ML20237C029: Difference between revisions
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these valves have demonstrated their capability of withstand-ing their environment without deterioration for twelve years,- i so a once per five year inspection frequency.is adequate to ) | these valves have demonstrated their capability of withstand-ing their environment without deterioration for twelve years,- i so a once per five year inspection frequency.is adequate to ) | ||
ensure valve operability. | ensure valve operability. | ||
These inspections shall photographically document the valve's condition and shall manually test the valve disk for free movement. This shall duplicate the' inspection done in 1980 and 1981 in response to an NRC request. (In the June 29, 1981 letter from Robert Clark of the NRC to W. C. Jones of OPPD, the attached Safety Analysis clearly indicated that upon receiving an acceptable inspection report from the Dis- | These inspections shall photographically document the valve's condition and shall manually test the valve disk for free movement. This shall duplicate the' inspection done in 1980 and 1981 in response to an NRC request. (In the {{letter dated|date=June 29, 1981|text=June 29, 1981 letter}} from Robert Clark of the NRC to W. C. Jones of OPPD, the attached Safety Analysis clearly indicated that upon receiving an acceptable inspection report from the Dis- | ||
[ trict on the condition of SI-160, the NRC would consider in-spection of SI-159 and SI-160 on a five-year basis adequate j for this ISI interval. In the same letter, it was noted that j this exception should be presented with other exceptions;for the ISI program). | [ trict on the condition of SI-160, the NRC would consider in-spection of SI-159 and SI-160 on a five-year basis adequate j for this ISI interval. In the same letter, it was noted that j this exception should be presented with other exceptions;for the ISI program). | ||
SI-175 These valves are inside the containment in the containment 176 spray headers. They cannot practically be flow tested to j verify that they open because to do so would actuate contain-ment spray. 'In lieu of the stroke testing required by ASME XI, OPPD shall do a sample disassembly' on these valves alter-nately at a rate of one per refueling outage. | SI-175 These valves are inside the containment in the containment 176 spray headers. They cannot practically be flow tested to j verify that they open because to do so would actuate contain-ment spray. 'In lieu of the stroke testing required by ASME XI, OPPD shall do a sample disassembly' on these valves alter-nately at a rate of one per refueling outage. | ||
Latest revision as of 17:11, 19 March 2021
| ML20237C029 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/31/1987 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20237C022 | List: |
| References | |
| PROC-871231, NUDOCS 8712180057 | |
| Download: ML20237C029 (69) | |
Text
{{#Wiki_filter:1 i O : Omaha Public Power District i Fort Calhoun Station, Unit 1 Inservice Inspection Program Plan for the 1983-1993 Interval i I i O I 1 I i O i R3 12/87 8712180057 871216 PDR ADOCK 05000285 l 0 ..DCD 1
PROGRAM TABLE OF CONTENTS Paae ABBREVIATIONS iii' INTRODUCTION: Discussion PART 1: ' Class 1, Class 2, and Class 3 Pressure Retaining Components 1 Program: 1.1 ' Scope and Responsibility 1 1.2 Inspection Intervals l' 1.3 Examination Categories 2 1.4 Examination' Methods 2 l 1.5 Evaluation of Examination Results 3 l 1.6 Repair Requirements 4 1.7 System Pressure Testing -4 1.8 Records and Reports 5 Appendix 1A Piping and Instrumentation Drawings 6 Appendix IB Exceptiens to Compliance with Table IWB-2500-1 7 Appendix IC Exceptions.to Compliance with Table-IWC-2500-1 .9 Appendix 1D Exceptions to Compliance with Paragraph
- i. IWD-2000 10 y Table 1.1 Components, Parts,-and Methods of Examination IWB-2500-1 11 Table 1.2 Components, Parts, and Methods of l Examination IWC-2500-1 15 PART 2: Class 1, Class 2, and Class 3 Pump and Valve Tests 17 Program: 2.1 Scope and Responsibility 17 2.2 Inservice Test' Frequency 17 2.3 Valve Categories 17 2.4 Test Methods -17 2.5 Evaluation of Test Results 17 2.6 Records and Reports 18 2.7 Repair Requirements 18 Appendix 2A Inservice Testing of Pumps '19' Appendix 2B Inservice Testing of Valves 24 Appendix 2C Justification for Exception to ASME Section XI Code .
25 Appendix 3 Definitions and Clarifications 36
References:
37 Valve Tables 38-66'[ O 11 R3 12/87
]
I ABBREVIATION 5 f)) w. A - addition ,
)
AD - air diaphragm operator ' AP - air piston
.j C - change '
CS - cold shutdown EX - exceptions 1 F - full stroke exercise ! FAI - fail as is FC - fail closed i F0 - fail open i i FTB - fail to bypass H0 - hand operator HP - hydraulic piston l LC - locked closed i M0 - motor operator NA - not applicable l NC - normally closed NO - normally opened 1 P - partial stroke exercise R0 - refueling outage a l RSU - reactor startup 1 S0 - solenoid operator ) Q - quarterly i V - variable position i I O iii R3 12/87
INTRODUCTION (n) This report defines the Inservice Inspection (ISI) Program for Class 1, Class 2, and Class 3 pressure retaining components for the 10-year period starting September 26, 1983, to September 26, 1993, and Class 1, Class 2, and Class 3 pump and valve testing for the 10-year period from September 26, 1983, to September 26, 1993. This program has been developed as required by Sec. 50.55& of 10 CFR Part 50 following the guidance of the ASME Boiler Pressure Vessel Code Section XI,
" Rules for Inservice Inspection of Nuclear Power Plant Components". The ISI Program will be controlled by the Fort Calhoun Station Unit 1 Technical Specifications. 1 This program is in compliance, where possible, with the applicable requirements of Section XI, of the ASME Boiler and Pressure Vessel Code, 1980 Edition through Winter of 1980 Addenda.
1 1 This program incorporates the results of previous inservice and preservice inspections. It is the intent of the Licensee to continue to review and apply, as appropriate, changes in the code which would improve the total ISI Program, ; pursuant to 10 CFR 50.55a. PART 1: Class 1, Class 2, and Class 3 Pressure Retaining Components 1 1.1 Scoce and Res.consibility p 1.1.1 The Piping and Instrumentation Drgwings (P& ids) in V Appendix 1A identify the class bour.dsries. These are always under review and are subjoct to change. 1.1.2 Class 1 and Class 2 components and the methods of examination for each component are listed in Tables 1.1 and 1.2, respectively. Class 3 components are those found on the P& ids in Appendix 1A. Tha specific components to be examined for each class shall be identified in the Fort Calhoun Station Unit 1 Inservice Examination Plan by title and/or number. Class 3 components will be examined tc the extent required by IWD-2500. Class 3 portions of the Waste Disposal System have been optionally classified as Class 3 in accordance with Sobarticle IWA-1300, Paragraph (9.) of the Section XI Code. Examination in accordance with the rules of Article IWD will not be performed on the Class 3 portion of , the Waste . Disposal System. Exceptions to j compliance with Tables IW8-2500 and IWC-2500 of l Section XI are listed in Appendix 18 and Appendix l IC, respectively. l 1.2 Jn_sngction Interval _s l () v 1.2.1 The inspection intervals for Class 1, Class 2, and Class 3 components will be 10-year intervals of service commen~cing on September 26, 1973. As l R3 12/87 i
i indicated previously, t~nis program plan covers the second 10-year interval, i.e., September 26, 1983, i g) to September 26, 1993. (V Ten-year examination plans will describe the distri-butien of examinations within the inspection inter- 1 vals in accordance with TWB-2400, IWC-2400, and IWD- i 2400 of Section XI. I 1.2.2 The inspection intervals may be extended by as much . as one year to permit inspections to be concurrent . with plant outages as permitted by IWA-2400(c) of Section XI. , 1.2.3 Select'fon of Class 1 and Class 2 pressure retaining ; l piping welds for examination shall be in accordance ' with the requirements of the 1974 edition of Sec- I tion XI, Summer of 1975 Addenda. 1.3 Examination Cateaories 1.3.1 Class 1 components will be examined to the extent and frequency required by Table IWB-2500-1 of Sec-tion XI. 1.3.2 Class 2 components will be examined to the extent and frequency as required by Table IWC-2500-1 of gq Section XI. j V l 1.3.3 Class 3 components as described in the 10-year exam-i ination plan shall be examined to the extent and i frequency as required by Table IWD-2500-1 of Sec-tion XI. Open-ended portion of a system extending to the first shutoff valve and buried systems compo-nents shall be exempted from pressure test and from inspection where accessibi'lity is restricted. 1.4 Examination Methods 1.4.1 Class 1 and Class 2 components shall be examined by the required visual, surface, and volumetric examin-ations. 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 examinations (UT) shall be performed in accordance with the following: 1.4.1.1 Ultrasonic examination of ferritic vessels with a wall thickness greater than 2 inches (51 mm) shall be conducted in accordance with Article 4 f_ of Section V. V) ( 2 R3 12/87
1 1.4.1.2 The ultrasonic examination of ferritic piping will be performed in accordance O with the procedural requirement of Ap-pendix III to-the Winter 1980 Addenda, ASME, Section XI. )
/
The ultrasonic examination of Austinitic. stainless steel piping will be performed-in accordance with the procedural require-ment of Appendix III to the Winter..'1980 Addenda, ASME, Section XI, Supplement 7. I 1.4.2 Class 3 components shall be visually examined for leakage in accordance with Article IWD-2600 of Sec-tion XI. ; 1.5 Evaluation of Examination Results . 1.5.1 Class 1 Components , 1.5.1.1 The evaluation of the nondestructive exam-- ination rerults shall be in accordance with Article IWB-3000 of Section XI. .All ' indications shall be subject to compari- j son with previous data to help in charac- i terization and in determining origin. 1.5.2 Class 2 Components O 1.5.2.1 The evaluation of nondestructive exam-
']
ination results shall be in.accordance with. Article IWC-3000 of Section XI. All indications shall be subject to compar-ison with previous data to help in char- l acterization and in. determining origin. 1.5.3 Class 3 Components 1.5.3.1 The evaluation of the visual examination , results shall be in accordance with 1 Article IWA-5000 of Section XI. ; 1.5.4 Indications which have been recorded in the preser-vice inspection or in a previous inservice inspection which are not characterized as propagating flaws i shall be considered acceptable for continued service. 1.6 Repair Requirements I 1.6.1 Repair'of Class 1, Class 2, and Class 3 components shall be performed in accordance with Article ~ i IWA-4000 of Section XI. ' O 3 i R3 12/87,
)
1.6.2 Surface defects in Class 1, Class 2, and Class 3 ,. bolts, studs, nuts, and ligaments may be removed by i
- mechanical means when the removal of a defect will not alter the basic configurations of the item.
Bolts, studs, and nuts that have defects that cannot i be removed by mechanical means will be replaced. 1.7 System Pressure Testina 4 1.7.1 General Requirements 1.7.1.1 System pressure tests will be conducted in accordance with Article IWA-5000 of Section XI. 1.7.1.2 Evaluation of any corroded area will be performed in accordance with Article I IWA-5000 of Section XI. l 1.7.1.3 Repairs of corroded areas shall be per-formed in accordance.with Section 1.6 of this program. 1.7.2 Class 1 Components 1.7.2.1 After each refueling outage, the system will be leak tested in accordance with l p Article IWB-5000 of Section XI and in I d accordance with Figures 2-1A and 2-1B of the Technical Specifications. l 1.7.2.2 At or near the end of each inspection in-terval, a hydrostati pressure test shall : be performed on the reactor coolant sys- l tem components. This test shall be con- i ducted in accordance with the require-ments of Article IWA-5000 and Article , IWB-5000 of Section XI. Test temperature shall be in accordance with Figures 2-1A and 2-1B of the Technical Specifications. j i 1.7.2.3 Partial penetration welds on the reactor vessel and the pressurizer shall be exam-ined in accordance with Table IWB-2500 Examination Category B-E of Section XI. j 1.7.3 Class 2 Components 1.7.3.1 Pressure tests and visual examination of Class 2 components will be performed in accordance with the guidelines of Section XI. The test pressure will be in accord-ance with the requirements of Article [] IWC-5000. Paragraph 2.1.1 of the Techni-v 4 R3 12/87
l cal Specification, which limits the num- ! g ber of cycles at 125% of design pressure i
;] to 10 for the secondary system (steam / \
feedwater) will be considered. 1.7.4 Class 3 Components I 1.7.4.1 Class 3 components shall be pressure test- ! ed in accordance with Article IWD-5000 of i Section XI. ' I 1.8 Records and Reports l Records and reports made in accordance with this program shall l be developed and maintained in accordance with Article IWA- ; 6000 of Section XI. ) 1 i i l 4 l l l O 5 R3 12/87
O APPENDICES O O 6 R3 12/87
l i APPENDIX IB Exceptions to Compliance with Table IWB-2500-1 - (Class 1 Components) in ASME Boiler and Pressure Vessel Code, 1 Section XI, 1980 (Winter Addenda) i Item No. Excebtion i B 1.40 The closure head to flange weld has physical obstructicas which limit the extent of the ultrasonic eno surface exams. Specifical-- l ly, there are twelve seismic skirt mounting lugs, each six inches l wide, located 37 inches apart, evenly spaced around the exam area. Thus 72 inches of the head to flange weld cannot be examined due to this physical obstruction. Also, due to interference from the seismic skirt and the head flange, the UT scanning is limited to 4 inches either side of the head to flange weld. This restricts the volume of the weld examination, and depending upon the angle of the transducers used may result in less than the code required volume to be examined. Radiation levels of 7-8 C/HR area and 10 R/HR surface have prohibited access to perform the UT from the inside surface of the head. B 3.30 The pressurizer surge line nozzle-to-shell weld cannot be 100% volumetrically examined due to interference from heater penetra-tions. The area will be volumetrically examined to the extent possible. The weld area will be visually examined for leakage l *O l near the end of the inapection interval in accordance with IWB-5221 and IWB-5222. 1 B 3.40 The pressurizer surge line inside radius section cannot be 100% volumetrically examined due to interference from heater penetra- 4 tions. The area will be volumetrically examined to the extent 'l possible. The Area will be visually examined for leakage near the end of the inspection interval in accordance with IWB-5221 and IWB-5222. B.6.20 & Closure head studs will be ultrasonically examined from the center B 6.30 drilled hole in accordance with ASME Code Case N-307 as referenced in Regulatory Guide 1.147, Inspection Code Case Acceptability. B 5.10 The primary piping is fabricated using centrifuga11y cast stain-B 9.40 less steel pipe and cast stainless steel elbows. Experience has ; shown that these materials and welds are not always amenable to l ultrasonic examination. Radiographic techniques'have been devel- ; oped to substantially overcome this problem. Volumetric examina-tion will be performed to the extent practical and according to O 7 R3 12/87 ;
i the schedule designated in the Examination Plan. Should of.her j specialized ultrasonic examination techniques become practical /Q which are more effective, they will be incorporated into the U Examination Plan. Inaccessible Piping Welds: Fiaure No.,* Line No. Weld No. A-22 12 in. - SI-12 16 A-25 12 in. - SI-24 16 A-27 6 in. - SI-14 10 A-27 6 in. - SI-14 11 A-32 3 in. - HPH-22 1 A-32 3 in. - HPH-22 3 - A-38 2 in. - HPH-2.12 5 A-42 12 in. - SDC-20 7 The welds listed above are inaccessible for examination because they are located within walls or floors. Areas on either side of the walls or floors containing these piping welds will be examined for signs of leakage during the pressure and hydrostatic testing s of the piping systems. j B 12.10 The reactor coolant pump casings are made of cast stainless steel sections which are then welded together. This type of material is I not amenable to ultrasonic examination. Further, radiographic ex- { n t amination of a Byron Jackson pump casing has not yet been demon-strated to be feasible in an operating environment. Acceptable i methods of performing a volumetric examination of these welds may be developed before the end of the second ten year interval. If such methods are found, they will be considered for use at the Fort Calhoun Station. If no acceptable volumetric examination can be performed, a surface exam will be performed on 100% of the cas-ing welds on one pump prior to the end of this 10 year interval. ' B 12.20 The District's position is that a visual examination will be per-formed only if a pump is disassembled for maintenance permitting such inspection. This is judged to be adequate based upon design, fabrication, and accessibility considerations.
*See the 10-Year Inservice Examination Plan, Fort Calhoun Station Unit 1 O
8 R3 12/87
l l APPENDIX IC
, Exceptions to Compliance with Table IWC-2500-1 Item No. Inaccessible Piping Welds:
C5.11 Ficure No.* Line No. Weld No. C5.12 i B-12 12 in. - LPSI-12 4 ! B-13 12 in. - LPSI-14 7 J B-13 12 in. - LPSI-14 10 8-13 12 in. - LPSI-14 11 B-14 12 in. - LPSI-22 10 B-15 12 in. - LPSI-24 4 l The welds listed above are inaccessible for examination because they are lo-l cated within walls or floors. Areas on either side of the walls or floors con-l taining these piping welds will be examined for signs of leakage during the l pressure testing of the piping system.
*See the 10-Year Inservice Examination Plan, fort Calhoun Station, Unit 1 9
R3 12/87
i l 1 i APPENDIX ID Exceptions to Compliance with Table IWD-2500-1 Item No. Inaccessible Piping: i D 2.10 Buried raw water lines from the intake structure to the auxiliary building cannot be tested since the isolation valves are not de-signed to be leak-tight shutoff valves. Flow instrumentation in the system is capable of detecting significant leaks by sensing a reduction of flow. 4 l l I O v l O 10 R3 12/87
'I TABLE 1.1 COMPONENTS, PARTS, AND METHODS OF EXAMINATION IWB-2500-1 Examination Category Item Table Components and Parts No. IWB-2500-1 to be Examined Method Reactor Vessel Bl.10 B-A Longitudinal and circumferential shell welds in core region Volumetric .
Bl.20* L'- A Circumferential and meridional head welds Volumetric Bl.30 B-A Shell-to-flange circumferential welds Volumetric ; Bl.40 B-A Head-to-flange circumferential weld Volumetric and j Surface B3.90 B-D Primary nozzle-to-vessel welds Volumetric , B3.100 B-D Nozzle inside radiused section Volumetric 't B4.10 B-E Vessel penetrations, including control ! rod drive and instrumentation penetrations Visual (IWA-5000) 85.10 B-F Nozzle-to-safe end welds Volumetric and Surface B6.20 B-G-1 Closure studs, in place Volumetric B6.30 B-G-1 Closure studs and nuts, when removed Volumetric and l O B6.40 B6.50 B-G-1 B-G-1 Threads in flange . Closure washers, bushing Surface Volumetric Visual B7.10 B-G-2 Pressure-retaining bolting Visual B13.10 B-N-1 Vessel interior Visual B13.30 B-N-3 Core support structures Visual 814.10 B-0 Control rod drive housings Volumetric or Surface B15.10 B-P Exempted components Visual (IWA-5000) Pressurizer 82.10 B-B Longitudinal and circumferential welds Volumetric B3.110 B-D Nozzle-to-vessel welds Volumetric B3.120 B-D Nozzle-to-vessel radiused section Volumetric B4.20 B-E Heater penetrations Visual (IWA-5000) l B5.20 B-F Nozzle-to-safe end welds Volumetric and i Surface ~ - I B8.20 B-H Integrally-welded vessel attachments Volumetric or i Surface ! B15.20 B-P Exempted components Visual-(IWA-5000) i B7.20 B-G-2 Pressure-retaining bolting Visual
- Flow baffles allow internal access to only 25% of the meridional welds.
O , 11 R3 12/g7 l.
- - - . . . - . _ _ . . - . _ - _m__ -
I TABLE 1.1 COMPONENTS, PARTS, AND MFTHODS OF EXAMINATION IWB-2500-1 (CONTINUED) Examination Category . Item Table Components and Parts No. IWB-2500-1 to be Examined Method Steam Generators (Primary Sidel B2.30 B-B Head welds, circumferential and meridional Volumetric B2.31 B2.32 B2.40 B-B Tubesheet-to-head weld Volumetric B3.130 B-D Nozzle-to-vessel Volumetric B3.140 B-D Nozzle inside radius section Volumetric B5.30 B-F Nozzle-to-safe end Volumetric and Surface 86.90 B-G-1 Bolts and studs Volumetric B6.100 B-G-1 Flange surface, when disassembled Visual 86.110 B-G 1 Nuts, bushings, and washers Visual j B7.30 B-G-2 Bolts, studs, and nuts Visual B8.30 B-H Integrally welded attachments Volumetric or Surface B15.30 B-P All pressure-retaining components Visual B16.20 B-Q Steam generator-tubing Volumetric O. 82.50 B-B Shell (or head) welds, circumferential Volumetric and longitudinal (or meridional) B2.52 82.60 B-B Tubesheet-to-shell (or head) welds Volumetric B3.150 B-D Nozzle-to-vessel welds Volumetric B3.160 Nozzle inside radius section Volumetric B5.40 B-F Nozzle-to-safe ehd welds Volumetric and Surface B6.120 B-G-1 Bolts and studs, ih place . Volumetric B6.130 B-G-1 Bolts and studs, when removed Surface and Volumetric B6.140 B-G-1 Bolting Visual B7.40 B-G-2 Bolts, studs, nuts Visual 88.40 B-H Integrally w;.lded attachments Volumetric or Surface B15.4 B-P Pressure-retaining boundary Visual O 12 R3 12/87 l
l TABLE 1.1
)
COMPONENTS, PARTS, AND METHODS OF EXAMINATION IWB-2500-1 (CONTINUED) Examination 3 Category , Item Table Components and Parts ' No. IWB-2500-1 to be Examined Method j Pipina Pressure Boundary 89.10 B-J Nominal pipe size 14 in. Surface B9.11 B-J Circumferential welds Surface and Volumetric B9.12 B-J Longitudinal welds Surface and Volumetric B9.20 B-J Nominal pipe size < 4 in. Surface 89.21 B-J Circumferential welds Surface B9.22 B-J Longitudinal welds Surface 89.30 B-J Branch pipe connection welds Surface 89.31 B-J Nominal pipe size > 2 in. Surface and Volumetric B9.32 B-J Nominal pipe size s 2 in. Surface 89.40 B-J Socket welds Surface B6.150 B-G-1 Bolts and studs, Volumetric B6.160 B-G-1 Flange surface, when disassembled Visual ( B6.170 B-G-1 Nuts, bushings, and washers Visual ( B7.50 B-G-2 Bolts, studs, and nuts Surface B10.10 B-K-1 Integrally welded attachments Volumetric or Surface B15.50 B-P Pressure-retaining boundary Visual Pumo Pressure Boundary B6.180 B-G-1 Bolts and studs Volumetric B6.190 B-G-1 Flange surface Visual B6.200 B-G-1 Nuts, bushings, and washers Visual B10.20 B-K-1 Integrally-welded attachments Volumetric or , Surface i B12.10 B-L-1 Pump casing welds Visual B12.20 B-L-2 Pump casings Visual i B15.60 B-P Pressure-retaining boundary Visual (IWA-5000) B7.60 B-G-2 Bolts, studs, and nuts { Visual l l D G 13 R3 12/87 i t___________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ . - _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
TABLE 1.1 , ( COMPONENTS, PARTS, AND METHODS OF EXAMINATI0d IWB-2500-1 (CONTINUED) Examination Category item Table Components and Parts No. IWB-2500-1 to be Examined Method Valve Pressure Boundary B6.210 B-G-1 Bolts and studs, in place Volumetric B6.220 B-G-1 Flange surface Visual B5.230 B-G-1 Nuts, bushings, and washers Visual B7.70 B-G-2 Bolts, studs, and nuts Visual B10.30 B-K-1 Integrally welded attachments Volumetric or Surface B12.30 B-M-1 Valve body welds < 4 in. Volumetric B12.40 B-M-2 Valve body 2 4-in. nominal pipe size Visual B15.70 B-P Pressure retaining boundary Visual O l O 14 R3 12/B7
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7 ;, j i? ) 1 TABLE 1.2 g m COMP 0NENTS, PARTS, AND METHODS OF EXAMINATION IWC-2500-1 *~ :j c
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Item Category Table Components andc,hd1 - d bnb If d No. IWB-2500-1 to be Examined? 'A$ I Meth64 s y . PressureVib1_g. 1 pe ./, ']J 1N 3 d[ f C1.10 C-A Shell c'trcumferential beld.o 3 91 A , , , Volumetric C1.20 C-A Head circumfadatial weldk ,k ; 0 folumetric
) [ $ 1umgr.ric
's C1.30 C-A Tube shut-torshell welk V .
C2.10 C-B Nozzles W vrpsels 1 },@-in.Ypinal " 7 I ,M. So; # ace-
, thickness - > 1 .
C2.20 C-B Nozzles in vedhis > 1/2!<iid, "@,inal h%' - 9* thickness Surfse,L , gi{ C2.21 C-8 -Nozzle-to-shell (or head) weld Surfat,ptog* 1 'g , Voluketf*d; C2.22 C-B Nozzle inside radius .section Ve hmetYic s 11 /j'l k Integrally weldedintachme;c #,, C3.10 C-C Surface' s,- fI C4.10 C-H Bolts and studs y, . Volume;tric < .c C7.10 C7.11 C-H Pressure-retaining components Pressure-retaining components t l' Vi sval g h'A C-H
,' Visual
[f ( / i (' f , Pioina ,.
\[ /
A g . .s C3.40 C-C Integrally welded attac ~2.its > Y Surface C4. 7.0 C-D Bolts and studs - VolumetH c
- C5.11 C-F Circumferential welds 4 3.-in. s .
nominal wall thickner,s>" ' ( Surface C5.12 C-F Longitudhe welds 11/ r' y nominal wa'il thickness ] It. 7 Seface C5.21 C-F Circumferential welds 51/2-in.' . nominal wall thickness *g C5.22 C-F Longitudinal weld P2 1/2-in. ([Drface blumetfv.,nd ,j jSurfacdanf nominal wall thickness Volumetric C5.31 C-F Circumferent.%1 pipe branch *- connection kelds Surface
$5.32 C-F , Longitudinal pipe branch jconnection welds
} ,
f,,.]tirface 1 i C7.20 C-H fressure-retainingcomponents I. 'ts Visual D t, p,* , 1
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TABLE 1.2 ,> ( COMPONENTS, PARTS, AND METHODS OF EXAMINATION IWC-2500-1 (CONTINUED) Examination s Category < Item Table Components and Parts No. IWB-2500-1 to be Examined . Pekhod
'I Pumos s e , C6.10 C-G Pump casing welds Surface C7.30 C-H Pressure-retaining components . Visual C3.70 C-C Integrally-welded attachments ' Surface )
l C4.30 C-D Bolts and stads Volumetric I
-1 Valves >
C6.20 C-G Valve body welds Surface + C7.40 C-H Pressure-retaining components Visual C3.100 C-C Integrally-welded attachments Surface C4.40 C-D Bolts and studs Volumetric; , i i - i r j O '
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PART 2: Class 1, Class 2, and' Class 3 Pump'and Valve Tests 2.1 ScoDe and Responsibility 2.1.1 The P& ids of Appendix 1A identify the location of ] each Class 1, Class 2, and Class 3 pump and valve. - ' t 2.1.2 Class 1, Class 2, and Class 3 pumps to be tested under Subsection IWP., the test methods for_each pump, and exceptions to the tests of Subsection.IWP-are found in Appendix 2A. The Class 1,. Class 2, and Class 3 valves to be tested under Subsection IWV, the methods of testing for.each valve,.and excep-
.tions to the tests of Subsection IWV are found in
. Appendices.2B and'2C. 1 J
2.2 Inservice Test Freauency 2.2.1 The inservice test frequency for Class 1, Class 2, and Class 3 pumps are in accordance with Article IWP-3000 of Section XI. The' inservice test fre-quency for Class 1, Class 2,-and Class 3 valves are
'in accordance with Article IWV-3000 of Section XI with exceptions as found in' Appendix 2C. i 2.2.2 Valves identified herein as being tested at cold-shutdown frequency shall be' tested each cold shut-
, down where the duration of the shutdown is suffi-cient-to accomplish the tests. Valve testing should commence not later than 48 hours after shutdown and continue until~ complete or plant is ready to return to power. Completion of all valve testing is not a prerequisite to return to power. Any< testing not completed at one cold shutdown should be performed ;
during subsequent: cold shutdown to meet-the code l required testing frequency. Where more.than one-. l cold shutdown occurs within three months, the test frequency shall not exceed once per three month period. i 2.3 Valve Cateaories 2.3.1 The valve categories for each Class 1, Class 2, and Class 3 valve have been determined from Article IWV-2000~of Section XI with exceptions as found in Appendix 2C. 2.4 Test Methods i 2.4.1 The methods to be used to test Class 1, Class 2, and ! l Class 3 pumps and valves have been determined from 1 the appropriate articles of Subsections IWP and IWV ! of Section XI, respectively. These methods, along O, with exceptions, are listed in Appendix 2C and i V ., 17 R3 12/87-3 N d' , , -
s Appendix 2B for Class 1, Class 2, and Class 3 pumps and valves, respectively. D (V 2.4.2 -Valves with remote position indicators shall be ob-served at least every two years to verify that valve operation is accurately indicated. 2.4.3 Valve with failure position indicated in the valve tables will be tested by observing valve operation upon loss of activator power at the frequency specified in the valve table. 2.4.4 Valve stroke time limits that prove to be impractical may be changed after completion of an engineering eval-uation to ensure valve operability. 2.5 Evaluation of Test Results
2.5.1 Pumps
2.5.1.1 The evaluation of test results shall be in accordance with Table IWP-3100-2 of Section XI as appropriate. All test data shall be analyzed within 96 hours after completion of a test in accordance with IWP-3220.
2.5.2 Valves
b 2.5.1.2 The evaluation of test results shall be in accordance with the appropriate Subarticles of Article IWV-3000 of Section XI. 2.6 Records and Reports 2.6.1 Records and reports for the testing of Class 1, Class 2, and Class 3 pumps shall be made in accordance with Article IWP-6000 of Section XI. Records and reports for the testing of Class 1, Class 2, and Class 3 valves shall be made in accordance with Article IWV-6000 of Section XI. 2.7 Repair Requirements
2.7.1 Pumps
2.7.1.1 Tests, after pump replacement, repair or ser-vicing, shall be made as required by Section XI, Article IWP-3000.
2.7.2 Valves
2.7.2.1 Tests, after valve replacement, repair or rQ maintenance, shall be made as required by (./ Section XI, Article IWV-3000. 18 R3 12/87
- - -----_- J
APPENDIX 2A p v Inservice Testing of Pumps Discussion: The pumps that require inservice tests for operational readiness un-der the ASME B&PV Code, Section XI, Subsection IWP are listed below. The inser-vice test parameters and test frequencies are tabulated for each pump. The re- ] quested test exceptions and basis for each exception are given for the applicable parameters. ; General: The pumps listed are directly coupled to induction motor drivers; there-fore, the rotation speed need not be measured as prescribed in Subarticle IWP- 1 4400. Operating modes, as designated in this appendix, are as follows: Mode 1 - Power Operation, Mode 2 - Hot Standby, Mode 3 - Hot Shutdown, Mode 4 - Cold Shut-down, Mode 5 - Refueling Shutdown. Low Pressure Safety injection Pumos SI-1A, B Class 2 P&lD: CE-E-23866-210-130, Sheet 1 of 2 (G4) Functiln: The LPSI pumps are available for safety injection of borated water into the reactor coolant system following a LOCA and are used to remove residual heat for cold shutdowns. l l Containment Spray Pumos SI-3A, B, C Class 2 P&ID: CE-E-23866-210-130, Sheet 1 of 2 (G3, G2, G2) Function: The CS pumps are available to spray borated water into contain-ment following a LOCA. Hiah Pressure Safety Iniection Pumos SI-2A,B, C Class 2 P&ID: CE-E-23866-210-130, Sheet 1 of 2 (G6, G7, G7) Function: The HPSI pumps are available for safety injection of borated water into the reactor coolant system following a LOCA and are used to main-tain the required water level in the safety injection tanks. Operating Modes Subarticle Required for Test Parameter ,Frecuency Exceptions Testina l l Inlet Pressure Quarterly IWP-3100 1, 2, 3, 4 or 5 Differential Pressure Quarterly IWP-3100 1, 2, 3, 4 or 5 Vibration Amplitude Quarterly 1, 2, 3, 4 or 5 l Lubrication Level Quarterly 1, 2, 3, 4 or 5 Bearing Temperature Yearly 1, 2, 3, 4 or 5 Flow Rate - IWP-3100 - 19 R3 12/87
Exceptions: []/ IWP-3100 Flow measurement Basis: Original plant design did not include flow mea-l
\
surement for these pumps. These pumps are in fixed resistance systems. The inservice testing l of differential pressure across these pumps un- 1 der a minimum recirculation flow condition (and !' thus near shutoff head) is deemed adequate to allow determination of pump functionality and/or degradation. 1 l IWP-3100 Inlet and differential pressure measurement I Sasis: Inlet pressure for these tests will be deter-mined by measuring the static head tank level. Charaina Pumos CH-1A, B, C Class 2 l P&ID: CE-E-23866-210-120, Sheet 1 of 2 (E6, E4, E3) Function: The charging pumps are provided to return the purification flow to the reactor coolant system during plant steady state operations. Subarticle Operating Mode Test Parameter Freauency Exceptions Reauired for Testina
/%
(#) Inlet Pressure Quarterly 1, 2 or 3 Differential Pressure Quarterly 1, 2 or 3 Flow Rate Quarterly IWP-4120 1, 2 or 3 l Vibration Amplitude Quarterly 1, 2 or 3 Lubricant Level and Pressure Quarterly 1, 2 or 3 l Bearing Temperature Yearly 1, 2 or 3 Exceptions: IWP-4120 Flow Measurement Basis: System is designed for simultaneous flow of all 4 three pumps. Therefore, reference flow is less than 1/3 of instrument full scale range. Component Coolina Pumos i AC-3A, B, C Class 3 l P&lD: GHDR-11405-M-10 (D2, C2,82) l l Function: The component cooling pumps supply cooling water to equipment in the containment and auxiliary building. Operating Modes ; Subarticle Required for i Test Parameter Freauency Exceptions ,. Testina Inlet Pressure - IWP-3100 - Differential Pressure - IWP-3100 - n Flow Rate - IWP-3100 - (,j Vibration Amplitude Quarterly - 1, 2, 3, 4 or 5 Lubricant Level of Pressure - IWP-3100 - Bearing Temperature Yearly - 1, 2, 3, 4 or 5 20 R3 12/87 i
Exceptions IWP-?l00 Inlet and differential pressure measurement Basis: System design does not include instrumentation for > measuring these parameters. Discharge pressure will be measured on a quarterly schedule to-help determine possible pump degradation. 'j Establishment of a reference value for flow rate f E,a si s: There are many components or subsystems on the com-ponent cooling' water system with several possible. piping configurations. Some of the components are critical elements to which the flow rate cannot-arbitrarily be varied for the sake of running a pump test. Consequently, establishing a reference flow rate for a pump test on a periodic basis is impractical. Lubricant level or pressure observation Sasis: The pump bearings are cartridge type that have been' pre-packed with the proper amount of grease and-under normal conditions require no further atten-tion for the life of the bearings.
Reference:
Ingersoll Rand Instruction Manual Boric Acid Pumos CH-4A, B Class 3 i P_AE: CE-E-23866-210-121 Function: The boric acid pumps supply blended boric acid to the charging. pump header and provide makeup 'to the SIRW and volume control tanks. Operating Modes Subarticle Required for-Test Parameter Frecuency Exceotions Testino Inlet Pressure Quarterly IWP-3100 1, 2, 3, 4 or 5 ; Differential Pressure Quarterly IWP-3100 1, 2, 3, 4 or 5 Vibration Amplitude Quarterly 1, 2, 3, 4 or 5 Lubricant Level Quarterly - 1, 2, 3, 4 or 5 Bearing Temperature Yearly -
-1, 2, 3, 4 or 5 Flow Rate -
IWP-3100 - Exceotions: I IWP-3100 Flow measurement Basis: Original plant design did not include flow measure-ment for these pumps. These pumps are in fixed re- q O sistance systems. The inservice testing of differ-ential pressure across these. pumps under a minimum 21 R3'12/87 1 L_________._.___ _______m___ -
i J e recirculation flow condition (and thus near shutoff
. head) is deemed. adequate'to allow determination of pump functionality and/or degradation.
Inlet and differential pressure measurement. Ba:is: Inlet pressure will be determined by measuring the static head tank level. Raw Water Pumos. AC-10A, B, C, D Class 3 P&ID: GHDR-11405-M-100 l l Function: The raw water pumps provide a cooling medium for the component cooling water system. 1 Operating Modes
'Subarticle Required for Test Parameter Freauency Exceptions Testino Inlet Pressure -
'IWP-3100 -
Differential Pressure - IWP-3100 - Flow Rate - IWP-3100 - Vibration Amplitude Quarterly 1,2,3,4 or 5 Bearing Temperature - IWF-3100 - Discharge Pressure vs. Motor Amperage Quarterly IWP-3100 1,2,3,4 or 5' E_xceotions: IWP-3100 Inlet pressure measurement Basis: System design does not permit direct measurement of' ! inlet pressure. Varying river level and unknown accumulations of sand near the pump shetion bell i make it impossible to determine the inlet pressure. I Differential pressure measurement Sasis: Because of the inability to measure inlet pressure, differential pressure measurement is not possible. Flow rate measurement Sasis: The system design does not provide an accurate .. indication of flow rate due to fouling by untreated ; river water. l Bearing tem,terature measurement 1 Basis: All bearings are inaccessible for temperature = 'l measurement. All are submerged in river water. 1 0 , 22 .{ R3 12/87 ;
Discharge pressure vs. motor amperage f Basis: To be performed in lieu of a differential pres-sure measurement. An acceptable motor amperage. j value will be determined over a discharge pres - sure range of 26 through 40 psig. Auxiliary Feedwater Pumps. FW-6, FW-10 Class 3 I PalQ: GHDR-11405-M-253 i Function: The auxiliary feedwater pumps provide water to the steam gen- l erators when normal condensate feedwater flow is unavailable. Subarticle P.equired for Test Parameter Freouency Exceptions Testina i Inlet Pressure- Quarterly IWP-3100 1, 2 or 3 Differential Quarterly IWP-3100 1, 2 or 3 Pressure Flow Rate Quarterly IWP-4120 1, 2 or 3 l Vibration Quarterly - 1, 2 or 3 Amplitude Bearing Yearly - 1, 2 or 3 Temperature ( Exceptions: IWP-3100 Inlet pressure measurement i Basis: System design does not permit direct measurement of inlet pressure. Inlet pressure to be measured by. observing Aux FW tank level or head. Differential pressure measurement Basis: Because of the inability to measure inlet pressure, l direct differential pressure measurement is not possible, but it will be' calculated by. subtracting input from output' pressure (in consistent units )- IWP-4120 Flow measurement Basis: Due to small diameter bypass piping, reference flow is less' than 1/3 of instrument's full ' scale range.. l 0 l 23 R3 12/87
APPENDIX 2B Inservice Testing of Valves Discussion: Valves that require an inservice test for operational readiness under the ASME B&PV Code, Section XI, Subsection IWV, are listed below. Test 3 parameters, frequencies, and test exceptions are tabulated for each valve. ' It has been determined that there are no Category D valves at the Fort Calhoun , Station Unit I which are subject to the inservice inspection program. J All Category A valves, unless otherwise noted, will be leak-rate tested, once every two years, during Cold Shutdown (CS) or during a Refueling Outage (RO). TABLE 28-1 The following Category A valves are listed in groups representing those valves which shall be leak-rate tested simultaneously due to system configuration. )
- 1. TCV-202, HCV-204
- 2. HCV-241, HCV-206
- 3. HCV-506A, HCV-506B
- 4. HCV-507A, HCV-5078
- 5. HCV-467A, HCV-4678 m 6.
7. HCV-4670, HCV-4670 HCV-438A, HCV-438B Q8 8. HCV-438C, HCV-438D
- 9. HCV-500A, HCV-500B
- 10. HCV-2983, SI-185, HCV-2956, HCV-2976, HCV-2936, HCV-2916, PCV-2949, HCV-2969, PCV-2909, PCV-2929
- 11. HCV-509A, HCV-509B
- 12. HCV-508A, HCV-508B
- 13. HCV-882, VA-289
- 14. HCV-425A, HCV-425B
- 15. HCV-425C, HCV-425D
- 16. HCV-2603A, HCV-2603B
- 17. HCV-2604A, HCV-2604B
- 18. HCV-2504A, HCV-2504B
- 19. PCV-742E, PCV-742F
- 20. PCV-742G, PCV-742H
- 21. HCV-746A, HCV-746B
- 22. HCV-881, VA-280
- 23. HCV-1560A, HCV-1560B
- 24. HCV-1559A, HCV-1559B
- 25. PCV-742A, PCV-742B
- 26. PCV-742C, PCV-7420 0
24 R3 12/87
I i i APPENDIX 2C O V Cateacry A Valves. l l J. Justification for stroke test frcouency of once per cold shutdown for valve that are impractical to test at the preferred quarterly frequency. See IWV-3412(a) HCV-425A These valves serve to isolate containment penetrations M-39 3 425B and M-53, component cooling system penetrations. Struing j 425C cannot be pe-formed quarterly because failure of these valve ) 425D in the closed position would trminute cooling to safety in- I jection tanks leakage coolers which would in turn have poten- ) tial for resulting in hot fluid streams entering ion ex-change resins of chemical volume control system, thereby causing damage. These valves cannot be partial-stroked be- , cause they are either fully opened or fully closed. These 1 valves shall be exercise tested during cold shutdown. 1
~
HCV-438A These valves serve to isolate containment penetrations M-18 4388 and M-19, RCP seal cooling water. The pump manufacturer 438C recommends seal flow when the RCS temperature is ever 130'F 4380 Stroke-testing cannot be performed quarterly or at cold shut- ; down when one or more reactor coolant pumps are in operation ' or when the RCS temperature is greater than 130*F because ) I stroking of these valves would terminate lube oil and seal l l cooling. These valves cannot be partial-stroked because j they are either fully opened or fully closed. These valves i O shall be exercise tested during each refueling outage and at cold shutdown when the RCP's are stopped and the RCS tempera- , ture is below 130*F. l HCV-467A These valves serve to isolate containment penetrations M-15 4678 and M-11, component cooling system penetrations. These 467C valves cannot be stroked quarterly because failure of the 4670 valve during testing would render the nuclear detector well cooling units inoperable. Should the nuclear detector well cooling units fail, the LC0 specified in Technical Specifi-cation 2.13 would be entered and could result in plant shut- ] down. These valves cannot be partial-stroked because they ! are either fully opened or fully closed. These valves shall ! be exercise at each cold shutdown. ! PCV-1849 This valve serves to isolate instrument air pressure (vik l penetration M-73) to containment systems. Stroke-testing ) cannot be performed quarterly since instrument air must be available at all times during operation. The valve cannot , be partial-stroked because it is either fully opened or ! fully closed. This valve cannot be stroke tested during 1 cold shutdown unless the RC Pumps are off and the RCS is i depressurized, because closing this valve would cause loss ! l of level and pressure control functions. This valve shall I be exercise tested during cold shutdown when the RC Pumps ! are off and the RCS is depressurized.
]
1 25 R3 12/87 j 4 e -___- -
TCV-202 This valve is used for RCS loop 2A, letdown isclation and tem-perature regulation. Stroking of this valve quarterly during
,\
[d operation could result in the termination of letdown flow. This could isolate the boronometer, process radiation monitor,
)
)
and reactor coolant system purification process and could have the potential of causing a reactivity excursion. The valve cannot be partially stroked because it is either fully open or - i fully closed. It shall be exercise tested during cold shut- l down when the RCS is depressurized. i HCV-206 This valve serves as penetration Il-7 isolation. This valve cannot be stroked when the reactor coolant system is pressur-ized because controlled bleed-off must be maintained to pre- i vent damage to the reactor coolant pump seals. The valve can- I not be partial-stroked because it is either fully open or fully closed. It shall be exercised during cold shutdown when the RCS is depressurized and the RC Pumps are stopped. HCV-241 This valve is used for reactor coolant pump control bleed-off isolation. It cannot be stroked when the reactor coolant system is pressurized, because controlled bleed-off flow must I be maintained to prevent damage to the reactor coolar.t r, ump j seal s. The valve cannot be partial-stroked because it is ! either fully open or fully closed. It shall be exercised ! duringcoldshutdownwhentheRCSisdepressurizedar.dtheRCl I Pumps are off. j The function of this valve is for containment penetration fi-2 p) ( HCV-204 isolation and letdown control. The stroking of tnis valve quarterly during operation would result in termination of let-down flow. This would also isolate the boronometer, process radiation monitor, and reactor coolant system purification pro- , cess. In addition, the potential would exist for a reactivity l excursion. The valve cannot be partial-stroked because it is ; either fully open or fully closed. It shall be ex9rcise test- ; ed during cold shutdown when the RCS is depressurized. i HCV-347 These valves cannot be exercised during operation because 348 they are interlocked closed when the RCS pressure >250 psia. , These valves will be exercise tested at cold shutdown when the shutdown cooling system is in service. HCV-2916 The function of these valves is to permit filling and drain-2936 ing of safety injection tanks. These valves cannot be 2956 stroked during operation because doing so would cause level 2976 fluctuations in the safety injection tanks. The level of the safety injection tanks is contrM ied by Technical Specifica-i tions, and strLking the valves may result in entering an LCO. They shall be exercise tested during cold shutdown. 51-194 These valves cannot be stroke tested during reactor operation 197 because no flowpath is available at operating pressure. These 200 valves are leak checked per TS 2.1.1(12), and stroke tested
,O 203 during cold shutdown when the shutdown cooling system is in service.
26 R3 12/87 l
R. Explanation of circuwtances that require relief from specific require-ments of Subsection IWV. The need for relief from the code requirement g typically arise out of concerns of safety or practicality. PCV-742A Valves PCV-742A and 742C cannot be tested in the direction 742C of their design function in accordance with IWV-3420 due to system configuration. The '.ntent of Subsection IWV to verify the leak rate is met, since testing in the direction opposite to the design function will result in a greater leakage than would be experienced in a test in the preferred direction. HCV-746A This valve cannet be leak-tested in the direction of its de-l sign function in accordance with IWV-3420 due to system con-figuration. The intent of Subsection IWV to verify the leak rate is met, since testing in the direction opposite to the design function will result in a greater leakage than would be experienced in a test in the preferred direction. l HCV-820B These valves cannot be tested in the direction of their de-821B sign function in accordance with IWV-3420 due to system con-883A figuration. The intent of subsection IWV to verify leak 884A rate is met, since testing in the direction opposite to the design function Will result in a greater leakage than would be experienced in a test in the preferred direction. HCV-2504A This valve serves to isolate the containment reactor coolant G system sample link at penetration M-45.' This valve cannot be
'V leak-tested in the direction of its design function in accord-ance with IWV-3420 due to system configuration. The intent of Subsection IWV to verify the leak rate is met, since testing in the direction opposite to the design function will result in a greater leakage than would be experienced in a test in the preferred direction.
HCV-1749 This valve serves compressed to isolate containment penetration M 74,Thisvalve air penetration. in the direction of its design function in accordance with IWV-3400 due to systera configuration. The intent 'of Subsec-tion IWV of the Section XI code, to verify the operational readiness, is met since testing in the direction opposite to the design function will result in a greater leakage than j i would be experienced in a test in the preferred direction. HCV-2603B These valves serve to isolate containment penetrations H-42 2604B and M-43 for the nitrogen gas header. These valves cannot be leak-tested in the direction of their design function in accordance with IWV-3420 due to system configuration. The intent of Subsection IWV to verify the leak rate is met since testing in the direction opposite to the design function will result in a greater leakage than would be experienced in a test in the preferred direction. (D 1 v 27 R3 12/87
l SI-208 These valves can only be full stroke tested when the head 4 212 is off the reactor pressure vessel to provice a flow path l for water from Safety Injection Tank. 216 These valves are f)3 n 220 leak cheched per TS.2.1.1(12), and stroke tested during refueling outages. j SI-195 These valves are between the HPSI header and the SI in-198 jection points to the RCS. They cannot be stroke tested 201 during operation because no flow path is available at oper-204 ating pressure. Stroke testing during cold shutdown could i result in low temperature overpressurization of the RCS. j These valves are leak tested per TS.2.1.1(12) and stroke j tested during refueling outages. 1 l l 1
^
( 1 L) l I I i 28 R3 12/87 1
l I Cateaorv B Valves .) J. Justification for stroke test frequency of once per cold shutdown for ; 4 valve that are impractical to test at the preferred quarterly frequency. .j See IWV-3412(a) HCV-2506A These valves serve to isolate steam generator blowdown samp-25068 ling lines. Stroke-testing'cannot be performed quarterly 2507A during operation because doing so'would terminate blowdown 2507B sample lino flow. The steam generator blowdown activity mon-itor is on the sample line. Technical Specification 2.9(1)e requires that blowdown activity shall be continuously moni-tored by the steam generator blowdown sample monitoring sys-tem. Partial-stroking cannot be performed since these valves are either fully opened or fully closed. These valves shall be cycled at cold shutdown. HCV-400A,B,C,D These valves serve to isolate component cooling to contain- ) 401A,E',C,D ment air cooling and filtering units. They cannot be cycled 402A,B,C,0 quarterly because doing so would terminate component cooling 403A,8,C,0 to air cooling and filtering units in containment. Failure of one of these valves in a nonconservative position during testing when the. plant is operating would cause entry into an LC0 as defined in Technical Specification 2.4. These valves shall be cycled at cold shutdown.
~'e HCV-1041A These valves serve to. isolate the main steam headers. They 1042A cannot be tested quarterly during operation because doing so would isolate steam flow in the steam generators and result-in a turbine and reactor trip. The valves cannot be partial-stroked because they are either fully opened or, fully closed.
These valves shall be stroke tested at cold shutdown. l HCV-1041C These valves serve to provide a. pathway from the steam gen-1042C erator.to a steam dump and bypass valves in'the event that the main steam isolation valves close. These valves are also used to preheat the turbine and related steam system during startup. Cycling of these valves on a quarterly basis during operation would cause the main steam isolation valves to , close, causing the turbine to trip and resulting in a reactor trip. The valves cannot be partial-stroked for the same rea-l son. These valves shall be cycled at-cold shutdown. HCV-1385 These valves serve t'o isolate main feedwater to the steam J 1386 generators. Quarterly stroke-testing cannot be performed during operation because doing so would isolate feedwater tc steam generators resulting in a reactor trip. These valves cannot be partial-stroked because they are either fully opened or fully closed, These valves shall be cycled at cold shutdown. '. O ! 29 R3 12/871 < l
)
HCV-1387A These valves serve to isolate steam generator blowdown. I 1387B They cannot be stroke-tested during operation quarterly be- )
- 1388A cause doing so would terminate steam generator blowdown and {
s 1388B disrupt all volatile chemistry control. They cannot be par- ! tial-stroked because they are fully opened or fully closed. I These valves shall be cycled at cold shutdown. LCV-218-2 These valves function to provide volume control tank level 218-3 control and switch charging suction to the SIRWT. The ; valves cannot be stroke-tested quarterly because doing so 1 would terminate charging flow to the reactor coolant system and would have the potential for disrepting pressurizer level regulation or boron concentration regulation. Pressur- ) izer level regulation disruption can lead to reactor coolant system pressure transients and disruption of boron concentra-tion could cause reactivity excursions. They shall be exer- 1 cised at cold shutdown. HCV-240 Full stroke exercising of these valves during operation will 249 lead to large scale depressurizqtion of the RCS and thermal { shock of the pressurizer spray nozzle. These values will be -{ cycled at cold shutdown. l HCV-258 These valves serve to isolate concentrated boric acid from 265 the charging pump suction header. These valves cannot be cycled quarterly because doing so would cause concentrated l boric acid to be injected into the reactor coolant system ' (. via charging pump suction header gravity feedline. Boration of the primary system during normal operat. ion would cause reactivity transients and possibly shut down'the plant. > These valves cannot be partial-stroked for the same reason. These valves shall be exercise tested during cold shutdown. , HCV-268 This valva serves to permit direct feed of concentrated bar-
~
l ic acid solution to the charging pump suction header. -This ! I valve cannot be stroke-tested quarterly because doing so l l would allow concentrated boric acid storage to the charging { pump suction header through the boric acid pumps. Beration ! , of the crimary system during normal operation would cause l reactivity transients &nd possibly shut down the plant. The valve cannot be partial-stroked for the same reason. The valve shall be exercise tested during cold shutdown. ; HCV-344 These valves serve as containment spray 1 solation. Stroke-345 testing during cold shut.down er quarterly is net advisable ; since the potentia'l for sprayirg down the containment is ta-creased. These valves represent the only boundary between the containment spray and safety injection pump headers'and containment spray nozzles when valves SI-177 and l'/8 are I open. The valves cannot be partial-stroked for the same l reason. These valves shall be exercised at cold shutdown. O : 30 R3 12/87
I HCV-3C4 These are valves on the HPSI Pump discharge header. They 305 cannot be tested during operation because failure in a non-306 conservative' position would block one of'the safety injec-1O 307 tion flow paths. These valves'will be stroke tested at cold shutdown. HCV-308 These valves provide an. alternate char 0ing flow path into 2988 the HPSI header and an alternate source for Long Term Core Cooling. They cannot be exercised during operation because a charging pump is always running eduring operation and open-ing one of these valves would expose the HPSI header to l charging pressure at a time when this is not a desired charg - { ing flow path. It is impractical to shut down the charging _- I flow to perform this test because of the thermal and flow transients that would be caused. These valves will be stroke tested at cold shutdown. , l HCV-2987 This valve closes to provide a long Term Core Cooling flow l path. It cannot be tasted during operation because failure a in a non-conservative position would block one of.the-safety I injection flow paths. This valve wil) be stroke tested at'- cold shutdown. HCV-176 Those valves are intended to vent a bubble in the RPV head. - 177 They cannot be exercised quarterly during power aperations since this would vent high temperature / pressure reactor cool-180 ant to the quench tank. The valves will be tested at cold shutdown'when the RCS is depressurized. O.. HCV-150 These are block valves that function to isolate the PORV.'s 151 in the event that the PORV leaks or fails to close. HCV-150 and 151 cannot be stroke tested during operation because failure of one of these valves would cause entry into an LC0 as defined in Technical Specification 2.1.6(5). These valves will be tested at cold shutdown. PCV-102-1 These valves are the pressurizer PORV's. They have solenoid 102-2 pilot valves that control their actuation. They can only open or close when there is a pressure differential across the valve. Since the PORV's have shown a high prchability of sticking open and are not needed for overpressure protec-tion during operation, quarterly exercising during power operat' ion is not practical. These valves will be stroke tested at cold shutdoxn. SA-147 These are the start valves on the diesel generators. These. 148 valves will be alternately tested by Surveillance Test ST-197 ESF-6 at least quarterly during the diesel generator start 198 test. The stroke times for these valves are considered acceptable if the diesel generator is ready for load within the time prescribed in the surveillance test. 31 R3 12/87
l Catea w y C Valves l [ k J. Justification for stroke test frequency of once per cold shutdown for valves that are impractical to test at the preferred quarterly frequency. See , IWV-3520. ! FW-163 These valves open for auxiliary feedwater flow to the S.G. Cycl- ) 164 ing these valves during operation would result in cold water in- I jection to a portion of the S.G., normally at operating temper-atures. These valves will be cycled open during each cold shut-down. These valves shall be exercise tested each cold shutdown or refueling outage. Since failure of these valves to function in the back flow direction would not interfere with the plant's 1 ability to shut down or mitigate the consequences of an acci- l dent, these valves shall only be tested in tne forward flow direction. FW-173 This valve opens for auxiliary feedwater flow to the steam gener-
.ator when the motor driven AFW pump (FW-6) is operated. Cycling this valve during operation would result in cold water injection to a portion of the steam generator normally at operating temp-erature. This valve shall be cycled open during startup follow-ing each cold shutdown or refueling outage. This valve shall be tested in the closed position quarterly during the pump sur-veillance test.
CH-205 Full stroke exercising of this valve during operation will lead g) (~ to large scale depressurization of the RCS and thermal shock to the pressurizer spray nozzle. This valve will be cycled at cold shutdown, { j SI-121 These valves function to prevent backflow to the LPSI pumps. I 129 These valves cannot be full stroke tested quarterly because ( there is no flow path available except during shutdown cooling. i Partial stroking cannot be performed for the same reason. Exer-cising shall be performed at cold shutdcwn. l SA-137 These are the check valves en the c'ischarge of the diesel gen- j 138 erator starting air compressors. They will not be stroke test-187 ed open because presence of specified air pressure in the start-188 ing air receivers is adequate to demonstrate that the valves are i opening. They will be tested to verify closure quarterly by ' sensing upstream pressure when the air compressor is off. I i R. Explanation of circumstances that require relief from specific requirements of Subsection IWV. The need for relief from the code requirement typically arise out of concerns of safety or practicality. FW-174 This valve opent for auxiliary feedwater flow to the steam gen-erator when the steam driven AFW pump (FW-10) is operated. Cycl-ing this valva during operation would result in cold water injec-tion to a portion of the steam generator normally at operating 7 temperature. This valve is not cycled during startup because steam is not available to run FW-10. (G 32 R3 12/87
This-valve shall be removed from the line for strcke testing during each refueling outage. This valve shall be tested in f^ the closed position quarterly du' ring.tha pump' surveillance test. CH-143 These valves serve to permit direct feed of concentrated boric 155 acid solution to the charging pump suction header. These 156 valves cannot be stroke-tested during cold shutdown or quarter-ly because doing so would allow concentrated boric acid storage to the charging pump suction header through the boric acid pumps. Boration of the primary system during normal operation would cause reactivity transients and possibly shut down the plant,and during cold shutdowns would delay startup. These valves shall be exercise tested during each refueling outage. SI-100 These valves serve to prevent back-flow from high pressure 113 headers to main safety injection headers. .They cannot be fully exercise tested during operation, quarterly or during cold shut-downs, since to do so would require safety injection to the reactor coolant system. Partial-stroking, quarterly,' i.s.possi-ble since these pumps can be placed~ in.a mhiimum recirculation mode of operation. l SI-102 These valves function to prevent back-flowL to high pressure 108 injection pumps and containment spray pumps. They cannot be 115 tested during operation quarterly or at cold shutdowns because 135 doing so would disrupt the safeguard system alignment, and 143 safety injection into the containment or the ,roactor. system
- O 149 would be required for valve testing. Partial-stroking csnnot be performed for the same reasons. Exercising shall be per-formed during each refueling outage.
SI-139 These valves function to prevent back-flow to the safety injec-140 tion and refueling water tank. Full stroke testing cannot be performed quarterly because no full flow path is available from the LPSI pump discharge. Full stroke testing cannot be per-formed at cold shutdown because utilizing a LPSI pump with suc-tion from the SIRWT during cold shutdown is a violation of the shutdown cooling procedure. (01-SC-1) The recirculation lines used for testing LPSI and HPSI pumps for partial-stroking lare not large enough to fully open the check valves. These valves will be partial stroke exercised every three months and' full-stroke exercised each refueling outage. SI-159, These valves function to prevent back flow to the contain-160 ment lower level and are normally closed. They are backed up by motor operated isolation valves, ilCV-383-3 and HCV-383-4, j which are normally closed, fail as is, and open only upon 4 receipt of a containment recirculation actuation signal. I No feasible means exists to perform an in-place operational test of valve SI-159 and SI-160. . In' lieu of the required testing frequency, of once per quarter, the District shall 33 R3 12/87
remove and inspect either SI-159 or SI-160 during the-first five years of the 10-year inspection' interval. During the second five years of the 10-year interval, the other valve O' will be inspected.- SI-159 was removed for inspection in 1980 and 1985. SI-160 was removed for inspection in 1981. After ; twelve years of service there is no sign of degradation or l any characteristic which would have a negative impact on i valve operability. The removal and inspection of one of these valves requires 60 manhours and requires processing of 4100 gallons'of radioactive waste water and results in 0.5 man-rem of radiation exposure. It is OPPD's position that' ! these valves have demonstrated their capability of withstand-ing their environment without deterioration for twelve years,- i so a once per five year inspection frequency.is adequate to ) ensure valve operability. These inspections shall photographically document the valve's condition and shall manually test the valve disk for free movement. This shall duplicate the' inspection done in 1980 and 1981 in response to an NRC request. (In the June 29, 1981 letter from Robert Clark of the NRC to W. C. Jones of OPPD, the attached Safety Analysis clearly indicated that upon receiving an acceptable inspection report from the Dis- [ trict on the condition of SI-160, the NRC would consider in-spection of SI-159 and SI-160 on a five-year basis adequate j for this ISI interval. In the same letter, it was noted that j this exception should be presented with other exceptions;for the ISI program). SI-175 These valves are inside the containment in the containment 176 spray headers. They cannot practically be flow tested to j verify that they open because to do so would actuate contain-ment spray. 'In lieu of the stroke testing required by ASME XI, OPPD shall do a sample disassembly' on these valves alter-nately at a rate of one per refueling outage. 1 ! SI-196 These valves function to prevent back-flow through the safety 3 199 injection pump discharge headers. These valves cannot be ! 202 stroke-tested during cold shutdowns or quarterly during oper-205 ation because to do so using the safety injection system would require introducing cold water into the reactor coolant ( system causing thermal shock and possibly a reactivity excur-sion. To do so using the chemical volume control system would disrupt charging and letdown flow to the reactor cool-ant system causing chemical and volume control to the system to be disrupted. Exercising shall be performed during each refueling outage. SI-207 These valves can only be full stroke tested by dumping the 211 safety ~ injection tanks while the head is off the reactor. 215 pressure vessel to provide a flow path for the water. Exer-219 cising will be performed during refueling outages. O 34 R3 12/87
a SI-323 This valve functions'to prevent backflow of chargi_ng flow to )
, the lower design pressure HPSI. piping when the alternate 1 charging flow path is active. ' This'. valve cannot be full (V] stroke tested quarterly during operation because HPSI pres-d sure is lower than operating pressure. This valve cannot be . 1 tested at cold shutdown because the HPSI' system is locked out 1 to prevent low temperature over pressure. - This" valve will .be I full stroke tested and-leak tested at refueling outages.
y l NOTES ) i l Note #1 These valves are check valves on instrument air accumulators at- d tached to process valves that are specified for testing elsewhere 1 in the ISI Program. The instrument air check valves will be tested -l on the same schedule as the process valve to which'it is attached. 1 Refer to the process valve for justification of test frequency. Note #2 These valves are check valves on ' instrument air. accumulators to dampers. The dampers themselves are considered to be outside the scope of ASME Section XI and are not specified for testing by the ISI Program. Note #3 .These valves are check valves on instrument air accumulators on g- bubblers that are part of the level indication / control system for g the SIRWT Tank. The ISI Program speaks only to the testing of the check valve in this system. O 35 R3 12/87
Definitions and Clarifications [
,L Justification for valve test freauency - ASME XI, IWV-3410 and IWV-3520 speci-fies valve full stroke test frequency at once every 3 months. However, if the valve function is such that it is impractical to test the valve during plant operation, the test frequency may be changed to once each cold shutdown (CS).
The NRC requires a Statement of Justification for any valve tested at CS fre-quency. These Statements of Justification are grouped by valve category under heading J in Appendix 2C of this Program Plan. Relief from valve test frecuency - Cases where it is not possible to test a valve quarterly or at cold shutdown, are not directly addressed by ASME XI. In these cases where a valve is testing at Refueling Outage (RO) frequency or some other interval longer than CS frequency, the NRC requires the utility to pre-pare a relief request that must be approved by the NRC. The relief requests for such valves are grouped by valve category under header R in Appendix 2C of this Program Plan. l l O 36 l R3 12/87
i REFERENCES i i I > 1. American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 4 July 1, 1980, Edition of Section XI through the Winter 1980 Addenda. { I
- 2. American Society of Mechanical Engineers Boiler and Pressure Vessel Code, j July 1, 1980, Edition of Section V through the Winter 1989 Addenda. '
- 3. American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 1974 Edition of Section XI through the Summer 1975 Addenda. '
4 O G l 37 R3 12/87
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