ML20085M008
| ML20085M008 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/15/1995 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20085M006 | List: |
| References | |
| PROC-950615, NUDOCS 9506280797 | |
| Download: ML20085M008 (168) | |
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i OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1~
l INSERVICE INSPECTION PROGRAM PLAN I
FOR THE 1993-2003 INTERVAL l
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1 9506280797 950621 I
PDR ADOCK 050002B5
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PDFi R2 June 15, 1995 Page 1 of 168 i
PROGRAM TABLE OF CONTENTS Page INTRODUCTION 5
PART 1:
Class 1, Class 2, and Class 3 Pressure Retaining Components..
6 Program 1.0 Program Summary.....................
6 2.0 Scope and Responsibility 6
3.0 Inspection Intervals 7
4.0 Examination Categories 7
5.0 Examination Methods................... 8 6.0 Evaluation of Examination Results............ 8 7.0 Repair Requireunts................... 8 8.0 System Pressure Testing.................
9 9.0 Records and Reports..................
10 Tables Table 1.1 Components, Parts, and Methods of Examination IWB-2500-1
...................12 Table 1.2 Components, Parts, and Methods of Examination IWC-2500-1
...................16 Table 1.3 Components, Parts, and Methods of Examination IWD-2500-1 18 Table 1.4 Components, Parts, and Methods of Examination IWF-2500-1
...................19 Appendices Appendix 1A Exceptions to Compliance with Subsection IWA..
21 Appendix 1B Exceptions to Compliance with Table IWB-2500-1 22 Appendix IC Exceptions to Compliance with Table IWC-2500-1 23 Appendix 1D Exceptions to Compliance with Table IWD-2500-1 24 Summary Tables Table 1A..........................
26 Table IB..........................
27 Table IC 35 Table ID 39 i
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PROGRAM TABLE OF CONTENTS (Continued)'
1 Page
.l PART 2:
Class 1, Class 2, and Class 3 Valve Tests...........u40 Program 1.0 Program Summary....................-. 40 2.0 Scope and Responsibility
...............40 3.0 Inservice Test Frequency...............
41 4.0 Valve Categories
...................41.
l 5.0 Test Methods......................
41 6.0 Evaluation of Test Results
..............42
.i 7.0 Records and Reports..................
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8.0 Repair Requirements..................
43 9.0 Valve Test-Program Matrix...............
43 10.0 Additions to Program - Valves.............
43 1
Tables Table Format Fort Calhoun Station Valve Test Program Matrix.
44' Table 2.1 Valve Test Program Matrix.............
50 Appendices Appendix 2A Justification for Test Frequencies Other than' Code Preferred....................
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Appendix 28 Justification for Exception to ASME Section XI/0&M Manual Parts l'and 10, Codes for Valves.....
131 PART 3:
Class 1, Class 2, and Class 3 Pump Tests 150 Program 1.0 Program Summary....................
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2.0 Scope and Responsibility 150 3.0 Inservice Test Frequency...............
150 4.0 Test Methods 150 5.0 Evaluation of Test Results 150 6.0 Records and Reports..................
151 7.0 Repair Requirements..................
151 8.0 Function of Pumps in the Program 151 9.0 Pump Test Program Table (Table 3.1)..........
152 10.0 Additions to Program - Pumps 153 t
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.3 PROGRAN TABLE OF CONTENTS (Continued).
l Page-Pump Tables Table Format Fort Calhoun Station Pump _ Test Program Matrix 155 Pump. Test Program Table 3.1.................
156 Appendix i
i Appendix 3A Justification for Exception to ASME O&M Manual Part.6 for Pumps 157 167 PART 4:
References I
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INTRODUCTION This report defines the Fort Calhoun Station Inservice Inspection (ISI)
Program Plan for Class 1, Class 2, and Class 3 pressure retaining components for-the ten year (120 month) interval from September 26, 1993, to September 25, 2003. This report also covers Class 1, Class 2, and Class 3 pump and valve Inservice Testing (IST) for the-ten year (120 month) interval from September 26, 1993, to September 25, 2003.
This program has been developed as required by Section 50.55a of 10CFR Part 50 following the guidance of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code Section XI (hereinafter called Section XI),
" Rules for Inservice Inspection of Nuclear Power Plant Components", and the ASME/ ANSI Operation and Maintenance of Nuclear Power Plants manual (hereinafter called 0&M Manual) Parts 1, 6, and 10, and the NRC Generic Letter 89-04, dated April 3, 1989.
The ISI Program Plan is controlled by the Fort Calhoun Station Unit 1 Technical Specifications 3.3.(1)a.
This program is in compliance, where possible, with the applicable requirements of ASME Section XI, 1989 Edition (Program B) and the ASME/ ANSI 0&M Manual Parts 1, 6, and 10, 1987 Edition, 1988 Addenda, except as noted below:
The 0&M Manual, Part 6, 1987 Edition and 1988 Addenda have omitted the Figure 1 referred to on Table 3, Note 2 for vibration ranges.
OPPD will use the Table 3 as listed in the 1989 addenda of the 0&M Manual, Part 6 for vibration ranges for test parameters.
This program incorporates the results of previous inservice and preservice inspections.
It is the intent of the Licensee (0maha Public Power District) to continue to review and apply, as appropriate, changes in the ASME Section XI Code that would improve the total ISI Program Plan, pursuant to 10CFR50.55a.
Revision 1 of this program plan incorporates changes to the ISI Program (Part
- 1) as requested by the NRC.
Revision 2 of this program plan incorporates resolutions to the NRC Safety Evaluation Report (SER) anomalies identified in Part 4, Reference 7 of this program plan as well as typographical errors and changes due to Engineering ChangeNotices(ECNs)/ Modifications (Mods)atFCS.
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f-o PART 1:
CLASS 1, CLASS 2,-AND CLASS 3 PRESSURE RETAINING CONPONENTS 1.0 Program Susumary 1.1 The Inservice Inspection (ISI) Program for Class 1, 2, and 3 l
pressure retaining components was developed in accordance with, and meets the requirements of, the ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition.
The ISI Program for Class l', 2, and 3 pressure retaining components will remain in effect for'the remainder of the ten year (120 month) interval, which commences on September 26, 1993. The Program will be reviewed and updated as required by the edition of the Code and Addenda in effect not more than-12 months prior to the start of the next (i.e., fourth) 120; month interval (beginning September 26,2003).
2.0 Scope and Responsibility 2.1 The Piping and Instrumentation Drawings (P& ids) for Fort Calhoun-Station (FCS)identifytheclassboundaries. These P& ids are subject to review and are changed as required in accordance with FCS administrative procedures.
2.2 Class 1, Class 2, and Class 3 components and the methods of examination for each component are listed in Tables 1.1, 1.2, and 1.3, respectively.
The total number of Class 1, 2, and 3 components and supports required by ASME Section XI 1989 Edition, no Addenda, are listed by category in Tables 18, IC, and ID respectively. The required number of-exams per category per forty (40) month period are also shown, as well as a proposed exam schedule per category per forty (40) month period. The specific components to be examined for each class shall be identified in the Fort Calhoun Station Unit 1 Ten Year Inservice Examination Plan by title and/or number.
Exceptions to compliance with Subsection IWA, Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1 of Section XI are listed in Appendices IA, 1B, 1C, and ID, respectively.
Class 3 portions of the Waste Disposal System have been classified as Class 3 in accordance with SubarticleIWA-1320, Paragraph (e)ofSectionXI.
Examination in accordance with the rules of Subsection IWD will not be performed on the Class 3 portion of the Waste Disposal System.
(Although the Waste Disposal System at FCS is classified Class 3, it is not considered safety related as required for inspection per IWD-2500.)
i 2.3 Class 1, Class 2, and Class 3 component supports and the methods of examination for each support are listed in Table 1.4.
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2.4 Steam Generator, safety-related snubbers, metallic liners (of Class CC), containment s examinations (Class CC) pray nozzles and the concrete component are not performed under this ISI Program Plan, but are performed as described below:
2.4.1 Steam Generator exams are performed under FCS Technical Specification 3.17.
2.4.2 Snubber exams are performed under FCS Technical Specification 3.14 and OM Code ISTD 1990, 1992 Addenda.
Reference NRC letter dated April 6, 1995 (NRC 95-071).
2.4.3 Metallic liner exams (of Class CC) are not required at the time of this submittal per 10CFR50.
2.4.4 Concrete component exams are performed under FCS Technical Specification 3.5.
2.5 The containment spray nozzles are tested under FCS Technical Specification 3.6.
3.0 Inspection Intervals 3.1 The inspection intervals for Class 1, Class 2, and Class 3 components are ten year (120 month) intervals of service which commenced on September 26, 1973. This program plan covers the third ten year interval, i.e. September 26, 1993 to September 25, 2003.
The ten year Inservice Examination Plan describes the distribution of examinations within the inspection intervals in accordance with IWB-2400, IWC-2400, IWD-2400 and IWF-2400 of Section XI.
3.2 The inspection intervals and periods may be extended by as much as one year to permit inspections to be concurrent with plant outages as permitted by IWA-2430(d) of Section XI.
3.3 Selection of Class 1 pressure retaining piping welds for examination shall be in accordance with the requirements of the 1974 Edition of Section XI, Summer of 1975 Addenda. [As permitted by10CFR50.55a(b)(2)(ii)]
4.0 Examination Categories 4.1 Class I components, as described in the ten-year examination plan, I
will be examined to the extent and frequency required by) Table IWB-2500-1 of Section XI (except as noted in Appendix 18.
i 4.2 Class 2 components as described in the ten-year examination plan will be examined to the extent and frequency required by) Table i
IWC-2500-1 of Section XI (except as noted in Appendix IC.
4.3 Class 3 components, as described in the ten year examination plan, shall be examined to the extent and frequency as required by Table R2 June 15, 1995 Page 7 of 168
IWD-2500-1 of Section XI (except as noted in Appendix 1D).
5.0 Examination Methods 5.1 Class 1 and Class 2 components shall be examined by the required visual, surface, and volumetric examination methods.. These examinations shall include one or a combination of the following methods:
visual (VT), liquid penetrant (PT), magnetic particle (MT), radiographic (RT), and ultrasonic (UT). Ultrasonic ^(UT) examinations shall be performed in.accordance with the following:
5.1.1 When listing calibration blocks on piping reports, the block thickness shall be within 125% of-the pipe wall thickness examined per the rules of Code Case N-461.
5.1.2 The reactor coolant pumps (RCP) shall be' examined per the rules of ASME Code Cases N-481 and N-498-1.
5.2 Class 3 components shall be visually examined for leakage in accordance with Article IWD-2500 of Section XI.
6.0 Evaluation of Examination Results 6.1 Class 1 Components The evaluation of the nondestructive examination results shall be in accordance with Article IWB-3000 of Section XI.
All indications shall be subject to comparison with previous data to help in characterization and in determining origin.
6.2 Class 2 Components The evaluation of nondestructive examination results shall be in accordance with Article IWC-3000 of Section'XI.
All indications shall be subject to comparison with previous data to help in characterization and in determining origin.
6.3 Class 3 Components The evaluation of the nondestructive examination results shall be in accordance with Article IWD-3000 of Section XI.
All indications shall be subject to comparison with previous t
data to help in characterization and in determining origin.
6.4 Indications which have been recorded in the preservice inspection or in a previous inservice inspection which are not characterized as propagating flaws shall be considered acceptable for continued service.
7.0 Repair Requirements 7.1 Repair of Class 1, Class 2, and Class 3 components shall be performed in accordance with Article IWA-4000 of Section XI.
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7.2 Surface defects in Class I and Class 2 pressure retaining components may be removed by mechanical means when the removal of a defect will not alter the basic configurations of the item.
Pressure retaining components that have defects that cannot be removed by mechanical means will be replaced in accordance with Article IWA-7000 of Section XI, or monitored for further growth per IWB-2420 or IWC-2420.
8.0 System Pressure Testing 8.1 General Requirements 8.1.1 System pressure tests will be conducted in accordance with Article IWA-5000 of Section XI and ASME Code Case N-498.
8.1.2 Evaluation of any corroded area will be performed in accordance with Section XI.
8.1.3 Repairs of corroded areas shall be performed in accordance with Section 7 of this Program.
8.2 Class 1 Components 8.2.1 After each Refueling Outage, the system will be leak tested in accordance with Article IWB-5000 of Section XI and in accordance with FCS Technical Specification 2.1 (Figures 2-1A and 2-1B).
8.2.2 The ten year hydrostatic tests for ASME Class 1 systems will not be performed in the ISI Program.
In lieu of the hydrostatic tests required by ASME Section XI, alternative testing consisting of system pressure and leakage tests as described in ASME Code Case N-498-1 will be performed.
Refer to ASME Code Case N-498-1, dated May 11, 1994, and NRC letter dated January 30, 1995 (NRC-95-017).
8.2.3 Partial penetration welds on the reactor vessel and the pressurizer shall be examined in accordance with Table IWB-2500 Examination Category B-E of Section XI.
8.3 Class 2 Components 8.3.1 Pressure tests and visual examination of Class 2 components will be performed in accordance with the guidelines of Table IWC-2500 of Section XI.
8.3.2 The ten year hydrostatic tests for ASME Class 2 systems will not be performed in the ISI Program.
In lieu of the hydrostatic tests required by Section XI, alternative testing consisting of system pressure and leakage tests as described in ASME Code Case N-498-1, will be performed.
Refer to ASME Code Case N-498-1, dated May 11, 1994, and NRC letter dated January 30,1995(NRC-95-017).
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8.3.3 System leakage tests will be used in lieu of required hydrostatic tests for repairs / replacements of Class 2 components / piping at the discretion of the ISI Coordinator and ANII in accordance with ASME Code Case N-416.
The required hydrostatic tests will be performed at the next regularly scheduled Refueling Outage.
8.4 Class 3 Components 8.4.1 Pressure tests and visual examination of Class.3 components will be performed in accordance with the guidelines of Table IWD-2500 of Section XI.
8.4.2 The ten year hydrostatic tests for ASME Class 3 systems will not be performed in the ISI Program.
In lieu of the hydrostatic tests required by Section XI, alternative testing consisting of system pressure and leakage tests as described in ASME Code Case N-498-1, will be performed.
Refer to ASME Code Case N-498-1, dated May 11, 1994, and NRC letter dated January 30,1995(NRC-95-017).
9.0 Records and Reports Records and reports maue in accordance with this program shall be developed and maintained in accordance with Article IWA-6000 of Section XI.
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l TABLE 1.1 COMPONENTS, PARTS, AND METHODS OF EXAMINATION IWB-2500-1 EXAMINATION ITEM CATEGORY TABLE COMPONENTS AND PARTS NO.
IWB-2500-1 TO BE EXAMINED METHOD REACTOR VESSEL 81.10 B-A Longitudinal and circumferential shell Volumetric welds Bl.20 B-A Circumferential and meridional head Volumetric welds (accessible length)
B1.30 B-A Shell-to-flange welds Volumetric Bl.40 B-A Head-to-flange weld Volumetric &
Surface 83.90 B-D Nozzle-to-vessel welds Volumetric B3.100 B-D Nozzle inside radius section Volumetric B4.10 B-E Partial penetration welds, including Visual, VT-2 vessel nozzles, control rod drive nozzles & instrumentation nozzles 85.10 B-F Nozzle-to-safe end butt welds NPS 4 or Volumetric &
larger Surface B6.10 B-G-1 Closure head nuts Surface 86.30 B-G-1 Closure studs, when removed Volumetric &
l Surface B6.40 B-G-1 Threads in flange Volumetric B6.50 B-G-1 Closure washers Visual, VT-1 B7.80 B-G-2 Bolts, studs & nut <2 in. diameter in Visual, VT-1 CRD housing B13.10 B-N-1 Vessel interior Visual, VT-3 B13.50 B-N-2 Interior attachments within beltline Visual, VT-1 region B13.60 B-N-2 Interior attachments beyond beltline Visual, VT-3 region B13.70 B-N-3 Core support structure Visual, VT-3 814.10 B-0 Pressure retaining welds in Control rod Surface or drive housings Volumetric B15.10 B-P Pressure retaining boundary Visual, VT-2 B15.11 B-P Pressure retaining boundary Visual, VT-2 R2 June 15, 1995 Page 12 of 168
l TABLE 1.1(Continued)
' COMPONENTS, PARTS, AND METHODS OF EXAMINATION IWB-2500-1 EXAMINATION-ITEM-CATEGORY TABLE COMPONENTS AND PARTS t
NO.
IWB-2500-1 TO BE EXAMINED METHOD-Pressurizer 82.10 B-B Longitudinal and circumferential Volumetric shell-to-head welds B3.110 B-D Nozzle-to-vessel welds Volumetric 4
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-2 B5.40 B-F Nozzle-to-safe end welds NPS 4 or larger Volumetric &
Surface B5.50 B-F Nozzle-to-safe end NPS less than 4 Surface 87.20 B-G-2 Bolts, studs and nuts 52 in. diameter Visual, VT-1 B10.10 B-K-1 Integrally welded attachments Surface or Volumetric B15.20 B-P Pressure retaining boundary Visual, VT-2 B15.21 B-P oressure retaining boundary Visual, VT-2 Steam Generators (Primary Side)
B2.30 B-B Head welds, circumferential and Volumetric i
meridional B2.40 B-B Tubesheet-to-head weld Volumetric B3.130 B-D Nozzle-to-vessel welds Volumetric B3.140 B-D Nozzle inside radius section Volumetric B5.70 B-F Nozzle-to-safe end welds NPS 4 or larger Volumetric &
1 Surface B7.30 B-G-2 Bolts, studs, and nuts 52 in. diameter Visual, VT-1 810.10 B-K-1 Integrally welded attachments Surface or Volumetric B15.30 B-P Pressure retaining boundary Visual, VT-2 i
I B15.31 B-P Pressure retaining boundary Visual, VT-2 Heat Exchanaer 82.50 B-B Head welds, circumferential and Volumetric meridional R2 June 15, 1995 Page 13 of 168
i TABLE 1.1 (Continued)
COMPONENTS, PARTS, AND METHODS OF EXAMINATION IWB-2500-1 j
EXAMINATION J
ITEM CATEGORY TABLE COMPONENTS AND PARTS NO.
IWB-2500-1 TO BE EXAMINED METHOD Heat Exchanaer (Continued)
B2.70 B-B Longitudinal welds Volumetric B2.80 B-B Tubesheet-to-shell welds Volumetric B3.150 B-D Nozzle-to-vessel welds Volumetric B3.160*
B-D Nozzle inside radius section Volumetric B15.40 B-P Pressure retaining boundary Visual, VT-2 B15.41 B-P Pressure retaining boundary Visual, VT-2 Pipina Pressure Boundary B5.130 B-F NPS 4 or larger dissimilar metal butt Surface &
welds Volumetric B5.140 B-F Less than NPS 4 dissimilar metal butt Surface welds B7.50 B-G-2 Bolts, studs and nuts <2 in diameter Visual, VT-1 89.10 B-J Circumferential welds & longitudinal Surface &
welds NPS 4 or larger Volumetric 89.20 B-J Circumferential & longitudinal welds Surface less than NPS 4 B9.31 B-J Branch pipe connection welds nominal Surface &
pipe size NPS 4 or larger Volumetric B9.32 B-J Branch pipe connection welds nominal Surface pipe size less than NPS 4 b?.40 B-J Socket welds Surface B10.'0 B-K-1 Integrally welded attachments Surface or Volumetric B15.50 B-P Pressure retaining boundary Visual, VT-2 815.51 B-P Pressure retaining boundary Visual, VT-2 Pump Pressure Boundary B6.180 B-G-1 Bolts and studs >2 in. diameter Volumetric
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TABLE 1.1(Continued)
COMPONENTS, PARTS, AND METHODS OF EXAMIWATION IWB-2500-1
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EXAMINATION ITEM CATEGORY TABLE COMPONENTS AND PARTS NO.
IWB-2500-1 TO BE EXAMINED METHOD l
Pump Pressure Boundary (Continued) 86.190 B-G-1 Flange surface when disassembled (with Visual, VT-1
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>2 in. bolting or studs)
B6.200 B-G-1 Nuts, bushings, and washers >2 in.
Visual, VT-1 B7.60 B-G-2 Bolts, studs, and nuts 52 in.
Visual, VT-1 t
B10.30 B-K-1 Integrally welded attachments Surface or 4
Volumetric B12.10 B-L-1 Pump casing welds
- Visual, VT-1 B12.20 B-L-2 Pump casings Visual, VT-3 B15.60 B-P Pressure retaining boundary Visual, VT-2 f
B15.61 B-P Pressure retaining boundary Visual, VT-2 Valve Pressure Boundary B7.70 B-G-2 Bolts, studs, and nuts 52 in diameter Visual, VT-1 B12.30 B-M-1 Valve body welds less than NPS 4 Surface B12.40 B-M-1 Valve body welds NPS 4 or larger Volumetric l
B12.50 B-M-2 Valve body exceeding NPS 4 Visual, VT-3 B15.70 B-P Pressure retaining boundary Visual, VT-2 815.71 B-P Pressure retaining boundary Visual, VT-2
- Per Code Case N-481 i
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TABLE 1.2 COMPONENTS, PARTS, AND METHODS OF EXAMINATION IWC-2500-1 EXAMINATION ITEM CATEGORY TABLE COMPONENTS AND PARTS l
NO.
IWC-2500-1 TO BE-EXAMINED METHOD L
Pressure Vessels C1.10 C-A Shell circumferential welds Volumetric C1.20 C-A Head circumferential welds Volumetric C1.30 C-A Tubesheet-to-shell weld Volumetric l
C2.21 C-B Nozzle-to-shell(orhead)weldin Surface &
L vessels >
in. nominal thickness without Volumetric j
reinforcing plate C2.22 C-B Nozzle inside radius in vessels >
in.
Volumetric nominal thickness without reinforcing plate C7.10 C-H Pressure retaining boundary Visual, VT-2 C7.20 C-H Pressure retaining boundary Visual, VT-2 All Pipino C3.10 C-C Vessels) y welded attachments (Pressure Integrall Surface C3.20 C-C Integrally welded attachments (Piping)
Surface j
C7.30 C-H Pressure retaining boundary Visual, VT-2' C7.40 C-H Pressure retaining boundary Visual, VT-2 l
Austenitic Stainless Steel or Hiah Allov Pipina l
C5.10 C-F-1 Circumferential & longitudinal welds >Jii Surface &
in. nominal wall thickness for piping Volumetric
> NPS 4
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C5.20 C-F-1 Circumferential & longitudinal welds Surface &
>1/5 in nominal wall thickness for Volumetric piping > NPS 2 and < NPS 4 C5.30 C-F-1 Socket welds Surface C5.40 C-F-1 Circumferential & longitudinal welds in Surface pipe branch connections of branch piping
__ NPS 2 l
C5.50 C-F-2 Circumferential & longitudinal welds >%
Surface &
in, nominal wall thickness for piping >
Volumetric NPS 4 i
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2 TABLE 1.2 (Continued) t COMPONENTS, PARTS, AND METHODS OF EXAMINATION IWC-2500-1 i
EXAMINATION ITEM CATEGORY TABLE COMPONENTS AND PARTS NO.
IWC-2500-1 TO BE EXAMINED METHOD Austenitic Stainless Steel or High Allor Pipina (Continued)
C5.60 C-F-2 Circumferential & longitudinal welds.
Surface &
>1/5 in. nominal wall thickness for Volumetric l
piping > NPS 2 and < NPS 4 C5.70 C-F-2 Socket welds Sarface C5.80*
C-F-2 Circumferential and longitudinal welds Surface in pipe branch connections of branch piping > NPS 2 Pumps l
C6.10 C-G Pump casing welds Surface C7.50 C-H Pressure retaining components Visual, VT-2 f
C7.60 C-H Pressure retaining components Visual, VT-2 j
Valves l
C6.20 C-G Valve body welds Surface l
C7.70 C-H Pressure retaining components Visual, VT-2 f
C7.80 C-H Pressure retaining components Visual, VT-2
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TABLE 1.3.
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COMPONENTS, PARTS, AND METHODS OF EXAMINATION IWD-2500-1 l
EXAMINATION ITEM CATEGORY TABLE COMPONENTS AND PARTS NO.
IWD-2500-1 TO BE EXAMINED METHOD D1.10 D-A Pressure retaining components Visual, VT-2 01.20 0-A Integral attachment, component supports Visual, VT-3 and restraints D1.30 D-A Integral attachment, mechanical and Visual, VT-3 hydraulic snubbers D1.40 D-A Integral attachment, spring type Visual, VT-3 supports D1.50 0-A Integral attachment, constant load type Visual, VT-3 supports D1.60 0-A Integral attachment, shock absorbers Visual, VT-3 1
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TABLE 1.4 COMPONENTS, PARTS, AND METHODS OF EXAMINATION IWF-2500 CODE CASE N-491 ALTERNATIVE RULES FOP, EXAMINATION OF CLASS 1, 2, 3 AND METAL CONTAINMENT COMPONENT SUPPORTS OF LIGHT-WATER COOLED POWER PLANTS EXAMINATION ITEM CATEGORY TABLE NO.
IWF-2500 SUPPORT TYPE EXAMINED METHOD
.F1.10 F-A Class 1 piping supports Visual, VT-3 F1.20 F-A Class 2 piping supports Visual, VT F1.30 F-A Class 3 piping supports Visual, VT-3 F1.40 F-A Supports other than piping supports Visual, VT-3 (Class 1,2,3andMC) l R2 June 15, 1995 Page 19 of'168
PART1 APPENDICES R2 June 15, 1995 Page 20 of 168
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'I APPENDIX 1A.
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EXCEPTIONS TO COMPLIANCE WITH SUBSECTION IWA p
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- Section Exception
' IWA-2600 Weld identifications will be marked at the time the weld is examined 1
per Station Engineering Instruction SEI-27.
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APPENDIX IB EXCEPTIONS TO COMPLIANCE WITH TABLE IWB-2500-1 (CLASS 1 COMPONENTS) IN ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI, 1989 EDITION Ites No.
Exception Bl.10 The Reactor Pressure Vessel (RPV) Shell Welds are limited to automated examinations from the RPV interior due to dose and accessibility of the exterior surface. The beltline circumferential weld (RPV-SC-C-11) and the three lower shell longitudinal welds' (RPV-SL-A-3, RPV-SL-B-3, RPV-SL-C-3) interior scanning surfaces are limited by the proximity on the six RPV surveillance capsule holders located at 45*, 85', 95", 225*, 265, and 275*.
The Code required exam volume cannot be met on these welds and a relief request has been submitted.
81.30 The RPV upper shell-to-flange weld (RPV-A-11) is limited to'a manual examination from the flange surface and an automated examination from the RPV interior, due to dose and accessibility of the exterior surface and to the geometry of the RPV. The Code required exam volume cannot be met on this weld and relief is included in the above mentioned relief request.
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APPENDIX IC l
-EXCEPTIONS TO COMPLIANCE WITH TABLE IWC-2500 Item No.
Exception i
None Substitute Examinations for Table IWC-2500-1 C5.81 The following are inaccessible branch connection welds due to cable wrapping which holds a system of heavy metal slats in place over the main steam piping in Room 81.
ISO #
Component-i B-04 28-MS-2001/12-BC-1 28-MS-2001/12-BC-2 i
28-MS-2001/15-BC-1 28-MS-2001/15-BC-2 B-06 28-MS-2002/12-BC-1 28-MS-2002/12-BC-2 28-MS-2002/15-BC-1 28-MS-2002/15-BC-3 The Fort Calhoun Updated Safety Analysis Report (USAR), Appendix M, Section 3.5.8 states:
"A protective enclosure (has been) provided around the main steam and feedwater lines between the penetration sleeves and the first isolation valves, where a large rupture is postulated.
This enclosure, although designed primarily to limit the effects of jet impingement, also serves to minimize the reaction effects of a longitudinal rupture by containing the jet and preventing the formation of an unbalanced external-force."
In the past, the NRC has conducted a review of the piping exam areas (Docket 50-285, November 10,1986) and determined that the required examinations were impractical to perform.
Since one of the eight branch connection welds listed above is required by ASME Section XI, OPPD will substitute a similar branch connection weld on-the non-class portion of the main steam line shown on isometric B-86.
The Code required IWA-5000 system leakage test monitors all the cable wrapped welds.
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APPENDIX ID EXCEPTIONS TO COMPLIANCE WITH TABLE IWD-2500-1 Item No.
Exception None i
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SUMMARY
TABLES 1
i i
i 1
R2 June 15, 1995 Page 25 of 168 h
i f
TABLE 1A THIS PAGE INTENTIONALLY LEFT BLANK 1
l 1
1 1
l R2 June 15, 1995 Page 26 of 168
TABLE 1B INTERVAL 3 CLASS 1 EXAMS ARE_A EGs ED 151 21 0
!E M
(B B-A PRESSURE RETAINING WELDS IN RFV 8-A l81.10l RPV 5 HELL WELDS B-A l81.11l CIRCUMFERENTIAL l
V1 l
ALL WELDS l
YES l
3 l
3 3
B-A l91.12l LONGITUDINAL l
V1 l
ALL WELDS l
YES l
9 l
9 9
B-A Bl.20 RPV HEAD WELDS B-A Bl.21 CIRCUMFERENTIAL VOL ACCES.gu tH ALL YES 2
2 2
j B-A 81.22 MERIDIONAL V1 ACCES.
N TH ALL YES 12 12 12 B-A Bl.30 RPV SHELL4 LAME WELD VOL FLANE FACE IST PERIOD PART.
1 I
PARTIAL I
B-A Bl.40 R[. HEAD 4 LANE WELD SifR/VOL FLANE FACE IST PERIOD PART.
I 1
PARilAL 1
TDTAL IIlfEER & DUUt5 PER CR18El l
28 l
28 2 PARTIAL 28 IUTAL 1R59ER & DUUt5 ACQftl LATED llEQUIRED ACQftE.ATED IROGER PER PERIDD 2 PARTIAL 28 B-B PRES 5URE RETAINING WELDS IN VESSELS OTHER RPV B-B l82.10l PZR SHELL-HEAD WELDS B-B lB2.11l CIRCurfERENTIAL l
VOL l
ALL WELDS l
NO l
2 l
2 1(UPPER) 1 (LOWER) 6-8 l' 0F WELD B2.12 LONGITUDINAL V1 IllTERSE G B2.11 NO 4
2 1(UPPER) 1(LOWER)
B-B lB2.20l HEAD WELD 5 l
N/A l
ONE PIECE HEADS B-8 lB2.30l SG HEAD WELDS R2 June 15, 1995 Page 27 of 168
TABLE 1B l
INTERVAL 3 CLASS 1 EXAMS 11 RED 15T CD 2M) 33 310 33 8-8 l B2.31 l EIRCUMFERENTIAL l
VOL l
1 ELD PER HEAD l
NO l
4 l
1 1
8-8 B2.32 MERIDIONAL VOL 1 WELD PER HEAD NO 8
1 1
B-8 B2.40 TUBE 5HEET-HEAD WELD WOL ELD NO 2
1 1
B-8 l62.50l MX SHELL (OR HEAD) ELDS B-8 lB2.51l EIREtITERENTIAL (RGHX) l VOL l
1 WELD PER HEAD l
NO l
2 j
1 1
B-8 l82.70l LONGITUDINAL (RGHX) l VOL l
ENTIRE WELD l
NO l
2 l
1 1
B-8 l82.80l TUBESHEEi-SHELL WELD (RGHX) l VOL l
ELD l
NO l
2 l
1 1
TOTAL IRMER W EXMts PER EU tMI l
26 l
10 2
3 5
TUTAL MMER & EXMt5 AEEIM1ATED 2
5 10 REQUIRED ACCM1ATED IRfeER PER PERIOD 2-3 5-6 10 B-D Full PENETRATION WELD OF N0ZAE5 IN VE55Et3 8-D l B3.90 l RPV N0ZAE-VE55EL WELDS l
VOL l
ALL N0ZZLE5 l
PART.
l 6
l 6
6 8-D l B3.100 l RPV NCIAE INNER RADIUS l
VOL l
ALL N0ZZLES l
NO l
6 l
6 6
B-D l 83.110 l PRI N0ZAE-VE5SEL WELDS l
VOL l
ALL N0ZZLES l
NO l
5 l
5 2
3 GM) l 83.120 l PRZ N0ZZLE-INNER RADIUS l
VOL l
ALL N0ZZLES l
NO l
5 l
5 2
3 8-D l B3.130 l SG N0ZZLE-VESSEL ELOS l
VOL l
ALL N0ZZLE5 l
N0 l
6 l
B-D l B3.140 l SG N0lILE-INNER RADIUS l
VOL l
ALL N0ZAES l
NO l
6 l
B-D l B3.150 l HX N0ZZLE-VE5SEL WELDS (RGHX) l VOL l
ALL N0ZZLES l
NO l
4 l
4 2
2 R2 June 15, 1995 Page 28 of 168
TABLE 1B INTERVAL 3 CLASS 1 EXAMS CATTERY ITEM EXMEIRATIGI EXMt KtRITRED (ETERRAL TUTAL mfER lafmi EfMR 1RDER RfER RfMR ANEA PETED El#45 TO EIR)
EfGER REQUIED IST PERIG) 290 PERIG) 3El PERItB B-D l 83.160 l HX N0ZZLE-IkNER RADIUS (RGHX) l VOL l
ALL N0ZZLES l
NO l
4 l
4 2
2 l
TUTM. EfeER 7 EXMI5 PER Ct1.IfEl l
42 l
42 14 12 16 l
TUTAL IRfeER OF EI#t5 ACQftLATED 14 24 42 l
l OQllIRED ACQMRATIGI PER PERIOD
- NOTE: SECTION XI CAT. B-D NOTE 2 REQUIRES 25% - 50% IN FIRST PERIOD
'll - 21 21 - 29 42 ll B-E PRE 550RE RETAIMING PARTIAL PENETRATION WELDS IN VE55EL5 l
ALL EXMts PERFORMED UNDER PROCEDURE OP-ST-RC-3007 B-F PRES 5URE RETAINING DISSIMILAR tETAL WELDS 8-F l 85.10 l RPV N02-5AFEEND ;4*
l SUR/VCL l ALL WELDS l
NO l
6 l
6*
6 ll l
B-F l 85.40 l PRZ N0Z-SMEEND 14* (SURGE SPRAY) l SUR/VOL l ALL WELDS l
NO l
2 l
2*
2 lI B-F lB5.50l PRZ N0Z-SMEEND <4" l SUR (PRL") l ALL WELOS l
NO l
3 l
3
- 1 (PRL) 2 (SMETY)
B-F lB5.70l SG N0Z-5MEEND 14*
l SUR/VOL l ALL WELDS l
NO l
6 l
6*
3 (LOOP A) 3 (LOOP B) ll B-F l B5.130 l BUTT WELD 14' (PRZ A-15/078) l SUR/VOL l ALL WELD 5 l
MO l
1 l
1 1
l B-F l B5.140 l BUTT WELD <4" (PRZ A-19/01) l SUR l
ALL WELDS l
NO l
1 l
1 1
TUTAL Rf8ER OF EXMt5 PER IILLf8 l
19 l
19 6
8 TUTAL RfeER OF EXM6 ACDfELATED 6
11 19 ItEQUIRED Act19tiLATED RBEER PER PERIG) 4-6 10 - 12 19
- NOTE: AUTGaATED EXM5
- SPRAY N0ZZLE WILL RECEIVE AN ADDlil0NAL UT EXAM R2 June 15, 1995 Page 29 of 168
co us M
O 3
5 g
3
=
g e
o R
M C
cm to 8
s 2
2 c.
hk 2
R E
I 2
w Em
~
d d
2
=
8 2
2
~.
g g
~
~
=
u R
d 6
=
=
-9gg
=
e 5
3 5
3 3
3 3
3 E
8 E
E E
E E
E E
E E
E E
2 F
T S
E T
g g
eW g
~
a m
o W
.g
=
g g
g E
w m
w v
v v
v dj P
8 5
g E
4 e
e Q
i E
m0 e
W" 4pn J
W 4
[5 5
g W
E W
E E
E E
E E
w m
tg W
bo Z
E me E
W R
d C
e E
d 8
o 5
8 E
W 4
W E
E n
=
N
'g
=
s a
o w
s s
h h
h k
I h
c
- i g
g
[
.s se a
s s
=
E c
g g
=
a g
a d
j I
8 Es a
g
~
=
w=
=
a
=
e g
E
[
h I
g E"
S 6
a g
s a
g 8
=W g
as
-~
W=
E GE W
g
=
i a
d
-s a
=
g l
Es
=
m E
WW W
g l
3" gu g
2
="
2
~
{E g
8 k
b b
05 W
8 id I
=
s a
a a
g i
i e-a
=
a a
a gI W
w o
g
+
+
+_
g c
~
~
~
~
+
+
+
+
+
+
+
+
a
~
g g
g g
3 N
TABLE 1B INTERVAL 3 CLASS 1 EXAMS
'Em"ui nWai
'"#'1'"
dea "d4P
'E'Eo" EuEii n"Ecu5En m"Eco 2m"Eao seTm 8-G-2 l87.10l VALVE 5 BOLTS /5TUDS/ NUT 5 l
Vil l
ALL <2" l
NO l
15 l
15 2
4 9
NO 37 Q-G-2 87.80 CRD 00LTS/$7UDS/ NUTS Vil IF 0 SAS ED Tax. meoi & Exms pen auMi l
si l
30 9
i0 in TUTAL NLOWR E oWM5 ACCLMA.ATED 9
19 30 REDIED NILMA.ATED mpKR PER PERIOo 5 - 10 15 - 20 30 5-J PRE 55URE RETAINING WELDS IN PIPING B-J l 89.10 l PIPE e4*
8-J l 89.11 l CIRCUMfERENTIAL l SUR/VOL l 25% ALL WELDS l
NO l
185 l
- 84 15 15 15 B-J l 89.12 l LONGITUDINAL l SUR/VOL l INTERSECT CIRC l
NO l SEAttE55 l B-J l 89.20 l PIPE <4*
B-J l 89.21 l CIRCUMFERENTIAL l
SUR l
25% ALL WELDS l
NO l
148 l
13 13 13 8-a l 89.22 l to G2TootNAL l
SuR l
NTERSECT CIRC l
NO l stutE55 l B-J l89.30l BRANCH CONNECTIONS l
25% ALL WELDS Q-J l89.31l PIPE SIZE e4' l SLR/k1L l l
NO l
6 l
- 5 1
1 5-J l99.32l PIPE SIZE <4*
l SU4 l
l NO l
13 l
1 1
1 6-J l 89.40 l SOCKET WELDS l
SUR l
25% ALL WELDS l
NO l
277 l
10 24 24 22 R2 June 15, 1995 Page 31 of 168
TABLE 1B INTERVAL 3 CLASS 1 EXAMS CATreoRY TTtM Exmier On Exm "LTuD m usw.
m AL seeER mesER EBeER RfeER meeER meeER mA uneD E 5 To um usesi monen m mzm ne PEuCD 3m staD TUTAL RfeER OF Exm5 PER G118e l
630 l
159 53 54 52 l
IUTAL E9eER OF Exm5 ACOBRLATED 53 106
!$9 KgIIRED ACQftRATED RfeER Put PERIOD 25 - 54 80 - 106 159
- EDIE REQUIRED NUMBER W EXAMS 15 FOR THE TOTALS W TH CIRC'MERENTIAL WELD 5 (334 x 25%) AND BOIN BRANCH CONMECTIONS 19 x 25%)
Q-K ! INTEGRAL ATTACHPENTS FOR CLASS 1 VE55ELS PIPING, PUMPS & VALVES l.
B-K-1 l 810.10 l SG & PZR IRT WELMD ATTACH l SUR OR VOL l ALL WELOS l
NO l
9 l
5 1
4 l
Q-K-1 l B10.20 l PIPING WELDED ATTACH. (A-42) l SUR OR VOL l ALL l
NO l
4 l
1 1
l B4-1 l 810.30 l PUMP WELDED ATTACH. (RC-38) l SUR OR VOL l 1 LOOP l
NO l
12 l
3 3
l mat useui Or Exm3 m Cause l
25 l
9 4
i l
EDTE: LOW NUMBER W EXAM LOCATIONS (4) PRECLUDES TYPICAL 5APPLIkG PER PERIOD l
B-t-1 PRESSURE RETAINING WELDS IN PUMP 5 B-L-! l 812.10 l PUPP CASING ELDS l
VT1 l ALL (CODE CASE 481) l YES l
4 l
1 1 (RC-3C) li B-L-2 PUMP CASING 5 E"
B-L-2 B12.20 PUMP INTERNALS (& BATTLE WELDS)
VT3 YES 4
(ONLY IF !
EMBL D)
B-M-1 PRESSURE RETAINING WELDS IN VALVE B00!ES 1 W EACN MILAR 14 B-M-1 812.30 PIPE SIZE <4*
SUR YE5 25 7
2 3
2 R2 June 15, 1995 Page 32 of 168
TABLE 1B INTERVAL 3 CLASS 1 EXAMS 15T 21E1 G3 MD Gi 1 0F EACH MILAR IN B-M-1 812.40 PIPE SIZE e4*
VOL YES 1
1 1
TUT 4. N & DUWE5 PER CIRDE l
26 l
8 2
3 3
TUTAL IRNEER E EXNES ACCl#ER.ATED 2
5 8
OQUIED ACC19tR.ATED N PER PERIGI 2
4-5 8
M2 VALVE BODIES B-M-2 l 812.50 l VALVE BODIES >4*
l VT3 l INTERNAL SURFACES l YES l
14 l
3
- THESE ERAMS WILL BE SCHECULED AROUND VALVE DISASSEMBLY MAINTENANCE (ONE OF EACH SIMILAR IN GROUP)
B-N-1 RPV INTERIOR Q-N-1 l B13.10 l VESSEL INTERIOR VT3 EACM INSPECTION PERIOD NO 1
3 1
1 1 (par)
B-N-2 l 813.50 l INTERIOR ATTACINENTS WITNIN BELTLINE (SURVEILLANCE CAPSULES) l Vil l
ACCESSIBLE WELDS l
YES l
6 l
6 6 (par)
B-N-2 B13.60 INTERIOR ATTAONENTS BEYDMD BELTLINE 6 CORE SUPPORT LUGS, 9 VT3 ACCESSIBLE WELDS YE5 15 15 15 (par)
CDRE STOP LUGS B-0-3 REMOVABLE CORE SUPPORT STRUCTURES B-N-3 813.70 CORE SUPPORT STRUCTURE VT3 YE5 1
1 1
WE 5
B-0 PRESSURE RETAINING WELD 5 IN CONTROL ROD HOUSINGS IhPE4 B-0 814.10 WELDS IN CRD MOUSING SUR YES (4
DS 8
2 3
3 gg 20 R2 June 15, 1995 Page 33 of 168
TABLE 1B INTERVAL 3 CLASS 1 EXAMS lE7MB 15T GB 21 0 MB B-P RL PRESSURE RETAINING CDFONENT5 EL WEDY M E
E g M R M SERIE5 B-P ALL F-A l F1.10 l PIPING 5UPPORT5 l
VT3 l
- 25%
l MO l
- 96 l
24 6
4 10 F-A l F1.40 l SUPDCET5 OTHER THAM PIPING (REQUIRES OPLY I 56,1 RCP & 1 PR2) l VT3 l
- 100%
l MO l
21 l
8 4
3 1
TUTAL NWEER W EAMES PER 01.154 l
l 32 10 11 11 TUTAL E8WR W EXNIS ACDfER.ATED 10 21 32 IEQUIRED ACD882.ATED NWER PER PERED 6 - 10 16 - 21 32 NOTE:
- EXAM 5 SELECTED PER CDDE CASE N-491
- THERE ARE AL50 48 SNUBBERS WHICH ARE INSPECTED UNDER TECHNICAL SPECIFICATIONS 3.14 R2 June 15,1995 Page 34 of 168
I
=_
g a
3 e
~
~
m e
O
- U Q.
8 E
z z
_f L
I h
h k
I a
~.
8 2
l E
E
~
~
~
~
~
s
~
i 9
~
t m2 4
w X
g
=
=
=
2 2
~
W a
y m
N h
h 5
5 8
m Qg s
s w
.a w
ma am ae UU N
9 l
53 EY Ob J
u
.g g,
o
~
~
~
El o g-4 w
f w
s a
e s
4 p
s a
a r
a Fe g
E-s a
li!
g l
Iw e
a v
a a
sgr cc
.s a
3~
d y
>==
E 2$Y Z
s 1%
5 m
3 E
!p$k
~!
a r
m 1
our 2
a c
g s
- g a
egs IE s
s E
E" i
t y
a o
n a
a-al'
_,d S
vg3 i
s s
8 E
a
[
g-e wy a
W g
=
, OWE li s
9 ni 5
E55 W
u
=
s oss
~
I W
E 2
g rv R
w a
!L 9
E g
a s
a
_M l
l E!!
i s
B lE s
g a
w e
g as5 s
a
=
=
E W
a e
a I-l g
d d
d E
g m
R g
6 6
6 E
R h~
8
=
E e
B 3
g 5
5 E
g g.o d
Ei) td B
b 5
E B
b gl
[
s l
4 4
w w
w w
w gg g
Q R
g Q
4 u
u v
c q
w w
e w
w
=
b E
E 7
8 N
N N
l
TABLE 1C INTERVAL 3 CLASS 2 EXAMS ETNMI EE RED 15T GI BC PERIt2 M
G3 C-C INTEGRAL ATTAClfENTS FOR VE5SELS. PIPING, PUMP 5 AND VALVE 5 PRESSW VES5EL
{g SG T UN I'ON\\)
~ ')
SUR 2%*
8 2
1(RGHI) 1(SG)
C-C C3.10 C-C l
C3.20 l
PIPING ATTACIfENTS l
SUR l
eg*
l 21 l
3 2
1 l
C-C l
C3.30 l
PUMP ATTAOf1ENTS l
SUR l
ag" l
0 l
C-C l
C3.40 l
VALVE ATTACHPENT5 l
SUR l
en*
l 0
l TUTAL RfGER OF EXM5 PER G11381 l
29 l
5 1
2 2
TUT 4. EDER (F EMR5 AE3fER.ATED 1
3 5
REQUIED AElfRA.ATED ROKR PER PERIG) 1 3
5 l
C-0 PRESSURE RETAINING BOLTING >2* DIAMETER l NONE IN PROGRAM l C-F-1 PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL OR HIGH ALLOY PIPING ^(NOTE: F.5% BUT NOT LE55 TRAN 28 WELOS)
C-F-1 l
C5.10 l
PIPING WELDS t3/8" WALL THICKNESS FOR PIPING > NPS 4 C-F -1 l
C5.11 l
CIRCUMFERENTIAL l SUR/VOL l NEE NOTE ABOVE l
359 l
45 15 15 15 C-F-1 l
C5.12 l
LONGITUDINAL l SUR/VOL l 2.5T AT INTER CIRC. l 306 l
C-F-1 l
C5.20 l
PIPING WELD 5 >1/5* NmINAL WALL THICKNESS FOR PIPING t NP5 2 s NPS 4 C-F-1 l
C5.21 l
CIRC 1MIERENTIAL l SUR/v0L l NE NOTE ABOVE l
158 l
12 4
4 4
l C-F -1 l
C5.22 l
LONGITUDINAL l SUR/WOL l 2.5T AT INTER. CIRC. l 0
l C-F-1 l
C5.30 l
50GET WELDS l
SUR l
l 480 l
36 12 12 12 R2 June 15, 1995 Page 36 of 168
TABLE 1C INTERVAL 3 CLASS 2 EXAMS CArr a T nui ExmIm non rm umurD Tara useER sween asuER mesa IRSKR NWuER NEA IETMB EING ESER llEQUImD IST PERIMI 21El PERIIB B PEREB C-F-1 l
C5.40 l
PIPE BRANCH C0hN. OF BRANOI PIPING k NP5 2 C4-1 l
C5.41 l
CIRCUMFERENTIAL l
SUR l 7EE NOTE ABOVE l
9 l
2 1
1 C4-1 l
C5.42 l
LONGITUDINAL l
SUR l 2.5T AT INTER. CIRC. l 0
l C-F-1 l
N/A l
PIPING WELDS > NPS 4 AND < 3/8* WALL THICKNESS l
273 l
0 "9:0TE:
LONG5EAM5 ARE EXAMINED WITH SELECTED INTERSECTING CIRCUMFERENTIAL hTLOS TOTAL E8ER & EXNIS PER CR15El l
1279 l
96 32 32 32 TUTAL IRSKR OF EANES ACC19tRATED 32 64 96 L' QUIRED ACQftiLATED 1RSKR PER PERIOD 16 - 32 48 - 64 96 C-F -2 PRES 5URE RETAINING WELOS IN CARSON OR LOW ALLOY STEEL PIPING *(NOTE: 7.5% BUT NOT LESS THAM 28 WELOS)
C-F-2 l
C5. 50 l PIPING WELOS t 3/8" WALL THICKNESS FOR PIPING > NPS 4 C-F -2 l
C5.51 l
CIRLUMfERENTIAL l SUR/VOL l
- 5EE NOTE ABOVE l
78 l
33 11 11 11 C-F-2 l
C5.52 l
LONGITUCIMAL l SUR/VOL l
2.5T AT INTER.
l 0
l C4-2 l
C5.60 l
PIPING WELOS > 1/5* NOMINAL WALL THICKNESS FOR PIPING t 2 NPS s 4 NP5 C4-2 l
C5.61 l
CIRCUffERENTIAL l SUR/VOL l
- SEE NOTE ABOVE O
j C-F-2 l
C5.62 l
LONGITUDINAL l SUR/VOL l
2.51 AT INTER.
0 C-F-2 l
C5.70 l
SOCKET WELDS l
SUR l
0 C4-2 l
C5.80 l
PIPE BRANCH CONNECTIONS OF BRANCN PIPING t NPS 2 l
R2 June 15, 1995 Page 37 of 168
TABLE 1C INTERVAL 3 CLASS 2 EXAMS CATTERY ITU8 EAMDIAT131 EXM KGIIED TOTAL RfMR REER REER RfGER RfGER AREA ETMW)
E2Nt5 IRfER IEIEllED IST (B
215 PERItB 38 PERItB C-F -2 C5.81 CIRCUMFERENTIAL SLR 8
1 l
C-F-2 C5.82 LONGITUDINAL SUR 2.5T AT INTER.
0 C-F-2 l
N/A l
- 3/8* WALL THICKNESS 358 TUTAL RfER W EINis PER CILifgl 444 34 11 11 12 TUTAL RBER W EINts ACQfERATED 11 22 34 OIpilllED AG15EA.ATED RSKR PER PERIWI 6 - 11 II - 22 34 PERFORMED UND[R SURVEILLANCE TESTS C-G PRESSURE RETAINING WCLOS IN PtNPS AND VALVE 5 C-G l
C6.10 l
PUMP CA11NG WELDS l
SUR l
ALL UNDER C-F l
0 l
C-G l
C6.20 l
VALVE BODY WELDS l
SUR l
ALL UNDER C-F l
1 l
1 1
C7.10 C-H THROUGH ALL OF THISE EXAMS ARE PERFORMED UNDER OPPD TECHNICAL SPECIFICATION 3.3(1)a C7.80 F-A l
F1.20 l
PIPING $UPPORT l
VT3 l
- 15%
l
- 487 l
74 25 24 25 TUTAL RfMR W EINES PER CLIBOI 25 24 25 TUTAL RfMR W EINES ACDftt.ATED 25 49 74 EQilIRED AQ15ERATED RfER PER PERItB 12 - 25 37 - 49 74 QTE:
EXAMS SELECTED PER CODE CASE N-491 THERE ARE AL50162 SNUBBERS WHICN ARE INSPECTED UNDER TECHNICAL SPECIFICATIONS 3.14 R2 June 15, 1995 Page 38 of 168
TABLE 1D INTERVAL 3 CLASS 3 EXAMS i
e t
CATTERY ITEM EXMtIqATIGI EXMI EmlTED TUTAL IRSER msER RsER N<
l IRBER NEER AKA KTME E3Nt1 ESER ltE411 RED 15T PDI31 2MB PERIIRI 3e PF a
D-8 SYSTEMS IN SUPPORT OF EMERGENCY CORE (DOLING. COMTAIMPENT HEAT REPOVAL. ATMO5PHERE CLEANUP & REACTOP RESIDUAL HEAT REPOVAL D-A D1.10 PRESSURE VE5SELS VT2 PRESSURE EfTAINING BOUND,UtY D-A l
D1.20 l
PIPING l
VT3 l INTEGRAL ATTACWENT l 70 l
7 2
2 3
0-A l
D1.30 l
PUMP 5 l
VT3 l INTEGRAL ATTAOMNT l 0
j 0
D-A l
D1.40 l
VALVE 5 l
VT3 l INTEGRAL ATTAOMNT l 0
l 0
TUTAL IRSER E EXMIS PER QLisgi l
70 l
7 2
2 3
TUTAL IRFER W EXMt5 ACCtfRR.ATED 2
4 7
[]UlRED ACCifRA.A!ED E8ER PER PERIG) 1-2 4
7 I
F-A SUPPORTS F-A F1.30A CLASS 3 PIPING SUPPORTS (ONE DIRECTION VT3 272 27 9
9 9
SUPPORTS)
F-A F1.308 CLASS 3 PIPING SLPPORT5 (PtJLII VT3 222 23 7
8 8
DIRECTIONAL RESTRAINTS)
F-4 l
Fl.30C l CLASS 3 PIPING $UPPORIS (SPRING CANS) lVT3 l
l 21 l
2 1
1 F-A l
F1.40 l
SEE CLA551 EX#ts l
VT3 l
l 0
l 0
TUTAL RBER OF EXM45 PER CELip41 l
- 515 l
52 17 17 18 TUTAL RsEER E ACOsERATED EX4E5 17 34 52 IIEglIRED ADCtstLATED MfGER PER PERIml 9 - 17 26 - 34 52 NOTE:
- EXMt3 SELECTED PER CODE CASE N-491
- THERE ARE ALSO 42 SNUBBERS WHICH ARE INSPECTED UNDER TECHNICAL SPECIFICATIONS 3.14 R2 June 15, 1995 Page 39 of 168
k i
PART 2: CLASS 1, CLASS 2, AND CLASS 3 VALVE TESTS 1.0' Program Susumary-l The Valve Test Program identifies test requirements for safety related valves and ensures that the valves are tested in accordance with the requirements of-Subsection IWV of the ASME Section XI Boiler and Pressure Vessel Code, 1989 Edition,.as delineated in 0&M Part I and Part 10, 1987 Edition up to and including the 1988 Addenda.
The Valve Test Program will be applicable for the 120-month interval, which begins on September 26, 1993. The Valve Test Program will be reviewed and updated as required with that edition of the Code and Addenda in effect not more than 12 months prior to the start of the next 120-month interval (beginning September 26,2003).
Individual valve test requirements are presented-by coded Valve Test Program Matrix, Table 2.1.
The codes used for these tables are defined in the " Table Format Fort Calhoun Station Valve Test Program Matrix Table 2.1."
The Valve Test Program Matrix (Table 2.1) is arranged in numerical sequence by valve number. Appendix.2A provides justifications for valve test frequencies other than Quarterly. A basis for the test-frequency is given as well as the frequency at which the valve will be tested. Appendix 2B provides justifications for exceptions taken to the ASME Section XI/0&M Code test requirements as provided for in 10CFR50.55a(g)(5)(iii). Two types of justifications are provided. The.
4 first is general in nature, and pertains to requirements found to be impractical for many valves.
The second type is used to justify Code exceptions for specific _ valves. Code exceptions are numbered and referenced by number on the Valve Test Program Matrix Table 2.1.
2.0 Scope and Responsibility i
2.1 The P& ids listed in Part 4 of the Plan identify the location of r
each Class 1, Class 2, and Class 3 and other classes of valves i
"important to safety" as determined by the Fort Calhoun Station (FCS) IST philosophy.
l 2.2 The Class 1, Class 2, and Class 3 and other classes of valves "important to safety" to be tested under 0&M Part 1 and Part 10, the methods of testing for each valve, and exceptions to the tests l
of 0&M Part 1 and Part 10, are found in the Valve' Test Program Matrix Table 2.1 and Appendices 2A and 28.
2.3 Many safety related systems, particularly those with heat exchangers, have been provided with relief valves.
These relief valves are thermal relief valves of small capacity intended to relieve pressure due to a thermal expansion of fluid in a
" bottled-up" condition (generallyoccurringonlyduring j
maintenance), which is considered a self-limiting transient.
Experience has shown that failures of these valves will not result in failure of a system to fulfill its safety related function.
Thus, most thermal relief valves are not considered to perform a J
safety function as defined by 0&M Part 1 and Part 10, and such R2 June 15, 1995 Page 40 of 168 s
r rs%._
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7 y.c-n
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valves have not been included in the ISI Program Plan at the Fort Calhoun Station.
2.4 As a result of regulatory concerns regarding) Containment Integrity issues (Reference CID Nos. 883627 and 882025 -the following actions.are taken and will be required of all future changes / upgrades to applicable surveillance tests required by the FCS ISI P9 gram Plan.
l 2.4.1 Surveillance Tests for Containment' Isolation Valves Leakage (Type C) tests have been upgraded to include detailed drawings of all designated test tees and require procedural signoffs for removal and reinsta11ation of test tee caps.
2.4.2 A separate documented and double' verified checklist of designated'swagelock caps has been developed and this check list will be performed by the Operations Department prior to power operation following a Refueling Outage to ensure i
~
ContainmentIntegrity(0I-CO-5).
3.0 Inservice Test Frequency 3.1 The inservice test frequency for Class 1, Class 2 and Class 3 valves and other valves "important to safety" is in accordance with O&M Part I and Part 10 with exceptions as found in Appendices 1
2A and 28, 3.2 Valves identified herein as being tested at Cold Shutdown frequency shall be tested each Cold Shutdown (as defined by FCS Technical Specifications) where the duration of the shutdown is-H sufficient to accomplish the tests.
Valve testing should. commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after Cold Shutdown and continue until complete or, the plant is ready to return to power.,
Completion of all valve testing is not a prerequisite to return to power. Any j
testing not completed at one Cold Shutdown should be-performed during subsequent Cold Shutdowns to meet the Code required testing frequency. Where more than one Cold Shutdown occurs within three months, the test frequency need not exceed once per three-month period (92 days).
4.0 Valve Categories The valve categories for each Class 1, Class 2, Class 3 and other "important to safety" valves have been determined from 0&M Part 1 and Part 10 with exceptions as found in Appendices 2A and 28.
1 5.0 Test Methods 5.1 The methods to be used to test Class 1, Class 2, Class 3 and "important to safety" valves have been determined.from the appropriate sections of 0&M Parts 1 and 10.
These methods, along with exceptions, are listed in the Valve Test Program Matrix Table 2.1 and Appendices 2A and 2B (of this Program Plan).
R2 June 15, 1995 Page 41 of 168
5.2 Valves with remote position indicators shall be observed locally, or verified by other positive methods (such as changes in flow or pressure directly attributed to valve movement) at least once every two years in order to verify that valve operation is accurately indicated.
5.3 Valves with safety related failure positions indicated in the valve tables will be tested by observing valve operation upon loss i
of actuator power at the frequency specified in the valve tabic.
5.4 Valve stroke times are measured from actuation of valve operating device to end of valve travel as indicated by remote valve position indication lights.
The valves will be timed using the lights in the Control Room as applicable.
5.5 Valve stroke times which exceed the acceptance criteria as stated in Paragraph 4.2.1.8 of O&M Part 10 will be immediately retested and corrective action taken as delineated in Paragraph 4.2.1.9 of 0&M, Part 10.
5.6 Valve stroke times which exceed the acceptance criteria as determined by guidance using Paragraph 4.2.1.4 of O&M Part 10 and.
listed in the Surveillance Test or the Acceptance Criteria Basis Document shall be immediately declared inoperable, and not i
returned to service until corrective action is taken.
6.0 Evaluation of Test Results 6.1 The evaluation of test results shall be in accordance with the appropriate paragraphs in 0&M Part 10.
6.2 If test data show that a valve is operating in the " Alert Range",
remedies shall be taken as required in accordance with 0&M Parts 1 and 10 until corrective action is taken.
If the test data shows that the valve is operating in the " Required Action Range", the valve shall be immediately declared inoperable and not returned to service until corrective action is taken.
Corrective action is defined as one or more of the following steps:
6.2.1 Recalibrate the applicable instruments and reperform test, or 6.2.2 Repair or replace the component as required, or 6.2.3 Perform an Engineering Analysis to demonstrate that the valve is still able to perform its required safety design function.
7.0 Records and Reports 7.1 Records and reports for the testing of Class 1, Class 2 and Class 3 and other "important to safety" valves shall be made in accordance with Paragraphs 6.2 and 6.3 of 0&M Part 10.
I R2 June 15, 1995 Page 42 of 168
1 1
7.2
. Records of corrective action for Class 1, Class 2, and Class 3 and other "important to safety" valves shall be made and maintained in accordance with Paragraph 6.4 of 0&M Part 10.
8.0 Repair Requirements l
Tests or examinations required to be performed after completion of valve replacement, repair or maintenance shall be completed as required per ASME, 0&M Parts 1 and 10, and Section XI.
9.0 Valve Test Program Matrix Tnis section provides a tabulation of. safety related valves, both those valves that are tested in accordance with the requirements of Part I and Part 10 of the 0&M, and those valves for which the Code requirements i
have been found to be impractical.
The Valve Test Program Matrix (Table
.l
-2.1) is arranged sequentially in numerical order by valve number.
10.0 Additions to Program - Valves Valves added to the ISI Program Plan as a result of plant / system modifications, engineering changes or re-evaluation of a component eligibility requirement, per the 0&M manual, are considered operable based on interim acceptance criteria (established by construction,.
preservice, post maintenance, or preoperational tests) until a trend is i
established.
)
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i R2 June 15, 1995 Page 43 of 168 i
-TABLE FORMAT FORT CALHOUN STATION VALVE TEST PROGRAM MATRIX TABLE 2.1 l
1.
Valve Number Unique number assigned to each valve.
t 2.
System (SYS)
Plant system where valve is located. Designated by two (2) or three (3) letters.
AFW - Auxiliary Feedwater System CA - Compressed Air System
. CCW - Component Cooling Water System CH - Charging System CS - Containment Spray t
DW - Demineralized Water System F0 - (Diesel Generator) Fuel Oil System
. FW - Feedwater System HG - Hydrogen Gas IA - Instrument Air System MS - Main Steam System NG - Nitrogen Gas System
. RC - Reactor Coolant System RW - Raw Water System SA - (Diesel Generator) Starting Air System SI - Safety Injection System SL - Primary Sample System SW - Service Water System l
VA - Ventilating Air System WD - Waste Disposal System 3.
Category (CAT)
Valve category as defined in 0&M Part 10.
a.
Category A Valves for which seat leakage is limited to a specific maximum amount in the closed position to fulfill their required functions.
l b.
Category B Valves for which seat leakage in the closed position is inconsequential for fulfillment of their required functions.
l c.
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 function (s).
d.
Category 0 Valves which are actuated by an energy source capable of only one operation, such as rupture disks or explosive-actuated valves.
4.
Class (CL)
ASME Class (1, 2, 3, 4, or N) 5.
P&ID Plant drawing number where valve is found.
6.
Coordinates Location of valve on plant drawing.
~ 2 June 15, 1995 Page 44 of 168 R
h 1
l TABLE FORMAT
. FORT'CALH0UN STATION VALVE TEST PROGRAM. MATRIX TABLE 2.1 (Continued) 7.
-Valve Type The following is a list of the type of valves with the code used in the Valve Test Program
~
Tables.
BU - Butterfly GA - Gate i
BL - Ball GL - Globe CK -' Check DI - Diaphragm:
PG - Plug RL - Relief-t 8.
Operator Type (OPER TYPE)
{
t The following.is a list of the types of operators used to change the position of the. valve, with the code used in the Valve Test Program Table to reflect the operator type.
A - Air Operator C - Self Actuated M - Motor Operator S - Solenoid Operator R - Relief H - Manual (Hand)
P - Piston Operator a
9.
Valve Size Nominal diameter of valve in inches.
10.
Normal Position (NOR POS)
The following is a list of valve positions during normal operation and the code used in the Valve Test Program Table to reflect that position.-
i A - Automatic NO - Normally Open LO - Locked Open NC - Normally Closed LC - Locked Closed i
- Valve position determined by other system parameters as in l
the case of check valves 11.
FailPosition(FAILPOS)
The following is a list of valve failure positions and the code used in the Valve Test Program Table to reflect that position.
FC - Fails Closed FAI - Fails As Is
- Valve failure position l
F0 - Fails Open determined by other system parameters as in the case of
{
1 l
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i R2 June 15, 1995 Page 45 of 168
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TABLE FORMAT
' FORT CALHOUN STATION VALVE TEST PROGRAM MATRIX TABLE 2.1 (Continued) 1 12.
Testing Requirements (TEST REQ)
This column indicates the position to which the valve is to be tested in order to satisfy the Code test requirements which apply to the valve.
The following is a list of the codes used in the Valve Test Program Table.
0 - Valve shall be exercised to the Open position C - Valve shall be exercised to the Closed position T - Valve shall be tested to ensure meeting a specific Trip position L - Valve shall be tested for seat tightness and Leak criteria 13.
Type Test The following is a list of tests required to be performed per ASME 0&M Part 1 and Part 10 Code and the code used in the Valve Test Program Table to reflect that test.
FS - Full-Stroke Test PS - Partial-Stroke Test 1
LT - Leak Test ST - Stroke-Time Test I
SP - Setpoint Trip Test j
SD - Sample Disassembly j
ME - Manual Exercise 14.
Testing Frequency (TEST FREQ)
The codes used in this column indicate the plant operational status that 1
must be achieved before a particular valve can be safely and practically tested.
Quarterly
-Q Valves in this category shall be tested Quarterly during normal plant operation.
(Technical j
Specification Modes 1 through 3) j l
Cold Shutdown CS Cold shutdown conditions are defined in the FCS Technical Specifications. (See Part 2 Section 3.2 of this Program Plan for further explanation).
i 1
R2 June 15, 1995 Page 46 of 168
TABLE FORMAT FORT CALH0UN STATION VALVE TEST PROGRAM MATRIX TABLE 2.1 (Continued)
. CS*
Pressure Isolation Valves Surveillance of.the Reactor Coolant System (RCS) l Pressure Isolation Valves (PIV) -Plant Technical.
Specification 3.3(2) states that periodic leakage testing on each valve. listed in Table 2-9 (as a PIV) shall be accomplished:
(1) prior to entering the power operation mode every e
time the plant is placed in the Cold Shutdown condition for refueling; (2) each time the plant is placed in a Cold Shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding nine months; and (3) prior to returning the valve to service after maintenance, repair or replacement work is performed.
Refueling Outage R0 Refueling conditions are defined in the FCS Technical Specifications.
Refueling Outage R0*
.The valves in this category will be sample disassembled and inspected at an interval not to i
exceed once every six (6) years.
2YR -
Periodic valve leakage rate determination for Category j
A valves shall be performed at a minimum of two year j
intervals in accordance with 0&M Part 10.
a OM -
The relief valves will be tested in accordance with the_ frequency established by O&M Part 1.
OM* -
The relief valve will be tested once every third refueling outage.
- 15. _
ValvePositionIndicationTest(VPITEST)
This column indicates if a remote Valve Position Indication verification i
test is required. Valves with remote position indicators, which are used to verify valve exercising or timing, will have their remote position indicators verified in accordance with O&M Paragraph 4.1 of Part 10.
R2 June 15, 1995 Page 47 of 168
TABLE FORMAT l
FORT.CALHOUN STATION VALVE TEST PROGRAM MATRIX TABLE 2.1 (Continued) i i
l 16.
Code Exception (CODE EXPT)
If the valve h being tested at the Code required frequency (e.g.,
Quarterly) in accordance with 0&M Part 1 or Part 10 requirements, this column will have a "." However, for valves with impractical 0&M Part 1 and Part 10 frequency requirements, this column will have a reference i
frequency justification number (JXX).
This number is addressed in i
Appendix 2A.
If the valve is being tested in accordance with 0&M Part 1 or Part 10 requirements, this column will havc. 4 However, for valves which the O&M Part 10 requirements have been found to be impractical, this column will have a reference code exception number (EXX). This reference number is addressed in Appendix 2B with a complete explanation of the specific exception and the justif.ication for that exception.
17.
Remarks i
This column is provided for pertinent information as appropriate.
Notes in Column 17 of the Instrument Air (IA) Check Valves refer to Notes 1 through 5 listed below.
NOTE #1 These valves are check valves on Instrument Air accumulators attached to process valves that are specified for testing l
elsewhere in the ISI Program Plan. The IA check valves will be tested on the same schedule as the process valve to which it is attached.
NOTE #2 These valves are check valves on IA accumulators on bubblers that are part of the level indication / control system for the Safety Injection Refueling Water Tank (SIRWT). The ISI l
Program Plan speaks only to the testing of the check valve in this system.
)
NOTE #3 These valves are check valves on IA accumulators attached to HCV-238 and HCV-239 (which are located inside the containment).
The process valves are remotely stroke tested Quarterly, but due to inaccessibility accumulator check valves IA-HCV-238-C and IA-HCV-239-C will be tested at Cold Shutdown.
NOTE #4 These valves are check valves on IA accumulators attached to PCV-6680A-1, PCV-6680A-2, PCV-66808-1, PCV-6680B-2 and PCV-l 6682.
The valves are located in Room 81.
The dampers are not required to be tested; however, the IA accumulator check valves are required to be tested at Cold Shutdown.
NOTE #5 These valves are check valvcs on IA accumulators attached to HCV-480, HCV-484, and HCV-485. The check valves are tested opened and closed quarterly. Reference MR-FC-89-032.
R2 June 15, 1995 Page 48 of 168
i TA8LE FORMAT-FORT CALHOUN STATION VALVE TEST PROGRAM MATRIX TABLE 2.1'(Continued) t
.. r NOTE #6 The valves are check valves on IA accumulators to HCV-
'2898A/B and HCV-2899A/B. The check valves are tested open and closed Quarterly. Reference MR-FC-94-020.
i I
i t
R2 June 15, 1995 Page 49 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE
~
NtDeER SYS CAT CLASS P&ID
- INATE, TYPE TYPE SIZE
2 210-130 3 C1 CK C
6 0
PS Q
2 210-130-3 C1 CK C
6 0
FS RO J1 OP-ST-SI-3007 AC-101 CCW C
3 M 10-2 E6 CK C
12 0
FS Q
3 M-10-2 E6 CK C
12 C
FS Q
OP-ST-CCW 3012/3022 PCV 102-1 RC B
1 210 110-1A E7 GL S
2.5 NC FC C
J2 OP-ST-RC-3004 FCV-102 1 RC B
1 210-110-1A E7 GL S
2.5 NC FC 0
J2 OP-ST-RC-3004 PCV-102-2 RC B
1 210 110-1A E8 GL 2.5 NC FC 0
J2 OP-ST-RC-3004 PCV 102-2 RC B
1 210-110 1A EB GL 5
2.5 NC FC C
J2 OP-ST RC 3004 51-102 SI C
2 210 130 3 C4 CK C
4 0
FS RO J3 OP ST SI-3007 51-102 SI C
2 210-130-3 C4 CK C
4 C
F5 RO.
J3 OP-ST-SI-3007 0
FS Q
3 M-10-2 D6 CK C
12 AC-104 CCW C
3 M 10-2 D6 CK C
12 C
FS Q
OP ST-CCW-3002/3022 FO 104 FD C
3 M-262-1 F6 CK C
1 OP-ST-FO-3002 C
FS Q
FO-104 F0 C
3 M 262-1 F6 CK C
1 0
FS Q
OP-ST-FO-3002 51 104 SI C
2 210 130 3 C4 CK C
1 0
FS Q
3 M-262 1 E6 CK C
1 C
FS Q
OP-ST-FO-3002 FO-105 F0 C
3 M 262 1 E6 CK C
1 0
FS Q
OP ST-FO-3002 FO 106 F0 C
3 M 262-1 D6 CK C
1 0
FS Q
3 M 262-1 D6 CK C
1 C
FS Q
3 M 10 2 C6 CK C
12 0
FS Q
3 M-10 2 C6 CK C
12 C
FS Q
OP ST-CCW-3002/3012 FO 107 FU C
3 M 262 1 C6 CK C
1 0
FS Q
OP-ST-FO-3001 FO 107 F0 C
3 M 262-1 C6 CK C
1 C
FS Q
OP-ST FO-3001 51-108 SI C
2 210-130-3 D4 CK C
4 0
FS RO J3 OP ST-SI 3007 51-108 SI C
2 210 130-3 D4 CK C
4 C
FS RD J3 OP-ST-SI 3007 51-110 SI C
2 210 130-3 E4 CK C
1 0
FS Q
OP-ST SI-3006 NG-113 CCW A/C 3
M42 SH. 1 D7 CK C
1 0
FS Q
SE-ST-CCW 3G03 NG 113 CCW A/C 3
M42 SH.1 D7 CK C
1 C
FS Q
~5 113 CCW A/C 3
M42 SH. 1 D7 CK C
1 L
LT 2VR SE ST-CCW 3003 51 113 SI C
2 210 130 3 El CK C
8 0
PS -
Q J1 OP ST-SI 3008 51 113 SI C
2 210-130-3 El CK C
B 0
FS RO J1 OP-ST SI-3007 RW 115 RW C
3 M-100 1 B4 CK C
20 0
FS Q
3 M 100 1 84 CK C
20 C
FS Q
OP-ST-RW 3004 51-115 SI C
2 210-130-3 E4 CK C
4 0
FS RO J3 OP ST SI-3007 SI-115 SI C
2 210-130-3 E4 CK -
C-4 C
FS RO J3 OP-ST-SI-3007 R2 June 15,1995 Page 50 of 168
t TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TIST VPI CODE NUPEER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE
3 M-100 1 BS CK C
20 0
FS Q
OP-ST-RW-3021 RW-117 RW C
3 M 100-1 B5 CK C
20 C
FS Q
OP-ST-RW 3004 51-117 SI C
2 210 130-3 F4 CK C
1 0
FS Q
3 M 100 1 B6 CK C
20 0
FS Q
OP ST-RW 3011
+
C FS Q
OP-ST-RW-3004 RW-121 RW C
3 M 100-1 B6 CK C
20 51 121 SI C
2 210 130-1 A4 CK C
B 0
FS CS J4 OP-ST-SI-3003 51 121 SI C
2 210 130-1 A4 CK C
B C
FS C5 J4 OP-ST-SI 3003 I
3 M-100-1 B7 CK C
20 C
FS Q
3 M 100-1 B7 CK C
20 0
FS Q
OP-ST-RW 3001 SA-127 SA C
3 B120F07001 1 E7 RL R
0.75 T
SP OM PE ST-VX-3004 PE-ST-VX 3004 SA 128 SA C
3 8120F07001-1 E7
' RL R
0.75 T
3 210-121 1 A6 CK C
3 0
FS Q
+
3 210 121 1 A6 CK C
3 C
FS Q
CH-4A DISCHARE OP ST-CH 3002 SA 129 SA C
3 B120F07001 1 C7 RL R
0.75 T
0 FS C5 J4 OP-ST SI 3003 -
51 129 SI C
2 210-130 1 B4 CK C
2 210 130 1 B4 CK C
B C
FS CS J4 OP ST-SI 3003 CH 130 CH C
3 210-121 1 B7 CK C
3 0
FS Q
CH 4B DISCMRGE OP-ST-CH 3002 CH-130 CH C
3 210 121-1 B7 CK C
3 C
FS Q
CH-4B DISCHARGE OP ST-CH 3002 SA 130 SA C
3 B120F07001 1 B7 RL R
0.75 T
51 135 SI C
2 210-130-1 C4 CK C
B 0
FS CS J36 OP-ST SI-3003 f
C FS C5 J36 OP-ST SI 3003 SI 135 SI C
2 210 130 1 C4 CK C
B 51-139 SI A/C 2
210-130 1 02 CK C
20 0
SD RO*
PS Q
El GP ST SI-3008 51 139 SI A/C 2
210-130-1 D2 CK C
210 130-1 D2 CK C
20 L
LT 2YR SE-ST-SI-3005 SI 139 St A/C 2
210-130 1 02 CK C
20 C
[
SI 140 51 A/C 2
210-130 1 C2 CK C
20 O
PS Q
El OP-ST-St-3008 51-140
'SI A/C 2
210 130 1 C2 CK C
20 0
SD RO*
El SS ST SI 3018 51-140 51 A/C 2
210 130 1 02 CK C
20 L
LT 2YR SE-ST-SI 3005 SE-ST SI-3005
[
51 140 51 A/C 2
210 130-1 C2 CK C
20 C
FS RO T
SP RO SENT OFFSITE SS ST RC 3002 RC-141 RC C
1 210 110 1A F6 RL R
3 NG 142 NG A/C 2
M42 SH. 1 E5 CK C
1 0-PS Q
NG-142 NG A/C 2
M42 SH. 1 E5 CK C
1 0
F5 CS J43 SE-ST NG 3002 NG 142 NG A/C 2
M42 SH. 1 E5 CK C
1 C
3 -142 NG A/C 2
M42 SH. 1 E5 CK C
1 L
LT 2YR SE-ST NG-3002 SENT OFFSITE SS ST-RC 3002 RC 142 RC C
1 210-110-1A F6 RL R
3 T
SP RO R2 June 15,1995 Page 51 of 168
TABLE 2 1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE j
COORD-VALVE OPER VALVE NORM FAIL TEST TYPE EST VPI CODE CAT C55 P&ID INATES TYPE TYPE SIZE -
POS POS REQ TEST FREQ TEST EXPT REMARKS
2 210-121-2 B5 CK C
3 0
SI-143 SI C
2 210 130-1 D4 CK C
8 0
FS CS J36 CP ST-SI-3003 l
51 143 SI C
_ 2 210-130 1 D4 CK C
8 C
FS CS J36 OP-ST St 3003 l
NG 144 NG A/C 2 M42 SH. 1 E6 CK C
1 0
PS Q
NG 144 E
A/C 2
M42 SH. 1 E6 CK C
1 0
FS CS J43 SE-ST-NG-3002 NG 144 E
A/C 2
M42 SH. 1 E6 CK C
1 C
FS CS J43 SE ST-NG 3002 NG 144 E
A/C 2
M42 SH. 1 E6 CK C
1 L
LT 2YR SE-ST NG-3002 NG 146 E
A/C 2
M42 SH. 1 E7 CK C
1 0
PS Q
NG-146 NG A/C 2
M42 SH 1 E7 CK C
1 0
FS CS J43 SE-ST-E 3002 NG 146 NG A/C 2
M42 SH. 1 E7 CK C
1 C
FS CS J43 SE-ST NG 3002 G 146 E
A/C 2
M42 SH. 1 E7 CK C
1 L
LT 2YR SE-ST-NG 3002 SA 147 SA B
3 B120F07001-1 D3 DI A
15 NC FO O
ST Q
Y DG START ACCEPT OP ST-DG 0001 SA-147 SA B
3 B120F07001 1 D3 DI A
1.5
.NC FO O
VPI Q
Y DG START ACCEPT OP-ST-DG 0001 NG 148 NG A/C 2
M42 SH. 1 E7 CK C
1 0
PS Q
l NG-148 NG A/C 2
M42 SH. 1 E7 CK C
1 0
FS CS J43 SE ST-HG-3002 i
NG 148 NG A/C 2
K42 SH. 1 E7 CK C
1 C
NG-148 NG A/C 2
M42 SH. 1 E7 CK C
1 L
LT 2YR SE ST E-3002 SA 148 SA B
3 B120F07001 1 C3 DI A
1.5 NC FO O
ST Q
Y DG START ACCEPT OP-ST DG 0002 SA 148 SA B
3 B120F07001-1 C3 DI A
15 NC FO O
VPI 2YR Y
DG START ACCEPT Co-ST DG 0002 51 149 SI C
2 210 130 1 E4 CK C
8 0
FS CS J36 OP-ST-SI 3003 51 149 51 C
2 210 130 1 E4 CK C
B C
FS CS J36 OP ST SI-3003 HCV 150 RC B
1 210 110-1A DB CA M
25 NO FAI C
S1 Q
1 210-110 G8 FA M
2.5 NO FAI VPI 2YR Y
2 210-121 2 C7 CK C
3 C
FS Q
1 210 110-1A D7 GA H
2.5 NO FAI C
ST Q
Y OP-ST-RC 3002 HCV-151 RC B
1 210-110 GB GA M
25 NO FAI VPI 2YR Y
2 210 130-1 E5 CK C
6 0
FS Q
2 210-121-2 AS CK C
3 0
FS CS J5 OP-ST CH-3006 CH-156 CH C
2 210 120 1 E3 CK C
3 0
FS CS J5 OP-ST-CH-3006 SI 159 SI C
2 210 130 3 B6 CK C
24 0
SD RO*
E2 SS-ST-SI-3016 51 160 SI C
2 210-130-3 B6 CK C
24 0
SD RO*
E2 SS-ST-SI-3016 W 161 FW C
2 H 253 1 D4 CK C
16 C
FS CS J6 SE-ST FW3002 FW 162 FM C
2 M-253-1 D6 CK C
16 C
FS CS J6 SE-ST FW-3002 FL 163 AFW C
2 M 253-4 F7 CK C
3 0
FS CS J7 OP-ST-AFW 3007 AC-164 CCW C
3, M-10 D6 RL R
0.75 T
)
R2 June 15,1995 Page 52 of 168 l
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI COE NUMBER SYS CAT CLASS P&ID ImTES TYPE TYPE SIZE
- POS POS REQ TEST FREQ TEST EXPT REMARKS FW 164 AN C
2 M 253 4 F8 CK C
3 0
FS CS J7 OP ST AFW-3007 AC-165 CCW C
3 M-10 C6 RL R
0.75 T
SP OM PE-ST VX-3007 CH 166 CH C
2 210 120-1 C2 CK C
4 C
FS CS J35 SE ST-ArW-3006 W 173 AN C
3 M 253 4 C6 CK C
4 0
FS Q
SE-ST AFW-3006 Ft$ 173 AN C
3 M-253-4 C6 CK C
4 C
FS Q
SE-ST AN-3005/3006 Ft$-174 AFW { C 3
M 253 4 CS CK C
4 0
FS Q
SE-ST-AFW 3005/3006 Ft$-174 AN C
3 M 253 4 C5 CK C
4 C
FS Q
SE ST-AN-3005 SI 175 SI C
2 210-130 2 81 CK C
12 0
SD RO*
E3 SS-ST-SI-3017 HCV 176 RC 8
2 D-4078 E5 GL S
1 NC FC 0
J8 OP-ST-RC-3005 HCV-176 RC B
2 D 4078 E5 GL S
1 NC FC C
J8 OP-ST-RC-3005 HCV-176 RC 8
2 D-4078 ES GL 5
1 NC FC VPI 2YR Y
OP ST-RC-3006 51-176 SI C
2 210-130-2 DI CK C
12 0
SD RO*
E3 SS ST-SI-3017 HCV 177 RC B
2 D-4078 D5 GL 5
1 NC FC 0
J8 OP ST-RC 3005 HCV-177 RC B
2 D 4078 05 GL S
1 NC FC C
J8 OP-ST-RC-3005 HCV-177 RC B
2 D-4078 D5 GL S
1 NC FC VPI 2YR Y
3 B120F07001-2 E7 RL R
0.75 T
SP OM PE-ST VX-3004 HCV 178 RC B
2 D 4078 C5 GL 5
1 NC FC 0
J8 OP ST RC-3005 HCV-178 RC B
2 D 4078 C5 GL 5
1 NC FC C
2 D-4078 C5 GL 5
1 NC FC VPI 2YR Y
OP-ST-RC-3006 SA-178 SA C
3 B120F07001 2 E7 RL R
0.75 T
SP OM PE ST VX-3004 HCV 179 RC B
2 D 4078 C5 GL 5
1 NC FC 0
J8 OP-ST RC 3005 HCV 179 RC 8
2 D-4078 C5 GL 5
1 NC FC C
J8 OP-ST RC-3005 HCV 179 RC B
2 D-4078 C5 GL 5
1 NC FC VPI 2YR Y
OP-ST RC-30%
SA-179 SA C
3 B120F07001-2 C7 RL R
0.75 T
SP OM PE ST VX-3004 HCV-180 RC B
2 D-4078 E3 GL 5
1 NC FC 0
J8 OP-ST-RC-3005 HCV-180 RC B
2 D-4078 E3 GL S
1 NC FC C
J8 OP-ST RC 3005 HCV 180 RC B
2 D-4078 E3 GL 5
1 NC FC VPI 2YR Y
OP ST-RC-3006 SA 180 SA C
3 B120F07001 2 B7 RL R
0.75 T
SP OM PE ST VX-3004 CH 181 CH C
2 210-120 1 F7 RL R
15 T
SP OM PE-ST-VX 3002 HCV 181 RC B
2 D-4078 C3 GL 1
NC FC 0
J8 OP-ST RC 3005 HCV 181 RC B
2 D 4078 C3 GL 5
1 NC FC C
J8 OP-ST-RC-3005 HCV 181 RC B
2 D 4078 C3 GL S
1 NC FC VPI 2YR Y
2 210 120-1 D7 RL R
1.5 T
SP OM PE-ST-VX 3002 CH-183 CH C
2 210 120-1 B7 RL R
1.5 T
SP OM PE-ST VX 3002 SI 183 SI A
2 210 130 1 E6 GL H
2 NC L
LT 2YR SE-ST-SI-3005 R2 June 15,1995 Page 53 of 168 m
-~
r-m
_,_c
=
T 1
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NtDGER SYS CAT CLASS P&ID IETES TYPE TYPE SIZE
- POS POS REQ TEST FREQ TEST EXPT REMARKS P
SI-184 SI A
2 210 130-1 D6 GA H
6 NC L
LT 2YR SE-ST SI-3005 51 185 SI A
2 210-130 1 EB GL H
2 NC L
LT
'2YR APPDOIX J J
2 210 120-1 E7 CK C
2 0
FS Q
2 210-120 1 E7 CK C
2 C
FS Q
2 210-130-2 H5 RL R
15 T
SP OM PE ST VX 3009 CH 188 CH C
2 210 120 1 C7 CK C
2 0
FS Q
2 210 120-1 C7 CK C
2 C
FS Q
OP ST-CH-3003 51-188 SI C
2 210 130-2 H5 RL R
15 T
2 210 120-1 A7 CK C
2 0
FS Q
OP ST-CH-3003 CH 189 CH C
2 210-120-1 A7 CK C
2 C
FS Q
OP ST-CH-3003 51 189 SI C
2 210 130-2 H6 RL R
1.5 T
SP OM PE ST VX-3009 51-190 SI C
2 210 130-2 H7 RL R
1.5 T
210 130-2A D7 CK C
6 0
FS CS J9 OP-ST SI-3003 i
SI-194 51 A/C 1
210 130 2A 07 CK C
6 L
LT CS*
J9 PIV SE-ST SI 3015 51-195 SI A/C 1
210-130 2A 08 CK C
2 L
LT CS*
J9 PIV SE-ST SI-3015 51-195 SI A/C 1
210 130 2A DB CK C
2 0
FS RO J10 OP-ST-51 3007 51-1 %
SI C
1 210 130-2A D8 CK C
2 O
PS CS J11 OP-ST-SI-3014 SI-1%
SI C
1 210 130-2A DB CK C
2 0
FS RO J11 OP ST SI 3007 SA 197 SA 8
3 B120F07001 2 D3 DI A
1.5 NC FO O
ST Q
Y DG START ACCEPT OP-ST DG 0001 SA 197 SA B
3 B120F07001 2 D3 DI A
1.5 NC FO O
VPI 2YR Y
DG START ACCEPT OP-ST-DG 0001 SI 197 SI A/C 1
210 130 2A D6 CK C
6 L
LT CS*
PIV SE ST-SI 3015 51 197 S1 A/C 1
210-130-2A D6 CK C
6 0
2 210-120-1A B2 CK C
2
~0 PS Q
2 210 120-1A B2 CK C
2 0
FS RO J12 SE ST-CH-3003 CH 198 CH C
2 210 120-1A B2 CH C
2 C
+
3 B120F07001 2 C3 DI A
1.5 NC FO O
ST Q
Y DG START ACCEPT OP-ST-DG-0001 SA 198 SA B
3 B120F07001 2 C3 DI A
1.5 NC FO O
VPI 2YR Y
DG START ACCEPT OP ST DG 0001 SI-198 SI A/C 1
210 130 2A D6 CK C
2 0
FS RO J10 OP-ST SI-3007
]
210 130 2A D6 CK C
2 L
LT CS*
J10 PIV SE-ST SI 3015 SI-199 SI C
1 210 130 2A C7 CK C
2 0
PS CS J11 OP-ST-51-3014 SI 199 SI C
1 210-130-2A C7 CK C
2 0
FS RO J11 GP-ST SI 3007 51 200 SI A/C 1
210-130-2A D5 CK C
6 L
LT CS*
PIV SE-ST SI-3015 51 200 SI A/C 1
210-130-2A D5 CK C
6 0
FS C5 J9 OP ST-SI-3003 51 201 SI A/C 1
210 130-2A D5 CK C
2 L
LT CS*
PIV SE-ST-SI-3015 0
51 201 SI A/C 1
210 130 2A D5 CK C
2 0
FS RO J10 OP ST-SI-3007 R2 June 15,1995 Page 54 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORH FAIL TEST TYPE TEST VPI COE NiMER SYS CAT CLASS P&lD INATES TYPE TYPE SIZE
3 B120F07001-1 C3 CK C
0.25 C
FS Q
)
51 202 SI C
1 210-130-2A C5 CK C
2 0
PS CS J11 OP-ST SI-3014 57 202 SI C
1 210-130 2A C5 CK C
2 0
FS RO J11 OP-ST-SI-3007 TCV 202 CH A
1 210-120 1A E5 GL A
2 A
FC C
J13 OP-ST-01-3005 TCV 202 CH A
1 210-120 1A E5 GL A
2 A
FC L
LT 2YR APPENDIX J TCV 202 CH A
1 210 120 1A E5 GL A
2 NO FC VPI 2YR Y
1 210 120 1A CS CK C
2 0
PS Q
J12 OP ST-CH-3003 CH-203 CH C
1 210 120-1A CS CK C
2 0
FS RO J12 SE ST-CH 3003 SA 203 SA C
3 B120F07001 1 CS CK C
0.25 C
FS Q
DG START ACCEPT OP ST-DG-0001
210-130-2A D3 CK C
6 L
LT CS*
PIV SE ST-SI-3015 51 203 51 A/C 1
210-130 2A D3 CK C
6 0
FS CS J9 OP-ST-SI-3003 CH-204 CH C
1 210 120-1A AS CK C
2 O
PS Q
1 210 120 1A A5 CK C
2 0
FS RO J12 SE-ST CH 3003 HCV 204 CH A
2 210-120-2 A2 GL A
2 NO FC L
LT 2YR E5 APPENDIX J l
2 210-120-2 A2 GL A
2 NO FC C
J13 OP-ST CH-3005 HCV 204 CH A
2 210-120-2 A7 GL A
2 NO FC VPI 21R Y
OP ST VX-3009 l
51 204 SI A/C 1
210-130-2A D3 CK C
2 0
FS RO J10 OP-ST-SI-3007 SI 204 51 A/C 1
210-130-2A D3 CK C
2 L
LT CS*
1 210 120 1A B6 CK C
2 0
PS Q
1 210-120 1A B6 CK C
2 0
FS RO J14 SE-ST-CH 3003 SI 205 SI C
1 210-130 2A C4 CK C
2 0
PS CS J11 OP-ST-SI-3014 51 205 SI C
1 210-130-2A C4 CK C
2 0
FS RO J11 OP-ST SI-3007 HCV-206 CH A
2 210-120-1A El GL A
0.75 NO FC C
J15 OP-ST-CH-3005 HCV 206 CH A
2 210-120-1A El GL A
0.75 NO FC L
2 210-120 1A El GL A
0.75 NO FC VPI 2YR Y
210-130 2A F7 CK C
12 L
LT CS*
OP-ST-SI-3008 51 207 SI A/C 1
210-130-2A F7 CK C
12 C
FS CS*
E4 OP-ST-SI 3008 51 207 SI A/C 1
210-130 2A F7 CK C
12 0
FS RO E4 SIT DUMP SS-ST-SI 3015 51-208 SI A/C 1
210 130-2A C7 CK C
12 L
LT CS*
PIV OP ST-SI-3013 SI 208 SI A/C 1
210 130 2A C7 CK C
12 0
FS RO E4 SIT DlNP SS-ST SI-3015 51 208 St A/C 1
210 130 2A C7 CK C
12 C
FS CS*
E4 OP ST-SI 3013 S1-208 SI A/C 1
210-130 2A C7 CK C
12 0
PS C5 E4 OP ST SI 3003 51 209 SI C
2 210 130-28 E3 RL R
1 T
SP OM PE-ST-VX-3005 SI-211 SI A/C 1
210-130-2A F6 CK C
12 L
LT CS*
PIV OP ST SI 3008 51 211 St A/C 1
210 130-2A F6 CK C
12 C
FS CS*
E4 OP ST-SI-3008 R2 June 15,1995 Page 55 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE C00RD-VA 1E OPER UALVE NORM FAIL TEST TYPE TEST VPI CODE HUMBER SYS CAT CLASS P&ID IfMTES TYPE TYPE SIZE
210-130-2A F6 CK C
12 0
FS RO E4 SIT DUMP SS-ST-SI 3015 51 212 SI A!C 1
210 130-2A C6 CK C
12 C
FS CS*
E4 Op-ST-SI 3013 51 212 SI A/C 1
210 130-2A C6 CK C
12 L
LT CS*
PIV OP-ST SI-3013 51 212 SI A/C 1
210-130 2A C6 CK C
12 0
FS RO E4 SIT DlNP SS ST-SI-3015 51 212
$1 A/C 1
210 130 2A C6 CK C
12 0
PS CS E4 OP ST-SI 3003 SI-213 51 C
2 210-130-2B E6 RL R
1 T
SP OM PE-ST VX-3005 51 215 SI A/C 1
210-130-2A F4 CK C
12 C
FS CS*
E4 OP ST-SI 3008 51-215 SI A/C 1
210 130-2A F4 CK C
12 L
LT CS*
OP ST-SI-3008 SI 215 SI A/C 1
210-130-2A F4 CK C
12 0
FS R0 E4 SIT DUMP SS-ST-SI 3015 51-216 SI A/C 1
210 130-2A C4 CK C
12 C
FS CS*
E4 0P ST SI-3013 51-216 SI A/C 1
210-130 2A C4 CK C
12 L
LT CS*
PlV OP-ST SI-3013 51 216 SI A/C 1
210-130 2A C4 CK C
12 0
FS RO E4 SIT DUMP SS-ST SI 3015 51-216 51 A/C 1
210-130-2A C4 CK C
12 O
PS CS E4 OP-ST-SI-3003 SI-217 SI C
2 210-130 2 E6 RL R
1 T
SP OM PE ST VX-3005 FO-218 F0 C
3 M 262 1 B3 CK C
2 0
FS Q
2 210 120-1 C2 GA M
4 NO FAI C
J16 OP-ST-CH 3005 LCV 218 2 CH B
2 210 120-1 C2 GA M
4 NO FAI VPI 2YR Y
OP ST-VX-3009 LCV 218-3 CH B
2 210 120 1 E3 GA M
3 NC FAI O
J16 OP-ST CH-3005 LCV 216 3 CH B
2 210-120-1 E3 GA M
3 NC FAI VPI 2YR Y
OP ST-VX 3009 FO-219 F0 C
3 M 262 1 B3 CK C
2 0
FS Q
OP-ST FO 3002
)
51 219 SI A/C 1
210 130 2A F3 CK C
12 C
FS CS*
E4 OP-ST-SI 3008 S1 219 SI A/C 1
210 130 2A F3 CK C
12 L
LT CS*
PIV OP ST SI-3008 SI 219 SI A/C 1
210-130 2A F3 CK C
12
- } O FS RO E4 SIT DUMP SS ST SI 3015 RW 220 RW C
3 M-100-1 F3 RL R
0.75 T
SP OM PE ST-VX-3008 j
210-130-2A C3 CK C
12 0
FS RO E4 SIT DUW SS-ST SI-3015 SI-220 SI A/C 1
210-130 2A C3 CK C
12 C
FS CS*
E4 PIV OP-ST SI-3G13 51 220 SI A/C 1
210-130-2A C3 CK C
12 L
LT CS*
OP-ST-SI-3013 51-220 51 A/C 1
210-130 2A C3 CK C
12 0
PS CS E4 OP ST SI 3003 RW-221 RW C
3 M-100 1 E3 RL R
0.75 T
SP OM PE ST-VX-3008 51 221 SI C
2 210-130 2 E3 RL R
1 T
SP OM PE ST-VX 3005 RW-222 RW C
3 M-100-1 D3 RL R
0 75 T
SP OM PE-ST VX 3008 RW 223 RW C
3 M-100 1 C3 RL R
0.75 T
SP OM PE-ST VX 3008 HCV 238 CH B
1 210 120 1A D5 GL A
2 NO F0 C
ST Q
1 210 120 1A D5 GL A
2 NO FO O
ST Q
Y OP ST-CH-3001 HCV-238 CH B
1 210-120 1A C5 GL A
2 NO F0 VPI 2YR Y
OP ST-VX-3008 R2 June 15,1995 Page 56 of 168 k
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COURD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NlkEER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE
1 210-120-1A A5 GL A
2 NO FO O
ST Q
Y OP-ST-CH-3001 HCV 239 CH, B 1
210 120 1A A5 GL A
2 NO F0 C
ST Q
Y OP ST-CH-3001 HCV 239 CH B
1 210 120-1A A5 GL A
2 NO FO VPI 2YR Y
1 210-120-1A B5 GL A
2 NC FC C
J17 OP ST-CH 3005 HCV 240 CH B
1 210-120-1A B5 GL A
2 NC FC 0
J17 OP ST CH-3005 HCV-240 CH B
1 210-120-1A B5 SL A
2 NC FC VPI 2Y2 Y
M 259 2 P4 CK C
0.5 C
FS Q
M-259-2 B4 CK C
0.5 L
LT 2YR IC-ST-RW 3001 HCV 241 CH A
2 210-120 1A E5 CL A
0.75 NO FC L
LT 2YR APPENDIX J HCV 241 CH A
2 210-12C-1A E5 GL A
0.75 NO FC C
J15 OP-ST CH 3005 HCV 241 CH A
2 210-120 1A E5 GL A
0.75 NO FC VPI 2YR Y
M 259 2 B5 CK C
0.5 C
FS Q
M-259 2 B5 CK C
0.5 L
LT 2YR IC-ST-RW 3001 SW 242 SW A/C 3
M 259 2 B6 CK C
0.5 C
FS Q
M-259-2 B6 CK C
0.5 L
LT 2YR IC-ST RW-3001 SW 243 SW A/C 3
M 259-2 B7 CK C
0.5 C
FS Q
M-259-2 B7 CK C
0.5 L
LT 2YR IC-ST-RW 3001 HCV 247 CH B
2 210 120 1A C5 GL 5
2 NO F0 C
ST Q
Y OP ST-CH-3001 ICV 247 CH B
2 210 120-1A C5 GL 5
2 NO FO O
ST Q
2 210-120-1A C5 GL S
2 NO FD VPI 2YR Y
OP-ST-VX 3008 HCV-248 CH B
2 210 120-1A AS GL S
2 NO F0 C
ST Q
2 210 120-1A A5 GL 5
2 NO FO O
ST Q
2 210 120-1A 15 GL 5
2 NO FO VPI 2YR Y
1 210 120 1A B5 GL 5
2 NC FC 0
J17 OP ST CH-3005 HCV-249 CH B
1 210-120-1A B5 GL 5
2 NC FC C
J17 OP-ST CH-3005 HCV 249 CH B
1 210-120 1A B5 GL S
2 NC FC VPI 2YR Y
3 B120F07001 2 05 CK C
0.25 C
FS Q
DG START ACCEPT OP ST 0G 0002 SA 253 SA C
3 B120F07001-2 D5 CK C
0.25 C
FS Q
DG START ACCEPT OP ST-[G 0002 RW-254 RW A/C 3
M-100 1 C4 CK C
0.75 0
FS Q
- 3. M 100 1 E4 CK C
0.75 0
FS Q
M 100 1 D4 CK C
0.75 0
FS Q
2 210 121-1 D7 GL A
2 NO FC C
ST Q
2 210 121 1 D7 GL A
2 NO FC VPI 2YR Y
M-100-1 E5 CK C
0.75 0
FS Q
IC-ST-RW-3001 HCV-258 CH B
2 210 121 1 B5 GA M
3 NC FAI O
ST Q
f OP ST CH 3001 R2 June 15,1995 Page 57 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NUPEER SYS CAT CLASS P&lD INATES TYPE TYPE SIZE
2 210 121-1 BS CA M
3 NC FAI VPI 2YR Y
2 210-121-1 D4 GL A
2 NO FC C
ST Q
2 210-121-1 D4 GL A
2 NO FC VPI 2YR Y
2 210 121-1 B3 GA M
3 NC FAI O
ST Q
2 210-121-1 B3 GA M
3 NC FAI VPI 2YR Y
OP-ST-VX-3008 Of-268 CH B
2 210-121 2 B4 GA M
3 NC FAI O
J18 OP-ST-CH 3005 HCV 268 CH B
2 210-121 2 B4 GA M
3 NC FAI VP1 2YR Y
2 210 121-1 C7 GL A
3 A
FC C
ST Q
Y OP ST-CH-3001 FCV 269 CH B
2 210 121 1 C7 GL A
3 A
FC VPI 2YR Y
OP ST-VX-3008 MS 275 MS C
2 M-252-1 F8 RL R
6 T
SP RO SS-ST MS-3003 MS-276 MS C
2 M 252-1 F8 RL R
6 T
SP RO SS ST MS-3003 MS-277 MS C
2 M 252-1 F7 RL R
6 T
SP RO SS ST-MS 3003 MS-278 MS C
2 M-252-1 F7 RL R
6 T
SP RO SS-ST-MS-3003 MS 279 MS C
2 M-252 1 EB RL R
6 T
SP RO SS-ST-MS 3003 MS 280 MS C
2 M 252-1 E7 RL R
6 T
SP RO SS-ST-MS-3003 VA 280 VA A
2 M12 A8 BU H
4 LC L
LT 2YR APPENDIX J MS-281 MS C
2 M-252-1 E7 RL R
6 T
SP RO SS-ST MS 3003 MS 2B2 MS C
2 M-252-1 E6 RL R
6 T
SP RO SS-ST MS-3003 SA-282 SA C
3 B120F07001 1 B7 CK C
0.5 C
FS Q
2 M-40-1 G7 RL R
0.75 T
SP OH PE ST-VX 3007 AC 2B4 CCW C
2 M-40-1 G7 Ri R
0.75 T
SP OH PE-ST-VX-3007 AC 285 CCW C
2 M 401 F6 RL R
0.75 T
SP OH PE ST-VX 3007 SA 285 SA C
3 B120F07001 1 F7 CK C
05 C
FS Q
2 M 40-1 F5 RL R
0 75 T
SP OM PE ST VX-3007 VA-287 VA C
3 M-1 2 B6 RL R
2 T
SP OH PE-ST-VX-3010 SA 288 SA C
3 B120F07001 2 B7 CK C
0.5 C
FS Q
3 H-1-2 B5 RL R
2 T
SP CH PE-ST VX-3010 VA-289 VA A
4 LC L
LT 2YR APPENDIX J MS 291 MS C
2 M 252-1 F7 RL R
2.5 T
+
3 B120F07001-2 F7 CK C
0.5 C
FS Q
IC-ST SA 3001 MS 292 MS C
2 M-252-1 E7 RL R
2.5 T
SP RO SS ST-MS-3004 51-298 SI C
2 210-130 1 D3 RL R
1 T
SP OM PE ST-VX 3009 51-299 SI C
2 210-130-1 D4 RL R
1 T
SP OH PE-ST VX 3009 51 300 51 C
2 210-130-1 B4 CK C
2 0
FS Q
OP ST-SI 3008 51 301 51 C
2 210-130 1 D4 CK C
2 0
FS Q
OP ST-SI-3008 R2 June 15,1995 Page 58 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX-VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE l
NUPeER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE
- POS POS REQ TEST FREQ TEST EXPT REMMKS j
SI-302 SI C
2 210-130-1 F4 CK C
2 0
FS Q
2 210-130-1 E4 CK C
2 0
FS Q
OP-ST-SI 3008 51 304 SI C
2 210 130-1 A4 CK C
2 0
FS Q
YOP-ST SI-3008 51-306 SI A
2 210 130-1 D7 GA H
6 LC L
LT 2YR I
2 210 130-1 D6 GA M
2 NC FAI O
ST Q
Y OP-ST-SI-3001 l
l l
HCV 308 St B
2 210 130-3 D6 GA M
2 NC FAI VPI 2YR Y
OP ST-VX-3019 SI 309 SI C
2 210-130 1 DS RL R
1 T
51 310 SI C
2 210 130-1 D3 RL R
1 T
SP OM PE-ST VX-3009 HCV 311 SI B
2 210-130-2A C3 GL M
2 NC FAI O
ST Q
Y OP-ST-SI-3001 i
HCV 311 51 B
2 210-130 2A C3 GL M
2 NC FAI VPI 2YR Y
2 210-130 2A C4 GL M
2 NC FAI O
ST Q
Y OP-ST-SI-3001 i
HCV-312 SI B
2 210 130 2A C4 GL M
2 NC FAI VPI 2YR Y
2 210-130 2A CS GL M
2 NC FAI O
ST Q
2 210-130-2A C5 GL M
2 NC FAI WPI 2YR Y
OP-ST-VX-3018 HCV 315 51 B
2 210-130 2A C5 GL M
2 NC FAI O
ST Q
2 210-130-2A C5 GL M
2 NC FAI VPI 2VR Y
OP-ST-VX-3018 HCV 317 51 B
2 210 130-2A C8 GL M
2 NC FAI O
ST Q
2 210-130-2A C8 GL M
2 NC FAI VPI 2YR Y
OP-ST-VX-3018 i
210 130-2A C8 GL M
2 NC FAI O
ST Q
2 210 130-2A C8 GL M
2 NC FAI VPI 2YR Y
2 210-130-2A C6 GL M
2 NC FAI O
ST Q
Y OP-ST-SI-3001 HCV-320 SI B
2 210-130 2A C6 GL M
2 NC FAI VPI 2YR Y
2 210 130-2A C7 GL M
2 NC FAI O
ST Q
'Y OP ST SI ':001 HCV 321 SI B
2 210 130-2A C7 GL M
2 NC FAI VPI 2YR Y
2 210 130-3 E6 CK C
4 0
FS RO J20 OP-ST SI-3007 51 373 SI C
2 210 130-3 E6 CK C
4 C
FS RO J20 SE-ST-SI 3010 HCV-327 SI B
2 210-130 2A C3 GL h
4 NC FAI O
-Q Y
2 210 130 2A C3 GL M
4 NC FAI VPI 2YR Y
OP ST-VX-3018 HCV 329 SI B
2 210 130 2A C4 GL M
4 NC FAI O
ST Q
Y OP-ST-SI 3001 i
2 210 130 2A C4 GL M
4 NC FAI VPI 2YR Y
OP ST VX 3018-HCV-331 St B
2 210-130 2A C7 GL M-4 NC FAI O
ST Q
Y OP ST-SI 3001 HCV-331 51 B
2 210 130 2A C7 GL M
4 NC FAI VPI 2YR Y
OP-ST-VX 3018 i
2 210 130 2A C6 GL M
4 NC FAI O
ST Q
Y OP ST-SI-3001 HCV-333 SI B
2 210-130 2A C6 GL M
4 NC FAI VPI 2VR Y
3 M-10-2 C3 RL R
1 T
SP OM PE-ST-VX-3001 R2 June 15,1995 Page 59 of 168
TABLE 2 1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NLH3ER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE
- POS POS REQ TEST FREQ TEST EXPT REMARKS 51 342 51 A
2 210-130-1 E7 GL H
I LC L
LT 2YR SE ST-SI 3005 SI-343 SI C
2l210-130-3 D6 CK C
2 0
FS RO J11 OP-ST-CH-3006 HCV 344 SI B
2' 210 130 1 D8 BL A
B NC FO O
J21 OP ST SI-3002 HCV-344 SI B
2 210 130-1 DB BL A
8 NC F0 C
J21 OP-ST-SI-3002 HCV 344 51 B
2 210 130 1 D8 BL A
8 NC F0 VPI 2YR Y
OP ST VX 3019 NG ICV-344 52 NG C
2 C-4175 5 E2 RL R
0.75 T
SP OM PE-ST VX 3006 ICV 345 SI B
2 210 130 1 B8 BL A
8 NC F0 0
J21 OP-ST-SI-3002 lCV 345 SI B
2 210-130-1 DB BL A
8 NC F0 VPI 2YR Y
OP-ST-VX-3019 HCV 347 Si A
1 210-130-3 F7 GA M
10 LC FAI L
LT 2YR AFPENDIX J HCV 347 SI A
1 210-130-3 F7 GA M
10 LC FAI C
J22 OP ST-SI-3002 HCV-347 51 A
1 210-130-3 F7 GA M
10 LC FAI VPI 2YR Y
1 210-130-2A C2 GA M
12 LC FAI L
LT 2YR APPENDIX J HCV-348 St A
1 210-130 2A C2 GA M.
12 LC FAI C
J22 OP-ST-SI-3002 HCV-348 51 A
1 210-130 2A C2 CA M
12 LC FAI VPI 2YR Y
OP-ST-VX-3019 MS 351 MS C
3 M 252-1 E5 CK C
2 0
FS Q
3 M-252-1 E5 CK C
2 0
FS Q
3 M-10 2 D4 RL R
2 T
SP OM PE-ST-VX-3001 FCV 383 3 SI A
2 210-130-3 B7 BU M
24 NC FAI O
J40 OP ST-SI-3002
)
2 210 130-3 B7 BU M
24 NC FAI L
LT 2YR APPENDIX J HCV-383-3 SI A
2 210 130 1 01 BU M
24 NO F0 VPI 2YR Y
OP ST-VX-3018 HCV 383 4 SI A
2 210-130-3 B7 BU M
24 NC FAI O
J40 OP-ST-SI-3002 HCV 383-4 SI A
2 210-130-3 B7 BU M
24 NC FAI L
LT 2YR APPENDIX J HCV 383-4 SI A
2 210-130 1 D1 BU M
24 NO F0 VPI 2YR Y
2 210-130-1 D1 BU A
20 NO F0 C
J40 OP-ST-SI-3002 LCV 383 1 SI A
2 210 130-1 D2 BU A
20 NO FO VPI 2YR Y
2 210-130-1 D1 BU A
20 NO FO O
J40 OP-ST SI-3002 LCV-383-1 SI A
2 210-130-1 D1 BU A
20 NO F0 L
LT 2YR SE-ST-SI 3005 LCV-383-2 SI A
2 210-130-1 D2 BU A
20 NO FO O
J40 OP ST-SI 3002 LCV-383-2 SI A
2 210 130-1 D2 BU A
20 NO F0 C
J40 OP-ST-SI-3002 LCV-383-2 SI A
2 210-130 1 D2 BU A
20 NO F0 L
LT 2YR SE-ST SI-3005 LCV-383-2 51 A
2 210-130-1 D2 BU A
20 NO F0 VPI 2YR Y
OP-ST VX 3018 NG LEV-383 1-52 NG C
3 C-4175-5 E2 RL R
0.75 T
SP OM PE-ST-VX 3006 NG-LCV-383 2-52 NG C
3 C-4175-5 E2 RL R
0.75 T
SP OM PE ST YX-3006 HCV 385 SI A
2 210 130 1 F4 GL A
4 NO FO O
J34 OP-ST-SI 3006 HCV 385 SI A
2 210-130-1 F4 GL A
4 NO F0 C
J34 OP ST-SI-3002 R2 June 15,1995 Page 60 0f 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI C00C NUPBER SYS CAT CLASS PEIO INATES TYPE TYPE SIZE
- POS POS REQ TEST FREQ TEST EXPT PEMARKS HCV-385 SI A
2 210-130 1 F4 GL A
4 NO F0 L
LT 2YR SE-ST SI 3005 HCV 385 SI A
2 210 130-1 F4 GL A
4 NO FD VPI 2YR Y
2 210-130-1 F4 GL A
4 NO F0 C
J34 OP ST-SI-3002 HCV-386 SI A
2 210 130 1 F4 GL A
4 NO FO O
J34 OP ST-SI-3002 HCV 396 SI A
2 210 130-1 F4 GL A
4 NO F0 L
LT 2YR SE ST-SI-3005 HCV 386 SI A
2 210 130-1 F4 GL A
2YR Y
OP-ST-VX 3018 AC-391 CCW A/C 3
M10 SH. 2 B4 CK C
15 0
FS Q
SE-ST-CCW 3003 AC-391 CCW A/C 3
M10 SH. 2 B4 CK C
15 C
FS Q
SE ST-CCW-3003 AC-391 CCW A/C 3
M10 SH. 2 B4 CK C
15 L
LT Q
2 M 40-1 C7 BU A
B NO FO O
ST Q
Y OP ST-CCW-3005 HCV 400A COf B
2 M-40-1 C7 BU A
8 NO F0 C
ST Q
Y OP-ST-CCW-3005 l
HCV-400A CCW B
2 M 40-1 C7 BU A
8 NO FD VP1 2VR Y
OP ST-VX 3007 3-HCV 400A 52 NG C
3 C 4175 6 F2 RL R
0.25 T
2 M-40 1 B7 BU A
8 NO FD 0
ST Q
Y OP-ST CCW 3005 HCV-4008 CCW B
2 M-40-1 B7 BU A
8 NO F0 VPI 2YR Y
OP-ST-VX-3007 NG HCV 400B 52 NG C
3 C 4175 6 F2 RL R
0.25 T
HCV-400C CCW B
2 M 401 02 BL A
B NO FO O
ST Q
Y OP-ST-CCW-3005 HCV 400C CCW B
2 M-40-1 D2 BL A
B NO F0 C
ST Q
Y OP-ST-CCW 3005 HCV 400C CCW B
2 M 401 D2 BL A
B NO F0 VPI 2VR Y
OP-ST-VX 3007 HCV-4000 CCW B
2 M 40 1 B2 BU A
B NO FO O
ST Q
Y OP ST-CCW-3005 HCV 400D CCW B
2 N 401 B2 BU A
8 NO F0 VPI 2YR Y
OP-ST-VX-3007-HCV 401A CCW B
2 M-40 1 C7 BU A
B NO FO O
ST Q
Y OP-5T CCW-3005 HCV 401A CCW B
2 M 40 1 C7 BU A
8 NO F0 C
ST Q
Y OP-ST-CCW 3005 i
E HCV-401A CCW B
2 M-40 1 C7 BU A
8 NO FO VPI 2YR Y
OP-ST-VX-3007 T
NG-HCV 401A 52 NG C
3 C-4175 6 F2 RL R
0.25 HCV-401B CCW B
2 M-40-1 B7 BU A
8 NO FO O
ST Q
Y OP ST-CCW 3005 HCV-401B CCW B
2 M 40-1 B7 BU A
8 NO FO VPI 2YR Y
OP-ST-VX 3007 NG-HCV-4018-52 NG C
3 C-4175-6 F2 RL R
0.25 T
2 M-40 1 D3 BL A
8 NO FO O
ST Q
Y OP ST-CCW 3005 HCV 401C CCW B
2 M-40-1 D3 BL A
8 NO F0 C
ST Q
Y OP-ST-CCW-3005 HCV 401C CCW B
2 M-40-1 D3 BL A
B
, NO F0 VPI 2YR Y
2 M 401 B3 BU A
8 N0 FO O
ST Q
Y OP ST-CCW-3005 HCV 401P CCW b
2 M 401 B3 BU A
8 NO F0 VPI 2YR Y
2 M 401 C6 BU A
6 NO FD 0
ST Q
Y OP-ST CCW-3005 HCV-402A CCW B
2 M 401 C6 BU A
6 NO F0 C
ST Q
Y OP-ST-CCW 3005 R2 June 15,1995 Page 61 of 168 r
-m-
-__, =
. - = - - -
r m-
,,_-,m,
....,,.._mm
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CNE M. DEER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE
2 M-40-1 C6 BU A
6 NO F0 VPI 2YR Y
OP ST-VX-3007 PE ST-VX 3006 l
3-HCV-402A-52 NG C
3 C-4175-6 E2 RL R
0.25 T
2 M 40-1 B6 BU A
6 NO FO O
ST Q
Y OP ST-CCW-3005 HCV 402B CCW B
2 M-40 1 B6 BU A
6 NO F0 VPI 2YR Y
OP ST VX-3007 T
3-HCV 4028 52 NG C
3 C-4175-6 E2 RL R
0.25 HCV-402C CCW B
2 M-40 1 D4 BL A
6 NO FO O
ST Q
Y OP ST CCW 3005 KCV 402C CCW B
2 M 401 D4 BL A
6 NO F0 C
ST Q
Y OP ST-CCW-3005 HCV-402C CCW B
2 M-40 1 D4 FL A
6 NO F0 VPI 2YR Y
OP ST-VX-3007 HCV-4020 CCW B
2 M 401 B4 BU A
6 NO FO O
ST Q
Y OP-ST-CCW-3005 HCV-402D CCW B
2 M-40 1 D4 BL A
6 NO F0 VPI 2YR Y
OP ST-VX-3007 HCV 403A CCW B
6 NO FO O
ST Q
Y OP ST-CCW-3005 HCV-403A CCW B
2 M 401 C5 BU A
6 NO F0 C
ST.
Q Y
OP ST-CCW-3005 TV 403A CCW B
6 NO F0 VPI 2YR Y
OP ST-VX-3007 3 HCV 403A 52 NG C
3 C-4175-6
'E2 RL R
0.25 T
2 M 40-1 85 BU A
6 NO FD 0
ST Q
Y OP ST-CCW-3005 HCV-4038 CCW B
2 M-40-1 BS BU A
6 NO F0 VPI 2VR Y
OP-ST-VX-3007 3 HCV-4038 52 NG C
3 C-4175 6 E2 RL R
0.25 T
HCV-403C CCW B
2 M 401 D4 BL A
6 NO FD 0
ST Q
Y OP ST-CCW-3005 HCV-403C CCW B
2 M-40-1 D4 BL A
6 NO F0 C
ST Q
Y OP-ST CCW 3005 HCV-403C CCW B
2 M 401 D4 BL A
6 NO F0 VPI 2YR Y
2 M-40-1 B4 BU A
6 NO FO O
ST Q
Y OP ST CCW 3005 OP-ST-VX 3007 HCV 4030 CCW B
2 M-40-1 B4 BU A
6 NO F0 VPI 2YR Y
2 M-40 3 C6 GL A
3 NO FC C
J23 OP-ST CCW-3004 HCV-425A CCW A
2 M-40-3 C6 GL A
3 NO FC L
LT 2YR APPE W IX J
2 M-40-3 C6 GL A
3 NO FC VPI 2YR Y
2 M-40-1 DI GL A
3 NO FC L
LT 2YR APPE E IX J l
2 M-40-1 D1 GL A
3 NO FC C
J23 OP-ST-CCW 3004 HCV-4258 CCW A
2 M 40-1 D1 GL A
3 NO FC VPI 2YR Y
2 M 40 3 B5 GL A
3 NO FC C
J23 OP-ST CCW 3004 HCV 425C CCW A
2 M 40 3 B5 GL A
3 NO FC L
LT 2YR APPE WIX J j
2 M-40 3 B5 GL A
3 NO FC VPI 2YR Y.
2 M 40-3 B5 GL A
3 NO FC L
LT 2YR APPEEIX J l
2 M-40 3 B5 GL A
3 NO FC VPI 2VR Y
2 M-40-3 B5 GL A
3 NO FC C
J23 OP ST-CCW 3004 HCV-43BA CCW A
2 M-40 2 FB GL A
6 NO F0 C
J24 OP ST-CCW-3004 R2 June 15,1995
. Page 62 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALW N(RM FAIL TEST TYPE TEST VPI CE)E LOSER SYS CAT CLASS P&lD INATES TYPE TYPE SIZE
- POS PDS REQ TEST FREQ TEST EXPT REMARKS APPE WIX J l
EV 438A CCW A
2 M-40-2 F8 GL A
6 NO F0 L
2 M-40-2 F8 GL A
6 NO FO O
J24 OP-ST-CCW-3004 HCV 438A CCW A
2 M-40-2 FB GL A
6 NO F0 VPI 2VR Y
2 M-40-1 A6 GL A
6 NO FD 0
ST C5 Y
J24 OP ST-CCW 3004 HCV 4388 CCW A
2 M-40 1 A6 GL A
6 NO FD L
LT 2YR APPE WlX J l
2 M-40 1 A6 GL A
6 NO F0 C
J24 OP ST-CCW-3004 HCV 438B CCW A
2 M-40-1 A6 GL A
6 NO F0 VPI 2YR Y
OP-ST VX 3006 NG HCV 4388 52 NG C
3 C-4175-6 D2 RL R
0.25 T
2 M-40 2 F2 GL A
6 NO F0 C
J24 OP ST CCW 3004 HCV 438C CCW A
2 M-40-2 F2 GL A
6 NO FD L
LT 2YR APPENDIX J l
2 M-40 2 F2 GL A
6 NO FO O
ST C5 Y
J24 OP ST-CCW 3004 HCV 438C CCW A
2 M-40-2 F2 GL A
6 NO FD VPI 2YR Y
2 M-40-1 A3 GL A
6 NO F0 '
C
J24 OP-ST CCW-3004 HCV-4380 CCW A
2 M-40-1 A3 GL A
6 NO FD L
LT 2YR APPENDIX J l
2 M 40-1 A3 GL A
6 NO FO O
J24 OP ST-CCW-3004 HCV-4380 CCW A
2 M-40-1 A3 GL A
6 NO F0 VPI 2YR Y
OP-ST VX 3006 NG-HCV 438D-52 NG C
3 C-4175 6 D2 RL R
0.25 T
SP CM PE-ST-VX 3006 HCV-467A CCW A
2 M 40-3 E3 GL A
1.5 MO FC L
LT 2VR APPEICIX J -
HCV-467A CCW A
2 M-40-3 E3 GL
-A 1.5 NO FC C
ST Q
Y OP ST-CCW 3004 HCV-467A CCW A
2 M 40-3 E3 GL A
1.5 NO FC VPI 2YR Y
2 M 401 A3 GL A
1.5 NO FC L
LT 2YR APPEEIX J HCV 467B CCW A
2 M-40-1 A3 GL A
1.5 NO FC C
ST Q
Y OP ST CCW 3004-HCV 467B CCW A
2 M-40-1 A3 GL A
1.5 MO FC VPI 2YR Y
OP-ST VX 3006 APPEWIX J HCV 467C CCW A
2 M-40 3 El GL A
1.5 NO FC L
2 M 40-3 El GL A
1.5 NO FC C
ST Q
Y OP ST CCW-3004
+
HCV-467C CCW A
2 M-40 3 El GL A
1.5 NO FC VPI 2YR Y
OP 5T-VX-3006 3
HCV-467D CCW A
2 M-40 1 A2 GL A
1.5
- NO FC C
ST Q
Y OP ST-CCW 3004 HCV-467D CCW A
2 M 40 1 A2 GL A
1.5 NO FC L
LT 2YR APPE EIX J HCV-467D CCW A
2 M-40-1 A2 GL A
1.5 NO FC VPI 2YR Y
1 210 120 1A BS CK C
2 0
PS CS J11 SE ST CH 3003 CH-469 CH C
1 210-120 1A B5 CK C
2 0
FS RO J11 OP ST CH-3003 EV 474 CCW B
3 M-10 3 F8 GL A
2 NO FO O
ST Q
Y OP-ST-CCW-3001 HCV 474 CCW B
3 M-10 3 FB GL A
2 NO F0 VPI 2YR Y
OP ST-VX-3006 EV-478 CCW B
3 M 10 3 D2 BU A
8 NO FD C
ST Q~
Y OP-ST-CCW-3001 HCV-478 CCW B
3 M 10-3 D2 BU A
B NO FO O
ST Q
Y OP-ST-CCW 3001-I R2 June 15,1995 Page 63 of 168 -
t
.,_.=m.m.
.. ~. -.,... - _,. -,
.-.r.---
..~~..._._._,--_4..-
.,.-m 4
m
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE IU EER SYS CAT CLASS P&lD INATES TYPE TYPE SIZE
- POS POS REQ TEST FREQ TEST EXPT REME5 HCV-478 CCW B
3 M-10 3 D2 BU A
8 NO F0 VPI 2YR Y
3 M-10-3 C6 BU A
14 NO FO O
ST Q
Y OP-ST CCW 3001 HCV-480 CCW B
3 M-10-3 C6 BU A
14 NO F0 VPI 2YR Y
OP-ST-VX 3005
.3-HCV-480 52 NG C
3 C-4175-6 B2 RL R
0.25 T
SP OM PE-ST VX-3006 HCV-481 CCW B
3 M-10-3 B7 BU A
14 NO FO O
ST Q
Y OP-ST-CCW-3001 HCV-481 CCW B
3 M 10 3 B7 BU A
14 NO F0 VPI 2YR Y
OP-ST VX 3005 G HCV 481 52 NG C
3 C 4175-6 B2 RL R
0.25 T
SP OH PE-5T-VX 30%
14 E
FO O
J41 OP-ST-RW 3003 HCV-482A RW B
3 M-10-3 05 BU A
14 NC F0 VPI 2YR Y
3 M 10-3 A4 BU A
14 NC FO O
J41 OP-ST-RW 3003 HCV-4828 RW B
3 M 10-3 A4 BU A
14 NC F0 VPI 2VR Y
3 M 10-3 B7 BU A
14 NC FO O
J41 OP-ST-RW-3003 HCV-483A RW B
3 M 10 3 B7 BU A
14 NC F0 VPI 2YR Y
OP-ST-VX 3017 HCV-4838 RW B
14 NC FO O
J41 OP ST-RW-3003 HCV 483B RW B
14 NC F0 VPI 2YR Y
OP-ST-VX-3017 HCV-484 CCW B
3 M-10 3 B4 BU A
14 NO FO O
ST Q
Y OP-ST CCW 3001 HCV-484 CCW B
3 M 10-3 B4 BU A
14 NO F0 VPI 2YR Y
OP-ST VX-3005 6 -485 CCW B
3 M 10-3 A5 BU A
14 NO FO O
ST Q
Y OP-ST-CCW 3001 HCV 485 CCW B
3 M-10-3 A5 BU A
14 NO F0 VPI 2YR Y
OP-ST VX 3005 HCV-489A CCW B
3 M 10 3 B2 BU A
10 NO FO O
ST Q
Y OP-ST-CCW 3001 HCV 489A CCW B
3 M-10-3 B2 BU A
10 NO F0 VPI 2YR Y
OP-ST-VX-3005 HCV-4898 CCW B
3 M-10 2 A6 BU A
10 NO F0 0
ST Q
Y OP ST-CCW-3001 HCV-489B CCW B
3 M 10-2 A6 BU A
10 NO F0 VP1 2YR Y
3 M 10 3 B2 BU A
10 NO FO O
ST Q
Y OP-ST-CCW-3001 HCV-490A CCW B
3 M 10-3 B2 BU A
10 NO F0 VPI 2YR Y
3 M-10-2 A6 BU A
10 NO FO O
ST Q
Y OP ST-CCW-3001 HCV-4908 CCW B
3 M-10 2 A6 BU A
10 NO F0 VPI 2YR Y
OP ST-VX 3005 j
3 M-10 3 C2 BU A
10 NO FO O
ST Q
Y OP-ST CCW-3001 HCV-491A CCW B
3 M 10-3 C2 BU A
10 NO F0 VPI 2VR Y
OP ST-VX-3005 HCV 491B CCW B
3 M-10 2 86 BU A
10 NO FO O
ST Q
Y OP-ST-CCW-3001 HCV 491B CCW B
3 M 10-2 B6 BU A
10 NO F0 VPI 2YR Y
OP ST-VX-3005 HCV-492A CCW B
3 M-10-3 C2 BU A
10 NO FO O
ST Q
Y OP ST CCW 3001 HCV 492A CCW B
3 M 10-3 C2 BU A
10 NO F0 VPI 2YR Y
OP-ST-VX-3005 l
HCV-4928 CCW B
3 M-10 2 C6 BU A
10 NO FO O
ST Q
Y OP-ST CCW-3001 HCV-492B CCW B
3 M 10-2 C6 BU A
10 NO F0 VPI-2YR Y
OP-ST-VX 3005 l
R2 June 15,1995 Page 64 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CE)E NUmER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE
- POS POS REQ TEST FREQ TEST EXPT REMARKS HCV 500A WD A
2 M62 A6 DI A
4 NO FC C
ST Q
Y OP-ST-WDL 3001 l
HCV 500A WD A
2 M-6-2 A6 DI A
4 NO FC L
LT 2YR APPENDIX J HCV-500A WD A
2 M 6-2 A6 DI A
4 NO FC VPI 2YR Y
OP-ST-VX-3025 HCV 5008 WD A
2 M-6 2 A6 DI A
4 NO FC C
ST Q
Y OP ST-WDL-3001 HCV 5008 WD A
2 H-6 2 A6 DI A
4 NO FC L
LT 2YR APPENDIX J l
HCV 5000 WD A
2 M62 A6 DI A
4 NO FC VPI 2YR Y
OP-ST vX-3025 l
HCV 506A WD A
2 M-7-1 A6 DI A
2 NO FC L
LT 2YR APPENDIX J HCV 506A WD A
2 M71 A6 DI A
2 NO FC C
ST Q
Y OP ST WDL-3001 HCV 506A WD A
2 M-7 1 A6 DI A
2 NO FC VPI 2YR Y
OP-ST-VX-3025 HCV 5068 WD A
2 M 7-1 A6 DI A
2 NO FC L
LT 2YR APPENDIX J
)
HCV-5068 WD A
2 M-7-1 A6 DI A
2 NO FC C
ST Q
Y OP ST-WDL-3001 HCV-5068 WD A
2 M71 A6 DI A
2 NO FC VPI 2YR Y
2 M 98-5 F7 DI A
3 NO FC C
ST Q
Y OP ST-WDL-3001 MCV-507A WD A
2 M-98 3 F7 DI A
3 NO FC L
LT 2YR APPENDIX J l
HCV-507A WD A
2 M-98 3 F7 DI A
3 NO FC VPI 2YR Y
OP-ST-VX-3025 HCV 507B WD A
2 M 98-3 F7 DI A
3 NO FC C
ST Q
Y OP-ST-WDL-3001 HCV 507B WD A
2 M-98-3 F7 DI A
3 NO FC L
LT 2YR APPENDIX J j
HCV-5078 WD A
2 M 98-3 F7 DI A
3 NO FC VPI 2YR Y
OP-ST-VX 3025 HCV 508A WD A
2 M-98-3 C7 DI A
0.5 NO FC L
LT 2YR APPENDIX J HCV 508A WO A
2 M-98-3 C7 DI A
0.5 NO FC C
ST Q
Y OP ST WDL-3001 HCV-508A WD A
2 M-98-3 C7 DI A
0.5 NO FC VPI 2YR Y
OP-ST-VX-3025
)
HCV-5088 WD A
2 M 98-3 C6 DI A
0.5 NO FC L
LT 2YR APPENDIX J HCV 508B WD A
2 M 98-3 C6 DI A
0.5 NO FC C
ST Q
Y OP-ST-WDL-3001 HCV 5088 WD A
2 M-98 3 C6 DI A
0.5 NO FC VPI 2YR Y
OP-ST-VX 3025 HCV-509A WD A
2 M-98 3 B7 DI A
0.5 NO FC L
LT 2YR APPENDIX J l
HCV 509A WD A
2 M 98-3 B7 DI A
0.5 NO FC C
ST Q
Y OP ST-WDL-3001 HCV 509A WD A
2 M 98-3 B7 DI A
0.5 NO FC VPI 2YR Y
OP-ST-VX 3025 HCV 509B WD A
2 M 98-3 B6 DI A
0.5 NO FC C
ST Q
Y OP-ST-WDL 3001 HCV 5098 WD A
2 M-98-3 B6 DI A
0.5 NO FC L
LT 2YR APPENDIX J HCV 5098 WD A
2 M 98 3 B6 DI A
0.5 NO FC VPI 2YR Y
OP ST-VX 3025 CA 555 CA A
2 M-13 F3 CA H
4 NO L
LT 2YR APPEEIX J FL 658 AFW C
3 M 254 2 D5 CK C
1.5 C
E Q
MANUALLY EXERCISE OP ST-AW-30%
3 M-254 2 D5 CK C
1.5 0
E Q
MANUALLY EXERCISE OP-ST-AFW-3006 l
W 672 AW C
3 M 253 4 B6 CK C
2 0
FS Q
SE-ST-AW 30%
A/HCV-742 VA A
2 M-1-2 DB DI A
1 NO F0 L
LT 2YR APPEE!X J R2 June 15,1995 Page 65 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE HlNBER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE
- POS POS REQ TEST FREQ TEST EXPT ret %RKS B/HCV 742 V4 A
2 M-1-2 DB DI A
1 NO F0 L
LT 2YR APPENDIX J C/HCV-742 VA A
2 M12 08 DI A
1 NO F0 L
LT 2YR APPENDIX J 0/HCV 742 VA A
2 M 1-2 08 DI A
1 NO FD L
LT 2YR APPEn0!X J PCV 742A VA A
2 M-1-1 02 BU A
42 A
FC L
LT 2YR APPENDIX J PCV 7428 VA A
2 M-1-2 C7 BU A
42 A
FC L
LT 2YR APPENDIX J PCV 742C VA A
2 M-1-1 C2 BU A
42 A
FC L
LT 2YR APPENDIX J PCV 742D VA A
2 M-1 2 B8 BU A
42 A
FC L
LT 2YR APPENDIX J PCV 742E VA A
2 M-1 1 F2
't A
1 A
FC L
LT 2YR APPENDIX J PCV 742E VA A
2 M 1-1 F2 A
1 NO FC VPI 2YR Y
2 M-1-1 F2 A
1 A
FC C
ST Q
2 M-1-2 E8 Da A
1 A
FC L
LT 2YR APPENDIX J PCV 742F VA A
2 M-1 2 E8 DI A
1 A
FC C
ST Q
2 M-1 2 E8 DI A
1 NO FC VPI 2YR Y
OP ST-VX-3024 PCV 742G VA A
2 M-1-1 E2 DI A
1 A
FC C
ST Q
Y OP-ST-VA-3001 PCV-742G VA A
2 M 1-1 E2 DI A
1 A
FC L
LT 2YR APPENDIX J FCV-742G VA A
2 M-1-1 E2 DI A
1 NO FC VPI 2YR Y
OP ST-VX-3024 PCV-742H VA A
2 H-1 2 EB DI A
1 NO FC C
ST Q
2 M-1 2 E8 DI A
1 NO FC L
LT 2YR APPENDIX J PCV-742H VA A
2 M-1 2 E8 DI A
1 NO FC VPI 2YR Y
OP-ST-VX 3024 HCV-746A VA A
2 M11 D2 BL A
2 NC FC L
LT 2YR APPENDIX J HCV 746A VA A
2 M-1 1 D2 BL A
2 NC FC C
ST Q
2 M11 D2 BL A
2 NC FC VPI 2YR Y
OP ST-VX-3024 HCV-746B VA A
2 M-1 2 C7 BL A
2 NC FC C
ST Q
2 M-1-2 C7 BL A
2 NC FC L
LT 2VR APPE!0IX J HCV-7468 VA A
2 M-1 2 C7 BL A
2 NC FC VPI 2YR Y
2 M-1 2 B8 GL S
1 NC FC L
LT 2YR APPENDIX J HCV B20A VA A
2 M-1-2 B8 GL 5
1 NC FC C
ST Q
Y OP-ST VA-3001 HCV-820A VA A
2 M-1-2 Ba GL S
1 NO FC VPI 2YR Y
OP-ST-VX 3024 HCV-8208 VA A
2 M-1-1 C2 GL S
1 NC F0 C
ST Q
Y OP-ST-VA-3001 HCV-8208 VA A
2 M 1-1 C2 GL 5
1 NC FO O
ST Q
2 H11 C2 GL S
1 NC F0 L
LT 2YR APPENDIX J HCV-8208 VA A
2 M-1-1 C2 GL S
1 NO F0 VPI 2YR Y
2 M-1-2 A8 G-5 1
NC FC C
ST Q
Y OP ST-VA-3001 HCV 821A VA A
2 M 1-2 A8 GL 5
1 NC FC L
LT ZYR APPENDIX J HCV 821A VA A
2 M-1-2 AB GL S
1 NO FC VPI 2YR Y
OP-ST VX 3024 R2 June 15,1995 Page 66 of 168
=
x A
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NUPSER SYS CAT CLASS P&IO INATES TYPE TYPE SIZE
2 M 1-1 A2 GL 5
1 NC F0 C
ST Q
2 M-1-1 A2 GL '
S 1
NC FO O
ST Q
2 M 1-1 A2 GL 5
1 NC FD L
LT 2YR APPEWIX J-HCV 8218 VA A
2 M-1 1 A2 GL S
1 NO F0 VPI 2YR Y
2 M 1-1 B2 BU A
4 NC F0 C
ST Q
Y OP-ST VA 3001 l
EV 881 VA A
2 M11 B2 BU A
4 NC FO O
ST Q
Y OP-ST-VA-3001 I
2 M-1-1 B2 BU A
4 NC F0 L
LT 2YR APPEEIX J l
HCV-881 VA A
2 M-1 1 B2 BU A
4 NC FC VPI 2YR Y
2 M-1-1 B2 BU A
4 NC FD 0
ST Q
2 M-1 1 B2 BU A
4 NC F0 C
ST Q
2 M 1-1 B2 BU A
4 NC FD L
LT 2YR APPEWIX J HCV-882 VA A
2 M11 B2 BU A
4 NC F0 VPI 2YR Y
2 M 1-1 C2 PG A
1 NC F0 L
LT 2VR APPENDIX J EV-883A VA A
2 M-1-1 C2 PG A
1 NC F0 C
ST Q
2 M-1-1 C2 PG A
1 NC F0 VPI 2YR Y
2 H11 C2 PG A
1 NC FD 0
ST Q
2 M-1-2 B8 GL S
1 NC FC L
LT 2YR APPEWIX J HCV 8838 VA A
2 M-1 2 B8 GL 5
1 NC FC C
ST Q
Y OP ST-VA-3001 HCV-8838 VA A
2 M 1-2 B8 GL 5
1 NC FC VPI 2YR Y
OP ST-VX-3024 HCV 884A VA A
2 M 1-1 C2 GL A
1 NC FD 0
ST Q
Y OP ST-VA-3001 HCV-884A VA A
2 M-1-1 C2 GL A
1 NC F0 C
ST Q
2 M-1-1 C2 GL A
1 NC FD L
LT 2YR APPE WIX J HCV-884A VA A
2 M 1-1 C2 GL A
1 NC F0 VPI 2YR Y
OP ST VX-3024 l
HCV-8848 VA A
2 M-1 2 B8 GL 5
1 NC FC L
LT 2YR APPEWIX J HCV 8848 VA A
2 H-1-2 B8 GL 5
1 NC FC C
ST Q
2 M12 B8 GL S
1 NC FC VPI 2YR Y
2 M 252 1 F6 CK A
28 NO FC C
J26 OP-ST MS-3002 HCV 1041A MS B
2 M-252 1 F6 CK A
28 NO FC VPI 2YR Y
OP-ST-VX-3013 EV-10418 MS C
2 M 252-1 F6 CK C
28 C
SD RO*
J39 SE ST-MS-3003 HCV 1041C MS B
2 M-252-1 F6 GL M
2 NC FAI C
J27 OP-ST MS-3002 HCV 1041C MS B
2 M 252-1 F6 GL M
2 NC FAI VPI 2YR Y
OP ST-VX 3013-HCV-1042A MS B
2 M 252 1 E6 CK A
28 NO FC C
J26 OP-ST-MS-3002 HCV 1042A MS B
2 M-252-1 E6 CK A
28 NO FC VPI 2YR Y
OP-ST-VX-3013 HCV-1042B MS C
2 M-252-1 E6 CK C
28 C
- 50 RO*
J39 SE ST MS 3003 HCV 1042C MS B
2 M-252 1 E6 GL M
2 NC FAI C
J27 OP-ST-MS-3002 R2 June 15,1995 Page 67 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL.
TEST TYPE TEST VPI CODE NUIEER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE
- POS POS REQ TEST FREQ TEST EXPT PIMMKS HCV-1042C MS B
2 M-252-1 E6 GL M
2 NC FAI VPI 2YR Y
OP-ST VX-3013 YCV 1045 MS B
3 M-252 1 C5 GL A
2 NC FO O
ST Q
Y SE-ST-AFW-3006 YCV 1045 MS B
3 M 252 1 C5 GL A
2 NC F0 VPI 2YR Y
OP-ST VX 3001 70V-1045A MS B
2 M 252-1 F5 GL A
2 NC FO O
ST Q
Y OP-ST-MS-3001 YCV 1045A MS B
2 M 252-1 F5 GL A
2 NC F0 C
ST Q
Y OP ST MS 3001 YCV-1045A MS B
2 M-252-1 F5 GL A
2 NC F0 VPI 2YR Y
OP-ST-VX-3012 YCV-1045B MS B
2 M-252-1 E5 GL A
2 NC FO O
ST Q
Y OP-ST-MS-3001 7CV 10458 MS B
2 M 252-1 ES GL A
2 NC F0 C
ST Q
Y OP-ST-MS 3001 YCV 1045B MS B
2 M 252-1 E5 GL A
2 NC F0 VPI 2YR Y
OP-ST-VX-3012 HCV-1103 FM B
N M-253-1 C3 GA M
16 NO FAI C
J28 OP-ST-FM 3002 HCV 1103 FW B
N M-253-1 C3 GA M
16 NO FAI VPI 2YR Y
N M 253-1 E3 GA M
16 NO FAI C
J28 OP ST-FW 3002 HCV-1104 FW B
N M 253 1 E3 GA M
16 NO FAI VPI 2YR Y
N H-253-1 D3 GL A
6 NC FC C
J28 OP-ST-FW 3002 HCV 1105 FW B
N M-253-1 D3 GL A
6 NC FC VPI 2YR Y
OP-ST-VX 30ll HCV-1106 FW B
N M-253-1 E3 GL A
6 NC FC C
J28 OP ST-FW-3002 HCV 1106 FW B
N M 253 1 E3 GL A
6 NC FC VPI 2YR Y
OP ST-VX-3011 HCV-1107A AFW B
2 M 253-1 FB GL A
3 NC FO O
ST Q
Y OP ST-AFW-30%
HCV-1107A AFW B
2 M 253-1 FB GL A
3 NC FO VPI 2YR Y
2 M 253 4 E8 GL A
3 NC FO O
ST Q
Y OP ST AFW-3006 HCV 1107B AFV B
2 M-253-4 EB GL A
3 NC F0 VPI 2YR Y
OP-ST-VX-3002 HCV-1108A AFW B
2 M-253 4 F7 GL A
3 NC FO O
ST Q
Y OP-ST AFW 3006 HCV-1108A AFW B
2 M-253 4 F7 GL A
3 NC FO VPI 2YR Y
OP ST-VX-3002 HCV 11088 AFW B
2 M 253-4 E7 GL A
3 NC FO O
ST Q
Y OP-ST AFW-3006 HCV 11088 AFW B
2 M 253-4 E7 GL A
3 NC F0 VPI 2YR Y
OP-ST-VX-3002 FCV-1368 AFW B
3 M 253-4 C6 GL A
1 A
FO O
ST Q
Y OP-ST-AFW 3006 FCV-1368 AFW B
3 M-253 4 C6 GL A
1 A
FO VPl 2YR Y
OP ST-VX-3002 FCV 1369 AFW B
3 M-253-4 B5 GL A
2
'A F0 VPI 2YR Y
OP-ST-VX-3002 6
3 M 253 4 B5 GL A
2 A
FO O
ST Q
Y OP ST-AFW-3006 HCV-1384 AFW B
3 M-253-4 D7 GA M
4 NC FAI O
ST Q
Y OP ST-AFW-3006 HCV-1384 AFW B
3 M-253-4 D7 GL M
4 NC FAI VPI 2YR Y
2 M 253-1 D3 GA M
16 NO FAI C
ST CS Y-J28 OP ST FW-3002 HCV 1385 FW B
2 M-253-1 D3 GA M
16 NO FAI VPI 2YR Y
OP-ST-VX-3011 HCV-1386 FW B
2 M 253-1 C6 GA M
16 NO FAI C
'Y J28 OP-ST FW-3002 j
2 M-253-1 C6 G%
M 16 NO FAI VPI 2YR Y
OP-ST-VX 3011 R.2 June 15,1995 Page 68 of 168
~
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NUEER SYS CAT CIASS P&!D INATES TYPE TYPE SIZE
2 M-253-1 C3 GL A
2 NO FC C
ST Q
Y OP-ST-FW-3002
)
2 M-253 1 C3 GL A
2 NO FC VPI 2YR Y
OP-ST VX 3011 HCV-13878 FW B
2 M-253 1 B3 GL A
2 NO FC C
ST Q
Y OP-ST FW-3002
)
2 M 253 1 B3 GL A
2 NO FC VPI 2YR Y
OP-ST-VX 3011 HCV-1388A FW 8
2 M 253-1 C8 GL A
2 NO FC C
ST Q
Y OP-ST-FW-3002 l
2 M 253-1 C8 GL A
2 NO FC VPI 2YR Y
OP-ST VX 3011 l
HCV-13888 FW B
2 M.253 1 B8 GL A
2 NO FC C
ST Q
Y OP ST-FW 3002 HCV 1388B FW B
2 M-253 1 B8 GL A
2 NO FC VPI 2YR Y
OP ST-VX-3011 FW 1443 FW C
3 M-253-4 B5 RL R
0 75 T
FD-1444 FW C
3 M-253-4 B5 RL R
0 75 T
SP OM PE-ST VX-3003 FM-1525 AFW C
3 M 253-4 B4 RL R
0.75 T
SP OM*
E6 PE-ST VX 3003 HCV-1559A DW A
2 M 5-2 ES DI A
2.5 NC FC L
LT 2YR APPEEIX J HCV 1559A DW A
2 M-5 2 E5 DI A
2.5 NC FC C
ST Q
Y OP ST-DW-3001 HCV-1559A DW A
2 M-5 2 E5 DI A
2.5 NC FC VPI 2YR Y
OP-ST VX-3010 HCV-15598 DW A
2 M-5-2 E5 DI A
2.5 NC FC L
LT 2YR APPENDIX J l
HCV-15598 DW A
2 M-5 2 ES DI A
2.5 NC FC C
ST Q
Y OP-ST-DW-3001 HCV-15598 DW A
2 M-5 2 E5 DI A
2.5 NC FC VPI 2VR Y
2 M52 A4 DI A
2 NC FC L
LT 2YR APPE E IX J l
2 M 5-2 A4 DI A
2 NC FC C
ST Q
Y OP-ST DW-3001
2 M-5 2 A4 DI A
2 NC FC VPI 2YR Y
OP-ST VX-3010 HCV-15608 DW A
2 M-5-2 A4 DI A
2 NC FC C
ST Q
Y OP ST-DW-3001 HCV 15608 DW A
2 M52 A4 DI A
2 NC FC L
LT 2YR APPE EIX J l
2 M-5-2 A4 DI A
2 NC FC VPI 2YR Y
OP ST-VX-3010 HCV-1749 CA A
2 M 13 F4 GL A
4 NC FC L
LT 2YR APPENDIX J HCV-1749 CA A
2 M-13 F4 GL A
4 NC FC C
ST Q
Y OP-ST-CA-3001 HCV 1749 CA A
2 M 13 F4 GL A
4 NC FC VPI 2VR Y
2 M-264-1 C8 GL A
2 NO FC L
LT 2YR APPENDIX J PCV-1849A IA A
2 M-264-1 C8 GL A
2 NO FC C
J30 OP ST-CA 3002 PCV-1849A IA A
2 H 264 1 C8 GL A
2 NO FC VPI 2YR Y
OP-ST-VX 3004 7
PCV-1849B IA A
2 M 264 1 F5 GL A
2 NO FC L
LT 2VR APPEEIX J
)
PCV-18498 IA A
2 M 264 1 F5 GL A
2 NO FC C
J30 OP ST-CA-3002 OP ST-VX 3004 PCV 18498 IA A
2 M 264 1 F5 GL A
2 NO FC VPI 2YR Y
2 M-12 1 F7 GL A
0.5 NC FC C
ST Q
Y OP-ST-SL-3001 EV-2504A SL A
2 M 12 1 F7 GL A
05 NC FC L
LT 2YR APPE EIX J HCV 2504A SL A
2 M 12-1 F7 GL A
0.5 NC FC VPI 2VR Y
OP ST-VX-3021 R2 June 15,1995 Page 69 0f 168 i
m
., - ~
TABLE 2 1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX, VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE MlfeER SYS CAT CL4SS P&ID INATES TYPE TYPE SIZE
2 M-12-1 F7 GL A
0.5 NC FC C
ST Q
Y OP ST-SL-3001 HCV 25048 SL A
2 M-12-1 F7 GL A
U.5 NC FC L
LT 2YR APPEEIX J HCV-2504B SL A
2 M 12-1 F7 GL A
0.5 NC FC VPI 2YR Y
2 M-12 1 D7 GL A
0.5 NO FC C
J31 OP-ST SL-3002 HCV-2506A SL B
2 M 12 1 D7 GL A
0.5 NO FC VP1 2YR Y
2 M 12-1 D7 GL A
0.5 NO FC C
J31 OP-ST-SL 3002 HCV 2506B SL B
2 H-12 1 D7 GL A
0.5 NO FC VPI 2YR Y
2 M 12-1 C7 GL A
0.5 N0 FC C
J31 OP-ST SL-3002 HCV 2507A SL B
2 M-12-1 C7 GL A
0.5 NO FC VPI 2YR Y
2 M 12-1 C7 GL A
0.5 NO FC C
J31 OP-ST-SL-3002 HCV-2507B SL B
2 M 12-1 C7 GL A
0.5 NO FC VPI 2YR Y
2 M-42-1 DB GL A
1 NC FC L
LT 2VR APPE E IX J l
HCV-2603A NG A
2 M 42 1 08 GL A
1 NC FC C
ST Q
Y OP-ST-NG 3001 HCV 2603A NG A
2 M 42 1 DB GL A
1 NC FC VPI 2YR Y
OP-ST VX-3014
- )
HCV 2603B NG A
2 M-42 1 DB GL A
1 NC FC C
ST Q
Y OP-ST MG 3001 HCV-2603B NG A
2 M 421 D8 GL A
1 NC FC L
LT 2YR APPEEIX J HCV-26038 NG A
2 M 421 DB GL A
1 NC FC VPI 2YR Y
OP-ST-VX 3014 HCV 2604A NG A
2 M-42 1 D5 GL A
1 NC FC C
ST Q
Y OP-ST MG-3001 HCV-2604A NG A
2 M 42-1 D5 GL A
1 NC FC L
LT 2YR APPEEIX J HCV-2604A NG A
2 M 42-1 D5 GL A
1 NC FC VPI 2YR Y
OP ST-VX-3014 HCV-26048 NG A
2 M 421 D5 GL A
1 NC FC L
LT 2YR APPENDIX J.
HCV 26048 NG A
2 M 42-1 D5 GL A
1 NC FC C
ST Q
Y OP-ST-NG-3001 HCV 26048 NG A
2 M 42-1 D5 GL A
1 NC FC VPI 2YR Y
3 M 10-4 E5 GL A
1.5 NO FO O
ST Q
Y OP ST-CCW 3001 i
3 M-10-4 ES GL A
1.5 NO F0 VPI 2YR Y
3 M 10 4 B5 GL A
1.5 NO FD -
0 ST Q
Y OP-ST-CCW-3001 HCV-2808B CCW B
3 M 10-4
- B5 GL A
1.5 MO FD VPI 2YR Y
3 M 10-4 D5 GL A
1.5 NC F0 0
E RO J41 OP-ST-RW 3003 HCV 2800C RW B
3 M-10-4 D5 GL A
1.5 NC F0 C
E RO J41 OP ST-RW-3003 l
3 M-10 4 A5 GL A
1.5 NC FO O
~
HCV-2808D RW B
3 M 10 4 A5 GL A
1.5 NC F0 C
E RO J41 OP ST RW-3003 HCV 2809A CCW B
3 M-10-4 E4 GL A
1.5 NO FO O
ST Q
Y OP ST-CCW 3001 HCV 2809A CCW B
3 M-10 4 E4 GL A
1.5 ND F0 VPI 2YR Y
OP-ST VX-3005 HCV-2809B CCW B
3 M-10-4 B4 GL A-1.5 NO FO O
ST Q
Y OP ST-CCW-3001 HCV 28098 CCW B
3 M-10 4 B4 GL A
1.5 NO F0 VPI 2YR Y
OP ST VX-3005 R2 June 15,1995 Page 70 of 168 1
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TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE C00RO-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NLMER SYS CAT CLASS P&IO INATE5 TYPE TYPE SIZE
- POS POS REQ TEST FREQ TEST EXPT REMARKS HCV-2809C RW B
3 M 10-4 D5 GL A
1.5 NC FO O
ME R3 J41 OP-ST RW 3003 HCV-2809C RW B
3 M 10 4 05 GL A
1.5 NC F0 C
E RO J41 OP-ST RW-3003 HCV 28090 RW B
3 M-10 4 B4 GL A
1.5 NC FD 0
K RO J41 OP-ST-RW-3003 HCV 28090 RW 8
3 M 10 4 B4 GL A
1.5 NC F0 C
E RO 341 OP-ST RW-3003 HCV-2810A CCW B
3 M 10-4 E3 GL A
1.5 NO F0 O
ST Q
Y OP-ST-CCW-3001 HCV 2810A CCW B
3 M-10 4 E3 GL A
1.5 NO FO VPI 2YR Y
3 M 10-4 B3 GL A
1.5 NO FO O
ST Q
Y OP-ST CCW-3001 HCV-28108 CCW B
3 M 10 4 B3 GL A
1.5 NO F0 VPI 2YR Y
3 M-10-4 E2 GL A
1.5 NO FO O
ST Q
Y OP-ST-CCW-3001 HCV 2811A CCW B
3 M 10-4 E2 GL A-1.5 NO F0 VPI 2YR Y
3 M 10 4 B2 GL A
1.5 NO FO O
ST Q
Y OP ST CCW-3001 HCV 2811B CCW B
3 M 10 4 B2 GL A
1.5 NO FO VPI 2YR Y
3 M-10 4 El GL A
1.5 NO FO O
ST Q
Y OP ST-CCW 3001 HCV-2812A CCW B
3 M-10 4 El GL A
1.5 NO F0 VPI 2YR Y
3 M-10-4 B1 GL A
1.5 NO FO O
ST Q
Y OP-ST CCW 3001 HCV-2812B CCW B
3 M-10 4 B1 GL A
1.5 NO F0 VPI 2YR Y
OP-ST-VX 3005 HCV-2813A CCW B
3 M-10 4 E6 GL A
1.5 NO FO O
ST Q
Y OP-ST-CCW-300?.
HCV-2813A CCW B
3 M-10-4 E6 GL A
1.5 NO F0 VPI 2YR Y
OP-ST-VX-300' HCV-28138 CCW B
3 M 10-4 B6 GL A
1.5 NO FO O
ST Q
Y OP ST CCW-30'J1 HCV 28138 CCW B
3 M-10-4 B6 GL A
1.5 NO F0 VPI 2YR Y
3 M-10 4 EB GL A
1.5 NO FO O
ST Q
Y
.DP ST-CCW J001 HCV 2814A CCW B
3 M 10 4 EB GL A
1.5 NO F0 VPI 2YR Y
- j0PST-VX-3005 HCV-28148 CCW B
3 H 10-4 B8 GL A
1.5 NO F0 0
ST Q
Y
'tP ST-CCW 3001 HCV 2814B CCW B
3 M-10 4 B8 GL A
1.5 NO F0 VPI 2YR Y
(P-ST VX 3005 HCV-2815A CCW B
3 H-10 4 E7 GL A
1.5 NO FO O
ST Q
Y GP ST-CCW 3001 HCV-2815A CCW B
3 M-10 4 E7 GL A
1.5 NO F0 VPI 2YR Y
3 M 10-4 B7 GL A
1.5 NO FO O
ST Q
Y 03-ST-CCW 3001 HCV-2815B CCW B
3 M-10-4 B7 GL A
1.5 NO FD VPI 2YR Y
3 M-100 1 B7 BU A
20 m
FO O
ST Q
3 M-100 1 B7 BU A
20 NO F0 VPI 2YR Y
3 M 100-1 B6 BU A
20 NO FO O
ST Q
3 M-100 1 B6 BU A
20 NO F0 VPI 2YR Y
OP-ST VX 3017 HCV-2852 RW B
3 M-100-1 B5 BU A
20 NO FD 0
ST Q
3 M-100 1 B5 BU A
20 NO F0 VP1 2YR Y
3 M-100-1 B4 BU A
20 NO FD 0
ST Q
Y OP ST RW 3002 R2 June 15,1995 Page 71 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE l
COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NLH3ER SYS ' CAT CLASS P&ID INATES TYPE TYPE SIZE
3 M 100-1 B4 BU A
20 NO F0 VPI 2YR Y
3 H 100 1 C7 BU A
20 NO F0 VPI ZYR Y
3 M 100-1 C7 BU A
20 NO FO O
ST Q
Y OP ST RW-3002 HCV 2874A RW B
3 M-100-1 C7 BU A
20 NO FD C
ST Q
Y OP-ST RW-3002 HCV 28748 RW B
3 M-100-1 C7 BU A
20 NO FO VPI 2YR Y
OP ST-VX-3017 HCV 28748 RW B
3 M-100-1 C7 BU A
20 NO FO O
ST Q
Y OP-ST RW-3002 HCV-28748 RW B
3 M 100 1 C7 BU A
20 NO F0 C
ST Q
Y OP ST RW 3002 HCV-2875A RW B
3 M 100-1 C6 BU A
20 NO FO VPI 2YR Y
3 M 100-1 C6 BU A
20 NO FO O
ST Q
Y OP-ST RW-3002 HCV-2875A RW B
3 H 100-1 C6 BU A
20 NO F0 C
ST Q
Y OP ST-RW-3002 HCV 28758 RW B
3 M-100-1 C6 BU A
20 NO F0 VP1 2YR Y
3 M-100-1 C6 BU A
20 NO FO O
ST Q
Y OP ST-RW 3002 HCV 2875B RW 8
3 M 100-1 C6 BU A,
20 NO F0 C
ST Q
Y OP ST-RW-3002 HCV 2876A RW B
3 M 100 1 C5 BU A
20 NO FD VPI 2YR Y
20 NO FD 0
ST Q
Y OP ST-RW-3002 HCV 2876A RW B
3 M-100 1 C5 BU A
20 NO FD C
ST Q
Y OP-ST-RW 3002 HCV 28768 RW B
20 NO F0 VPI 2YR Y
3 M 100-1 C5 BU A
20 NO FO O
ST Q
Y OP-ST-RW-3002 HCV 28768 RW B
20 NO F0 C
ST Q
Y CP ST RW 3002 HCV 2877A RW B
3 M-100 1 E4 BU A
14 NO F0 VP1 2YR Y
3 M 100-1 E4 BU A
14 NO FO O
ST Q
Y OP-ST-RW 3002 HCV-2877A RW B
3 M-100-1 E4 BU A
14 NO F0 C
ST Q
Y OP-ST RW-3002 HCV 28778 RW B
3 M-100-1 E4 BU A
14 NO F0 VPI 2YR Y
OP-ST-VX 3017 HCV-28778 RW B
3 H-100-1 E4 BU A
14 NO FD 0
ST Q
Y OP ST-RW 3002 HCV 28778 RW B
3 M 100-1 E4 BU A
14 NO F0 C
ST Q
Y OP-ST RW 3002 HCV 287BA RW B
3 M-100-1 DS BU A
8 NO F0 VPI 2YR Y
OP ST-YX-3017 HCV 2878A RW B
3 M 100 1 D4 BU A
B NO FD 0
ST Q
Y OP-ST RW 3002 HCV 287BA RW B
3 M-100-1 D4 BU A
B NO F0 C
ST Q
Y OP ST-RW 3002 HCV 28788 RW B
3 M 100-1 D4 BU A
B NO F0 VPI 2YR Y
3 M-100 1 D4 BU A
8 NO FO O
ST Q
Y OP-ST RW 3002 HCV-28788 RW B
3 M-100-1 D4 BU A
8 NO FU C
ST Q
Y OP-ST RW 3002 HCV 2879A RW B
3 M-100 1 C4 BU A
14 NO F0 VP1 2YR Y
3 M 100 1 C4 BU A
14 NO FO O
ST Q
Y OP-ST-RW 3002 HCV 2879A RW B
3 M-100 1 C4 BU A
14 NO F0 C
ST Q
Y OP-ST RW 3002 HCV 2879B RW B
3 M-100-1 B4 BU A
14 NO FO VPI 2YR Y
OP ST-VX-3017 R2 June 15,1995 Page 72 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NUMBER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE -
POS POS REQ TEST FREQ TEST EXPT REMARKS HCV 28798 RW B
3 M-100-1 B4 BU A
14 NO FO O
ST Q
Y OP-ST-RW-3002 HCV-28798 RW B
3 M 100-1 B4 BU A
14 NO F0 C
ST Q
Y OP ST RW 3002 HCV-2880A RW B
3 M-100-1 E3 BU A
12 NO FO O
ST Q
Y OP-ST RW-3002 HCV-2880A RW B
3 M 100 1 E3 BU A
12 NO F0 VPI 2YR Y
3 M-100-1 El BU A
12 NO FO O
ST Q
Y OP ST-RW-3002 HCV-28808 RW B
3 M-100 1 El BU A
12 NO F0 VPI 2YR Y
3 M 100 1 C3 BU A
12 NO FO O
ST Q
Y OP ST-RW-3002 HCV-2881A RW B
3 M 100-1 C3 BU A
12 NO F0 VPI 2YR Y
OP-ST VX-3017 Y
3 M-100 1 C1 BU A
12 NO FD 0
ST Q _
3 M-100 1 C1 BU A
12 NO F0 VPI 2VR Y
3 M 100 1 F3 BU A
12 NO FD 0
ST Q
Y OP ST RW 3002 HCV-2882A RW B
3 M-100-1 F3 BU A
12 NO F0 VPI ZYR Y
3 M 100-1 F1 BU A
12 NO FO O
ST Q
{RW B
3 M-100-1 F1 BU A
12 NO F0 VPI 2YR Y
3 M 100-1 B3 BU A
12 NO FO O
ST Q
Y OP ST-RW 3002 HCV-2B83A RW B
3 M 100 1 B3 BU A
12 NO FO VPI 2YR Y
3 M 100 1 B1 BU A
12 NO FO O
ST Q
Y OP-ST-RW 3002 HCV 28838 RW B
3 M-100-1 B1 BU A
12 NO F0 VPI 2YR Y
3 M 100-1 B5 BU A
16 NO F0 VPI 2YR Y
OP ST-VX-3017 HCV 2893 RW B
3 M 100 1 B5 BU A
16 NO FO O
ST Q
16 NO FO VPI 2YR Y
16 NO FO O
ST Q
Y OP ST RW 3002 HCV 2898A CCW B
3 M 10-1 D6 GL A
2 NO FO O
ST Q
Y OP ST-CCW 3001 HCV 2898A CCW B
3 M 10-1 D6 GL A
2 NO F0 VPI 2YR Y
3 M-10 1 D4 GL A
2 NO FO O
ST Q
Y OP-ST-CCW 3001 HCV 28988 CCW B
3 M-10 1 D4 GL A
2 NO F0 VPI 2YR Y
3 M 10-1 D6 GL A
2 NC FO O
ME RO J41 OP ST-RW 3003 PCV 2898C RW B
3 M 10-1 D6 GL A
2 NC F0 C
E RO J41 OP ST RW-3003 HCV 28980 RW B
3 M 10-1 D6 GL A
2 NC FD 0
E RO J41 OP-ST RW-3003 HCV 2898D RW B
3 M-10-1 D6 GL A
2 NC F0 C
E RO J41 OP ST-RW 3003 HCV-2899A CCW B
3 M 101 C6 GL A
2 NO FO O
ST Q
Y OP-ST-CCW-3001 HCV 2899A CCW B
3 M-10-1 C6 GL A
2 NO F0 VPI 2YR Y
3 M-10 1 C4 GL A
2 NO FO O
ST Q
Y OP ST-CCW 3001 HCV 2899B CCW B
3 M-10-1 C4 GL A
2 NO F0 VPI 2YR Y
OP ST-VX-3005 HCV-2899C RW B
3 M-10-1 C6 GL A
2 NC FO O
ME RO J41 OP-ST-RW-3003
)
R2 June 15,1995 Page 73 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORN FAIL TEST TYPE TEST VPI CODE NUMER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE "
POS POS REQ TEST FREQ EST EXPT REMARKS HCV 2899C RW B
3 N-10 1 C6 GL A
2 NC F0 C
E RO J41 OP ST RW 3003 HCV 28990 RW B
3 N-10-1 C4 GL A
2 NC FO O
E RO J41-OP-ST-RW-3003 HCV 28990 RW B
3 N-10-1 C4 GL A
2 NC F0 C
E RO J41 OP ST RW 3003 PCV 2909 SI A
2 210 130-2 BS GL A
1 NC FC C
ST Q
Y OP ST-51-3001 PCV 2909 SI A
2 210-130-2 BS GL A
1 NC FC VPI 2YR Y
2 210-130-2 B5 GL A
1 NC FC L
LT 2YR APPEEIX J HCV 2916 SI A
2 210 130-2 CS GL A
1 NC FC L
LT 2YR APPEEIX J HCV-2916 SI A
2 210 130-2 C5 GL A
1 NC FC C
ST Q
Y OP ST SI-3001 HCV-2916 51 A
2 210-130 2 C5 GL A
1 NC FC VPI 2YR Y
OP-ST VX-3018 PCV-2929 SI A
2 210-130 2 B8 GL A
1 NC FC L
LT 2YR APPE E IX J PCV-2929 SI A
2 210 130 2 88 GL A
1 NC FC C
ST Q
2 210-130-2 BB GL A
1 NC FC VPI 2VR Y
2 210 130 2 C7 GL A
1 NC FC C
ST Q
2 210 130 2 C7 GL A
1 NC FC L
L1 2YR APPENDIX J j
HCV 2936 51 A
2 210 130 2 C7 GL A
1 NC FC VPI 2YR Y
OP ST-VX-3018 PCV 2949 SI A
2 210-130 28 B8 GL A
1 NC FC L
LT 2YR APPENDIX J PCV-2949 SI A
2 210 130 2B B8 GL A
1 NC FC C
ST Q
2 210-130 2B B8 GL A
1 NC FC VPI 2YR Y
2 210-130-2B C7 GL A
1 NC FC C
ST Q
Y OP-ST SI-3001 HCV-2956 SI A
2 210 130 2B C7 GL A
1 NC FC L
LT 2YR APPENDIX J l
HCV-2%6 SI A
2 210 130 2B C7 GL A
1 NC FC VPI 2YR Y
2 210 130-2B B4 GL A
1 NC FC L
LT 2YR APPENDIX J PCV 2969 SI A
2 210-130 2B B4 GL A
1 NC FC C
ST Q
2 210-130 2B B4 GL A
1 NC FC WPI 2YR Y
2 210-130 2B C4 GL A
1 NC FC L
LT 2YR APPENDIX J HCV 2976 SI A
2 110 130-28 C4 GL A
1 NC FC C
ST Q
2 210 130-2B C4 GL A
1 NC FC VPI 2YR V
2 210-130-1 E8 GL A
2 NC FC L
LT 2YR APPENDIX J l
2 210-130-1 EB GL A
2 NC FC VPI 2YR Y
2 210-130 1 E8 GL A
2 NC FC C
ST Q
OP-ST-SI-3001 HCV-2987 SI B
2 210-130 3 E7 GA P
4 NO FD
'C ST Q
2 210-130-3 E7 GA P
4 NO FD 0
ST Q
2 210 130-3 E8 GA A
4 NO FAI VPI 2YR Y
2 210 130-3 D6 GL 5
2 NC FC C
ST Q
Y OP ST-SI-3001 HCV-2988 SI B
2 210 130-3 D6 GL 5
2 NC FC 0
ST Q
Y OP-ST-SI-3001 R2 June 15,1995 Page 74 of 168
f TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NUMBER SYS CAT CLASS P&lD INATES TYPE TYPE SIZE
2 210 130-3 D6 GL S
2 NC FC VPI 2YR Y
OP-ST-VX 3019 IA HCV-238 C IA C
3 C-4175-8 F7 CK C
0.5 0
FS CS J33 NOTE 3 IC-ST-IA-3002 IA-HCV-238 C IA C
3 C-4175 8 F7 CK C
0.5 C
FS CS J33 NOTE 3 IC ST-IA 3002 IA HCV-239 C IA C
3 C-4175 8 F7 CK C
0.5 0
FS CS J33 NOTE 3 IC ST IA-3002 IA4CV 239 C IA C
3 C 4175 8 F7 CK C
0.5 C
FS CS J33 NOTE 3 IC-ST IA 3002 IA HCV 240 C IA C
3 C-4175 8 E7 CK C
0.5 C
FS CS J17 NOTE 1 IC ST-IA 3002 IA-HCV-240 C IA C
3 C-4175-8 E7 CK C
0.5 0
FS CS J17 NOTE 1 IC-ST IA-3002 IA-HCV-344 C IA C
2 C-4175-5 E7 CK C
0.5 0
FS CS J21 NOTE 1 OP-ST SI-3002 IA HCV 344 C IA C
2 C-4175 5 E7 CK C
0.5 C
FS CS J21 NOTE 1 OP ST SI 3002 IA HCV-345 C IA C
2 C-4175 5 E7 CK C
0.5 0
FS CS J21 NOTE 1 OP ST-SI 3002 IA-HCV-345 C IA C
2 C-4175 5 E7 CK C
0.5 C
F5 CS J21 NOTE 1 OP 4T-SI 3002 IA A/FIC-383 C IA C
2 M 264 4 D3 CK C
0.5 0
FS Q
NOTE 2 IC-ST-IA 3001 IA-A/FIC-383-C IA C
3 M 264-4 D3 CK C
0.5 C
FS Q
NOTE 2 IC-ST-IA-3001 IA 8/FIC-383-C IA C
3 M-264 4 B3 CK C
0.5 0
FS Q
NOTE 2 IC-ST IA-3001 IA B/FIC-383-C IA C
3 M 264 4 83 CK C
0.5 C
FS Q
NOTE 2 IC ST IA 3001 IA C/FIC-383 C IA C
3 M-264-4 C3 CK C
0.5 C
FS Q
NOTE 2 IC-ST-1A 3001 IA-C/FIC-383 C IA C
3 M-264-4 C3 CK C
0.5 0
FS Q
NOTE 2 IC-ST-1A-3001 IA-D/FIC-383-C IA C
3 M 264 4 A3 CK C
0.5 C
FS Q
NOTE 2 IC ST IA 3001 IA D/FIC-383 C IA C
3 M 264 4 A3 CK C
0.5 0
FS Q
NOTE 2 IC-ST-IA 3001 IA LCV 383 1-C IA C
3 C 4175 5 E7 CK C
0.375 0
FS CS J40 NOTE 1 OP ST-SI-3002 IA LCV-383-1 C IA C
3 C 4175 5 E7 CK C
0.375 C
FS CS J40 NOTE 1 OP-ST-SI-3002 IA-LCV-383 2-C IA C
3 C-4175-5 E7 CK C
0.375 C
FS CS J40 NOTE 1 OP ST-SI 3002 IA-LCV 393 2-C IA C
3 C-4175-5 E7 CK C
0.375 0
FS CS J40 NOTE 1 Op ST-SI-3002 IA HCV-385-C IA C
3 C 4175-5 E7 CK C
0.5 0
FS CS J34 NOTE 1 IC-ST-IA 3004 IA HCV 385-C IA C
3 C-4175 5 E7 CK C
0.5 C
FS CS J34 NOTE 1 IC-ST-IA-3004 IA HCV-386-C IA C
3 C-4175 5 E7 CK C
0.5 0
FS CS J34 NOTE 1 IC ST IA 3004 IA-HCV-386 C IA C
3 C-4175-5 E7 CK C
0.5 C
FS CS J34 NOTE 1 IC-ST-IA 3004 IA-HCV 400A C IA C
3 C-4175-6 F7 CK C
0.25 C
FS Q
NOTE 1 OP ST-CCW-3005 IA HCV 400A C IA C
3 C-4175-6 F7 CK C
0.25
- f0 FS Q
NOTE 1 OP ST CCW-3005 IA HCV-4008 C IA C
3 C-4175-6 F7 CK C
0.25 C
FS Q
NOTE 1 OP ST-CCW 3005 IA HCV 4008-C IA C
3 C-4175-6 F7 CK C
0.25 0
FS Q
NOTE 1 OP ST-CCW-3005 IA-HCV 400C-TV IA C
3 C 4175 6 F3 CK C
0.25 0
FS Q
NOTE 1 OP ST CIW 3005 IA HCV 400C-TV IA C
3 C-4175 6 F3 CK C
0.25 C
FS Q
NOTE 1 OP ST-CCW 3005 iA HCV 400D C IA C
3 C-4175-6 F7 CK C
0.25 0
FS Q
NOTE 1 OP-ST CCW 3005 IA-HCV-4000-C IA C
3 C-4175 6 F7 CK C
0.25 C
FS Q
NOTE 1 OP-ST-CCW 3005 R2 June 15,1995 Page 75 of 168
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST WI CODE NtM3ER SYS CAT CIASS.
P&lD INATES TYPE TYPE SIZE -
P05 POS REQ TEST FREQ TEST EXPT REMARKS IA-HCV-401A C IA C
3 C 4175 6 F7 CK C
0.25 C
FS NOTE 1 OP-ST-CCW 3005
^
3 C 4175 6 F7 CK C
0.25 0
FS Q
NOTE 1 OP ST CCW-3005 IA HCV 4018 C IA C
3 C-4175 6 F7 CK C
0.25 0
FS Q
NOTE 1 OP-ST-CCW-3005 IA HCV 4018 C IA C
3 C 4175 6 F7 CK C
0.25 C
FS Q
NOTE 1 OP-ST-CCW 3005 IA HCV 401C-W IA C
3 C-4175-6 F3 CK C
0.25 C
FS Q
NOTE 1 OP ST C 3-3005 IA HCV-401C-TV IA C
3 C 4175 6 F3 CK C
0.25 0
FS Q
NOTE 1 OP ST CCW 3005 IA-HCV-401D C IA C
3 C-4175-6 F7 CK C
0.25 C
FS Q
NOTE 1 OP ST-CCW-3005 IA-HCV-401D-C IA C
3 C-4175 6 F7 CK C
0.25 0
FS Q
NOTE 1 OP-ST CCW 3005 IA-HCV 402A C IA C
3 C-4175 6 E7 CK C
0.25 C
FS Q
NOTE 1 OP ST-CCW-3005 IA.HCV 402A-C IA C
3 C-4175 6 E7 CK C
0.25 0
FS Q
NOTE 1 OP-ST-CCW-3005 IA HCV 4028-C IA C
3 C 4175-6 E7 CK C
0.25 C
FS Q
NOTE 1 OP-ST CCW-3005 IA-HCV 402B C IA C
3 C-4175 6 E7 CK C
0.25 0
FS Q
NOTE 1 OP ST-CCW 3005 IA HCV 402C TV IA C
3 C-4175-6 E3 CK C
0.25 C
FS Q
NOTE 1 OP ST-CCW-3005 IA-HCV 402C-TV IA C
3 C-4175 6 E3 CK C
0.25 0
FS Q
NOTE 1 OP-ST-CCW 3005 IA-HCV 402D C IA C
3 C-4175-t, E7 CK C
0.25 0
FS Q
NOIE 1 OP-ST-CCW-3005 IA HCV 402D-C IA C
3 C 4175 6 E7 CK C
0.25 C
FS Q
NOTE 1 OP-ST-CCW-3005 NOTE 1 OP ST-CCW 3005 IA HCV-403A C IA C
3 C 4175 6 E7 CK C
0.25 0
FS Q
3 C-4175-6 E7 CK C
0.25 C
FS Q
NOTE 1 OP-ST CCW-3005 IA HCV 4038 C IA C
3 C-4175 6 E7 CK C
0.25 C
FS Q
NOTE 1 OP-ST-CCW 3005 IA41CV 4038-C IA C
3 C-4175 6 E7 CK C
0.25 0
FS Q
NOTE 1 OP-ST CCW 3005 IA HCV 403C-TV IA C
3 C 4175 6 E3 CK C
0.25 0
FS Q
NOTE 1 OP ST-CCW-3005 la HCV 403C-TV IA C
3 C-4175 6 E3 CK C
0.25 C
FS Q
NOTE 1 OP-ST-CCW 3005 IA HCV-4030-C IA C
3 C-4175 6 E7 CK C
0.25 0
FS Q
NOTE 1 OP ST-CCW-3005 IA-HCV-403D-C IA C
3 C-4175-6 E7 CK C
0.25 C
FS Q
NOTE 1 OP ST-CCW 3005 IA HCV 4388 C IA C
3 C-4175-6 07 CK C
0.5 C
FS CS J24 NOTE 1 OP ST-CCW-3004 IA HCV 438B C IA C
3 C-4175 6 D7 CK C
0.5 0
FS CS NOTE 1 OP-ST-CCW 3004 IA40V 438D C IA C
3 C-4175 6 D7 CK C
0.5 C
FS CS J24 NOTE 1 OP ST CCW 3004 IA HCV 4380-C IA C
3 C-4175 6 D7 CK C
0.5 0
FS CS
+
NOTE 1 OP-ST CCW 3004 IA-HCV 480 C IA C
3 C 4175-6 B7 CK C
0.5 0
FS Q
NOTE #5 OP ST-CCW 3005 C
FS Q
NOTE #5 OP-ST CCW 3005 IA HCV 480 C IA C
3 C 4175 6 B7 CK C
0.5 IA-HCV 481-C
!A C
3 C 4175-6 B7 CK C
0.5 0
FS Q
NOTE #5 OP-ST-CCW-3005 IA HCV-481-C IA C
3 C-4175 6 BT CK C
0.5 C
FS Q
NOTE #5 OP-ST-CCW 3005 IA-HCV-484 C IA C
?
C-4175 6 B7 CK C
0.5 0
FS Q
NOTE #5 OP ST-CCW 3005 IA-HCV-484-C IA C
3 'C-4175 6 B7 CK C
0.5 C
FS Q
NOTE #5 OP ST CCW 3005 IA HCV 485-C IA C
3 C-4175-6 B7 CK C
0.5 0
FS Q
NOTE #5 OP ST CCW 3005 R2 June 15,1995 Page 76 of 168
+
TABLE 2.1 - FORT CALHOUN VALVE TEST PROGRAM MATRIX VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NUPEER SYS CAT CLASS P&ID INATES TYPE TYPE SIZE
3 C-4175-6 87 CK C
0.5 C
FS Q
NOTE #5 OP-ST CCW-3005 NOTE 1 OP ST MS-3001 IA YCV 1045A C IA C
3 C-4175 4 87 CK C
0.5 0
FS Q
!A YCV 1045A C IA C
3 C-4175-4 87 CK C
G5 C
FS Q
NOTE 1 OP-ST-MS 3001 I YCV 10458-C IA C
3 C-4175-4 B7 CK C
0.5 0
FS Q
NOTE 1 OP ST-MS 3001 IA-YCV-10458-C IA C
3 C-4175 4 87 CK C
0.5 C
FS Q
NOTE 1 OP-ST MS-3001 IA-HCV 1107A C IA C
3 C-4175 8 E7 CK C
0.5 C
FS CS J38 IC ST-AFW 3002 IA HCV 1107A-C IA C
3 C-4175-8 E7 CK C
0.5 0
FS CS J38 IC ST-AFW 3002 IA-HCV 11078-C IA C
3 C 4175-8 07 CK C
0.5 C
FS CS J38 IC ST-AFW 3002 IA-HCV 11078 C IA C
3 C-4175 8 D7 CK C
0.5 0
FS CS J38 IC-ST-AFW-3002 IA HCV 1108A C IA C
3 C 4175 8 D7 CK C
0.5 C
FS CS J38 IC ST-AFW 3002 IA HCV 1108A C IA C
3 C-4175 8 D7 CK C
0.5 0
FS CS J38 IC-ST AFW-3002 IA HCV-11088-C IA C
3 C-4175 8 07 CK C
0.5 C
FS CS J38 IC ST AFW 3002 IA-HCV-11088 C IA C
3 C 4175-8 07 CK C
0.5 0
FS CS J38 IC ST AFW-3002 IA ICV 1368 C IA C
3 C-4175-8 D7 CK C
0.5 C
FS CS J38 IC-ST-AFW-3001 0
FS CS J38 IC ST-AFW-3001 IA FCV-1368 C IA C
3 C 4175-8 D7 CK C
3 C-4175 8 D7 CK C
0.5 C
FS CS J38 IC ST-AFW-3001 IA FCV 1369 C IA C
3 C 4175 8 D7 CK C
05 0
FS CS J38 IC-ST-AFW 3001 PCV 1849A 20A IA A
2 M-264 1 D8 GL 5
0.5 0
FC L
LT 2YR APPEEIX J PCV-1849A 208 IA A
2 M-264-1 08 GL S
0.5 0
FC L
LT 2YR APPENDIX J 1A-HCV 2851-C IA C
3 C 4175-7 D7 CK C
0.5 0
FS Q
NOTE 1 IC-ST-IA-3003 IA HCV 2851 C IA C
3 C 4175 7 07 CK C
0.5 C
FS Q
NOTE 1 IC-ST IA-3003 IA HCV 2852 C IA C
3 C-4175-7 D7 CK C
0.5 C
FS Q
NOTE 1 IC-ST IA-3003 IA-HCV 2852 C IA C
3 C-4175-7 07 CK C
0.5 0
FS Q
NOTE 1 IC-ST-IA 3003 IA HCV 2853 C IA C
3 C-4175 7 D7 CK C
0.5 0
FS Q
NOTE 1 IC ST-IA 3003 IA-HCV-2853 C IA C
3 C 4175 7 D7 CK C
0.5 C
FS Q
NOTE 1 IC-ST IA-3003 IA-HCV 2898A C IA C
3 M-100 CK C
0.5 C
FS Q
NOTE 6 IA ST IA 3008 IA-HCV-2898A C IA C
3 M 100 CK C
0.5 0
FS Q
NOTE 6 IA-ST IA-3008 IA-HCV 28988 C IA C
3 M 100 CK C
0.5 C
FS Q
NOTE 6 IA ST-IA 3008 IA HCV 28988-C IA C
3 M-100 CK C
0.5 0
FS Q
NOTE 6 IA-ST-IA-3008 IA-HCV-2899A-C IA C
3 M 100 CK C
0.5 C
FS Q
NOTE 6 IA ST-IA 3008 NOTE 6 IA-ST IA 3008 IA HCV 2899A-C IA C
3 M 100 CK C
0.5 0
FS Q
3 M 100 CK C
0.5 C
FS Q
NOTE 6 IA-ST-IA-3008 IA-HCV 28998 C IA C
3 M-100 CK C
0.5 0
FS Q
NOTE 6 IA-ST IA 3008 NOTE 1 IC ST-IA-3005 IA-HCV 2987-C IA C
3 C-4175-5 C7 CK C
0.375 0
FS Q
3 C 4175-5 C7 CK C
0.375 C
FS Q
NOTE 1 IC ST-IA 3005 R2 June 15,1995 Page 77 of 168
i TABLE 2.1-- FORT CALHOUN VALVE TEST PROGRAM MATRIX' VALVE COORD-VALVE OPER VALVE NORM FAIL TEST TYPE TEST VPI CODE NUPeER SYS CAT CIASS P6ID INATES TYPE TYPE SIZE
- POS -
POS REQ TEST FREQ TEST EXPT REMMKS APPENDIX J IA-3092 IA A
2 N 264 4 BS GL H
0.5 L
2 N 264 4 B5 GL H
0.5 L
LT 2YR APPEW IX J APPEIGIK J IA-3094 IA A
2 N-264 4 B5 BL H
0.5 L
3 P 49323 N/A CK C
0.5 C
FS CS J38 NOTE 4 IC ST-IA-3006 C
FS CS J38 NOTE 4 IC ST IA 3007 IA PCV 6680A 2 C IA C
3 P-49323 N/A CK C
0.5 C
FS CS J38 NOTE 4 IC-ST IA 3007 IA PCV 66808 1 C IA C
3 P-49323 N/A CK C
3 P 49323 N/A CK C
0.5 C
FS CS J38 NOTE 4 IC ST-IA-3007 IA-PCV-6682-C IA C
3 P 49323 N/A CK C
0.5 C
FS CS J38 NOTE 4 IC-ST IA-3007-i t
- t i
k
?
E
. k 1
i 4
i R2 June 15,1995 Page 78 of 168 m -.m.- m m
. -..m
_.,rh
.. m --
_m___m _a__wmm-_m,h.._m.%.-v_,,
..,m,.w--
,..-,.,....w, v._..m-.,,uv wn,
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I-APPENDIX 2A JUSTIFICATION FOR TESTS FREQUENCIES OTHER THAN CODE PREFERRED R2 June 15, 1995 Page 79 of 168
JUSTIFICATION FOR TEST FREQUENCIES OTHER THAN CODE PREFERRED This section provides justification for alternate frequencies other than those preferred in the Code.
Each fre number and identifies the valve (quency justification is identified by a unique s) for which the frequency justification is presented.
The specific Code test frequency requirement found to be impractical is defined and the justification for an alternative test frequency i
is given.
Frequency justifications are numbered and referenced by number (Jx) on the Valve Test Program Matrix Table 2.1 for specific valves.
1.
Frequency Justification Number J1 - Refueling Outage Justification Components:
SI-100, SI-113 Function:
High Pressure Safety Injection (HPSI) Pump Suction Check Valves l
j Class:
2 Test Requirements:
Quarterly Full Flow Exercising in the Open Direction Basis for Justification:
These valves cannot be full-stroke exercised open Quarterly during plant operation or during Cold Shutdowns, since to do so would require a flow path to the Reactor Coolant System (RCS).
That i
flow path cannot be utilized during power operation because the High Pressure Safety Injection (HPSI) pumps do not develop sufficient discharge pressure to overcome RCS pressure.
This same flow path cannot be utilized during Cold Shutdowns because there is insufficient volume in the RCS to accommodate the flow required and a low temperature overpressure condition of the RCS could result.
Alternate Testing:
Valves will be partial-stroke exercised open, using the minimum l
recirculation flow path Quarterly during normal operations, and full-stroke exercised open during Refueling Outages.
This method of partial-stroke exercising open Quarterly and I
full-stroke exercising open during Refueling Outages is in accordance with the guidance set forth in Paragraph 4.2.1.2 0&M Part 10.
R2 June 15, 1995 Page 80 of 168
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2.
Frequency Justification Number J2 - Cold Shutdown Justification Components:
t PCV-102-1, PCV-102-2 Function:
Power Operated Relief Valves (PORV) for the Pressurizer t
Class:
1 Test Requirements:
Quarterly Stroke-Timing Open and Closed Basis for Justification:
These valves can only be opened or closed when there is.a pressure' differential across the valve.
The valves have solenoid pilot valves that control their actuation.
Since valves of this type have a history in the industry of sticking open and the PORVs are not credited in the safety analysis for overpressure protection i
during power operations, it is impractical to stroke these valves t
Quarterly during power operation.
These valves cannot be partial-stroke tested open because they are either fully opened or l fully closed.
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Alternate Testing:
The PORVs will be stroke-timed in the op(en and closed direction s
during the transition to Cold Shutdown primary plant pressure is between 350 - 450 psia and primary plant temperature is between i
300 - 350*F) prior to entering Mode 4.
The PORVs will be tested during the transition from Hot Shutdown to Cold Shutdown (as definedbyFCSTechnicalSpecifications)wheneverpractical,i.e.,
j normal plant shutdown.
During a Technical Specification mandated shutdown, the PORVs will be tested during plant startup prior to entering Mode 2 (when primary plant pressure is between 350 - 450 psia and primary plant temperature is between 300 - 350*F).
R2 June 15, 1995 Page 81 of 168
3.
Frequency Justification Number J3 - Refueling Outage Justification
~
Components:
SI-102, SI-108, SI-115 Function:
HPSI Pump Discharge Check Valves Class:
2 Test Requirements:
Quarterly Full Flow Exercising in both the Open and Closed Directions Basis for Justification:
These valves cannot be full-stroke or partial-stroke exercised open or closed during plant operation, Quarterly or during Cold Shutdowns, since to do so would require a flow path to the RCS.
That flow path cannot be utilized during power operation because the HPSI pumps do not develop sufficient discharge 3ressure to overcome RCS pressure.
This same flow path cannot )e utilized during Cold Shutdowns because there is insufficient volume in.the RCS to accommodate the flow required, and a low temperature overpressure condition of the RCS could result. Additionally, these valves cannot be exercised during Quarterly pump tests or miniflow because the minimum flow lines branch off upstream of the check valves and no flow occurs through these valves.
Alternate Testing:
Valves will be full-stroke exercised open and closed during Refueling Outages when the Reactor Vessel head is removed. This will provide an expansion volume to accommodate the flow required.
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R2 June 15, 1995 Page 82 of 168
l 4.
Frequency Justification Number J4 - Cold Shutdown Justification Components:
SI-121, SI-129 Function:'
Low Pressure Safety Injection (LPSI) Pump Discharge Check Valves l
Class:
2 Test Requirements:
l-'
Quarterly Full-Stroke Exercising in both the Open and Closed Directions Basis for Justification:
These valves cannot be partial-stroke or full-stroke exercised in the open or closed direction Quarterly during power operation because there is no flow path available except during shutdown cooling.. Additionally, these valves cannot be exercised open or closed during Quarterly pump tests or using the miniflow line because the minimum flow lines branch off upstream of the check valves and no flow occurs through these valves.
Alternate Testing:
Valves will be full-stroke exercised open and closed during Cold Shutdown.
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R2 June 15, 1995 Page 83 of 168
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15, -
Frequency Justification Number J5 - Cold Shutdown Justification l
Components:-
CH-143, CH-155, CH-156 Function:
CH-143 - Charging Pump Boric Acid Supply Check Valve CH-155 - Charging Pump Boric Acid Gravity Feed Check Valve CH-156 - Charging Pump Safety Injection and Refueling Water Tank (SIRWT) Suction Check Valve Class:
2 Test Requirements:
Quarterly Full Flow Exercising in the Open Direction i
Basis for Justification:
These check valves serve to permit direct feed of concentrated boric acid solution to the charging pump suction header.
These check valves cannot be full-stroke or partial-stroke exercised open Quarterly during power operation. The only flow path through these valves is into the RCS; exercising would result in injecting' highly concentrated boric' acid into the RCS.
Injecting i
concentrated boric acid into the RCS during power operation could cause an uncontrolled reactivity excursion, a plant shutdown, or a plant trip.
Alternate Testing:
.i i
Valves will be full-stroke exercised open during Cold Shutdown in accordance with the FCS ISI Program Plan implementing procedures.
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-R2 June 15, 1995 Page 84 of 168
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6.
Frequency Justification Number J6 - Cold Shutdown Justification 7
Components:
FW-161, FW-162 Function:
Steam Generator Normal Feedwater Inlet Check Valves Class:
2 Test Requirements:
Quarterly Full-Stroke Exercising in the Closed Direction Basis for Justification:
These check valves function to prevent the loss.of inventory of the Steam Generators in the event of a line break upstream between valves HCV-1386 (HCV-1385) and check valve FW-161 (FW-162).
These-check valves cannot be full-stroke exercised closed Quarterly-during power operation because the valves FW-161 and FW-162 are the only feedwater supply flow paths to the Steam Generators.
During power operation, the feedwater paths to the Steam Generators must not be isolated-as this would remove the " heat sink" for the Reactor Coolant System (RCS).
l Alternate Testing:
Valves will be full-stroke exercised closed during Cold Shutdown as defined in the FCS Technical Specifications, in accordance with the requirements of the FCS ISI Program Plan implementing j
procedures.
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y 7.
Frequency Justification Number J7'- Cold Shutdown Justification Components:
FW-163, FW-164 Function:
L
' Steam Generator Auxiliary Feedwater Injection Check' Valves Class:
2 Test Requirements:
Quarterly Full-Stroke Exercising in the Open Direction Basis For Justification:
These check valves open for auxiliary feedwater (AFW) flow to.the. l Steam Generators.
Exercising these valves during power operation would result in cold water injection to a portion of.the Steam Generators normally at 400 - 500*F, which would cause unnecessary and possibly damaging thermal stresses in the Steam Generators.
The check valves are not required to be exercised in the closed direction, as there are two containment isolation valves upstream of each of the check valves which are normally closed.
In addition, there is an AFW pump check valve upstream of the containment isolation valves which is exercised closed quarterly in accordance with the FCS ISI Program Plan. As a result of the above mentioned ISI tests, FCS has addressed adequately the l
concern of " thermal binding" of the AFW pumps and has determined that FW-163 and FW-164 do not provide a safety-related function in the reverse flow direction.
It should also be noted that the discharge piping temperature upstream of FW-153 and FW-164 is monitored on a regular basis, further ensuring that the AFW pumps will not experience " thermal binding."
Alternate Testing:
These check valves are exercised open during Cold Shutdown.
Since failure of these valves to function in the reverse flow direction would not interfere with the plant's ability to shutdown or to mitigate the consequences of an accident, these check valves shall be full-stroke exercised only in the open direction.
R2 June 15, 1995 Page 86 of 168
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8.
Frequency Justification Number J8 - Cold Shutdown Justification l
i Components:
HCV-176, HCV-177, HCV-178, HCV-179,_HCV-180, HCV-181 Function:
Reactor Vessel Head and Pressurizer Vents Class:
2 3
Test Requirements:
Quarterly Stroke-Timing Open and Closed Basis for Justification:
r These valves are intended to be used to vent the Reactor Pressure Vessel (RPV) head and pressurizer. These valves are Target Rock solenoid valves, which have a history of sticking open when exercised. This could result in a small break Loss of Coolant Accident (LOCA) if these valves are stroke-timed at power.
Therefore, partial or full-stroke timing during normal operation is impractical.
Alternate Testing:
These valves will be stroke-timed in the open and closed directions during Cold Shutdown, in accordance_with the FCS ISI Program Plan implementing procedures.
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R2 June 15, 1995 Page 87 of 168
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4 9.
Frequency Justification Number J9 - Cold Shutdown Justification Components:
SI-194, SI-197, SI-200, SI-203 Function:
Shutdown Cooling Injection Check Valves.
Class:-
1 q
Testing Requirements:
Quarterly Full-Stroke Exercising in the Open Direction and Leakage Test During Cold Shutdown l
Basis for Justification:
These check valves cannot be full-stroke exercised open or.
partial-stroke exercised Quarterly during power operation because no flow path is available at operating pressure due to system configuration.
SincetheSafetyInjection(SI)pumpsarenotablel to develop sufficient discharge pressure to overcore RCS pressure, the valves are not able to be exercised. Valves SI-194,fSI-197, SI-200andSI-203arePressureIsolationValves(PIVs)asdefined by NRC Generic Letter (GL) 89-04 and as listed in the FCS Technical Specifications.
Alternate Testing:
These check valves are full-stroke exercised open during. Cold 1
Shutdown when the Shutdown Cooling system is in' service.
These check valves will be leak tested during Cold Shutdown in.
accordance with the requirements of FCS Technical Specification 2.1, Table 2-9, and Item 14 of the table format of this Program Plan.
i R2 June 15, 1995 Page 88 of 168 l
p 10.
. Frequency Justification Number J10 - Refueling Outage Frequency Components:
I 51-195, SI-198, SI-201, SI-204 i
Function:.
l High Pressure Safety Injection to Reactor Coolant Loop Check Valves Class:
I i
Test Requirements:
Quarterly Full-Stroke Exercising in the Open Direction and Leakage Test During Cold Shutdown Basis for Justification:
'These check valves cannot be full-stroke or partial-stroke i
exercised open Quarterly during power operation because the only flow path available is into the RCS.
Since the HPSI pumps do not.
develop sufficient discharge pressure to-overcome RCS operating-pressure, the valves cannot be exercised during Cold Shutdown.
because the RCS does not contain an adequate expansion volume and' i
a low temperature overpressurization (LTOP) of the RCS could l
result. Valves SI-195, SI-198, SI-201 and SI-204 are pressure i
isolation valves (PIVs) as defined by NRC GL 89-04 and as listed in the FCS Technical Specifications.
Alternate Testing:
These check valves will be full-stroke exercised open.during i
Refueling Outages when the RCS is depressurized and the Reactor Pressure Vessel (RPV) Head is removed in order to provide an expansion volume to accommodate the flow required.
These check valves will be leak tested during Cold Shutdown in accordance with the requirements of FCS Technical Specification 2.1, Table 2-9, and Item 14 of the table format of this. Program Plan.
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-11.
Frequency Justification Number J11 - Refueling Outage Frequency
~
Components:-
l SI-196, SI-199, SI-202, SI-205, SI-343, CH-469 Function:
High Pressure Safety Injection to Reactor Coolant Loop Check Valves Class:
SI-196, SI-199, SI-202, SI-205, CH-469 1
SI-343 2
Testing Requirements:
Quarterly Full-Stroke Exercising in the Open Direction Basis for Justification:
Valves SI-196, -199, -202, -205, and CH-469 function to prevent backflow through the Safety Injection (SI) pump. discharge headers.
These valves cannot be full-stroke or partial-stroke exercised open during power operation utilizing flow because the HPSI pumps do not develop sufficient discharge pressure to overcome RCS pressure. The charging pumps cannot be used during power 1
operation because the flow path from the pumps would bypass the Regenerative Heat Exchanger and result in injecting cold water, causing thermal shock to the injection nozzles and a reactivity transient.
This could result in an unnecessary plant trip. Check valve SI-343 cannot be partial-stroke exercised during Cold Shutdowns because using the HPSI pumps without an adequate vent path could cause an overpressurization of the RCS.
The HPSI pumps are therefore tagged out to prevent inadvertent operation and potential overpressurization to the RCS.
Alternate Testing:
Check valves SI-196, SI-199, SI-202, and SI-205 will be partial-stroke exercised open during Cold Shutdown using the Charging Pumps and full-stroke exercised Open during Refueling Outages when the HPSI pumps are able to be utilized.
Check valve CH-469 will be partial-stroke exercised open during i
Cold Shutdown using the charging pumps.
Both check valves, CH-469 and SI-343, will be full-stroke exercised open during Refueling Outages using the charging pumps and the HPSI pumps, as necessary.
i R2 June 15, 1995 Page 90 of 168
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12.
Frequency Justification Number J12 - Refueling Outage Justification Components:
CH-198, CH-203, CH-204 Function.'
i ChargingPumpdischargetoRCSCheckValve(CH-198)
Loop Charging Line to RCS Check Valves (CH-203, CH-204)
Class:
Test Requirements:
i
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Quarterly Full-Stroke Exercising CH-198 in the Open and Closed i
Directions Quarterly full-stroke exercising CH-203 and CH-204 in the Open Direction Basis for Justification:
These check valves cannot be full-stroke exercised open (or closed for CH-198) during plant operations Quarterly or during Cold' Shutdowns, since to do so would require the charging and HPSI pumps to be run which would require a flow path to the RCS.
That flow path cannot be utilized during power operation because the HPSI pumps do not develop sufficient discharge pressure to overcome RCS pressure.
This same flow path cannot be utilized during Cold Shutdowns because there is insufficient volume in the RCS to accommodate the flow required and a low temperature overpressure condition of the RCS could result.
.l Alternate Testing:
The check valves CH-198, CH-203, and CH-204 will be partial-stroke exercised in the open direction Quarterly during power operation using the charging pumps.
The check valves'will.be full-stroke exercised in the open direction during Refueling Outages when the Reactor Pressure Vessel (RPV) head is removed, using the charging l
pumps and the HPSI pumps. Check valve CH-198 will be full-stroke exercised in the close direction during Refueling Outages.
1 R2 June 15, 1995 Page 91 of 168
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13.
Frequency Justification Number J13 - Cold Shutdown Justification Component:
1 TCV-202, HCV-204 Function:
Letdown Temperature. Control Valve, Letdown Isolation Valve l
Class:
i 1-TCV-202 2-TCV-204 Test Requirements:
Quarterly Stroke-Timing Closed Basis for Justification:
These valves are used for RCS Loop 2A letdown isolation and temperature regulation.
Stroking these valves Quarterly during power operation could result in the termination of letdown flow.
This would isolate the RCS purification process and could l
potentially cause a reactivity excursion. These valves cannot be partial-stroked because the valves are either fully open or fully closed.
l Alternate Testing:
These valves will be stroke-timed in the closed direction during t
Cold Shutdown in accordance with the.FCS ISI Program Plan implementing procedures.
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R2 June 15, 1995 Page 92 of 168
l 14.
Frequency Justification Number J14 - Cold Shutdown Justification
. Component:'
,1 CH-205-
-Function:
[
Auxiliary Pressurizer Spray Check Valve l
Class:
1 1-Test Requirements:
Quarterly Full Flow Exercising in the Open Direction Basis for Justification:
This check valve cannot be full-stroke exercised during plant operations Quarterly or during Cold Shutdowns, since to do so would require a flow path to the RCS.
That flow path cannot be utilized during power operation because the HPSI pumps do not develop sufficient discharge pressure to overcome RCS pressure.
This same flow path cannot be utilized during' Cold Shutdown!
~
because.there is insufficient volume in the RCS to accommodate the flow required and a low temperature overpressure condition of the RCS could result.
Alternate Testing:
The check valves will be partial-stroke exercised in the open direction Quarterly during power operation using the charging' pumps.
The check valves will be full-stroke exercised in the open direction during Refueling Outages when the RVP head is removed, l
using the charging pumps 3nd the HPSI pumps.
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R2 June 15, 1995 Page 93 of 168
]
-15.. -Frequency Justification Number J15 Refueling Outage Justification
-Component:
HCV-206, HCV-241 Function:
RC Pump Control Bleedoff Isolation Valves Class:
2 Test Requirements:
Quarterly Stroke-Timing Closed Basis for Justification:
The Reactor Coolant Pump (RCP) seals serve'as an RCS pressure boundary, therefore, seal failure could result in unisolable coolant leakage from the RCS.
Isolation of the RCP seal bleed-off-by stroking these valves closed would cause the seal bleed-off line relief valve (CH-208) to lift, directing reactor coolant directly to the Reactor Coolant Drain Tank (RCDT).
If the leakage remained unchecked, the RCDT relief valve could lift directing reactor coolant to the Containment floor, causing a Ventilation Isolation Actuation Signal (VIAS).
Additionally, the temporary isolation of pump seal flow (until the relief valve lifted) would eliminate the ability of the RCP seal to break down RCS pressure and could potentially cause localized overheating of the seals.
The pump seals can be damaged by overheating if. seal water flow is stopped while the pumps are ranning.
It is impractical to-exercise these valves Quarterly or during any plant conditions that could result in abnormal seal wear.
This could lead to failure of the RCP seals, creating unisolable leakage equivalent to a small break LOCA.
l Alternate Testing:
The valves will be stroke-timed in the closed direction during Cold Shutdown, when the RCS is depressurized and the RCPs are secured.
I R2 June 15, 1995 Page 94 of 168
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16.
Frequency Justification Number J16.-' Cold Shutdown Justification
~
Components:
LCV-218-2, LCV-218-3 Function:
.o VolumeControlTank'OutletIsolationValveand. Charging (Pump)
Suction From Safety Injection and Refueling Water Tank SIRWT 1
Isolation Valve g
i Class:
2 Test Requirements:
Quarterly Stroke-Timing Closed for LCV-218-2 and Quarterly Stroke-Timing Open for LCV-218-3 Basis for Justification:
{
These valves function to provide Volume Control Tank (VCT) level jr control and switch charging suction to the Safety Injection and i
Refueling Water Storage Tank-(SIRWT). The valves cannot be stroke-tested Quarterly because doing so would terminate charging i
flow to the RCS and would have the potential for disrupting pressurizer level regulation or boron concentration regulation.
Pressurizer level regulation disruption can lead to RCS pressure transients and disruption of. boron concentration could cause reactivity excursions.
Alternate Testing:
Valve LCV-218-2 will be stroke-timed in the closed direction and valve LCV-218-3 will be stroke-timed in the open direction during i
Cold Shutdowns.
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17.
Frequency Justification Number J17 - Cold Shutdown Justification Components:
IA-HCV-240-C, HCV-240. HCV-249 Function:
InstrumentAir(IA)AccumulatorCheckValveforHCV-240, l
Auxiliary Pressurizer Spray Isolation Valves Class:
3 (IA-HCV-240-C), Class 1 (HCV-249, HCV-240)
Test Requirements:
Quarterly Exercising in the Open and Closed Directions for IA-HCV-240-C, Quarterly Exercising Open for HCV-249 and Stroke-Testing in the Open and Closed Directions for HCV-240 Basis for Justification:
Valves HCV-240 and HCV-249 cannot be stroke-timed Quarterly during power operation because doing so will lead to large scale depressurization of the RCS and thermal shock of the pressurizer spray nozzle. The IA accumulator check valve (IA-HCV-240-C) cannot be full-stroke exercised in the open direction Quarterly during power operation, as exercising of the check valve will cause HCV-240 to cycle.
This could cause large scale depressurization of the RCS and thermal shock of the pressurizer spray nozzle.
The check valve (IA-HCV-240-C) cannot be partial-stroke exercised for the same reason.
Alternate Testing:
Valve IA-HCV-240-C will be exercised in the open and closed directions during Cold Shutdowns.
Valves HCV-240 and HCV-249 will be stroke-timed in both the open and closed directions during Cold Shutdowns.
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l R2 June 15, 1995 Page 96 of 168 l
18..
Frequency Justification Number J18 - Cold Shutdown Justification Components:
HCV-268 Function:
Concentrated Boric Acid to Charging Pump Suction Isolation Valves Class:
2 l
Test Requirements:
Quarterly Stroke-Timing in the Open Direction Basis for Justification:
These valves serve to isolate concentrated boric acid from the charging pump suction header. These valves cannot be stroke-timed Quarterly during power operation because doing so would allow concentrated boric acid solution to be injected into the RCS.
Boration of the primary system during normal power operation would cause reactivity transients and possibly result in a plant shutdown.
These valves cannot be partial-stroked for the same reason.
Alternate Testing:
Valves will be stroke-timed in the open direction during Cold Shutdown.
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19.
Frequency Justification Number J19 - Cold Shutdown Justification DELETED I
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f 20.
. Frequency Justification Number J20 - Refueling Outage Justification Component:
SI-323 Function:
High Pressure Safety Injection Header Check Valve Class:
2 Test Requirements:
Quarterly Full Flow Exercising in the Open and Closed Directions Basis for Justification:
This check valve functions to prevent backflow of charging flow to the lower design pressure HPSI piping when the alternate charging flow path is active.
The only flow path available is into the RCS and since the HPSI pumps do not develop sufficient discharge pressure to overcome RCS operating pressure, this valve'cannot be exercised Quarterly during power operation.
This valve cannot be exercised during Cold Shutdowns because the RCS does not contain i
an adequate expansion volume and a-low-temperature I
overpressurization of the RCS could result. Additionally, this valve cannot be partial-stroke exercised during pump test or l
miniflow because the minimum flow lines branch off upstream of the i
check valve and no flow occurs through this valve.
Alternate Testing:
This check valve will be exercised full-open and full-closed i
during Refueling Outages.
R2 June 15, 1995 Page 99 of 168
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21.
Frequency Justification Number J21 - Cold Shutdown Justification Components:
HCV-344, HCV-345 IA-HCV-344-C, IA-HCV-345-C Function:
Containment Spray (CS) Header Isolation Valves Instrument Air Accumulator Check Valve Class:
2 HCV-344, HCV-345 2 IA-HCV-344-C, IA-HCV-345-C l
Test Requirements:
Quarterly Stroke-Timing in Both the Open and Closed Directions for HCV-344 and the Open Direction Only for HCV-345. Quarterly Exercising to the Closed Direction for IA-HCV-344-C and IA-HCV-345-C.
Basis for Justification:
Valves HCV-344 and HCV-345 serve as CS isolation.
These valves cannot be stroke-tested Quarterly during power operation since the potential for spraying down the Containment is greatly increased.
Spraying down the Containment could cause equipment damage, electrical grounds and unnecessary corrosion (due to electrical shorts) to equipment and equipment malfunctions and unnecessary plant trips. These valves represent the only boundary between the CS and SI pump headers and the CS notzles when manual valves SI-177 and SI-178 are open. The valves cannot be partial-stroked for the same reason.
Valves IA-HCV-344-C and IA-HCV-345-C are the IA accumulator check valves for process valves HCV-344 and HCV-345, and function to i
allow the valves to be closed on loss of IA, if required.
These
)
check valves cannot be exercised Quarterly as required as this would stroke the process valves, HCV-344 and/or HCV-345.
Alternate Testing:
Valve HCV-344 shall be stroke-timed in both the open and closed directions during Cold Shutdown.
HCV-345 shall be stroke-timed in the open direction during Cold Shutdown.
The IA check valves IA-HCV-344-C and IA-HCV-345-C shall be exercised in the closed direction during Cold Shutdown.
l R2 June 15, 1995 Page 100 of 168
22.
Frequency Justification Number J22 - Cold Shutdown Justification Components:
HCV-347, HCV-348 Function:
Shutdown Cooling from Loop Isolation Valves Class:
1 Test Requirements:
Quarterly Stroke-Timing in the Closed Direction Basis for Justification:
These valves cannot be Quarterly stroke-timed closed during power operation because they are interlocked closed to ensure the integrity of the pressure boundary between Class 2501 and Class 301 piping when the RCS pressure is > 250 psia.
Alternate Testing:
These valves will be stroke-timed in the closed direction during Cold Shutdown prior to initiating Shutdown Cooling (<300*F and
<250 psi) while the Steam Generator is still available for removing decay heat from the primary system.
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- 23. -
Frequency Justification Number.J23 - Cold Shutdown Justification Components:
HCV-425A, HCV-425B, HCV-425C, HCV-425D Function:
Inlet and Outlet Isolation Valves to SI Tank Leakage Coolers Class:
2 Test Requirements:
Quarterly Stroke-Timing in the Closed Direction Basis for Justification:
These valves serve to isolate Containment Penetrations M-39 and M-53, Component Cooling Water (CCW) System penetrations.
They l
cannot be Quarterly stroke-timed closed during power operation because failure of these valves in the closed position would terminate cooling flow to Safety Injection Tank leakage. coolers.
This would have the potential for lifting the relief valve (SI-222) to the Reactor Coolant Drain Tank (RCDT) which could
)
eventually cause reactor coolant to overflow to the Containment i
floor, causing a Ventilation Isolation Actuation Signal (VIAS).
)
These valves cannot be partial-stroked because they are either fully opened or fully closed.
Alternate Testing:
These valves will be stroke-timed in the closed direction during Cold Shutdowns.
i R2 June 15, 1995 Page 102 of 168
24.
Frequency Justification Number J24 - Refueling Outage Justification Components:
HCV-438A, HCV-438B, HCV-438C, HCV-4380, IA-HCV-438B-C, IA-HCV-4380-C Function:
RCP Cooler Isolation Valves, Instrument Air Supply Check Valves Class:
2 (HCV-438A, HCV-438B, HCV-438C, HCV-4380) 3 (IA-HCV-438B-C, IA-HCV-438D-C)
Test Requirements:
HCV-438A, HCV-438B, HCV-438C and HCV-438D are Required to be Stroke-Timed Both in the Open and Closed Directions Quarterly.
IA Accumulator Check Valves (IA-HCV-4388-C and IA-HCV-438D-C) are Required to be Exercised Quarterly in the Open and Closed Directions.
Basis for Justification:
These valves serve to isolate Containment Penetrations M-18 and M-19, RCP seal cooling water. Exercising these valves would isolate cooling water flow to the RC Pumps which could damage the pumps if they are operating.
RC pump failure during power operation could result in a plant shutdown.
Therefore, it is not practical to exercise these valves Quarterly during power operations. During some Cold Shutdowns, Reactor Coolant temperature may be held above 130'F and plant conditions may not allow further cooldown or stopping all RC pumps.
Exercising these valves during Cold Shutdowns when RC temperature is greater than 130*F or when any RC pump is running could result in RC pump damage.
Therefore, it is not practical to exercise these valves when those plant conditions exist.
These valves cannot be i
partial-stroked because they are either fully opened or fully closed.
The IA accumulator check valves cannot be exercised Quarterly during power operation as exercising these check valves will cause cycling of the process valves.
R2 June 15, 1995 Page 103 of 168
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J24.
Frequency Justification Number J24 - Refueling Outage Justification (Continued) r Alternate Testing:
Valves HCV-438A, HCV-438B, HCV-438C and HCV-438D will be-stroke-tined in both the open and closed directions during Cold Shutdown, provided the RCS is depressurized, RCS temperature is less than 130*F, and the RCPs are secured.- IA accumulator check valves (IA-HCV-4388-C, IA-HCV-438D-C) will be exercised closed f
during Cold Shutdown, provided the RCS is depressurized, RCS temperature is less than 130*F and the RCPs are secured.
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25.
Frequency Justification Number J25 - Cold Shutdown Justification DELETED l
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-26.
Frequency Justification Number J26 - Cold Shutdown Justification Components:
HCV-1041A, HCV-1042A Function:-
i Main Steam Isolation Stop Check Valves i
Class:
2 Test Requirements:
Quarterly Stroke-Timing in the Closed Direction Basis for Justification:
cannotbetestedQuarterlyduringpoweroperationbecausedoingsol These valves serve to isolate the Main Steam (MS) headers. They r
would isolate steam flow in the Steam Generators and result in a turbine and reactor trip. These valves cannot be partial-stroked i
because they are either fully opened or fully closed.
Alternate Testing:
These valves will be stroke-timed in the closed direction during Cold Shutdown.
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27.
Frequency Justification Number J27
' Cold Shutdown Justification Components:
HCV-1041C, HCV-1042C
{
Function:
l Main Steam Isolation Bypass Valves Class:.
2 Test Requirements:
j Quarterly Stroke-Timing in the Closed Direction Basis for Justification:
These valves serve to provide a pathway from the Steam Generators to the steam dump and bypass valves in the event that the Main l
Steam-Isolation Valves (MSIV) close. -Stroke-timing these valvee Quarterly during power operation is not acceptable because the i
valves are interlocked closed when the MSIVs are open.
Bypasst ;
this interlock could cause the MSIVs to close, causing the turbine to trip and resulting in a reactor trip. The valves.cannot be-j partial-stroked for the same reason.
1
-Alternate Testing:
These valves.will be stroke-timed in the closed direction during.
Cold Shutdown.-
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28.
Frequency. Justification Number J28 - Cold Shutdown Justification p
Components:
HCV-1385, HCV-1386 HCV-1103, HCV-1104, HCV-1105, HCV-1106 l
Function:
Main Feedwater Isolation Valves Class:
2 N
I Test Requirements:
Quarterly Stroke-Timing in the Closed Direction Basis for Justification:
Valves HCV-1385, HCV-1386, HCV-1103, HCV-1104, HCV-1105 and l
HCV-1106 cannot be stroke-timed Quarterly during power operation because doing so would isolate feedwater to Steam Generators resulting in a reactor trip. These valves cannot be partial-stroked because they are either fully opened or fully closed.
Alternate' Testing:
These valves will be stroke-timed in the closed direction during Cold Shutdown.
R2 June 15, 1995 Page 108 of 168
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Frequency Justification Number J29 - Cold Shutdown Justification DELETED 1
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30.
Frequency Justification Number J30 - Refueling Outage Justification Components:
PCV-1849A, PCV-1849B Function:
Instrument Air Containment Isolation Valves Class:
2 Test Requirements:
Quarterly Stroke-Timing in the Closed Direction Basis for Justification:
These valves serve to isolate IA pressure (via Penetration M-73) to containment systems. PCV-1849A (inboard) and PCV-18498 (outboard) were added during the refueling and maintenance outage (Fuel Cycle 12) in 1988 by Modification MR-FC-88-11 (0SAR 87-10).
Stroke-timing cannot be performed Quarterly during power operations or Cold Shutdown with RCS temperature greater than 130*F and the RCS is not depressurized.
The valves cannot be partial-stroked, because they are either fully opened or fully closed.
The closing of these valves could:
(1) cause fluctuations in the pressure control of the pressurizer (PCV-103-1, PCV-103-2),
(2) result in damage to RCP seals (HCV-241),
(3) disrupt RCS letdown to the Chemical Volume Control System (CVCS)(TCV-202,LCV-101-1,LCV-101-2),
l l
(4) damage the Nuclear Detector instrumentation (HCV-467A/C),
l l
(5) cause level fluctuation in the SI Tank level (HCV-2916, l
l HCV-2936,HCV-2956,HCV-2976),and (6) cause loss of the Steam Generator Blowdown (HCV-1387A and HCV-1388A).
The ripple effect caused by the exercise stroking of PCV-1849A/B would be detrimental during power operation or when in Cold Shutdown with RCS temperature greater than 130'F and not depressurized.
R2 June 15, 1995 Page 110 of 168
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30..
Frequency Justification Number J30 - Refueling Outage Justification-(Continued)
Alternate Testing:
These valves will be stroke-timed in the closed direction during Cold Shutdown when the RCS temperature is less than 130*F with RCPs off and the RCS depressurized.
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R2 June 15, 1995 Page 111 of 168 i
31.
Frequency Justification Number J31 - Cold Shutdown Justification Components:
L HCV-2506A, HCV-2506B, HCV-2507A, HCV-25078 Function:
Steam Generator Blowdown Sample Isolation Valves Class:
2 Test Requirements:
Quarterly Stroke-Timing in the Closed Direction Basis for Justification:
These valves serve to isolate Steam Generator Blowdown sampling lines.
These valves cannot be Quarterly stroke-timed during power operation because doing so would terminate blowdown sample-line flow. The Steam Generator Blowdown activity monitor is on the sample line. Technical Specification 2.9(1)e recuires that blowdown activity shall be continuously monitorec by the Steam Generator Blowdown Sample Monitoring System when blowdown is i
occurring.
Steam generator blowdown is a continuous function at FCS. Partial-stroking cannot be performed since these valves are i
either fully opened or fully closed.
Alternate Testing:
j These valves will be stroke-timed in the closed direction during Cold Shutdown.
R2 June 15, 1995 Page 112 of 168
32.
Frequency Justification Number J32 - Cold Shutdown Justification DELETED l
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33.
_ Frequency ~ Justification Number J33 - Cold Shutdown Justification Components:
IA-HCV-238-C, IA-HCV-239-C-
-Function:.
Instrument Air Supply Check Valves Class:-
3 Test Requirements:
Quarterly Full-Stroke Exercising in Both the Open and Closed Directions Basis for Justification:
These valves are check valves on IA accumulators attached to i
HCV-238 and HCV-239, which are located inside the Containment.
The process valves (HCV-238 and HCV-239) are remotely stroke-tested in both the open and closed directions Quarterly, but due to inaccessibility during power operation, the check valves are not able to be tested.
i Alternate Testing:
These check valves will be full-stroke exercised in the open and l
closed directions at Cold Shutdown.
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R2 June 15, 10"b Page 114 of 168
34.
Frequency Justification Number J34 - Cold Shutdown Justification Components:
IA-HCV-385-C, IA-HCV-386-C HCV-385, HCV-386 Function:
Instrument Air Supply Check Valves SIRWT Minimum Recirculation Isolation Valves Class:
3 (IA-HCV-385-C, IA-HCV-386-C) 2 (HCV-385, HCV-386)
Test Requirements:
Quarterly Full-Stroke Exercising in Both the Open and the Closed Directions.
Quarterly Stroke Timing in Both the Open and the Closed Directions.
Basis for Justification:
These valves (IA-HCV-385-C and IA-HCV-386-C) are check valves on IA accumulators attached to HCV-385 and HCV-386 (Safety Injection Mini Flow Bypass Isolation Valves). The test methodology for the IA accumulator check valves requires the process valves to be closed greater than one hour each. This isolates the SI miniflow recirculation line, which, if the SI pumps start, could cause these pumps to operate at shutoff head.
Therefore, the check valves are not able to be tested Quarterly.
Running the SI pumps at shutoff head could cause the pumps to overheat and cavitate.
Prolonged closure of these valves could cause equipment damage.
These valves (HCV-385 and HCV-386) are Safety Injection Minimum Recirculation Flow isolation valves to the SIRWT (SI-5). The test methodology for these valves requires these valves to be stroke tested closed which isolates the SI pump minimum recirculation flow path. During the time where one er both minimum-4 recirculation isolation valves are closed and a real or inadvertent start of a Safety Injection Pump occurs the pump would be deadheaded.
This could cause damage to the SI pump and potentially degrade the margin of safety inherent to the SI system.
Although the probability that a small Break LOCA would occur at the same time is very remote.
Fort Calhoun Station has decided to stroke time HCV-385 and HCV-386 during Cold Shutdown.
It is also important to know that during normal operations valves HCV-385 and HCV-386 are Normally Open, Fail Open, and are only).
required to close during a Recirculation Actuation Signal (RAS R2 June 15, 1995 Page 115 of 168
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i 34.
-Frequency Justification Number J34 - Cold Shutdown Justification
.(Continued)
Fort Calhoun Station is confident that performing the' stroke testing of HCV-385 and HCV-386 during Cold Shutdown, in accordance with the ISI Program Plan, will provide an acceptable alternative test frequency.and will provide a reasonable assurance of the ability of.the valves to function as required during a' design accident condition.
Alternate Testing:
These valves-(IA-HCV-385-C and'IA-HCV-386-C) will beifull-stroke exercised in the open and closed directions at Cold Shutdown.
Valves HCV-385 and HCV-386 will be stroke-timed in both the open and closed directions at Cold Shutdown.
R2 June 15, 1995 Page 116 of 168 l
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'35.-
Frequency' Justification Number.J35 - Cold Shutdown Justification l
Component:
f CH-166 Function:
Volume Control Tank Outlet Check Valve Class:
2 l
Test Requirements:
'l Quarterly Full-Stroke Exercising in the Closed Direction Basis for Justification:
This check valve serves to prevent a divergent path from the Boric Acid Injection system to the VCT. A divergent path may reduce the concentration of boric acid required to be injected into the RCS.
i This check valve cannot be full-stroke exercised in the closed direction Quarterly during power operation.
The only flow path l
through this valve is to the RCS, and would result in injecting highly concentrated boric acid into the RCS.
Injecting concentrated boric acid into the RCS during power operation could cause an uncontrolled reactivity excursion, a plant shutdown or a plant trip.
Alternate Testing:
Valve will be full-stroke exercised in the closed direction during q
Cold Shutdown frequency in accordance with the FCS ISI Program
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- 36. -
Frequency' Justification Number J36
. Refueling Outage Justification i
Components:
SI-135, SI-143, SI-149 l
i Function:
1 Containment Spray Pump Discharge Check Valves Class:
l l
2 l
Test Requirements:
Quarterly Full Flow Exercising;in both the Open and Closed Directions Basis for Justification:
These valves cannot be full-stroke exercised open or close Quarterly during power operation because the only full flow path is into the CS headers.
This would result in the spraying down of the. equipment in containment, possibly causing equipment damage and requiring extensive cleanup. Also, these valves cannot be s
aartial-stroke exercised during the Quarterly CS pump tests
)
3ecause the minimum flow lines branch off upstream of the check l
valves and therefore no flow occurs through these valves.
Using the discharge tap downstream of the minimum flowlines will overflow the floor drains in the Auxiliary Building potentially creating an increase in radioactive contamination and background 1
radiation levels.
Alternate Testing:
Valves will be full-stroke exercised in the open and closed directions during Cold Shutdown when the CS pumps are able to be aligned for shutdown cooling to the Shutdown Cooling Heat 1
Exchangers (< 120*F primary temperature), in accordance with the FCS Technical Specifications.
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R2 June 15, 1995 Page 118 of 168
37.
Frequency Justification Number J37 - Cold Shutdown Justification DELCTED l
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- 38.
Frequency Justification Number J38 - Cold Shutdown ~ Justification j
4 Components:
IA-PCV-6680A-1-C, IA-PCV-6680A-2-C, IA-PCV-66808-1-C,-
IA-PCV-66808-2-C, and IA-PCV-6682-C-j IA-HCV-1107A-C, IA-HCV-11078-C, IA-HCV-1108A-C j
IA-HCV-11088-C, IA-FCV-1368-C,- and IA-FCV-1369-C Function-These check valves are' Instrument Air supply header check valves i
for dampers PCV-6680A-1, PCV-6680A-2, PCV-66808-1, PCV-6680B-2,.
andPCV-6682(ControlRoomHVACdampers).
l These check valves are Instrument Air (IA) supply header check valvesforAuxiliaryFeedwater(AFW)isolationvalvesHCV-1107A/B and HCV-1108A/B and for the AFW pumps FW-6 and FW-10 recirculation isolation valves.
Class:
3 Test Requirements:
j
~
Quarterly Full Flow Exercising in the Closed Direction Basis for Justification:
l These valves-(IA-PCV-6680A-1-C/-2-C, -66808-1-C/-2-C and j
IA-PCV-6682-C) cannot be exercised. Quarter.ly during power.-
operation, as exercising these check valves will cause isolation of-the Control Room (CR) air filtration-dampers.
Failure of the CR air filtration dampers in a non'-conservative position would cause the CR filtration system to be inoperable. This-would-require the plant to be in Cold Shutdown per Technical 1
Specification (TS) 2.12.
Failure of the dampers'in the OPEN position would not allow the CR to be isolated during a toxic gas release. This would result in entry into Technical Specification l
2.0.1.
i Check valves IA-HCV-1107A/B-C, -1108A/B-C, and FCV-1368-C/1369-C cannot be exercised Quarterly during power operation as exercising these check valves will cause possible' isolation of AFW and render-the AFW system inoperable for an extended period of time, possibly requiring the' plant to be in Cold Shutdown.per Technical Specification 2.5.
Failure of the isolation valves in the open direction would not allow the required flow rate to the Steam Generator assuming loss of FW-10.
This would result in entry into Technical Specification 2.0.1, i.e., Notification of Unusual Event (NOVE).
R2 June 15, 1995 Page 120 of 168
> 38.'
Frequency. Justification Number J38 - Cold Shutdown Justification l
-(Continued)
[
Alternate Testing:
Check valves.IA-PCV-6680A-1-C, IA-PCV-6680A-2-C, IA-PCV-66808-1-C, IA-PCV-66808-2-C,'and IA-PCV-6682-C will be full-stroke exercised in the closed direction during Cold Shutdown.
IA-HCV-1107A-C, IA-HCV-11078-C, IA-HCV-1108A-C, IA-HCV-11088-C, IA-FCV-1368-C, and IA-FCV-1369-C will be full-stroke exercised in both the open and closed directions during cold shutdown.
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39.
Frequency Justification Number J39 - Refueling Outage Justification Components:
HCV-1041B, HCV-1042B Function:
Main Steam Stop Check (Reverse Flow) Valve Class:
2 Test Requirements:
Quarterly Reverse Full Flow Test Exercise Basis for Exception from O&M Part 10, Subsection 4.3.2.4:
These check valves are swing type check valves which are installed to provide a positive isolation of the Steam Generators.
If Main Steam (MS) header pressure is greater than Steam Generator I
pressure, the check valves prevent reverse back flow into a faulted Steam Generator. The corrective maintenance history of these two check valves has been limited to gasket / bolt / nut replacements since installation.
In addition, the check valves are 28 inch carbon steel Ametek, Inc. type check valves which see flow during normal operations. OPPD has previously disassembled and inspected each of these check valves once and the check valves were acceptable.
"Like new" is defined as a condition of the component that has visible indication of wear, but the valve is able to function as required.
In order to assess the condition of the check valves during sample disassembly and inspection and to l
provide a consistent and precise method of gauging the check valves physical and mechanical condition, a check list was developed and incorporated into the surveillance tests used for sample disassembly and inspection. An example of items evaluated on the check list are:
i 1
Whether valve discs are initially seated 2
A determination of obstructions 3
Cracking or linear indications 4
Loose / missing / broken parts 5
Whether obstruction to moving parts 6
Wear / Corrosion / Erosion 7
Presence of foreign material 8
Misalignment (if any) and effect on valve operation 9
Mechanical damage 10)
Hinge Pin condition 11)
Disc / seat condition 12)
Perform manual exercise of discs.
Each check valve has been disassembled and inspected in the previous outages. The assessment of the valves' mechanical and R2 June 15, 1995 Page 122 of 168
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39.
Frequency Justification Number J39 - Refueling Outage Justification (Continued) physical condition is performed by FCS Inspectors qualified to VT-3 in accordance with ASME Section XI.
In addition, the review / evaluation of any observed deficiencies / indications is performed by Engineering for a final acceptance of the valves condition.
In addition a review of the installation of each check valve has been addressed using the "EPRI Applications Guideline for Check Valves in Nuclear Power Plants" and appropriate actions havebeentaken(i.e.,PreventiveMaintenance(PM) inspections)as a result of the completion of the design application for the check valves.
Disassembly and reassembly of both valves (i.e., every Refueling Outage) introduces unnecessary potential for valve failure due to damage caused by maintenance without providing a commensurate increase in plant safety or check valve reliability.
These check valves cannot be exercised Quarterly during power operation because doing so would cause steam to be isolated to the Main Steam header, causing the turbine to trip and resulting in a reactor trip.
It is impractical to reverse flow test these check valves during Cold Shutdown; to do so would require the downstream side of the valves to have reverse flow sufficient to close the
~600 pound, 28-inch disks.
To close these disks would require extensive modifications to the secondary side of the Main Steam system to permit sufficient oP to close the valve disks. Another method would be to fill the downstream side of the valve disks with fluid.
To do this would require extensive piping and support modifications because of excessive loading on the Main Steam piping.
To perform any type of successful reverse flow test on these check valves would require extensive plant modifications and manpower, and would subject the Main Steam system to potentially detrimental conditions, without providing a commensurate increase in public safety or check valve reliability.
Alternate Testing:
Check Valves HCV-1041B and HCV-1042B will be alternately disassembled and inspected one each Refueling Outage.
Sample i
disassembly of these check valves is in accordance with 0&M Part 10 and the NRC guidelines established in Generic Letter 89-04,, Position 2.
For an 18-month refueling cycle, this method of sample disassembly and inspection ensures that each check valve is disassembled and inspected at least once every three years.
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40.
Frequency Justification Number J40 - Cold Shutdown Justification Components:
l LCV-383-1, LCV-383-2, HCV-383-3, HCV-383-4 IA-LCV-383-1-C, IA-LCV-383-2-C Functions:
l LCV-383-1, LCV-383-2; SIRWT Isolation Valves l
HCV-383-3, HCV-383-4: Containment Sump Isolation Valves LCV-383-1-C, LCV-383-2-C; Instrument Air Supply Check Valves Class:
2(LCV-383-1,LCV-383-2,HCV-383-3,HCV-383-4) 3 (IA-LCV-383-1-C, IA-LCV-383-2-C)
Test Requirements:
LCV-383-1, LCV-383-2; Quarterly stroke timing in both the Open and the Closed directions HCV-383-3, HCV-383-4; Quarterly stroke timing in the Open directions LCV-383-1-C, LCV-383-2-C: Quarterly full-flow exercising in both the Open and Closed directions Basis for Justification:
Tech Spec implications OP-ST-SI-3001, Attachment 5, prior to PC 42612 contained a caution stating that " Closing LCV-383-1 renders LPSI Pump SI-18, HPSI Pump SI-28, and CS pumps SI-3C and 3B IN0PERABLE." The applicable Limiting Conditions for Operation (LCO) action statements of Technical Specifications 2.1.1, 2.3, 2.4 and 2.7 must be implemented.
Technical Specification 2.3(2) specifically states that during power operation, the Minimum Requirements may be modified to allow one of the following conditions to be true at any one time.
If the system is not restored to meet the minimum....
...a. One low-pressure safety injection pump may be inoperable provided the pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
...b. One high-pressure safety injection pump may be inoperable provided the pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I R2 June 15, 1995 Page 124 of 168
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40.
Frequency Justification Number J40 - Cold Shutdown Justification
+
- (Continued)
By performing this test at power, two provisions of Tech Spec 2.3(2) are violated concurrently, requiring entry into Technical Specification 2.0.1.
Safeauards Imolications Operations reviewed the possibility of utilizing a' dedicated operator during performance of this surveillance test.
Using the guidance of the NRC Generic Letter 91-18, Operations Memo 93-11, and Standing Order G-100 (approved and issued),.the following conclusions can be drawn.
The Generic Letter information is explicit in stating that, generally, equipment is inoperable during surveillance.
The use of a dedicated operator must be reviewed to ensure that the operator and his necessary actions would result in a configuration where the system did not need to be considered inoperable.
In the case of LCV-383-1 and -2, this determination cannot be made.
Even if a dedicated operator were stationed at the valve and were to immediately return the valve to an open condition in the event of an accident signal, the open travel time of the valves is roughly 30 seconds. The sequencer timer for a HPSI pump is approximately 3 seconds, with LPSI pumps following shortly in less than 15 seconds. Adding in reaction time of the operator, even a few seconds, there is a high probability that more than one SI pump would start without a suction source.
Practically speaking, the most prudent action to prevent equipment damage would be to place the respective pumps in pull-out. This, however, renders the pumps inoperable and the Tech Specs noted above apply.
Thus, no positive operability determination can be made; instead, Tech Spec 2.0.1 again applies, j
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Testing of HCV-383-3 and -383-4 is performed in conjunction with l
the testing of LCV-383-1 and -383-2 (during the time frame when l
these valves are closed) because of the possibility that the check j
valves in the recirculation lines may not' hold.
If the check l
valve did not hold, and LCV-383-1 or -2 was left open, cycling HCV-383-3 or -4 to the open position could result in backing the SIRWT up into the containment sump. Among possible consequences of this, violating the Technical Specification on SIRWT level is one possibility.
Consequently, it is preferable to close LCV-383-1/2 during cycling of HCV-383-3 or -4.
Closing LCV-383-1/2 during power operation results in entry to Tech Spec LCO 2.0.1 (see discussion for LCV-383-1/2, above).
R2 June 15, 1995 Page 125 of 168
40.
Frequency Justification Number J40 - Cold Shutdown Justification (Continued)
Testing of LCV-383-1-C and -383-2-C is performed to demonstrate the ability of the instrument air check valve'to isolate instrument air and continue to hold the valve closed with backup nitrogen.
The )urpose of the test is to demonstrate the ability of nitrogen to 1old the valve closed, and thus must be performed with LCV-383-1/2 in the closed condition.
The closure of LCV-383-1/2 during power operation results in entry to Tech Spec 2.0.1 (see discussion for LCV-383-1/2, above).
Therefore, testing of these check valves must be deferred to a Cold Shutdown / Refueling condition.
Alternate Testing Valves (LCV-383-1, LCV-383-2) shall-be stroke-timed in both the open and closed directions at cold shutdown frequency.
Valves (HCV-383-3, HCV-383-4) shall be stroke-timed in the open direction at Cold Shutdown frequency.
Valves (LCV-383-1-C, LCV-383-2-C) shall be exercised'in the open and closed directions at Cold Shutdown frequency.
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41.
Frequency Justification Number J41 - Refueling Outage Justification Components:
HCV-482A, HCV-4828, HCV-483A, HCV-483B, HCV-2808C, HCV-28080, j
HCV-2809C, HCV-2809D, HCV-2898C, HCV-2898D, HCV-2899C, HCV-2899D Functions:
HCV-482A, HCV-482B:
Shutdown Cooling (SDC) Heat Exchanger (HX), AC-4A, Backup Raw Water Inlet and Outlet Valves.
HCV-483A, HCV-483B:
Shutdown Cooling Heat Exchanger, AC-4B, Backup Raw Water Inlet and Outlet Valves.
HCV-2808C, HCV-2808D:
Low Pressure Safety Injection (LPSI) Pump SI-1A Bearing Cooling Backup Raw Water Inlet and Outlet Valves.
HCV-2809C, HCV-2809D:
Low Pressure Safety Injection (LPSI) Pump SI-1B Bearing Cooler Backup Raw Water Inlet and Outlet Valves.
HCV-2898C, HCV-2898D:
Control Room VA Unit VA-46A Backup Raw Water Inlet and Outlet Valves.
HCV-2899C, HCV-28990:
Control Room VA Unit VA-46B Backup Raw Water Inlet and Outlet Valves.
Class:
3 Test Requirements:
Quarterly exercising in the Open and Closed directions.
Basis for Justification:
The subject valves are locally operated by air and provide backup Raw Water (RW) for cooling plant loads such as Control Room HVAC, LPSI Bearin Water (CCW)g Coolers, SDC HX normally cooled by Component Cooling in the event of a loss of CCW for an extended period of time.
The valves cannot be exercised quarterly or during Cold Shutdown because the performance of this test requires a complete RW outage and securing CCW so as to not allow nitrates to contaminatetheriverwater,(whichisanenvironmentalconcern),
nor to contaminate the CCW system with sand from the RW system.
F The RW system must be secured and drained as much as practical and l
the CCW system pressure must be low so as not to contaminate the RW system.
Securing CCW and RW during every Cold Shutdown may not be practical due to the high decay heat experienced during Cold Shutdowns of short duration.
i R2 June 15, 1995 Page 127 of 168
4 41.
Frequency Justification Number J41 - Refueling Outage Justification (Continued)
Alternate' Testing:
W These valves'will be' manually exercised in' both the open and -
closed directions during Refueling Outages.
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42.
Frequency Justification Number J42 - Cold Shutdown Stroke Test frequency DELETED l
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F 43.:
Frequency Justification Number J43 - Cold Shutdown Frequency Components:
NG-142, NG-144', NG-146, NG-148 Function:
Nitrogen supply to.the Safety-Injection (SI) tanks (SI-6A, SI-68,.
SI-6C, and SI-6D) check valves.
Class:
3 Testing Requirements:
Quarterly full-stroke exercising in the Close direction.
Basis for Justification:
Check valves NG-142, NG-144, NG-146 and NG-148 function to prevent backflow through the check valves and the nitrogen (Ng) supply to the SI Tanks during an accident condition.
The check valves prevent loss of N2 from the SI Tanks during an accident condition.
These check valves cannot be full-stroke exercised Quarterly, as the containment _would be inaccessible during power operation and the SI Tanks would be required to be made inoperable in order to perform this test. The SI Tanks are required to function in order to provide adequate protection to_the plant personnel and the general public during a postulated loss of coolant accident (LOCA). Check valves will be partial-stroke exercised quarterly, during normal plant operations or. using a PM0 procedure as required in order to ensure that the check valves are partially stroke exercised at least quarterly.
Alternate Testing:
Check valves, NG-142, NG-144, NG-146 and NG-148 will be partial-stroke exercised quarterly during power operation in the-open and close directions using normal plant operations / logs. The check valves will be full-stroke exercised open and closed during Cold Shutdowns.
R2 June 15, 1995 Page 130 of 168
APPENDIX 2B JUSTIFICATION FOR EXCEPTION TO ASME SECTION XI/O&M MANUAL PARTS 1 AND 10, CODES FOR VALVES R2 June 15, 1995 Page 131 of 168
i l
l JUSTIFICATION FOR EXCEPTION l
TO ASME SECTION XI/0&M PARTS 1 AND 10 CODES FOR VALVES i
This section provides justification for the exceptions taken to Code test requirements as allowed for in 10CFR50.55a(g)(5)(iii).
Each Code exception is l
identified by a unique number and identifies the valve (s) for which the Code exception is being taken.
The specific Code test requirement found to be impractical is defined and the basis for exclusion from Code requirements is presented. Any testing performed in lieu of Code requirements.is specified.
i Two types of justifications are provided. The first is general in nature and i
pertains to Code requirements found to be impractical for numerous valves.
l The second type is used to justify Code exceptions for specific valves.
Code exceptions for specific valves are numbered (Ex) and referenced by number on the Valve Test Program Matrix Table 2.1 for specific valves.
General: Code Exception Number G1 Components:
l Category C Thermal Relief Valves I
Function:
Thermal relief valves on safety-related systems
]
Class:
i 1, 2, and 3 Test Requirements:
0&M Part 1 Subsection 1.1 Scope Basis for Exception from 0&M Part 1, Subsection 1.1:
The 0&M Code Part 1 provides general requirements for periodic performance testing and monitoring of pressure relief devices utilized in nuclear power plant systems which are required to perform a specific function in shutting down a reactor or in mitigating the consequences of an accident. Thermal relief valves will not be tested in accordance with 0&M Part 1 guidance as part of the FCS ISI Program Plan, as FCS has determined that the thermal relief valves do not fully meet the intent of the scope of O&M Part 1.
Many safety-related systems, particularly those with heat exchangers, have been provided with relief valves. These relief valves are thermal relief valves of small capacity intended to relieve pressure due to a thermal expansion of fluid.in a
" bottled-up" condition, which is considered a self-limiting transient. Experience has shown that failure of these valves will i
not result in a failure of the system to fulfill its safety function.
Thus, most thermal relief valves are not cons.idered to perform a function "important to safety", and as such have not been included in the FCS ISI Program Plan.
R2 June 15, 1995 Page 132 of 168
1 I
I General: Code Exception Number G1 (Continued)
Further. clarification was provided in the NRC SER (Reference 7),
for applicability to the Section XI Code.
Thermal relief valves installed to protect portions of safety-related systems against i
overpressure may be included in this expanded scope. The relief-j valves that may be involved are those that meet the following criteria:
I a.
The relief valve protects a portion of a safety -
related system, 1
b.
The protected piping and/or component may be isolated i
during a plant operating mode where credit is taken A
for. operation of the safety-related system, c.
The protected section is subjected to a mechanism that could over pressurize the system / component when
- isolated, l
d.
The integrity of the protected section is required for the system to meet its safety function, (i.e., stuck.
open relief valve).
1 A safety-related valve is defined as an active or passive valve which is required to )erform a specific function in shutting down i
the reactor to cold slutdown condition, in maintaining the Cold Shutdown condition, or in mitigating the consequences of an accident. Relief valves which protect over-pressurization of portions of systems / components that perform a safety related i
function are included.
Because some thermal relief valves at FCS may be included in the expanded scope discussed above, general relief was not granted as l
requested for all thermal relief valves.
A request was made that j
the licensee provide further justification for exclusion of relief valves from the Section XI Program based on the criteria mentioned-above.
An engineering (Class 1, 2, and 3) relief valves at Fort Calhoun review was completed for all Critical Quality Element (CQE)
Station with the provided guidance in addition to the OM-1 Code 1
guidance. The thermal relief valves which have been excluded from the Section XI program were excluded for the following reasons.
Justification:
i i
1.
The relief valve protects Class 1, 2, or 3 (Class Code) systems / components that.are not required to shutdown the plant / reactor, maintaining the
)
plant / reactor in a shutdown condition or mitigate an j
accident.
-l l
R2 June 15, 1995 Page 133 of 168
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General: Code Exception Number G1 (Continued)
OR 1
2.
The relief valve is. installed on safety related systems / components which are not isolated during the operating cycle and are therefore not subjected to a mechanism that could cause over. pressure.
In addition, the integrity of the protected section.
(i.e., stuck open relief valve) is not required for-the system to meet its safety function, nor.will-loss of integrity render the system inoperable.
1 OR 3.
The relief valve is installed on safety related i
systems / components, which are not subjected to any i
overpressure mechanism due to system design.
Justification for Exclusion from the FCS ISI Program Plan:
AC-166, AC-167, AC-168, AC-169, AC-291, AC-292, AC-P.93, and AC-294 j
RCP RC-3A/B/C&D Seal Cooler CCW Inlet Relief Valves RCP RC-3A/B/C&D Lube Oil Cooler CCW Inlet Relief Valves l
Justification:
1 TheReactorCoolantPumps(RCPs)arenotrequiredforsafe shutdown of the plant. The USAR assumes that only natural circulation is available for the RCS to cool down. Hence, the portion of the CCW system protected by these relief valves is not required. Although this portion of the CCW system is. isolable, this portion of the CCW system is never isolated with the RCPs in operation.
t AC-170 and AC-183 1
Sample Heat Exchanger SL-8A and SL-8B CCW Inlet Relief Valve
]
(Secondary)
Sample Heat Exchanger SL-3 CCW Inlet Relief Valve (Primary)
Justification:
1&2 I
These sample heat exchangers are not required for safe shutdown of l
the plant nor do they protect equipment which mitigate an accident. The inlet and outlet isolation valves are administrative 1y controlled open during the operating cycle.
)
1
)
.R2 June 15, 1995 Page 134 cf 168 i
l 1
/
General: CodeExceptionNumberGl.(Continued)
AC-173 and AC-178 Waste Gas Compressor WD-28A & B Seal Water Heat Exchanger CCW Inlet Relief Valves 1
/ Justification:
'l & 2 The Waste Gas Compressors are not required for safe shutdown of the plant.nor do they protect equipment which mitigate an-accident.
The inlet and outlet isolation valves are-E administratively controlled open during the-operating cycle.
l AC-258 i
Letdown Heat Exchanger CH-7 CCW Inlet Relief Valve Justification:
1&2
^
The Letdown Heat Exchanger is not-required for safe shutdown of the plant nor is it utilized in mitigation of an accident.
In addition, the portion of the system remains in service during the
[
operating cycle and therefore is not subjected to an-overpressurization mechanism.
AC-336, AC-337, and AC-338 Charging Pump CH-1A, B, & C Oil Cooler CCW Inlet Relief Valves j
Justification:
2 This portion of the CCW system remains inservice during the operating cycle. Hence this section of the CCW system are.
administratively controlled open on the inlet and outlet piping of the cooler to the rest of the CCW system. This section of piping is not subjected to an overpressurization mechanism.
AC-1026, AC-1027 and AC-1059 j
Shutdown Cooling Heat Exchanger AC-4A & B CCW Relief Valves Spent Fuel Pool Heat Exchanger AC-8 CCW Relief Valve Justification:
3 i
Due'to the design of'the isolation / flow control valves, these components and piping are not subjected to an overpressurization mechanism.
The inlet isolation / flow control valves are Fisher.
Model 7620 series valves.
The type 7600 series butterfly valve is
)
a heavy-duty valve suitable for general control applications where l
j R2 June 15, 1995 Page 135 of 168
J
' General: Code Exception Number G1 (Continued) i extreme low leakage rates are not requi,'ed. This valve design is not equipped with a valve seat.
i
\\
(
Charging Pump CH-1A, B & C Suction Relief Valves Justification:
2 This portion of the CVCS Charging system. remains inservice during the operating cycle.
If the charging pump is.not inservice at the time, then the charging pumps-remain unisolated and in the standby condition. These pumps are taken out'of service routinely for-i maintenance due to the nature of positive displacement. charging i
pumps. However, when the charging pump.is isolated to be tagged.
i out of service, the tagcut requires that the system be drained and vented. Reference Computerized Tagging System for tagoat-of a charging pump.
Hence.this section of the CVCS Charging system remains open on the inlet and outlet piping of the charging pumps i
to the rest of the CVCS system. This section of piping is not subjected to an overpressurization mechanism.
CH-202 Reactor Coolant System Loop Charging System Bypass Valve / Thermal Relief Justification:
2 CH-202 is the Bypass valve _around CH-238. The Charging system loop injection headers into loop 1A and 18 are open during the operating cycle with at least 40 gpm charging flow. This_ system
)
is not taken out of service.
Hence, there is no j
overpressurization mechanism which requires CH-202 to open.
Failure of this spring loaded check valve to the open position would not prevent this system from performing it's design i
function.
{
CH-219 Charging Pumps Suction Relief Valve on Common Suction Header from VCT Justification:
2 This piping is continually in service during the operating cycle.
There is no overpressurization mechanism which will challenge this relief valve.
i R2 June 15, 1995 Page 136 of 168 i
General: Code Exception Number G1 (Continued)
CH-159, CH-223, and CH-224 VCT CH-14 Outlet Relief Valve Regenerative Heat Exchanger CH-6 Letdown Relief Valve Letdown Heat Exchanger CH-7 Letdown Relief Valve Justification:
1 The letdown portion of the CVCS system is not required to shutdown the plant, maintain the plant shutdown, or mitigate an accident.
Therefore, these thermal relief valvas do not meet the requirements of Section XI.
JW-4-1 and JW-4-2 Expansion Tank JW-1-1 and JW-2-1 Pressure Caps Justification:
3 These caps were not installed until 1988.
There is no operational significance for these caps.
The jacket water system runs at atmospheric pressure.
These caps were installed to prevent the jacket water from burping onto the floor after the diesel generator is shutdown.
If these caps would stick in the open or closed position, there would be no effect on the operation / operability of the cooling system.
Based on this lack of safety significance and affect these caps have of the jacket water system, there is no applicability to the Section XI Program.51-222 and 51-311 Safety Injection Tanks Fill / Drain Line Relief Valve SIRWT SI-5 Return Line Relief Valve Justification:
1 These portions of the Safety Injection system are not required to shutdown the plant, maintain the plant shutdown, or mitigate an accident.
Therefore, these relief valves do not meet the requirements of Section XI.51-278, SI-279, SI-280, and SI-281 Safety Injection Tank (SIT) SI-6A/B/C & D Outlet Relief Valves Justification:
3 These relief valves have a setpoint of 395 psig and are located on the discharge piping downstream of the Safety Injection Tanks (SIT) outlet isolation valves, (HCV-2914, HCV-2934, HCV-2954 and R2 June 15, 1995 Page 137 of 168
i i
. General:. Code Exception. Number G1 (Continued) i HCV-2974). The SIT. valves are locked open during the operating i
cycle.
Therefore overpressure protection is provided by the SITJ l
relief valves (SI-209^ SI-213,51-217, and SI-221) which are set-at a lower pressure of 275 psig. These relief valves are. tested j
in-the Section XI Program.' There is~no overpressure mechanism
-that subjects this portion of outlet piping to exceed the design pressure.
i Alternate Testing:
Tests and test frequency for thermal relief valves not~ included I
will be' controlled under the FCS Preventive Maintenance (PM).
Program and be conducted in a similar manner as the FCS-ISI Program Plan.-
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. 4 I
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4 R2 June 15, 1995 Page 138 of.168
1.
Code Exception Number E1 - Relief Request Components:
l SI-139, SI-140 Function:
SIRWT Discharge Check Valves Class:
2 Test Requirements:
Quarterly Full Flow Exercising in the Open Direction and Leakage Testing Once Every Two Years Basis for Exception from 0&M Part 10, Subsection 4.2.1.2:
These check valves function to prevent backflow to the Safety InjectionandRefuelingWaterTank(SIRWT). These check valves are located in the lines leading from the SIRWT to the suctions of the Containment Spray (CS) pumps, the Low Pressure Safety Injection (LPSI) pumps and the High Pressure Safety Injection (HPSI) Pumps. The check valves under certain accident conditions must open sufficiently to provide design basis flow to all of these pumps. Because of this system design requirement, the full-stroke exercising of these check valves Quarterly or during Cold Shutdowns cannot be performed.
During power operation, no full flow path exists for the combination of pumps because the l
l HPSI and LPSI pumps cannot overcome the RCS pressure, and the CS system cannot be permitted to spray down the Containment.
No full flow path is available during Cold Shutdowns because operating the HPSI pumps could create a low-temperature overpressurization condition in the RCS. CS cannot be used because the Containment would be sprayed down. Additionally, it is not possible to l
achieve the maximum design accident flow through the check valves during full flow exercising.
The corrective maintenance history of these two check valves has been limited to gasket / bolt / nut replacements since installation.
In addition, the check valves are 20 inch stainless steel Mission-Duochek type valves which see very little flow during normal operations. OPPD has previously disassembled and inspected each of these check valves once and these check valves were "like new."
"Like new" is defined as a condition of the component that has little or no visible indication of wear, as if the valve was just installed from the factory.
In order to assess the condition of the check valves during sample disassembly and inspection and, to provide a consistent and precise method of gauging the check R2 June 15, 1995 Page 139 of 168
1.
Code Exception Number E1 - Relief Request (Continued) valves physical and mechanical condition, a checklist was l
developed and incorporated into the Surveillance Tests used for sample disassembly and inspection.
An example of items evaluated on the check list are:
1.
Whether valve discs are initially seated 2.
A determination of obstructions 3.
Cracking or linear indications l
4.
Loose / missing / broken parts 5.
Whether obstruction to moving parts 6.
Wear / Corrosion / Erosion 7.
Presence of foreign material j
8.
Misalignment (if any) and effect on valve operation 9.
Mechanical damage 10.
Hinge pin condition 11.
Disc / seat condition 12.
Perform manual exercise of discs Each check valve has been disassembled and inspected in previous outages. The assessment of the valves mechanical and physical condition is performed by FCS Inspectors qualified to VT-3 in accordance with ASME Section XI.
In addition, the review / evaluation of any observed deficiencies / indications is performed by engineering for a final acceptance of the condition of the valve.
In addition, a review of the installation of each check valve has been addressed using the "EPRI Applications Guidelines for Check Valves in Nuclear Power Plants" and appropriate actions have been taken (i.e., PM inspections) as a result of the completion of the design application review for the check valves. The industry has experienced no failures with this type of check valve in similar applications at other facilities.
The disassembly and subsequent inspection of these valves requires unnecessary radiation exposure as well as creating significant (i.e., > 50 gallons) liquid radwaste requiring disposal. Also, frequent disassembly and reassembly of the valves (i.e., every Refueling Outage) introduces unnecessary potential for valve failure due to damage caused by maintenance without providing a commensurate increase in plant safety or check valve reliability.
R2 June 15, 1995 Page 140 of 168
..e I
1.
Code Exception Number E1 - Relief Request (Continued)
Alternate Testing:
OPPD will require check valves SI-139 and SI-140 to be alternately-disassembled and inspected every other Refueling Outage..This sample disassembly of these check valves is in accordance with the' NRC guidelines established in Generic Letter 89-04, Attachment 1, Position 2.
In addition, the check valves.will be partial-stroke exercised in the open direction Quarterly and after reassembly.
during Refueling Outages.
The check valves will be full-stroke i
exercised in the closed direction during each Refueling Outage.
This method of sample' disassembly'and inspection will ensure that.
each check valve is disassembled and inspected at least once every six years and will help to maintain personnel exposure ALARA, while at the same time providing reasonable assurance that integrity, quality and the ability to detect component degradation are maintained.
P L
I s
i 3
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R2 June 15, 1995 Page 141 of 168.
c
- 2. - : Code Exception Number E2 - Re' lief Request Components:
SI-159, SI-160 Function:
Containment Recirculation Check Valves Class:
\\
'2-Test Requirements:
- Quarterly Full Flow Exercisir.g in.the Open Direction Basis for Exception from O&M Part 10, Subsection 4.2.1.2:
These valves function to prevent backflow to the Containment lower level. These valves are backed up by motor operated. isolation-valves HCV-383-3 and HCV-383-4 which are normally closed,
-fail-as-is, and open only upon receipt of a containment RecirculationActuationSignal:(RAS).
Due to system design, these-valves cannot be partial-stroke or full-stroke exercised open during power operation, Cold Shutdown or Refueling Outage because the Containment sump is normally dry and there is no flow' path available for testing. Full-stroke exercising these valves open requires that the Containment sump be filled with water and provided with a source of. makeup water in addition to operating.
'the CS pumps and the HPSI pumps at. rated capacity. Therefore,.
system configuration renders flow' testing of these valves impractical.
The corrective maintenance history of these two check. valves has been limited to gasket / bolt / nut replacements since installation.
In addition, the check valves are 24-inch stainless steel Mission-Duochek-type valves which see no flow during normal-operations. _OPPD has previously disassembled and inspected'each of these check valves and these check valves were'"like new."
"Like new" is defined as a condition of the component that has little or no visible indication of wear, as if thejvalve was just installed from the factory.
In order to assess the condition of-the check valves during sample disassembly and inspection and, to provide a consistent and precise method of gauging the check valves physical and mechanical condition, a checklist was developed and incorporated into the Surveillance Tests used for-sample disassembly and inspection. An example of items evaluated on the check list are:
1.
Whether valve discs are initially seated R2 June 15, 1995 Page 142 of 168
.)
i 2.
Code Exception Number E2 - Relief Request (Continued) 2.
A determination of obstructions
]
i 3.
Cracking or linear indications 4.
Loose / missing / broken parts 5.
Whether obstruction to moving parts 6.
Wear / Corrosion / Erosion 7.
Presence of foreign material 8.
Misalignment (ifany)andeffectonvalveoperation l
9.
Mechanical damage 10.
Hinge pin condition 11.
Disc / seat condition 12.
Perform manual exercise of discs Each check valve has been disassembled and inspected in previous outages.
The assessment of the valves mechanical and physical condition is performed by FCS Inspectors qualified to VT-3 in accordance with ASME Section XI.
In addition, the review / evaluation of any observed deficiencies / indications is performed by engineering for a final acce)tance of the condition of the valve.
In addition, a review of t1e installation of each check valve has been addressed using the "EPRI Applications Guidelines for Check Valves in Nuclear Power Plants" and appropriate actions have been taken (i.e., PM inspections) as a result of the completion of the design application review for the check valves. The industry has experienced no failures with this type of check valve in similar applications at.other facilities.
The disassembly and subsequent inspection of these valves requires unnecessary radiation exposure as well as creating significant (i.e., > 50 gallons) liquid radwaste requiring disposal, with'.
minimal benefits. Also, frequent disassembly and reassembly-of thevalves(i.e.,everyRefuelingOutage)introducesunnecessary potential for valve failure due to damage caused by maintenance without providing a commensurate increase in plant safety or check' valve reliability.
.R2 June 15, 1995 Page 143 of 168
n,
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2.
Code Exception Number E2 - Relief Request (Continued) 4 Alternate Testing:
U
-0 PPD will require check valves SI-159 and SI-160 to be alternately.
disassembled and inspected.every other Refueling Outage.' This i
sample disassembly of these check valves is.in accordance with the NRC guidelines established in Generic Letter 89-04, Attachment 1,-
?
Position 2 with the exception of partial-stroke exercising.1: This' method of sample disassembly.and inspection will ensure that each 1
check valve is disassembled and inspected at least once every six years and will help-to maintain personnel exposure ALARA, while at
-the~same time providing reasonable assurance-that.the integrity, quality and the ability to detect component degradation is maintained.
1 i
l 1
1 j
R9 ae 15, 1995 Page 144 of 168
4 1
3.
-Code Exception Number E3 - Relief Request Components:
i SI-175,.SI-176 1
Function:
)
l Containment Spray Header Check Valves Class:
1 2
i Test Requirements:
Quarterly Full Flow Exercising in the Open Direction l
Basis for Exception from 0&M Part 10, Subsection 4.2.1.2:
These check valves are located inside Containment. These valves cannot be full-stroke or partial-stroke exercised open using system flow during any plant operating conditions because the only flow path is into the C5 headers and would result in spraying down the Containment, causing equipment damage and requiring extensive cleanup.
The corrective maintenance history of these two check valves has i
been limited to gasket / bolt / nut replacements since installation.
In addition, the check valves are 12-inch stainless steel Mission-Duochek type valves which see no flow during. normal operations. OPPD has previously disassembled and inspected each of these check valves and these check valves were "like'new."
"Like new" is defined as a condition of the component that has little or no visible indication of wear, as if the valve was just installed from the factory.
In order to assess the condition of the check valves during sample disassembly and inspection and; to provide a consistent and precise method of gauging the check valves physical and mechanical condition, a checklist was developed and incorporated into the Surveillance Tests used for' sample disassembly and inspection. An example of items evaluated on the check list are:
~l 1.
Whether valve discs are' initially seated 2.
A determination of obstructions 3.
Cracking or linear indications 4.
Loo,se/ missing / broken parts 5.
Whether obstruction to moving parts p
6.
Wear / Corrosion / Erosion R2 June 15, 1995 Page 145 of 168
3.
Code Exception Number E3 - Relief Request (Continued) 7.
Presence of foreign material 8.
Misalignment (ifany)andeffectonvalveoperation 9.
Mechanical damage 10.
Hinge pin condition 11.
Disc / seat condition 12.
Perform manual exercise of discs Each check valve has been disassembled and inspected in previous outages.
The assessment of the valves mechanical and physical condition is performed by FCS Inspectors qualified to VT-3 in accordance with ASME Section XI.
In addition, the review / evaluation of any observed deficiencies / indications is performed by Engineering for a final acceptance of the condition of the valve.
In addition, a review of the installation of each check valve has been addressed using the "EPRI Applications Guidelines for Check Valves in Nuclear Power Plants" and appropriate actions have been taken (i.e., PM inspections) as a result of the completion of the design application review for the check valves. The industry has experienced no failures with this type of check valve in similar applications at other facilities.
The disassembly and subsequent inspection of these valves requires unnecessary radiation exposure with minimal benefits. Also, frequent disassembly and reassembly of the valves (i.e., every Refueling Outage) introduces unnecessary potential for valve failure due to damage caused by maintenance without providing a commensurate increase in plant safety or check valve reliability.
Alternate Testing:
Check valves SI-175 and SI-176 will be alternately disassembled every other refueling outage.
The sample disassembly of these check valves is in accordance with the NRC guidelines established in Generic Letter 89-04, Attachment 1, Position 2.
In addition, the check valves will be partial-stroke exercised in the open direction during Refueling. This method of' sample disassembly and inspection will ensure that each check valve is disassembled and inspected at least once every six years and will help to maintain personnel exposure ALARA, while at the same time providing reasonable assurance that the integrity, quality and the ability to detect component degradation is maintained.
1 R2 June 15, 1995 Page 146 of 168
9 i
4.
Code Exception Number E4 - Relief Request Components:
. SI-207, SI-208, SI-211,51-212, SI-215, SI-216, SI-219,'SI-220 l
Function:
Safety Injection Tank (SIT) Check Valves Class:'
1 Test Requirements:
l Quarterly Full Flow Exercising in the Open' Direction Quarterly Full Flow Exercising in the Closed Direction and Leak-Testing during Cold Shutdown Basis for Exception from 0&M Part 10, Subsection 4.2.1.2:
i These valves cannot be exercised during power operation because a flow path does not exist due to the higher RCS pressure. The Safety Injection Tank pressure is less than RCS pressure during.
power operation. Also, these check valves cannot be exercised
-j during Cold Sh~utdowns because the RCS does not contain sufficient i
volume to accept the flow required and a low temperature overpressure condition of the RCS could result.
Alternate Testing:
Check Valves will be full-stroke exercised in the opn direction during Refueling Outages by " dumping" the Safety Injection Tanks to the Reactor Vessel. Test parameters such as SI tank level decrease vs. time, SI tank pressure, valve differential pressure, flow rate etc. are used to determine a flow coefficient. The-minimum flow coefficient was determined using the safety analysis data provided by the NSSS vendor.
Comparing this minimum flow-I coefficient as acceptance criteria to the flow coefficient determined by testing, assures FCS the valve is able to perform its safety function. This method of testing the check valves i
complies with the guidance provided'in Generic Letter 89-04,, Position 1.
Additionally, valves SI-208, SI-212, SI-216 and 5I-220 will be partial-stroke exercised at Cold Shutdown frequency in the open direction using Shutdown Cooling-flow.
R2 June 15, 1995 Page 147 of 168 4
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i 5.
Code Exception Number E5 - Relief Request DELETED l
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R2 June 15, 1995 Page 148 of 168
.6..
Code Exception Number E6 - Periodic Testing of Relief Valves Components:
FW-1525 Function:
Auxiliary Feedwater Pump 011 Cooler Relief Valve Class:
3 Test Requirements:
A Minimum of 20% of Each Type and Manufacture Shall be Tested Within any 48 Months.
Basis for Exception from O&M Part 1 Subsection 1.3.5(b):
The relief valve is the only one of its type and manufacturer in its respective group.
The intent of the Code is that'all Class 3 relief valves be tested at'least once every ten years (Reference 0&M Part 1, Subsection 1.3.5(b)). This intent will be met. The current Refueling Outage frecuency.is 18 months. A review of historical maintenance recorcs reveals that there have been no maintenance problems which justify testing the relief. valve every other refueling outage. The scope of 0&M Part 1 is to verify valve operability and detect any degradation in valve performance.
Alternate. Testing:
The relief valve will be tested every third refueling outage.
'l R2 June 15, 1995 Page 149 of 168
t
-PART 3: CLASS 1, CLASS 2, AND CLASS 3 PUMP TESTS 1.0 Program Summary The Inservice Testing (IST) Program for ASME Class 1, 2 and 3 pumps was developed in accordance with and meets the requirements of ASME Operation and Maintenance of Nuclear Power Plants (0&M) 1987 Edition, 1988 Addenda. The IST for pumps will remain in effect for the remainder of the 120-month interval which began on September 26, 1993.
The Program will be reviewed and updated, as appropriate, with that Edition i
of the Code in effect not more than 12 months prior to the start of the next 120-month interval.
l The function of each pump in the Program is described in Section 3.8.
Section 3.9 contains individual pump test requirements and exceptions to the Code (Table 3.1), as well as the codes used in the Table.
Appendix 3A contains justifications for exceptions taken to the Code test requirements as provided for in 10CFR50.55a(g)(5)(iii).
Justifications l
are general in nature and pertain to requirements found to be impractical.
Code exceptions are numbered and referenced by number on the Pump Test Program Table 3.1.
2.0 Scope and Responsibility i
2.1 The P& ids of Part 4 identify the location of each Class 1, Class 2, and Class 3 pump.
2.2 Class 1, Class 2, and Class 3 pumps are to be tested in accordance with Part 6 of the 0&M Manual.
The test methods for each pump, and exceptions to the tests of O&M Part 6, are found in Appendix 3A.
3.0 Inservice Test Frequency I
The inservice test frequency for Class 1, Class 2, and Class 3 pumps are in accordance with Part 6 of the O&M Manual, with exceptions as found in Table 3.1 and Appendix 3A.
i 4.0 Test Methods l
The methods to be used to test Class 1, Class 2, and Class 3 pumps have i
been determined from Part 6 of the 0&M manual.
These methods, along with exceptions, are listed in Table 3.1 and Appendix 3A.
5.0 Evaluation of Test Results e
The allowable ranges of test results shall be in accordance with Table 3 of Part 6 of the 0&M Manual, as appropriate.
All test data shall be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of a test in accordance with Part 6 of the 0&M Manual.
R2 June 15, 1995 Page 150 of 168
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If test data show that a pump is operating in the " Alert Range",
remedies shall be taken, as required in accordance with 0&M Part 6, until corrective action is taken.
If the test data show that a pump is operating in the " Required Action Range," the pump shall be declared inoperable until corrective action is taken.
Corrective action is defined as one or more of the following steps:
5.1 Recalibrate the applicable instruments and reperform the test, or 5.2 Repair or replace the component as required, or 5.3 Perform an Engineering Analysis to demonstrate that the pump is still able to perform its required safety design function.
6.0 Records and Reports Records and reports for the testing of Class 1, Class 2, and Class 3 pumps shall be made in accordance with Part 6, Subsection 7, of the O&M Manual.
7.0 Repair Requirements Tests, after pump replacement, repair or servicing, shall be made as required by O&M Part 6, Subsection 4.4.
8.0 Function of Pumps in the Program 8.1 Auxiliary Feedwater (AFW) Pumps FW-6 and FW-10 are the motor driven and the steam driven AFW pumps, respectively.
They supply makeup water to the Steam Generators during startup/ shutdown conditions.
Subsequent to an automatic initiation signal when normal feedwater flow is unavailable, they supply water to the Steam Generators.
8.2 Component Cooling Water (CCW) Pumps
)
i AC-3A, AC-3B and AC-3C are the three CCW Pumps.
They supply cooling water to safety-related components in the Containment and Auxiliary Buildings, including components containing radioactive or potentially radioactive fluids.
They provide cooling water to Containment air coolers and the Control Room air conditioning units during both normal and accident conditions.
In the event of a design basis accident, these pumps provide sufficient cooling water to the Engineered Safeguards equipment. Additionally, they i
supply cooling water to components to support normal plant operation, and to remove heat from the RCS via the Shutdown Cooling Heat Exchangers during normal plant cooldowns.
4 R2 June 15, 1995 Page 151 of 168
8.3 Raw Water Pumps AC-10A, AC-108, AC-10C and AC-100 are the four Raw Water Pumps.
They supply cooling water to the CCW Heat Exchangers.
They also supply cooling water directly to select safety related components in the event the CCW System is unavailable. Additionally, they supply water to the Demineralized Water System.
8.4 Safety Injection Pumps SI-1A and SI-1B are the two LPSI Pumps.
They inject borated water into the reactor coolant system following a LOCA. Additionally, they serve as Shutdown Cooling pumps by supplying water to the Shutdown Cooling Heat Exchangers for removal of residual heat during normal plant cooldown.
SI-2A, SI-2B and SI-2C are the three HPSI Pumps. They inject borated water into the reactor coolant system following a LOCA.
Additionally, they are used to maintain the required water level in the Safety Injection Tanks.
SI-3A, SI-3B and SI-3C are the three CS Pumps. They spray borated water into the Containment to remove energy from the Containment vapor space after the initiation of a pressurization event in containment. Although there is a possibility of physically aligning the CS Pumps for Shutdown Cooling, that alignment should only be considered when the RCS is below 120*F and tne RCS is vented to the Containment atmosphere with the vent area equivalent to a twelve-inch diameter pipe.
8.5 Chemical Volume and Control Pumps CH-1A, CH-1B and CH-1C are the three Charging Pumps.
CH-4A and CH-4B are the two Boric Acid Pumps. These five pumps inject concentrated borated water into the RCS under emergency conditions. These pumps also serve several non-safety related functions.
8.6 Diesel Generator Fuel Oil Transfer Pumps FO-4A-1, F0-4A-2 and F0-48-1, F0-4B-2 are the four Diesel Generator Fuel Oil Transfer Pumps. They take suction from the underground fuel oil storage tank and transfer fuel oil to the wall mounted auxiliary tanks.
9.0 Pump Test Program Table (Table 3.1)
This section 3rovides a tabulation of all safety related pumps, both those pumps t1at are tested in accordance with the requirements of O&M Manual Part 6, and those pumps for which the Code requirements have been found to be impractical.
R2 June 15, 1995 Page 152 of 168
10.0 Additions to Program - Pumps Pumps added to the ISI Program Plan as a result of plant / system modifications, engineering changes or re-evaluation of component eligibility requirements as per 0&M Manual, Part 6, are considered operable based on interim acceptance criteria (established by construction or preoperational tests) until a reference value is able to be established.
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PUMP TABLES i
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R2 June 15, 1995 Page 154 of 168
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i TABLE FORMAT FORT CALHOUN STATION PUMP TEST PROGRAM MATRIX' TABLE 3.1 i
The Pump Test Program Table has been coded to provide the following
-information.
1.
System and Drawing Number - System the pump is in and the P&ID number.
[
2.
Coordinates - Location on the P&ID where the pump is found.
3.
Pump Number - Unique number assigned to each pump.
i 4.
Speed n - This parameter is addressed with one of the following entries, which indicate test applicability, interval, or Code exception number, respectively.
Not Required NR Quarterly Test 0
El, E2, E3, E4 Code Exception Number 5.
Inlet Pressure P, - Same as number 4.
6.
Differential Pressure AP - Same as number 4.
l 7.
Flow Rate Q - Same as number 4.
8.
Vibration Amplitude V - Same as number 4.
i V, - Displacement ( 3eak-peak)
V, - Velocity (peac) 9.
Discharge Pressure (P) - Same as number 4.
j 10.
Code Exceptions
.If the pump is being tested in accordance with O&M l
Part 6 requirements, this column will be blank. - However, for-pumps which the 0&M Part 6 requirements have been found to be' impractical, a reference number is entered in this column. The reference number is addressed in Appendix 3A with a complete explanation of the specific exception and justification for that exception.
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i R2 June 15, 1995 Page 155 of 168
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JUSTIFICATION FOR EXCEPTION TO O&M MANUAL PART 6 FOR PUMPS
' R2 June 15, 1995 Page 157 of 168 l
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APPENDIX 3A JUSTIFICATION FOR EXCEPTION TO 0&M MANUAL PART 6 FOR PUMPS 1.
Code Exception Number E1 - Relief Request Components:
Raw Water Pumps AC-10A, AC-108, AC-10C, AC-10D Low Pressure Safety Injection Pumps SI-1A, SI-1B High Pressure Safety. Injection Pumps SI-2A, SI-28, SI-2C Containment Spray Pumps SI-3A, SI-38, SI-3C~
Boric Acid Pumps CH-4A, CH-4B Class:
2 3
Test Requirements:
Measurement of Pump Inlet Pressure and Differential Pressure Raw Water Pumps Basis for Exception 0&M Part 6, Subsection 4.6.2.2, 5.2 and Table 2:
System design does not include instrumentation for direct measurement of inlet and differential pressure.
Alternate Testing:
The pump inlet pressure will be calculated based on the river l
1evel and the elevation of the pump suction bells. -The pump differential pressure will then be calculated based on the 1
measured discharge pressure and the calculated inlet pressure, i
Since (1) the river provides the required positive pressure at the suction of the pumps, (2) the river level does not change when a pump is started, and (3) at least one pump is usually in service, the calculated inlet pressure prior to starting a pump is the same as with a pump running.
l LPSI, HPSI and Containment Spray Pumps Basis for Exception from 0&M Part 6, Subsections 4.6.2.2, 5.2 and Table 2:
System design does not include instrumentation for direct measurement of inlet and differential pressure.
R2 June 15, 1995 Page 158 of 168
1.
Code' Exception Number E1 - Relief Request (Continued)
Alternate Testing:
The LPSI, HPSI~and CS pumps take'their suction directly from~the Safety Injection and Refueling Water Tank and have inlet pressures due to the level of water in the tank'above the pump inlets. The pump inlet pressures will be calculated based on the tank level and the difference in' elevation between the tank and the pump inlets.
Pump differential pressures will then be calculated by subtracting the calculated inlet pressure from the measured discharge pressures.
Since the Safety Injection and Refueling Water Tank provides.the required positive pressure at the suction of the pumps and since the tank level does not significantly change when a pump is started, the calculated pump inlet pressure prior to starting a pump is the same as with a pump running. Flow losses through the suction )iping of these pumps are' negligible.
Since the losses would be tie.same from test to test, not
~
including them in the test would still enable pump degradation to be identified.
Boric Acid Pumps Basis for Exception for'0&M Part 6, Subsections 4.6.2.2, 5.2 and Table 2:
System design does not include instrumentation for direct measurement of inlet and differential pressure.
Alternate Testing:
The-Boric Acid Pumps take their suction directly from the Boric Acid Tanks and have an inlet pressure due to the level of acid in i
the tanks above the pump inlet.
The pump inlet pressure will be calculated based on the Boric Acid Storage Tank level and the elevation difference between the tank level and the pump inlet.
Pump differential pressure will then be calculated by subtracting-the calculated inlet pressure from the measured discharge pressure.
R2 June 15, 1995 Page 159 of 168-w-
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Code Exception Number E2 - Relief Request j
- Components
' Low Pressure Safety. Injection Pumps SI-1A, SB j
High Pressure Safety Injection Pumps SI-2A, B, C Containment Spray Pumps SI-3A, B, C l
Class:
2L l
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k
. Test Requirements:
t i
Measurement ~of Flow Rate Quarterly j
3 Low Pressure Safety Injection Pumps l
Basis for Exception from O&M Part 6, Subsection 5.1 and Table 2:.
f i
The flow rate of the LPSI pumps cannot be measured while they are i
operating on the minimum flow recirculation line because flow l
measurement instrumentation is not installed on this-line. The.
pump minimum flow recirculation line must be used when testing i
these puinps Quarterly during power operation, because. the only other flow path is into the RCS. This flow path cannot be utilized because the pump discharge pressure cannot overcome the i
RCS pressure.
t Alternate Testing:-
In addition to the Quarterly mini-flow test,' pump flow rate will be measured on a Cold Shutdown frequency when an instrumented flow l
path-to the.RCS is available. This is in accordance with Position-l 9 (Pump Testing Ilsing Minimum' Flow Line With or Without Flow-i Measuring Devices) of Attachment I to the Generic Letter 89-04.
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i R2' June 15, 1995 dage 160 of 168
)
i
-2.
Code Exception Number E2 - Relief Request (Continued)
Containment Spray Pumps Basis for Exception from 0&M Part 6, Subsection 5.1 and Table 2:
The flow rate of the CS Pumps cannot be measured while they are operating on-the minimum flow recirculation line because the flow measurement instrumentation is not installed on this line. The pump minimum flow recirculation line.must be used when testing these pumps Quarterly during power o)eration, because the only other flow path is into tie Containment spray headers which would result in water damage.to equipment in Containment. Additionally, as approved by Amendment 136, Technical Specifications 2.1.1 states that the CS pumps will not be lined up on the shutdown cooling flow path until RCS temperature is I
below 120*F and a vent path is available.
This is due to the fact that the suction side piping is designed to DBA conditions (60 psig) and valves on the suction.
piping are designed to 150 psig.
Alternate Testing:
In addition to the Quarterly mini-flow test, pump _ flow rate will be measured on a refueling outage frequency when an instrumented flow path to the RCS is available.
This is in accordance with Item 9 (Pump Testing Using Minimum Flow Line With or Without Flow i
Measuring Devices) of Attachment 1 to Generic Letter 89-04.
High Pressure Safety Injection Pumps Basis for Exception from O&M Part 6, Subsection 5.1 and Table 2:
i The flow rate of the HPSI pumps cannot be measured while they are operating'on the minimum flow recirculation line because the flow measurement instrumentation is not installed on this line.
The pump minimum flow recirculation line must be used when testing these pumps Quarterly during power operation, because the only other flow path is into the RCS which cannot be utilized because the pump discharge pressure cannot overcome the RCS pressure.
Alternate Testing:
i In addition to the Quarterly mini-flow test, aump flow rate will i
be measured on a refueling outage frequency w1en an instrumented flow path to the RCS is available. This is in accordance with Position 9 (Pump Testing Using Minimum Flow Line With or Without Flow Measuring Devices) of Attachment I to Generic Letter 89-04.
l R2 June 15, 1995 Page 161 of 168
3.
Code Exception Number E3 - Relief Request DELETED l
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4.
Code Exception Number E4 - Relief Request Components Component Cooling Water Pumps AC-3A, AC-3B, AC-3C Raw Water Pumps AC-10A, AC-108, AC-10C, AC-10D Class 3
Test Requirements Section 5.2 of OM-6 requires that the system resistance be varied until either the measured differential pressure or measured flow rate equals the corresponding reference value. The quantities listed in Table 2 of OM-6 are then measured or observed and compared to the corresponding reference value. Rather than set the applicable pumps at a reference value, the licensee proposes to establish a range of values (pump curves) and test the pumps in the as-found operating condition.
Basis for Exception from O&M Part 6, Subsection 5.2 Table 2:
The Raw Water (RW) and Component Cooling Water (CCW) systems at Fort Calhoun Station (FCS) are designed such that the total pump flow cannot be adjusted'to one specific value for the purpose of testing without adversely affecting the system flow balance and technical specification operability requirements.
Therefore, the RW and CCW pumps must be tested in a manner that the RW and CCW loops remain properly flow balanced during and after the testing.
In addition, certain supplied loads (e.g. cooling of Control Element Drive Mechanisms) must remain fully operable per Technical Specifications to maintain the required level of plant safety during power operation.
The RW and CCW systems loops are not designed with full flow test lines with single throttle valves.
Therefore, the flow cannot be throttled to a fixed reference value every time a pump test is performed.
Total pump flow rate can only be measured using the total flow indication as installed and read on the supply headers.
There are no valves available in any of the loops, on either the supply or return lines, for the purpose of throttling total RW or CCW system flows. Only the flow of the served components are able to be individually throttled.
The main loops of RW and CCW are piped in parallel with each other.
r Many loads are throttled to flow ranges specified in the FCS Design Basis Documents (DBD). All loads are aligned in parallel, and receive RW/CCW flow when the RW/CCW pumps are running regardless of R2 June 15, 1995 Page 163 of 168
a
,v 4.
Code Exception Number E4 - Relief Request (Continued) which served components are in service. During power operation,'certain loops of RW/CCW are required to be operable per Technical Specifications.
Specific.
loops / components of RW/CCW cannot be taken out of service for testing without entering an action statement for a LimitingConditionforOperation(LCO). Also, exceeding certain individual component flows / temperatures (e.g.,
reactor coolant pump seals) can require plant shutdown in two hours, depending on the load in question.
t Certain RW/CCW loops are flow balanced during each refueling outage (at a nominal-18-month frequency) to, ensure that all loads are adequately supplied.
Flow ranges are specified for these loads in order to balance flows against each other.
Once properly flow t
balanced, minimal flow adjustment can be made for any l
one particular load without adversely impacting the i
operability of the remaining loads (i.e.,-increasing).
flow for one load reduces flow for all of the others Each time the system is flow balanced, proper individual component flows are produced, but-this in turn does not necessarily result in one specific'value for total flow.
Because certain loads have an:
acceptable flow range, overall system full flow (the sum of the individual component flows) also has a
.i range. Consequently, the Code requirements to quarterly adjust RW/CCW loop flow to one specific flow value for the performance of inservice' testing conflicts with FCS system design and component operabilityrequirements(i.e.,flowbalance)as required by Technical Specifications.
j Alternate Testing As discussed above in the Test Requirements section, it is extremely difficult to return to a specific value of flow rate or differential pressure for testing of these pumps. Multiple reference points could be established according to the Code, but obtaining reference values at every possible point, even over a small range is not feasible. An alternative to the testing requirements of OM Part 6, Section 5.2, is to base _the acceptance criteria on a reference pump curve.
Flow rate and differential l
pressure are measured / calculated during inservice testing and compared to an established baseline reference curve.
In addition, trending is accomplished by taking the ratio of the reference curve differential pressure versus flow and the actual t
differential pressure versus flow.
The following elements are used in developing and implementing the reference pump curves:
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l R2 June 15, 1995 Page 164 of 168 i
'4.
Code Exception Number E4 - Relief Request (Continued) 1.
A reference pump curve (differential pressure vs. flow) has been established for RW pumos AC-10A, AC-10B, AC-10C, and AC-100, and for CCW pumps AC-3A, AC.3B, and AC-3C from data taken on these pumps when they were known to be operating acceptably.
These pump curves represent pump performance close to the original manufacturer's pump test data.
2.
Pump curves are based on four or more test points whenever possible. Rated capacities of these pumps are 6,000 - 7,000 gpm for the RW pumps and 4,500 - 5,500 gpm for the CCW pumps.
3.
To reduce the uncertainty associated with the pump curves and to ensure the adequacy of the acceptance criteria, all instruments used in establishing the baseline reference curves either meet or exceed the Code required accuracy. pump 4.
The reference baseline pump curves are compared to the manufacturer's pump curves which were validated during plant preoperational testing.
5.
Review of the pump hydraulic data trend plots indicates close correlation with established pump reference curves, thus validating the accuracy of the pump curves to assess the pumps' operational readiness.
6.
The reference pump curves are based on differential pressure vs. flow.- See the attached sample AC-3A and AC-10A pump acceptance criteria sheets. Areas for Required Action are as required per 0M-6.
Areas for Acceptable, Alert, and Required Action are as required per 0M-6.
These acceptance criteria limits do not conflict with operability criteria (minimumoperability).
7.
Only a small portion of the established reference curve is being used to accommodate flow rate variance due to flow balancing of various system loads.
8.
Review of recent vibration data trend plots indicates that the change in vibration readings over the range of the pump curves being used is insignificant; therefore, only one fixed reference value has been assigned for each vibration measurement location.
9.
After maintenance or repair that may affect the existing baseline reference pump curves, a new reference pump curve is determined or the existing pump curve revalidated by an inservice test.
The design of the FCS RW and CCW systems and the Technical Specification requirements make it impractical to adjust system flows to a fixed reference value for inservice testing without adversely affecting the system flow balance and Technical specification operability R2 June 15, 1995 Page 165 of 168
V"
- 4. -
Code' Exception Number E4'- Relief Request (Continued) requirements.
Proposed alternate testing using a reference pump curve for each pump provides adequate assurance and.
accuracy.in monitoring pump condition to assess pump g
-operational readiness _and will adequately detect pump t
degradation. The proposed alternate testing will have no adverse impact on plant or public safety.
1 Conclusion e
Relief to use pump curves for testing (the RW and CCW pumps is' granted pursuant to 10CFR50.55a(f)(6) 1) based on the impracticality _of performing testing in accordance with the Code requirements to test pumps at a reference value of either differential pressure and measure flow, or flow and measure differential pressure. The granting of relief is in consideration of the adequacy of an alternative method of testing and the burden if the Code requirements were imposed.
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PART 4 REFERENCES s
1.
Fort Calhoun Station Technical Specifications.
2.
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition.
3.
ASME/ ANSI Operation and Maintenance of Nuclear Power Plants, 1987 Edition, 1988 Addenda.
4.
NRC Generic Letter No. 89-04, " Guidance on Developing Acceptable Inservice Testing Programs".
5.
NRC's Safety Evaluation Report on Revisions 3 and 4 of the Fort Calhoun Station's Inservice Inspection / Testing Program Plan (1983-1993), dated December 22, 1988 and July 3, 1989, respectively.
6.
NRC's Safety Evaluation Report on Revision 5 of the Fort Calhoun Station's Inservice Inspection / Testing Program Plan (1983-1993), dated March 13, 1990.
7.
NRC's Safety Evaluation Report on Revision 0 of the Fort Calhoun Station's Inservice Testing Program Plan Third Ten Year Interval (1993 -
2003), dated June 21, 1994.
8.
Letter from NRC (W. H. Bateman) to OPPD (T. L. Patterson), dated April 6, 1995 (NRC 95-071).
9.
ASME Code Cases Incorporated into the FCS ISI Program Plan i
Code Case N-416* Alternative Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping Section XI Division 1.
Approval Date: December 5, 1984 j
Code Case N-416-1 Alternative Pressure Test Requirement for Welded Repairs on Installation of Replacement Items by Welding, Class 1, 2, and 3,Section XI Division 1.
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Code Case N-461* Alternative Rules for Piping Calibration Block Thickness.
Approval Date: November 30, 1988 Code Case N-481* Alternative Examination Requirements for Cast Austenitic Pump Casings.
Approval Date: March 5, 1990 Code Case N-491* Alternative Rules for Examination of Class 1, 2, 3 and MC Component Supports of Light-Water Cooled Power Plants.
Approval Date: March 14, 1991 L
R2 June 15, 1995 Page 167 of 168
Code Case N-498-1**
Alternative Rules for Ten-year System Hydrostatic Pressure Testing for Class 1, 2, and 3 Systems.
i Approval Date:
May 11, 1994 Code cases approved by NEC-Reference NRC Regulatory Guide 1.147.
Code cases approved by NRC-Refer to NRC Letter dated January 30, 1995 l
(NRC95-017) 9.
The following 0 PPD Piping and Instrumentation Drawings:
Number Title 11405-H-1 Containment Heating Cooling & Ventilating System 11405-H-5 Demineralized Water System 11405-H-6 Waste Disposal System 11405-H-7 Waste Disposal System 11405-H-10 Auxiliary Coolant Component Cooling System 11405-H-12 Primary Plant Sampling System 11405-H-13 Plant Air System 11405-H-40 Auxiliary Coolant Component Cooling System Flow 11405-H-42 Nitrogen, Hydrogen, Methane, Propane & 0xygen Gas System 11405-H-98 Waste Disposal System 11405-H-100 Raw Water System '
11405-H-252 Steam System 11405-H-253 Steam Generator Feedwater & Blowdown System 11405-H-254 Condensate System 11405-H-262 Fuel Oil System 11405-H-264 Instrument Air System E-23866-210-110 Reactor Coolant System E-23866-210-120 Chemical & Volume Control System E-23866-210-121 Chemical & Volume Control System E-23866-210-130 Safety Injection & Containment Spray System B120F07001 Diesel Generator Starting Air System C-4175 Control Valve Air Source Valve Lineup / Listing D-4078 Reactor Coolant Gas Vent System i
R2 June 15, 1995 Page 168 of 168