such exercise is not required if the time period since the previous fullstroke exercise is less than three months. Valve exercising during cold shutdown shall commence within 48 hours of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power. For extended outages, testing need not be commenced in 48 hours provided all valves required to be tested during cold shutdown will be tested prior to plant startup. Periodic testing requirements during an extended cold shutdown are addressed for each valve separately in the respective cold shutdown justification.
- o RF - Perform exercise test (and fail safe test, if applicable) during each refueling outage.
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0 VALVE TABLE INDEX (Page 4 of 4) 0
- s:
)> TEST SCHEDULES (Continued) z 0 I TS- Perform test at the applicable Technical Specification frequency. m 7J m )> NYR- Perform test at least once every N years. For leak tests (LT) and position indicator tests (PIT), N equals two years
- ,;
- ; for High Safety Significance or six years for Low Safety Significance valves. For pressure relief device performance tests (SRV), N nominally equals five years or ten years for Class 1 or Class 2 & 3 devices C
z respectively. However, other test frequencies may apply for pressure relief devices. See ASME OM Code 2004 -f Edition through 2006 Addenda, Appendix I. (/) )> z 0 N 0 7J z 7J
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0 TABLE 1 -AUXILIARY FEEDWATER 0 s:
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PAGE 1 OF 11 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
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Group 4 C Swing Check Valve/Self Actuating z Borg-Warner 75000 Series
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(/) AF-0014 M1-0206-1 LOW 6 3 C A 0 N/A CV/6YR NIA NIA AFW Flowpath
....>. (B-2) (1) DDl6YR )> M2-0206-1 z (B-2) 0 I\.) AF-0024 M1-0206-1 LOW 6 3 C A 0 NIA CV/6YR NIA NIA AFW Flowpath (B-3) (1) DDl6YR M2-0206-1 0 """()
(B-3) z AF-0032 M1-0206-1 LOW 8 3 C A 0 N/A CV/6YR NIA NIA AFW Flowpath """()
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(B-5) (1) DD/6YR ::::: M2-0206-1 (J) (B-5) --i
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AF-0038 M1-0206-1 LOW 8 3 C A 0 NIA CVl6YR NIA NIA AFW Flowpath Q) (E-4) (1) DD/6YR ::::l M2-0206-1 (E-4) AF-0051 M1-0206-1 LOW 6 3 C A 0 NIA CV/6YR NIA NIA AFW Flowpath (E-3) (1) DDl6YR M2-0206-1 (E-3) AF-0065 M1-0206-1 LOW 6 3 C A 0 N/A CVl6YR NIA NIA AFW Flowpath (E-2) (1) DDl6YR M2-0206-1 (E-2) AF-0167 M1-0206-2 LOW 8 3 C A 0 NIA CVl6YR NIA NIA Pump Miniflow Path (A-5) (1) DD/6YR M2-0206-2 (A-5)
- 0 CD
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0 TABLE 1 -AUXILIARY FEEDWATER 0 s:
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PAGE 2 of 11 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""CJ Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
A CVCM Group X-6 C Swing Check Valve / Self Actuating z Borg Warner 75000 Series
--l AF-0009 M1-0206-2 LOW 3 3 C A C NIA DD/12YR NIA N/A Non-Safety Makeup Line
(/)
->. (D-1) (4) Isolation )> M2-0206-2 z (D-1) 0 CVCM Group 1-19 N
Nozzle Check Valve / Self Actuating Mokveld Model TKZ-Y-0 0 LOW C A O/C NIA DD/12YR NIA NIA AFW Flowpath/AFW Flowpath ""CJ 1AF-0075 M1-0206 4 3 (C-4) (4) Boundary & AFW Line Break z
""CJ Mitigation & FW Backflow ""CJ Prevention During Startup (/)
1AF-0083 M1-0206 LOW 4 3 C A O/C NIA DD/12YR N/A NIA AFW Flowpath/AFW Flowpath --l (C-2) (4) Boundary & AFW Line Break ""CJ Ill Mitigation & FW Backflow :::J Prevention During Startup 1AF-0086 M1-0206 LOW 4 3 C A O/C NIA DD/12YR NIA N/A AFW Flowpath/AFW Flowpath (C-3) (4) Boundary & AFW Line Break Mitigation & FW Backflow Prevention During Startup CVCM Group X-15 Nozzle Check Valve / Self Actuating Ene[lech Model DRV-Z 1AF-0078 M1-0206 LOW 4 3 C A O/C N/A DD/12YR NIA NIA AFW Flowpath/AFW Flowpath (C-4) (4) Boundary & AFW Line Break Mitigation & FW Backflow Prevention During Startup 2AF-0101 M2-0206 LOW 4 3 C A O/C N/A DD/12YR NIA N/A AFW Flowpath/AFW Flowpath (C-5) (4) Boundary & AFW Line Break Mitigation & FW Backflow
- o Prevention During Startup CD
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0 TABLE 1 - AUXILIARY FEEDWATER 0
~ PAGE 3 of 11 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
--0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
CVCM Group 2-19 C Nozzle Check Valve I Self Actuating z Mokveld Model TKZ-Y-0
=i (f) 2AF-0075 M2-0206 LOW 4 3 C A O/C NIA DD/16YR NIA NIA AFW Flowpath/AFW Flowpath
_,_ (C-4) (4) Boundary & AFW Line Break
)> Mitigation & FW Backflow z Prevention During Startup 0 2AF-0078 M2-0206 LOW 4 3 C A O/C NIA DD/16YR N/A NIA AFW Flowpath/AFW Flowpath N
(C-4) (4) Boundary & AFW Line Break Mitigation & FW Backflow 0 Prevention During Startup --0 2AF-0083 M2-0206 LOW 4 3 C A O/C N/A DD/16YR N/A N/A AFW Flowpath/AFW Flowpath z
""CJ (C-2) (4) Boundary & AFW Line Break ""CJ Mitigation & FW Backflow (f)
Prevention During Startup -l 2AF-0086 M2-0206 LOW 4 3 C A O/C N/A DD/16YR NIA N/A AFW Flowpath/AFW Flowpath 31 0) (C-3) (4) Boundary & AFW Line Break ::i Mitigation & FW Backflow Prevention During Startup CVCM Group 1-5 Nozzle Check Valve I Self Actuating Mokveld Model TKZ-Y-0 1AF-0093 M1-0206 LOW 4 3 C A OIC N/A DD/16YR NIA N/A AFW Flowpath/AFW Flowpath (C-1) (4) Boundary & AFW Line Break Mitigation & FW Backflow Prevention During Startup 1AF-0098 M1-0206 LOW 4 3 C A O/C N/A DD/16YR NIA NIA AFW Flowpath/AFW Flowpath (C-2) (4) Boundary & AFW Line Break Mitigation & FW Backflow Prevention During Startup 1AF-0101 M1-0206 LOW 4 3 C A O/C N/A DD/16YR N/A N/A AFW Flowpath/AFW Flowpath (C-5) (4) Boundary & AFW Line Break I-
- o Mitigation & FW Backflow CD Prevention During Startup
- c==-
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0 TABLE 1 -AUXILIARY FEEDWATER 0
~ PAGE 4 of 11 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
--0 Number (Coard.) Ranking Size Class gory tion Pas. Test Test Test Test Remarks m )>
1AF-0106 M1-0206 LOW 4 3 C A O/C NIA DD/16YR N/A N/A AFW Flowpath/AFW Flowpath C (C-5) (4) Boundary & AFW Line Break z Mitigation & FW Backflow
=i
(/) Prevention During Startup
...... CVCM Group 2-5 )> Nozzle Check Valve / Self Actuating z Mokveld Model TKZ-Y-0 0 2AF-0093 M2-0206 LOW 4 3 C A O/C N/A DD/12YR N/A N/A AFW Flowpath/AFW Flowpath N
(C-1) (4) Boundary & AFW Line Break Mitigation & FW Backflow 0 Prevention During Startup --0 2AF-0098 M2-0206 LOW 4 3 C A O/C N/A DD/12YR N/A N/A AFW Flowpath/AFW Flowpath z
--0 (C-2) (4) Boundary & AFW Line Break --0 Mitigation & FW Backflow (f)
Prevention During Startup -l 2AF-0106 M2-0206 LOW 4 3 C A O/C NIA DD/12YR N/A N/A AFW Flowpath/AFW Flowpath --0 (C-5) (4) Boundary & AFW Line Break ru
- i Mitigation & FW Backflow Prevention During Startup CVCM Group X-8 Piston Check Valve / Self Actuating Edw;;i[dS Model D36274F316JT1 AF-0350 M1-0206-2 LOW 2 3 C A C N/A DD/12YR N/A N/A Non-Safety Makeup Line (D-1) (4) Isolation M2-0206-2 (D-1)
CVCM Group X-9 Swing Check Valve / Self Actuating Westinghguse Model #3000CS8200000 AF-0351 M1-0206-2 LOW 3 3 C A C N/A DD/12YR NIA NIA Non-Safety Makeup Line (D-1) (4) Isolation
- 0 M2-0206-2 CD
- < (D-1)
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0 TABLE 1 -AUXILIARY FEEDWATER 0
~ PAGE 5 of 11 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
\) Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
7' GROUP 114 - Not Used C GROUP3 z Nozzle Check Valve I Self Actuating
-I Circle Seal Model N162-180 (f) ...... 1AF-0215 M1-0218-1A LOW 1/2 3 A/C A C LTl6YR CVl6YR NIA NIA Safety-Related Air )> (E-4) (1) (3) Accumulator to Non-Safety Air z Supply Isolation 0 Safety-Related Air N 1AF-0216 M1-0218-1A LOW 1/2 3 A/C A C LT/6YR CVl6YR NIA N/A (E-4) (1) (3) Accumulator to Non-Safety Air Supply Isolation 0 \)
Safety-Related Air 1AF-0217 M1-0218-1A LOW 1/2 3 A/C A C LTl6YR CV/6YR NIA NIA Accumulator to Non-Safety Air z\) (D-4) (1) (3) Supply Isolation \) 1AF-0218 M1-0218-1A LOW 1/2 3 A/C A C LTl6YR CVl6YR NIA NIA Safety-Related Air (f) (D-4) (1) (3) Accumulator to Non-Safety Air -I Supply Isolation \) 0) 1AF-0219 M1-0218-1A LOW 1/2 3 A/C A C LT/6YR CVl6YR N/A N/A Safety-Related Air ::i (C-4) (1) (3) Accumulator to Non-Safety Air Supply Isolation 1AF-0220 M1-0218-1A LOW 1/2 3 A/C A C LTl6YR CV/6YR NIA NIA Safety-Related Air (C-4) (1) (3) Accumulator to Non-Safety Air Supply Isolation AF-0221 M1-0218-1A LOW 1/2 3 A/C A C LTl6YR CVl6YR N/A NIA Safety-Related Air (C-4) (1) (3) Accumulator to Non-Safety Air M2-0218-2 Supply Isolation (C-5) AF-0222 M1-0218-1A LOW 1/2 3 A/C A C LTl6YR CV/6YR N/A NIA Safety-Related Air (C-4) (1) (3) Accumulator to Non-Safety Air M2-0218-2 Supply Isolation (C-5) AF-0223 M1-0218-1A LOW 1/2 3 A/C A C LTl6YR CV/6YR N/A NIA Safety-Related Air (A-4) (1) (3) Accumulator to Non-Safety Air
- a M2-0218-2 Supply Isolation (D
- < (C-4)
.i:,..
0 TABLE 1 -AUXILIARY FEEDWATER 0
~ PAGE 6 of 11 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator "U Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m
)>
AF-0224 M1-0218-1A LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air C (A-4) (1) (3) Accumulator to Non-Safety Air z M2-0218-2 Supply Isolation
=i
(/) (C-4) AF-0226 M1-0218-1A LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air (B-4) (1) (3) Accumulator to Non-Safety Air
)>
z M2-0218-2 Supply Isolation 0 (B-4) N Safety-Related Air AF-0227 M1-0218-1A LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A (B-4) (1) (3) Accumulator to Non-Safety Air 0 M2-0218-2 Supply Isolation "U (B-4) z "U AF-0228 M1-0218-1A LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA N/A Safety-Related Air "U Accumulator to Non-Safety Air :::::: (A-4) (1) (3) (/) M2-0218-2 Supply Isolation -I (D/E-4) u AF-0229 M1-0218-1A LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air OJ
- i (A-4) (1) (3) Accumulator to Non-Safety Air M2-0218-2 Supply Isolation (D/E-4)
AF-0230 M1-0218-1A LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air (B-4) (1) (3) Accumulator to Non-Safety Air M2-0218-2 Supply Isolation (F-4) AF-0231 M1-0218-1A LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA NIA Safety-Related Air (B-4) (1) (3) Accumulator to Non-Safety Air M2-0218-2 Supply Isolation (F-4) AF-0232 M1-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA N/A Safety-Related Air (F-2) (1) (3) Accumulator to Non-Safety Air M2-0218-1 Supply Isolation (F-2)
- o CD
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0 TABLE 1 -AUXILIARY FEEDWATER 0 s:
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PAGE 7 of 11 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
7' Safety-Related Air AF-0233 M1-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A C (F-2) (1) (3) Accumulator to Non-Safety Air z M2-0218-1 Supply Isolation
=i (f)
(F-2)
....... AF-0234 M1-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air )> (F-1) (1) (3) Accumulator to Non-Safety Air z M2-0218-1 Supply Isolation 0 (D-1)
N Safety-Related Air AF-0235 M1-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA N/A (F-1) (1) (3) Accumulator to Non-Safety Air 0 M2-0218-1 Supply Isolation -0 (D-1) z
-0 2AF-0236 M2-0218-2 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air -0 Accumulator to Non-Safety Air :::::
(F-5) (1) (3) (f) Supply Isolation -l 2AF-0237 M2-0218-2 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air -0 (E-5) (3) Accumulator to Non-Safety Air OJ (1) ::J Supply Isolation 2AF-0238 M2-0218-2 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air (E-5) (1) (3) Accumulator to Non-Safety Air Supply Isolation 2AF-0239 M2-0218-2 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air (D-5) (1) (3) Accumulator to Non-Safety Air Supply Isolation 2AF-0240 M2-0218-2 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air (D-5) (1) (3) Accumulator to Non-Safety Air Supply Isolation 2AF-0291 M2-0218-2 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air (F-5) (1) (3) Accumulator to Non-Safety Air Supply Isolation
- 0 CD
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PAGE 8 of 11 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
--0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
GROUPS C Globe Valve / Air Operated z Fisher Model DBQ
=1
(/) FV-2456 M1-0206-1 LOW 2 3 B A O/C NIA ET/18MO FO/6YR PIT/ Pump Miniflow Palh/AFW
--"- (D-1) (1) MT/6YR 6YR Flowpath Boundary )> M2-0206-1 z (D-1) 0 FV-2457 M1-0206-1 LOW 2 3 B A O/C NIA ET/18MO FO/6YR PIT/ Pump Miniflow Path/AFW N
(D-3) (1) MT/6YR 6YR Flowpath Boundary M2-0206-1 0 (D-3) -u z GROUP 6 - Not Used. -u GROUP? --0 Gate Valve/ Manually Operated (/) Borg-Warner & Edwards Models AF-0042 M1-0206-1 LOW 6 3 B p C N/A N/A NIA PIT/ AFW Flowpath Boundary 32 ID (F-4) (1) 6YR ::J M2-0206-1 (F-4) AF-0041 M1-0206-1 LOW 8 3 B p 0 NIA N/A N/A PIT/ AFW Flowpath (E-4) (1) 6YR M2-0206-1 (E-4) AF-0054 M1-0206-1 LOW 6 3 B p 0 N/A N/A N/A PIT/ AFW Flowpath (E-3) (1) 6YR M2-0206-1 (E-3) AF-0055 M1-0206-1 LOW 6 3 B p C NIA N/A N/A PIT/ AFW Flowpath Boundary (F-3) (1) 6YR M2-0206-1 (F-3)
- 0 CD
0 TABLE 1 -AUXILIARY FEEDWATER 0
~ PAGE 9 of 11 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
---0 Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
AF-0066 M1-0206-1 LOW 6 3 B p 0 NIA N/A NIA PIT/ AFW Flowpath C (E-2) (1) 6YR z M2-0206-1
-I (E-2)
(/)
...... AF-0067 M1-0206-1 LOW 6 3 B p C N/A N/A N/A PIT/ AFW Flowpath Boundary )> (F-2) (1) 6YR z M2-0206-1 0 (F-2)
N GROUP 111 Globe Valve / Air Operated 0 Fisher Model ES & ET ---0 PV-2453A M1-0206 LOW 3 3 B A O/C NIA MT/6YR FO/6YR PIT/ AFW to SG Flowpath/AFW to z
---0 (B-4) (1) ET/1 SMO 6YR Faulted SG Flow Isolation ---0 M2-0206 (/)
(B-4) -I PV-2453B M1-0206 LOW 3 3 B A OIC NIA MT/6YR FO/6YR PIT/ AFW to SG Flowpath/AFW to ---0 Q) (B-2) (1) ET/1 SMO 6YR Faulted SG Flow Isolation ::i M2-0206 (B-2) PV-2454A M1-0206 LOW 3 3 B A O/C N/A MT/6YR FO/6YR PIT/ AFW to SG Flowpath/AFW to (B-1) (1) ET/1 SMO 6YR Faulted SG Flow Isolation M2-0206 (B-1) PV-2454B M1-0206 LOW 3 3 B A O!C N/A MT/6YR FO/6YR PIT/ AFW to SG Flowpath/AFW to (B-5) (1) ET/1 SMO 6YR Faulted SG Flow Isolation M2-0206 (B-5) HV-2459 M1-0206 LOW 3 3 B A O/C N/A MT/6YR FO/6YR PIT/ AFW to SG Flowpath/AFW to (B-4) (1) ET/1 SMO 6YR Faulted SG Flow Isolation M2-0206 (B-4) HV-2460 M1-0206 LOW 3 3 B A O/C N/A MT/6YR FO/6YR PIT/ AFW to SG Flowpath/AFW to
- 0 (B-3) (1) ET/18MO 6YR Faulted SG Flow Isolation CD M2-0206
- < (B-3)
+>-
0 TABLE 1 - AUXILIARY FEEDWATER 0
- s: PAGE10of11
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z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
A HV-2461 M1-0206 LOW 3 3 B A O/C N/A MT/6YR FO/6YR PIT/ AFW to SG Flowpath/AFW to C (B-2) (1) ET/18MO 6YR Faulted SG Flow Isolation z M2-0206
=i
(/) (B-2)
-'- HV-2462 M1-0206 LOW 3 3 B A O/C N/A MT/6YR FO/6YR PIT/ AFW to SG Flowpath/AFW to )> (B-5) (1) ET/18MO 6YR Faulted SG Flow Isolation z M2-0206 0 (B-5)
N 0
-0 z ""O ~
(/)
-l ""O iii"
- l
- 0 CD
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0 TABLE 1 -AUXILIARY FEEDWATER 0
~ PAGE 11 of 11
)> z 0 I NOTES m -u 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group. m )>
- ,;
- 2. DELETED C
z 3. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan. =i CJ) ....... 4. A Check Valve Condition Monitoring Plan has been established per ASME OM Code Appendix II for valves in this group. )> z 0 N 0
-u z -u -u CJ) -I -u OJ
- J
0 TABLE 2- COMPONENT COOLING WATER 0
~ PAGE 1 OF 8 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )> /\
HIGH SAFETY SIGNIFICANCE C Ball Valve/Air Operated z Fisher Model U
=i (f) PV-4552 M1-0229-A HIGH 3 3 B A N/A N/A N/A F0/18MO PIT/ Safety Chilled Water ....... (D-5) (2) 18MO Condenser Cooling Flow )> M2-0229-A Control z (E-5) 0 N PV-4553 M1-0229-B HIGH 3 3 B A N/A N/A N/A FO/18MO PIT/ Safety Chilled Water (D-5) (2) 18MO Condenser Cooling Flow M2-0229-B Control 0 (D-1) -0 CVCM GROUP 1-12 / 2-12 z -0 Swing Check Valve / Self Actuating -0 Borg-Warner Model 75500 (f)
CC-0003 M1-0229-A LOW 3 3 C A 0 N/A DD/12YR N/A N/A Surge Tank Emergency -I (C-1) (4) Makeup Flowpath -0 M2-0229 OJ
- i (C-1)
CC-0004 M1-0229-A LOW 3 3 C A C NIA DD/12YR N/A N/A Surge Tank Emergency (D-1) (4) Makeup Flowpath Boundary M2-0229 (E-1) CVCM Group X-5 Swing Check Valve/ Self Actuating Borg-Warner Model 75690 CC-0713 M1-0231-A LOW 8 2 A/C A C LT J/TS DD/12YR N/A N/A Containment Isolation (C-6) (4) (3) M2-0231 (C-6) GROUP 105 Nozzle Check Valve/ Self Actuating Circle Seal Model N162-180
- o 1CC-1079 M1-0216-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air CD (F-4) (1) (3) Accumulator to Non-Safety
- < Air Supply Isolation
~
0 TABLE 2 - COMPONENT COOLING WATER 0
$.'. PAGE 2 of 8 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coord.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
1CC-1080 M1-0216-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA NIA Safety-Related Air C (F-4) (1) (3) Accumulator to Non-Safety z Air Supply Isolation
=l 1CC-1081 M1-0216-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA NIA Safety-Related Air (f) ...... (F-4) (1) (3) Accumulator to Non-Safety )> Air Supply Isolation z 1CC-1082 M1-0216-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA NIA Safety-Related Air 0 (F-4) (1) (3) Accumulator to Non-Safety N
Air Supply Isolation 2CC-1091 M2-0216-B LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA NIA Safety-Related Air 0 (D-1) (1) (3) Accumulator to Non-Safety -0 Air Supply Isolation z
-0 2CC-1092 M2-0216-B LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA NIA Safety-Related Air -0 (D-1) (1) (3) Accumulator to Non-Safety (f)
Air Supply Isolation -I
-0 2CC-1093 M2-0216-B LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA NIA Safety-Related Air 0)
(D-1) (1) (3) Accumulator to Non-Safety ::; Air Supply Isolation 2CC-1094 M2-0216-B LOW 1/2 3 A/C A C LT/6YR CV/6YR NIA NIA Safety-Related Air (D-1) (1) (3) Accumulator to Non-Safety Air Supply Isolation GROUP 11 Piston Check Valve / Self Actuating Edwards Model 838YT1 and D36274T2 CC-0629 M1-0231 LOW 2 2 A/C A O/C LT J/TS CV/6YR NIA NIA Containment Penetration (C-4) (1) Thermal Relief/Containment M2-0231 Isolation (A-6) CC-0831 M1-0231 LOW 2 A/C A O/C LT J/TS CV/6YR NIA NIA Containment Penetration (C-4) (1) Thermal Relief/Containment M2-0231 Isolation (A-4)
- o (D
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0 TABLE 2 - COMPONENT COOLING WATER 0
~ PAGE 3 of 8 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-u Number (Coard.) Ranking Size Class gory tion Pas. Test Test Test Test Remarks m )>
GROUP12 C Swing Check Valve / Self Actuating z Edwards Model 24-670BTY
-i CC-0031 M1-0229-A LOW 24 3 C A O/C N/A CV/6YR N/A N/A CCW Flowpath/CCW Cf) ...... (E-3) (1) Flowpath Boundary )> M2-0229 z (B-4) 0 CC-0061 M1-0229-B LOW 24 3 C A O/C N/A CV/6YR NIA N/A CCW Flowpath/CCW N
(C-3) (1) Flowpath Boundary M2-0229 0 (F-4) -u z GROUP13 -u Stop Check Valve / Self Actuating -0 Edwards Model 3664T1 Cf) CC-0646 M1-0231-A LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier -i (D-4) (1) (3) Rupture Isolation -0 Q) M2-0231 :::J (D-4) CC-0657 M1-0231-A LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier (D-3) (1) (3) Rupture Isolation M2-0231 (D-3) CC-0687 M1-0231-A LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier (G-3) (1) (3) Rupture Isolation M2-0231 (G-3) CC-0694 M1-0231-A LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier (G-4) (1) (3) Rupture Isolation M2-0231 (G-4)
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PAGE 4 of 8 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""CJ Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
7' GROUP14 C Stop Check Valve/ Self Actuating z Edwards Model B36164B3
- j (f) 1CC-1075 M1-0231-A LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier
...... (G-4) (1) (3) Rupture Isolation )> 1CC-1076 M1-0231-A LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier z (G-3) (1) (3) Rupture Isolation 0
N 1CC-1077 M1-0231-A LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier (D-3) (1) (3) Rupture Isolation 1CC-1078 M1-0231-A LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier 0
""CJ (D-4) (1) (3) Rupture Isolation z ""CJ 2CC-0371 M2-0231 LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier ""CJ (G-4) (1) (3) Rupture Isolation ::::::
(f) 2CC-0372 M2-0231 LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier -I (F-3) (1) (3) Rupture Isolation ""CJ 2CC-0373 M2-0231 LOW 2 3 C A C N/A CV/6YR N/A N/A RCP Thermal Barrier ru
- J (D-3) (1) (3) Rupture Isolation 2CC-0374 M2-0231 LOW 2 3 C A C N/A CV/6YR N/A NIA RCP Thermal Barrier (D-4) (1) (3) Rupture Isolation GROUP15 Globe Valve / Air Operated Fisher Model DBQ HV-4631A M1-0230-A LOW 2 3 B A C N/A ET/18MO FC/6YR PIT/ Non-Safety Flowpath (D-3) (1) MT/6YR 6YR (Process Sample Cooling)
M2-0230-A Isolation (C-5) HV-4631B M1-0230-A LOW 2 3 B A C N/A ET/18MO FC/6YR PIT/ Non-Safety Flowpath (D-6) (1) MT/6YR 6YR (Process Sample Cooling) M2-0230-A Isolation (C-6)
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PAGE 5 of8 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""() Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
GROUP 109 C Globe Valve / Air Operated z Fisher Model DBQ
=i (f)
HV-4725 M1-0231 LOW 2 2 A A C LTJ/TS MT/6YR FC/6YR PIT/ Containment Isolation
....>. (C-5) (1) ET/18MO 6YR )> M2-0231-A z (F-3) 0 HV-4726 M1-0231 LOW 2 2 A A C LTJ/TS MT/6YR FC/6YR PIT/ Containment Isolation N (B-5) (1) ET/18MO 6YR M2-0231-A 0 (G-3) ""()
GROUP16 z
""()
Globe Valve/ Air Operated ""() Fisher Model ES ::::: (f) LV-4500 M1-0229-A LOW 3 3 B A O/C N/A ET/18MO FC/6YR PIT/ Surge Tank Emergency --l (C-2) MT/6YR 6YR ""() (1) Makeup Flowpath/lsolation M2-0229 w
- )
(C-1) LV-4500-1 M1-0229-A LOW 3 3 B A 0 NIA ET/18MO FO/6YR PIT/ Surge Tank Emergency (C-1) (1) MT/6YR 6YR Makeup Flowpath M2-0229 (C-1) LV-4501 M1-0229-A LOW 3 3 B A O/C N/A ET/18MO FC/6YR PIT/ Surge Tank Emergency (D-2) (1) MT/6YR 6YR Makeup Flowpath/lsolation M2-0229 (D-1) HV-4710 M1-0231 LOW 4 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation (B-1) (1) MT/6YR 6YR M2-0230-A (F-3) HV-4711 M1-0231 LOW 4 2 B A C NIA ET/18MO FC/6YR PIT/ Containment Isolation (B-2) (1) MT/6YR 6YR
- a M2-0230-A CD (F-5)
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0 TABLE 2 - COMPONENT COOLING WATER 0 s:
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PAGE 6 of8 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
GROUP 17 C Plug Valve / Air Operated z Tufline Model 166SW
--l X-PCV-H116A M1-0229-A LOW 3 B A N/A NIA N/A FO/6YR NIA UPS NC Condenser Cooling (J)
_,_ (A-4) (1) (2) Flow Control
)> X-PCV-H116B M1-0229-B LOW 3 B A NIA N/A N/A FO/6YR N/A UPS NC Condenser Cooling z (F-4) (1) (2) Flow Control 0
N GROUP18 Butterfly Valve/ Air Operated Fisher Model 9510 0
-0 FV-4650A M1-0230-A LOW 10 3 B A C N/A ET/18MO FC/6YR PIT/ Non-Safety Flowpath z (F-2) (1) MT/6YR 6YR (Ventilation Chillers, -0 M2-0230 Letdown Chiller) Isolation -0 (F-2) (J) --l FV-4650B M1-0230-B LOW 10 3 B A C N/A ET/18MO FC/6YR PIT/ Non-Safety Flowpath -0 (A-5) (1) MT/6YR 6YR (Ventilation Chillers, Ql M2-0230 Letdown Chiller) Isolation ::J (F-5)
FV-4536 M1-0229-A LOW 10 3 B A C N/A MT/6YR FC/6YR PIT/ CCW Flowpath Boundary (F-2) (1) ET/18MO 6YR M2-0229 (A-1) FV-4537 M1-0229-B LOW 10 3 B A C N/A MT/6YR FC/6YR PIT/ CCW Flowpath Boundary (B-2) (1) ET/18MO 6YR M2-0229 (G-1) GROUP 98 Butterfly Valve/ Manual Gear Posi-Seal Model 2144 CC-0109 M1-0229 LOW 18 3 B A O/C N/A ET/6YR N/A N/A RHR heat exchanger CCW (D-2) (1) (3) inlet valve (modified to M2-0229-A function as a restrictive
- 0 orifice)
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0 TABLE 2 - COMPONENT COOLING WATER 0 s::: PAGE 7 of 8
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z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )> /\
CC-0157 M1-0229 LOW 18 3 B A O/C N/A ET/6YR N/A N/A RHR heat exchanger CCW C (E-5) (1) (3) inlet valve (modified to z M2-0229-B function as a restrictive
--! (C-4) orifice)
(J)
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z 0 N 0
-0 z -0 -0 (J) -0 w
- J
- o (D
.i:,,.
0 TABLE 2 - COMPONENT COOLING WATER 0 s: )> PAGE 8 of 8 z 0 I NOTES m -0 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group. m )>
- ,;; 2. X-PCV-H116A, -H116B, UPS A/C Condenser Cooling Flow Control Valves; C These valves are exempt from lnservice Testing per ASME OM Code 2004 Edition, through 2006 Addenda, Subsection ISTC-1200. However, the valves are fail open by z accumulators. Therefore the fail open function is required to be tested per NUREG-1482 Rev. 1 paragraph 4.2.9.
--l (f) ...... PV-4552, -4553, Safety Chilled Water Condenser Cooling Flow Control Valves: )> These valves are included in the 1ST program based on PRA HSSC ranking (ER-EA-010 Rev. 2). These are exempt from the ASME OM code per ISTC 1200. The valve's z safety function is to modulate to control temperature. The valves are fail open by design, however they are not fail safe. Air accumulators are required to perform safety 0 N function of low temperature control upon loss of instrument air. Thus the testing should be commensurate with the safety significance. Therefore, a full stroke PIT and Fail-Open test should be done every 18 months. Since this is a self-revealing, in-process failure mode for normally operating equipment, this is considered an adequate test and 0 is a conservative approach. -0 z
-0
- 3. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan. -0 (f)
- 4. A Check Valve Condition Monitoring Plan has been established per ASME OM Code Appendix II for valves in this group. --l
-0 ru
- i
0 TABLE 3- CHILLED WATER (SAFETY & NON-SAFETY) 0 s: )> PAGE 1 OF 2 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator -u Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )> CVCM Group X-3 C Swing Check Valve / Self Actuating z Borg-Warner Model 75630 --l CH-0024 M1-0307-A LOW 6 2 A/C A C LTJ/TS DD/12YR N/A N/A Containment Isolation (J) __,_ (C-2) (3) (2) )> M2-0307 z (B-3) 0 CVCM GROUP 1-3 / 2-3 N Piston Check Valve/ Self Actuating Edwards Model 838YT1 0 CH-0300 M1-0311- LOW 3 C A 0 N/A DD/12YR N/A N/A Surge Tank Emergency -u M2-0311 (3) Makeup Flowpath z
-u (D-3) -u CH-0301 M1-0311- LOW 3 C A C N/A DD/12YR N/A N/A Surge Tank Emergency (J)
M2-0311 (3) Makeup Flowpath Boundary --l (F-3) -u OJ GROUP 20 ::::, Globe Valve/ Manually Operated Edwards Model 848YT1 CH-0302 M1-0311- LOW 3 B A O/C N/A ET/6YR N/A N/A Surge Tank Emergency M2-0311 (1) Makeup Flowpath/lsolation (D-3) CH-0305 M1-0311- LOW 3 B A O/C N/A ET/6YR N/A N/A Surge Tank Emergency M2-0311 (1) Makeup Flowpath/lsolalion (E-3)
0 TABLE 3- CHILLED WATER (SAFETY & NON-SAFETY) 0 s: )> PAGE 2 of2 z 0 NOTES I m ""O 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group. m )> 7' 2. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan. C z 3. A Check Valve Condition Monitoring Plan has been established per ASME OM Code Appendix II for valves in this group. =i (/) )> z 0 N 0
""O z ""O ""O
(/)
-l ""O ru
- l
0 TABLE 4 - CHEMICAL AND VOLUME CONTROL 0 s:
)>
PAGE 1 OF 8 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
--0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
CVCM GROUP X-11 C Swing Check Valve / Self Actuating z Westinghouse 08000CS8800000
---i (J) 8546 M1-0255 HIGH 8 2 C A 0 NIA DD/12YR NIA NIA ECCS Injection Flowpath &
_,,_ (C-6) (3) Boration Flowpath
)> M2-0254 C NIA DD/12YR NIA NIA ECCS Recirculation z (C-5) Flowpath Boundary 0
N CVCM GROUP X-20 Piston Check Valve/ Self Actuating Edwards Model 3674F316T / 3/4-inch 0
--0 XCS-0037 M1-0257 LOW 3/4 3 C A 0 NIA DD/16YR NIA NIA Pump Miniflow Path z (C-3) (3) --0 --0 XCS-0039 M1-0257 LOW 3/4 3 C A 0 NIA DD/16YR NIA NIA Pump Miniflow Path :::::
(J) (C-5) (3)
---i XCS-0041 M1-0257 LOW 3/4 3 C A 0 NIA DD/16YR NIA NIA Pump Miniflow Path --0 (C-4) (3) iii"
- i XCS-0044 M1-0257 LOW 3/4 3 C A 0 NIA DD/16YR NIA NIA Pump Miniflow Path (C-6) (3)
GROUP 22 Piston Check Valve / Self Actuating Edwards Model 3674F316T CS-8180 M1-0253 LOW 3/4 2 A/C A O/C LT J/TS CV/6YR NIA NIA Containment Penetration (B-4) (1) Thermal Relief/Containment M2-0255-1 Isolation (B-4) CS-8350A M1-0253 LOW 2 C A C NIA CVl6YR NIA NIA Reactor Coolant Pressure (C-6) (1) (6) Boundary M2-0255-1 (C-6) CS-8350B M1-0253 LOW 2 C A C NIA CV/6YR NIA NIA Reactor Coolant Pressure (G-6) (1) (6) Boundary
- a M2-0255-1 CD (G-6)
.J::,,.
0 TABLE 4- CHEMICAL AND VOLUME CONTROL 0 s:
)>
PAGE 2 of 8 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
7' CS-8350C M1-0253 LOW 2 C A C N/A CV/6YR N/A N/A Reactor Coolant Pressure C (G-3) (1) (6) Boundary z M2-0255-1
=i (J)
(G-3)
...... CS-8350D M1-0253 LOW 2 C A C N/A CV/6YR N/A N/A Reactor Coolant Pressure )> (C-3) (1) (6) Boundary z M2-0255-1 0 (C-3)
N N/A N/A N/A Reactor Coolant Pressure CS-8367A M1-0253 LOW 2 C A C CV/6YR (C-6) (1) DD/6YR Boundary 0 M2-0255-1 (6) ""O (C-6) z
""O CS-8367B M1-0253 LOW 2 C A C N/A CV/6YR N/A N/A Reactor Coolant Pressure ""O (G-6) (1) DD/6YR Boundary (J)
M2-0255-1 (6) -I (G-6) ""O N/A CV/6YR N/A N/A Reactor Coolant Pressure ru CS-8367C M1-0253 LOW 2 C A C :::J (G-3) (1) DD/6YR Boundary M2-0255-1 (6) (G-3) CS-8367D M1-0253 LOW 2 C A C N/A CV/6YR N/A N/A Reactor Coolant Pressure (C-3) (1) DD/6YR Boundary M2-0255-1 (6) (C-3) CS-8368A M1-0253 LOW 2 2 C A C N/A CV/6YR N/A N/A Containment Isolation (B-6) (1) DD/6YR M2-0255-1 (6) (B-6) CS-8368B M1-0253 LOW 2 2 C A C N/A CV/6YR N/A N/A Containment Isolation (E-6) (1) DD/6YR M2-0255-1 (6) (E-6)
- o CD
~ ~
0 TABLE 4 - CHEMICAL AND VOLUME CONTROL 0 s
}>
PAGE 3 of 8 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m }>
CS-8368C M1-0253 LOW 2 2 C A C NIA CV/6YR N/A NIA Containment Isolation C (F-3) (1) DD/6YR z M2-0255-1 (6)
=l (J)
(F-3)
...... CS-8368D M1-0253 LOW 2 2 C A C NIA CV/6YR NIA NIA Containment Isolation }> (B-3) (1) DD/6YR z M2-0255-1 (6) 0 (B-3)
N CS-8377 M1-0253-A LOW 2 C A C NIA CV/6YR N/A N/A Reactor Coolant Pressure (B-6) (1) DD/6YR Boundary 0 M2-0255 -0 (G-4) z
-0 CS-8442 M1-0255-2 LOW 2 2 C A 0 NIA CV/6YR N/A N/A Boration Flowpath -0 (F-5) (1) CVD/SYR (J)
M2-0255-2 -; (B-3) :g OJ CS-8473 M1-0257 LOW 2 3 C A O/C N/A CV/6YR NIA N/A Boralion Flowpath/Boralion :::J (C-4) (1) Flowpath Boundary M1-0257 (C-5) CS-8480A M1-0255-1 LOW 2 2 C A C N/A CV/6YR NIA NIA ECCS Flowpath Boundary (E-4) (1) (6) M2-0254 (E-5) CS-8480B M1-0255-1 LOW 2 2 C A C NIA CV/6YR N/A NIA ECCS Flowpath Boundary (E-5) (1) (6) M2-0254 (E-6) CS-8487 M1-0257 LOW 2 3 C A O/C N/A CV/6YR N/A NIA Boration Flowpalh/Boralion (C-4) (1) Flowpath Boundary M1-0257 (C-6)
- 0 CD
- =:::
.t,..
0 TABLE 4 - CHEMICAL AND VOLUME CONTROL 0 5'. PAGE 4 of 8
)>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""'O Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
GROUP 23 C Swing Check Valve I Self Actuating z Westinghouse CS8800000 Series
-, 8378A M1-0253-A LOW 3 C A 0 N/A CV/6YR N/A N/A Boration Flowpath (J) ...... (B-5) (1) (4) )> M2-0255 C N/A CV/6YR N/A N/A Reactor Coolant Pressure z (G-3) Boundary 0 83788 M1-0253-A LOW 3 C A 0 NIA CV/6YR N/A N/A Boration Flowpath N
(8-5) (1) (4) M2-0255 C N/A CV/6YR N/A N/A Reactor Coolant Pressure 0 (G-3) Boundary ""'O 8379A M1-0253-A LOW 3 C A 0 N/A CV/6YR N/A N/A Boration Flowpath z
""'O (8-5) (1) (4) ""'O CV/6YR M2-0255 C NIA N/A N/A Reactor Coolant Pressure (J)
(G-3) Boundary -, 83798 M1-0253-A LOW 3 C A 0 N/A CV/6YR N/A NIA Boration Flowpath ""'O (B-5) (1) (4) ru
- i M2-0255 C N/A CV/6YR N/A N/A Reactor Coolant Pressure (G-3) Boundary 8381 M1-0253-A LOW 3 2 A/C A 0 N/A CV/6YR N/A NIA Boration Flowpath (E-3) (1)
M2-0255 C LTJ/TS CV/6YR N/A N/A Containment Isolation (E-2) 8481A M1-0255-1 LOW 4 2 C A 0 N/A CV/6YR N/A N/A ECCS Flowpath & Boration (E-4) (1) Flowpath M2-0254 C N/A CV/6YR NIA N/A ECCS Flowpath Boundary (F-5) 84818 M1-0255-1 LOW 4 2 C A 0 N/A CV/6YR N/A NIA ECCS Flowpath & Boration (D-5) (1) Flowpath M2-0254 C N/A CV/6YR N/A NIA ECCS Flowpath Boundary (F-6) 8497 M1-0255-1 LOW 3 2 C A C N/A CV/6YR N/A N/A ECCS Flowpath Boundary
- 0 (D-2) (1) (6)
CD M2-0254 .t,.. (F-4)
0 TABLE 4 - CHEMICAL AND VOLUME CONTROL 0 s;: PAGE 5 of8
)>
z Test Parameters/Schedule 0 I Flow Safely Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""CJ Number (Coard.) Ranking Size Class gory tion Pas. Test Test Test Test Remarks m )>
A GROUP 24 C Globe Valve / Air Operated z CoQes-Vulcan Model D-100
=i
(/) FCV-0111A M1-0255-2 LOW 2 3 B p C N/A N/A N/A PIT/ Boralion Flowpath Boundary
.....>. (C-2) (1) 6YR )> M2-0255-2 z (C-2) 0 LCV-0459 M1-0253-A LOW 3 B A C N/A MT/6YR FC/6YR PIT/ Reactor Coolant Pressure N
(B-4) (1) ET/18MO 6YR Boundary M2-0253 (6) 0 (B-3) ""CJ LCV-0460 M1-0253-A LOW 3 B A C N/A MT/6YR FC/6YR PIT/ Reactor Coolant Pressure z
""CJ (B-4) (1) ET/18MO 6YR Boundary ""CJ M2-0253 (6)
(/) (A-3) -, 8145 M1-0253-A LOW 2 B A C N/A ET/18MO FC/6YR PIT/ Reactor Coolant Pressure 31 0) (C-6) (1) (6) 6YR Boundary :::, M2-0255 MT/6YR (F-4) 8146 M1-0253-A LOW 3 2 B p 0 N/A N/A N/A PIT/ Boration Flowpath (C-5) (1) 6YR M2-0255 (F-3) 8147 M1-0253-A LOW 3 2 B p 0 N/A NIA N/A PIT/ Boration Flowpath (C-5) (1) 6YR M2-0255 (F-3) 8153 M1-0253-A LOW B A C N/A ET/18MO FC/6YR PIT/ Reactor Coolant Pressure (E-1) (1) MT/6YR 6YR Boundary M2-0253 (B-5) 8154 M1-0253-A LOW B A C N/A ET/18MO FC/6YR PIT/ Reactor Coolant Pressure
- o (F-1) (1) MT/6YR 6YR Boundary CD M2-0253
- < (A-5)
.i,..
0 TABLE 4 - CHEMICAL AND VOLUME CONTROL 0 s:: PAGE 6 of 8
)>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator "lJ Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m
)>
8152 M1-0253-A LOW 3 2 A A C LTJ/TS MT/6YR FC/6YR PIT/ Containment Isolation C (F-2) (1) ET/18MO 6YR z M2-0253
--l (F-3)
(J)
....,,_ 8160 M1-0253-A LOW 3 2 A A C LTJ/TS MT/6YR FC/6YR PIT/ Containment Isolation )> (E-2) (1) ET/18MO 6YR z M2-0253 0 (E-3) 1')
GROUP25 Diaphragm Globe Valve/ Air Operated 0 ITT Model SD-C-102880 "lJ FCV-0110B M1-0255 LOW 2 2 B p C N/A N/A N/A PIT/ Boration Flowpath Boundary z
"lJ (F-5) (1) 6YR "lJ M2-0255-2 (J)
(F-3) -I FCV-0111B M1-0255 LOW 2 2 B p C N/A N/A N/A PIT/ Boration Flowpalh Boundary J2 Ill (G-3) (1) 6YR & Boron Dilution Flowpath ::i M2-0255-2 Isolation (during Mode 6) (E-2) GROUP 26 Globe Valve/ Solenoid Operated Valcor Model V526-5295-53 8202A M1-0255-1 LOW 2 B A C N/A ET/18MO FC/6YR PIT/ ECCS Flowpath Boundary & (E-1) (1) MT/6YR 6YR Isolation of VCT Cover Gas M2-0254 from Charging Pumps' (D-1) Suction Header 8202B M1-0255-1 LOW 2 B A C N/A ET/18MO FC/6YR PIT/ ECCS Flowpath Boundary & (E-1) (1) MT/6YR 6YR Isolation of VCT Cover Gas M2-0254 from Charging Pumps' (D-1) Suction Header 8210A M1-0255-1 LOW 2 B A C N/A ET/18MO FC/6YR PIT/ ECCS Flowpath Boundary & (D-1) (1) MT/6YR 6YR Isolation of PD Pump Suction
- u M2-0254 Stabilizer Gas Supply from CD (E-3) Charging Pumps' Suction
- c::
.i,. Header
0 TABLE 4- CHEMICAL AND VOLUME CONTROL 0 ~ PAGE 7 of8
- t>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator ""'O Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )> 8210B M1-0255-1 LOW 2 B A C NIA ET/18MO FC/6YR PIT/ ECCS Flowpath Boundary & C (D-1) (1) MT/6YR 6YR Isolation of PD Pump Suction z M2-0254 Stabilizer Gas Supply from =i (J) (E-3) Charging Pumps' Suction Header )> GROUP 27 z Ball Valve I Air Operated 0 Flowserve Model #043005382670801 "' HV-8220 M1-0255 (E-2) LOW (1) 2 B A C N/A ET/18MO MT/6YR FC/6YR PIT/ 6YR ECCS Flowpath Boundary & Isolation of VCT Cover Gas 0 M2-0254 from Charging Pumps' ""'O (D-2) Suction Header (upon low z
""'O VCT level) ""'O HV-8221 M1-0255 LOW 2 B A C NIA ET/18MO FC/6YR PIT/ ECCS Flowpath Boundary & (j)
(E-2) (1) MT/6YR 6YR Isolation of VCT Cover Gas -I M2-0254 from Charging Pumps' ""'O (D-2) Suction Header (upon low Ql
- l VCT level)
0 TABLE 4 - CHEMICAL AND VOLUME CONTROL 0 ~ PAGE 8 of 8 )> z 0 I NOTES m "U 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group. m )>
- 2. 8152, 8160, Letdown Line Containment Isolation Valves; are full-stroke closed exercised during a cold shutdown outage. These valves cannot be full-stroke close C exercised during plant operation because closing the valves isolates letdown flow from the RCS. In that letdown flow is used to preheat charging flow, isolation of letdown z
--l will cause thermal transients on the RCS charging nozzles, the regenerative heat exchanger and the letdown heat exchanger for which they are not designed. The (/) subject power operated valves cannot be part-stroke close exercised during plant operation. In the case of 8152, 8160, their stroke times are so short that any part-stroke )> exercise attempt would effectively be a full-stroke and thus is not performed for the reasons given above. These valves perform an 1STA-11 00(a) function in MODES 1,2, z 3, and 4. During an extended cold shutdown outage, exercise testing is required to be repeated every 3 months if the plant is in hot shutdown (MODE 4). 0 N
- 3. A Check Valve Condition Monitoring Plan has been established per ASME OM Code Appendix II for valves in this group.
0 "U
- 4. Charging service is alternated approximately every refueling outage between the normal charging line (containing check valves 8378A and 8378B) and the alternate z "U
charging line (containing check valves 8379A and 8379B) such that neither flowpath will be exposed to more than 60% of the thermal transients associated with stoppage "U and restart of charging flow. In accordance with ASME OM Code 2004 Edition, through 2006 Addenda, Subsection ISTC-3510, the pair of check valves in the charging line (/) which is out of service need not be open exercise tested as they are only relied on to perform their open boration path function when they are designated to be in service.
--l "U
However, they must have a valid, current open exercise tested prior to placing the charging line back in service. iii"
- i The check valves in both the normal and alternate charging lines are relied on to perform their closed reactor coolant pressure boundary function at all times when this function is required. Therefore, the close exercise test schedule must be maintained for all four check valves, regardless of which charging line is designated to be in service.
- 5. Not Used.
- 6. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan.
0 TABLE 5 - CONTAINMENT SPRAY 0 s:
)>
PAGE 1 OF 4 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
GROUP 28 C Swing Check Valve / Self Actuating z Borg-Warner Model 75810
- j (J) CT-0025 M1-0232-A LOW 16 2 C A O/C N/A CV/6YR NIA N/A Containment Spray Injection
...... (E-3) (1) Flowpath/Sump )> M2-0232-A Recirculation Flowpath z (E-3) Boundary 0
N CT-0077 M1-0232-A LOW 16 2 C A O/C N/A CV/6YR NIA N/A Containment Spray Injection (D-2) (1) Flowpath/Sump M2-0232-A Recirculation Flowpath 0 (D-2) Boundary -0 z CT-0142 M1-0232 LOW 16 2 A/C A O/C N/A CVD/8YR N/A N/A Containment Spray ""O (B-5) (1) (3) (2) Flowpath/Containment -0 M2-0232 Isolation (J) (B-5) --1 CT-0145 A/C A O/C N/A CVD/8YR N/A N/A Containment Spray
""O M1-0232 (B-2)
LOW (1) 16 2 (3) (2) Flowpath/Containment m M2-0232 Isolation (B-2) CT-0148 M1-0232-A LOW 16 2 C A 0 N/A CVD/8YR N/A NIA Sump Recirculation (E-4) (1) (2) Flowpath M2-0232-A (E-4) CT-0149 M1-0232-A LOW 16 2 C A 0 N/A CVD/8YR N/A N/A Sump Recirculation (D-3) (1) (2) Flowpath M2-0232-A (D-3) CVCM GROUP 1-13 / 2-13 Swing Check Valve/ Self Actuating Borg-Warner Model 75750 CT-0013 M1-0232 (E-2) LOW (4) 10 2 C A 0 N/A CV/16YR DD/16YR N/A N/A Containment Spray Flowpath I
- a M2-0232 CD
- < (E-2)
.J:>,.
0 TABLE 5- CONTAINMENT SPRAY 0
~ PAGE 2 of 4 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-u Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
C CT-0042 M1-0232 (E-3) LOW (4) 10 2 C A 0 N/A CV/16YR DD/16YR N/A N/A Containment Spray Flowpath I z M2-0232
=i (E-3)
(/)
)>
CT-0065 M1-0232 (E-5) LOW (4) 10 2 C A 0 N/A CV/16YR DD/16YR N/A NIA Containment Spray Flowpath I z M2-0232 0 (E-5) N CT-0094 M1-0232 (E-6) LOW (4) 10 2 C A 0 N/A CV/16YR DD/16YR N/A N/A Containment Spray Flowpath I 0 M2-0232 -u (E-6) z
-u CVCM GROUP 1-14 / 2-14 -u Swing Check Valve / Self Actuating (f)
Bl,lr n Jackson Model 422JDB1-002 -I CT-0047 M1-0232 LOW 4 2 C A 0 NIA CV/16YR N/A NIA Pump Miniflow Path -u (F-3) (4) DD/16YR OJ
- J M2-0232 (F-3)
CT-0048 M1-0232 LOW 4 2 C A 0 N/A CV/16YR NIA N/A Pump Miniflow Path (F-3) (4) DD/16YR M2-0232 (F-3) CT-0063 M1-0232 LOW 4 2 C A 0 NIA CV/16YR N/A N/A Pump Miniflow Path (E-5) (4) DD/16YR M2-0232 (E-5) CT-0064 M1-0232 LOW 4 2 C A 0 N/A CV/16YR N/A N/A Pump Miniflow Path (E-6) (4) DD/16YR M2-0232 (E-6)
- o CD
~ .J:>.
0 TABLE 5 - CONTAINMENT SPRAY 0
~ PAGE 3 of4 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
CVCM GROUP 1-25 / 2-25 C Swing Check Valve / Self Actuating z Edwards Model 3674F316T1
=i (J) )>
CT-0020 M1-0232 (F-2) M2-0232 LOW (4) 2 2 C A 0 N/A CV/16YR DD/16YR N/A N/A Chemical Additive Flowpath I z (F-2) 0 N CT-0031 M1-0232 (F-3) M2-0232 LOW (4) 2 2 C A 0 N/A CV/16YR DD/16YR N/A N/A Chemical Additive Flowpath I 0 (F-3) -0 z CT-0072 M1-0232 (F-4) M2-0232 LOW (4) 2 2 C A 0 N/A CV/16YR DD/16YR N/A N/A Chemical Additive Flowpath I -0
-0 (J)
(F-4) -l
-0 CT-0082 M1-0232 (F-5)
M2-0232 LOW (4) 2 2 C A 0 N/A CV/16YR DD/16YR N/A N/A Chemical Additive Flowpath I 0)
- i (F-5)
- 0 CD
.i,..
0 TABLE 5 - CONTAINMENT SPRAY 0 s PAGE4of4 J> z 0 NOTES I m -0 m J> 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group. A C 2. CT-0142, CT-0145, Containment Spray Header Check Valves; CT-0148, CT-0149, Containment Spray Pump Suction Check Valves from the Recirculation Sumps, are z disassembled at refueling outages to verify operability. Full or part-stroke exercising these valves with flow is not practicable. In the case of CT-0142 and CT-0145, the --i Cl) flowpath downstream of the valves is open to the Containment Building via the spray headers. No meaningful flow can be achieved through these valves without deluging the Containment and causing a significant cleanup problem and potential equipment damage. In the case of CT-0148 and CT-0149, the flowpath upstream of the valves is J> z open to the normally dry Containment Recirculation Sumps. Sump inventory only exists post-accident when the RWST has been depleted. Flooding the sumps for test 0 purposes would introduce contaminants into the Containment Spray System and the RWST which otherwise contain reactor quality water. Additionally, sump makeup N would be required at a high rate to protect the Containment Spray Pumps from a loss of suction. 0
-0
- 3. This valve has a water filled loop seal and is not required to be leakrate tested (see DBD-ME-013, Rev. 22, Attachment 1, Note 3). z
-0 -0
- 4. A Check Valve Condition Monitoring Plan has been established per ASME OM Code Appendix II for valves in this group. :::::
Cl)
--i -0 OJ
- J
0 TABLE 6- DEMINERALIZED & REACTOR MAKEUP WATER 0 s
)>
PAGE 1 OF 4 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""CJ Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )> /\
CVCM GROUP X-7 C Swing Check Valve/ Self Actuating z Borg Warner Model 75520
-I 200-0002 M2-0241 LOW 3 3 C A C NIA DD/12YR NIA NIA Non-Safety Makeup Line
(/) (C-2) (3) (2) Isolation
)> DD-0006 M1-0241-1 LOW 3 3 C A C NIA DD/12YR NIA NIA Non-Safety Makeup Line z (C-6) (3) (2) Isolation 0 M2-0241 N (C-2) 100-065 M1-0241-1 LOW 3 3 C A C NIA DD/12YR NIA NIA Non-Safety Makeup Line 0 (C-5) (3) (2) Isolation ""CJ CVCM GROUP X-4 z ""CJ Swing Check Valve / Self Actuating ""CJ Edwards Model 3674F316T1 (/)
200-0008 M2-0241 LOW 2 3 C A C NIA DD/12YR NIA NIA Non-Safety Makeup Line -I (F-1) (3) (2) Isolation ""CJ 0) 200-0009 M2-0241 LOW 2 3 C A C NIA DD/12YR NIA NIA Non-Safety Makeup Line ::J (D-1) (3) (2) Isolation 100-0064 M1-0241-1 LOW 2 3 C A C NIA DD/12YR NIA NIA Non-Safety Makeup Line (D-4) (3) (2) Isolation 100-0066 M1-0241-1 LOW 2 3 C A C NIA DD/12YR NIA NIA Non-Safety Makeup Line (C-4) (3) (2) Isolation CVCM GROUP X-10 Swing Check Valve / Self Actuating Borg Warner Model 75520 DD-0018 M1-0241-1 LOW 3 3 C A 0 NIA DD/12YR NIA NIA Pump Discharge Flowpath (E-2) (3) M2-0241 (E-4) XDD-0048 M1-0241-1 LOW 3 3 C A 0 NIA DD/12YR NIA NIA Pump Discharge Flowpath (E-2) (3)
- a CD
~ .i:,..
0 TABLE 6- DEMINERALIZED & REACTOR MAKEUP WATER 0 s:
)>
PAGE 2 of4 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
"'O Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
A GROUP 33 C Swing Check Valve / Self Actuating z Westinghouse & Worcester Controls Models
~ DD-0016 M1-0241-1 LOW 2 3 C A 0 N/A CV/6YR N/A N/A Pump Miniflow Path
(/) (D-3) (1) DD/6YR M2-0241
)>
z (F-5) 0 XDD-0044 M1-0241-1 LOW 2 3 C A 0 N/A CV/3YR N/A N/A Pump Miniflow Path N (D-2) (1) DD/6YR 8046 M1-0251 LOW 3 2 A/C A C LTJ/TS CV/6YR N/A N/A Containment Isolation 0 (E-2) (1) (2) "'O M2-0251 z
"'O (E-2) "'O GROUP 34
(/) Globe Valve/ Air Operated -, Fisher Model ES "'O M1-0242-B 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation 0) HV-5365 LOW 3 :J (E-2) (1) MT/6YR 6YR M2-0242 (C-3) HV-5366 M1-0242-B LOW 3 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (E-2) (1) MT/6YR 6YR M2-0242 (B-3) HV-6720 0311 LOW 3 B A 0 N/A ET/18MO F0/6YR PIT/ Surge Tank Emergency (D-3) (1) MT/6YR 6YR Makeup Flowpath LV-2478 M1-0206-2 LOW 3 3 B p C NIA N/A N/A PIT/ Non-Safety Makeup Line (E-1) (1) 6YR Isolation M2-0206-2 (E-1) GROUP35 Ball Valve/ Manually Operated
- o BNL Model HBV-B2-30-0006 CD 1D0-0020 M1-0241-1 LOW 3 3 B A C N/A ET/3YR N/A N/A Non-Safety Flowpath
'.' (F-2) (1) Isolation ..r,,..
0 TABLE 6- DEMINERALIZED & REACTOR MAKEUP WATER 0 s:
)>
PAGE 3 of4 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""CJ Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
XDD-0103 M1-0241-1 LOW 3 3 B A C NIA ET/3YR N/A N/A Non-Safety Flowpath C (F-2) (1) Isolation z
=i
(/)
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z 0 N 0
""CJ z ""CJ ""CJ
(/) J2 OJ
- J
- o CD
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0 TABLE 6 - DEMINERALIZED & REACTOR MAKEUP WATER 0 s: )> PAGE 4 of4 z NOTES 0 I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group. "U m 2. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan. )> A
- 3. A Check Valve Condition Monitoring Plan has been established per ASME OM Code Appendix II for valves in this group.
C z =i Cf) )> z 0 N 0
"U z "U ~
Cf)
-I
- g Ill
- i
0 TABLE 7 - DIESEL GENERATOR AUXILIARIES 0
~ PAGE 1 OF 4 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
7' GROUP 113 C Swing Check Valve/ Self Actuating z Edwards Model 838YT1
~ DO-0049 M1-0215-F LOW 2 3 C A 0 N/A CV/6YR N/A N/A Fuel Oil Flowpath (J) ...... (C-4) (1) CVD/BYR )> M2-0215-F z (C-4) 0 100-0050 M1-0215-G LOW 2 3 C A 0 NIA CV/6YR N/A N/A Fuel Oil Flowpath N (C-4) (1) CVD/BYR 2DO-0052 M2-0215-G LOW 2 3 C A 0 N/A CV/6YR N/A N/A Fuel Oil Flowpath 0 (C-4) (1) CVD/BYR -0 GROUP37 z -0 Swing Check Valve / Self Actuating -0 Clear Flow & Durabla Series (J)
DO-0157 M1-0215-B LOW 6 3 C A 0 N/A CV/6YR NIA N/A Lube Oil Flowpath ~ (C-6) (1) (2) J2 M2-0215-B OJ
- J (C-6)
DO-0158 M1-0215-B LOW 6 3 C A C N/A CV/6YR N/A N/A Lube Oil Flowpath Boundary (C-6) (1) (2) M2-0215-B (C-6) DO-0257 M1-0215-C LOW 6 3 C A 0 N/A CV/6YR N/A N/A Lube Oil Flowpath (C-6) (1) (2) M2-0215-C (C-6) DO-0258 M1-0215-C LOW 6 3 C A C N/A CV/6YR N/A N/A Lube Oil Flowpath Boundary (C-6) (1) (2) M2-0215-C (C-6)
- a CD
~
0 TABLE 7 - DIESEL GENERATOR AUXILIARIES 0
~ PAGE 2 of4 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-u Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
GROUP 38 C Swing Check Valve I Self Actuating z Edwards Model 838YT1
=i (J)
DO-0004 M1-0215-F LOW 2 3 C A OIC NIA CVl6YR NIA NIA Fuel Oil FlowpathlFuel Oil
....,. (F-5) (1) Flowpath Boundary M2-0215-F )>
z (F-5) 0 DO-0005 M1-0215-F LOW 2 3 C A OIC NIA CVl6YR NIA NIA Fuel Oil FlowpathlFuel Oil N (F-6) (1) Flowpath Boundary M2-0215-F (F-6) 0
-u DO-0016 M1-0215-G LOW 2 3 C A O/C NIA CVl6YR NIA NIA Fuel Oil FlowpathlFuel Oil z (F-5) (1) Flowpath Boundary -u -u M2-0215-G ::::::
(J) (F-5)
-I DO-0017 M1-0215-G LOW 2 3 C A OIC NIA CVl6YR NIA NIA Fuel Oil FlowpathlFuel Oil -u (F-6) (1) Flowpath Boundary o3"
- J M2-0215-G (F-6) 100-0062 M1-0215-D LOW 11/2 3 C A C NIA CVl3YR NIA NIA Safety-Related Air (F-6) (1) (2) Receiver to Non-Safety Air Supply Isolation 1DO-0063 M1-0215-D LOW 11/2 3 C A C NIA CVl3YR NIA NIA Safety-Related Air (E-1) (1) (2) Receiver to Non-Safety Air Supply Isolation 1DO-0064 M1-0215-E LOW 11/2 3 C A C NIA CVl3YR NIA NIA Safety-Related Air (F-6) (1) (2) Receiver to Non-Safety Air Supply Isolation 1DO-0065 M1-0215-E LOW 11/2 3 C A C NIA CVl3YR NIA NIA Safety-Related Air (E-1) (1) (2) Receiver to Non-Safety Air Supply Isolation 2DO-0074 M2-0215-D LOW 11/2 3 C A C NIA CVl3YR NIA NIA Safety-Related Air (E-1) (1) (2) Receiver to Non-Safety Air
- o CD Supply Isolation
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0 TABLE 7 - DIESEL GENERATOR AUXILIARIES 0 s:
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PAGE 3 of4 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
A 200-0075 M2-0215-O LOW 11/2 3 C A C N/A CV/3YR N/A N/A Safety-Related Air C (F-5) (1) (2) Receiver to Non-Safety Air z Supply Isolation
=i Cf) 200-0076 M2-0215-E LOW 11/2 3 C A C N/A CV/3YR N/A N/A Safety-Related Air
_,., (E-1) (1) (2) Receiver to Non-Safety Air Supply Isolation
)>
z 200-0077 M2-0215-E LOW 11/2 3 C A C N/A CV/3YR N/A N/A Safety-Related Air 0 (F-5) (1) (2) Receiver to Non-Safety Air N Supply Isolation 0
-0 z -0 -0 Cf) -0 ru
- I
- o CD
0 TABLE 7 - DIESEL GENERATOR AUXILIARIES 0 ~ PAGE 4 of4 )> z NOTES 0 I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group. -0 m 2. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan. )> C z =i (J) )> z 0 N 0
""'CJ z ""'CJ ""'CJ (J) -I ""'CJ ru
0 TABLE 8- FEEDWATER 0 s::
)>
PAGE 1 OF 7 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""CJ Number (Coard.) Ranking Size Class lion Pos. Test Test Test Test Remarks m gory )>
HIGH SAFETY SIGNIFICANCE C Globe Valve I Air Operated z Co~es Vulcan Model D-1000
=i CJ)
FCV-0510 M1-0203-1 HIGH 18 5 B A C N/A MT/CS FC/CS PIT/ Feedwater Isolation
...... (8-1) (3) 2YR )> M2-0203-1 z (8-1) 0 FCV-0520 M1-0203-1 HIGH 18 5 B A C N/A MT/CS FC/CS PIT/ Feedwater Isolation N (8-3) (3) 2YR M2-0203-1 0 (8-3) ""CJ FCV-0530 M1-0203-1 HIGH 18 5 B A C N/A MT/CS FC/CS PIT/ Feedwater Isolation z ""CJ (8-4) (3) 2YR ""CJ M2-0203-1 :::::
(f) (B-4) -I FCV-0540 M1-0203-1 HIGH 18 5 B A C N/A MT/CS FC/CS PIT/ Feedwater Isolation ""CJ (8-6) (3) 2YR ru
- J M2-0203-1 (8-6)
GROUP 41 Swing Check Valve / Self Actuating Borg-Warner Model 454KAB1 FW-0198 M1-0203-1A LOW 6 2 C A O/C N/A CV/6YR N/A N/A See Note 7 below (8-4) (1) M2-0203-1A (8-1) FW-0199 M1-0203-1A LOW 6 2 C A O/C N/A CV/6YR N/A N/A See Note 7 below (C-5) (1) M2-0203-1A (C-5) FW-0200 M1-0203-1A LOW 6 2 C A O/C N/A CV/6YR N/A N/A See Note 7 below (C-1) (1) M2-0203-1A
- a CD (C-4)
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0 TABLE 8- FEEDWATER 0 s
)>
PAGE2 of7 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
FW-0201 M1-0203-1A LOW 6 2 C A O/C N/A CV/6YR N/A N/A See Note 7 below C (C-3) (1) z M2-0203-1A
=i
(/) (C-3) _,_ FW-0202 M1-0203-1A LOW 6 2 C A O/C NIA CV/6YR N/A N/A See Note 7 below (C-4) (1)
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z M2-0203-1A (C-1) 0 N FW-0195 M1-0203-1A LOW 6 2 C A O/C N/A CV/6YR NIA NIA See Note 7 below (B-5) (1) M2-0203-1A 0
-0 (B-5) z FW-0196 M1-0203-1A LOW 6 2 C A O/C NIA CV/6YR NIA NIA See Note 7 below -0 -0 (B-1) (1) :::::
(/) M2-0203-1A
-I (B-4) -0 FW-0197 M1-0203-1A LOW 6 2 C A O/C N/A CV/6YR N/A N/A See Note 7 below ill
- l (B-2) (1)
M2-0203-1A (B-3) GROUP42 Swing Check Valve / Self Actuating Edwards Model 18-970BQTY FW-0070 M1-0203-1 LOW 18 2 C A C N/A CVD/8YR N/A N/A Main Feedline Break (C-4) (1) (2) Isolation M2-0203-1 (C-1) FW-0076 M1-0203-1 LOW 18 2 C A C N/A CVD/8YR N/A N/A Main Feedline Break (C-3) (1) (2) Isolation M2-0203-1 (C-3) FW-0082 M1-0203-1 LOW 18 2 C A C N/A CVD/8YR N/A N/A Main Feedline Break (C-1) (1) (2) Isolation
- o M2-0203-1 CD
- < (C-4)
.t,..
0 TABLE 8 - FEEDWATER 0
- s:: PAGE 3 of?
)>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator "lJ Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m
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A FW-0088 M1-0203-1 LOW 18 2 C A C NIA CVD/8YR NIA NIA Main Feedline Break C (C-6) (1) (2) Isolation z M2-0203-1
-l (C-6)
(/) GROUP 43 Gate Valve/ Hydraulic-Pneumatic Operated
)>
z Borg-Warner Model 75830 0 HV-2134 M1-0203-1 LOW 18 2 B A C NIA ET/18MO FC/6YR PIT/ Feedwater Isolation & N (D-1) (1) MT/6YR 6YR Containment Isolation M2-0203-1 0 (D-4) "lJ HV-2135 M1-0203-1 LOW 18 2 B A C NIA ET/18MO FC/6YR PIT/ Feedwater Isolation & z MT/6YR 6YR Containment Isolation "lJ (D-3) (1) "lJ M2-0203-1 ::::: (/) (D-3)
-l HV-2136 M1-0203-1 LOW 18 2 B A C NIA ET/18MO FC/6YR PIT/ Feedwater Isolation & "lJ (D-4) (1) MT/6YR) 6YR Containment Isolation ru
- J M2-0203-1 (D-1)
HV-2137 M1-0203-1 LOW 18 2 B A C NIA ET/18MO FC/6YR PIT/ Feedwater Isolation & (D-6) (1) MT/6YR 6YR Containment Isolation M2-0203-1 (D-6) GROUP 45 Globe Valve/ Air Operated Fisher Model SS120 HV-2185 M1-0203-1 LOW 3 2 B A C NIA ET/18MO FC/6YR PIT/ Feedwater Isolation & (D-2) (1) MT/6YR 6YR Containment Isolation M2-0203-1 (D-5)
- 0 (D
.j:>..
0 TABLE 8 - FEEDWATER 0
~ PAGE 4 of7 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator "U Number (Coard.) Ranking Size Class gory tion Pas. Test Test Test Test Remarks m
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HV-2186 M1-0203-1 LOW 3 2 C A C N/A ET/18MO FC/6YR PIT/ Feedwater Isolation & C (D-3) (1) MT/6YR 6YR Containment Isolation z M2-0203-1
--, (D-3)
(/) HV-2187 M1-0203-1 LOW 3 2 C A C N/A ET/18MO FC/6YR PIT/ Feedwater Isolation & (D-5) (1) MT/6YR 6YR Containment Isolation
)>
z M2-0203-1 0 (D-2) N HV-2188 M1-0203-1 LOW 3 2 C A C N/A ET/18MO FC/6YR PIT/ Feedwater Isolation & (D-6) (1) MT/6YR 6YR Containment Isolation M2-0203-1 0
"U (D-6) z LOW C N/A ET/18MO FC/6YR PIT/ Feedwater Isolation & "U 2-FV-2193 M2-0203-1 3 2 C A "U (D-4) (1) MT/6YR 6YR Containment Isolation :::::
(/) 2-FV-2194 M2-0203-1 LOW 3 2 C A C N/A ET/18MO FC/6YR PIT/ Feedwater Isolation & --, (D-3) (1) MT/6YR 6YR Containment Isolation "U 2-FV-2195 M2-0203-1 LOW 3 2 C A C N/A ET/18MO FC/6YR PIT/ Feedwater Isolation & ru (D-1) (1) MT/6YR 6YR Containment Isolation 2-FV-2196 M2-0203-1 LOW 3 2 C A C N/A ET/18MO FC/6YR PIT/ Feedwater Isolation & (D-5) (1) MT/6YR 6YR Containment Isolation GROUP46 Butterfly Valve / Air Operated ITT Conoflow Model 30006ZSFN 2-FV-2181 M2-0203-1A LOW 6 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary (B-4) (1) MT/6YR 6YR 2-FV-2182 M2-0203-1A LOW 6 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary (B-2) (1) MT/6YR 6YR 2-FV-2183 M2-0203-1A LOW 6 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary (B-1) (1) MT/6YR 6YR 2-FV-2184 M2-0203-1A LOW 6 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary (B-5) (1) MT/6YR 6YR
- o CD
~
0 TABLE 8 - FEEDWATER 0 s;:: PAGE 5 of7
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z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""CJ Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
GROUP 103 C Globe Valve/ Air Operated z Fisher Model ED
=i (J)
LV-2162 M1-0203-1 LOW 8 5 B A C N/A ET/18MO FC/6YR PIT/ Feedwater Isolation (B-2) (1) (4) 2YR M2-0203-1 MT/6YR
)>
z (B-5) 0 LV-2163 M1-0203 LOW 8 5 B A C N/A ET/18MO FC/6YR PIT/ Feedwater Isolation N (B-3) (1) (4) 2YR M2-0203 MT/6YR (B-3) 0
""CJ LV-2164 M1-0203 LOW 8 5 B A C NIA ET/18MO FC/6YR PIT/ Feedwater Isolation z ""CJ (B-5) (1) (4) 2YR ""CJ M2-0203 MT/6YR :::::
(/) (B-2)
-I LV-2165 M1-0203 LOW 8 5 B A C NIA ET/18MO FC/6YR PIT/ Feedwater Isolation ""CJ (B-6) (1) (4) 2YR ru
- J M2-0203 MT/6YR (B-6)
GROUP 104 Globe Valve / Manually Operated Edwards Model 848YT1 FW-0113 M1-0203-1 LOW 3/4 2 B p C N/A NIA N/A N/A Containment Isolation (F-3) (1) (5) M2-0203-1 (F-3) FW-0116 M1-0203-1 LOW 3/4 2 B p C N/A NIA N/A NIA Containment Isolation (B-3) (1) (5) M2-0203-1 (B-3) CVCM GROUP 2-17 Swing Check Valve / Self Actuating Borg-Warner Model 454KAB1
- o CD 2FW-0191 M2-0203-1 LOW 6 2 C A C N/A DD/16YR NIA NIA AFW Flowpath Boundary
- < (D-5) (6)
.i:=,..
0 TABLE 8- FEEDWATER 0
~ PAGE 6 of7 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
--0 Number (Coord.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )> ;;,;;; 2FW-0192 M2-0203-1 LOW A NIA DD/16YR NIA NIA 6 2 C C AFW Flowpath Boundary C (D-4) (6) z 2FW-0193 M2-0203-1 LOW 6 2 C A C NIA DD/16YR N/A N/A AFW Flowpath Boundary =i
(/) (D-2) (6)
...... 2FW-0194 M2-0203-1 LOW 6 2 C A C N/A DD/16YR NIA N/A AFW Flowpath Boundary )> (D-1) (6) z 0
N 0
--0 z --0 --0
(/)
-I --0 ru
- 0 CD
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0 TABLE 8 - FEEDWATER 0 s:
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PAGE 7 of7 z NOTES 0 I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group.
-0 m 2. FW-0070, FW-0076, FW-0082, and FW-0088, Main Feedwater Header Check Valves, are disassembled at refueling outages to verify operability as allowed by ASME OM )> ;:,;;; Code, 2004 Edition, through 2006 Addenda, Subsection ISTC-5220. Full or part stroking these valves is not practical. Leak testing of the valves has proven to be impractical due to the insufficient amount oftest makeup available versus the valve's size. Pursuant to Generic Letter 89-04 and NUREG-1482, verification of the C operability of the subject check valves will be performed through disassembly and inspection of one of the four valves at each refueling outage for each unit. The z disassembled valve will be verified to be capable offull-stroking and it will be verified that the internals of the valve are structurally sound (no loose or corroded parts). Also, =i (J) the disk will be manually exercised. Each valve will be disassembled, inspected and manually full-stroke exercised on a rotating basis at each refueling outage until the
_,,, entire group has been tested. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in the group in that unit will also be tested during the same outage. Once this is completed, the sequence of disassembly will be repeated unless extension of the interval can
)>
be justified. z 0 N 3. FCV-0510, FCV-0520, FCV-0530, FCV-0540, Feedwater Regulating Valves are full-stroke exercised during cold shutdown outages. These valves cannot be full-stroke exercised during plant operation because closing the valves interrupts feedwater flow resulting in severe steam generator level transients and, most likely, a turbine and reactor trip. These valves perform an ISTA-1100(a) function in MODES 1, 2, and 3. During an extended cold shutdown outage, exercise testing is required to be repeated 0 every 3 months if the plant is in hot standby (MODE 3). -0 z
-0
- 4. The ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan. -0 (J)
- 5. FW-0013, FW-0016, FW Line Section Sample Isolation Valves, are manual containment isolation valves. These valves are locked closed to establish containment isolation -I and AFW operability. There is no operational need to cycle these valves (passive). -0 ru
- 6. Check Valve Condition Monitoring Plan 2-17 has been established per ASME OM Code Appendix II for valves in this group.
- 7. The feedwater check valves in the auxiliary feedwater lines to the steam generator open to provide the AFW flowpath during design basis events. These valves must close in the event of a line break upstream of the outboard check valve in order to terminate a Condition Ill loss of feedwater event. In addition, these valve se also must close post-LOCA to protect the cold containment penetration during intermittent operation of AFW.
- u (D
.i:,..
0 TABLE 9 - MAIN STEAM 0
- s:: PAGE 1 OF 9
)>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-a Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
HIGH SAFETY SIGNIFICANCE C Globe Valve / Air Operated z Control Com[Jonents Model DRAG-M1G9-X7-X8BW-X8BW-XXCEE2
-I PV-2325 M1-0202 HIGH 8 2 B A O/C NIA MT/18MO FC/18MO PIT/ Steam Vent Flowpath (for (I) ...... (B-3) (3) (4) 2YR residual heat removal)/ )> M2-0202 Containment Isolation z (B-3) 0 PV-2326 M1-0202 HIGH 8 2 B A O/C NIA MT/18MO FC/18MO PIT/ Steam Vent Flowpath (for N (B-2) (3) (4) 2YR residual heat removal)/
M2-0202 Containment Isolation 0 (B-2) -a PV-2327 M1-0202 HIGH 8 2 B A O/C NIA MT/18MO FC/18MO PIT/ Steam Vent Flowpath (for z
-a (B-1) (3) (4) 2YR residual heat removal)/ -a M2-0202 Containment Isolation (I)
(B-1) -I PV-2328 M1-0202 HIGH 8 2 B A O/C NIA MT/18MO FC/18MO PIT/ Steam Vent Flowpath (for -a (B-4) (3) (4) 2YR residual heat removal)/ ru
- J M2-0202 Containment Isolation (B-4)
GROUP 112 Globe Valve / Hydraulic Pneumatic Operated Edwards Model 32-612(WCC}GJMMPTY HV-2333A M1-0202 LOW 32 2 B A C NIA ET/18MO FC/6YR PIT/ Steam Line Isolation & (F-4) (1) X MT/6YR 6YR Containment Isolation M2-0202 34 (F-4) HV-2334A M1-0202 LOW 32 2 B A C NIA ET/18MO FC/6YR PIT/ Steam Line Isolation & (F-2) (1) X MT/6YR 6YR Containment Isolation M2-0202 34 (F-2) HV-2335A M1-0202 LOW 32 2 B A C NIA ET/18MO FC/6YR PIT/ Steam Line Isolation & (F-1) (1) X MT/6YR 6YR Containment Isolation M2-0202 34
- o CD (F-1) 0
0 TABLE 9 - MAIN STEAM 0
~ PAGE 2 of9 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator 7J Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m
)>
- ,;; HV-2336A M1-0202 LOW 32 2 B A N/A ET/18MO FC/6YR PIT/ Steam Line Isolation &
C C (F-5) (1) X MT/6YR 6YR Containment Isolation z M2-0202 34
-I (F-5)
(/)
.....,_ GROUP 47 Swing Check Valve / Self Actuating )>
z Borg-Warner Model 75560-1 0 MS-0142 M1-0202 LOW 4 3 C A O/C N/A CV/6YR N/A N/A TDAFW Pump Steam Supply I\.) (B-5) (1) Flowpath/TDAFW Pump M2-0202 Steam Supply Flowpath Boundary 0 (B-5) 7J MS-0143 M1-0202 LOW 4 3 C A O/C N/A CV/6YR N/A N/A TDAFW Pump Steam Supply z Flowpath/TDAFW Pump 7J (B-6) (1) 7J M2-0202 Steam Supply Flowpath ::::: (/) (B-6) Boundary
-I GROUP 48 ~
Swing Check Valve / Self Actuating !ll
- i Circle Seal Model N162-180 2MS-0663 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-(F-2) (1) (2) lator to Non-Safety Air Supply Isolation 2MS-0664 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-(F-2) (1) (2) lator to Non-Safety Air Supply Isolation 2MS-0665 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-(F-1) (1) (2) lator to Non-Safety Air Supply Isolation 2MS-0666 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-(F-1) (1) (2) lator to Non-Safety Air Supply Isolation 2MS-0667 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-(F-1) (1) (2) lator to Non-Safety Air Supply Isolation
- 0 CD
~ 0
0 TABLE 9 - MAIN STEAM 0
~ PAGE 3 of9 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
2MS-0668 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-C (F-1) (1) (2) lator to Non-Safety Air z Supply Isolation
=i CJ) 2MS-0669 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-
_,,_ (F-2) (1) (2) lator to Non-Safety Air Supply Isolation
)>
z 2MS-0670 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-0 (F-2) (1) (2) lator to Non-Safety Air I\.) Supply Isolation 1MS-0680 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-0 (F-3) (1) (2) lator to Non-Safety Air ""O Supply Isolation z
""O 1MS-0681 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu- ""O (F-3) (1) (2) lator to Non-Safety Air :::::
CJ) Supply Isolation -I 1MS-0682 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu- ""O (F-3) (1) (2) lator to Non-Safety Air 0) Supply Isolation 1MS-0683 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A NIA Safety-Related Air Accumu-(F-3) (1) (2) lator to Non-Safety Air Supply Isolation 1MS-0684 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-(F-4) (1) (2) lator to Non-Safety Air Supply Isolation 1MS-0685 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-(F-4) (1) (2) lator to Non-Safety Air Supply Isolation 1MS-0686 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-(F-4) (1) (2) lator to Non-Safety Air Supply Isolation 1MS-0687 M2-0218-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-(F-4) (1) (2) lator to Non-Safety Air
- u Supply Isolation CD 0
0 TABLE 9 - MAIN STEAM 0 s::
)>
PAGE 4 of9 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
--0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )> ?\ GROUP49 C Globe Valve / Air Operated z Fisher Model BXA =i (J)
HV-2401A M1-0202-2 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary (C-2) (1) MT/6YR 6YR
..... M2-0202-2 )>
z (C-2) 0 HV-24018 M1-0202-2 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary N (C-3) (1) MT/6YR 6YR M2-0202-2 0 (C-3) --0 HV-2402A M1-0202-2 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary z MT/6YR 6YR
--0 (C-2) (1) --0 M2-0202-2 :::::
(J) (C-2) -l HV-2402B M1-0202-2 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary --0 (C-3) (1) MT/6YR 6YR ru
- i M2-0202-2 (C-3)
HV-2403A M1-0202-2 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary (B-5) (1) MT/6YR 6YR M2-0202-2 (B-5) HV-2403B M1-0202-2 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary (B-6) (1) MT/6YR 6YR M2-0202-2 (B-6) HV-2404A M1-0202-2 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary (C-5) (1) MT/6YR 6YR M2-0202-2 (C-5) HV-2404B M1-0202-2 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ AFW Flowpath Boundary (C-6) (1) MT/6YR 6YR
- a M2-0202-2 CD
- < (C-6) 0
0 TABLE 9- MAIN STEAM 0
$ PAGE 5 of9 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-u Number (Coord.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
HV-2405 M1-0202-2 LOW 3/4 2 B A C NIA ET/18MO FC/6YR PIT/ Containment Isolation & AFW C (F-2) (1) MT/6YR 6YR Flowpath Boundary z M2-0202-2
-i (F-2)
(/} HV-2406 M1-0202-2 LOW 3/4 2 B A C NIA ET/18MO FC/6YR PIT/ Containment Isolation & AFW (F-3) (1) MT/6YR 6YR Flowpath Boundary
)>
z M2-0202-2 0 (F-3) N HV-2407 M1-0202-2 LOW 3/4 2 B A C NIA ET/18MO FC/6YR PIT/ Containment Isolation & AFW (F-4) (1) MT/6YR 6YR Flowpath Boundary 0 M2-0202-2 -u (F-4) z HV-2408 M1-0202-2 LOW 3/4 2 B A C NIA ET/18MO FC/6YR PIT/ Containment Isolation & AFW
-u -0 (F-5) (1) MT/6YR 6YR Flowpath Boundary ::::::
(/} M2-0202-2 -i (F-5) -0 GROUP 50 iii"
- J Globe Valve / Air Operated Fisher Model DBQ HV-2409 M1-0202 LOW 2 2 B A C NIA MT/18MO FC/18MO PIT/ Steam Line Isolation &
(E-4) (1) 6YR Containment Isolation M2-0202 (E-4) HV-2410 M1-0202 LOW 2 2 B A C NIA MT/18MO FC/18MO PIT/ Steam Line Isolation & (E-3) (1) 6YR Containment Isolation M2-0202 (E-3) HV-2411 M1-0202 LOW 2 2 B A C NIA MT/18MO FC/18MO PIT/ Steam Line Isolation & (E-2) (1) 6YR Containment Isolation M2-0202 (E-2) HV-2412 M1-0202 LOW 2 2 B A C NIA MT/18MO FC/18MO PIT/ Steam Line Isolation & (E-5) (1) 6YR Containment Isolation
- o M2-0202 CD
~ (E-5) 0
0 TABLE 9- MAIN STEAM 0
~ PAGE 6 of9 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
GROUP 51 C Globe Valve / Air Operated z Fisher Model ES
--l HV-2397 M1-0202-2 LOW 3 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation &
(J) _,._ (F-2) (1) MT/6YR 6YR HELB Isolation & AFW M2-0202-2 Flowpath Boundary
)>
z (F-2) 0 HV-2397A M1-0202-2 LOW 3 2 B A C N/A ET/18MO FC/6YR PIT/ HELB Isolation & AFW N (F-2) (1) MT/6YR 6YR Flowpath Boundary M2-0202-2 0 (F-2) -0 HV-2398 M1-0202-2 LOW 3 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation & z MT/6YR 6YR HELB Isolation & AFW
-0 (F-3) (1) -0 M2-0202-2 Flowpath Boundary :::::
(J) (F-3) --l HV-2398A M1-0202-2 LOW 3 2 B A C N/A ET/18MO FC/6YR PIT/ HELB Isolation & AFW -0 (F-3) (1) MT/6YR 6YR Flowpath Boundary !l)
~
M2-0202-2 (F-3) HV-2399 M1-0202-2 LOW 3 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation & (F-4) (1) MT/6YR 6YR HELB Isolation & AFW M2-0202-2 Flowpath Boundary (F-4) HV-2399A M1-0202-2 LOW 3 2 B A C N/A ET/18MO FC/6YR PIT/ HELB Isolation & AFW (F-4) (1) MT/6YR 6YR Flowpath Boundary M2-0202-2 (F-4) HV-2400 M1-0202-2 LOW 3 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation & (F-5) (1) MT/6YR 6YR HELB Isolation & AFW M2-0202-2 Flowpath Boundary (F-5) HV-2400A M1-0202-2 LOW 3 2 B A C N/A ET/18MO FC/6YR PIT/ HELB Isolation & AFW (F-5) (1) MT/6YR 6YR Flowpath Boundary
- 0 M2-0202-2 CD
- < (F-5) 0
0 TABLE 9- MAIN STEAM 0
~ PAGE 7 of9 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coord.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
GROUP 52 C Globe Valve / Air Operated z Fisher Model ES
-! HV-2452-1 M1-0202 LOW 4 2 B A O/C N/A ET/18MO FO/6YR PIT/ TDAFW Pump Steam Supply
(/)
....,. (A-6) (1) MT/6YR 6YR Flowpath/Containment M2-0202 Isolation )>
z (A-6) 0 HV-2452-2 M1-0202 LOW 4 2 B A O/C N/A ET/18MO FO/6YR PIT/ TDAFW Pump Steam Supply N (A-5) (1) MT/6YR 6YR Flowpath/Containment M2-0202 Isolation 0 (A-5) ""O GROUP 53 - Not Used. z
""O GROUP 54 ""O Gate Valve / Manually Operated :::::
(/) Borg-Warner Model 75730-1 -! MS-0026 M1-0202 LOW 8 2 B A C N/A ET/6YR N/A N/A Steam Generator Tube ""O Rupture Isolation 0) (B-3) (1)
- i M2-0202 (Isolates PORV)
(B-3) MS-0063 M1-0202 LOW 8 2 B A C N/A ET/6YR N/A N/A Steam Generator Tube (B-2) (1) Rupture Isolation M2-0202 (Isolates PORV) (B-2) MS-0098 M1-0202 LOW 8 2 B A C N/A ET/6YR N/A N/A Steam Generator Tube (B-1) (1) Rupture Isolation M2-0202 (Isolates PORV) (B-1) MS-0134 M1-0202 LOW 8 2 B A C N/A ET/6YR N/A N/A Steam Generator Tube (B-5) (1) Rupture Isolation M2-0202 (Isolates PORV) (B-5)
- u CD 0
() TABLE 9- MAIN STEAM 0
$". PAGE 8 of9 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
GROUP 55 C Globe Valve/ Manually Operated z Edwards Model 4016 JPQYT
-{ HV-2333B M1-0202 LOW 4 2 B p C N/A N/A N/A PIT/ Steam Line Isolation &
(J)
....,,_ (F-4) (1) 6YR Containment Isolation M2-0202 )>
z (F-4) 0 HV-23348 M1-0202 LOW 4 2 B p C N/A N/A NIA PIT/ Steam Line Isolation & N (F-2) (1) 6YR Containment Isolation M2-0202 () (F-2) -0 HV-2335B M1-0202 LOW 4 2 B p C N/A N/A N/A PIT/ Steam Line Isolation & z 6YR Containment Isolation
-0 (F-1) (1) -0 M2-0202 :::::,
(J) (F-1) -{ HV-2336B M1-0202 LOW 4 2 B p C N/A NIA NIA PIT/ Steam Line Isolation & -0 (F-5) (1) 6YR Containment Isolation ru
- J M2-0202 (F-5)
GROUP 107 Gate Valve / Manually Operated Borg-Warner Model 75600-2 MS-0101 M1-0202 LOW 4 2 B A C N/A ET/6YR NIA N/A TDAFWP Steam Supply (A-6) (1) Flowpath/Containment M2-0202 Isolation (A-6) MS-0128 M1-0202 LOW 4 2 B A C N/A ET/6YR N/A NIA TDAFWP Steam Supply (A-5) (1) Flowpath/Containment M2-0202 Isolation (A-5)
- o CD
~ 0
0 TABLE 9 - MAIN STEAM 0
- 5'. PAGE 9 of9
)> z NOTES 0 I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group. ""O m 2. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan. )> A
- 3. ISTC-3510 Exercising Test Frequency - Power-operated relief valves shall be tested once per fuel cycle.
C z 4. ISTC-3560 Fail-Safe Valves - Valves with fail-safe actuators shall be tested in accordance with the exercising frequency in ISTC-3510. =i (f) )> z 0 I'.) 0
""O z ""O ""O
(/)
-I ""O 0)
0 TABLE 10- REACTOR COOLANT 0
~ PAGE 1 OF 4 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator 7J Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m
)>
HIGH SAFElY SIGNIFICANCE C Globe Valve / Air Operated z Westinghouse
- j PCV-0455A M1-0251 HIGH 3 B A O/C NIA MT/18MO FC/18MO PIT/ Post Accident Vent (f)
...,. (A-4) (4) (5) 2YR PathNent Path Isolation )> M2-0251 & Reactor Coolant Pressure z (A-4) Boundary 0 PCV-0456 M1-0251 HIGH 3 B A O/C NIA MT/18MO FC/18MO PIT/ Post Accident Vent N (A-4) (4) (5) 2YR PathNent Path Isolation M2-0251 & Reactor Coolant Pressure 0 (A-4) Boundary 7J GROUP 56 z
7J Diaphram Valve / Air Operated 7J ITT Model SD-C-102872 & SD-C-100598 :::::: (f) 8026 M1-0251 LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation --, (E-1) (1) MT/6YR 6YR 7J M2-0251 iii"
- J (E-1) 8027 M1-0251 LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (F-1) (1) MT/6YR 6YR M2-0251 (F-1) 8047 M1-0251 LOW 3 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (F-2) (1) MT/6YR 6YR M2-0251 (F-2)
GROUP 57 Globe Valve / Solenoid Operated Target Rock Model 79AB-001/79AB-008-1/79AB-001BB HV-3607 M1-0250 LOW 1 2 B A O/C N/A ET/18MO FC/6YR PIT/ Post Accident Vent (F-4) (1) MT/6YR 6YR PathNent Path Isolation M2-0250 (F-4)
- 0 CD
~
0 TABLE 10 - REACTOR COOLANT 0 s:
)>
PAGE2of4 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
HV-3608 M1-0250 LOW 2 B A O/C N/A ET/18MO FC/6YR PIT/ Post Accident Vent C (F-4) (1) MT/6YR 6YR PathNent Path Isolation z M2-0250
-I (F-4)
(J) _,_ HV-3609 M1-0251 LOW 2 B A O/C N/A ET/18MO FC/6YR PIT/ Post Accident Vent (B-4) (1) MT/6YR 6YR PathNent Path Isolation
)>
z M2-0251 0 (B-4) N HV-3610 M1-0251 LOW 2 B A O/C NIA ET/18MO FC/6YR PIT/ Post Accident Vent (B-4) (1) MT/6YR 6YR PathNent Path Isolation M2-0251 0
""O (B-4) z GROUP 109 ""O ""O Globe Valve / Solenoid Operated :::::
(J) Targe Rock Model 79AB-001 BB
-I 2-HV-3607 M2-0250 LOW 2 B A O/C N/A MT/CS FC/CS PIT/2YR Post Accident Vent ""O (F-4) (1) (3) (3) PathNent Path Isolation ru
- J 2-HV-3608 M2-0250 LOW 2 B A O/C N/A MT/CS FC/CS PIT/2YR Post Accident Vent (F-4) (1) (3) (3) PathNent Path Isolation GROUP 108 Check Valve/ Self Actuating Edwards Valve Model 838 YT1 Sl-0166 M1-0262 LOW 3/4 3 NC A C LT/6YR CV/6YR N/A N/A Safety Related Nitrogen (2) (F-5) (1) (6) Accumulator to Non-Safety M2-0263-B Nitrogen Supply Isolation (B-5)
Sl-0167 M1-0262 LOW 3/4 3 NC A C LT/6YR CV/6YR N/A N/A Safety Related Nitrogen (2) (F-5) (1) (6) Accumulator to Non-Safety M1-0263-B Nitrogen Supply Isolation (B-5) Sl-0168 M1-0262 LOW 3/4 3 NC A C LT/6YR CV/6YR N/A N/A Safety Related Nitrogen (2) (G-5) (1) (6) Accumulator to Non-Safety M2-0263-B Nitrogen Supply Isolation
- o CD (A-5)
.i:,.
0 TABLE 10 - REACTOR COOLANT 0 s:: )> PAGE 3 of4 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator '"U Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )> A Sl-0169 M1-0262 LOW 3/4 3 NC A C LT/6YR CV/6YR NIA NIA Safety Related Nitrogen C (2) (G-5) (1) (6) Accumulator to Non-Safety z M2-0263-B Nitrogen Supply Isolation -I (A-5) (/) )> z 0 I\J 0
'"U z "U "U
(/)
-I "U
ru
- J
0 TABLE 10 - REACTOR COOLANT 0
~ PAGE 4 of4 )>
z NOTES 0 I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group.
-u m )>
- 2. Sl-0166, Sl-0167, Sl-0168, Sl-0169 are part of Safety Injection System but are included in this table because they are more closely associated with Reactor Coolant System.
C 3. DELETED z
=i (J)
- 4. ISTC-351 O Exercising Test Frequency - Power-operated relief valves shall be tested once per fuel cycle. PCV-0455A & PCV-0456, Pressurizer Power Operated Relief
....,. Valves, are full-stroke exercised during cold shutdown outages. These valves cannot be fullstroke exercised during plant operation because cycling the valves introduces the unnecessary risk of inadvertently opening an RCS vent path which would result in a design basis event. The stroke length (and stroke time) of these valves is so short )>
that any part-stroke exercise attempt would effectively be a full-stroke and thus is not performed for the same reasons. These valves perform an ISTA-1100(a) function in z MODES 1, 2, 3, 4, 5, and 6 with the reactor vessel head on. During an extended cold shutdown outage, exercise testing is required to be repeated every 3 months if the 0 N plant is in cold shutdown or refueling (MODE 5 or 6 with the reactor vessel head on).
- 5. ISTC-3560 Fail-Safe Valves - Valves with fail-safe actuators shall be tested in accordance with the exercising frequency in ISTC-3510. 0
-u z
- 6. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan. -u
-0 (f) -I -0 ru
- J
- o CD
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0 TABLE 11 - RESIDUAL HEAT REMOVAL 0 s:
)>
PAGE 1 OF 3 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
HIGH SAFETY SIGNIFICANCE C Butterfly Valve / Air Operated z Fisher Model 7613
-l HCV-0606 M1-0260 HIGH 10 2 B p 0 N/A N/A N/A PIT/ ECCS Flowpath
(/) _,., (B-3) 2YR
)> M2-0260 z (B-3) 0 HCV-0607 M1-0260 HIGH 10 2 B p 0 NIA N/A N/A PIT/ ECCS Flowpath N (B-5) 2YR M2-0260 0
(B-5) -0 GROUP 115 z
-0 Gate Valve/ Manually Operated -0 Westinghouse Model 08000GH84000050 :::::
(/) 8717 M1-0260 LOW 8 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary -l (A-4) (1) 2YR -0 M2-0260 0)
- J (A-4)
GROUP 58 Swing Check Valve / Self Actuating Westinghouse Model 10000CS8400000 8730A M1-0260 LOW 10 2 C A O/C N/A CV/3YR N/A N/A ECCS & RHR Flowpath/ (B-3) (1) ECCS Injection Flowpath M2-0260 Boundary (B-3) 8730B M1-0260 LOW 10 2 C A O/C N/A CV/3YR N/A N/A ECCS & RHR Flowpath/ (B-5) (1) ECCS Injection Flowpath M2-0260 Boundary (B-5)
- a CD
.j:s..
0 TABLE 11 - RESIDUAL HEAT REMOVAL 0 s:
)>
PAGE 2 of3 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-u Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
GROUP 59 C Butterfly Valve / Air Operated z Fisher Model 7613
=i
(/) FCV-0618 M1-0260 LOW 8 2 B p C NIA NIA NIA PIT/ ECCS Flowpath Boundary
...... (C-3) (1) 6YR M2-0260 )>
z (C-3) 0 FCV-0619 M1-0260 LOW 8 2 B p C NIA NIA NIA PIT/ ECCS Flowpath Boundary N (C-6) (1) 6YR M2-0260 (C-6) 0
-u GROUP 60 z Angle Valve/ Air Operated -u -0 Fisher Model BXA :::::
(/) HV-4178 M1-0228 LOW 3/4 2 B A C NIA ET/18MO FC/6YR PIT/ RHR System to Non-Safety --l (2) (A-3) (1) MT/6YR 6YR Process Sampling System -0 M1-0228 Isolation ru
- J (A-3)
HV-4179 M1-0228 LOW 3/4 2 B A C NIA ET/18MO FC/6YR PIT/ RHR System to Non-Safety (2) (A-4) (1) MT/6YR 6YR Process Sampling System M2-0228 Isolation (A-4) HV-4182 M1-0228-1 LOW 3/4 2 B A C NIA ET/18MO FC/6YR PIT/ RHR System to Non-Safety (2) (B-4) (1) MT/6YR 6YR Post Accident Sampling M2-0228-1 System Isolation (B-4)
- o CD
~
0 TABLE 11 - RESIDUAL HEAT REMOVAL 0 s::: PAGE 3 of3 )> z NOTES 0 I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group. ""CJ m 2. HV-4178 and HV-4179 are part of Process Sampling System and HV-4182 is part of Post Accident Sampling System but are included in this table because their safety )> functions are more closely associated with Residual Heat Removal System. ?\ C z -I (f) )> z 0 N 0
""CJ z ""CJ ""CJ (f) -I ""CJ ru
- l
0 TABLE 12 - SPENT FUEL POOL COOLING 0
~ PAGE 1 OF 3 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )> ?\
GROUP 61 C Swing Check Valve / Self Actuating z Borg-Warner 75000 Series
-I XSF-0003 M1-0235 LOW 10 3 C A 0 N/A CV/3YR N/A N/A Spent Fuel Pool Cooling
(/)
->- (D-2) (1) DD/6YR Flowpath )> XSF-0004 M1-0235 LOW 10 3 C A 0 N/A CV/3YR N/A N/A Spent Fuel Pool Cooling z (D-5) (1) DD/6YR Flowpath 0 XSF-0160 M1-0235 LOW 3 3 C A 0 N/A CV/6YR N/A N/A Spent Fuel Pool Emergency N
(B-2) (1) DD/6YR Makeup Flowpath XSF-0180 M1-0235 LOW 3 3 C A 0 N/A CV/6YR N/A N/A Spent Fuel Pool Emergency 0 (B-4) (1) DD/6YR Makeup Flowpath ""O z GROUP 62 ""O Diaphram Valve/ Manual Operated ""O ITT Models (/) p LTJ/TS N/A N/A N/A Containment Isolation
-I SF-0011 M1-0235-2 LOW 4 2 A C ""O (A-1) (1)
M2-0235 ro
- l (B-3)
SF-0012 M1-0235-2 LOW 4 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (B-1) (1) M2-0235 (B-3) SF-0021 M1-0235-2 LOW 4 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (A-3) (1) M2-0235 (B-5) SF-0022 M1-0235-2 LOW 4 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (A-2) (1) M2-0235 (B-5) 1SF-0053 M1-0235-2 LOW 3 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (F-2) (1)
- 0 1SF-0054 M1-0235-2 LOW 3 2 A p C LTJ/TS N/A N/A NIA Containment Isolation CD
- < (F-2) (1) 0
0 TABLE 12 - SPENT FUEL POOL COOLING 0
- s:
)>
PAGE 2 of3 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )> ;:,;; p 2SF-0055 M2-0235 LOW 3 2 A C LTJ/TS N/A N/A N/A Containment Isolation C (B-2) (1) z 2SF-0056 M2-0235 LOW 3 2 A p C LTJ/TS N/A N/A N/A Containment Isolation -I (B-2) (1)
(f)
...... XSF-0161 M1-0235 LOW 3 3 B A O/C N/A ET/6YR N/A N/A Spent Fuel Pool Emergency )> (B-2) (1) Makeup Flowpath/lsolation z XSF-0179 M1-0235 LOW 3 3 B A O/C N/A ET/6YR N/A N/A Spent Fuel Pool Emergency 0 (B-4) (1) Makeup Flowpath/lsolation N
0
-0 z -0 -0 (f) -I -0 !ll
- i
- o CD 0
0 TABLE 12 - SPENT FUEL POOL COOLING 0
~ PAGE 3 of3 )>
z NOTES 0 I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group.
"U m )>
C z
-I (J) )>
z 0 N 0
"U z "U ~
(J)
-I J;!
w
- J
- o CD 0
0 TABLE 13 - SAFETY INJECTION 0 s
)>
PAGE 1 OF 13 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory tion Pas. Test Test Test Test Remarks m )>
HIGH SAFETY SIGNIFICANCE C Piston or Nozzle Check Valve/ Self Actuating z Edwards Model D36274F316JT1 or
=i
(/) Enertech Model ERV-Z _,,_ Sl-8819A M1-0263 HIGH 2 NC A O/C LT/TS CV/RF N/A N/A ECCS to CL/ RCS Press
)> (D-4) (2) (3) Boundary & CNTMT Isolation z M2-0263 0 (D-4)
N Sl-8819B M1-0263 HIGH 2 NC A O/C LT/TS CV/RF N/A N/A ECCS to CL/ RCS Press (C-4) (2) (3) Boundary & CNTMT Isolation 0 M2-0263 -0 (D-4) z
-0 Sl-8819C M1-0263 HIGH 2 NC A O/C LT/TS CV/RF N/A N/A ECCS to CL/ RCS Press -0 (B-4) (2) (3) Boundary & CNTMT Isolation :::::
(/) M2-0263 -I (E-4) -0 Sl-8819D M1-0263 HIGH 2 NC A O/C LT/TS CV/RF N/A N/A ECCS to CL/ RCS Press 0)
- i (F-4) (2) (3) Boundary & CNTMT Isolation M2-0263 (F-4)
HIGH SAFETY SIGNIFICANCE Swing Check Valve / Self Actuating Westinghouse Model 03000CS8800000 8815 M1-0261 HIGH 3 NC A O/C LT/TS CV/RF N/A N/A ECCS to Cold Legs Flowpath (B-2) (2) (3) & Boration Flowpath/Reactor M2-0261 Coolant Pressure Boundary & (E-4) Containment Isolation HIGH SAFETY SIGNIFICANCE Swing Check Valve / Self Actuating Westinghouse Model 06000CS8800000 8818A M1-0263 HIGH 6 NC A 0 LT/TS CV/RF N/A N/A ECCS to Cold Legs (E-4) (2) (5) Flowpath/Reactor Coolant M2-0263 CV/CS Pressure Boundary &
- 0 (C-4) C (5) Containment Isolation co
~
0 TABLE 13 - SAFETY INJECTION 0 s::
)>
PAGE 2 of 13 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
- ,;
- LT/TS CV/RF N/A N/A ECCS to Cold Legs 8818B M1-0263 HIGH 6 A/C A 0 C (D-5) (2) (5) Flowpath/Reactor Coolant z M2-0263 CV/CS Pressure Boundary &
-I (C-5) C (5) Containment Isolation (f) 8818C M1-0263 HIGH 6 A/C A 0 LT/TS CV/RF N/A N/A ECCS to Cold Legs (C-6) (2) (5) Flowpath/Reactor Coolant )>
M2-0263 CV/CS Pressure Boundary & z (E-6) C (5) Containment Isolation 0 i') 8818D M1-0263 HIGH 6 A/C A 0 LT/TS CV/RF N/A N/A ECCS to Cold Legs (C-6) (2) (5) Flowpath/Reactor Coolant CV/CS Pressure Boundary & 0 M2-0263 ""O (E-6) C (5) Containment Isolation z
""O HIGH SAFETY SIGNIFICANCE ""O Swing Check Valve / Self Actuating :::::
(f) Westinghouse Model 08000CS8200000 -I 8926 M1-0263-A HIGH 8 2 C A O/C N/A CV/RF N/A N/A ECCS Injection Flowpath/ ""O (G-2) (3) ECCS Recirculation Flowpath iii"
- i M2-0262 Boundary (A-2)
CVCM GROUP 1-2 / 2-2 Swing Check Valve / Self Actuating Westinghouse Model 10000CS8800000 8948A M1-0262 (A-2) HIGH 10 A/C A O/C LT/TS (2) DD/16YR (4) N/A N/A ECCS to Cold Legs Flowpath/ Reactor Coolant Pressure I M2-0263-B Boundary 8948B (G-2) M1-0262 (A-3) HIGH 10 A/C A O/C LT/TS (2) DD/16YR (4) N/A N/A ECCS to Cold Legs Flowpath/ Reactor Coolant Pressure I M2-0263-B Boundary 8948C (G-3) M1-0262 (A-5) HIGH 10 A/C A O/C LT/TS (2) DD/16YR (4) N/A N/A ECCS to Cold Legs Flowpath/ Reactor Coolant Pressure I M2-0263-B Boundary
- 0 (G-5)
CD ~
0 TABLE 13 - SAFETY INJECTION 0 s;:: PAGE 3 of 13
)>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
8948D M1-0262 (A-6) HIGH 10 A/C A O/C LT/TS (2) DD/16YR (4) N/A N/A ECCS to Cold Legs Flowpath/ Reactor Coolant Pressure I C z M2-0263-B Boundary
=i (J)
(G-6) _,,_ HIGH SAFETY SIGNIFICANCE Swing Check Valve / Self Actuating
)>
z Westinghouse Model CS Series 0 8922A M1-0263-A HIGH 4 2 C A O/C N/A CV/RF N/A N/A ECCS Flowpath/ECCS N (D-2) (3) Flowpath Boundary M2-0262 (D-2) 0
""O 8922B M1-0263-A HIGH 4 2 C A O/C N/A CV/RF N/A N/A ECCS Flowpath/ECCS z (D-3) (3) Flowpath Boundary ""O ""O M2-0262 ::::::
(J) (D-5) -l 8969B M1-0263-A HIGH 8 2 C A O/C N/A CV/RF N/A N/A ECCS Recirculation Flowpath/ECCS Flowpath 31 (F-3) (3) 0) Boundary (during Re- ::J M2-0262 (B-4) circulation with Loss of RHRA) HIGH SAFETY SIGNIFICANCE Swing Check Valve / Self Actuating Westinghouse Model CS Series 8841A M1-0263 HIGH 6 A/C A O/C LT/TS CV/RF N/A NIA ECCS to Hot Legs Flowpath/ (C-1) (2) (5) Reactor Coolant Pressure M2-0263 Boundary & Containment (E-1) Isolation 8841B M1-0263 HIGH 6 A/C A O/C LT/TS CV/RF N/A N/A ECCS to Hot Legs Flowpath/ (C-2) (2) (5) Reactor Coolant Pressure M2-0263 Boundary & Containment (E-2) Isolation 8949A M1-0263 HIGH 6 A/C A O/C LT/TS CV/RF N/A NIA ECCS to Hot Legs Flowpath/ (A-2) (2) (5) Reactor Coolant Pressure
- o M2-0263 Boundary (D
- ==:: (F-2)
.t,.
0 TABLE 13 - SAFETY INJECTION 0
- s:
)>
PAGE 4 of 13 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-u Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
89498 M1-0263 HIGH 6 A/C A O/C LT/TS CV/RF NIA NIA ECCS to Hot Legs Flowpath/ C (A-1) (2) (5) Reactor Coolant Pressure z M2-0263 Boundary
--, (G-1)
(/) _,._ 8949C M1-0263 HIGH 6 A/C A O/C LT/TS CV/RF NIA NIA ECCS to Hot Legs Flowpath/ (A-1) (2) (5) Reactor Coolant Pressure
)>
z M2-0263 (G-2) Boundary 0 N 8949D M1-0263 HIGH 6 A/C A O/C LT/TS CV/RF NIA NIA ECCS to Hot Legs Flowpath/ (A-3) (2) (5) Reactor Coolant Pressure M2-0263 Boundary 0
-u (F-3) z HIGH SAFETY SIGNIFICANCE -u -u Gate Valve / Manually Operated CJ)
Borg-Warner Model 82790 --, Sl-0047 M1-0261 HIGH 24 2 B p 0 NIA NIA NIA PIT/ ECCS Injection Flowpath -u (F-1) 2YR n:, M2-0261 (D-1) HIGH SAFETY SIGNIFICANCE Swing Check Valve / Self Actuating Edwards Models Sl-8905A M1-0263 HIGH 2 A/C A O/C LT/TS CV/RF NIA NIA ECCS to Hot Legs Flowpath/ (C-2) (2) (3) Reactor Coolant Pressure M2-0263 Boundary & Containment (D-2) Isolation Sl-89058 M1-0263 HIGH 2 A/C A O/C LT/TS CV/RF NIA NIA ECCS to Hot Legs Flowpath/ (D-1) (2) (3) Reactor Coolant Pressure M2-0263 Boundary & Containment (D-1) Isolation Sl-8905C M1-0263 HIGH 2 A/C A O/C LT/TS CV/RF NIA NIA ECCS to Hot Legs Flowpath/ (D-1) (2) (3) Reactor Coolant Pressure M2-0263 Boundary & Containment
- o (D-2) Isolation (D
=< .i:,..
0 TABLE 13 - SAFETY INJECTION 0
~ PAGE 5 of 13 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
"""CJ Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )> ;;,;;; Sl-8905D M1-0263 HIGH 2 AJC A O/C LT/TS CV/RF N/A N/A ECCS to Hot Legs Flowpalh/
C (C-3) (2) (3) Reactor Coolant Pressure z M2-0263 Boundary & Containment
--i (D-3) Isolation (f)
_,,_ GROUP 63 Swing Check Valve / Self Actuating
)>
z Edwards Models 0 Sl-8900A M1-0261 LOW 11/2 AJC A O/C LT/TS CV/6YR N/A N/A ECCS to Cold Legs Flowpath N (A-2) (1) (2) & Boralion Flowpath/Reactor M2-0261 Coolant Pressure Boundary (G-4) 0
"""CJ Sl-8900B M1-0261 LOW 11/2 AJC A O/C LT/TS CV/6YR N/A N/A ECCS to Cold Legs Flowpath z """CJ (A-1) (1) (2) & Boration Flowpath/Reactor """CJ M2-0261 Coolant Pressure Boundary :::::
(f) (G-4) -, Sl-8900C M1-0261 LOW 11/2 AJC A O/C LT/TS CV/6YR N/A N/A ECCS to Cold Legs Flowpath """CJ (A-3) (1) (2) & Boration Flowpath/Reactor Q)
- J M2-0261 Coolant Pressure Boundary (G-5)
Sl-8900D M1-0261 LOW 11/2 AIC A O/C LT/TS CV/6YR N/A N/A ECCS to Cold Legs Flowpath (A-2) (1) (2) & Boration Flowpath/Reactor M2-0261 Coolant Pressure Boundary (G-5) Sl-8919A M1-0263-A LOW 11/2 2 C A O/C N/A CV/6YR NIA N/A SI Pump Miniflow Path/ECCS (D-3) (1) Recirculation Flowpath M2-0262 Boundary (D-3) Sl-8919B M1-0263-A LOW 11/2 2 C A O/C N/A CV/6YR N/A N/A SI Pump Miniflow Path/ECCS (D-4) (1) Recirculation Flowpath M2-0262 Boundary (D-4) Sl-8968 M1-0262 LOW 2 AJC A C LTJ/TS CV/6YR N/A NIA Containment Isolation (F-1) (1) (6)
- o M2-0263-B (D
- < (A-1)
.f::>.
0 TABLE 13- SAFETY INJECTION 0
~ PAGE 6 of 13 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
GROUP 64 C Swing Check Valve / Self Actuating z Westinghouse Model CS Series
=i (f) 8958A M1-0263-B LOW 14 2 C A O/C N/A CV/3YR N/A N/A ECCS Injection Flowpath/ ...... (F-2) (1) ECCS Recirculation Flowpath M2-0263-A Boundary )>
z (B-2) 0 8958B M1-0263-B LOW 14 2 C A O/C N/A CV/3YR N/A N/A ECCS Injection Flowpath/ N (F-4) (1) ECCS Recirculation Flowpath M2-0263-A Boundary (B-3) 0
""O 8969A M1-0261 LOW 8 2 C A O/C N/A CV/6YR N/A N/A ECCS Recirculation z (E-4) (1) Flowpath/ECCS Flowpath ""O ""O M2-0261 Boundary (during Re- :::::
(f) (B-5) circulation with Loss of
--I RHRB)
CVCM GROUP 1-1 /2-1 31 Q) Swing Check Valve / Self Actuating ::J Westinghouse Model 10000CS8800000 8956A M1-0262 LOW 10 AIC A O/C LT/TS DD/16YR N/A N/A ECCS to Cold Legs Flowpath/ (B-2) (2) (4) Reactor Coolant Pressure M2-0263-B Boundary (E-2) 8956B M1-0262 LOW 10 A!C A O/C LT/TS DD/16YR N/A N/A ECCS to Cold Legs Flowpath/ f (B-3) (2) (4) Reactor Coolant Pressure M2-0263-B Boundary (E-3) 8956C M1-0262 LOW 10 AIC A O/C LT/TS DD/16YR N/A N/A ECCS to Cold Legs Flowpath/ f (B-5) (2) (4) Reactor Coolant Pressure M2-0263-B Boundary (E-5) 8956D M1-0262 LOW 10 AIC A O/C LT/TS DD/16YR N/A N/A ECCS to Cold Legs Flowpath/ f (B-6) (2) (4) Reactor Coolant Pressure
- 0 M2-0263-B Boundary CD
~ (E-6) .i:,..
0 TABLE 13 - SAFETY INJECTION 0 s;:: PAGE 7 of 13
)>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
--u Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )> ;,;; GROUP65 C Globe Valve / Air Operated z Co12es Vulcan Model D-100 (3/4-inch)(Active) -I 8823 M1-0263 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation &
(/) (E-3) (1) MT/6YR 6YR ECCS Flowpath Boundary M2-0263
)>
z (B-3) 0 8824 M1-0263 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation & N (E-2) (1) MT/6YR 6YR ECCS Flowpath Boundary M2-0263 0 (B-2) --u 8825 M1-0263 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation & z (E-1) (1) MT/6YR 6YR
--u ECCS Flowpath Boundary --u M2-0263
(/) (B-2)
-I 8843 M1-0261 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation & --u (B-2) (1) MT/6YR 6YR ECCS Flowpath Boundary ru
- i M2-0261 (E-4) 8871 M1-0262 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (B-1) (1) MT/6YR 6YR M2-0263-C (D-2) 8881 M1-0263 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation &
(E-1) (1) MT/6YR 6YR ECCS Flowpath Boundary M2-0263 (B-1) 8888 M1-0263-A LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation & (B-2) (1) MT/6YR 6YR ECCS Flowpath Boundary M2-0262 (E-2) 8890A M1-0263 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation & (E-4) (1) MT/6YR 6YR ECCS Flowpath Boundary
- o M2-0263 (D
.i:,..
0 TABLE 13 - SAFETY INJECTION 0 s:
)>
PAGE 8 of 13 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""CJ Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
7' 8890B M1-0263 LOW 3/4 2 B A C N/A ET/18MO FC/6YR PIT/ Containment Isolation & C (E-5) (1) MT/6YR 6YR ECCS Flowpath Boundary z M2-0263
=i (J)
(C-5) _,,_ 8964 M1-0262 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (A-1) (1) MT/6YR 6YR
)>
M2-0263-C z (E-2) 0 N GROUP 66 Globe Valve / Air Operated 0 Co~es Vulcan Model D-100 {1-inch & greater)(Active) ""CJ 8800A M1-0261 LOW 3 2 B A C N/A ET/18MO FC/6YR PIT/ RWST to Non-Safety z
""CJ (F-4) (1) MT/6YR 6YR Purification System ""CJ M2-0261 Isolation :::::
(/J (D-4) -l 8800B M1-0261 LOW 3 2 B A C N/A ET/18MO FC/6YR PIT/ RWST to Non-Safety J;! (F-4) (1) MT/6YR 6YR Purification System Dl
- i M2-0261 Isolation (D-3) 8880 M1-0262 LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (G-1) (1) MT/6YR 6YR M2-0263-B (A-1)
GROUP 67 Globe Valve I Air Operated Co~es Vulcan Model D-100 (3/4-inch)(Passive) 8877A M1-0262 LOW 3/4 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (C-2) (1) 6YR M2-0263-B (E-2) 8877B M1-0262 LOW 3/4 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (C-3) (1) 6YR M2-0263-B
- o (E-3)
CD .i:,..
0 TABLE 13 - SAFETY INJECTION 0
~ PAGE 9 of 13 )>
z Test Parameters/Schedule 0
- r: Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""CJ Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )> ;,;;; p 8877C M1-0262 LOW 3/4 2 B C N/A N/A N/A PIT/ ECCS Flowpath Boundary C (C-5) (1) 6YR z M2-0263-B --1 (E-5)
(f) p 88770 M1-0262 LOW 3/4 2 B C N/A N/A N/A PIT/ ECCS Flowpath Boundary (C-6) (1) 6YR
)>
z M2-0263-B 0 (E-6) N 8879A M1-0263 LOW 3/4 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (0-4) (1) 6YR M2-0263 0
""CJ (C-4) z p ""CJ 8879B M1-0263 LOW 3/4 2 B C N/A N/A N/A PIT/ ECCS Flowpath Boundary ""CJ (C-5) (1) 6YR :::::
(/) M2-0263
--1 (E-5) ""CJ 8879C M1-0263 LOW 3/4 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary Ill (B-5) (1) 6YR M2-0263 (F-5) 88790 M1-0263 LOW 3/4 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (B-6) (1) 6YR M2-0263 (E-6) 8882 M1-0261 LOW 3/4 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (B-3) (1) 6YR M2-0261 (F-3) 8889A M1-0263 LOW 3/4 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (B-2) (1) 6YR M2-0263 (F-2)
- 0 CD
~ ~
0 TABLE 13- SAFETY INJECTION 0
~ PAGE 10 of 13 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator 7J Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m
)> ;,;; p 88898 M1-0263 LOW 3/4 2 B C N/A N/A N/A PIT/ ECCS Flowpath Boundary C (B-1) (1) 6YR z M2-0263 =i (f)
(E-1) 8889C M1-0263 LOW 3/4 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (8-1) (1) 6YR
)>
z M2-0263 (F-1) 0 N 8889D M1-0263 LOW 3/4 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (B-3) (1) 6YR M2-0263 0 7J (F-3) z GROUP 68 7J 7J Globe Valve / Air Operated ::::: (f) Copes Vulcan Model D-100 (1-inch)(Passive)
-I 8875A M1-0262 LOW 1 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary 7J (E-1) (1) 6YR Ql M2-0263-B (C-1) 88758 M1-0262 LOW 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (E-2) (1) 6YR M2-0263-B (C-2) 8875C M1-0262 LOW 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (E-4) (1) 6YR M2-0263-B (C-4) 8875D M1-0262 LOW 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (E-5) 6YR M2-0263-B (C-5) 8878A M1-0262 LOW 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (E-2) (1) 6YR
- o M2-0263-B CD
- =::: (C-2)
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0 TABLE 13 - SAFETY INJECTION 0 s: )> PAGE11of13 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator -u Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )> A 88788 M1-0262 LOW 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary C (E-3) (1) 6YR z M2-0263-B -I (C-3) (/) p 8878C M1-0262 LOW 2 B C N/A N/A N/A PIT/ ECCS Flowpalh Boundary (E-5) (1) 6YR )> z M2-0263-B 0 (C-5) N 8878D M1-0262 LOW 2 B p C N/A N/A N/A PIT/ ECCS Flowpath Boundary (E-6) (1) 6YR 0 M2-0263-B -u (C-6) z
-u -u (J) -I -u OJ
- J
(") TABLE 13- SAFETY INJECTION 0
~ PAGE 12 or 13 )>
z(") NOTES I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group.
"'Cl m )> 2. The tes! frequency requin!ments ofTer.hn1cal Spet11fit.c1lJon SR 3 4 14 1 apply for leak testi ng of 8815; 88 18A. B, C. O: S1-8819A, 8, C. D, 8841A, B; Sl-8900A. B, C. D; S1-A 8905A, B. C, 0, 8948A, B, C, D: 6949A, 8 , C, D; 8956A, B, C, D. The Technical Specificahon .S~ 3..114 *, test f~uency requiremenIs are more restrictive than the test frequency requirements of ASME OM Code 2004 Edition. 1hrough 2006 Addenda, Subsection ISTC-3630.
C z 3. 8815 High Head Safety Injection Flowpa!h Check Valve: S1-8819A. B, C, D, 8926, 89698, 6922A. B. and S1-8905A. B. C,D. 8949A and D Intermediate Head Safety
~ Injection F!owpalh Check Valves are full-stroke exercised al refueling outages. These valves cannot be full stroke open exercised during plant operation or during cold shutdowns because the Oowpaths discharge into the RCS.
z In the case of the High Head subsystem. the valves cannot be lull-stroke exercised during plant operation because the high RCS pressure will not allow the maximum 0 required injection flowrate to be achieved. I'-> In the case of the Intermediate Head subsystems. ihe 11alves cannot be full stroke exercised during plan! operation because the relatively higher pressure of the Reactor (") Coolanl Syslern will not allow forward fiow through these paths. (An exception to \his is valve 8926 which lies In \he SI Pumps* miniHow path and thus 1s part-stroke open "'Cl exercised quarterly during pump tests.) The check valves in the intermediate head injection paths cannot be full-stroke exercised at cold shutdowns using the Safety z
"'Cl Injection Pumps because the resulting high flowrates arid pressures could challenge the RCS Cold Overpressure Mitlgaliori System. This leak testing is not practicable lo perform at cold Shl1ldowns due to its complexity and critical path nature Such testing would prevent lhe immediate return of a shutdown unit to power operation which is ~
CJ) contrary to the intent of ASME OM Code 2004 Edition, through 2006 Addenda. Subsection ISTC-3522. -i The subject check valves are full-stroke closti exercised at refueling outages at the same frequency as the full-stroke open exercise for the reasons described above. 32 Ill
- J 4, Valves 8956A, B. C. D. 8948A, B. C, and D test interval and method per ASME OM Coe Appendix IJ. Check Valve Condition Monitoring.
- 5. 8818A, B, C, 0, 8841 A, B, 89498, and C Low Head Safety lnjec1ion Flowpalh Check Valves, are full-stroke exercised al refueling outages to verify operability. These valves cannot be full or oarl-stroke open exercised during plant operation because the relatively higher pressure of the Reactor Coolant System will not allow forward flow through these paths, Pan-stroke exercising oflhese check valves during plant operation via the SI test header is not practicable because this path yields ftowrales too small (approximately 5 gpm) to be meaningful for assessing the operational readiness of these valves, II is not practicable to full stroke exercise these valves at cold shutdowns because the acoustic emission testing needed to verify the valves go full-open requires both Residual Heal Removal Pumps running and all Reactor Coolant Pumps secured to perform a satisfactory test. Both Residual Heat Removal Pumps are required to fiow through a single SI header to achieve the hydraulic transient necessary to create lhe acoustic signature. During the test Residual Heal Removal flow must be secured. The Reactor Coolant Pumps must be secured to lower background noise suffi~ently to record the acoustic signature.
Non-intrusive testing technkJues. such as the acoustic emission method applied here is considered "other po5itive means'* as defined in ASME OM Code 2004 Edition. through 2006 Addenda, Subsection ISTC-3520. During 1he initial acoustic emission testing for these valves, the system flow conditions were established to cause !he valves to fully s1roke. During subsequent testing, all 11alves shalf be fully stroked al repeatable system conditions, The acoustic emission monitoring or the valves, however, will only be performed on one 11alve per group per outage on a rotating schedule each time testing 1s performed (a sampling program). This method is applied to the following group of four valves: 8818A, B, C, D. If problems are round with the sample valve, all valves in the gruup must be tested using acoustic emission monitoring during
- 0 the same outage. An alternative would be to perform acoustic emission tesling on all valves list~d above instead of measuring flow conditions. Either method is acceptable.
(l) .c,..
0 TABLE 13 - SAFETY INJECTION 0 s:
)>
PAGE 13 of 13 z In addition to full-stroke open exercising as described above, the subject check valves are part-stroke exercised open and full-stroke exercised closed during cold shutdown 0 outages because acoustic emission monitoring is not required for these tests. These valves perform an ISTA-11 00(a) function in MODES 1,2,3,4,5, and 6. During an I m extended cold shutdown outage, 8818A, B, C, D, part-stroke open exercise testing is required to be repeated every 3 months while the plant is in cold shutdown or refueling "lJ (MODES 5 or 6). m
)> ;,;; 6. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan.
C z
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0 TABLE 14- SERVICE WATER 0
~ PAGE 1 OF 1 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
Group 116 C Swing Check Valve / Self Actuating z CRANE DUO-CHEK MODEL G15 BAF-PL
--i SW-0373 M1-0233 LOW 24 3 C A O/C N/A CV/6YR N/A N/A Service Water Flowpath/
(/)
...... (D-3) (1) Backflow Prevention (lo )> M2-0233 facilitate pump restart) &
z (B-3) Service Water Flowpath 0 Boundary (following pump I\.) failure) SW-0374 M1-0233 LOW 24 3 C A O/C N/A CV/6YR N/A N/A Service Water Flowpath/ 0 (E-3) (1) Backflow Prevention (to -0 M2-0233 facilitate pump restart) & z (D-3) Service Water Flowpath
-0 -0 Boundary (following pump :::::
(/) failure)
--i HIGH SAFETY SIGNIFICANCE -0 Nozzle Check/ Self Actuating ru
- i Enertech Model DRV-Z SWVAVB-01 M1-0234 HIGH 2 3 C A O/C N/A CV/3MO N/A N/A Vent Path (for water hammer (A-6) prevention)/Flowpath M2-0234 Boundary (A-6)
SWVAVB-02 M1-0234 HIGH 2 3 C A O/C N/A CV/3MO N/A N/A Vent Path (for water hammer (A-1) prevention)/Flowpath M2-0234 Boundary (A-1)
- 0 CD
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0 TABLE 15-VENTILATION (CONTROL ROOM AIR CONDITIONING) 0
~ PAGE 1 OF 2 )>
z 0 I Test Parameters/Schedule m Safety Fail Position "lJ Flow m
)>
Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks A C GROUP 106 z Check Valve / Self Actuating
=i (J) Circle Seal Model N162-180 --"- 1Cl-0644 M1-0216-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu- )> (1) (B-2) (3) (2) lator to Non-Safety Air z Supply Isolation 0
1Cl-0645 M1-0216-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu-N (1) (B-2) (3) (2) lator to Non-Safety Air Supply Isolation 0 LT/6YR CV/6YR N/A Safety-Related Air Accumu-
"lJ 1Cl-0646 (1)
M1-0216-1 (B-5) LOW (3) 1/2 3 A/C A C (2) N/A lator to Non-Safety Air z
"lJ Supply Isolation "lJ 1Cl-0647 M1-0216-1 LOW 1/2 3 A/C A C LT/6YR CV/6YR N/A N/A Safety-Related Air Accumu- (f)
(1) (B-5) (3) (2) lator to Non-Safety Air -l Supply Isolation "lJ ru
- iJ CD 0
0 TABLE 15-VENTILATION (CONTROL ROOM AIR CONDITIONING) 0
~ PAGE 2 of2 )>
z NOTES 0 I m 1. 1Cl-0644, 1Cl-0645, 1Cl-0646, 1Cl-0647 are part of Instrument Air System but are included in this table because their safety function is more closely associated with "U Control Room Air Conditioning System. m
)>
- 2. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan.
C 3. A risk informed-staggered test basis (RI-STB) shall be established for the valves within the specified group. z
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0 TABLE 16 - VENTS & DRAINS 0 s
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PAGE 1 OF 2 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
7\ GROUP 69 C Swing Check Valve / Self Actuated z Edwards Model 838YT1
-I VD-0003 M1-0236-B LOW 2 3 C A O/C NIA CV/6YR NIA NIA Sump Discharge Flowpath /
(JJ
...... (F-2) (1) Sump Discharge Flowpath )> M2-0236-B Boundary z (F-2) 0 VD-0004 M1-0236-B LOW 2 3 C A O/C NIA CV/6YR NIA NIA Sump Discharge Flowpath /
N (F-2) (1) Sump Discharge Flowpath M2-0236-B Boundary 0 (F-2) ""O VD-0011 M1-0236-B LOW 2 3 C A O/C NIA CV/6YR NIA NIA Sump Discharge Flowpath / z
""O (C-5) (1) Sump Discharge Flowpath ""O M2-0236-B Boundary :::::
(JJ (C-5) -I VD-0012 M1-0236-B LOW 2 3 C A O/C NIA CV/6YR NIA NIA Sump Discharge Flowpath / ""O Sump Discharge Flowpath 0) (C-5) (1)
- s M2-0236-B Boundary (C-5)
GROUP 110 Diaphram Valve/ Air Operated ITT Model SD-C-105925 HV-5157 M1-0238 LOW 4 2 A A C LTJ/TS MT/6YR FC/6YR PIT/ Containment Isolation (B-6) (1) ET/18MO 6YR M2-0238 (B-6) HV-5158 M1-0238 LOW 4 2 A A C LTJ/TS MT/6YR FC/6YR PIT/ Containment Isolation (B-6) (1) ET/18MO 6YR M2-0238 (B-6)
- 0 CD
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0 TABLE 16-VENTS & DRAINS 0
$'. PAGE 2 of2 )>
z NOTES 0 I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group.
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0 TABLE 17 - MISCELLANEOUS CONTAINMENT ISOLATION VALVES 0 s::
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PAGE 1 OF 9 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
--0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
GROUP 70 C Swing Check Valve/ Self Actuated z Borg-Warner 75000 Series
=i
(/) CA-0016 M1-0216-A LOW 3 2 A/C A C LTJ/TS CV/6YR N/A N/A Containment Isolation
...... (F-2) (1) (4) )> M2-0216-A z (F-2) 0 Cl-0030 M1-0216-A LOW 3 2 A/C A C LTJ/TS CV/6YR N/A N/A Containment Isolation N (F-5) (1) (4)
M2-0216-B 0 (F-2) ""CJ GROUP 71 z
""CJ Globe Valve / Air Operated ""CJ Fisher Model BXA :::a
(/) HV-4165 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation -I (B-2) (1) MT/6YR 6YR ""CJ M2-0228 ru (B-2) HV-4166 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (B-1) (1) MT/6YR 6YR M2-0228 (B-1) HV-4167 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (C-1) (1) MT/6YR 6YR M2-0228 (C-1) HV-4168 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (B-2) (1) MT/6YR 6YR M2-0228 (B-2) HV-4169 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (B-2) (1) MT/6YR 6YR M2-0228
- a (D (B-2)
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0 TABLE 17 - MISCELLANEOUS CONTAINMENT ISOLATION VALVES 0 s::
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PAGE 2 of 9 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""'O Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
HV-4170 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation C (B-2) (1) MT/6YR 6YR z M2-0228
-i (8-2)
(f) HV-4171 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (B-3) (1) MT/6YR 6YR
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z M2-0228 0 (B-3) N HV-4172 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (8-3) (1) MT/6YR 6YR M2-0228 0
""'O (B-3) z LTJ/TS ET/18MO FC/6YR Containment Isolation ""'O HV-4173 M1-0228 LOW 3/4 2 A A C PIT/ ""'O (B-3) (1) MT/6YR 6YR :::::
(f) M2-0228 -i (B-3)
""'O HV-4174 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation Ill
- J (B-3) (1) MT/6YR 6YR M2-0228 (B-3)
HV-4175 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (C-2) (1) MT/6YR 6YR M2-0228 (C-2) HV-4176 M1-0228 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (C-1) (1) MT/6YR 6YR M2-0228 (C-1) HV-7311 M1-0264 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (D-4) (1) MT/6YR 6YR M2-0264 (D-4)
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0 TABLE 17- MISCELLANEOUS CONTAINMENT ISOLATION VALVES 0 s::
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PAGE 3 of9 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator 7J Number (Coard.) Ranking Size Class gory tion Pas. Test Test Test Test Remarks m
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A HV-7312 M1-0264 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation C (D-3) (1) MT/6YR 6YR z M2-0264
- j (D-3)
(/) GROUP 72 Globe Valve / Air Operated
)>
z CoQeS Vulcan & Fisher 3-inch Models 0 HV-3486 M1-0216-A LOW 3 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation N (E-2) (1) MT/6YR 6YR M2-0216-A (E-2) 0 7J HV-3487 M1-0216-A LOW 3 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation z MT/6YR 6YR 7J (E-5) (1) 7J M2-0216-B :::::: (/) (F-2) -I LCV-1003 M1-0264 LOW 3 2 A A C LTJ/TS MT/6YR FC/6YR PIT/ Containment Isolation 7J (G-2) (1) ET/18MO 6YR DJ
- J M2-0264 (G-2)
GROUP 73 Butterfly Valve / Air Operated Posi-Seal Model 9134-05-07-03, 48-inch HV-5536 M1-0301 LOW 48 2 A p C LTJ/TS N/A N/A PIT/ Containment Isolation (F-2) (1) 6YR M2-0301 (E-2) HV-5537 M1-0301 LOW 48 2 A p C LTJ/TS N/A N/A PIT/ Containment Isolation (E-2) (1) 6YR M2-0301 (D-2) HV-5538 M1-0301 LOW 48 2 A p C LTJ/TS N/A N/A PIT/ Containment Isolation (F-3) (1) 6YR M2-0301
- a (E-3)
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0 TABLE 17- MISCELLANEOUS CONTAINMENT ISOLATION VALVES 0 s:
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PAGE 4 of9 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coord.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
A HV-5539 M1-0301 LOW 48 2 A p C LTJ/TS N/A N/A PIT/ Containment Isolation C (E-3) (1) 6YR z M2-0301
--l (D-3)
(f) GROUP 74 Butterfly Valve / Air Operated
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Posi-Seal Model 9134-05-07-03, 18-inch z 0 HV-5548 M1-0301 LOW 18 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation I\.) (F-3) (1) MT/6YR 6YR M2-0301 (E-4) 0
-0 HV-5549 M1-0301 LOW 18 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation z (E-3) (1) MT/6YR 6YR -0 -0 M2-0301 ::::::
(f) (D-4)
--l GROUP 75 -0 Diaphram Valve / Air Operated ru
- J ITT Model SD-C-102863/100598 7126 M1-0264 LOW 3/4 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (B-2) (1) MT/6YR 6YR M2-0264 (B-2) 7150 M1-0264 LOW 3/4 2 A A C LT J/TS ET/18MO FC/6YR PIT/ Containment Isolation (C-1) (1) MT/6YR 6YR M2-0264 (C-1) 7136 M1-0264 LOW 3 2 A A C LTJ/TS MT/6YR FC/6YR PIT/ Containment Isolation (G-3) (1) ET/18MO 6YR M2-0264 (G-3)
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0 TABLE 17 - MISCELLANEOUS CONTAINMENT ISOLATION VALVES 0 s::
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PAGE 5 of9 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
- ,;; GROUP 76 C Ball Valve/ Hydraulic Operated z Neles-Jamesbury Model 3-A 150F-36TT
-I BS-0025 M1-0245 LOW 3 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (J)
(D-1) (1) M2-0245
)>
z (D-2) 0 BS-0030 M1-0245 LOW 3 2 A p C LTJ/TS N/A N/A N/A Containment Isolation N (C-1) (1) M2-0245 (C-2) 0
-0 GROUP77 z Globe Valve/ Solenoid Operated -0 -0 Valcor Model V52600-5292-7 :::::
(J) HV-5556 M1-0301-A LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation -I (C-4) (1) MT/6YR 6YR ];! M2-0301-A Q.)
- J (C-4)
HV-5557 M1-0301-A LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (D-4) (1) MT/6YR 6YR M2-0301-A (D-4) HV-5558 M1-0301-A LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (C-4) (1) MT/6YR 6YR M2-0301-A (C-4) HV-5559 M1-0301-A LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (D-4) (1) MT/6YR 6YR M2-0301-A (D-4) HV-5560 M1-0301-A LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (C-4) (1) MT/6YR 6YR M2-0301-A
- o (C-4)
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0 TABLE 17- MISCELLANEOUS CONTAINMENT ISOLATION VALVES 0
$ PAGE 6 of9 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )> ;:,;:: HV-5561 M1-0301-A LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation C (D-4) (1) MT/6YR 6YR z M2-0301-A -I (D-4)
(f) GROUP 78 Globe Valve / Solenoid Operated
)>
z Valcor Model V52600-5950-11 0 HV-5544 M1-0301-A LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation N (C-1) (1) MT/6YR 6YR M2-0301-A (C-1) 0
""O HV-5545 M1-0301-A LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation z (D-1) (1) MT/6YR 6YR ""O ""O M2-0301-A ::::::
(f) (D-1)
-I HV-5546 M1-0301-A LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation ""O (C-2) (1) MT/6YR 6YR ro
- i M2-0301-A (C-2)
HV-5547 M1-0301-A LOW 2 A A C LTJ/TS ET/18MO FC/6YR PIT/ Containment Isolation (D-2) (1) MT/6YR 6YR M2-0301-A (D-2) GROUP 79 Ball Valve / Manually Operated Worcester Controls / Neles-Jamesbury 1BS-0015 M1-0245 LOW 3/4 NIA A p C LTJ/TS N/A N/A NIA Containment Isolation (D-3) (1) (2) 1BS-0029 M1-0245 LOW 3/4 N/A A p C LTJ/TS N/A N/A N/A Containment Isolation (E-2) (1) (2) 1BS-0044 M1-0245 LOW 3/4 NIA A p C LTJ/TS N/A N/A NIA Containment Isolation (B-2) (1) (2)
- o 1BS-0056 M1-0245 LOW 3/4 N/A A p C LTJ/TS N/A N/A N/A Containm~nt Isolation CD (B-3) (1) (2)
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0 TABLE 17- MISCELLANEOUS CONTAINMENT ISOLATION VALVES 0
~ PAGE 7 of9 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )> ;;,;; BS-0202 M1-0245 LOW 2 2 A p C LTJ/TS N/A N/A N/A Containment Isolation C (A-5) (1) z M2-0245-A =i
(/) (B-3) BS-0203 M1-0245 LOW 2 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (C-5) (1) z M2-0245-A (E-3) 0 N GROUP 80 Diaphram Valve I Manually Operated 0 ITT Model SD-C-100552 -0 7135 M1-0264 LOW 3 2 A p C LTJ/TS N/A N/A N/A Containment Isolation z
-0 (G-2) (1) -0 M2-0264 ::::::
(/) (G-2) -l GROUP 81 -0 Globe Valve I Manually Operated ru
- J Anderson-Greenwood Model NO3-6020-504 2BS-0016 M2-0245 LOW 3/8 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (C-4) (1) 2BS-0017 M2-0245 LOW 3/8 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (C-4) (1) 2BS-0039 M2-0245 LOW 3/8 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (D-4) (1) 2BS-0040 M2-0245 LOW 3/8 2 A p C LT J/TS N/A N/A N/A Containment Isolation (D-4) (1)
GROUP 82 Relief Valve/ Manually Operated Anderson-Greenwood Model 83NS80608LG-N2 2BS-0015 M2-0245 LOW 3/4 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (E-4) (1) X (3) 1
- o 2BS-0029 M2-0245 LOW 3/4 2 A p C LTJ/TS N/A N/A N/A Containment Isolation CD (D-3) (1) X (3)
~ 1 .i:,..
0 TABLE 17 - MISCELLANEOUS CONTAINMENT ISOLATION VALVES 0
$ PAGE 8 of9 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
A 2BS-0044 M2-0245 LOW 3/4 2 A p C LTJ/TS N/A N/A N/A Containment Isolation C (C-3) (1) X (3) z 1
--1 2BS-0056 M2-0245 LOW 3/4 2 A p C LTJ/TS N/A N/A N/A Containment Isolation Cl) .... (B-4) (1) X 1
(3)
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z 0 N 0
-0 z -0 -0 Cl) --1 -0 ru
- J
- 0 CD
- J
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0 TABLE 17 - MISCELLANEOUS CONTAINMENT ISOLATION VALVES 0
~ PAGE 9 of9 )>
z NOTES 0 I m 1. A risk informed - staggered test basis (RI-STB) shall be established for the valves within the specified group.
-0 m )>
- 2. 1BS-0015, 1BS-0029, 1BS-0044, 1BS-0056 are non-ASME valves. However, they are included in the lnservice Valve Testing Plan in accordance with Generic Letter 89-04, Attachment 1, Position 10 because they are containment isolation valves which are included in the 10CFR50 Appendix J Program.
A C 3. 2BS-0015, 2BS-0029, 2BS-0044, 2BS-0056 are relief valves and therefore would normally be classified as Category A/C. In this application, however, they are being used z as lever operated manual valves which spring return to closed and not for self-actuated overpressure relief. For this reason they are classified as Category A.
=i (f)
_,_ 4. ISTC-3550 Valve in Regular Use - This valve operates in the course of plant operation at a frequency that satisfies the requirements of this 1ST Plan.
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z 0 N 0
-0 z -0 -0 (f) --i -0 ru
- J
- 0 CD
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0 TABLE 18- SAFETY & RELIEF VALVES 0
~ PAGE 1 OF 15 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""CJ m Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks )>
A GROUP 83 HIGH SAFETY SIGNIFICANCE C Safety Valve / Self Actuating z Crosby Model HB-BP-86, Size 6M6
-I 8010A M1-0251 HIGH 6 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection/
(J)
...... (A-1) Reactor Coolant Pressure )> M2-0251 Boundary z (A-1) 0 8010B M1-0251 HIGH 6 C A O/C N/A SRV/5YR NIA PIT/2YR Overpressure Protection/
N (B-1) Reactor Coolant Pressure M2-0251 Boundary 0 (B-1) ""CJ 8010C M1-0251 HIGH 6 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection/ z
""CJ (C-1) Reactor Coolant Pressure ""CJ M2-0251 Boundary :::::
(J) (C-1) -I GROUP 84 ""CJ Safety Valve / Self Actuating ru
- J Crosby Model HA-75-FN, Size 6R8X8 MS-0021 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection &
(C-4) X Steam Vent Flowpath (for M2-0202 8 residual heat removal)/ (C-4) Steam Line Isolation & Containment Isolation MS-0022 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & (C-4) X Steam Vent Flowpath (for M2-0202 8 residual heat removal)/ (C-4) Steam Line Isolation & Containment Isolation MS-0023 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & (D-4) X Steam Vent Flowpath (for M2-0202 8 residual heat removal)/ (D-4) Steam Line Isolation & Containment Isolation
- o CD
~ .i::-
0 TABLE 18 - SAFETY & RELIEF VALVES 0
~ PAGE 2 of15 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
--0 Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
MS-0024 M1-0202 LOW 6 2 C A O/C NIA SRV/5YR N/A PIT/2YR Overpressure Protection & C (D-4) X Steam Vent Flowpath (for z M2-0202 8 residual heat removal)/
-I (D-4) Steam Line Isolation &
(/) Containment Isolation MS-0025 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection &
)>
z (E-4) X Steam Vent Flowpath (for 0 M2-0202 8 residual heat removal)/ N (E-4) Steam Line Isolation & Containment Isolation MS-0058 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & 0
--0 (C-2) X Steam Vent Flowpath (for z M2-0202 8 residual heat removal)/ --0 --0 (C-2) Steam Line Isolation & :::::
Containment Isolation (/)
-I MS-0059 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR NIA PIT/2YR Overpressure Protection & --0 (C-2) X Steam Vent Flowpath (for 0)
M2-0202 8 residual heat removal)/ :J (C-2) Steam Line Isolation & Containment Isolation MS-0060 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & (D-2) X Steam Vent Flowpath (for M2-0202 8 residual heat removal)/ (D-2) Steam Line Isolation & Containment Isolation MS-0061 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & (D-2) X Steam Vent Flowpath (for M2-0202 8 residual heat removal)/ (D-2) Steam Line Isolation & Containment Isolation MS-0062 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & (E-2) X Steam Vent Flowpath (for M2-0202 8 residual heat removal)/
- a (E-2) Steam Line Isolation &
CD Containment Isolation ~ ~
0 TABLE 18- SAFETY & RELIEF VALVES 0 s:
)>
PAGE 3 of 15 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
MS-0093 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & C (C-1) X Steam Vent Flowpath (for z M2-0202 8 residual heat removal)/
-l (C-1) Steam Line Isolation &
(/J Containment Isolation MS-0094 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR NIA PIT/2YR Overpressure Protection &
)>
z (C-1) X Steam Vent Flowpath (for 0 M2-0202 8 residual heat removal)/ N (C-1) Steam Line Isolation & Containment Isolation MS-0095 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & 0
-0 (D-1) X Steam Vent Flowpath (for z M2-0202 8 residual heat removal)/ -0 Steam Line Isolation & -0 (D-1) :::::
Containment Isolation (J)
-l MS-0096 M1-0202 LOW 6 2 C A O!C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & -0 (D-1) X Steam Vent Flowpath (for 53""
M2-0202 8 residual heat removal)/ :::J (D-1) Steam Line Isolation & Containment Isolation MS-0097 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & (E-1) X Steam Vent Flowpath (for M2-0202 8 residual heat removal)/ (E-1) Steam Line Isolation & Containment Isolation MS-0129 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & (C-5) X Steam Vent Flowpath (for M2-0202 8 residual heat removal)/ (C-5) Steam Line Isolation & Containment Isolation MS-0130 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & (C-5) X Steam Vent Flowpath (for M2-0202 8 residual heat removal)/
- o (C-5) Steam Line Isolation &
CD Containment Isolation ~ .p..
0 TABLE 18 - SAFETY & RELIEF VALVES 0 s::
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PAGE 4 of 15 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-u Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )> ;:,;: SRV/5YR N/A PIT/2YR Overpressure Protection &
MS-0131 M1-0202 LOW 6 2 C A O/C N/A (D-5) X Steam Vent Flowpath (for C z M2-0202 8 residual heat removal)/
-I (D-5) Steam Line Isolation &
(f) Containment Isolation MS-0132 M1-0202 LOW 6 2 C A O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection &
)>
(D-5) X Steam Vent Flowpath (for z M2-0202 8 residual heat removal)/ 0 N (D-5) Steam Line Isolation & Containment Isolation O/C N/A SRV/5YR N/A PIT/2YR Overpressure Protection & 0 MS-0133 M1-0202 LOW 6 2 C A -u (E-5) X Steam Vent Flowpath (for z M2-0202 8 residual heat removal)/ -u (E-5) Steam Line Isolation &
-u Containment Isolation (f) -I GROUP 85 HIGH SAFETY SIGNIFICANCE -u Relief Valve / Self Actuating / Safety Function ru
- J Crosby Model JB 8708A M1-0260 HIGH 3 2 A/C p O/C N/A SRV/10YR N/A NIA RCS Overpressure (E-2) X (2) Protection/RHR Flowpath M2-0260 4 Boundary and Containment (E-2) Isolation 8708B M1-0260 HIGH 3 2 AIC p O/C NIA SRV/10YR N/A N/A RCS Overpressure (E-5) X (2) Protection/RHR Flowpath M2-0260 4 Boundary and Containment (E-5) Isolation GROUP 86 Relief Valve / Self Actuating / Safety Function Crosby Model JBAK 8510A M1-0255-1 LOW 11/2 2 C A O/C N/A SRV/8YR N/A N/A High Head Safety Injection (D-4) X Pump Miniflow Path/ECCS M2-0254 2 Recirculation Flowpath (F-5) Boundary
- o
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0 TABLE 18 - SAFETY & RELIEF VALVES 0
$': PAGE 5 of 15 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )> ;;,;; M1-0255-1 8510B LOW 11/2 2 C A O/C N/A SRV/8YR N/A N/A High Head Safety Injection C (D-4) X Pump Miniflow Path/ECCS z M2-0254 2 Recirculation Flowpath =1
(/) (F-6) Boundary
...... GROUP 87 Relief Valve / Self Actuating / Safety Function )>
z Crosby Model JMAK 0 CC-0611 M1-0231 LOW 3/4 2 C A O/C N/A SRV/10YR N/A N/A Containment Penetration N (F-2) X (1) Thermal Relief M2-0231-A (C-2) 0
-0 CC-0618 M1-0231 LOW 3/4 2 C A O/C N/A SRV/10YR N/A N/A Containment Penetration z (F-3) X (1) Thermal Relief -0 -0 M2-0231-A 1 :::::
(/) (C-3)
--i 1CC-1067 M1-0231 LOW 3/4 2 NC A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration -0 (B-5) X (1) Thermal Relief/Containment 0)
- J Isolation 2CC-1090 M2-0231-A LOW 3/4 2 NC A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration (F-2) X (1) Thermal Relief/Containment Isolation 1CH-0271 M1-0307-A LOW 3/4 2 NC A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration (B-1) X (1) Thermal Relief/Containment 1 Isolation 1CH-0272 M1-0307-A LOW 3/4 2 NC A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration (B-1) X (1) Thermal Relief/Containment Isolation 2CH-0281 M2-0307 LOW 3/4 2 NC A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration (B-3) X (1) Thermal Relief/Containment Isolation 2CH-0282 M2-0307 LOW 3/4 2 NC A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration (B-2) X (1) Thermal Relief/Containment 1 Isolation
- a CD
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0 TABLE 18 - SAFETY & RELIEF VALVES 0 s:
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PAGE 6 of 15 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-u Number (Coard.) Ranking Size Class gory lion Pas. Test Test Test Test Remarks m )>
7' DD-0430 M1-0242-B LOW 3/4 2 A/C A O/C LT J/TS SRV/10YR N/A N/A Containment Penetration C (E-2) X (1) Thermal Relief/Containment z M2-0242 Isolation
=i (f)
(C-3) GROUP 88 Relief Valve / Self Actuating / Safety Function
)>
z Crosby Model JRAK 0 PS-0500 M1-0228 LOW 3/4 2 A/C A C LTJ/TS SRV/10YR NIA N/A Containment Penetration N (B-3) X (1) Thermal Relief/Containment M2-0228 Isolation (B-3) 0
-0 PS-0501 M1-0228 LOW 3/4 2 A/C A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration z (B-1) X (1) Thermal Relief/Containment -0 -0 M2-0228 1 Isolation ::::::
(f) (B-1)
-l PS-0502 M1-0228 LOW 3/4 2 A/C A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration -0 (B-1) X (1) Thermal Relief/Containment 0)
- J M2-0228 1 Isolation (B-1)
PS-0503 M1-0228 LOW 3/4 2 A/C A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration (B-2) X (1) Thermal Relief/Containment M2-0228 Isolation (B-2) 1Sl-8972 M1-0262 LOW 3/4 2 A/C A O/C LTJ/TS SRV/10YR N/A NIA Containment Penetration (B-1) X (1) Thermal Relief/Containment Isolation 2Sl-8983 M2-0263-C LOW 3/4 2 A/C A O/C LTJ/TS SRV/10YR N/A NIA Containment Penetration (D-2) X (1) Thermal Relief/Containment Isolation WP-7177 M1-0264 LOW 3/4 2 AIC A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration (C-4) X (1) Thermal Relief/Containment M2-0264 1 Isolation (C-4)
- 0 CD
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0 TABLE 18 - SAFETY & RELIEF VALVES 0
- s:
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PAGE 7 of 15 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
A GROUP 89 C Relief Valve/ Self Actuating/ Safety Function z Crosby Model 900 with Omni Trim
=i (J)
Sl-0182 M1-0263-B HIGH 3/4 2 C A O/C N/A SRV/10YR N/A N/A 8811 A Bonnet Overpressure _,._ (B-6) X Relief/Containment M2-0263-A Isolation
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z (B-5) 0 Sl-0183 M1-0263-B HIGH 3/4 2 C A O/C N/A SRV/10YR N/A N/A 8811 B Bonnet Overpressure N (B-5) X Relief/Containment M2-0263-A Isolation (B-6) 0
""O CT-0309 M1-0232-A LOW 3/4 2 C A O/C N/A SRV/10YR N/A N/A HV-4782 Bonnet z (C-5) X Overpressure ""O ""O M2-0232-A 1 Relief/Containment ::::::
(J) (C-5) Isolation
-l CT-0310 M1-0232-A LOW 3/4 2 C A O/C N/A SRV/10YR N/A N/A HV-4783 Bonnet ""O (C-6) X Overpressure ru M2-0232-A Relief/Containment (C-6) Isolation RH-0033 M1-0260 LOW 3/4 2 C A O/C N/A SRV/10YR N/A N/A 8716A Bonnet Overpressure (A-3) X Relief/ECCS Recirculation M2-0260 Flowpath Boundary (A-3)
RH-0034 M1-0260 LOW 3/4 2 C A O/C N/A SRV/10YR N/A N/A 8716B Bonnet Overpressure (A-4) X Relief/ECCS Recirculation M2-0260 Flowpath Boundary (A-5) GROUP 90 Relief Valve / Self Actuating / No Active Safety Function Anderson-Greenwood Model N06-1047-009 DO-0123 M1-0215-D LOW 1 3 C p C N/A SRV/10YR N/A N/A Diesel Generator Starting (F-2) X (1) Air Receiver Relief Valve M2-0215-D
- o (F-2)
CD
- c::
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0 TABLE 18 - SAFETY & RELIEF VALVES 0 s::
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PAGE 8 of 15 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-u Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )> ;;,;;: DO-0129 M1-0215-D p N/A SRV/10YR N/A N/A Diesel Generator Starting LOW 3 C C C (F-4) X (1) Air Receiver Relief Valve z M2-0215-D 1 -I (F-4)
(f) DO-0223 M1-0215-E LOW 3 C p C NIA SRV/10YR N/A N/A Diesel Generator Starling (F-2) X (1) Air Receiver Relief Valve
)>
z M2-0215-E 0 (F-2) N DO-0229 M1-0215-E LOW 3 C p C N/A SRV/10YR N/A N/A Diesel Generator Starting (F-4) X (1) Air Receiver Relief Valve M2-0215-E 1 0
-u (F-4) z GROUP 91 -u -u Relief Valve/ Self Actuating / No Active Safety Function (f)
Crosby Model JO -I DO-0111 M1-0215-F LOW 11/2 3 C A C NIA SRV/10YR NIA N/A Diesel Generator Fuel Oil -u (E-5) X (1) Transfer Pump Discharge ru M2-0215-F 2 Relief Valve (E-5) Sl-0176 M1-0262 LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Nitrogen Supply Header Relief (F-6) X (1) M2-0263-B 1 (B-6) Sl-0177 M1-0262 LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Nitrogen Supply Header Relief (G-6) X (1) M2-0263-B (A-6) DO-0187 M1-0215-F LOW 11/2 3 C A C N/A SRV/10YR N/A N/A Diesel Generator Fuel Oil (E-5) X (1) Transfer Pump Discharge M2-0215-F 2 Relief Valve (E-5) DO-0211 M1-0215-G LOW 11/2 3 C A C NIA SRV/10YR NIA NIA Diesel Generator Fuel Oil (E-5) X (1) Transfer Pump Discharge
- a M2-0215-G 2 Relief Valve CD
- < (E-5)
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0 TABLE 18 - SAFETY & RELIEF VALVES 0 s;: PAGE 9 of 15
)>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator "U Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m
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- ,;; p N/A SRV/10YR N/A N/A Chemical Additive Tank CT-0218 M1-0232-A LOW 11/2 2 C C C (F-4) X (1) Relief Valve z M2-0232-A 21/2
=i (/) (F-4) _,,_ DO-0287 M1-0215-G LOW 11/2 2 C A C N/A SRV/10YR N/A N/A Diesel Generator Fuel Oil (E-5) X (1) Transfer Pump Discharge )> M2-0215-G 2 Relief Valve z (E-5) 0 N 2CS-8000 M2-0251 LOW 1 2 C p C N/A SRV/10YR N/A N/A RCP Seal Water Return Line (D-3) X (1) Relief Valve 0 11/2 "U 1-8121 M1-0251 LOW 2 2 C p C N/A SRV/10YR N/A N/A RCP Seal Water Return Line z Relief Valve "U (D-3) X (1) "U 3 ::::: (/) GROUP 92 -I Relief Valve/ Self Actuating/ No Active Safety Function "U Crosby Model JMAK !ll
- s CC-0042 M1-0229-B LOW 3/4 3 C p C NIA SRV/10YR N/A N/A Non-Safeguards Loop (A-5) X (1) Supply Relief Valve M2-0229 1 (D-6)
CC-0183 M1-0229-A LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Component Cooling Water (E-4) X (1) Hx Relief Valve M2-0229 1 (A-4) CC-0184 M1-0229-B LOW 3/4 3 C p C N/A SRV/10YR NIA N/A Component Cooling Water (B-4) X (1) Hx Relief Valve M2-0229 1 (F-4) AF-0248 M1-0206-1 LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Motor Driven AFW Pump (B-1) X (1) Suction Relief Valve M2-0206-1 1 (B-1)
- o CD
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0 TABLE 18 - SAFETY & RELIEF VALVES 0
$'. PAGE 10 of 15 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory tion Pas. Test Test Test Test Remarks m )> ;;,;; p AF-0249 M1-0206-1 LOW 3/4 3 C C N/A SRV/10YR N/A N/A Motor Driven AFW Pump C (B-2) X (1) Suction Relief Valve z M2-0206-1 1 =i
(/) (B-2) AF-0250 M1-206-1 LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Turbine Driven AFW Pump
...... Suction Relief Valve (B-5) X (1) )>
M2-206-1 1 z (B-5) 0 I\) 1SW-0448 M1-0234 LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Diesel Jacket Water Cooler (F-2) X (1) Relief Valve 1 0
""O 1SW-0449 M1-0234 LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Diesel Jacket Water Cooler z Relief Valve ""O (F-5) X (1) ""O 1 ::::
(/) 2SW-0432 M2-0234 LOW 3/4 3 C p C NIA SRV/10YR N/A N/A Diesel Jacket Water Cooler --i (F-2) X (1) Relief Valve ""O 1 w 2SW-0433 M2-0234 LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Diesel Jacket Water Cooler (F-5) X (1) Relief Valve 1 CC-0722 M1-0231-A LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Component Cooling Water (D-1) X (1) Supply Line M2-0231 1 (D-1) CH-0600 M1-0311 LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Safety Chilled Water (F-2) X (1) Recirculation Pump M2-0311 1 Discharge Relief Valves (F-2) CH-0601 M1-0311 LOW 3/4 3 C p C N/A SRV/10YR N/A N/A Safety Chilled Water (F-5) X (1) Recirculation Pump M2-0311 1 Discharge Relief Valve (F-5)
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0 TABLE 18-SAFETY & RELIEF VALVES 0
- s:
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PAGE11of15 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
""O Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
A GROUP 93 C Relief Valve/ Self Actuating I No Active Safety Function z Crosby Model JRAK
=i
(/) 8124 M1-0255 LOW 3/4 2 C p C N/A SRV/10YR N/A N/A Charging Pump Suction Line (B-5) X (1) Relief Valve M2-0254 1
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z (C-5) 0 2-8468A M2-0254 LOW 3/4 2 C p C N/A SRV/10YR N/A N/A Positive Displacement Pump N (D-4) X (1) Suction Line Relief Valve M1-0259-A 1 (C-3) 0
""O 2-8468B M2-0254 LOW 3/4 2 C p C N/A SRV/10YR N/A N/A Centrifugal Charging Pump z Suction Line Relief Valve ""O (D-5) X (1) ""O 1 :::::
(/) 2-8468C M2-0254 LOW 3/4 2 C p C N/A SRV/10YR NIA N/A Centrifugal Charging Pump -I (D-6) X (1) Suction Line Relief Valve ""O 1 0)
- J 8858A M1-0263-A LOW 3/4 2 C p C N/A SRV/10YR N/A N/A SI PMP Section Relief (F-2) X (1)
M2-0262 1 (B-2) 8858B M1-0263-A LOW 3/4 2 C p C N/A SRV/10YR N/A N/A SI PMP section Relief (F-3) X (1) M2-0262 1 (B-4) GROUP 94 Relief Valve/ Self Actuating/ No Active Safety Function Target Rock Model 76K-003 CT-0005 M1-0232 LOW 3/4 2 C p C N/A SRV/10YR N/A N/A Containment Spray HX (D-2) X (1) Relief Valve M2-0232 1 (D-2)
- 0 CD
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0 TABLE 18- SAFETY & RELIEF VALVES 0 s: PAGE12of15
- t>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator - ""O Number (Coord.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m
- t>
;:,;; M1-0232 p CT-0056 LOW 3/4 2 C C N/A SRV/10YR N/A N/A Containment Spray HX C (D-4) X (1) Relief Valve z M2-0232 1 -I (D-4)
CJ)
)> GROUP 96 z Vacuum Breaker/ Self Actuating 0 Crosby Model VR N CTVBCA-01 M1-0232-A HIGH 2 3 C A O/C N/A SRV/2YR N/A N/A Chemical Additive Tank (F-4) Ventpath/System Boundary 0
M2-0232-A ""O (F-4) z
""O CTVBCA-02 M1-0232-A HIGH 2 3 C A O/C N/A SRV/2YR N/A N/A Chemical Additive Tank ""O (F-4) Ventpath/System Boundary :::::
CJ) M2-0232-A -I (F-4) ""O ru
- i GROUP 99 Relief Valve/ Self Actuating/ No Active Safety Function Crosby Model JRAK - Medium/High Pressure S[:Jring Set 8851 M1-0263-A LOW 3/4 2 C p C N/A SRV/10YR N/A N/A SI PMP Discharge to Cold leg, (B-4) X Reactor Coolant Pressure M2-0262 1 Boundary Valve Leakage (F-3) 8853A M1-0263-A LOW 3/4 2 C p C N/A SRV/10YR N/A N/A SI PMP Discharge to Cold leg, (B-2) X Reactor Coolant Pressure M2-0262 1 Boundary Valve Leakage (F-2) 8853B M1-0263-A LOW 3/4 2 C p C N/A SRV/10YR N/A N/A SI PMP Discharge to Cold leg, (F-3) X Reactor Coolant Pressure M2-0262 Boundary Valve Leakage (F-4)
;o CD .i:,.
0 TABLE 18- SAFETY & RELIEF VALVES 0
~ PAGE 13 of 15 )>
z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-u Number (Coard.) Ranking Size Class gory tion Pos. Test Test Test Test Remarks m )>
C z
-I
(/) GROUP 100 Relief Valve/ Self Actuating/ Safety Function
)> Crosby Model JRAK- Medium Pressure SQring Set z
0 p N 8842 M1-0263-B LOW 3/4 2 C C N/A SRV/10YR N/A N/A RHR To Hot Leg Injection (B-2) X Relief Valve, Reactor Coolant M2-0263-A 1 Pressure Boundary Valve 0 (F-2) Leakage -u z 8856A M1-0263-B LOW 3/4 2 C p C N/A SRV/10YR N/A N/A RHR to Cold Leg Injection -u (B-1) X Relief Valve, Reactor Coolant -u M2-0263-A 1 Pressure Boundary Valve (/) (F-1) Leakage -I 8856B M1-0263-B LOW 2 C p C N/A SRV/10YR N/A N/A RHR to Cold Leg Injection -u (B-3) 3/4 X Relief Valve, Reactor Coolant ru M2-0263-A 1 Pressure Boundary Valve (F-3) Leakage GROUP 101 Relief Valve / Self Actuating / Safety Function Crosby Model JRAK - Low Pressure SQring Set 2VD-0896 M2-0238 LOW 3/4 2 A/C A O/C LTJ/TS SRV/10YR N/A NIA Containment Penetration (B-6) X (1) Thermal Relief/Containment 1 Isolation 1VD-0907 M1-0238 LOW 3/4 2 AIC A O/C LT J/TS SRV/10YR N/A N/A Containment Penetration (B-6) X (1) Thermal Relief/Containment 1 Isolation WP-7176 M1-0264 LOW 3/4 2 A/C A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration (E-3) X (1) Thermal Relief/Containment M2-0264 1 Isolation (E-3)
- o CD
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0 TABLE 18- SAFETY & RELIEF VALVES 0 s:
)>
PAGE 14 of 15 z Test Parameters/Schedule 0 I Flow Safety Fail Position m Valve Diagram Risk Code Cate- Fune- Fune. Leak Exercise Safe Indicator
-0 Number (Coard.) Ranking Size Class gory lion Pos. Test Test Test Test Remarks m )>
7' RC-0036 M1-0251 LOW 2 NC A O/C LTJ/TS SRV/10YR N/A N/A Containment Penetration 3/4 C (F-2) X (1) Thermal Relief/Containment z M2-0251 Isolation
=i (f)
(F-2) GROUP 102 Relief Valve/ Self Actuating I No Active Safety Function
)>
Crosby Model JO z 0 8855A M1-0262 LOW 1 2 C p C N/A SRV/10YR N/A N/A SI Accumulator Relief N (D-1) X M2-0263-B 2 (C-1) 0
-0 8855B M1-0262 LOW 2 C p C N/A SRV/10YR N/A N/A SI Accumulator Relief z (D-2) X -0 -0 M2-0263-B 2 :::::
(f) (C-2)
--1 8855C M1-0262 LOW 1 2 C p C N/A SRV/10YR N/A NIA SI Accumulator Relief -0 (D-4) X ru
- J M2-0263-B 2 (C-4) 8855D M1-0262 LOW 2 C p C N/A SRV/10YR NIA N/A SI Accumulator Relief (D-5) X M2-0263-B 2 (C-5)
- 0 CD
~
0 TABLE 18- SAFETY & RELIEF VALVES 0 $'. PAGE 15 of 15 )> z NOTES 0 I m 1. These valves meet the scoping requirement of ISTA-1100(b) for relief devices that protect systems or portion of systems that perform one or more of the three safety ""CJ m functions (shutdown the reactor to the safe shutdown condition, maintain the safe shutdown condition, or mitigate the consequences of an accident). Additionally, these )> relief valves meet the criteria of ASME OM CODE 2004 Edition through 2006 Addenda, 1-1390 "Test Frequency, Class 2 and 3 Pressure Relief Devices That Are Used for
- ,;;; Thermal Relief Application." These thermal relief valves shall be tested every 10 years, unless performance data indicate more frequent testing is necessary. In lieu of tests, relief valves may be replaced at frequency of every 1O years, unless performance data indicate more frequent replacement is necessary. No additional valves are C required to be tested if a thermal relief valve exceeds its as-found set pressure tolerance.
z =i (J) 2. 8708A and 87088, RHR Suction Relief Valves, are Passive and are therefore exempt from performance 2004 through 2006 Addenda, Subsection ISTC, Table ISTC-3500- ....,,_ 1.) Technical Specification LCO 3.4.12, however, allows crediting these valves for LTOP protection in MODES 4, 5, 6. Therefore, these valves are performance tested to )> the requirements of ASME OM Code 2004 Edition, through 2006 Addenda, Appendix I. z 0 N 0
""CJ z ""CJ ""CJ (J) -I ""CJ 0)
- J
0 TABLE 19 - MOTOR OPERATED VALVES 0 s::
)>
PAGE 1 OF 20 z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
-u Number (Coard.) Ranking Size Class gory lion Pas. PIT Test Test Testing Remarks m )>
AUXILIARY FEEDWATER C Gate Valve/ Motor Operated z Borg-Warner 75000 Series with Limitorgue Actuator
-I HV-2480 M1-0206-1 LOW 6 3 B A 0 N/A ET/18MO N/A (1) AFW Pump Emergency
(/) _,._ (B-2) Supply Flowpath
)> M2-0206-1 z (B-2) 0 HV-2481 M1-0206-1 LOW 6 3 B A 0 N/A ET/18MO N/A (1) AFW Pump Emergency N (B-4) Supply Flowpath M2-0206-1 0 (B-4) -u HV-2482 M1-0206-1 LOW 8 3 B A 0 N/A ET/18MO N/A (1) AFW Pump Emergency z -u (B-4) Supply Flowpath -u M2-0206-1 (/)
(B-4) -I AUXILIARY FEEDWATER -u Gate Valve/ Motor Operated Ql
- i Borg-Warner Model 75610-1 with Limitorgue Actuator HV-2491A M1-0206 LOW 4 2 B A C N/A ET/18MO N/A (1) Containment Isolation & AFW (D-4) to Faulted SG Flow M2-0206 Isolation (D-4)
HV-2491B M1-0206 LOW 4 2 B A C N/A ET/18MO N/A (1) Containment Isolation & AFW (D-4) to Faulted SG Flow M2-0206 Isolation (D-4) HV-2492A M1-0206 LOW 4 2 B A C N/A ET/18MO N/A (1) Containment Isolation & AFW (D-3) to Faulted SG Flow M2-0206 Isolation (D-3) HV-2492B M1-0206 LOW 4 2 B A C N/A ET/18MO N/A (1) Containment Isolation & AFW (D-2) to Faulted SG Flow M2-0206 Isolation
- o CD (D-2)
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0 TABLE 19- MOTOR OPERATED VALVES 0 s)> PAGE 2 of 20 z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
--0 Number (Coard.) Ranking Size Class gory tion Pas. PIT Test Test Testing Remarks m )>
HV-2493A M1-0206 LOW 4 2 B A C N/A ET/18MO NIA (1) Containment Isolation & AFW C (D-1) to Faulted SG Flow z M2-0206 Isolation
- j (D-1)
(J)
....,,_ HV-2493B M1-0206 LOW 4 2 B A C N/A ET/18MO N/A (1) Containment Isolation & AFW (D-2) to Faulted SG Flow )>
M2-0206 z (D-2) Isolation 0 N HV-2494A M1-0206 LOW 4 2 B A C N/A ET/18MO NIA (1) Containment Isolation & AFW (D- 5) to Faulted SG Flow M2-0206 Isolation 0
--0 (D-5) z HV-2494B M1-0206 LOW 4 2 B A C N/A ET/18MO N/A (1) Containment Isolation & AFW --0 --0 (D-5) to Faulted SG Flow :::::::
(J) M2-0206 Isolation --l (D-5)
--0 AUXILIARY FEEDWATER ru
- J Butterfly Valve/ Motor Operated Fisher Controls Series with Limitorgue Actuator HV-2484 M1-0206-2 LOW 12 3 B A C N/A ET/18MO N/A (1) Condensate System to (D-4) Condensate Storage Tank M2-0206-2 Isolation to Preclude Tank (D-4) Overpressurization HV-2485 M1-0206-2 LOW 12 3 B A C N/A ET/18MO N/A (1) Condensate System to (D-4) Condensate Storage Tank M2-0206-2 Isolation to Preclude Tank (D-4) Overpressurization COMPONENT COOLING WATER Butterfly Valve/ Motor Operated Fisher with Limitorgue Actuator (24-inch2 HV-4512 M1-0229-A LOW 24 3 B A C N/A ET/18MO NIA (1) Train A to Train B Crosstie (F-1) Isolation M2-0229
- 0 (C-3)
- J Butterfly Valve/ Motor Operated Fisher Controls Series with Limitorgue Actuator HV-2484 M1-0206-2 LOW 12 3 B A C N/A ET/18MO N/A (1) Condensate System to (D-4) Condensate Storage Tank M2-0206-2 Isolation to Preclude Tank (D-4) Overpressurization HV-2485 M1-0206-2 LOW 12 3 B A C N/A ET/18MO N/A (1) Condensate System to (D-4) Condensate Storage Tank M2-0206-2 Isolation to Preclude Tank (D-4) Overpressurization COMPONENT COOLING WATER Butterfly Valve/ Motor Operated Fisher with Limitorgue Actuator (24-inch2 HV-4512 M1-0229-A LOW 24 3 B A C N/A ET/18MO NIA (1) Train A to Train B Crosstie (F-1) Isolation M2-0229
CD .i:,..
0 TABLE 19 - MOTOR OPERATED VALVES 0
~ PAGE 3 of20 )>
z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
-0 Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m )>
A HV-4513 M1-0229-A LOW 24 3 B A C N/A ET/18MO N/A (1) Train A to Train B Crosstie C (G-1) Isolation z M2-0229
=i Cl)
(E-3) HV-4514 M1-0229-B LOW 24 3 B A C NIA ET/18MO NIA (1) Train A to Train B Crosslie (A-4) Isolation
)>
z M2-0229 0 (C-6) i'J HV-4515 M1-0229-B LOW 24 3 B A C NIA ET/18MO N/A (1) Train A to Train B Crosslie (A-4) Isolation M2-0229 0
-0 (D-6) z NIA Non-Safety Loop Flowpath -0 HV-4524 M1-0229-A LOW 24 3 B A C N/A ET/18MO (1) -0 (F-1) Isolation :::::
Cl) M2-0229 -I (D-4)
"U HV-4525 M1-0229-A LOW 24 3 B A C N/A ET/18MO NIA (1) Non-Safety Loop Flowpath Ol
- J (F-1) Isolation M2-0229 (D-4)
HV-4526 M1-0229-B LOW 24 3 B A C NIA ET/18MO N/A (1) Non-Safety Loop Flowpath (A-5) Isolation M2-0229 (D-6) HV-4527 M1-0229-B LOW 24 3 B A C N/A ET/18MO N/A (1) Non-Safety Loop Flowpath (A-5) Isolation M2-0229 (D-6) COMPONENT COOLING WATER - HIGH SAFETY SIGNIFICANCE Butterfly Valve/ Motor Operated Velan with Limitorgue Actuator (18-inch) HV-4572 M1-0229 HIGH 18 3 B A 0 NIA ET/18MO NIA (1) RHR Heat Exchanger Cooling (B-2) Flowpath
- 0 M2-0229-A (D
- < (C-4)
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0 TABLE 19- MOTOR OPERATED VALVES 0 s:
)>
PAGE 4 of 20 z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic "U Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m
)>
HV-4573 M1-0229-B HIGH 18 3 B A 0 N/A ET/18MO N/A (1) RHR Heat Exchanger Cooling C (F-6) Flowpath z M2-0229-B
=i (J)
(F-4) _,_ COMPONENT COOLING WATER Gate Valve / Motor Operated
)>
z Borg-Warner with Limitorgue Actuator 0 HV-4696 M1-0231 LOW 4 2 A A C LTJ/TS ET/18MO N/A (1) Containment Isolation & RCP N (C-4) Thermal Barrier Rupture M2-0231 Isolation (A-4) 0 "U HV-4699 M1-0231-A LOW 8 2 B A C N/A ET/18MO N/A (1) Passive Pipe Break Isolation z (B-6) (inside Containment)
"U "U
M2-0230-A :::::: (J) (E-2) --l HV-4700 M1-0231-A LOW 8 2 A A C LTJ/TS ET/18MO N/A (1) Containment Isolation & RCP "U (B-6) Thermal Barrier Rupture ru
- l M2-0230-A Isolation (E-3)
HV-4701 M1-0231 LOW 8 2 A A C LTJ/TS ET/18MO N/A (1) Containment Isolation (C-4) M2-0231 (A-6) HV-4708 M1-0231 LOW 8 2 A A C LTJ/TS ET/18MO NIA (1) Containment Isolation (B-4) M2-0230-A (E-4) HV-4709 M1-0231 LOW 4 2 A A C LTJ/TS ET/18MO N/A (1) Containment Isolation & RCP (B-4) Thermal Barrier Rupture M2-0230-A Isolation (F-4)
- 0 (I)
~
0 TABLE 19- MOTOR OPERATED VALVES 0 s::
)>
PAGE 5 of20 z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
""O Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m )> /\ COMPONENT COOLING WATER C Butterily Valve/ Motor Operated z Velan with Limitorgue Actuator -I HV-4574 M1-0229 LOW 18 3 B A 0 NIA ET/18MO NIA (1) Containment Spray Heat Cf)
(B-4) Exchanger Cooling Flowpath M2-0229-A
)>
z (C-2) 0 HV-4575 M1-0229-B LOW 18 3 B A 0 NIA ET/18MO NIA (1) Containment Spray Heat N (F-6) Exchanger Cooling Flowpath M2-0229-B 0 (F-5) ""O SAFETY & NON-SAFETY CHILLED WATER z
""O Gate Valve/ Motor Operated ""O Borg-Warner with Limitorgue Actuator :::::
Cf) HV-6082 M1-0307-A LOW 6 2 A A C LTJ/TS ET/18MO NIA (1) Containment Isolation -I (B-1) ""O M2-0307 w
- J (B-2)
HV-6083 M1-0307-A LOW 6 2 A A C LTJ/TS ET/18MO NIA (1) Containment Isolation (C-1) M2-0307 (B-2) HV-6084 M1-0307-A LOW 6 2 A A C LTJ/TS ET/18MO NIA (1) Containment Isolation (B-2) M2-0307 (B-3) CHEMICAL and VOLUME CONTROL - HIGH SAFETY SIGNIFICANCE Globe Valve/ Motor Operated Velan with Limitorgue Actuator 8110 M1-0255 HIGH 2 2 B A C NIA ET/18MO NIA (1) ECCS Flowpath Boundary (B-2) M2-0254 (A-2)
- o (D
~ .i:,..
0 TABLE 19- MOTOR OPERATED VALVES 0
~ PAGE 6 of20 )>
z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
"""CJ Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m )>
- ,
- ;: 8111 M1-0255 HIGH 2 2 B A C N/A ET/18MO N/A (1) ECCS Flowpath Boundary C (8-2) z M2-0254
=i (J)
(A-2)
...... CHEMICAL and VOLUME CONTROL - HIGH SAFETY SIGNIFICANCE Gate Valve/ Motor Operated )>
z Westinghouse with Limitorgue Actuator 0 LCV-01128 M1-0255 HIGH 4 2 B A C N/A ET/18MO N/A (1) ECCS Flowpath Boundary & N (E-6) Isolation of VCT Cover Gas M2-0254 from Charging Pumps' (C-4) Suction Header (upon low 0
"""CJ VCT level) & Boron Dilution z Flowpath Isolation """CJ """CJ LCV-0112C M1-0255 HIGH 4 2 B A C N/A ET/18MO N/A (1) ECCS Flowpath Boundary & :::::
(J) (D-6) Isolation of VCT Cover Gas -j M2-0254 from Charging Pumps'
"""CJ (C-4) Suction Header (upon low ru
- i VCT level) & Boron Dilution Flowpath Isolation LCV-0112D M1-0255 HIGH 8 2 B A O/C N/A ET/18MO N/A (1) ECCS Injection Flowpath &
(C-5) Boration Flowpath/ECCS M2-0254 Recirculation Flowpath (B-5) Boundary LCV-0112E M1-0255 HIGH 8 2 B A O/C NIA ET/18MO NIA (1) ECCS Injection Flowpath & (C-4) Boration Flowpath/ECCS M2-0254 Recirculation Flowpath (B-5) Boundary CHEMICAL and VOLUME CONTROL - HIGH SAFETY SIGNIFICANCE Gate Valve/ Motor Operated Westinghouse with Limitorgue Actuator 8105 M1-0255-1 HIGH 3 2 A A O/C LTJ/TS ET/18MO N/A (1) Boration Flowpath/ECCS (A-2) Flowpath Boundary & M2-0255 Containment Isolation
- o (D-1)
CD ~
0 TABLE 19- MOTOR OPERATED VALVES 0 s:
)>
PAGE 7 of 20 z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
-0 Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m )>
A 8106 M1-0255-1 HIGH 3 2 B A O/C N/A ET/18MO N/A (1) Boration Flowpath/ECCS C (B-2) Flowpath Boundary z M2-0255
-I (C-1)
(/) _,,_ CHEMICAL and VOLUME CONTROL Gate Valve / Motor Operated
)>
z Flowserve with Limitorque Actuator 0 HV-8402A M1-0255-1 LOW 3 2 B p O/C N/A ET/18MO N/A (1) Boration Flowpath N (B-2) (5) (5) M2-0255 (B-1) 0
-0 CHEMICAL and VOLUME CONTROL z Globe Valve / Motor Operated -0 -0 Velan with Limitorque Actuator :::::
(/) 8100 M1-0253 LOW 2 2 A A C LTJ/TS ET/18MO N/A (1) Containment Isolation -I (A-4) -0 M2-0253 0) (D-6) 8104 M1-0255-2 LOW 2 2 B A 0 N/A ET/18MO N/A (1) Boration Flowpath (F-5) M2-0255-2 (B-3) 8109 M1-0255-1 LOW 2 2 B p C PIT/ N/A N/A N/A ECCS Flowpath Boundary (E-1) 2YR M2-0254 (4) (D-3) 8112 M1-0253 LOW 2 2 A A C LTJ/TS ET/18MO N/A (1) Containment Isolation (A-4) M2-0255-1 (B-4) 8351A M1-0253 LOW 2 2 B A C N/A ET/18MO N/A (1) Containment Isolation (A-6) M2-0255
- a (D-5)
CD ~
0 TABLE 19- MOTOR OPERATED VALVES 0 s:
)>
PAGE 8 of20 z Test Parameters/Schedule 0
- r: Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
""CJ Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m )>
83518 M1-0253 LOW 2 2 B A C N/A ET/18MO N/A (1) Containment Isolation C (E-6) z M2-0255
--l (D-4)
(/) 8351C M1-0253 LOW 2 2 B A C N/A ET/18MO N/A (1) Containment Isolation (E-3)
)>
z M2-0255 0 (D-6) N 83510 M1-0253 LOW 2 2 B A C N/A ET/18MO N/A (1) Containment Isolation (A-3) M2-0255 0
""CJ (D-5) z ""CJ 8511A M1-0255-1 LOW 2 2 B A O/C N/A ET/18MO N/A (1) High Head Safety Injection ""CJ (D-4) Pump Miniflow Path/ECCS :::::
(/) M2-0254 Recirculation Flowpath
--l (E-5) Boundary ""CJ 85118 M1-0255-1 LOW 2 2 B A O/C N/A ET/18MO N/A (1) High Head Safety Injection Q)
- J (D-4) Pump Miniflow Path/ECCS M2-0254 Recirculation Flowpath (E-6) Boundary 8512A M1-0255-1 LOW 2 2 B A C N/A ET/18MO N/A (1) ECCS Recirculation Flowpath (D-4) Boundary M2-0254 (F-6) 85128 M1-0255-1 LOW 2 2 B A C N/A ET/18MO N/A (1) ECCS Recirculation Flowpath (D-4) Boundary M2-0254 (F-5)
CONTAINMENT SPRAY Gate Valve/ Motor Operated Borg-Warner with Limitorgue Actuator HV-4776 M1-0232 LOW 16 2 B A O/C N/A ET/18MO N/A (1) Containment Spray Flowpath/ (C-5) (2) Containment Isolation
- o M2-0232 CD
- < (C-5)
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0 TABLE 19- MOTOR OPERATED VALVES 0
- s:: PAGE 9 of 20
)>
z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
-u Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m )> ;,;;: ET/18MO NIA Containment Spray Flowpath/
HV-4777 M1-0232 LOW 16 2 B A O/C NIA (1) C (C-2) (2) Containment Isolation z M2-0232
=i
(/) (C-2) HV-4782 M1-0232-A LOW 16 2 B A O/C NIA ET/18MO NIA (1) Sump Recirculation (C-5) Flowpath/Containment
)>
M2-0232-A Isolation z (C-5) 0 N HV-4783 M1-0232-A LOW 16 2 B A O/C NIA ET/18MO NIA (1) Sump Recirculation (C-6) Flowpath/Containment M2-0232-A Isolation 0
-u (C-6) z --0 CONTAINMENT SPRAY --0 Butterfly Valve I Motor Operated ::::::
(/) Copes Vulcan with Limitorque Actuator -, HV-4758 M1-0232-A LOW 16 2 B A C NIA ET/18MO NIA (1) Sump Recirculation Flowpath --0 (D-2) Boundary ru
- J M2-0232-A (D-2)
HV-4759 M1-0232-A LOW 16 2 B A C NIA ET/18MO NIA (1) Sump Recirculation Flowpath (D-2) Boundary M2-0232-A (E-3) CONTAINMENT SPRAY Globe Valve / Motor Operated Fisher with Limitorgue Actuator FV-4772-1 M1-0232 LOW 4 2 B A O/C NIA ET/18MO NIA (1) Pump Miniflow Flowpath/ (E-6) Containment Spray Flowpath M2-0232 Boundary (E-6) FV-4772-2 M1-0232 LOW 4 2 B A O/C NIA ET/18MO NIA (1) Pump Miniflow Flowpath/ (E-5) Containment Spray Flowpath M2-0232 Boundary
- o (E-5)
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0 TABLE 19 - MOTOR OPERATED VALVES 0 s;: PAGE 10 of20 J> z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic lJ Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m J> FV-4773-1 M1-0232 LOW 4 2 B A O/C N/A ET/18MO N/A (1) Pump Miniflow Flowpath/ C (F-3) Containment Spray Flowpath z M2-0232 Boundary
-I (F-3)
(J) FV-4773-2 M1-0232 LOW 4 2 B A O/C N/A ET/18MO N/A (1) Pump Miniflow Flowpath/ (F-2) Containment Spray Flowpath J> z M2-0232 Boundary 0 (F-2) N CONTAINMENT SPRAY Diaphram Valve / Motor Operated ITT with Limitorgue Actuator 0 lJ LV-4754 M1-0232-A LOW 3 3 B A O/C NIA ET/18MO N/A (1) Chemical Additive Flowpath/ z (F-5) Chemical Additive Tank lJ lJ M2-0232-A Isolation ::::: (J) (F-5)
-I LV-4755 M1-0232-A LOW 3 3 B A O/C N/A ET/18MO N/A (1) Chemical Additive Flowpath/ lJ (F-5) Chemical Additive Tank ru
- i M2-0232-A Isolation (F-5)
REACTOR COOLANT Gate Valve/ Motor Operated Westinghouse Model 03000GM88FNH000 8000A M1-0251 LOW 3 B A O/C N/A ET/18MO N/A (1) Post Accident Vent (A-4) PathNent Path Isolation M2-0251 & Reactor Coolant Pressure (A-4) Boundary 8000B M1-0251 LOW 3 B A O/C NIA ET/18MO N/A (1) Post Accident Vent (A-4) PathNent Path Isolation M2-0251 & Reactor Coolant Pressure (A-4) Boundary
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PAGE 11 of20 z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
-u Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m )>
RESIDUAL HEAT REMOVAL C Globe Valve / Motor Operated z Co~es Vulcan with Limitorgue Actuator
-i FCV-0610 M1-0260 LOW 3 2 B A O/C N/A ET/18MO N/A (1) Pump Miniflow Path/ECCS &
(J) (D-1) RHR Flowpath Boundary M2-0260
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z (D-1) 0 FCV-0611 M1-0260 LOW 3 2 B A O/C N/A ET/18MO N/A (1) Pump Miniflow Path/ECCS & N (D-6) RHR Flowpath Boundary M2-0260 (D-6) 0
-u RESIDUAL HEAT REMOVAL - HIGH SAFETY SIGNIFICANCE z Gate Valve/ Motor Operated -u -u Westinghouse with Limitorgue Actuator (12-inch) :::::
(J) 8701A M1-0260 HIGH 12 A A OIC LT/TS ET/18MO N/A (1) RHR Flowpath/Containment -i (F-3) (3) Isolation & Reactor Coolant -u M2-0260 Pressure Boundary 0)
- J (F-3) 87018 M1-0260 HIGH 12 A A O/C LT/TS ET/18MO N/A (1) RHR Flowpath/Containment (F-5) (3) Isolation & Reactor Coolant M2-0260 Pressure Boundary (F-5) 8702A M1-0260 HIGH 12 A A O/C LT/TS ET/18MO N/A (1) RHR Flowpath/Reactor (F-3) (3) Coolant Pressure Boundary M2-0260 (F-3) 87028 M1-0260 HIGH 12 A A O/C LT/TS ET/18MO N/A (1) RHR Flowpath/Reactor (F-5) (3) Coolant Pressure Boundary M2-0260 (F-5)
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z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTesl/ Exercise Safe Diagnostic "lJ Number (Coard.) Ranking Size Class gory lion Pas. PIT Test Test Testing Remarks m
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RESIDUAL HEAT REMOVAL C Gate Valve/ Motor Operated z Westinghouse with Limitorgue Actuator (10-inch)
=i
(/) 8716A M1-0260 LOW 10 2 B A O/C N/A ET/18MO N/A (1) ECCS Injection (B-3) Flowpath/ECCS Recirculation M2-0260 Flowpath Boundary
)>
z (B-3) 0 8716B M1-0260 LOW 10 2 B A O/C N/A ET/18MO N/A (1) ECCS Injection N (B-4) Flowpath/ECCS Recirculation M2-0260 Flowpath Boundary (B-4) 0 "lJ SAFETY INJECTION z Globe Valve / Motor Operated "lJ "lJ Westinghouse with Limitorgue Actuator ::::::: (/) 8814A M1-0263-A LOW 11/2 2 B A C N/A ET/18MO N/A (1) ECCS Recirculation Flowpath -{ (D-3) Boundary "lJ M2-0262 Q)
- I (D-3) 8814B M1-0263-A LOW 11/2 2 B A C N/A ET/18MO N/A (1) ECCS Recirculation Flowpath (D-4) Boundary M2-0262 (D-4)
SAFETY INJECTION - HIGH SAFETY SIGNIFICANCE Globe Valve / Motor Operated Westinghouse with Limitorgue Actuator 8813 M1-0263-A HIGH 2 2 B A C N/A ET/18MO N/A (1) ECCS Recirculation Flowpath (E-5) Boundary M2-0262 (C-3) SAFETY INJECTION - HIGH SAFETY SIGNIFICANCE Gate Valve / Motor Operated Westinghouse with Limitorgue Actuator (less than 8-inch)
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z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
""'O Number (Coard.) Ranking Size Class gory tion Pas. PIT Test Test Testing Remarks m )> ;:,;;; M1-0263-A B A O/C NIA ET/18MO NIA (1) ECCS to Cold Legs Flowpath/
8835 HIGH 4 2 C (A-5) ECCS to Hot Legs Flowpath z M2-0262 Boundary & Containment
=i (F-3) Isolation & Passive Pipe
(/) Break Isolation 8923A M1-0263-A HIGH 6 2 B A C NIA ET/18MO NIA (1) Passive Pipe Break
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(F-2) Isolation z M2-0262 0 I\.) (A-2) 8923B M1-0263-A HIGH 6 2 B A C NIA ET/18MO NIA (1) Passive Pipe Break Isolation 0 (F-3) ""'O M2-0262 z (A-5) ""'O
""'O SAFETY INJECTION - HIGH SAFETY SIGNIFICANCE :::::
(/) Gate Valve / Motor Operated ---i Westinghouse with Limitorgue Actuator (8-inch) ""'O 8804B M1-0263-A HIGH 8 2 B A O/C NIA ET/18MO NIA (1) ECCS Recirculation !ll
- i (F-3) Flowpath/Passive Pipe M2-0262 Break Isolation (B-4) 8806 M1-0263-A HIGH 8 2 B A C NIA ET/18MO NIA (1) ECCS Flowpath Boundary (G-2) (during Recirculation)
M2-0262 (A-2) SAFETY INJECTION - HIGH SAFETY SIGNIFICANCE Gate Valve / Motor Operated Westinghouse with Limitorgue Actuator (10-inch) 8809A M1-0263-B HIGH 10 2 B A O/C NIA ET/18MO NIA (1) ECCS to Cold Legs Flowpath/ (A-2) (2) ECCS to Hot Legs Flowpath M2-0263-A Boundary & Passive Pipe (F-1) Break Isolation & Contain-ment Isolation
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z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
-0 Number (Coard.) Ranking Size Class gory lion Pas. PIT Test Test Testing Remarks m )> ;,;;; 8809B M1-0263-B HIGH 10 2 B A O/C NIA ET/18MO NIA (1) ECCS to Cold Legs Flowpath/
C (A-4) (2) ECCS to Hot Legs Flowpath z M2-0263-A Boundary & Passive Pipe
-I (F-3) Break Isolation & Contain-(J) men! Isolation )>
z SAFETY INJECTION - HIGH SAFETY SIGNIFICANCE 0 Gate Valve / Motor Operated N Westinghouse with Limitorgue Actuator (14-inch) 8811A M1-0263-B HIGH 14 2 B A O/C NIA ET/18MO NIA (1) ECCS Recirculation 0 (B-6) Flowpath/Containment -0 M2-0263-A Isolation & Passive z (B-5) Pipe Break Isolation -0
-0 8811 B M1-0263-B HIGH 14 2 B A O/C NIA ET/18MO NIA (1) ECCS Recirculation :::::
(J) (B-5) Flowpath/Containment
-I M2-0263-A Isolation & Passive (B-6) Pipe Break Isolation J2 n:,
8812A M1-0263-B HIGH 14 2 B A C NIA ET/18MO NIA (1) ECCS Recirculation Flowpath (F-2) Boundary & Shutdown M2-0263-A Cooling Flowpath Boundary (B-2) (during Safety Grade Cold Shutdown) 8812B M1-0263-B HIGH 14 2 B A C NIA ET/18MO NIA (1) ECCS Recirculation Flowpath (F-3) Boundary & Shutdown M2-0263-A Cooling Flowpath Boundary (B-3) (during Safety Grade Cold Shutdown) SAFETY INJECTION - HIGH SAFETY SIGNIFICANCE Gate Valve / Motor Operated Westinghouse with Limitorgue Actuator (4-inch) 8801A M1-0261 HIGH 4 2 B A O/C NIA ET/18MO NIA (1) ECCS to Cold Legs Flowpath (C-2) & Boration Flowpath/ M2-0261 Containment Isolation &
- o (E-4) Passive Pipe Break CD Isolation
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~ PAGE15of20 )>
z Test Parameters/Schedule 0 I Flow Safety Fail rn Valve Diagram Risk Code Cate- Fune- Fune. LeakTesV Exercise Safe Diagnostic
-0 Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks rn )>
- '\ 8801B M1-0261 HIGH 4 2 B A O/C N/A ET/18MO NIA (1) ECCS to Cold Legs Flowpath C (C-2) & Boration Flowpath/
z M2-0261 Containment Isolation &
=i (E-5) Passive Pipe Break en Isolation SAFETY INJECTION - HIGH SAFETY SIGNIFICANCE )>
z Gate Valve/ Motor Operated 0 Westinghouse with Limitorque Actuator (10-inch) N 8840 M1-0263-B HIGH 10 2 B A O/C N/A ET/18MO N/A (1) ECCS to Hot Legs Flowpath/ (A-3) (2) ECCS to Cold Legs Flowpath M2-0263-A Boundary & Containment 0
-0 (F-2) Isolation & Passive Pipe z Break Isolation -0 -0 SAFETY INJECTION - HIGH SAFETY SIGNIFICANCE :::::
Gate Valve/ Motor Operated en
-I Westinghouse with Limitorgue Actuator (4-inch) -0 8802A M1-0263-A HIGH 4 2 B A O/C N/A ET/18MO N/A (1) ECCS to Hot Legs Flowpath/ 0)
- J (A-2) ECCS to Cold Legs Flowpath M2-0262 Boundary & Containment (F-2) Isolation & Passive Pipe Break Isolation 8802B M1-0263-A HIGH 4 2 B A O/C N/A ET/18MO N/A (1) ECCS to Hot Legs Flowpath/
(A-3) ECCS to Cold Legs Flowpath M2-0262 Boundary & Containment (F-5) Isolation & Passive Pipe Break Isolation 8821A M1-0263-A HIGH 4 2 B A OIC NIA ET/18MO N/A (1) ECCS to ColdLegsFlowpath/ (C-3) ECCS to Hot Legs Flowpath M2-0262 Boundary & Passive Pipe (E-3) Break Isolation 88218 M1-0263-A HIGH 4 2 B A O/C N/A ET/18MO N/A (1) ECCS to ColdLegsFlowpath/ (C-4) EGGS to Hot Legs Flowpath M2-0262 Boundary & Passive Pipe
- () (E-4) Break Isolation CD
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z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
""O Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m )>
SAFETY INJECTION C Gate Valve / Motor Operated z Westinghouse with Limitorgue Actuator {larger than 4-inch)
-l 8807A M1-0261 LOW 6 2 B A O/C N/A ET/18MO N/A (1) ECCS Recirculation (f)
(E-5) Flowpath/Passive Pipe Break M2-0261 Isolation
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z (B-6) 0 8807B M1-0261 LOW 6 2 B A O/C N/A ET/18MO NIA (1) ECCS Recirculation N (E-5) Flowpath/Passive Pipe M2-0261 Break Isolation (B-6) 0
""O 8808A M1-0262 LOW 10 2 B p 0 PIT/ N/A N/A N/A ECCS from Accumulators to z (C-2) 2YR Cold Legs Flowpath ""O ""O M2-0263-B (4) :::::
(f) (E-2)
-l 8808B M1-0262 LOW 10 2 B p 0 PIT/ N/A N/A N/A ECCS from Accumulators to ""O (C-3) 2YR Cold Legs Flowpath ru
- J M2-0263-B (4)
(E-3) 8808C M1-0262 LOW 10 2 B p 0 PIT/ N/A N/A N/A ECCS from Accumulators to (C-5) 2YR Cold Legs Flowpath M2-0263-B (4) (E-5) 8808D M1-0262 LOW 10 2 B p 0 PIT/ N/A N/A N/A ECCS from Accumulators to (C-6) 2YR Cold Legs Flowpath M2-0263-B (4) (E-6) 8924 M1-0261 LOW 6 2 B A C N/A ET/18MO N/A (1) Passive Pipe Break (E-4) Isolation M2-0261 (B-5) 8804A M1-0261 LOW 8 2 B A O/C N/A ET/18MO N/A (1) ECCS Recirculation (F-5) Flowpath/Passive Pipe
- o M2-0261 Break Isolation CD
- < (A-6)
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PAGE 17 of20 z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTest/ Exercise Safe Diagnostic
"""CJ Number (Coard.) Ranking Size Class gory lion Pas. PIT Test Test Testing Remarks m )>
STATION SERVICE WATER- HIGH SAFElY SIGNIFICANCE C Buttertly Valve / Motor Operated z Fisher with Limitorgue Actuator
--f HV-4286 M1-0233 HIGH 24 3 B A O/C N/A ET/18MO N/A (1) Service Water Flowpath/
Cl)
...... (E-2) Throttling during Pump M2-0233 Start )>
z (D-3) 0 HV-4287 M1-0233 HIGH 24 3 B A O/C N/A ET/18MO N/A (1) Service Water Flowpath/ N (D-2) Throttling during Pump M2-0233 Start (B-3) 0
"""CJ STATION SERVICE WATER z """CJ Buttertly Valve/ Motor Operated """CJ Fisher with Limitorgue Actuator :::::
(f) HV-4393 M1-0234 LOW 10 3 B A 0 N/A ET/18MO N/A (1) Service Water Flowpath --f (F-6) """CJ M2-0234 ru
- J (F-6)
HV-4394 M1-0234 LOW 10 3 B A 0 N/A ET/18MO N/A (1) Service Water Flowpath (F-1) M2-0234 (F-1) HV-4395 M1-0234 LOW 10 3 B A 0 N/A ET/18MO N/A (1) AFW Pump Emergency (G-6) Supply Flowpath M2-0234 (G-6) HV-4396 M1-0234 LOW 10 3 B A 0 N/A ET/18MO N/A (1) AFW Pump Emergency (G-1) Supply Flowpath M2-0234 (G-1)
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"""CJ Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m )>
CONTAINMENT ISOLATION C Gate Valve / Motor Operated z Borg-Warner with Limitorgue Actuator
-i HV-40758 M1-0225-5 LOW 4 2 A A C LTJ/TS ET/18MO N/A (1) Containment Isolation (f)
(8-3) M2-0225-5
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z (B-3) 0 HV-4075C M1-0225-5 LOW 4 2 A A C LTJ/TS ET/18MO N/A (1) Containment Isolation N (D-3) M2-0225-5 (D-3) 0
"""CJ z """CJ """CJ (f)
CONTAINMENT ISOLATION -i Butterfly Valve/ Motor Operated """CJ Q) Posi-Seal with Limitorque Actuator ::i HV-5540 M1-0301 LOW 12 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (C-2) M2-0301 (B-2) HV-5541 M1-0301 LOW 12 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (D-2) M2-0301 (C-2) HV-5542 M1-0301 LOW 12 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (C-4) M2-0301 (8-4) HV-5543 M1-0301 LOW 12 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (D-4) M2-0301
- 0 (C-4)
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PAGE 19 of20 z Test Parameters/Schedule 0 I Flow Safety Fail m Valve Diagram Risk Code Cate- Fune- Fune. LeakTesU Exercise Safe Diagnostic
""CJ Number (Coard.) Ranking Size Class gory lion Pos. PIT Test Test Testing Remarks m )> ;:,;:: M1-0301 p HV-5562 LOW 12 2 A C LTJ/TS N/A N/A N/A Containment Isolation C (D-2) z M2-0301 =i Cf)
(C-2) HV-5563 M1-0301 LOW 12 2 A p C LTJ/TS N/A N/A N/A Containment Isolation (D-4)
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z M2-0301 0 (C-4) N 0
""CJ z ""CJ ""CJ Cf) -I ""CJ m
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0 TABLE 19- MOTOR OPERATED VALVES 0 s PAGE 20 of20 )> z NOTES 0 I m 1. The test frequency for each MOV shall be determined from the chart (see Relief Request V-1 for more details): ""CJ m )> Initial lnservice Test Frequency
- ,;
- ; MARGIN C
z R Low Medium High =i (J) I High 1 cycle 2 cycles 3 cycles _,__ s Low 2 cycles 4 cycles 6 cycles* K )> z *Notto exceed 1O years 0 N A. Criteria for MOV Margin Categories Low Margin: < 10% 0
""CJ Medium Margin: ~ 10% and< 15% z ""CJ High Margin: ~ 15% ~
(J) B. Criteria for Risk Categories -I High Risk: Risk-Informed 1ST Program ""CJ Low Risk: Risk-Informed 1ST Program ill
- i
- 2. This valve has a water filled loop seal and is not required to be leakrate tested (see DBD-ME-013, Rev. 22, Attachment 1, Note 3).
- 3. The test frequency requirements of Technical Specification SR 3.4.14.1 apply for leak testing of 8701A, 8701 B, 8702A, 8702B, which are more restrictive than the test frequency requirements of ASME OM Code 2004 Edition, through 2006 Addenda, Subsection ISTC-3630.
- 4. For valves 8109, 8808A, 8808B, 8808C and 8808D, position indication testing (PIT) will be performed every two years. These valves have a low safety significance and a six year test frequency requirement; however, a two year test frequency is established to avoid scheduling staggered tests.
- 5. MOV HV-8402A is a passive valve with open safety function for boration flowpath. The design function of HV-8402A is to isolate and bypass HCV-0182 during maintenance and in case of a fire to ensure that the normal charging path is isolated. Since the function to close during a fire is important to safety, HV-8402A will be exercise tested open and closed.
CPNPP UNIT 1 & 2 RISK INFORMED- INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES The following pages contain requests for relief from certain Code test requirements which are identified in the Pump and Valve Testing Plans' tables. The Relief Requests address instances where an alternative to the Code requirements is proposed or where it has been determined that compliance with certain Code requirements is impractical or presents a hardship or unusual difficulty without a compensating increase in the level of plant quality and safety. Relief Requests associated with the lnservice Pump Testing Plan have numbers prefixed with "P". Relief Requests associated with the lnservice Valve Testing Plan have numbers prefixed with "V". Administrative Relief Requests have numbers prefixed with "A". The guidance presented in References 1.5.2, 1.5.8 and 1.5.9 was used to the greatest extent possible in formatting the Relief Requests in this appendix. NRC staff approval pursuant to 10CFR50.55a(a)(3) or (f)(5) is required prior to implementation of a Relief Request. The approval status of each Relief Request in this appendix is indicated individually as part of the Relief Request. COMANCHE PEAK - UNITS 1 AND 2 A-1 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES RELIEF REQUEST NO. A-1 SYSTEM See Tables O through 19. CODE CLASS See Tables O through 19. CATEGORY See Tables 0 t hrough 19. COM PONE NT NO. & See Tables a through 19. This change affects all current components COMPONENT in the CPNPP lnservice Testing (1ST) Plan, and also adds some new DESCRIPTION components to the RI-IST Plan. DESCRIPTlON Risked Informed - lnservice Testing, Alternative from 10CFR50.55a(f}{4)(i) and (ii) for lnservice Testing Frequency: This alternative utilizes a risk-based approach to change the test frequencies of certain low safety significant components (LSSCs) in the ASME OM Code pump and valve inservicetesting (1ST) Program. The extended frequencies are greater than those currently allowed by the ASME OM Code. The process used to identify candidates for frequency extension is discussed under ~Proposed Alternativen and "Basis for Alternative." CURRENT TEST Test frequencies of 2 years or less, the specified frequency for each REQUIREMENTS inservice test is met if the test is performed within 1.25 times the interval specified in frequency. For test frequencies greater than 2 years. the specified frequency for each inservice test is met if the test is performed with the interval specified in frequency (1.25 times interval does not apply). Regulation 10 CFR 50, Section 50.55a(f)(4){i) states; lnservice tests to verify operation readiness of pumps and valves, whose function is required for safety, conducted during the initial 120-month interval must comply with the requirements in the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section on the date 12 months prior to the date of issuance of the operating license subject to the limitations and modifications listed in paragraph (b) of this section. Regulation 10 CFR 50, Section 50.55a(f)(4)(ii) states; In service tests to verify operation readiness of pumps and valves. whose function is required for safety, conducted during successive 120-month interval must comply with the requirements in the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section 12 months prior to the start of the 120-COMANCHE PEAK - UNITS 1 AND 2 A-2 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES month interval, subject to the limitations and modifications listed in paragraph (b) of this section. The ASME Code of record for CPNPP is the ASME OM Code 2004 Edition through 2006 Addenda. The Code specifies the following test frequencies: Test Type Test Frequency (nominal) Code Reference Pump Test 3 months OM ISTB Valve Position Indication 2 years OM ISTC Verification Valve Exercising Test 3 months OM ISTC Valve Fail-Safe Test 3 months OM ISTC Valve Leak Rate Test 2 years OM ISTC (Non-Containment Isolation Valves) Frequency per Appendix J 10CFR50 App. J (Containment Isolation Valves) Check Valve Exercise Test 3 months OM ISTC Safety/Relief Valve Setpoint Test 5 years OM Appendix I (class 1, class 2 MSSV) 10 years (class 2, 3) OM Appendix I PROPOSED In lieu of performing inservice tests on pumps and valves whose ALTERNATIVE function is required for safety at frequencies specified in the ASME Code, as required by 10 CFR 50.55a(f)(4)(i) during the 120-month operating interval, this alternative would allow the in service test frequencies of those pumps and valves to be determined in accordance with an NRC approved Risk-Informed 1ST Program Description at CPNPP as follows: (1) The safety significance of pumps and valves whose function is required for safety will be assessed in accordance with the NRC approved Risk-Informed 1ST Program Description. These components will be classified as either High Safety Significant COMANCHE PEAK - UNITS 1 AND 2 A-3 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Components (HSSCs) or Low Safety Significant Components (LSSCs). The inservice testing of those components classified as LSSC will be performed at extended test frequencies determined in accordance with the Risk-Informed 1ST Program Description. The inservice test methods for all pumps and valves whose function is important to safety will continue to be performed in accordance with the ASME Code. (2) The safety significance assessment of pumps and valves will be updated, as specified in the Risk-Informed 1ST Program Description. This alternative will also apply to 10CFR50.55a(f)(4)(ii) for successive 120-month 1ST intervals. See Attachment 1 for the Risk-Informed lnservice Testing Program Description. BASIS FOR Section 50.55a(a)(3) of 10 CFR states in part: ALTERNATIVE Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f), (g), and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that: (i) The proposed alternatives would provide an acceptable level of quality and safety. TU Electric requests NRC approval to implement the Risk-Informed lnservice Testing Program Description as an alternative to the requirements of 10 CFR 50.55a(f)(4)(i) and (ii). These regulations require that inservice tests on pumps and valves, whose function is required for safety, must comply with a specified ASME Code. Specifically, TU Electric requests approval to utilize a risk-Informed inservice testing program to determine inservice test frequencies for valves and pumps that are identified as low safety significant, in lieu of testing those components at the frequencies specified in the ASME Code. The use of the Risk-Informed lnservice Testing Program Description will provide an acceptable level of quality and safety. The current Code is based on a deterministic approach which considers a set of challenges to safety and determines how those challenges should be mitigated. The deterministic approach contains elements of probability, such as the selection of accidents to be analyzed as design basis accidents (e.g., the reactor vessel rupture is considered too improbable to be included) and the requirements for emergency core cooling (e.g., safety train redundancy). COMANCHE PEAK - UNITS 1 AND 2 A-4 Rev.4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES The Risk-Informed 1ST Program that would be implemented with this alternative incorporates a probabilistic approach to regulation which enhances and extends this traditional, deterministic approach, by: ( 1) allowing consideration of a broader set of potential challenges to safety, (2) providing a logical means for prioritizing these challenges based on risk significance, and (3) allowing consideration of a broader set of resources to defend against these challenges. First, the PRA model has identified a broader set of challenges to safety. The Risk-Informed lnservice Testing Program identified High Safety Significant Components (HSSCs) which were not in the previous ASME 1ST Program. Even though the components are outside the ASME Code class boundary, they will be tested commensurate with their safety significance. Where the ASME OM Code testing is practical, HSSCs not in the current ASME 1ST Program Plan will be tested in accordance with Appendix I for safety relief valves, Subsection ISTC for active valves and Subsection ISTB for pumps. Where ASME OM Code testing is not practical, alternative methods will be developed to ensure operational readiness. Components in the current ASME 1ST Program which are determined to be HSSCs will continue to be tested in accordance with the current Program, which meets the requirements of the ASME OM Code, except where specific written relief has been granted. Components in the current ASME 1ST Program which are determined to be LSSC will also be tested in accordance with the ASME 1ST Program, except that the test frequency will initially be extended to once every 6 years. The extended test frequency will be staggered over 6 years as described in Attachment 1. No LSSC will be deleted from the ASME 1ST Program. Second, the Risk-Informed lnservice Testing Program prioritizes these challenges based on the results of the CPNPP PRA. The risk rankings are then complemented with rankings based on consideration of other accident initiators (e.g. fires, tornadoes, and earthquakes) and plant operating modes. These rankings considered importance with respect to core damage prevention, and prevention of large early releases of radiation to the public. Attachment 1 (pages 5 through 20 of Enclosure 1 to TXX-98086) describes the program methodology. Enclosure 3 to TXX-96371 (TU Electric letter dated June 3, 1996, from C. L. Terry to the NRC) provides the current list of LSSCs from the initial implementation of that methodology. COMANCHE PEAK- UNITS 1 AND 2 A-5 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Third, an Integrated Decision Process (IDP) allows a broader set of resources to be considered to defend against challenges to safety. The I DP is composed of experienced individuals with expertise in the areas of ASME Code, plant operations, maintenance engineering, system engineering, design engineering, and probabilistic risk assessment. The IDP is responsible to ensure the risk ranking input information is consistent with plant design, operating procedures, and with plant-specific operating experience. At the end of the IDP review process every component in the CPNPP ASME 1ST Program is reviewed. The risk-informed process will assure that a defense-in-depth philosophy is maintained. As a living process, components will be reassessed periodically to reflect changes in plant configuration, component performance, test results, industry experience, and other factors. When the list of components is affected, changes will be provided to the NRC in regular Program updates. There could be safety enhancements obtained by focusing resources on HSSCs and reducing the testing frequency on LSSCs. Extensive testing on LSSCs could have an adverse effect on safety. Reduction of testing should reduce component wear-out, operator burden, system unavailability, cost of testing, and radiation exposure. Reduced testing could also achieve a more optimum balance between the positive impacts of testing and the negative effects of disturbing equipment from service and entering less than optimum plant configuration, such as valve misalignments. RADIOLOGICAL Potential radiation exposure will be diminished due to less frequent CONCERNS (ALARA) testing. COMANCHE PEAK - UNITS 1 AND 2 A-6 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 RISK-INFORMED INSERVICE TESTING PROGRAM DESCRIPTION (RI-IST) The proposed alternative is a risk informed process to determine the safety significance and testing strategy of components in the ASME lnservice Testing (1ST) Program, and identify non-ASME 1ST components (pumps & valves) modeled in the Probabilistic Risk Analysis (PRA) that are determined to be High Safety Significant Components (HSSCs). The process consists of the following elements.
- 1) Utilization of the Probabilistic Risk Analysis (PRA) techniques to identify component importance measure values. (PRA Techniques)
- 2) Categorize components based on importance measures determined by the PRA techniques. (Component Risk Category)
- 3) Blended deterministic and probabilistic data to perform a final importance ranking of components and categorization as either Low Safety Significant Component (LSSC) or High Safety Significant Component (HSSC). (Integrated Decision Process) (IDP)
- 4) Develop/Determine Test Frequencies and Test Methodologies for the 1ST components. (Testing Philosophy)
- 5) Evaluate the cumulative impact of the test frequency changes on total plant risk (i.e., CDF and LERF) to ensure that the change in plant safety is within the acceptable range. (Cumulative impact)
- 6) Develop an implementation plan. (Implementation)
- 7) Develop a Corrective Action plan. (Corrective Action)
- 8) Perform periodic reassessments. (Periodic Reassessments)
- 9) Methodology for making changes to the RI-IST. (Changes to RI-IST Program after Initial NRC Approval)
- 1) PRA Techniques PRA methods will be used to determine the risk significance of components based on end states of interest, such as core damage frequency (CDF) and release of radioactivity (e.g.
large early release frequency (LERF)). The PRA techniques are used in conjunction with the Integrated Decision Process (IDP) to ensure that all the available information is accounted for in developing the importance measures. As such, a review of plant equipment and operating procedures will be performed to identify potential plant specific initiating events as well as those initiating events that have been identified in the Nuclear industry. Evaluation of initiating events COMANCHE PEAK - UNITS 1 AND 2 A-7 Rev.4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 will also include loss of support systems and other special initiators. Any changes to the PRA models used for the development of importance measures for the RI-IST will be independently reviewed. The independent reviews will be by either the in-house personnel or outside consultants. The PRA will be periodically evaluated (See Section 8) to reflect the current plant design, procedures, and programs. Also the PRA will be evaluated prior to moving components to the LSSC category. A full scope PRA is not required. However, any limitations {e.g. missing initiating events) will be addressed by the IDP using the methodology described in Section 2 below. The potential degradation of components will be considered in the overall assessment of risk associated with the implementation of the RI-IST. As a result, any effect on common cause failure estimations will also be evaluated. To the extent possible, plant-specific data will be utilized to assess component degradation. Compensatory measures which are used as part of the IDP process to qualitatively justify the extension of test interval will be re-verified during the IDP process update (See Section 6) .
- 2) Component Risk Category Two figures of merit will be used to initially determine the risk categories of 1ST components. These two methods are Fussell-Vesely (FV) and Risk Achievement Worth (RAW,. For the RI-IST Program, the following criteria will be used to initially rank components for review by the Integrated Decision Process (IDP).
Category Criterion High FV > 0.001 Potentially High FV < 0.001 and RAW> 2 Low FV < 0.001 and RAW< 2 The ~CDF and ~LERF for the change are within the acceptance guidelines of Regulatory Guide 1.174. COMANCHE PEAK - UNITS 1 AND 2 A-8 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 Methodology/Decision Criteria for Limited Scope PRA The following describes the methodology used to categorize components in the RI-IST when the program is reassessed. However, only those elements that are significantly affected by the model changes (e.g., design modifications or procedural changes) need to be reviewed in detail using this process. The scope of the review and the justification for it will be documented as part of the IDP. Apply Importance Criteria to PRA and Review Review FV and RAW importance measures for pumps and valves considered in the PRA against the criteria and determine if the grouping of components is logical. Review component importance measures to make sure that their bases are well understood. Robustness/Validation of Results Address the sensitivity of the results to common cause failures (CCF), assuming all/none of the CCF importance is assigned to the associated component.
- Evaluate the sensitivity due to human action modeling. Identify/evaluate operator actions omitted by the PRA that can change the ranking of a component. The omitted recovery actions are those not credited because they are not important to the GDF.
Consider industry history for particular 1ST components. Review such sources as NRG Generic Letters, SOERs, IOERs and Technical Bulletins and rank accordingly. For components with low FV/high RAW ensure that other compensatory measures are available to maintain the reliability of the component.
- Identify and evaluate components whose performance shows a history of causing entry into LCO conditions. To ensure that safety margins are maintained, consider retaining the ASME test frequency for these components.
Ensure that truncated components have been eliminated due to redundancy of function rather than solely due to reliability. If they are truncated due to their high reliability, then those components should be qualitatively re-evaluated and re-categorized appropriately. COMANCHE PEAK - UNITS 1 AND 2 A-9 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/RA-1 Validate or change the PRA-based component ranking. If the validated PRA ranking is high, rank the component high; if the PRA ranking is low and the other factors such as the operating performance of the component validate the ranking, rank as low. Fire, Tornado and Seismic Considerations Consider the following for risk ranking components for external events. Calculate risk importance measures for components in the fire and tornado cutsets. Compare these calculated values and the PRA values to identify those components that are low risk significant for the PRA but high risk significant for fire and tornado.
- Review component importance measures and the PRA limitations for fire and tornado in a manner similar to that described for internal events discussed above and adjust the rankings of the components accordingly.
- For those components on the Safe Shutdown Equipment List (SSEL) and the containment systems list, review their risk categories to ensure that those components important to seismic and containment integrity are appropriately categorized.
Outage Risk Importance A qualitative assessment of PRA systems modeled for shutdown modes will be performed to determine the impact of shutdown modes on 1ST rankings. To perform this analysis a three step process will be used. First, using existing PRA system models as the basis, components and system configurations that are unique to the shutdown modes from the at power PRA will be identified. Second, using a qualitative set of rules, components in key trains will be ranked into three categories:
- 1. Category 1: High safety significant components (high FV)
- 2. Category 2: Potentially high safety significant components (low FV, moderate to high RAW).
- 3. Category 3: Low safety significant components (low FV, low RAW)
Third, support systems that are unique to shutdown configurations will also be identified and ranked accordingly. There are several safety functions important to shutdown. These are Over-Pressure Protection, Shutdown Cooling, Spent Fuel Pool Cooling, Inventory COMANCHE PEAK- UNITS 1 AND 2 A-10 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 Control, Reactivity Control, AC Power, and Containment Integrity. Rather than analyzing each function separately, the systems required for the shutdown accident sequences will be analyzed and ranked with respect to their shutdown configurations. This will provide a comprehensive review of the shutdown systems and their unique configurations. The risk profile for an outage changes as maintenance activities start and stop and plant states change. Therefore, the importance of components can also change during the outage, depending on the plant configuration as governed by the outage schedule. There can be times when almost any component can become more risk significant depending upon the outage scenario. If the plant is in a configuration of increased risk, and an 1ST component must operate to respond to an accident, that component will be more risk significant for that time period. If that period of time is extended, then the component on average will be more risk significant. A major difference between at power and shutdown is that safety systems are in a standby mode at power and active components must start or reposition automatically for success. Since actuation failure is much more likely than failure to continue to operate, a reliability-oriented risk importance measure like Fussell-Vesely is lower for outage than at power. However, since functional importance is similar, the RAW value is likely to be the same and its FV is correspondingly lower. Also, during shutdown, automatic actuations are usually blocked and pumps and valves are actuated by manual operation only. Since the failure probability for human action may at times be more likely than automatic actuation, the contribution of equipment failure is relatively less likely. Therefore, in most cases the ranking of components at power is higher than during shutdown, although the system configuration must still be compared to determine if there are unique differences for the shutdown mode. Based upon the insights discussed above, the approach to risk ranking is as follows:
- If a component performs the same function and is in the same initial state as at power, the at power ranking is assumed to bound the outage ranking.
- If a component performs a different function or is in a different initial state than at power, then the outage ranking must be evaluated.
The latter evaluation involves cases where a different system is used, i.e., spent fuel pool cooling, or where a different function is performed by a component in a system "used" at power or during an outage. Additionally the following guidelines are used for risk ranking for shutdown. COMANCHE PEAK - UNITS 1 AND 2 A-11 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 Category 1 - High Safety Significant Components (High FV): Pumps that must start to perform function (assume all pumps in systems that cycle operating trains)(High FV) Motor Operated Valve (MOV) or Air Operated Valve (AOV) that must change state to perform function (but not portions with redundant paths, e.g. two supply sources to one pump)(High FV)
- MOV or AOV that must change state to prevent flow diversion that can fail redundant trains (high FV, extremely high RAW)
- Pressure relief valves (safety or power operated) needed to control pressure so that redundant trains of systems can perform function (high FV or low FV, high RAW)
Category 2 - Potentially High Safety Significant Components (low FV & moderate to high RAW): Pumps that must continue running (low FV, moderate RAW) Valves in single path portions of redundant systems that are not required to change state (RHR outlet valves)(usually low FV, moderate or high RAW)
- Check valve plus MOV or AOV that must remain as is if they are in the trains only flow path (low FV, moderate RAW)
- Check valves for which reverse flow can fail redundant trains simultaneously (low FV, extremely high RAW)
- MOV or AOV which if they change state can cause flow diversion that can fail redundant trains (low FV, extremely high RAW)
Control components that need to function to prevent system degradation (e.g. AFWflow control valves to the Steam Generators that can fail the Turbine Driven AFW pump)(low FV, moderate RAW) Category 3 - Low Safety Significant Components (low FV & low RAW): All other Components that do not fall into category 1 or 2 were ranked low. COMANCHE PEAK - UNITS 1 AND 2 A-12 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/RA-1 These rules will be applied to the systems that support the safety functions described herein. Back-end Risk Importance It is equally important to identify those pumps and valves that prevent containment failure or bypass that could result in an unacceptable release. Examples might include the valves that provide the boundary between the reactor coolant system and low-pressure systems located outside containment. Various analyses have shown that large releases, though infrequent and of low probability, tend to dominate offsite consequences. Therefore, those 1ST components identified by back-end analyses will be ranked according to their importance to large early release frequency only. Containment isolation failures or containment bypass events can, in some accident scenarios, cause a large, early release. The associated valves represent a substantial fraction of components treated by the 1ST program. However, their importance varies significantly depending on their initial position, their size, the leak path they are in, etc. These factors will be evaluated with a simple model consistent with the PRA back-end analysis. Risk importance of containment functions will be measured by developing quantitative importance measures for accidents contributing to large, early releases. The large, early releases are more likely to result from accidents with the following attributes:
- A failure in containment exists at the time of the accident, either because the containment fails to isolate or it is bypassed, or
- A high-pressure core meltdown occurs with containment heat removal (sprays) unavailable at the time of core melting.
One cause of a large, early release is a steam generator tube rupture, with immediate failure of core cooling, and failure of the main steam system to isolate. A large but not early release can also occur if the same scenario occurs except that core cooling fails late in the accident rather than immediately. This latter scenario is the most likely source of a large release. However, because adequate time would be available to implement emergency response measures, this source of a large release will not be considered in the importance measure calculation. Instead, the most important sources of main steam isolation failure are considered potentially important and will be reviewed by the IDP to determine if the associated valves should be categorized as high. COMANCHE PEAK - UNITS 1 AND 2 A-13 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 1ST Components Not in PRA Review components not explicitly modeled in the PRA to ensure an 1ST component is, in fact, low risk. High-Risk PRA Components Not in the 1ST Program Identify other high risk pumps and valves that are not in the 1ST program but should be tested commensurate with their risk importance.
- Evaluate the PRA modeling assumptions, component failure modes, operator actions, recoveries and any other effects that could substantiate the components risk category as "high risk" even if they are not in the 1ST Program.
- Determine whether current plant testing is commensurate with the importance of these valves. If not, determine what test, e.g., the 1ST test, would be the most appropriate.
Other Considerations Perform sensitivity studies, as needed, to evaluate the cumulative impact of changes in the 1ST Program test strategies on the total Core Damage Frequency (CDF).
- 3) Integrated Decision Process The purpose of utilizing the Integrated Decision Process (IDP) is to confirm or adjust the initial risk ranking developed from the PRA results, and to provide qualitative assessment based on engineering judgement and experience. This qualitative assessment compensates for limitations of the PRA, including cases where adequate quantitative data is not available.
The IDP utilizes deterministic insights, engineering judgement, experience and regulatory requirements as described above in Section 2. The IDP will review the initial PRA risk ranking, evaluate applicable deterministic information, and determine the final safety significance categories. The IDP considerations will be documented for each individual component to allow for future repeatability and scrutiny of the categorization process. The scope of the IDP includes both categorization and application. The IDP is to provide deterministic insights that might influence categorization. The IDP will identify components whose performance justifies a higher categorization. The IDP will determine appropriate changes to testing strategies. The IDP will identify compensatory measures for potentially high components or justify the final COMANCHE PEAK - UNITS 1 AND 2 A-14 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 categorization. The IDP will also concur on the test interval for components categorized as low. The end product of the I DP will be components categorized as Low Safety Significant Component (LSSC) or High Safety Significant Component (HSSC). In making these determinations, the IDP will ensure that key safety principles, namely defense-in-depth and safety margins, are maintained and that the changes in risk for both CDF and LERF are acceptable per the guidelines discussed in Section 2 above. The key safety principles are described below. Defense in Depth To ensure that defense-in-depth is maintained by the CPNPP RI-IST program, adherence to four basic principles will be reviewed and documented as part of the I DP for any future changes to the program. The following describes these four basic principles:
- 1. No changes to the plant design or operation's procedures will be made as part of the RI-IST program which either significantly reduce defense-in-depth or place strong reliance on any particular plant feature, human action, or programmatic activity.
- 2. The results and dominant contributors to core damage risk will be reviewed to ensure that the categorization of components using PRA is done on an evenhanded basis covering the full scope of safety functions. A review will be done to ensure that components which mitigate the spectrum of accidents are not ranked low solely because of initiating event frequency. Further, sensitivity studies will be performed for human actions to ensure that components which mitigate the spectrum of accidents are not ranked low solely because of the reliability of a human action.
- 3. The methodology for component categorization, namely the selection of importance measures and how they are applied and understanding the basic reasons why components are categorized HSSC or LSSC, will be reviewed to ensure that redundancy and diversity are preserved as the more important principles. If a component is categorized as LSSC solely due to its high reliability, then it must be confirmed that: 1) plant performance has been good and 2) a compensatory measure or feedback mechanism is available to ensure adverse trends in equipment performance can be detected in a timely manner. A review will be done to ensure that relaxation in the RI-IST program occurs only when the level of redundancy or diversity in the plant design or operation supports it. In this regard, all components that have significant contributions to common cause failure will be reviewed to avoid relaxation of requirements on those components with the lowest level of diversity within the system.
COMANCHE PEAK - UNITS 1 AND 2 A-15 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1
- 4. The use of multiple risk metrics, including core damage frequency (CDF) and large early release frequency (LERF), with additional checks for large but late releases and consequence mitigation, will be done to ensure a reasonable balance between risk reduction methods.
Other Considerations Related To Defense-In-Depth When the PRA does not explicitly model a component, function or mode of operation, a qualitative method may be used to classify the component HSSC or LSSC and to determine whether a compensatory measure is required. Sufficient Safety Margin is Maintained The IDP will perform reviews to ensure that sufficient safety margin is maintained when compared to the existing 1ST program. In performing this review, the IDP will consider such things as proposed changes to test intervals and, where appropriate, test methods. The IDP will ensure that the proposed compensatory measures are effective fault finding tasks, where this is required in the program, to assure safety margin is maintained. To enhance the safety margin, the IDP will also review PRA-important components not in the current 1ST program for potential inclusion in the RI-IST program. Categorization Guidelines Modeled Components/Functions For modeled components/functions with a FV >0.001 the IDP either confirms the component categorization is HSSC or justification of conservatism in the PRA model will be developed. For modeled components/functions with a FV <0.001, but a RAW >2.0, the component will be categorized LSSC provided a compensatory measure exists that ensures operational readiness and the components' performance has been acceptable. If a compensatory measure is not available or the component has a history of performance problems, the component will be ranked HSSC. For modeled components/functions with a FV <0.001 and a RAW <2.0, the component will be categorized as LSSC provided the components' performance has been acceptable. For those components with performance problems, a compensatory measure will be identified to ensure operational readiness or the component will be categorized as HSSC. Non-Modeled Components/Functions For components not modeled or the safety function not modeled in the PRA, the categorization is as follows: COMANCHE PEAK- UNITS 1 AND 2 A-16 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 If the sister train is modeled then the component takes that final categorization. If the component is implicitly modeled, the FV and RAW are estimated and the deliberation is as discussed for modeled components/functions. If the component is not implicitly modeled, the system ranking associated with the Maintenance Rule will be confirmed. For confirmed system ranking, the component performance history will be reviewed. For acceptable performance history the component will be categorized as LSSC. For poor performance history, a compensatory measure will be identified to ensure operational readiness and the component categorized as LSSC, or if no compensatory measures are available, categorize the component as HSSC. Documentation Documentation of the IDP will be available for review at the plant site.
- 4) Testing Philosophy Motor Operated Valves (MOVs)
HSSC Testing will be performed in accordance with Code Case OMN-1 (except the maximum diagnostic test interval will be 6 years), and NRG Generic Letter 89-10 and 96-05 commitments. LSSC Testing will be performed in accordance with Code Case OMN-1 (except the maximum diagnostic test interval will be 10 years), and NRG Generic Letter 89-10 and 96-05 commitments. Performance Monitoring (applicable to HSSC and LSSC):
- termination inspection stem threads re-lubed
- actuator gear box grease if')spection
- T-drain inspection limit switch gear box grease inspection
- visual inspection of housings stem nut staked and secure COMANCHE PEAK- UNITS 1 AND 2 A-17 Rev.4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 Relief Valves HSSC & Testing will be performed in accordance with Code of Record as LSSC defined in 10CFR50.55a. Performance Monitoring (applicable to HSSC and LSSC): test results trended
- new valves tested prior to installation
- valves set as close to nominal as practical Check Valve Testing Strategy HSSC Testing will be performed in accordance with the ASME Code of Record as defined by 10CFR50.55a.
Certain HSSC check valves will also be tested in accordance with the Check Valve Reliability Program (CVRP). This program was developed in response to INPO SOER 86-03. Testing for the CVRP includes nonintrusive testing (e.g. acoustic monitoring) and where conditions direct, valve disassembly. The enhanced nonintrusive testing provides for condition monitoring by comparing data from current testing to a known baseline where the valve was operating in a satisfactory manner LSSC Testing will be performed in accordance with the ASME Code of Record as defined by 10CFR50.55a except at a test frequency not to exceed 6 years. Test frequencies of 2 years or less, the specified frequency for each inservice test is met if the test is performed within 1.25 times the interval specified in frequency. For staggered test frequencies greater than 2 years (typically 3 to 6 years), the specified frequency for each inservice test is met if the test is performed within 1.25 times the 18 month interval, but not to be deferred past the next refueling outage. Certain LSSC check valves will be tested in accordance with the CVRP as necessary. COMANCHE PEAK - UNITS 1 AND 2 A-18 Rev.4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 Check valves included in the CVRP are those which have been evaluated to be susceptible to wear, fatigue, or corrosion. Performance Monitoring (applicable to HSSC and LSSC): acoustic monitoring data when taken is trended check valve disassembly inspections where necessary Air Operated Valves (AOVs) HSSC Testing will be performed in accordance with the Code of Record as defined by 10CFR50.55a. LSSC Testing will be performed in accordance with the Code of Record as defined by 10CFR50.55a except with a test frequency not to exceed 6 years. Additionally LSSC AOVs will be stroked at least once during the operating cycle. Test frequencies of 2 years or less, the specified frequency for each inservice test is met if the test is performed within 1.25 times the interval specified in frequency. For staggered test frequencies greater than 2 years (typically 3 to 6 years), the specified frequency for each inservice test is met if the test is performed within 1.25 times the 18 month interval, but not to be deferred past the next refueling outage. Performance Monitoring (applicable to HSSC and LSSC):
- diagnostic testing
- elastomer replacement response time testing Note: Luminant Power is participating in a tailored collaboration project with EPRI to develop an AOV program similar to the MOV Program mandated by GL 89-10 and 96-05. This program will evaluate the valve/operator characteristics/capabilities and the design conditions under which the valve is expected to operate. Once this information is developed the valves will be tested and modified as necessary to meet their safety function. AOV's which are being evaluated by the EPRI Tailored Collaboration are:
COMANCHE PEAK - UNITS 1 AND 2 A-19 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED- INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1
- 1) an HSSC AOV from each grouping (i.e. same manufacturer, size)
- 2) an LSSC AOV from other groups not included from (1) above.
Pumps HSSC Testing will be performed in accordance with the Code of Record as defined by 10CFR50.55a. LSSC Testing will be performed in accordance with the Code of Record as defined by 10CFR50.55a except with a test frequency not to exceed 6 years. Test frequencies of 2 years or less, the specified frequency for each inservice test is met if the test is performed within 1.25 times the interval specified in frequency. For staggered test frequencies greater than 2 years (typically 3 to 6 years), the specified frequency for each inservice test is met if the test is performed within 1.25 times the 18 month interval, but not to be deferred past the next refueling outage. COMANCHE PEAK- UNITS 1 AND 2 A-20 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 Performance Monitoring (applicable to HSSC and LSSC):
- thermography of the drivers
- lube oil analysis
- alignment checks
- motor current testing vibration monitoring
- flange loading checks of connected piping
- 5) Cumulative Impact Evaluate the cumulative impact of the test frequency changes on total plant risk (i.e., CDF and LERF) to ensure that the change in plant safety is within the acceptable range.
This will be done by performing various sensitivity studies to determine the potential risk impact of increasing in-service testing intervals simultaneously on all low risk significant components. The unavailabilities of the 1ST components in the low-risk category will be increased by a factor equivalent to the proposed increase in the component test interval. For each sensitivity case, the PRA cutset results will be requantified using the adjusted component unavailabilities due to the proposed test intervals. The new total CDF and LERF for each case will be obtained. These new values will, then, be compared with the CDF and LERF of the base case to assess the net change in total plant risk due to proposed 1ST test frequencies. In addition, component risk importances will be re-evaluated for the following groups of 1ST components to identify any components that may move up from low safety significant components to high safety significant components: Group 1: Low FV, high RAW with credit taken for compensatory measures identified by the IDP (i.e., other surveillance tests on the same piece of equipment). Group 2: Low FV, low RAW with no credit taken for compensatory measures because this category implies that increases in component unavailabilities are not expected to impact risk significantly. COMANCHE PEAK- UNITS 1 AND 2 A-21 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1 Due to uncertainty in how test interval changes will actually affect the component unavailabilities, a number of conservative assumptions are made as summarized below: It is assumed that any increase in test intervals would simultaneously impact the reliability of all 1ST components in the low safety-significant component (LSSC) category.
- Consistent with the PRA techniques, the component unavailability required to change state, is assumed to be:
Q = Aoo + A(T/2) Q = total component unavailability Where Aoo = Component unavailability on demand A = Component failure rate per hour T = Interval between tests that verify operability of the component The component unavailability is assumed to increase by the same factor as the increase in the test interval. For example, a change in the test interval from quarterly to semi-annually is assumed to increase the total component unavailability by a factor of two. This is a very conservative assumption because it assumes that not only the A(T/2) term would be increased by a factor of two, but also the failure on demand term (Aoo) term is assumed to be directly impacted by the change in the test interval.
- Decrease in wear out due to less frequent testing is assumed to be negligible although frequent testing has been seen to cause components to be less available due to wearout.
- It is conservatively assumed that all 1ST tests are fully effective in finding the causes of component unavailabilities.
The PRA models will be updated to reflect the changes to the test frequency of modeled components, and the PRA study will be re-evaluated to quantify the aggregate impact of the changes. The cumulative impact of the test frequency changes will be reviewed through the IDP. COMANCHE PEAK - UNITS 1 AND 2 A-22 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/R A-1
- 6) Implementation Implementation of the RI-IST to LSSC will consist of grouping components and then staggering the testing of the group over the test frequency.
Grouping: Components will be grouped based on:
- manufacturer - model - service condition - size The population of the group will be dependent on: - total population available - maintaining current testing schedule Grouping components in this manner and testing on a staggered basis over the test frequency will reduce the importance of common cause failure modes as components in the same staggering failure mode group are continually being tested. This ensures that the component capability will be maintained over the test interval (i.e., 6 years).
Testing of components within the defined group will be staggered over the test interval, typically 6 years. Testing will be scheduled on regular intervals over the 6 year period to ensure all components in the group are tested at least once during the 6 year test interval and not all components are tested at one time. The staggering allows the trending of components in the group to ensure the test frequency selected is appropriate. Testing will be scheduled/planned such that there is no more than one cycle between tests of components in a group.
- 7) Corrective Action When a component on the extended test interval fails to meet established test criteria, corrective actions will be taken in accordance with the CPNPP corrective action program as described below for the RI-IST.
For components not meeting the acceptance criteria, a Smart Form will be generated. This document initiates the corrective action process. Also, the initiating event for a COMANCHE PEAK - UNITS 1 AND 2 A-23 Rev.4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES ATTACHMENT TO R/RA-1 Smart Form may be from causes other than an unacceptable 1ST test. Programs exist that provide timely information to the 1ST Engineer that the performance of a reliable component has degraded. For example, a common compensatory action for pump discharge check valves would be the 1ST pump test. Since this test can not be considered satisfactory if the check valve fails to perform its risk significant function, a test failure would be recorded and a Smart Form initiated. The recorded information could then be used to assess whether a significant change in component reliability has occurred such that the component would merit a change in test interval. The initiating event could be any other indication that the component is in a non-conforming condition. The unsatisfactory condition will be evaluated to: a) Determine the impact on system operability and take appropriate action. b) Review the previous test data for the component and all components in the group. c) Perform a root cause analysis. d) Determine if this is a generic failure. If it is a generic failure whose implications affect a group of components, initiate corrective action for all components in the affected group. e) Initiate corrective action for failed 1ST components. f) Evaluate the adequacy of the test strategy. If a change is required, review the 1ST test schedule and change as appropriate. The results of component testing will be provided to the PRA group for input to PRA model evaluation. (See Section 8) For an emergent plant modification, any new 1ST component added will initially be included at the current Code of Record test frequency. Only after evaluation of the component through the RI-IST Program (i.e., PRA model evaluation if applicable and IDP review) will this be considered LSSC.
- 8) Periodic Reassessment As a living process, components will be reassessed at a frequency not to exceed every other refueling outage (based on Unit 1 refueling outages) to reflect changes in plant configuration, component performance test results, industry experience, and other inputs to the process. The RI-IST reassessment will be completed within 9 months of completion of the outage.
Part of this periodic reassessment will be a feedback loop of information to the PRA. This will include information such as components tested since last reassessment, number and COMANCHE PEAK- UNITS 1 AND 2 A-24 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES type of tests, number of failures, corrective actions taken including generic implication and changed test frequencies. Once the PRA has been reassessed, the information will be brought back to the IDP for deliberation and confirmation of the existing lists of HSSCs and LCCSs or modification of these lists based on the new data. As part of the IDP, confirmatory measures previously utilized to categorize components as LSSC will be validated. Additionally, the maximum test interval will be verified or modified as dictated by the IDP.
- 9) Changes to RI-IST after Initial NRC Approval Changes to the process described above and to the evaluation of risk impact will require prior NRC approval. Changes to the categorization of components and associated testing strategies using the above process will not require prior NRC approval. As changes to component categorization are made, TU Electric will periodically submit them to the NRC for their information.
NRC APPROVAL Approved. Reference safety evaluation dated August 14, 1998 for STATUS Units 1 & 2. COMANCHE PEAK - UNITS 1 AND 2 A-25 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES RELIEF REQUEST NO. P-1 SYSTEM Vents & Drains PUMP NUMBER CP1-WPAPSS-01 CP2-WPAPSS-0 1 CP1-WPAPSS-02 CP2-WPAPSS-02 CP1-WPAPSS-03 CP2-WPAPSS-03 CP1-WPAPSS-04 CP2-WPAPSS-04 CLASS 3 DESCRIPTION Safeguards Building Floor Drain Sump TEST REQUIREMENT ASME OM Code: ISTB-3540 (b), "Vibration" ISTB-5200 (a) (1 ), "Duration of Tests" ISTB-5221, "Group A Test Procedure" ISTB-5223, "Comprehensive Test Procedure" REFERENCES 1. Generic Letter 89-04, "Guidance for Developing Acceptablelnservice Testing Programs"
- 2. NUREG-1482, Revision 1, "Guidelines for lnservice Testing atNuclear Power Plants" BASIS FOR RELIEF The Safeguards Building Sump Pumps are required to detect and mitigate passive failures in the Emergency Core Cooling System (ECCS) and Containment Spray (CT) System post-LOCA and to prevent flooding of the safety-related systems.
There is no recirculation line from the discharge header of the pumps back to the sumps. There are no installed pressure instruments on the pump suction or discharge. Without a recirculation line on each pump discharge, the only method to meet the Group A Test procedure requirement is to set a reference flow of 0 gpm, dead-head the pump, calculate the differential pressure and record vibration. Differential pressure is determined by making elevation corrections to the discharge pressure reading taken from an installed test gage at a vent connection. This vent connection is remotely located in a different COMANCHE PEAK- UNITS 1 AND 2 A-26 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES room on a different floor elevation than the sump pumps. An elevation difference is also measured on the suction side between the sump cover and the sump water surface. This procedure takes a minimum of four test personnel to conduct the test in this manner. This test has proven to be very difficult and operating experience and equipment history show that testing the pump in a dead-head condition can cause equipment reliability concerns. CPNPP lnservice Testing Program is an approved Risk-Informed lnservice Testing (RI-IST) Program as described in the Safety Evaluation Report (TAC NOS. M94165, M94166, MA1972, and MA 1973). The basis of the RI-IST Program is that there could be safety enhancements obtained by focusing resources on High Safety Significant Components (HSSCs). Extensive testing on Low Safety Significant Components (LSSCs) could have an adverse effect on safety. Reduction of testing should reduce component wear, operator burden, system unavailability, cost of testing, and radiation exposure. Reduced testing could also achieve a more optimum balance between the positive impacts of testing and the negative effects of disturbing equipment from service and entering a less than optimum plant configuration, such as valve misalignments. The CPNPP Safeguards Building Sump Pumps (SBSPs) have a low risk ranking and are tested every six years on a staggered test basis, such that at least two pumps are tested every 18 months. To meet the operational readiness requirements for these pumps, a test should require that the pump starts on the proper level switch actuation, determine that the pump is capable of delivering a minimum of 50 gpm to the Waste Holdup Tank (WHT), and that velocity-based vibration readings are satisfactory. Differential pressure measurement is not needed to show adequate pump performance. Differential pressure measurement may result in additional radiation exposure to personnel (ALARA) and potential equipment damage due to dead-heading the pump. Pumping 50 gpm or more to the WHT demonstrates that an adequate head was developed to overcome system resistance and greater confidence exists that the ASME OM Code requirements for operational readiness have been met. These pumps alert the operator of potential leakage in the safeguards building and mitigate the consequences of the leakage. To meet the testing requirements of ASME OM Code, Subsection ISTB, the pumps must be dead-headed for extended periods. SUBSTITUTE TEST The pumps shall be tested in accordance with ISTB-5221 (Group A pump test) and ISTB-5223 (Comprehensive pump test) for measuring flow and vibration. The sump will be filled to a predetermined level and the pump will operate until the rapidly (approximately 50 seconds) by COMANCHE PEAK - UNITS 1 AND 2 A-27 Rev.4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES automatic low-level cutoff switch actuates. The sump will be pumped down rapidly (approximately 50 seconds). Suction pressure will vary as sump level changes; therefore, the 2 minute stabilization time and differential pressure measurement are not achievable. The test will require pumping the same quantity of fluid along a repeatable system path while measuring flow and vibration. A baseline reference value shall be established for flow and vibration. Alert and Required Action Limits for vibration will be established and maintained as per Table ISTB-5221-1 for vertical line shaft centrifugal pumps. Vibration will be measured in a single direction due to the short pump run and the ability to acquire a single vibration reading during this time period. The acceptance criteria for flow will be greater than the design flow of 50 gpm. The flowrate delivered will be trended for detecting pump degradation to ensure the SBSPs have adequate design margin. NRC APPROVAL Approved for the third ten year 1ST program interval; reference safety STATUS evaluation dated June 26, 2013 for Units 1 & 2, TAC NOS. ME9259 and M E9260 [ML13050A183]. COMANCHE PEAK - UNITS 1 AND 2 A-28 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES RELIEF REQUEST NO. T-1 SYSTEM See Tables O through 19 CODE CLASS See Tables O through 19 CATEGORY See Tables O through 19 COMPONENT NO. & See Tables Othrough 19, this change affects all current components in COMPONENT the CPNPP lnservice Testing (1ST) Plan. DESCRIPTION BASIS FOR RELIEF ASME OM Code Section 1ST establishes the inservice test frequency for all components within the scope of the Code. The frequencies (e.g., quarterly) have always been interpreted as "nominal" frequencies (generally as defined in the Table 3.2 of NUREG-1482, Guidelines for lnservice Testing at Nuclear Power Plants, Revision 2 [dated October 2013 (ADAMS Accession No. ML13295A020)]) and owners routinely applied the surveillance extension time period (i.e., grace period) contained in the plant Technical Specifications (TSs) Surveillance Requirements (SRs). The TSs typically allow for a less than or equal to 25% extension of the surveillance test interval to accommodate plant conditions that may not be suitable for conducting the surveillance (TS SR 3.0.2). However, Regulatory Issue Summary 2012-10, NRC Staff Position on Applying Surveillance Requirements (SRs) 3.0.2 and 3.0.3 to Administrative Controls Program Tests, [dated August 23, 2012 (ADAMS Accession No. ML12079A393),] states that SR 3.0.2 and 3.0.3 cannot be applied to TS 5.5, Programs and Manuals, for tests that are not associated with a TS SR. TS SR 3.0.2 is equivalent to SR 3.0.2 contained in NUREG-1431, Standard Technical Specifications, Westinghouse Plants, [Revision 4 (ADAMS Accession No. ML12100A222)] The lack of a tolerance band on the ASME OM Code inservice test frequency restricts operational flexibility. There may be a conflict where a surveillance test could be required (i.e., its frequency could expire), but where it is not possible or not desired that it be performed until sometime after a plant condition or associated Limiting Condition for Operation (LCO) is within its applicability. The NRC recognized this potential issue in the TSs by allowing a frequency tolerance as described in TS SR 3.0.2. The lack of a similar tolerance applied to the [ASME] OM Code testing places an unusual hardship on the plant to adequately schedule work tasks without operational flexibility. COMANCHE PEAK - UNITS 1 AND 2 A-29 Rev.4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Thus, just as with TS-required surveillance testing, some tolerance is needed to allow adjusting [ASME] OM Code testing intervals to suit the plant conditions and other maintenance and testing activities. This assures operational flexibility when scheduling surveillance tests that minimize the conflicts between the need to complete the surveillance and plant conditions. TEST REQUIREMENT ISTA-3120, "lnservice Test Interval," (a) states, "The frequency for inservice testing shall be in accordance with the requirements of Section IST." ISTB-3400, "Frequency of lnservice Tests," states, "An inservice test shall be run on each pump as specified in Table ISTB-3400-1." ISTC-3510, "Exercising Test Frequency," states, "Active Category A, Category 8, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, ISTC-3550, ISTC-3570, ISTC-5221, and ISTC-5222. Power-operated valves shall be exercise tested once per fuel cycle." ISTC-3540, "Manual Valves," states, "Manual valves shall be full-stroke exercised at least once every 2 years, except where adverse conditions may require the valve to be tested more frequently to ensure operational readiness. Any increased testing frequency shall be specified by the Owner. The valve shall exhibit the required change of obturator position." ISTC-3630, "Leakage Rate for Other Than Containment Isolation Valves," (a) "Frequency," states, "Tests shall be conducted at least once every 2 years." ISTC-3700, "Position Verification Testing," states, in part, "Valves with remote position indicators shall be observed locally at least once every 2 years to verify that valve operation is accurately indicated." ISTC-5221, "Valve Obturator Movement," (c)(3), states, "At least one valve from each group shall be disassembled and examined at each refueling outage; all valves in each group shall be disassembled and examined at least once every 8 years." Mandatory Appendix I, "lnservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear Power Plants," 1-1320, "Test Frequencies, Class 1 Pressure Relief Valves," (a), "5-Year Test Interval," states, in part, "Class 1 pressure relief valves shall be tested at least once every 5 years, starting with initial electric power generation." COMANCHE PEAK - UNITS 1 AND 2 A-30 Rev.4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Mandatory Appendix I, 1-1330, 'Test Frequency, Class 1 Nonreclosing Pressure Relief Devices," states, "Class 1 nonreclosing pressure relief devices shall be replaced every 5 years unless historical data indicates a requirement for more frequent replacement." Mandatory Appendix I, 1-1340, 'Test Frequency, Class 1 Pressure Relief Valves That Are Used for Thermal Relief Application," states,
'Tests shall be performed in accordance with 1-1320, Test Frequencies, Class 1 Pressure Relief Valves."
Mandatory Appendix I, 1-1350, 'Test Frequency, Classes 2 and 3 Pressure Relief Valves," (a), "10-Year Test Interval," states, in part, "Class 2 and 3 pressure relief valves, with the exception of PWR [pressurized-water reactor] main steam safety valves, shall be tested every 10 years, starting with initial electric power generation." Mandatory Appendix I, 1-1360, "Test Frequency, Classes 2 and 3 Nonreclosing Pressure Relief Devices," states, "Classes 2 and 3 nonreclosing pressure relief devices shall be replaced every 5 years, unless historical data indicates a requirement for more frequent replacement." Mandatory Appendix I, 1-1370, "Test Frequency, Classes 2 and 3 Primary Containment Vacuum Relief Valves," (a) states, "Tests shall be performed on all Classes 2 and 3 containment vacuum relief valves at each refueling outage or every 2 years, whichever is sooner, unless historical data requires more frequent testing." 1-1370 (b) states "Leak tests shall be performed on all Classes 2 and 3 containment vacuum relief valves at a frequency designated by the Owner in accordance with Table ISTC-3500-1." Mandatory Appendix I, 1-1380, "Test Frequency, Classes 2 and 3 Vacuum Relief Valves, Except for Primary Containment Vacuum Relief Valves," states, "All Classes 2 and 3 vacuum relief valves shall be tested every 2 years, unless performance data suggest the need for a more appropriate test interval." Mandatory Appendix I, 1-1390, 'Test Frequency, Classes 2 and 3 Pressure Relief Devices That Are Used for Thermal Relief Application," states, 'Tests shall be performed on all Classes 2 and 3 relief devices used in thermal relief application every 10 years, unless performance data indicate more frequent testing is necessary. In lieu of tests the Owner may replace the relief devices at a frequency of every 10 years, unless performance data indicate more frequent replacements are necessary." COMANCHE PEAK - UNITS 1 AND 2 A-31 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED- INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES PROPOSED The ASME OM Code specifies component test frequencies based ALTERNATIVE either on elapsed time periods (e.g., quarterly, 2 years, etc.) or on the occurrence of plant conditions or events (e.g., cold shutdown, refueling outage, upon detection of a sample failure, following maintenance, etc.). ASME OM Code, Code Case OMN-20, describes test frequency grace periods associated with the 1ST program for pumps and valves as follows: (a) Components whose test frequencies are based on elapsed time periods shall be tested at the frequencies specified in Section 1ST with a specified time period between tests as shown in the table below. Frequency Specified Time Period Between Tests Quarterly 92 days (or every 3 months) Semiannually 184 days (or every 6 months) Annually 366 days (or every year) x Years x calendar years where 'x' is a whole number of years ~ 2 The specified time period between tests may be reduced or extended as follows:
- 1) For periods specified as less than 2 yr, the period may be extended by up to 25 percent for any given test.
- 2) For periods specified as greater than or equal to 2 yr, the period may be extended by up to 6 months for any given test.
- 3) All periods specified may be reduced at the discretion of the owner (i.e., there is no minimum period requirement).
Period extension is to facilitate test scheduling and considers plant operating conditions that may not be suitable for performance of the required testing (e.g., performance of the test would cause an unacceptable increase in the plant risk profile due to transient conditions or other ongoing surveillance, test or maintenance activities). Period extensions are not intended to be used repeatedly COMANCHE PEAK- UNITS 1 AND 2 A-32 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES merely as an operational convenience to extend test intervals beyond those specified. Period extensions may also be applied to accelerated test frequencies (e.g., pumps in alert range) and other less than 2 yr test frequencies not specified in the table above. Period extensions may not be applied to the test frequency requirements specified in ASME OM Code Subsection ISTD, Preservice and lnservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants, as Subsection ISTD contains its own rules for period extensions. (b) Components whose test frequencies are based on the occurrence of plant conditions or events may not have their period between tests extended except as allowed by the ASME OM Code. NRC APPROVAL Approved for the remainder of the third ten year 1ST program interval; STATUS reference safety evaluation dated January 19, 2016 for Units 1 & 2, [ML16011A073]. COMANCHE PEAK- UNITS 1 AND 2 A-33 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES RELIEF REQUEST NO. V-1, Revision 0 SYSTEM See attached table VALVE NUMBER See attached table CA TE GORY See attached table CLASS See attached table DESCRIPTION See attached table BASIS FOR RELIEF Pursuant to the guidelines provided in NUREG-1482, Rev. 1, Section 4.2.5, and the conditions stated in RG 1.192, CPNPP proposes to implement Code Case OMN-1 Revision 1, in lieu of the stroke-time provisions specified in ISTC-5120 for MOVs as well as the position verification testing in ISTC-3700. TEST REQUIREMENT ISTC-5120, Motor-Operated Valves, ISTC-5121(a) states: "Active valves shall have their stroke times measured when exercised in accordance with ISTC-3500." ISTC-3700, Position Verification Testing, states in part: "Valves with remote position indicators shall be observed locally at least once every 2 years to verify that valve operation is accurately indicated." ISTC-3510, Exercising Test Frequency, states: "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, ISTC-3550, ISTC-3560, ISTC-5221, and ISTC-5222. Power-operated relief valves shall be exercise tested once per fuel cycle." SUBSTITUTE TEST The use of Code Case OMN-1 Revision 1 by CPNPP permits it to replace stroke time and position verification testing of MOVs with a program of exercising MOVs every refueling cycle and diagnostically testing on longer intervals. This alternative is considered to be acceptable because Code Case OMN-1 Revision 1 provides a superior method than the stroke-timing method required by the OM code for assessing the operational readiness of MOVs. Using the alternative to the MOV stroke time testing requirements of ISTC-5120 and position indication verification of ISTC-3700 provide an acceptable level of quality for determination of valve operational readiness. Code Case OMN-1 Revision 1 should be considered COMANCHE PEAK - UNITS 1 AND 2 A-34 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES acceptable for use with ASME OM Code 2004 Edition through 2006 Addenda as the Code of Record.
- 1) The potential benefits ( such as identification of decreased thrustoutput and increase thrust requirements) and potential adverseeffects (such as accelerated aging or valve damage) will beconsidered when determining the appropriate testing for each MOV.
- 2) Where the selected inservice test frequency extends beyond6 years or 4 refueling outages (whichever is longer),performance and test experience obtained from valve testingconducted during the first 6 year or 4 refueling outage timeperiod shall be evaluated to justify the longer periodicverification frequency.
- 3) The risk insights determined during TU Electric's participationin the Electric Power Research Institute (EPRI) Risk-lnformedlnservice Testing Pilot Project (ref. EPRI TR-105869) and on- going development of an updated risk-informed categorizationprocess based upon ASME Research guidance and Codes asapplicable will be used in accordance with the requirements ofthe ASME OM Code Case OMN-1.
lnservice testing shall be conducted in the "as-found" condition only.
"As-found" referring to: no maintenance activities that may affect the performance of an MOV shall be conducted prior to performing inservice testing. MOV Preventative Maintenance (PM) activities (including stem lubrication) will be performed on time based intervals to ensure the MOV is maintained in optimum working condition. PM activities will be scheduled separately and frequencies determined independently from MOV inservice test requirements. Performance of a MOV PM will not alter an MOVs "as-found" status with regards to performing inservice testing. The effects of PM activities on MOV operational readiness will be assessed to ensure the PM activities do not affect the validity of the MOV inservice test results.
lnservice testing shall be sufficient to assess changes in MOV functional margin. Therefore, MOVs requiring maintenance prior to their scheduled inservice test frequency shall be evaluated to determine whether or not performance of an inservice test prior to the maintenance activity will provide sufficient and/or valuable information in assessing changes in the MOVs functional margin. This. evaluation, as a minimum, shall consider: inservice test frequency, time from last inservice or preservice test, functional margin, maintenance activity to be performed, grouping, MOV history, risk significance, and a review of the last inservice or preservice test performed. In addition, this COMANCHE PEAK - UNITS 1 AND 2 A-35 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED- INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES evaluation shall be documented for future reference. Any OMN-1 Code Case requirements that are not currently included in the CPNPP MOV program will be implemented using a controlled process in accordance with OMN-1 and evaluated under 10 CFR 50.59. CPNPP intends to Maintain the following exceptions to the requirements in ASME Code Case OMN-1 as described below:
- 1) Paragraph 3.3.1, items (a) & (b) The initial inservice testfrequency for each MOV shall be determined based upon theMOV's risk significance category (i.e. High or Low) andmagnitude of margin. See Figure 1 for initial inservice testfrequency details. The inservice test frequency may changewhen sufficient test data has been collected and analyzed todetermine a more appropriate test frequency. No testfrequency shall exceed 10 years.
- 2) Paragraph 6.4.3 - In order to maintain consistency andcompatibility with the Joint Owners Group (JOG) MOV PeriodicVerification Program, "Functional Margin" will be redefined toagree with the definition of "Margin" as detailed in TopicalReport MPR-1807 (Reference 1). The terms "FunctionalMargin" and "Margin" shall be synonymous within the CPNPPMOV Periodic verification program.
Margin", as defined in Reference 1, is dependent upon"Required Thrust." At CPNPP "Required Thrust" for rising stemMOVs has been determined from stem thrust measurementstaken during extensive baseline testing performed in responseto GL 89-10 under both static and dynamic test conditions.Valve factors have been determined by statistical means foreach group of rising stem MOVs; these factors will bereviewed/verified as new data is obtained from CPNPP testingand results are received from the JOG Periodic VerificationProgram." REFERENCES
- 1) Joint BWR, Westinghouse and Combustion Engineering Owners' Group Program onPeriodic Verification on Motor-Operated Valves (MOV) Periodic Verification, TopicalReport MPR-1807, Revision 2, July 1997" COMANCHE PEAK - UNITS 1 AND 2 A-36 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Valve System Number Category Class Description Auxiliary HV-2480 B 3 Aux Feedwater Pump Emergency Supply Feedwater Flowpath HV-2481 B 3 Aux Feedwater Pump Emergency Supply Flowpath HV-2482 B 3 Aux Feedwater Pump Emergency Supply Flowpath HV-2484 B 3 Condensate System to Condensate Storage Tank Isolation to Preclude Tank Overpressurization HV-2485 B 3 Condensate System to Condensate Storage Tank Isolation to Preclude Tank Overpressurization HV-2491A B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2491 B B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2492A B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2492B B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2493A B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2493B B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2494A B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2494B B 2 Containment Isolation & AFW to Faulted SG Flow Isolation Component HV-4512 B 3 Train A to Train B Crosstie Isolation Cooling Water HV-4513 B 3 Train A to Train B Crosstie Isolation COMANCHE PEAK - UNITS 1 AND 2 A-37 Rev.4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Valve System Number Category Class Description HV-4514 B 3 Train A to Train B Crosstie Isolation HV-4515 B 3 Train A to Train B Crosstie Isolation HV-4524 B 3 Non-Safety Loop Flowpath Isolation HV-4525 B 3 Non-Safety Loop Flowpath Isolation HV-4526 B 3 Non-Safety Loop Flowpath Isolation HV-4527 B 3 Non-Safety Loop Flowpath Isolation HV-4572 B 3 RHR Heat Exchanger Cooling Flowpath HV-4573 B 3 RHR Heat Exchanger Cooling Flowpath HV-4574 B 3 Containment Spray Heat Exchanger Cooling Flowpath HV-4575 B 3 Containment Spray Heat Exchanger Cooling Flowpath HV-4696 A 2 Containment Isolation & RCP Thermal Barrier Rupture Isolation HV-4699 B 2 Passive Pipe Break Isolation (Inside Containment) HV-4700 A 2 Containment Isolation & Passive Pipe Break Isolation (Inside Containment) HV-4701 A 2 Containment Isolation HV-4708 A 2 Containment Isolation HV-4709 A 2 Containment Isolation & RCP Thermal Barrier Rupture Isolation Chemical & LCV-0112B B 2 ECCS Flowpath Boundary & Isolation of VCT Volume Cover Gas from Charging Pumps' Suction Control Header (upon low VCT level) & Boron Dilution Flowpath Isolation LCV-0112C B 2 ECCS Flowpath Boundary & Isolation of VCT Cover Gas from Charging Pumps' Suction Header (upon low VCT level) & Boron Dilution Flowpath Isolation COMANCHE PEAK- UNITS 1 AND 2 A-38 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Valve System Number Category Class Description LCV-0112D B 2 ECCS Injection Flowpath & Boration Flowpath/ECCS Recirc Flowpath Boundary LCV-0112E B 2 ECCS Injection Flowpath & Boration Flowpath/ECCS Recirc Flowpath Boundary 8100 A 2 Containment Isolation 8104 B 2 Boration Flowpath 8105 A 2 Boration Flowpath/ECCS Flowpath Boundary
& Containment Isolation 8106 B 2 Boration Flowpath/ECCS Flowpath Boundary 8109 B 2 ECCS Flowpath Boundary 8110 B 2 ECCS Flowpath Boundary 8111 B 2 ECCS Flowpath Boundary 8112 A 2 Containment Isolation 8351A B 2 Containment Isolation 8351B B 2 Containment Isolation 8351C B 2 Containment Isolation 8351D B 2 Containment Isolation 8511A B 2 High Head Safety Injection Pump Miniflow Path/ECCS Recirculation Flowpath Boundary 8511B B 2 High Head Safety Injection Pump Miniflow Path/ECCS Recirculation Flowpath Boundary 8512A B 2 ECCS Recirculation Flowpath Boundary 8512B B 2 ECCS Recirculation Flowpath Boundary Containment LV-4754 B 3 Chemical Additive Flowpath/Chemical Spray Additive Tank Isolation LV-4755 B 3 Chemical Additive Flowpath/Chemical Additive Tank Isolation HV-4758 B 2 Sump Recirculation Flowpath Boundary COMANCHE PEAK - UNITS 1 AND 2 A-39 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Valve System Number Category Class Description HV-4759 B 2 Sump Recirculation Flowpath Boundary FV-4772-1 B 2 Pump Miniflow Flowpath/Containment Spray Flowpath Boundary FV-4772-2 B 2 Pump Miniflow Flowpath/Containment Spray Flowpath Boundary FV-4773-1 B 2 Pump Miniflow Flowpath/Containment Spray Flowpath Boundary FV-4773-2 B 2 Pump Miniflow Flowpath/Containment Spray Flowpath Boundary HV-4776 A 2 Containment Spray Flowpath/Containment Isolation HV-4777 A 2 Containment Spray Flowpath/Containment Isolation HV-4782 B 2 Sump Recirculation Flowpath/Containment Isolation HV-4783 B 2 Sump Recirculation Flowpath/Containment Isolation Reactor 8000A B 1 Post Accident Vent PathNentPath Isolation Coolant & Reactor Coolant Pressure Boundary 8000B B 1 Post Accident Vent PathNent Path Isolation
& Reactor Coolant Pressure Boundary Residual FCV-0610 B 2 Pump Miniflow Path/ECCS & RHR Flowpath Heat Boundary Removal FCV-0611 B 2 Pump Miniflow Path/ECCS & RHR Flowpath Boundary 8701A A 1 RHR Flowpath/Containment Isolation &
Reactor Coolant Pressure Boundary 8701B A 1 RHR Flowpath/Containment Isolation & Reactor Coolant Pressure Boundary 8702A A 1 RHR Flowpath/Reactor Coolant Pressure Boundary COMANCHE PEAK - UNITS 1 AND 2 A-40 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Valve System Number Category Class Description 8702B A 1 RHR Flowpath/Reactor Coolant Pressure Boundary 8716A B 2 ECCS Injection Flowpath/ECCS Recirculation Flowpath Boundary 8716B B 2 ECCS Injection Flowpath/ECCS Recirculation Flowpath Boundary Safety 8801A B 2 ECCS to Cold Legs Flowpath & Boration Injection Flowpath/ Containment Isolation & Passive Pipe Break Isolation 8801B B 2 ECCS to Cold Legs Flowpath & Boration Flowpath/ Containment Isolation & Passive Pipe Break Isolation 8802A B 2 ECCS to Hot Legs Flowpath/ECCS to Cold Legs Flowpath Boundary & Containment Isolation & Passive Pipe Break Isolation 8802B B 2 ECCS to Hot Legs Flowpath/ECCS to Cold Legs Flowpath Boundary & Containment Isolation & Passive Pipe Break Isolation 8804A B 2 ECCS Recirculation Flowpath/Passive Pipe Break Isolation 8804B B 2 ECCS Recirculation Flowpath/Passive Pipe Break Isolation 8806 B 2 ECCS Flowpath Boundary (during Recirculation) 8807A B 2 ECCS Recirculation Flowpath/Passive Pipe Break Isolation 8807B B 2 ECCS Recirculation Flowpath/Passive Pipe Break Isolation 8808A B 2 ECCS from Accumulators to RC Cold Legs 8808B B 2 ECCS from Accumulators to RC Cold Legs 8808C B 2 ECCS from Accumulators to RC Cold Legs 8808D B 2 ECCS from Accumulators to RC Cold Legs COMANCHE PEAK - UNITS 1 AND 2 A-41 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Valve System Number Category Class Description 8809A A 2 ECCS to Cold Legs Flowpath/ECCS to Hot Legs Flowpath Boundary & Passive Pipe Break Isolation & Containment Isolation 8809B A 2 ECCS to Cold Legs Flowpath/ECCS to Hot Legs Flowpath Boundary & Passive Pipe Break Isolation & Containment Isolation 8811A B 2 ECCS Recirculation Flowpath/Containment Isolation & Passive Pipe Break Isolation 8811B B 2 ECCS Recirculation Flowpath/Containment Isolation & Passive Pipe Break Isolation 8812A B 2 ECCS Recirculation Flowpath Boundary & Shutdown Cooling Flowpath Boundary (during Safety Grade Cold Shutdown) 8812B B 2 ECCS Recirculation Flowpath Boundary & Shutdown Cooling Flowpath Boundary (during Safety Grade Cold Shutdown) 8813 B 2 ECCS Recirculation Flowpath Boundary 8814A B 2 ECCS Recirculation Flowpath Boundary 8814B B 2 ECCS Recirculation Flowpath Boundary 8821A B 2 ECCS to Cold Legs Flowpath/ECCS to Hot Legs Flowpath Boundary & Passive Pipe Break Isolation 8821B B 2 ECCS to Cold Legs Flowpath/ECCS to Hot Legs Flowpath Boundary & Passive Pipe Break Isolation 8835 B 2 ECCS to Cold Legs Flowpath/ECCS to Hot Legs Flowpath Boundary & Containment Isolation & Passive Pipe Break Isolation 8840 A 2 ECCS to Hot Legs Flowpath/ECCS to Cold Legs Flowpath Boundary & Containment Isolation & Passive Pipe Break Isolation 8923A B 2 Passive Pipe Break Isolation COMANCHE PEAK - UNITS 1 AND 2 A-42 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Valve System Number Category Class Description 89238 B 2 Passive Pipe Break Isolation 8924 B 2 Passive Pipe Break Isolation Service HV-4286 B 3 Service Water Flowpath/Throttling during Water Pump Start HV-4287 B 3 Service Water Flowpath/Throttling during Pump Start HV-4393 B 3 Service Water Flowpath HV-4394 B 3 Service Water Flowpath HV-4395 B 3 AFW Pump Emergency Supply Flowpath HV-4396 B 3 AFW Pump Emergency Supply Flowpath Containment HV-6082 A 2 Containment Isolation Isolation HV-6083 A 2 Containment Isolation HV-6084 A 2 Containment Isolation HV-40758 A 2 Containment Isolation HV-4075C A 2 Containment Isolation HV-5540 A 2 Containment Isolation HV-5541 A 2 Containment Isolation HV-5542 A 2 Containment Isolation HV-5543 A 2 Containment Isolation HV-5562 A 2 Containment Isolation HV-5563 A 2 Containment Isolation COMANCHE PEAK - UNITS 1 AND 2 A-43 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES LEGEND: Category A = Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required safety function(s). Category B = Valves for which seat leakage in the closed position is inconsequential for fulfillment of their required safety function(s). Class= Code class COMANCHE PEAK - UNITS 1 AND 2 A-44 Rev. 4
CPNPP UNIT 1 & 2 RISK INFORMED - INSERVICE TESTING PLAN APPENDIX A RELIEF REQUESTS FOR PUMPS AND VALVES Figure 1 Initial lnservice Test Frequency MARGIN Low Medium High R I High 1 cycle 2 cycles 3 cycles s K Low 2 cycles 4 cycles 6 cycles*
- Not to exceed 10 years Notes:
- 1. Criteria for MOV Margin Categories Low Margin: <10%
Medium Margin: :2:: 10% and< 15% High Margin: :2:: 15%
- 2. Criteria for Risk Categories High Risk: Risk-Informed 1ST Program Low Risk: Risk-Informed 1ST Program COMANCHE PEAK - UNITS 1 AND 2 A-45 Rev.4
INSERVICE TESTING PLAN FOR PUMPS & VALVES - Description of Changes THIRD INTERVAL REVISION 0: LDCR-IT-2013-004 (EV-CR-2011-009418-12) (JCH): General Editorial Changes: Page Nos: 1-1, 1-3, 2-1, 2-3, 3-1, 3-4 Valve Table Index all pages; Table 2 Page 8 of 8;Table 4 Page 8 of 8; Table 8 Page 7 of 7; Table 13 Page 12 of 13; Table 18 Page 15 of 15; Table 19 Page 20 of 20
Description:
Changed Code Edition and Addenda year from 1998 Edition through 2000Addenda to 2004 Edition through 2006 Addenda. Justification: To comply with 10 CFR 50.55a (f)(4)(i) for the third inservice testing interval, which will be adoption of 2004 Edition through 2006 Addenda. Affected Pages: Cover Page and General
Description:
Added "Third" Interval, Removed "Second" throughout the 1ST Plan, and added the address of CPNPP. Justification: Editorial change for the third interval annotation. Added the address of the facility as required by ASME OM Code Subsection ISTA-9220.
Description:
Added the approval date for the RI-IST and implementation start date. Section 1.3 Added a sentence to indicate the start and end date of the third interval. Section 1.3 Added sentence 'the first interval' for consistency. Page 1-3 added Ref. 10 RI-IST approval letter. Justification: Editorial addition and consistency.
Description:
Removed Para 2.1 and renumbered the paragraphs. Added Para c) to add the skid mounted pumps Justification: Para 2.1 was redundant, the 1ST Plan is in accordance with the ASME OM Code and its Subsections for pumps and valves; Section 1 explains this adequately.
Description:
Added definition of centrifugal vertical line shaft direct coupled pumps Justification: To depict the actual configuration of the safeguards pumps. Refer to AI-CR-2011-009418-2 and AI-CR-2011-009418-3.
Description:
Changed the pump type from C/DC to C/DCNLS Justification: To depict the actual configuration of the safeguards pumps. Refer to AI-CR-2011-009418-2 and AI-CR-2011-009418-3.
Description:
Removed Para 3.1 and renumbered the paragraphs. Added Para e) to reflect that Category A & B safety and relief are excluded from certain testing requirements. CPNPP/IST DOC-1 Revision 4
INSERVICE TESTING PLAN FOR PUMPS & VALVES - Description of Changes LDCR-IT-2013-004 (EV-CR-2011-009418-12) (JCH) (continued): Justification: Previous Para 3.1 was redundant, the 1ST Plan is in accordance with the ASME OM Code and its Subsections for pumps and valves; Section 1 explains this adequately. Category A & B safety and relief are excluded from the testing requirements of stroke and position verification testing. Refer to ISTC-1200, "Exemptions", which excludes Category A & B safety and relief valves.
Description:
Added additional sentence to first paragraph. Justification: Clarification for N/A.
Description:
Added Rev. 1 to NUREG-1482 and included NRC RI-IST approval letter as reference 3. Justification: Editorial and enhancement. Affected Pages: 4, 5, & 15
Description:
For Group 86, valves 851 0A and 851 OB removed footnote 2 and extended the frequency of these valves to 4 years. Removed Note 2 and Note 3, and renumbered the notes in the table accordingly. Justification: Note 2 was a commitment to in response to NRC IN-92-61, this commitment (CDF # 26357) was closed using STA-509, "Commitment Management Program", and a CMCE # 4636255 was issued and was approved to remove the commitment identified in Note 2. Also refer to EV-CR-2013-004411-3. Note 3 did not correspond to any items in the Table.
Description:
Removed measured stroke time testing (MT) and position indication verification (PIT) was removed from certain valves as marked. Justification: Comanche Peak Relief request has been reviewed and approved by the NRC to adopt the OMN-1 Rev 1. This relief request eliminates MT and PIT; refer to NRC SER TAC Nos. ME9503 and ME9504 for both units.
Description:
Removed old relief request V-8 and inserted V-1 in its place. Justification: Comanche Peak Relief request has been reviewed and approved by the NRC to adopt the OMN-1 Rev 1. This relief request eliminates MT and PIT; refer to NRC SER TAC Nos. ME9503 and ME9504 for both units. Therefore, V-8 is not applicable anymore.
Description:
Removed old Relief Request P-2 and inserted P-1 in its place. Justification: Comanche Peak Relief Request has been reviewed and approved by the NRC on June 26, 2013. It is approved for the third ten year 1ST program interval; reference safety evaluattion dated June 26, 2013 for Units 1 & 2, TAC NOS. ME9259 and ME9260 [ML13050A183]. This relief request supersedes old relief request P-1. CPNPP/IST DOC-2 Revision 4
INSERVICE TESTING PLAN FOR PUMPS & VALVES- Description of Changes LDCR-IT-2013-003 (EV-CR-2012-002342-1) (JCH):
Description:
Table 5, "Containment Spray", Add "(3)" under Leak Test for CT-0142/0145 in Group 28 on Page 1 of 4. Add Note 3 to Page 4: "3. This valve has a water filled loop seal and is not required to be leakrate tested (see DBD-ME-013, rev. 22, Attachment 1, Note 3)." Justification: Valves CT-0142/0145 have water seals and are exempt from Appendix J leak testing. Per DBD-ME-013,Attachment 1, Note 3, "These valves are part of closed systems outside containment tested per NUREG-0737 Section II1.D.1 which are in service post-accident and have a water filled loop seal on the containment side of the valves. These valves are either open or closed providing a third barrier to containment leakage. A water seal is maintained both inside and outside containment. These valves are therefore not required to be leakrate tested.
Description:
Table 19, "Motor Operated Valves", Add "(2)" under Leak Test for HV-4776 on Page 8, HV-4777 on Page 9, 8809A on Page 13, 8809B on Page 14, 8840 on page 15 Add Note 2 to Page 20: 2. "This valve has a water filled loop seal and is not required to be leakrate tested (see DBD-ME-013, rev. 22, Attachment 1, Note 3)." Justification: Valves HV-4776/4777/8809A/8809B/8840 have water seals and are exempt from Appendix J leak testing. Per DBD-ME-013,Attachment 1, Note 3, "These valves are part of closed systems outside containment tested per NUREG-0737 Section II1.D.1 which are in service post-accident and have a water filled loop seal on the containment side of the valves. These valves are either open or closed providing a third barrier to containment leakage. A water seal is maintained both inside and outside containment. These valves are therefore not required to be leakrate tested. LDCR-IT-2012-001 (EV-CR-2010-004331-60) (JCH): Table 19 - Motor Operated Valves
Description:
add the following valve to Table 19: 1-HV-8402A under "Chemical and Volume Control-High Safety Significance" Under "Gate Valve/Motor Operated Westinghouse with Limitorque Actuator":
-Change 2-HV-8402A to HV-8402A - Add Flow Diagram- M1-0255(B-1)
CPNPP/IST DOC-3 Revision 4
INSERVICE TESTING PLAN FOR PUMPS & VALVES- Description of Changes LDCR-IT-2012-001 (EV-CR-2010-004331-60) (JCH) (continued): Justification: The new 3-inch motor operated valve is classified as Nuclear Safety Class 2. The control switch will be used to isolate and bypass 1-HCV-0182 during maintenance and in case of a fire to ensure that the normal charging path is isolated. Replacement of this manual operated valve with a motor operated gate valve will maintain all design and operational functions of the existing valve. This includes the requirement that the valve is a "PASSIVE" open valve. Since the function to close during a fire is important to safety, 1-HV-8402A will be exercise open and closed and position indicated tested. LDCR-IT-2013-002 (EV-CR-2012-003165-4) (JCH):
Description:
Change the function from "P" to "A" for the following valves in Table 18, Group 91: DO-011, DO-0187, DO-0211, DO-0287 Justification: These valves are required to protect diesel fuel oil transfer pumps when backpressure from the "Y" strainers requires it. Since this could happen during the Emergency Diesel Generator mission time (30 Days) and no credit had been taken for online maintenance or operator action to protect the pumps, these valves must be classifed as ACTIVE to perform their function as described in the FSAR. THIRD INTERVAL REVISION 1: LDCR-IT-2013-005 (EV-CR-2011-009418-17) (JCH): Table 19- Motor Operated Valves VALVE TABLE INDEX (VTI)
Description:
Diagnostic Testing column under Test Parameters/Schedule. The Valve Table Index defines diagnostic testing as follows: OT-Diagnostic testing determines the cause or mechanism associated with failure, degradation, or performance anomaly of a motor operated valve per the requirements of OMN-1 Rev. 1 (Relief Request V-1) Justification: Code Case OMN-1 allows users to replace MOV stroke-time testing with a combination of MOV exercising at least every refueling outage and MON diagnostic testing on a longer interval. Table 19 is being enhanced to include an additional column which will identify those MOVs which are required to be "diagnostic" tested. CPNPP/IST DOC-4 Revision 4
INSERVICE TESTING PLAN FOR PUMPS & VALVES- Description of Changes LDCR-IT-2013-005 (EV-CR-2011-009418-17) (JCH) (continued): VALVE TABLE INDEX (VTI)
Description:
add the following under Exercise Test: OT-Diagnostic testing determines the cause or mechanism associated with failure, degradation, or performance anomaly of a motor operated valve per the requirements of OMN-1 Rev. 1 (Relief Request V-1) Justification: Code Case OMN-1 allows users to replace MOV stroke-tiem testing with a combination of MOV exercising at least every refueling outage and MON diagnostic testing on a longer interval THIRD INTERVAL REVISION 2: LDCR-IT-2014-001 (EV-CR-2012-011620-15) (JCH): Referenced Section: Table 13, Safety Injection Description of Change: This activity replaces the Unit 2 Safety Injection (SI) to Cold Leg (CL) 2-01 piston check valve (2Sl-8819A) with a 2" Enertech nozzle check valve. Technical Justification: The nozzle check valve is a ASME Section 111 Class 1513 valve with a pressure rating of 3632 psig at 100F and a design rating of 2485 psig at 650F per drawing MD22754 Revision E (VDRT-3902424). This meets the requirements of 2323-MS-43B Category 2501 component. For flow characteristics, Westinghouse reviewed the new valve and the old valve and concluded the flow changes are insiginificant and acceptable; the Westinghouse conclusions regarding 2Sl-8819A are documented in WPT-17762. The replacement valve is designed and manufactured in accordance with the requirements of ASME B&PV Code Section 111, Class 1, 1974 Edition through winter 1975 Summer Addenda LDCR-IT-2014-003 (EV-CR-2014-005580-7) (JCH): Table 1-Auxiliary Feedwater
Description:
Change frequency for the following valves for dual direction testing (DD) from "3MO" to "RF"- AF-0014, AF-0024, AF-0032, AF-0038, AF-0051, AF-0065 Justification: Reverse flow testing (dual direction) is not practical at power operations. Such testing would unacceptably increase plant risk due to system unavailability. The Code of Record allows performance of this testing during plant refueling. CPNPP/IST DOC-5 Revision 4
INSERVICE TESTING PLAN FOR PUMPS & VALVES - Description of Changes LDCR-IT-2014-003 (EV-CR-2014-005580-7) (JCH) (continued):
Description:
Add Note 4 to end of Table 1:
"AF-0014, AF-0024, AF-0032, AFW Pump suction valves and AF-0065, AF-0051, AF-0038, AFW Pump discharge check valves are reverse flow (closed) tested at refueling.
These valves are not reverse flow tested during plant operation because such testing would unacceptably increase plant risk due to system unavailability." Justification: Note 4 provides clarification for reverse flow testing during plant refueling outages. Table 18-SAFETY & RELIEF VALVES
Description:
Page 5-Change Flow Diagram number for 2CH-0281 and 2CH-0282 from "M1-0307" to "M2-0307" Justification: The following corrections are needed to correct typos for the drawing numbers These are Unit 2 valves and the drawing numbers should start as M2 and not M1.
Description:
Table 13- Page 8: Change 8825 Category from "A" to "8" Table 13-Page 8: Change 8890A and 88908 from "A" to "8" Table 19-Page 8: Change HV-4776 from "A" to "8" Table 19-Page 9: Change HV-4777 from "A" to "8" Table 19-Page 13: Change 8809A from "A" to "8" Table 19-Page 14: Change 88098 from "A" to "8" Table 19-Page 15: Change 8840 from "A" to "8" Justification: The affected valves were listed as Category A valves; they should be listed as Category 8, because they do not require leak testing criteria. CPNPP/IST DOC-6 Revision 4
INSERVICE TESTING PLAN FOR PUMPS & VALVES - Description of Changes THIRD INTERVAL REVISION 3: LDCR-IT-2019-001 (EV-TR-2018-000922-18) (GWS): Document use of Code Case OMN-16 Rev. 1. Update Risk Rank in accordance with EREA-010 R5. Revise Test Parameters/Schedule per Relief Request A-1 RO and V-1 RO. Add Relief Request T-1. Revision changed Pump Test Table and System Tables 1 (AFW), 2 (CCW), 4 (CVCS), 8 (FW), 13 (SI), 14 (SW), 16 (VD), 17 (Misc. CIVs), 18 (Safeties & Reliefs), and 19 (MOVs). THIRD INTERVAL REVISION 4: LDCR-IT-2019-002 (EV-CR-2015-011094-8) (GWS): 1ST Plan Table 13 Safety Injection Update. LDCR-IT-2020-001 (EV-TR-2019-008291-12) (GWS): As allowed by ISTC-5220, implementation of a Check Valve Condition Monitoring Program in accordance with ASME OM Code Mandatory Appendix II. LDCR-IT-2020-002 (EV-TR-2020-002118-23) (GWS): Change maximum diagnostic test interval for LSSC Motor Operated Valves from 6 years to 10 years. LDCR-IT-2021-001 (EV-TR-2019-001528-8) (GWS): Remove Group 39 and all associated valve and test information due to replacing DG Starting Air Compressors per FDA-2017-000092-01. CPNPP/IST DOC-7 Revision 4}}