ML20091P464
| ML20091P464 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/30/1995 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20091P463 | List: |
| References | |
| PROC-950830, NUDOCS 9509010220 | |
| Download: ML20091P464 (621) | |
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- WOLF CREEK GENERATING STATION
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SECOND INTERVAL INSERVICE INSPECTION !
lO PROGRAM PLAN-NRC SUBMITTAL !
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9509010220 950830 PDR ALDCK 05000482
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
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TABLE OF CONTENTS Section Description Pane 1.0 INTROD UCTION AN D B ACKG ROUND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 BASIS FOR INSERVICE INSPECTION PROGRAM PLAN ................................... 3 2.1 Code Of Federal Regulations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.2 Augmented Examination Requ irements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3.0 INSERVICE INSPECTION PROGRAM PLAN DESCRIPTION .............................. 6 3.1 WCGS System Quality Group Classification and System Safety Classes ... ........ 6 3.2 WCGS Systems and Components Subject to Examination .............................. 6
- 3.3 WCGS Nonexempt Components . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.4 WCGS Exempt Components . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.4.1 ASM E Class 1 Components . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 m 3.4.2 ASME Class 2 Components . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
() 3.4.3 ASM E Class 3 Components . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 3.4.4 ASME Class 1, 2, and 3 Component Supports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 3.5 System Pressure Testing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1 3.6 Piping Isometrics and Component Drawings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 3.7 Requests For Relief From ASME Section XI Requirements ..........................12 APPENDICES Apnendiv Description Of Contents Iah !
A ISI Program Piping and Instrumentation Diagrams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A B ISI Program Isometrics and Component Drawings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B C ISI Program Component Summary Table . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C 1
D List Of WCGS ASME Class 1,2, and 3 Components Subject To Examination / Scheduled For Examination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .D v
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i WOLF CREEK GENERATING STATION SECOND INTERVAL. ISI PROGRAM PLAN J
1.0 INTRODUCTION AND BACKGROUND
1 INTRODUCTION i
l . This Inservice Inspection (ISI) Program Plan outlines the requirements for the examination j of ASME Class 1,2, and 3 components and component supports at Wolf Creek i Generating Station (WCGS). The Program Plan is effective from September 3,1995 through September 2,2005.
j- BACKGROUND
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- The Wolf Creek Nuclear Operating Company (WCNOC) obtained a Construction Permit j to build Wolf Creek Generating Station (WCGS) on May 31,1977. After satisfactory 4 plant construction and preoperational testing was completed, WCNOC was granted a full power operating license, NPF-42 on June 4,1985 and subsequently commenced
- commercial operation on September 3,1985.
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4 FIRST INTERVAL ISI PROGRAM Pursuant to the Code Of Federal Regulations, Title 10, Part 50, Section 55a, Codes and
- standanis, (10 CFR 50.55a), WCGS was required to meet the requirements of paragraph (g), inservice inspection requirements, of that section.
- Specifically, paragraph (g)(4)(i) calls for the inservice inspection requirements of the j initial 120 month inspection interval to comply with the requirements of the latest edition and addenda of ASME Section XI referenced in paragraph (b) of 10 CFR 50.55a on the l
- date 12 months prior the date of issuance of the operating license, subject to the limitations and modifications listed in paragraph (b) of 10 CFR 50.55a.
l The version of 10 CFR 50.55a in effect at that time referenced ASME Section XI,1980
- Edition with Addenda through the Winter 1981 Addenda (SXI 80/W81) in paragraph (b)(2). The extent of the application of SXI 80/W81 is limited by paragraph (2)(iv)(A) such that Section XI,1974 Edition with Addenda through Summer 1975 Addenda (SXI i 74/S75) must be employed for ASME Code Class 2 pressure retaining welds in Residual Heat Removal Systems, Emergency Core Cooling Systems, and Containment Heat l
Removal Systems. Optionally, per paragraph (2) (iv)(B), plants with Construction Permits docketed prior to July 1,1978, such as WCGS, may use SXI 74/S75 to examine ASME i Code Class 2 pressure retaining welds in systems other than those in paragraph (2)(iv)(A).
Based on these 10 CFR 50.55a mandatory and optional requirements, the WCGS Section
- XI ISI Program Plan for the initial ten year interval was developed by Nuclear Energy
! Services (NES) in WCRE-07, Wolf Creek Generating Station ISI Program Plan i Document.
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WOLF CREEK GENERATING STATivN SECOND INTERVAL ISI PROGRAM PLAN l
Additional, Augmented ISI requirements are included in WCRE-07 based on Updated Safety Analysis Report (USAR) commitments to NUREG 0800, Standard Review Plan 3.6.2, Regulatory Guide 1.14, and other licensing commitments per NRC Inspection &
- Enforcement Notice 80-36, " Failure Of Steam Generator Support Bolting", Code Case i N-408 for Code Class 2 piping supplemental weld examinations in the Borated Refueling Water Storage, Chemical and Volume Control and Containment Spray System, and an NRC imposed program in the High Pressure Coolant Injection System pump suction j piping, also based on Code Case N-408.
Augmented ISI of the WCGS Reactor Vessel welds mandated by 10 CFR 50.55a(g)(6)(ii)(A) were included in the first inpection interval program plan for completion in the the first inspection interval .
SECOND INTERVAL ISI PROGRAM In accordance with 10 CFR 50.55a(g) WCNOC is required to update the ISI program per i
ASME Section XI (the Code) for WCGS once every ten years or interval. The ISI program is required to comply with the latest edition and addenda of the Code j incorporated by reference in 10 CFR 50.55a one year prior to the start of the interval per
- 10 CFR 50.55a(g)(4)(ii). The next interval for ISI is currently scheduled to commence September 3,1995 and be completed September 2,2005. Accordingly, the 1989 Edition l
i of ASME Section XI is the Code that WCGS must meet for Second Interval.
!i Per Footnote 6 of 10 CFR 50.55a, ASME Code Cases that have been determined to be suitable for use in ISI Program Plans by the NRC are listed in Regulatory Guide 1.147
" Inservice Inspection Code Case Acceptability-ASME Section XI, Division 1". Footnote l ;
6 also states that the use of other Code cases (than those listed in Regulatory Guide 1.147) l ;
may be authorized by the Director of the office of Nuclear Reactor Regulation upon l request pursuant to 10 CFR 50.55a(a)(3).
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! In accordance with 10 CFR 50.55a(g)(5), when specific ASME Section XI requirements for inservice inspection are considered impractical, the licensee shall notify the NRC and
- submit information to support the determination. The submittal of this information will be
- referred to in this document as a " Relief Request" or " Request for Relief". Relief Requests for the second interval are included in Section 3.7 of this document. The relief l request format employed includes a section with the heading " Basis For Relief". Per 10
- CFR 50.55a(a)(3), the text of that section will demostrate that
- (i) The proposed alternatives would provide an acceptable level of quality and safety, or (ii) Compliance j
- with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
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. Per 10 CFR 50.55a paragraphs (a)(3) and (g)(6)(i), the Director of the Office of Nuclear Reactor Regulation will evaluate relief requests per Paragraph (g)(5) and "..may grant i such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is l
js otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility".
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d 2.0 BASIS FOR INSERVICE INSPECTION PROGRAM 2.1 Code Of Federal Regulations Requirements In accordance with the Code Of Federal Regulations, Title 10, Part 50, Section 55a, (10 CFR 50.55a), in effect on September 3,1994, this ISI Program Plan was developed in accordance with the requirements delineated in the 1989 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Subsections -
IWA, IWB, IWC, IWD, IWF, Mandatory Appendices, and Inspection Program B of IWA-2432, except as follows:
2.1.1 The ISI Program Plan for Subsection IWC was developed in accordance with Code Case N-408-2, which is approved for use in ISI Programs per Regulatory Guide 1.147, Revision 11. The alternative rules in this Code Case are essentially the same as the 1989 Edition of Section XI, except for explanatory footnotes 2 and 4, which are being employed at WCGS.
2.1.2 The ISI Program Plan for Subsection IWF, Articles IWF-1000, IWF-2000, and IWF-3000 was developed in accordance with Code Case N-491, which is approved for use in ISI Programs per Regulatory Guide 1.147, Revision O 11. Inspection Program B of Table 2410-2 in Code Case N-491 will be employed.
V 2.1.3 System pressure testing will be performed in accordance with Code Case N-498-1 (or N-498-2 upon approval for use by NRC), except for Class 2 .
containment components meeting the criteria of Code Case N-522 (see 2.1.4). l WCNOC has received approval from the NRC to employ Code Case N-498-1 until l
- it is incorporated into Regulatory Guide 1.147. WCNOC anticipates that this Case will be approved for use in ISI Programs and included in upcoming Revision 12 of Regulatory Guide 1.147 prior to the commencement of second interval pressure testing acivities at WCGS. Accordingly, a relief request per 10 CFR 50.55a is not j included in this Program Plan.
2.1.4 System pressure testing of Class 2 containment components which are attached to nonclassed piping which is outside the scope of Section XI will be performed in accordance with Code Case N-522. Relief Request 12R-13 has been developed to employ this case, see Section 3.7.
2.1.5 Integrally welded attachments will be selected and examined per Code Case N-509. WCNOC anticipates that this Code Case will be approved for use in ISI Programs and included in upcoming Revision 12 of Regdatory Guide 1.147 prior to the commencement of second interval inspection activities at WCGS. Accordingly, a i p relief request per 10 CFR 50.55a is not included in this Program Plan. l
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\ 2.1.6 Volumetric examination coverage for Class 1 and 2 welds will be in accordance with Code Case N-460 as allowed by Regulatory Guide 1.147 Revision 11, 2.1.7 Examination of Class 2 longitudinal piping welds will be performed per Code Case N-524. Relief Request I2R-12 has been developed to employ this case, see Section 3.7.
2.1.8 Visual examination of snubbers will be performed in accordance with the snubber program required by the relocated WCGS Technical Specfications in Chapter 16 of the Updated Safety Analysis Report in lieu of the requirements of IWF-5000. Relief Request 12R-15 has been developed to employ these alternative rules.
2.1.9 Testing of snubbers per IWF-5000 is not currently required to be performed per 10 CFR 50.55a. WCGS performs snubber testing in accordance with the relocated WCGS Technical Specfications in Chapter 16 of the Updated Safety Analysis Report.
2.1.10 Other system and component specific deviations from the rules of Section XI q
V are detailed in Relief Requests I2R-1 through I2R-11,12R-13,12R-14, and I2R-16 through 12R-18 in Section 3.7.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN 2.2 Augmented Examination Requirements The following augmented inservice inpection requirements, which are specified by documents other than ASME Section XI, are also included in the WCGS ISI Program Plan.
sq, k 2.2.1 WCGS USAR Sections 3.6.1, Postulated Pipine Failures In Fluid Systems jh mg Inside and Outside Containment and 3.6.2, Determination Of Break Locations and Dynamic Effects Associated With The Postulated Ruoture Of
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h(pu il Piping-These USAR Sections detail WCGS compliance with USNRC Branch Technical Position MEB 3-1, which includes requrements for j ]p licensees to perform a 100% volumetric examination of circumferential and 9
3 longitudinal pipe welds (except piping socket welds which receive a 100%
surface examination) within the "no break zone" associated with high f( $
i energy piping in containment penetration areas. The "no break zone" is an area where pipe breaks were not postulated due to the stress levels being within limits specified in USAR Section 3.6.2. The applicable welds are shown on the Main Steam (AB), Feedwater (AE), Chemical and Volume Control (BG), Steam Generator Blowdown (BM), and Auxiliary Feedwater Pump Turbine (FC) System Isometrics in Appendix B within the "No Break Zone" and included in Component Listing of Appendix D (associated with this document), with Category "USAR" and Item No. "3.6.2".
2.2.2 USNRC Regulatory Guide 1.14. Reactor Coolant Pumo Flywheel Inteerity-This Regulatory Guide includes inspection requirements for Reactor Coolant Pump flywhweels in Section 4. WCNOC has committed to these inspections per USAR Appendix 3A. The Reactor Coolant Pump flywheels included in the Reactor Coolant (BB) System Component Listing of Appendix D (associated with this document), with Category "USAR" and Item No. "RG 1.14" .
2.2.3 USNRC Reculatory Guide 1.65. Materials and Inscections for Reactor Vessel Closure Studs-This Regulatory Guide includes inspection requirements for the Reactor Vessel Closure Studs in Section 4. WCNOC has committed to these inspections per USAR Appendix 3A. These inservice inspections are satisfied by the performance of Section XI Category B-G-1 Item Number B6.30 examinations included in the Reactor Coolant (BB) System Component Listing of Appendix D (associated with this document).
2.2.4 USNRC Regulatorv Guide 1.150. Ultrasonic Testine of Reactor Vessel Welds Durine Preservice and Inservice Examinations -This Regulatory Guide includes inspection requirements for the ultrasonic examination of Reactor Vessel Welds during Preservice and Inservice Examinations.
G WCNOC has committed to these inspections per USAR Appendix 3A and Section 5.2.4. l 0078.00087.50000 Revision 0 5
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN 3.0 INSERVICE INSPECTION PROGRAM DESCRIPTION j 3.1 WCGS System Quality Group Classification and System Safety Classes
- The Qualty Group Classifcation of WCGS systems and compont.nts meet the intent of I USNRC Regulatory Guide 1.26. In addition, the criteria of ANSI N18.2-1973 was l employed in the design of WCGS to provide an added degree of assurance that the plant 4- was designed, constructed and is operated without undue risk to the health and safety of i the public. Components which form the reactor coolant pressure boundary were designed
- per Quality Group A Standards in accordance with 10 CFR 50.55a. The design standards
! specified in 10 CFR 50.55a. Regulatory Guide 1.26 and ANSI N18.2 are reflected in the i
piping classes shown on the plant P& ids as detailed in Section 3.2 below.
! 3.2 WCGS Systems and Components Subject To Examination 4
The systems and components included in the WCGS ASME Section XI Program are those designed per ASME Section III, Class 1, 2, and 3 and shown on the Piping and j
Instrumentation Diagrams (P& ids), included in Appendix A (associated with this j document). As indicated on P&ID M-120102, Symbols and Legend For System Flow and Instrumentation Diagrams, under the column heading " PIPING IDENTIFICATION", the ASME Section III, Class 1,2, and 3 piping components are those with pipe class third
)O character A, B, or C, respectively, in the line identification number. Unless otherwise noted on the P&ID, the components attached to the ASME Class 1,2, and 3 piping (e.g.
pumps, tanks, strainers, vessels, etc.) are the same ASME Class as the piping.
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! NOTE: The "U" Flag shown on Symbol and 12gends drawing M-120102, (under the
- column heading " MISCELLANEOUS (CONT.)", column) was on employed on P& ids to identify the boundaries of components subject to ultrasonic examination during the first inspection interval. The second interval boundaries (on the applicable P& ids) for ultrasonic examination idenified by the "U" Flag are being revised to reflect the requirements specified in this document.
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. 3.3 WCGS Nonexempt ASME Class Components The WCGS ASME Class 1,2, and 3 components identified on the Appendix
- A P& ids which are not exempt from the examination per Section XI, IWB- .
1220, IWC-1220, and IWD-1220 are listed in Appendix D of this document. l
- The WCGS ISI Isometrics and Component Drawings are included in l Appendix B of this document. A table which summarizes the WCGS Section l XI components (nonexempt and exempt) by Category and Item No. is included in Appendix C of this document.
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3.4 WCGS Exempt ASME Class Components and Component Supports 1 The WCGS ASME Class 1,2, and 3 components identified on the Appendix
! A P& ids which are exempt from examination are those which meet the 3 criteria of Section XI, subarticles IWB-1220, IWC-1220, and IWD-1220. l Component supports which meet the criteria of subarticle -1230 of Code )
- Case N-491 are also exempt from examination. Code Case N-491 is being l employed by WCGS in this Program Plan, as allowed by Regulatory Guide i 1.147 Revision 11. Specifically, the following Section XI exemptions were ,
- employed in the development of the WCGS ISI Program Plan. A table which I l summarizes the WCGS Section XI components (nonexempt and exempt) by
't Category and Item No. is included in Appendix C of this document.
3.4.1 ASME Class 1 Exempt Components i
A. IWB-1220. Comnonents Exempt from Examination - The I following components (or parts of components) are exempted t
from the volumetric and surface examination requirements of IWB-2500:
. (a) (IWB-1220(a) is not employed at WCGS)
- (b)(1) piping of NPS 1 and smaller, except for steam
! generator tubing; (b)(2) components and their connections in piping' of NPS 1 and smaller; (c) not employed at WCGS i
,f 'In piping is defined as having one inlet and one outlet pipe, each of which shall be l' NPS or smaller.
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- T 3.4.2 ASME Class 2 Exempt Components The following exemptions se contained in Code Case N-408-2 and
- are alternatives to those included in ASME Section XI,1989 Edition.
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i (a) The following components (or parts of components) of RHR, '
ECC, and CHR Systems (or portions of systems)' are exempt from the volumetric and surface examination requirements ofIWC-2500:
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- (1) piping NPS 4" and smaller in all systems except high pressure '
?- safety injection systems of pressurized water reactor plants.
2 f (2) vessels, pumps and valves and their connections in piping
. NPS 4" and smaller in all systems except high pressure safety injection systems of pressurized water reactor plants. ,
(3) piping NPS 1 1/2" and smaller in high pressure safety injection systems of pressurized water reactor plants.
2 (4) vessels, pumps, valves and their connections in piping NPS 1 l
- - A 1/2" and smaller in high pressure safety injection systems of pressurized water reactor plants.
(5) Vessels, piping, pumps, valves, other components, and 1-component connections of any size in statically p'ressurized, passive (i.e., no pumps) safety injection systems of f pressurized water reactor plants.
(6) Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not d
contain water during normal plant operating conditions .
i RilR, ECC, and CIIR systems are Residual IIcat Removal, Emergency Core Cooling, and Containment lleat Removal systems, respectively.
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/npiping is defined as haviag a cumulative inlet and a cumulative outlet pipe cross-sectional area neither of which exceeds the nomin' oD cross-sectional area of the designated size.
8 Statically pressurized, passive safety injection systems of pressurized water plants are typically called by such names as accumulator tank and associated system, safety injection tank and associated system, and core flood and associated system.
A ' Normal plant operating conditions include reactor startup, operation at power, hot standby, and reactor cooldown to cold shutdown conditions, but do not include test conditions.
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(b) The following components (or parts of components) other than
. RHR, ECC, and CHR Systems (or portions of systems)' are exempt
- from the volumetric and surface examination requirements of IWC-2500:
(1) piping NPS 4" and smaller.
(2) vessels, pumps and valves and their connections in piping?
NPS 4" and smaller.
(3) vessels, piping, pumps, valves and other components and component connections that operate (when the system function is required) at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200* F.
(4) Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions.'
O Q 3 RHR, ECC, and CHR systems are Residual Heat Removal, Emergency Core Cooling, and Containment Heat Removal systems, respectively.
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8/n piping is defined as having a cumulative inlet and a cumulative outlet pipe cross-sectional area i
neither of which exceeds the nominal OD cross-sectional area of the designated size.
SStatically pressurized, passive safety injection systems of pressurized water plants are typically called by such names as accumulator tank and associated system, safety injection tank and associated system, and core flood and associated system.
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' Normal plant operating conditions include reactor startup, operation at power, hot standby, and reactor
< cooldown to cold shutdown conditions, but do not include test conditions.
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h WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN C. IWC-1230 Concrete EncaceA Comoonents I Piping support members and piping support components that are
- encased in concrete shall be exempted from the examination i requirements of IWC-2500.
l 3.4.3 ASME Class 3/ Quality Group C Exempt Components
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A. IWD-1220. Items Exemnt from Examination j IWD-1220.1 - Integral attachments of supports and restraints to
- components that are NPS 4" and smaller ydthin the system i
boundaries of Examination Categories D-A, D-B, and D-C of l'
Table IWD-2500-1 shall be exempt from the visual examination VT-3, except for PWR Auxiliary Feedwater Systems.
IWD-1220.2 - Integral attachments of supports and restraints to components exceeding NPS 4 may be exempted from the visual i examination VT-3 of Table IWD-2500-1 provided:
(a) the components are located in systems (or portions of systems) whose function is not required in support of reactor ;
residual heat removal, containment heat removal, or i emergency core cooling; and I (b) the components operate at a pressure of 275 psig or less and at a temperature of 200" F or less.
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'V 3.4.4 ASME Class 1,2, and 3 Exempt Component Supports A. IWF. Suonorts Exemnt from Examination Article IWF of ASME Section XI,1989 Edition, does not contain any specific exemption criteria for component supports. Components exempt from examination will be in accordance with the criteria contained in Code Case N-491, Alternate Rules for Examination of Class 1,2,3 and MC Component Supports of Light-Water Cooled Power Plants,Section XI, Division 1, -1230:
-1230. Suncorts Exemot From Exnmination Component supports exempt from the examination requirements of IWF-2000 are those connected to components and items exempted from examination under IWB-1220, IWC-1220, IWD-1220, and IWE-1220.
In addition, portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe are also exempt from the examination requirements of -2000.
3.5 System Pressure Testing System Pressure Testing of ASME Class 1,2, and 3 components will be performed
]V per the requirements of Section XI, IWA-5000, IWB-5000, IWC-5000, and IWD-5000 as modified by Code Cases N-416-1, N-498-1 (or N-498-2 upon approval for use by NRC) and N-522. Per telephone conversations with USNRC personnel responsible for Regulatory Guide 1.147, Inservice inspection Code Case
. Acceptability, ASME Section XI, Division 1, Cases N-416-1, and N-498-1 will be included in this upcoming (Revision 12) version of this document. Case N-522 is not anticipated for inclusion in Revision 12. Accordingly, Relief Request 12R-13 has been developed in Section 3.7 of this document to allow WCGS to employ these alternative rules.
3.6 ISI lsometrics and Component Drawings The ISI isometrics and ISI Component Drawings included in Appendix B were developed to detail the ASME Code Class 1,2, and 3 components (welds, bolting,
- etc.) and component supports which are subject to examination per ASME Section XI. An index of these isometrics and component drawings is included on Inservice Inspection Drawing Index & Cross Reference, ISI-REF, Sheets 1 and 2. The identification system employed on these drawings for welds, hangers and valves is included on ISI-REF Sheets 3 and 4.
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Each nonexempt component and component support shown on the ISI '
l Isometrics and Component Drawings is listed in Appendix D. Appendix D
- is a tabulation of components and component supports sorted by Section XI Category, Item Number, system, and by isometric / component drawing .
!. number and includes ASME Section XI Category, Item Number,
! Examination Method, System, Relief Request Number, and applicable Notes.
l 3.7 Requests For Relief From ASME Section XI Requirements ,
h This subsection contains relief requests wr%n in accordance with 10CFR50.55a (a)(3) and (g)(5) for situations where specific ASME Section
- XI requirements for inservice inspection are considered impractical or pose an undue burden on the licensee. The enclosed relief requests are subject to
} change throughout the inspection interval. If examination requirements are
- determined to be impractical, or result in hardship or unusual difficulty
. without a compensating increase in the level of quality and safety, during
- the course of the interval, additional or modified relief requests will be '
i submitted in accordance with 10CFR50.55a(a)(3) and (g)(5).
! An index which summarizes each relief request is included at the beginning
!h of this section.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
) TABLE 3.7-1 V
RELIEF REQUEST INDEX -
Relief kequest Summary Page 12R-01 Alternative Rules To IWA-5242(a): Insulation j
Borated For the Purpose Of Controlling Reactivity 12R-02 Alternative Rules To IWA-5250(a): Removal Of Bolts After Detection Of Leakage at Mechanical 18 Connections 12R-03 Limited Volumetric Examination Of The Reactor Vessel Flange-To-Vessel Weld 20 12R-04 Limited Volumetric Examination Of The Reactor Vessel Closure Head Upper 22 e
Circumferential Weld 12R-05 Limited Volumetric Examination Of The Steam Generator D Tubesheet-To-Channel Head 24 Weld 12R-06 Limited Volumetric Examinadon Of The Pressurizer Nozzle-To-Head Welds 26 i
- 12R-07 Limited Volumetric Examination Of The Pressurizer Surge Nozzle-To-Bottom Head Weld 28 12R-08 Limited Volumetric Examination Of The Pressurizer Surge Nozzle Inner Radius 32
- I2R-09 Limited Volumetric Examination Of The Pressurizer Nozzle-To-Safe End Welds 35 12R-10 Alternative Rules To Table IWB-2500-1 Category B-G-1 Item No. B6.10
- Acceptance Standards For 37 Reactor Vessel Closure Head Nuts 12R-11 Alternative Rules To IWB-2420 and IWC-2420:
Sucessive Inspection Of Class 1 and 2 Vesssels 39 12R-12 Alternative Rules To Table IWC-2500-1, Categories C-F-1 and C-F-2, Examination Of 41 p)
( I.ongitudinal Welds In ASME Class 2 Piping 0078.00087.50000 Revision 0 13
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN TABLE 3.7-1
,. ' RELIEF REQUEST INDEX Relief Request Summary Page Longitudinal Welds In ASME Class 2 Piping I2R-13 Alternative Rules To Table IWC-2500-1 Category C-H: Pressure Testing Of Containment Penetration 43 Piping With Attached Nonclassed Piping I2R-14 Limited Visual, VT-3 Examination Of The Reactor Vessel Supports 46 12R-15 Alternative Rules To IWF-5000: Inservice Inspection Requirements For Snubbers 50 12R-16 Alternative Rules To IWA-2311(b) and Appendix VII: Ultrasonic Examination Personnel 52 >
Requirements I2R-17 Alternative Rules For System Pressure Testing Of Standby Diesel Generator Subsystem Components 54 12R-18 Limited Volumetric Examination Of Reactor Coolant System Branch Connection Welds 57 f
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
,'( RELIEF REQUEST 12R-01 (Page 1 of 3)
COMPONENT IDENTIFICATION Code Class: 1 and 2
References:
IWA-5242(a)
Examination Category: B-P, C-H Item Number: All Item Numbers per Catagories B-P and C-H
Description:
Alternative Rules for Insulation Removal at Bolted Connections in Systems Borated for the Purpose of Controlling Reactivity
~
CODE REOUIREMENT IWA-5242(a), states "For systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examination VT-2".
BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is reques*ed on the basis that the proposed alternative would provide an acceptable level of quality and safety. Specifically, relief is requested from the requirement to remove insulation at bolted connections for visual, VT-2
'- examination during system pressure testing for the following reasons:
- 1. Code Class 1 and 2 systems borated for the purpose of controlling reactivity are extensive and large systems extend into multiple areas and elevations. Scaffolding will be required to access many of the bolted connections. In addition, many of the bolted connections are located in difficult to access areas and in medium to high radiation areas. Insulation removal combined with scaffolding requirements will increase the financial cost, personnel exposure, and generation of radwaste associated with performanc:: of visual VT-2 examinations.
- 2. The visual VT-2 examination of Class 1 systems, primarily the Reactor Coolant System (RCS) piping and components, is performed between plant mode 3 and 2 ascending. As required by IWB-5221, the RCS is at a normal operating pressure of 2235 psig. Between modes 3 and 2 ascending, the temperature is approximately 557*F.
Performance of a visual VT-2 examination, installation ofinsulation, and disassembly of scaffolding at bolted connections under these operating conditions is a personnel safety hazard. The visual VT-2 examination is a critical path activity and normally has a duration of six to eight hours. Since the majority of Class 1 piping is inside the containment building bio-shield wall, insulation installation and disassembly of scaffolding will add to the outage duration. Critical path cost is currently estimated at
, g) $216,000 per day.
(J 0078.00087.50000 Revision 0 1
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l WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN lp V RELIEF REQUEST I2R-01 (Page 2 of 3) ,
The following WCNOC bolting examination commitments and material control programs in
) conjunction with the proposed altemate provisions provide an acceptable level of safety and
) quality for bolted connections in systems borated for the purpose of controlling reactivity.
i A. In an acceptable response to NRC Generic Letter 88-05, " Boric Acid Corrosion Of Carbon Steel Reactor Pressure Boundary Components In PWR Plants", WCGS has j established a program to inspect all boric acid leaks discovered in the containment building and to evaluate the impact of those leaks on carbon steel or low alloy steel l
components. All evidence of leaks, including boric acid crystals or residue, is l
inspected and evaluated regardless of whether the leak was discovered at power or during an outage. Based on the evaluation, appropriate corrective actions are initiated l
- to prevent reoccurrence of the leak and to repair, if necessary, any degraded materials j or components. -
! B. In addition to the nondestructive examinations required by ASME Section XI, WCGS has committed to the bolting examination requirements of NRC Bulletin 82-02, " Degradation Of Threaded Fasteners In The Reactor Coolant Pressure l
Boundary Of PWR Plants". In accordance with this bulletin, at least two '
nondestructive examination techniques (e.g., ultrasonic, liquid penetrant, magnetic
- ( particle, or visual VT-1) are performed on bolted connections of the following l components: Steam Generator primary manways, Pressurizer primary manway, Pressurizer safety valves, and a total of 22 Reactor Coolant System isolation valves that are greater than 6" NPS. As a minimum, two nondestructive examination techniques are used whenever the bolted connection of one of the subject components is disassembled for maintenance or other inspection. These additional examinations
- ensure that degradation mechanisms such as Stress Corrosion Cracking or corrosion do not go undetected in bolted connections critical to reactor safety.
3 i C. The only carbon steel and low alloy pressure boundary components at WCGS that i are in systems borated for the purpose of controlling reactivity are clad with stainless steel. Specifically, these clad components are the Reactor Vessel, Steam Generators (primary side), and Picesurizer. All other pressure boundary piping and components
- in borated systems that are within inservice inspection boundaries are constructed of i stainless steel. There is stbstantial information, such as EPRI NP-5679, attesting to I the resistance of stainless steels to boric acid corrosion. To ensure that degradation i mechanisms in stainless steels are mitigated, WCNOC maintains a program for 4
controlling materials (insulation, thread lubricant, boron, etc.) that may come in '
! contact with safety related components, including bolting. This program ensures that impurities are not present in concentrations that would promote development of Stress Corrosion Cracking in stainless steel bolted connections.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN 1
p RELIEF REQUEST 12R-01 (Page 3 of 3)
V ,
PROPOSED ALTERNATE PROVISIONS Bolted connections in systems borated for the purpose of co.. trolling reactivity shall receive a visual, VT-2 examination during the system pressure tests of IWB 5000 and IWC-5000 with the insulation installed. If evidence of leakage is detected, either by discovery of active leakage or evidence of boric acid crystals, the insulation shall be removed and the bolted connection shall be reexamined and if necessary, evaluated in accordance wth the corrective measures of subarticle IWA-5250.
PERIOD FOR WHICH RELIEF IS REOUESTED {
l Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM P1 AN .
RELIEF REQUEST 12R-02
' (Page 1 of 2) , l COMPONENT IDENTIFICATION !'
l l Code Class: 1, 2 and 3 ;
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References:
' . IWA-5250(a)(2) j Examination Category: N/A.
Item Number: . N/A l l
Alternative Rules for Corrective Measures if Leakage Occurs at I
Description:
a Bolted Connection CODE REOUIREMENT
- IWA-5250(a)(2) states "if leakage occurs at a bolted connection, the bolting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-3000.
BASIS FOR RELIEF i
Pursunnt to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed .
alternative would provide an acceptable level of quality and safety.
LO Removal of pressure retaining bolting at mechanical connections for visual, VT-3 examination and subsequent evaluation in locations where leakage has been identified is not always the most prudent course of action to determine condition of the bolting and/or the root cause of the leak.
l The Code requirem'nt to remove, examine and evaluate bolting in this situation does not l
allow the Owner to consider other factors which may indicate the condition of mechanical l
Joint bolting. WCNOC considers this requirement to be unnecessarily prescriptive and restrictive.
h
- j. Other factors which should bc considered when evaluating bolting condition when leakage has been identified at a mechanical joint include, but should not be limited to: joint bolting
]
materials, service age of joint bolting materials, location of the leakage, history of leakage at
. the joint, evidence of corrosion with the joint assembled, corrosiveness of piucess fluid, and plant / industry studies of similar bolting materials in a similar environment.
A situation frequently encountered at commercial nuclear plants such as WCGS is the complete replacement of bolting materials (studs, bolts, nuts, washers, etc) at mechanical joints during plant outages. When the associated system process piping is pressurized during plant start-up, leakage is identified at these joinu. The root cause of this leakage is most oAen due to thermal expansion of the piping and bolting materials at the join' and subsequent process fluid seepage at the joint gasket. Proper retorquing of the joint bolting, in most cases, stops the leakage. Removal of any of the joint bolting to evaluate for corrosion would i
0078.00087.50000 Revision 0 18
WOLF CREEK GENERATING STATION !
I SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-02 l (Page 2 of 2) ,
j be unwarranted in this situation due to new condition of the bolting materials. ASME Section XI Interpretation XI-1-92-01 has recognized this situation as one which the requirements of IWA-5250(a)(2) do not apply.
WCNOC proposes the following alternative methodology to the requirements of IWA-5250(a)(2) which will provide an equivalent level of quality and safety when evaluating i leakage and bolting material condition s.t Class 1,2, and 3 bolted connections.
l PROPOSED ALTERNATE EXAMINATIONS When leakage is identified at bolted connections by visual, VT-2 examination during system pressure testing, an evaluation will be performed to determine the susceptibility of the bolting to corrosion and assess the potential for failure. The following factors may be considered, but not limited to, when evaluating the leakage:
- 1) Bolting materials l
- 2) Corrosiveness of process fluid leaking l
- 3) leakage location i
- 4) Leakage history at connection O 5) Visual evidence of corrosion at connection (connection assembled)
- 6) Industry studies and history of similar bolting in similar environment
- 7) Condition and leakage history of adjacent components j
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PERIOD FOR WHICH RELIEF IS REOUESTED l l
Relief is requested for the second inspection interval, September 3,1995 through l September 2, 2005.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN l\P RELIEF REQUEST 12R-03 (Page 1 of 2) _
2 COMPONENT IDENTIFICATION Code Class: 1
References:
IWB-2500, Table IWB-2500-1 l Examination Category: B-A-
. Item Number: Bl.30
)
Description:
Limited Volumetric Examination of the Reactor Vessel Shell-to Flange Weld ,
Compenent Number: RV-101-121 Drawing Number: ISI-RBB01 Sheet 1
- CODE REQUIREMENT Table IWB-2500-1, Examination Category B-A, Item Number Bl.30 requires a 100%
volumetric examination of the Reactor Vessel Shell-to-Flange weld as detailed in Figure l
j IWB-2500-4. 1 l
l BASIS FOR RELIEF l
!(~ \
Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating
. increase in the level of quality and safety.
Due to the vessel flange taper above the subject weld, only 75% of the Code required weld volume can be examined durit:g the parallel scan portion of the volumetric examination.
l Redesign and refabrication of the Reactor Vessel would be required in order to complete the Code required volumetric examination.
l l The limited Code examination of the subject weld in conjunction with full Code volumetric examination of other similiar welds in the Reactor Vessel provides an acceptable verification of the structural integrity of this pressure retaining weld. The limitations described above
- were included in a request for relief for the first ten year interval at WCGS, and relief was subsequently granted.
PROPOSED ALTERNATE EXAMINATION None; the Code required volumetric examination will be completed to the maximum extent practical.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-03
> (Page 2 of 2) ~
i PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second inspection interval, September 3, I >5 through j September 2, 2005.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN ,
RELIEF REQUEST I2R-04 i (Page 1 of 2)
- i
!- COMPONENT IDENTIFICATION Code Class: 1
References:
IWB-2500, Table IWB-2500-1 Examination Category: B-A
- Item Number
- Bl.21'
Description:
Limited Volumetric Examination of the Reactor Vessel Closure 3 Head Upper Circumferential Weld
- Component Nu'mber: 1-RV-103-101
- Drawing Number
- ISI-RBB01 Sheet 1 :
. t CODE REQUIREMENT !
l Table IWB-2500-1, Examination Category B-A, Item Number Bl.21 requires a 100%
' volumetric examination of the Reactor Vessel Closure Head Upper Circumferential Weld as detailed in Figure IWB-2500-3. Figure IWB-2500-3 requires the subject weld plus 1/2t of the base metal to be examined.
BASIS FOR RELIEF
- Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that compliance with the j specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
I i Due to the cooling duct ring limiting the required scan path and three lifting lugs obstructing the portions of the weld examination volume, the Code required examination cannot be completed. The weld metal was 100% inspected in one direction by the 45 degree and the 60 degree angle beam, but was limited in the other direction due to the cooling ring. This resulted
, in 16.8% of the weld metal not being examined by the_45 degree angle beam and 47.3% not being examined by the 60 degree angle beam. Three lifting lugs resulted in 5.2% of the
~
required examination volume not being examined. The limitations described above were included in a request for relief for the first ten year interval at WCGS, and relief was subsequently granted.
The Reactor Vessel was designed and fabricated in accordance with the stringent quality controls of ASME Section III; subsequent volumetric and surface examinations as well as pressure testing was performed on this weld with acceptable results. The weld was examined j during Preservice Inspections (PSI) and during the first interval insevice Inspection (ISI) with no irregularities found. The probability of a flaw occuring and not being detected by the O
v examinations previously performed is small. Future indications of significant size will be found by examination of the acessible weld volume described.
0078.00087.50000 22 Revision O
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-04 (Page 2 of 2)
Based on the above information, reasonable asssurance of the continued inservice structural integrity of the subject weld is achieved without performing a complete Code examination.
PROPOSED ALTERNATE EXAMINATION None; the Code required volumetric examination will be completed to the maximum extent practical.
PERIOD FOR WHICH REI IEF IS REQUESTED Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
- RELIEF REQUEST I2R-05
- (Page 1 of 2)
COMPONENT IDENTIFICATION 1
Code Class: 1
References:
IWB-2500, Table IWB-2500-1 Examination Category: B-B Item Number: B2.40 Descriptio't: Limited Volumetric Examination of the Steam Generator j Tubesheet-to-Channel Head Weld
, Component Number: EBB 01D-SEAM-1-W Drawing Number: ISI-EBB 01D Sheet 1 CODE REQUIREMENT 1
Table IWB-2500-1, Examination Category B-B, Item Number B2.40 requires a 100%
volumetric examination of Steam Generator Tubesheet-to-Channel Head Welds as detailed in 3 Figure IWB-2500-6.
BASIS FOR RELIEF O
b Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
! Due to the four (4) support legs obstructing 22.4% of the volumetric examination with, at ;
< least, an additional 9.3% and 33.4% of the volumetric examination obstructed by the component design, while using the 45* and 60* angle beam, respectively, the Code required l examination cannot be completed. The limitations described above were included in a request j for relief for the first ten year interval at WCGS, and relief was subsequently granted.
The Steam Generator was designed and fabricated in accordance with the stringent quality controls of ASME Section III; subsequent Preservice and first interval Inservice ultrasonic scans at 0,45, and 60 degrees revealed no indications. The probability of a flaw occuring and ;
not being detected by the examinations previously performed is small. Future indications of significant size will be found by examination of'he accessible weld volume described. The limitations described above were included in a request for relief for the first ten year interval :
at WCGS, and relief was subsequently granted.
Based on the above information, reasonable asssurance of the continued inservice structural integrity of the subject weld is achieved without performing a complete Code examination.
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0078.00087.50000 24 Revision O
i WOLF CREEK GENERATING STATION
, SECOND INTERVAL ISI PROGRAM PLAN 4
O RELIEF REQUEST 12R-05 (Page 2 of 2)
PROPOSED ALTERNATE EXAMINATION
) None; the Code required volumetric examination will be completed to the maximum extent j practical.
i 1
PERIOD FOR WHICH RELIEF IS REQUESTED i'
Relief is requested for the second inspection interval, September 3,1995 through
- September 2, 2005.
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0078.00087.50000 Revision 0 25
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN l RELIEF REQUEST 12R-06 i (Page 1 of 2) ,
y COMPONENT IDENTIFICATION
~
Code Class: 1
References:
IWB-2500, Table IWB-2500-1 4 Examination Category: B-D 2
Item Number: B3.110
Description:
. Limited Volumetric Examination of the Pressurizer Nozzle-to-1 Vessel Welds
, Component Numbers: TBB03-10B-C-W and TBB03-10B-D-W Drawing Number: ISI-TBB03 Sheet 1 ,
i CODE REOUIREMENT I
Table IWB-25001, Examination Category B-D, Item Number B3.110 requires a 100% )
volumetric examination of Pressurizer Nozzle-to-Vessel Welds as detailed in Figure j IWB-2500 7.
BASIS FOR RELIEF
! l Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the Msis that comphance with the j
- spec'.ned requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Reliefis requested from the Code requirement to volumetrically examine 100% of the subject j welds due to the Pressurizer Nozzle weld taper and base metal taper near the nozzle causing transducer to lift off.
i l
! As a result of this transducer lift off, a portion of the weld required volume (WRV) receives no shear wave examination when using 45* and 60* angle beams. This was observed when
! examining Nozzle to Vessel Welds TBB03-10B-C-W and TBB03-10B-D-W. For both welds, l 15% of the WRV could not be scanned using a 45' angle beam and 11.5% of the WRV could not be scanned using a 60' angle beam.
l Strict ASME Section III quality controls were used when designing, fabricating, and instalhng these welds. In addition, these welds were examined using ultrasonic equipment, ;
showing only geometrical indications. The probability of a flaw occurring only in one of i these areas not being examined is extremely small. Future indications of significant size will
- be found by the examination of the welds as they now are.
i The limitations described above were included in a request for relief for the first ten year
- interval at WCGS, and relief was subsequently granted.
LO 0078.00087.50000 Revision 0 26
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN O
v RELIEF REQUEST 12R-06 (Page 2 of 2) .
BASIS FOR RFIIEF (Cont'd) hW on the above information, reasonable asssurance of the continued inservice structural integrity of the subject welds is achieved without performing a complete Code examination.
Compliance with the applicable Code requirements can only be accomplished by redesigning and refabricating the Pressurizer. WCNOC deems this course of action a hardship without a compensating increase in the level of quality and safety, i
PROPOSED ALTERNATE EXAMINATION None; the Code required volumetric examination will be completed to the maximum extent practical.
PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGR.e1 PLAN l9 RELIEF REQUEST 12R-07 (Page 1 of 4)
COMPONENT IDENTIFICATION Code Class: 1
References:
IWB-2500, Table IWB-2500-1 Examination Category: B-D Item Number: B3.110
Description:
Limited Volumetric Examination of the Pressurizer Surge Nozele-to-Bottom Head Weld Component c4 umber: TBB03-10A-W Drawing Number: ISI-TBB03, Sheet 1 CODE REOUIREMENT ,
Table IWB-2500-1, Examination Category B-D, Item Number B3.110 requires a 100%
volumetric examination of Pressurizer Nozzle-to-Vesse! Welds as detailed in Figure :
IWB-2500-7(b).
BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating 4
increase in the level of quality and safety.
Relief is requested from the Code requirement to volumetrically examine 100% of the subject
- welds due to the Pressurizer shell configuration and the obstmetion caused by the Pressurizer heaters.
The shell configuration resulted in 35% of the weld required volume not being examined with the 0 degree or with the parallel angle beam scan (See Figure 1). In addition, the weld metal was only examined in the one direction and the adjacent base metal was not fully examined in one direction with two beam angles (92% complete with 60 degree angle beam and 88.4%
complete with 45 degree angle beam, See Figure 2).
Strict ASME Section III quality controls were used when designing, fabricating, and installing this weld. In addition, this weld was volumetrically examined (PSI as well as current ISI),
with no irregularities fomxi. The probability of a flaw occurring only in one of these areas not being examined is extremely small. Future indications of significant size will be found by the examination of the weld as it is now. The limitations described above were included in a request for relief for the first ten year interval at WCGS, and relief was subsequently granted.
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i WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
- RELIEF REQUEST 12R-07 (Page 2 of 4) ,
BASIS FOR RELIEF (Cont'd) i Based on the above information, reasonable asssurance of the continued inservice structural j integrity of the subject welds is achieved without performing .: complete the Code i examination.
4 Compliance with the applicable Code requirements can only be accomplished by redesigning and refabricating the Pressurizer. WCNOC deems this course of action a hardship without a
- , compensating increase in the level of quality and safety.
i PROPOSED ALTERNATE EXAMINATION i
j None; the Code required volumetric examination will be completed to the maximum extent practical.
PERIOD FOR WHICH RELIEF IS REOUESTED 4
! Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN ,
RELIEF REQUEST 12R-07
[ (Page 3 of 4)
FIGURE 1 I
Pressurizer Surge Nozzle s \/ %s s
'1/2c' ' weld 1/2c' ;
Pressurizer ! i f l <
Bottom Head ;
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, l I
5 D
Volume not Examined With 0 Degree or With Parallel Angle Beam 35 %
V 0078.00087.50000 Revision 0 3,0
WOLF CREEK GENERATING STATION SECOND LNTERVAL ISI PROGRAM PLAN RELEF REQUEST 12R-07 N (Page 4 of 4)
FIGURE 2 i Pressurizer 2 Surge Nozzle
- )
l M o*F*e 45 Degree I
Pressurizer i
Bottom Head li l, l. s
! l l l l l 2
l i i
,1/2t v Weld s ,1/2(
s sy an i 4
! e' .
!- ffy Volume not Examined by 45 Degree Angle Beam -- 3.6 %
?} Volume not Examined by 45 or 60 Degree Angle Beam 8%
4
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, 0078.00087.50000 Revision O 3'1 1
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
- RELIEF REQUEST 12R-08
! (Page 1 of 3)
COMPONENT IDENTIFICATION Code Class: 1
References:
IWB-2500, Table IWB-2500-1 Examination Category: B-D Item Number: B3.120
Description:
Limited Volumetric Examination of the Pressurizer Surge Nozzle
- Inside Radius Section Component Number
- TBB03-10A-IR i Drawing Number: ISI-TBB03, Sheet 1 l CODE REQUIREMENT i Table IWB-2500-1, Examination Category B-D, Item Number B3.120 requires a 100%
volumetric examination of Pressurizer Nozzle Inner Radius Section as detailed in Figure IWB-2500-7(b).
BASIS FOR RELIEF G
Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that compliance with the
- specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, i
Reliefis requested from the Code requirement to volumetrically examine 100% of the subject welds due to the interferences by the Pressurizer heater penetrations and the nozzle configuration. As a result,70% of the required weld volume cannot be inspected, i
See Figure 1 for details.
i Strict ASME Section III quality controls were used when designing, fabricating, and installing this weld. In addition, this weld was volumetrically examined (PSI as well as current ISI),
with no irregularities found. The probability of a flaw occurring only in one of these areas not being examined is small.
1 Based on the above information, reasonable asssurance of the continued inservice structural l integrity of the subject welds is achie',ed without performing a complete the Code i examination. The limitations described above were included in a request for relief for the first ten year interval at WCGS, and relief was subsequently granted.
O 0078.00087.50000 32 l Revision o
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST I2R-08 O BASIS FOR RELIEF (Cont'd)
(Page 2 of 3) ,
Compliance with the applicable Code requirements can only be accomplished by redesigning and refabricating the Pressurizer. WCNOC deems this course of action a hardship without a compensating increase in the level of quality and safety.
l PROPOSED ALTERNATE EXAMINATION j None; the Code required volumetric examination will be completed to the maximum extent practical.
1 PERIOD FOR WHICH RELIEF IS REOUESTED J
j Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
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FIGURE 1 l'
Pressurizer 3 Surge Nozzle p.
i 1/2t j A pgg .B Pressurizer C#
Bottom Head W4 7
Ei D _
J 4
\
C 1-gg '
s Volume not Examined, 360 Degrees -- 41 %
i I
<< Volume Examined, 360 Degrees 21 % l Volume Examined, 86 Degrees Only 38 % ;
(resulting from 18" gap in heater penetrations) l
, . l
., 70% of Total Exam Volume is not Examined l 4 .
NOTE: Exam Volume is the area of ABCD 1
U 0078.00087.50000 Revision 0 34 i 4
i 1
- WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN i
l RELIEF REQUEST I2R-09 ,
(Page 1 of 2)
! COMPONENT IDENTIFICATION 1
4 Code Class: 1 i
References:
IWB-2500, Table IWB-2500-1 ,
- Examination Category
- B-F 1 Item Number: B5.40 l
Description:
Limited Volumetric Examination of the Pressurizer Nozzle-to-
- Safe End Weld l Component Numbers
- TBB03-4-W, TBB03-3-A-W, TBB03-1-W, TBB03-3-B-W, TBB03-2-W, TBB03-3-C-W Drawing Number: ISI-TBB03, Sheet 1 1
j CODE REQUIREMENT ;
f Table IWB-2500-1, Examination Category B-F, item Number B5.40 requires a 100% :
volumetric examination of Pressurizer Nozzle-to-Safe End Welds as detailed in Figure j l '
j IWB-2500 8.
! BASIS FOR RELIEF 4
A lO Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
l l
Reliefis requested from me Code requirement to volumetrically examine 100% of the subject i welds due to surface undulations which restrict search unit movement and due to the metal l structure of inconel buttering which inhibits ultrasonic shear wave transmission. The
! approximate loss of volumetric examination coverage is as follows:
WEIE WELD DESCRIPTION PERCENT NOT EXAMINED NUMBER l TBB03-4-W Relief Nozzle-to-Safe End 20% - 60* axial scan /45% - 45* axial scan TBB03-3-A-W Safety Nozzle-to-Safe Eod 50% - 60' axial scan /35% - 45' axial scan TBB03-1-W Surge Nozzle-to-Safe End 15% - 60* axial scan /40% - 45' axial scan TBB03-3-B-W Safety Nozzle-to-Safe End 55% - 60* axial scan /40% - 45* axial scan TBB03-2-W Spray Nozzle-to-Safe End 10% - 60' axial scan /40% - 45* axial scan TBB03-3-C-W Safety Nozzle-to-Safe End 20% - 60* axial scan /40% - 45' axial scan lO 9
! 0078.00087.50000
, Revision 0 35
i l
WOLF CREEK GENERATING STiTION l
.' SECOND INTERVAL ISI PROGRAM PLAN
, i RELIEF REQUEST 12R-09
\ (' - (Page 2 of 2) ,
BASIS FOR RFIJEF (Cont'd) !
'the data presented in the previous table was obtained during Interval 1 examinations; i however, WCNOC anticipates that use of improved examination techniques and equipment j may capture more of the required weld volume but still not attain the 90% coverage as
- j. allowed by Code Case N-460. The limitations described above were included in a request for
- j. . relief for the first ten year interval at WCGS, and relief was subsequently granted. ;
Strict ASME Section III quality controls were used when designing, fabricating, and
- installing this weld. In addition, this weld was volumetrically examined (PSI as well as current ISI), with no irregularities found. The probability of a flaw occurring only in one of l
these areas not being examined is extremely small. Future indications of significant size will i be found by the examination of the weld as it is now.
hwi on the above information, reasonable asssurance of the continued inservice structural integrity of the subject welds is achieved without performing a complete the Code j examination. ,
l-l Compliance with the applicable Code requirements can only be accomplished by redesigning '
i and refabricating the Pressurizer. WCNOC deems this course of action a hardship without a l
s compensating increase in the level of quality and safety.
- PROPOSED ALTERNATE EXAMINATION None; the Code required volumetric examination will be completed to the maximum extent
- practical.
PERIOD FOR WHICH RELIEF IS REOUESTED l Reliefis requested for the second inspection interval, September 3,1995 through September 2, 2005.
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j 0078.00087.50000 j Revision 0 36
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
[ RELIEF REQUEST I2R-10 (Page 1 of 2)
COMPONENT IDENTIFICATION Code Class: 1
Reference:
IWB-2500, Table IWB-2500-1 Examination Cat.: gory: B-G-1 Item Numbn: B6.10 DescriMion: Use of Alternative Examination Requirements, Examination Method, and Acceptance Standard for Reactor Vessel Closure Head Nuts
- Component Numbers: CH-NUT-01 to CH-NUT-54 Drawing Number: ISI-RDB01 Sheet 1 CODE REOUIREMENT IWB-2500 states that components shall be examined and tested as specified in Table IWB-2500-1. ,
Table IWB-2500-1 requires a surface examination to be performed on reactor vessel closure head nuts.
BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety.
Table IWB-2500-1 of the 1989 Edition of ASME Section XI requires a surface examination to
, be performed on the reactor vessel closure head nuts. However, Table IWB-2500-1 does not provide the corresponding " Examination Requirements / Figure Number" and " Acceptance Standard". These provisions were still in the course of preparation.
The 1989 Edition of ASME Section XI, Category B-G-1, employs a VT-1 visual examination for nuts associated with Heat Exchangers, Piping, Pumps, and Valves (Item Numbers B6.140, B6.170, B6.200, and B6.230, respectively). These Category B-G-1 requirements also provide an Acceptance Standard, IWB-3517, for the VT-1 examinations. Accordingly, these rules are deemed by WCGS as an acceptable and complete set of rules to assure the integrity of reactor vessel closure nuts.
Based on the above, WCNOC requests relief from the requirements specified in Table IWB-2500-1 of the 1989 Edition of ASME Section XI for reactor vessel closure head nuts, p.
0078.00087.50000 37 Revision 0
l WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN P RELIEF REQUEST 12R-10 (Page 1 of 2) ,
PROPOSED ALTERNATE PROVISIONS As an alternate examination, WCGS will perform a VT-1 visual examination of the surface of all reactor closure head nuts, utilizing the mptance criteria of IWB-3517, as delineated !
in the 1989 Edition of ASME Section XI. !
l PERIOD FOR WHICH RELIEF IS REOUFSTED Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
9
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0078.00087.50000 Revision 0 38
~ _ _ __ ._. . _ __ ._ _ _ _ . . _ . _ _ __ _. . . _ . . _ _ _ . _ _ - ._
1 WOLF CREEK GENERATING STATION '
SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-11 l (Page 1 of 2) - .
i COMPONENT IDENTIFICATION 1, 2 Code Class:
Reference:
IWB-2420, IWC-2420 Examination Category Various
. Item No.: Various
Description:
Successive Examinations of Class 1 and 2 Vessels f.
CODE REOUIREMENTS IWB-2420 Succ*uive Insocctions
.(a) The sequence of component examinations established during the first inspection interval shall be repeated during each successive inspection interval, to the extent
- practical.
i '(b) If flaw indications or relevant conditions are evaluated in accordance with IWB-l 3132.4 or IWB-3142.4, respectively, and the component qualifies as acceptable for continued service, the areas containing such flaw indications or relevant conditions
! shall be re-examined during the next three inspection periods listed in the schedules of the inspection programs of IWB-2410.
1 (c) If the re-examinations required by (b) above reveal that the flaw indications remain i essentially unchanged for three successive inspection periods, the component
' examination schedule may revert to the original schedule of successive inspections.
(d) For steam generator tubing, the successive examinations shall be governed by the
- plant Technical Specification.
i IWC-2420 Successive Insoections ~
1, (a) 'Ihe sequence of component examinations established during the first inspection i interval shall be repeated during each successive inspection interval, to the extent practical.
J (b) If component examination results require evaluation of flaw indications in accordance with IWC-3000, and the component qualifies as conditionally acceptable for continued i
service, the areas containing such flaw indications shall be re-examined during the next inspection period listed in the schedules of the inspection programs of IWC-2411 and IWC-2412.
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1 l WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN 4
O RELIEF REQUEST 12R-11 (Page 1 of 2) -
(c) If the re-examinations required by (b) above reveal that the flaw indications remain j essentially unchanged for the next period, the component examination schedule may revert to the original schedule of successivo inspections.
t BASIS mR RELIEF l Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed l
alternative would provide an acceptable level of quality and safety. .
Industry experience has shown that most vessel flaws located during inservice inspection '
!. volumetric examinations are not planar or cracklike; they are embedded volumetric anomalies j resulting from material manufacture or component fabrication, e.g., laminations, mid-plate segregate, slag, or side-wall lack of fusion. Similarly, most of those flaws are located at j mid-wall or a neutral zone with regard to stresses. Analysis in all cases show those flaws to
- be non-propagating or benign for growth considerations. The industry ultrasonic examination capability for flaw identification is available and can be readily demonstrated. The cost to
- perform out-of-interval or unscheduled examinations on benign embedded fabrication flaws are extensive and have no value added benefit with regard to safety.
4 a
' PROPOSED ALTERNATE PROVISIONS '
l As an al2rnate to IWB-2420 and IWC-2420, WCGS Station will not perform successive examinations per IWB-2420 or IWC-2420 on vessel flaws which are determined to originate j from material manufacture or fabrication subject to the following limitations:
a) The flaw is characterized as subsurface in accordance with IWA-3000; l
) b) The NDE technique and evaluation which identified the flaw as originating j from material manufacture or fabrication is documented in the flaw 4 evaluation report; and 1
l c) The flaw is acceptable for continued service in accordance with IWB-j 3132.4,or IWC-3122.4, and demonstrated to have acceptable growth until i the next scheduled inspection or the end of service lifetime nf the component.
- PERIOD mR WHICH RELIEF IS REOUESTED Relief is requested for the second inspection interval, September 3,1995 th'.ough r
{ September 2, 2005.
- O 0078.00087.50000 Revision 0 40
-.,,n., - - - _ . , , , ,n
WOLF CREEK GENERATING STATION
, SECOND INTERVAL ISI PROGRAM PLAN f RELIEF REQUEST 12R-I2 (Page 1 of 2) .
l i
4 COMPONENT IDENTIFICATION Code Classes: 2
References:
Table IWC-2500-1 l Examination Categories: C-F-1, C-F-2
- Item Numbers
- C5.11, C5.12, C5.22, C5.42, C5.52, C5.62, and C5.82
Description:
Alternate Examination Requirements for Longitudinal Welds in Class 2 Piping
! Component Numbers: All Class 2 Longitudinal Piping Welds Subject to Surface or 1- Volumetric Examination CODE REQUIREMENTS
' Table IWC-2500-1 requires the performance of surface and volumetric examination on Item l
, Nos. C5.12, C5.22, C5.52 and C5.62, and a surface examination on Item Nos. C5.42 and '
C5.82. The examination includes a length of 2.5t at the intersecting circumferential welds
[ required to be examined by Examination Categories C-F-1 and C-F-2.
I
! BASIS FOR RELIEF LO
' Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed
- alternative would provide an acceptable level of quality and safety.
l Based on the following discussion, the performance of surface and volumetric examination on l longitudinal piping welds has a negligible compensating effect on the quality or safety of j Class 2 piping. In addition, there is little, if any, technical benefit associated with the )
performance of these examinations, and may result in a substantial man-rem exposure and cost.
i
- 1) 'Ihroughout the nuclear industry, there ha:: been no evidence of rejectable service
- induced flaws being attributed to longitudinal piping welds.
i I
- 2) During the first inservice inspection interval at the WCGS, no inservice flaws were i detected in longitudinal piping welds.
4
- 3) 'Ihere are distinct differences between the pr-cet used in the manufacturing of I longitudinal and circumferential welds which enhance the integrity of longitudinal i welds. First, longitudinal welds are typically manufactured under controlled shop conditions whereas circumferential welds are produced in the field under less ideal j conditions. Secondly, longitudinal welds usually undergo heat treatment in the shop which improves their material properties and relieves the residual stresses created by welding. Finally, shop manufacturing inspections can be performed under more l 0078.00087.50000 ,
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-12 j {d \
(Page 1 of 2) ,
i favorable conditions which further increase the confidence level of the longitudinal weld quality.
4
, 4) During field installation of piping, the ends of the longitudinal welds may be affected
- during welding of the intersecting circumferential field welds. This small area falls j within the circumferential weld inspection boundaries. Therefore, the ends of the longitudinal welds will still be subject to examination.
s
- 5) From an industry-wide standpoint, there has been no evidence of longitudinal weld i defects compromising safety at nuclear generating facilities.
i
- 6) No significant loading conditions or known material degradation mechanisms have become evident to date which specifically relate to longitudinal seam welds in nuclear
- plant piping, s
- 7) There is a significant accumulation of man-rem exposure and cost associated with the inspection of Class 2 longitudinal piping welds.
- 8) The alternative examinations proposed below provide an acceptable level of quality and safety without causing undue hardship or difficulties.
l PROPOSED ALTERNATE EXAMINATION
!. Surface and volumetric examinations shall be performed, as applicable, on the length of the
{ longitudinal weld that is normally examined during examination of the intersecting l circumferential weld (s). The volumetric examination at the intersection of circumferential i and longitudinal welds will include both transverse and parallel scans within the lerSth of the i longitudinal weld that falls within the circumferential weld examination boundary.
PERIOD FOR WHICH RELTEF IS REOUESTED i
- Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
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0078.00087.50000 Revision 0 42 i
i WOLF CREEK GENERATING STATION 1
SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-13 V (Page 1 of 3) ,
4 COMPONENT IDENTIFICATION Code Class: 2
Reference:
Table IWC-2500-1 i Examination Category: C-H
- Item Numbers: C7.30, C7.40, C7.70, and C7.80
Description:
Alternate Rules To Table IWC-2500-1, Category C-H: Pressure i Testing Of Containment Penetration Piping With Attached Nonclassed Piping Component Numbers: See Table 1 '
Drawing Numbers: See Table 1 (Referenced P& ids are included in Appendix A)
CODE REQUIREMENT i ASME Section XI, Table IWC-2500-1, Examination Category C-H, requires the performance i of a visual VT-2 examination during a system pressure test on Code Class 2 pressure i
retaining components. Note 7 of this table states, "The pressure boundary includes only l those portions of the system required to operate or support the safety system function up to j and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required."
! BASIS FOR RELIEF 1 l
Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed i l
alternative would provide an acceptable level of quality and safety. l
. 1 i ;
Specifically, WCNOC requests relief from the requirement to perform a pressure test in i accordance with ASME Section XI, Table IWC-2500-1, Examination Category C-H on the l Code Class 2 lines listed in Table 1.
i The lines listed in Table 1 are portions of non-safety related piping systems that penetrate the
, primary reactor containment. At each containment penetration, the process pipe is classified Code Class 2 and provided with isolation valves that are either locked shut during normal
- operation, capable of automatic closure, or capable of remote closure to support the containment safety function. These components perform no other safety function.
l
'Ihe primary reactor containment integrity, including all containment penetrations, is !
periodically verified by performing leakage tests in accordance with a 10 CFR 50, Appendix J. Each of the Code Class 2 lines listed in Table 1 and their associated isolation valves are tested during an Appendix J, Type A, B or C leakage test at a pressure not less than 48.1 g*
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0078.00087.50000 Revision 0 43 1
, . - . . _.--e . - . _ . __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ . _ _ _ _ _ . _ . _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-13
- (Page 2 of 3) ,
Performance of these Appendix J ieak tests verifies the integrity of the subject Code Class 2 1 lines at each respective penetration. The performance of ASME Section XI, Examination Category C-H pressure tests on these same lines will provide little, if any, additional verification of primary reactor containment integrity and are thus redundant tests.
Per the preceding information, WCNOC requests relief from the ASME Section XI requirements for pressure testing these Code Class 2 containment penetration components on the basis that Proposed Alternate Provisions provide an adequate level of quality and safety.
4 PROPOSED ALTERNATE PROVISIONS WCNOC shall perform 10 CFR 50, Appendix J leakage tests on the primary reactor I containment penetration lines listed above, and on their associated valves as required by 10 1 CFR 50, etc. WCGS Technical Specification 3/4.6.
PERIOD FOR WHICH RELIEF IS REOUESTED 1
^
Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
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iO 0078.00087.50000 Revision 0 44
WOLF CREEK GENERATING STATION 4 SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-13 (Page 3 of 3) ,
TABLE 1 i
P&ID Number Line Number (s) Penetration l M-12BB02 BB-103-HCB-1" P-62 M-12BIA1 BI.e028-HCB-3" P-25 M-12BM01 BM-053-HBB-3" P-78 M-12ECO2 EC-067-HCB-6" P-53 M-12EC02 EC-072-HCB-6" P-54 M-12ECO'2 EC-081-HCB-3" P-55 l M-12EM01 EM-071-BCB-3/4" P-92 M-12GP01 GP-003-HBB-1" P-51 M-12GP01 GP-005-HBB-1" P-51 M-12GS01 GS-025-HBB-6" P-65 M-12GW1 GT-007-HBB-36" V-160 M-12GW1 GT-004-HBB-36" V-161 M-12GW1 GT-029-HBB-18" V-161 l M-12GW1 GT-034-HBB-18" V-160 M-12GW1 GT-033-HBB-18" V-160 l V-161
! M-12GW1 GT-030-HBB-18" M-12HB01 HB-015-HCB-3" P-26 M-12HB01 HB-025-HBB-3/4" P-44 M-12HD01 HD-015-HBB-2" P-43 M-12KA01 KA-244-HCB-1 1/2" P-30 M-12KA01 KA-259-HCB-1 1/2" P-30 M-12KA02 . KA-051-HBB-4" P-63 M-12KA02 KA-261-HBB-1" P-63 M-12KA05 KA-732-HBB-1" Personnel hatch M-12KA05 KA-733-HBB-1" Personnel hatch M-12KA05 KB-001-HCB-2" P-98 M-12KC02 KC-560-HBB-4" P-67 M-12LF09 LF-842-HCB-6" P-32 M-12SJ01 SJ-003-ECB-1" P-95 M-12SJ01 SJ-002-BCB-1" P-64 o )
0078.00087.50000 Revision 0 45
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WOLF CREEK GENERATING STATION )
SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST I2R-14
' (Page 1 of 4)
COMPONENT IDENTIFICATION Code Class: 1
References:
Code Case N-491, Table -2500-1 Examination Category: F-A Item Number: F1.40 l
Description:
Limited Examination of Reactor Vessel Supports Component Numbers: RBB01-01, RBB01-02, RBB01-03, and BB01-04 CODE REOUIREMENT l
ASME Section XI, Code Case N-491, Table -2500-1 requires that 100% of Class 1 supports, j other than piping, be subject to a visual VT-3 examination once every inspection interval.
BASIS FOR RELIEF The WCGS Reactor Vessel is supported by two cold leg nozzles and two hot leg nozzles.
There is a support assembly at each of these nozzles that consists of a nozzle weld build up,
'O V
shoe plate, air cooled box, and steel support structure embedded in the primary shield wall.
Figure 1 depicts these support assemblies. As shown in the figure, only the nozzle weld build up and shoe plate are completely accessible for a visual VT-3 examination. The majority of the air cooled box and the entire steel support structure are located beneath a steel walk plate and only the top of the air cooled box is directly accessible. An additional 20 to 30 percent of the air cooled box and a very small percentage of the steel support structure would be made accessible if the steel walk plate and insulation were removed.
The Reactor Vessel supports are located in a confined space below the refueling pool ,
permanent seal ring. The area can only be accessed through four seal ring hatches. In j addition to difficult access, die radiation in the area is between 1.5 to 2.0 man-rem per hour.It is estimated that the removal and re-installation of the walk plate and insulation in this confined space, combined with the visual VT-3 examination, would result in an exposure of I I
approximately 36 man-rem. Removal of the walk plate and insulation under these conditions to increase the examination of the air cooled box by approximately 20 to 30 percent and a very l small percentage of the steel support stmeture is considered impractical without a l commensurate increase in quality or safety. Based on this, relief is requested from the visual VT-3 examination of the air cooled box and steel support structure that is obstructed by the walk plate and insulation. The limitations described above were included in a request for ;
relief for the first ten year interval at WCGS, and relief was subsequently granted. ,
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0078.00087.50000 46 Revision O .
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
/9 RELIEF REQUEST 12R-14 V (Page 2 of 4)
PROPOSED ALTERNATE EXAMINATION A limited visual VT-3 examination, with the walk plate and insulation installed, shall be performed on the accessible NF portions of the Reactor Vessel support assemblies to satisfy the requiremems of Code Case N-491, Table -2500-1, Item No. F1.40. If conditions are discovered during this limited VT-3 examination that do not meet the acceptance standards of N-491, -3400, the walk plate or insulation will, if necessary, be removed to meet the evaluation requirements of N-491, -3112.2 or -3112.3.
PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
O 4
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0078.00087.50000 47 Revision 0 -
A-- - ~ ~ ,
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
,FT RELIEF REQUEST 12R-14
() (Page 3 of 4) i FIGURE 1
< J I
f RV - . , / ;- .
RV SUPPORT AIR BOX
[ \
. - Ai
- . A
_3 -
7
,r . ..
i e : W VER INSULATION STEEL SLPPORT IN CONCRETE r
I
- D 0078.00087.50000 Revision O 48
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-14 (V~) (Page 4 of 4)
FIGURE 2
^
WALKWAY OVER . .
Mi% \ l _! = i (}- f.-
,/
e- -
RV SHOE RV SUPPORT 8
==== h AIR BOX , ,,,,, ,a
\
n b : @ k!ff b
l REACTOR Id
- 18 k32
..- 1 I narr""/
M" g
t' 'x am 1R 19' 81 m lkW f
y T SECTION A-A 1 i
i I
V) 0078.00087.50000 t Revision 0 49 I
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-15 (Page 1 of 2)
COMPONENT IDENTIFICATION Code Class: 1,2 and 3
References:
IWF-5000 Examination Category: Not Applicable Item Number: Not Applicable
Description:
Alternative Rules To IWF-5000 Inservice Inspection Requirements CODE REQUIREMENT Inservice Inspection of snubbers shall be performed as follows:
Preservice examination per IWF-5200(a) and Inservice examination per IWF-5300(a) in accordance with the first addenda to ASME/ ANSI OM-1987 Edition, Part 4, published in 1988 (OMa-1988 Part 4).
Repair and replacement of snubbers per IWF-5400 in accordance with the first addenda to ASME/ ANSI OM-1987 Edition, Part 4, published in 1988 (OMa-1988 Part 4).
BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternatives provide an acceptable level of quality and safety.
WCGS has comprehensive programs for visual examination, repair and replacement, and functional testing of all safety related snubbers. The program scope encompasses all snubbers l within Code Class 1,2, and 3 boundaries. WCGS TS 4.0.5 also includes requirements for visual examination of snubbers within Code Class 1,2 and 3 boundaries per ASME Section XI and ASME/ ANSI OMa-1988, Part 4. Because 10 CFR 50.55a does not currently address snubber testing, the snubber testing requirements of Section XI, IWF-5000 are not imposed on l WCGS per TS 4.0.5. l Because all snubbers within Class 1,2, and 3 inspection boundaries are visually examined and functionally tested in accordance with the Technical Specification required snubber inspection program, the additional requirements of ASME Section XI, IWF-5000 presents an unnecessary redundancy. Since the visual examination in both programs is rigorous, the imposition of only l one program ir necesssary to assure an acceptable level of quality and safety. j I
O I 0078.00087.50000 50 Revision 0
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN O RELIEF REQUEST 12R-15 (Page 2 of 2)
The Technical Specification required snubber inspection program and the program presented in OMa-1988, Part 4 per IWF-5200(a) and IWF-5300(a) are similar in content. Both programs include parallel criteria for visual examination, examination frequency, examination sample size, examination failure evaluation, examination corrective action and examination documentation.
It is WCNOC's position that the Technical Specification required snubber visual examinations meets the intent of the program required by OMa-1988, Part 4. No plant safety benefits will be realized by imposing both programs on the safety related snubbers at WCGS.
Based on the preceding information, WCNOC requests relief from the ASME Section XI requirements for visual examination, repair ud replacement of safety related snubbers.
4 PROPOSED ALTERNATE PROVISIONS WCGS will perform visual examinations of safety related snubbers in accordance with the Technical Specification required snubber inspection program in lieu of the requirements of ASME/ ANSI OMa-1988, Part 4. The visual examination required by the Technical O Specification snubber inspection program will include the snubber attachment to the foundation U or supporting structure up to and including the fasteners for connecting the snubbers to the pipe attachment or component attachment. Personnel performing the snubber visual examinations will be qualified to perform Visual, VT-3 examinations per IWA-2300.
WCGS will perform repairs and replacements of snubbers within Code Class 1,2 and 3 boundaries per the Technical Specification required snubber inspection program in lieu of the requirements of ASME/ ANSI OMa-1988, Part 4. Per IWF-5400, the requirements ofIWF-l 4000 and IWF-7000 will also be met for repair and replacement of Code Class 1,2 and 3 snubbers.
As required by IWF-5200(c) and IWF-5300(c) the examination of snubber integral and nonintegral attachments will be performed in accordance with Subsection IWF (as modified by the adoption of Code Case N-491). As part of the examinations required by this Program Plan, WCGS will visually examine (VT-3) the ASME Section III NF steel not included in the Technical Specification required snubber inspection program.
PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
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0078.00087.50000 51 Revision 0
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
( RELIEF REQUEST I2R-16 (Page 1 of 2)
COMPONENT IDENTIFICATION Code Classes: 1 and 2
References:
IWA-2311(b) and Appendix VII Examination Categories: B-A, B-B, B-D, B-F, B-G-1, B-J, C-A, C-B, C-D, C-F-1, C-F-2 Item Numbers: Bl.11, Bl.12, Bl.21, Bl.22, Bl.30, Bl.40, B2.11, B2.12, B2.40, B3.90, B3.100, B3.110, B3.120, B3.140, B5.10, B5.40, 4 B5.70, B6.20, B6.30, B6.40, B6.180, B9.11, B9.12, B9.31 C1.10, C1.20, C1.30, C2.21, C2.22, C4.40, C5.11, C5.12, C5.21, C5.51, C5.52
Description:
Exemption from Appendix VII Ultrasonic Examination Personnel Qualification Requirements Component Numbers: All Class 1 and 2 components requiring ultrasonic examination CODE REQUIREMENT Paragraph IWA-2311(b) specifies that the training, qualification, and certification of ultrasonic examination personnel shall also comply with the requirements of Appendix VII.
Appendix VII provides requirements for the employer's written practice, qualification of ultrasonic examiners, qualification records, and the minimum content of initial training courses for the ultrasonic examination method in addition to those required in Recommended Practice No. SNT-TC-1 A, Personnel Qualification and Certification In Nondestructive Testing.
- BASIS FOR RELIEF WCNOC requests relief from implementation of Appendix VII until the performance demonstration requirements of Appendix VIII are fully implemented. Implementation of Appendix VII prior to full implementation of Appendix VIII is considered impractical and without a compensating increase in quality or safety.
Appendix VII was first introduced in the 1988 Addenda to Section XI. This Appendix represents a dramatic change from previous Code editions and current industry practices in the requirements for qualification of ultrasonicpxamination personnel. New training programs must be developed and taught by trained instructors, employer's written practices must be completely rewritten, examination question banks must be developed, flaw specimens containing actual or simulated flaws must be acquired, and performance D. demonstrations (practical examinations) must be completed.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN l RELIEF REQUEST I2R-16 (Page 2 of 2)
Implementation of Appendix VII will require a substantial industry effort. Although work j is progressing towards compliance with Appendix VII, full implementation has not yet l been achieved. Since Appendix VII provides for use of specimens prepared for ultrasonic !
performance demonstrations per Appendix VIII, many NDE vendors are developing these l two programs concurrently in order to avoid duplicated effort. Though currently not i required, the nuclear industry anticipates that the Appendix VIII performance ,
demonstration requirements will be mandated by a backfit ruling in the Federal Register. l In anticipation of this ruling, the Performance Demonstration Initiative (PDJ ' Committee is currently leading an industry wide effort to implement Appendix VIII. The tentative completion dates for pipe weld performance demonstra; ions and reactor vessel performance demonstrations are January of 1996, and January of 1997, respectively.
The WCNOC intends to implement Appendix VII when the performance demonstrations of Appendix VIII are mandated by a backfit ruling in the Federal Register.
PROPOSED ALTERNATE PROVISIONS WCGS shall utilize ultrasonic examination personnel qualified in accordance with the
(
w requirements of IWA-2300, except for IWA-2311(b). The additional Appendix VII training, qualificatice and certification requirements referenced in IWA-2311(b) shall be i reviewed for implementation when the performance demonstrations of Appendix VIII are mandated by c . ruling in the Federal Register.
I PERIOD FOR WHICH RFI IEF IS REOUESTED Relief is requested for the second inspection interval, September 3,1995 through .
September 2, 2005. l
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0078.00087.50000 53 Revision 0 - .
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN m
) RELIEF REQUEST 12R-17
- (Page 1 of 3)
COMPONENT IDENTIFICATION ,
Code Class: 3
References:
IWD-2500, Table IWD-2500-1 Examination Category: D-B ,
Item Number: D2.10
Description:
Alternative Rules For System Pressure Testing of Standby Diesel Generator Subsystem Components Applicable Components: Code Class 3 components within the Standby Diesel 4
Generator "A" and "B" Starting Air, Jacket Cooling Water, Intake and Exhaust Air and Fuel Rack Supply Air Subsystems Drawing Numbers: P& ids M-12KJ01, M-12KJ02, M-12KJ04, M-12KJ05 (See Appendix A)
CODE REOUIREMENT Table IWD-2500-1, Category D-B requires that a system pressure test per IWD-5222 be performed each inspection period and a system hydrostatic test per IWD-5223 be performed each inspection interval on pressure retaining components. .
BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alternatives provide an acceptable level of quality and safety and pursuant to 10 CFR 50.55a(a)(3)(ii) compliance with the specified requirements would result in a hardship 1 without a compensating increase in quality and safety.
. Due to the safety related function of the Standby Diesel Generators (SDGs) at WCGS, the
, components within the Starting Air, Jacket Cooling Water, Intake and Exhaust Air and Fuel Rack Supply Air Subsystems were designed per ASME Section III, Class 3 or equivalent codes and standards based on the criteria in ANSI N18.2, which was used in the design and classification of WCGS systems and components as a supplement to Regulatory Guide 1.26 criteria. Accordingly, per Technical Specification 4.0.5 Surveillance Requirements, ASME Section XI was employed during the first interval at WCGS.
~ The applicable testing requirements for these components include those in Technical Specification Surveillance Requirements 4.8.1.1.2 and 4.0.5. The Surveillance Requirements of 4.8.1.1.2 include extensive operability testing and inspection for the Standby Diesel Generators (and associated subsystems, components, etc, at frequencies (3 between 31 days and 10 years.
V 0078.00087.50000 54 Revision 0
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i WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-17 (Page 2 of 3) l The Surveillance Requirements of 4.0.5 include inservice inspection and inservice testing !
. per ASME Section XI. System pressure testing (at operational pressure) of Code Class 3 3
components is required to be performed once per inspection period (approximately 40
- months); and system hydrostatic testing (at pressures above operational) of Code Class 3
- components is required to be performed once per inspection interval (10 years) per Table 4
IWD-2500-1 of Section XI. Code Case N-498-1, which allows system pressure testing to ,
be performed in lieu of hydrostatic testing has been authorized for use at WCGS, per a 4
~
relief request, until this Case is incorporated into Regulatory Guide 1.147. For components in subsystems such as the Intake and Exhaust Air, which are open ended,Section XI 1
allows a test which confirms adequate flow to be performed in lieu of the system ,
- hydrostutic test.
The focus of the Technical Specification Surveillance Requirements is slightly different; e 4.8.1.1.2 concentrates on component operability and 4.0.5 (inservice inspection) concentrates on component pressure boundary integrity. Because successful Standby Diesel
- Generator operability testing requires the associated subsystems such as the Starting Air, l Jacket Cooling Water, Intake and Exhaust Air, and Fuel Rack Supply Air to maintain l pressure boundary integrity, this operability testing indirectly verifies individual
- Q component integrity. For subsystems such as the Intake and Exhaust Air, adequate flow is
- .b demonstrated by successfully operating the Standby Diesel Generators during testing. In
- some cases, the repeatability of subsystem instumentation (pressure and temperature)
, recorded during testing provides supporting data for the " indirect verification of l i
component integrity". In addition, operations personnel specifically trained in the design and testing of the Standby Diesel Generators are aware of the necessity to maintain :
- pressure boundary integrity for certain components and also of the necessity to maintain !
! adequate flow characteristics for open ended components which provide intake air and
! process exhaust air. Although not a specific step in the Surveillance Procedure, visual l verification of component pressure boundary integrity and adequate flow is an understood j responsibility of the operations personnel performing Standby Diesel Generators operability testing. If evidence of leakage or inadequate flow is identified during testing, !
, written notification is forwarded to plant maintenance for corrective actions or repairs and follow-up confirmatory testing is performed.
Per Surveillance Requirement 4.8.1.1.2.g, each Standby Diesel Generator is subjected to an inspection in accordance with procedures prepared per the manufacturer's recommendation. The inspections performed per this procedure provide additional
, assurance that the components within the Starting Air, Jacket Cooling Water, Intake and 4
Exhaust Air, and Fuel Rack Supply Air subsystems demonstrate pressure boundary integrity and the ability to provide adequate flow for satisfactory Standby Diesel Generator operation.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-f 7 (Page 3 of 3)
Per the informat. ion above, WCNOC requests relief from the Section XI requirements to perform system pressure testing on the Code Class 3 Standby Diesel Generators subsystems listed above on the basis that Technical Specification Surveillance Requirements of 4.8.1.1.2 provide an acceptable level of quality and safety. The implementation of separate procedures to apply Section XI system pressure testing requirements to the components within these subsystems would result in a hardship to WCNOC in the form of financial burden, without a compensating increase in quality and safety.
PROPOSED ALTERNATE EXAMINATION None, WCNOC will continue to implement the Technical Specification Surveillance Requirements of 4.8.1.1.2.
PERIOD FOR WIIICII REI,IEF IS REOUESTED p
ul Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
,O RELIEF REQUEST I2R-18 (Page 1 of 2)
COMPONENT IDENTIFICATION
. Code Class: 1
References:
IWB-2500, Table IWB-2500-1 Examination Category: B-J Item Number: B9.31
Description:
Limited Volumetric Examination of Reactor Coolant System Branch Connection Welds Component Numbers: BB-01-S101-7, BB-01-S302-3, and BB-01-S402-3 Drawing Numbers: BB-01-01 Sheet 1, BB-01-03 Sheet 1, and BB-01-04 Sheet 1 CODE REOUIREMENT Table IWB-2500-1, Examination Category B-J, Item Number B9.31 requires a 100%
volumetric examination of Piping Branch Connection Welds as detailed in Figure IWB-2500-9.
BASIS FOR RELIEF O
V Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that compliance with i the specified requirements would result in hardship or unusual difficulty without a j compensating increase in the level of quality and safety.
Volumetric examination of these welds is limited to the pipe side only due to component geometry (pipe branch connection geometry) and metallurgical properties (centrifically cast stainless steel). Because of the coarse grain material and high attenuative nature of the materials, it is necessary to use a refracted longitudinal sound wave to achieve the best ultrasonic response. This type of wave cannot be extended to provide two beam path direction coverage.
Strict ASME Section III quality controls were used when designing, fabricating, and installing these welds. In addition, these welds were examined using ultrasonic equipment to the fullest extent possible, including examination of 100% of the volume in two beam
, path directions for reflectors tranverse to the weld seam, with no irregularities identified.
This fact, in conjunction with the surface examination results and RCS visual examinations (VT-2) following each refueling outage, provides confidence that the welds are structurally sound and that the limited exam does not compromise the health and safety of the pubhc. )
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0078.00087.50000 57 '
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN RELIEF REQUEST 12R-18 (Page 2 of 2)
PROPOSED ALTERNATE EXAMINATION None; the Code required volumetric examination will be completed to the maximum extent ,
practical.
PERIOD FOR WHICH RFI IEF IS REOUESTED i Relief is requested for the second inspection interval, September 3,1995 through September 2, 2005.
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0078.00087.50000 58 Revision 0 L
WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN APPENDIX A ISI PROGRAM PIPING AND INSTRUMENT DIAGRAMS 4
e i
E
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lO 0078-00087.50000 Revision 0 -
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WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN
- APPENDIX A TABLE OF CONTENTS ISI PROGRAM PIPING AND INSTRUMENT DIAGRAMS SYSTEM DRAWING NO.
! Symbols & Iegend . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-120101 Symbols & Iegend . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-120102 Symbols & Iegend . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-120103
' Symbols & Iegend . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-120104 Main Steam . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12 AB01 Main Steam . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12AB02 Feedwater . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12AE01
. Feedwater . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12 AE02 d
Auxiliary Feedwater .................................... M-12AL01 Reactor Coolant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BB01 Reactor Coolant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BB02 Reactor Coolant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BB03 Reactor Coolant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BB04 Chemical and Volume Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BG01 Chemical and Volume Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BG02 I Chemical and Volume Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BG03 Chemical and Volume Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BG04
, yp/ Chemical and Volume Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BG05 Reactor Makeup Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BIA1 Steam Generator Blowdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BM01 Borated Refueling Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12BN01 Fuel Pool Cooling and Clean-Up . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12EC01 Fuel Pool Cooling and Clean-Up . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12EC02 Essential Service Water .................................. M-12EF01 Essential Service Water .................................. M-12EF02 Essential Service Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-K2EF01 Essential Service Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M -K2 EF03 Component Cooling Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12EG01 Component Cooling Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M - 12 EG02
]
Component Cooling Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12EG03 Residual Heat Removal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12EI01
,' High Pressure Coolant Injection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12EM01 High Pressure Coolant Injection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12EM02 Containment Spray . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12EN01
< Accumulator Safety Injection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12EP01
- Auxiliary Feedwater Pump Tmbine . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12FC02 Miscellaneous Buildings HVAC ............................. M-12GF01 Fuel Building HVAC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12 G G02 Control Building HVAC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12GK01
, pd 0078-00087.50000 Revision 0 A-1
. WOLF CREEK GENERATING STATION SECOND INTERVAL ISI PROGRAM PLAN APPENDIX A
!'O TABLE OF CONTENTS (CONT'D)
ISI PROGRAM PIPING AND INSTRUMENT DIAGRAMS i
4 SYSTEM DRAWING NO.
i 3
Auxiliary Building HVAC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12G K03 i Auxiliary Building HVAC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12GIA1
- Auxiliary Building HVAC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12GL02 j Auxiliary Building HVAC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12GIA3 J Containment Cooling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12 G N01
! Containment Integrated Leak Rate Test . . . . . . . . . . . . . . . . . . . . . . . . . . M-12GP01 2
Containment Hydrogen Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12G S01 Containment Purge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12GT01 l Liquid Radwaste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12HB01 j Decontamination System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12 HD01 l Emergency Fuel Oil System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12JFA 1 i Compressed Air System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12KA01
! Compressed Air System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12KA02 1
Compuxsed Air System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12KA05
) Breathing Air System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M- 12KB01
{ Fire Protection System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12KC02 l' Standby Diesel Generator "A" Cooling Water . . . . . . . . . c . . . . . . . . . . . . M-12KJ01 j Standby Diesel Generator "A" Intake, Exhaust, Fuel Oil & Starting Air System . M-12KJ02 Standby Diesel Generator "A" Lube Oil . . . . . . . . . . . . . . . . . . . . . . . . . M- 12KJ03 Standby Diesel Generator "B" Cooling Water . . . . . . . . . . . . . . . . . . . . . . M-12KJ04 l Standby Diesel Generator "B" Intake, Exhaust, Fuel Oil & Starting Air . . . . . M-12KJ05 Standby Diesel Generator "B" Lube Oil . . . . . . . . . . . . . . . . . . . . . . . . . M- 12KJ06 i Auxiliary Building Floor and Equipment Drain System . . . . . . . . . . . . . . . . M-12LF03 l Reactor Building and Hot Machine Shop Floor and Equipment Drain . . . . . . . M-12LF09
- Nuclear Sampling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12SJ01 7
Nuclear Sampling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M-12SJ04 i
4 II
- O 0078-00087.50000 Revision 0 A-2
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