ML20216H976
| ML20216H976 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/16/1998 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20216H974 | List: |
| References | |
| PROC-980416, NUDOCS 9804210276 | |
| Download: ML20216H976 (250) | |
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FLORIDA POWER CORPORATION 99 CRYSTAL RIVER UNIT 3 Gb ASME SECTION XI INSERVICE INSPECTION l
INTERVAL 3 !
O,i) .
TEN YEAR 3< DE)
PROGRAM MANUAL EMCTIVE DATES: AUGUST 14 " 1998 through AUGUST 14 " 2008 Prepared By: - - -
,gg Approved By:
ANU Review-l 3884188R Zi88Mo2 !
G PDR
Crystal River Unit #3 ASME Section XI
!nservice inspection Program l74 INSERVICE INSPECTION PROGRAM MANUAL ,
REVISION HISTORY l Revision Change Reasons for Revision Date Entered Q3 Number Number Entered By
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[ % Crystal River Unit #3
(% Power ASME Section XI Inservice Inspection Program NkABLE OF CONTENTS Volume I Ten Year NDE Program (Code Compliance for IWA, IWB, RVC, IWD, DVF)
Section Page Number b') 1.0 Introduction 1 1.1 General 1 1.2 Inspection Interval 3 1 1.3 Third Interval ASME Code of Record 2 1.4 Inservice Inspection Ten Year Program Description 2 1.5 Other Programs 3 1.6 Administrative Controls 6 2.0 References 8
, , , 3.0 ASME Code Case Applicability 10 t 4.0 ASME Systems and Boundaries 12 I
5.0 ReliefRequests 17 l I
6.0 ASME Section XI Application Criteria 21 7.0 Augmented Inservice Inspection Program 33 8.0 Listing of Abbreviations 57
'.b 9.0 Listing of ASME Calibration Blocks 60 10.0 Records and Reports 63 11.0 Component & Isometric Drawings 64 Components
, , Class 1 Piping Isometric Class 1 Hanger Isometric UNDER DEVELOPMENT Class 2 Piping l Class 2 Hanger Isometric UNDER DEVELOPMENT Class 3 Hanger Isometric UNDER DEVELOPMENT i
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i Crystal River Unit #3 !
ASME Section XI 9 '*"*""" Inservice inspection Program t m j s ': TABLE OF CONTENTS l 1 l Volume I Ten Year NDE Program (Code Compliance f or IWA, IWB, IWC, IWD, IWF)
Section Page Number
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l l 1 ist of Tables Table 1 - Crystal River Unit 3 ASNE Code Class Systems 14 Table 2 - Crystal River Unit 3 Interval 3 Relief Requests 18 I
Table 3 - ASME Section XI Application Criteria Summary 36 Table 4 - Inservice Inspection Data Base Abbreviations 58 Table 5 - Crystal River Unit 3 ASNE Calibration Blocks 60 l
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}g Crystal River Unit #3 g ASME Section XI W} Power Inservice inspection Program i
1.O INTRODUCTION I (d 1.1 General j The Crystal River Unit 3 (CR- 3 ) Inservice Inspection Program is established in accordance with Title 10 Code of Federal l Regulations Part 50.55a (10CFR50.55a). This program has l l
been developed to comply with the American Society of i Mechanical Engineers (ASME)Section XI, Rules For Inservice I.gI Inspection Of Nuclear Power Plant Components and implements the requirements of CR-3's Improved Technical Specifications )
(ITS), Surveillance Requirement 5.6.2.8, Inservice Inspection Program.
I CR-3 received its Construction Permit September 25, 1968 and j was designed, fabricated and erected in accordance with USAS B31.7, 1968 draft edition, and USAS B31.1, 1967 edition.
The Nuclea; Steam Supply System (NSSS) was furnished by Babcock & i cox (B&W) and has two Reactor Coolant loops. l The Archittmt Engineer for CR-3 during construction was l Gilbert Commonwealth. The reactor vessel, steam generators t, and pressurizer were designed to meet the requirements of ASME Section III, 1965 Edition with Summer 1967 Addenda. j Florida Power Corporation's (FPC) Nuclear Engineering Organization used Nuclear Regulatory Commission (NRC)
Regulatory Guide 1.26 to determine the ASME Code l classification for Class 2 and 3 Systems, Structures, and Components.
1.2 Inspection Interval 3 The Operating License for CR-3, DPR 72, was issued on i h,) January 28, 1977 The commercial operation date for CR-3 was March 13, 1977. The first Ten-Year inspection interval I ended March 13, 1987. The second Ten-Year inspection interval was scheduled to end March 13, 1987. Due to an extended outage, the second inspection interval was extended. ASME Code Section XI, 1983 Edition with Summer 1983 Addenda, Article IWA-2400(c) states, for power units that are out of service continuously for 6 months or more,
, the inspection interval during which the outage occurred may be extended for a period equivalent to the outage. The extended outage during the second interval began September 4, 1996 and ended February 5, 1998. The end of the second inspection interval was extended from March 13, 1997 to l August 13, 1998.
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@gg Power Crystal River Unit #3 ASME Section XI Inservice Inspection Program 1.2 Inspection Interval 3 (cont)
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'." The third inspection interval for CR-3 will begin on August 14, 1998. The third inspection interval is divided into three 40 month inspection periods. The inspection periods are scheduled as follows:
1st Period: From August 14, 1998 to December 14, 2001 i
{y 2nd Period: From December 15, 2001 to April 14, 2005 '
3rd Period: From April 15, 2005 to August 14, 2008 1.3 ASME Section XI Code of Record for Interval 3 10CFR50.55a requires that inservice inspection of components and system pressure tests conducted during successive 120 month inspection intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference 12 months prior to the start of the 120 month
( . ', i inspection interval. The latest edition of the ASME Code Section XI accepted by the NRC, is the 1989 Edition with no l Addenda.
The ISI Program for ASME Class 1, 2, and 3 components for the third inspection interval has been developed using the ASME Code,Section XI, 1989 Edition; except where specific written relief from Code requirements has been requested by FPC and granted by the NRC.
1.4 Inservice Inspection Ten Year Program Description 4
4 The ISI Ten Year Program details FPC's compliance with ASME Code,Section XI 1989, Edition, Articles IWA, IWB, IWC, IWD, and IWF. This document defines the third inspection interval and period dates, Class 1, 2, and 3 systems, components and Code classification boundaries, applicable ASME Code Cases, specific Relief Requests, the required examinations for each ASME Code, Section XI examination category, the augmented inspection scope and administration of the ISI program.
The purpose of the ISI Ten Year Program is to periodically perform nondestructive examination of ASME Class 1, 2, or 3 safety related components and supports in order to identify the presence of any service related degradation.
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Florida Crystal River Unit #3 pm ASME Section XI inservice Inspection Program i
1.4 Inservice Inspection Ten Year Program Description (cont)
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The Administrative controls and Inspection Schedule described in the ISI Ten Year Program, combined with applicable FPC and approved vendor procedures, constitute the Nondestructive Examination (NDE) portion of the ISI Ten Year Program required by ITS 5.6.2.8. For convenience in implementation of commitments, the ISI Ten Year Program also contains information applicable to augmented examinations
- )'. which are performed to fulfill 10CFR50.55a Augmented l
Examination cequirements or are performed to address .
industry operating experience, but are not required to be (
examined according to the ASME Code. '
l The Ten Year ISI NDE plan is contained in an ISI computer data base. This information is retained at the plant site and is available for review upon request.
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j 1.5 Other Programs !
I 1.5.1 Inservice Testing l l
The Inservice Testing Program (IST) requirements of ASME Code, Section XI 1989 Edition, Articles IWP and INV are implemented through the CR-3 Pump and Valve Program. This l program is designed to assess the operational readiness of i ASME Class 1, 2, or 3 pumps and valves and to provide a I means for early detection of degradation in either the l mechanical or hydraulic characteristics of the components.
The Pump and Valve Program is a guidance manual which describes the classification of CR-3 pumps and valves,
([j, describes cross references of components to flow diagrams, and identifies testing required to comply with ASME Code requirements.
AI-701, Administration of the ASME Section XI Inservice Inspection and Inservice Testing Programs provides the administrative guidelines and implementing procedures for this program.
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The Pump and Valve Program is maintained separately from the ISI program and was submitted under separate cover.
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% Crystal River Unit #3 Power ASME Section XI Inservice inspection Program 1.5.2 Repair and Replacement db d The Repair and Replacement Program Plan is a guidance manual which describes the implementation process for the repair and replacement provisions of ASME Code, Section XI, Articles IWA-4000, IWB-4000, IWC-4000, IWD-4000, IWE-4000, IWL-4000, IWA-7000, IWB-7000, IWC-7000, IWD-7000, IWE-7000, IWF-7000, and IWL-7000. The Code of Record for all repairs and replacements at CR-3, with the exception of the I O, Containment Inspection Program, is the 1989 Edition of ASME l* Section XI. The Code of Record for the Containment Inspection Program, as mandated by 10CFR50.55a is the 1992 Edition of ASME Section XI with 1992 Addenda.
l AI-701, Administration of the ASME Section XI Inservice l Inspection and Inservice Testing Programs provides the l l
administrative guidelines and implementing procedures for this program.
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1.5.3 Component Supports f;
The Component Support Program Plan is a guidance manual
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l which describes the classification of CR-3 component and piping supports, types of hangers, type of inspection, and inspections required during each inspection Period.
The Code of Record for the Component and Piping Support Program is the 1989 Edition of ASME Section XI. The selection of component and piping supports is based on the l Code of Record and Code Case N-491. The extent and schedule i of examination for examination category F-A is defined in Table 3, ASME Section XI Application Criteria Summary.
1 h' AI-701, Administration of the ASME Section XI Inservice l
Inspection and Inservice Testing Programs provides the administrative guidelines and implementing procedures for this program.
1.5.4 Snubbers The Snubber Program is a guidance manual which details the snubbers included in the program by tag number, location, accessibility, and srubber manufacturer.
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Crystal River Unit #3
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ASME Section Xi Inservice Inspection Program 1.5.4 Snubbers (cont)
?c'* The examination and testing of snubbers (pin to pin only) is performed in accordance with the requirements of Subsection ISTD of the 1997 Addenda to the 1995 ASME OM Code. (See ,
Relief Request 98-001-SS)
AI-701, Administration of the ASME Section XI Inservice Inspection and Inservice Testing Programs provides the
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administrative guidelines and implementing procedures for this program.
1.5.5 Pressure Test The pressure testing program at CR-3 meets the requirements of ASME Section XI, 1989 Edition for Class 1, Class 2 and Class 3 systems as revised by Relief Request 98-001-PT which j incorporates the requirements of ASME Code Case N-498-1, Relief Request 98-002-PT which incorporates the requirements of ASME Code Case N-416-1, and by Relief Request 98-003-PT
- which incorporates the requirements of ASME Code Case N-522.
The Pressure Test Program satisfies the requirements established in ITS 5.6.2.8 and ASME Code,Section XI, Articles IWA-5000, IWB-5000, IWC-5000, and IWD-5000.
1 AI-701, Administration of the ASME Section XI Inservice l Inspection and Inservice Testing Programs provides the administrative guidelines and implementing procedures for l this program. '
C@ 1.5.6 Containment Inspection d
The Containment Inspection Program implements the requirements of the 1992 Edition of ASME Code,Section XI Articles IWE and IWL (Class MC and CC components).
AI-701, Administration of the ASME Section XI Inservice Inspection and Inservice Testing Programs provides the administrative guidelines and implementing procedures for this program.
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a g'% Crystal River Unit #3 g ,. Power ASME Section XI j V " " ' " "" Inservice inspection Program j I
1.5.7 Steam Generator Tube Surveillance l tW W l
The Once Through Steam Generator (OTSG) Tube Surveillance )
Program implements the technical and administrative requirements of ASME Section XI, 1989 Edition and ITS 3.4.12.2, 5.6.2.8, 5.6.2.10, and 5.7.2. 1 i
AI-701, Administration of the ASME Section XI Inservice Inspection and Inservice Testing Programs provides the 4 i f) administrative guidelines and implementing procedures for this program. The implementing documents which constitute l" !
l the tube surveillance program required by ITS 5.6.2.10, are l SP-305, OTSG Inservice Inspection, and The Steam Generator l
Eddy Current Inspector Guidelines.
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1 1.6 Administrative Controls The Administrative and Technical Content Owner of the ASME Code,Section XI ISI Ten Year Program is the Manager, Nuclear Engineering Programs.
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' Administrative Instruction AI-701, Administration of the ASME Section XI Inservice Inspection and Inservice Testing Programs, is the Plant Operations Quality Assurance Manual (POQAM) procedure used to provide administrative guidance for the ASME Code,Section XI programs. This procedure also describes the ASME Code,Section XI ISI Program at CR-3, delineates the functional responsibilities of personnel relative to the administration and implementation of the ASME Code, Section XI ISI Program and lists the POQAM procedures necessary to implement the program.
1 g Preparation and changes responsibility of the to ISI the Program ISI Program Manager.
are the Nuclear Engineering Procedure, NEP-301, Control of ASME Section XI Examination Program Plans, Manuals, and Reports, provides the methodology for review and comment, revision, and approval of manuals. NEP-301 also establishes treatment of the manuals as quality records.
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The ISI Ten-Year Program manual is considered a procedural manual and is maintained per NEP-115, Control of Nuclear Engineering Manuals.
Distribution of the ISI Program manual is controlled by a standardized distribution process as defined per NEP-131, Document Approval and Control.
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dP Crystal River Unit #3 ASME Section XI i
D "ower Inservice inspection Program i
! ,@ 1.5 Administrative Controls (cont)
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10CFR50. 55a (a) ( 3 ) states that alternatives to 10 CFR l 50. 55a (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level l of quality and safety, or (ii) compliance with the specified l requirements would result in hardship or unusual dif ficulty ;
without a compensating increase in the level of quality and j( ,
safety. {
4 Relief Requests to amend the inspection and testing requirements for the third inspection interval, as defined j by ASME Code,Section XI, 1989 Edition, are developed and i processed in accordance with NEP-305, Control of Relief )
Requests. Copies of the Relief Requests and the NRC Safety )
Evaluation Reports are contained within Section 5.0 of the !
ISI Program manual.
NEP-303, Retention and Control of Calibration Blocks details the design and control of ASME Code Section XI ultrasonic
(-.g calibration standards and drawings. Compliance Procedure, CP-132, Control of ISI Calibration Blocks, details the retention and maintenance of ASME calibration standards.
NEP-302, Verification of Certification for NDE Personnel, Equipment, and Consumables describes specific requirements for vendors when used to perform ASME Code,Section XI examinations.
The NDE procedures used to perform ASME Section XI examinations are prepared and reviewed in accordance with NEP-304, Control of FPC Section XI NDE Procedures. NEP-304 addresses procedures developed by FPC and those procedures v written and supplied by a vendor.
NEP-307, ANII Interface Requirements, defines the interface requirements between Nuclear Engineering Programs and the Authorized Nuclear Inservice Inspector (ANII) as required by the ASME Boiler and Pressure Vessel Code,Section XI.
Surveillance Procedure SP-215, ASME Section XI used to Nondestructive Examination, is the procedure implement the ISI NDE Plan. This procedure is not applicable to preservice inspections following repairs, replacements or modifications.
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% Crystal River Unit #3 Power ASME Section XI Inservice inspection Program 2.O REFERENCES hf?
2.1 Title 10, Code of Federal Regulations.
2.2 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, 1989 edition.
2.3 Regulatory Guide 1.14, Reactor Coolant Pump Flywheel
,,, Integrity.
2.4 Regulatory Guide 1.147, Code Case Applicability.
2.5 Regulatory Guide 1.150, Reactor Pressure Vessel Ultrasonic Inspection.
2.6 Regulatory Guide 1.26, Quality Group Classifications.
2.7 NRC Information Notice 97-46, Unisolable Crack in High Pressure Injection Piping.
2.8 B&W Document 77-1140611-00, Generic Investigation of HPI/MU Q Nozzle Component Cracking.
2.9 CR-3 Improved Technical Specifications 2.10 NEP-115, Control of Nuclear Engineering Manuals.
2.11 NEP-131, Document Approval and Control.
2.12 NEP-221, Engineering Software and Technical Information Review. '
- 2.13 NEP-301, Control of ASME Section XI Examination Program ,
IM Plans, Manuals, and Reports. l 2.14 NEP-302, Verification of Certification for NDE Personnel, j Equipment and Consumables. ;
2.15 NEP-303, Retention and Control of Calibration Blocks.
., 2.16 NEP-304, Control of EPC Section XI NDE Procedures.
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2.17 NEP-305, Control of Relief Requests. (
2.18 NEP-306, Control of Plant Modifications for PSI and ISI Requirements. I l
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Florida CUstal Rivar Unit #3 Power ASME Section XI inservice inspection Program
2.0 REFERENCES
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l 2.19 NEP-307, ANII Interface Requirements.
2.20 AI-701, Administration of the ASME Section XI Inservice l Inspection and Inservice Testing Programs. !
l 2.21 CP-132, Control of ISI Calibration Blocks.
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h 2.22 SP-215, ASME Section XI Non-Destructive Examination i
2.23 Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations 2.24 NRC Correspondence dated March 7, 1994 - TAC NO. M82173 2.25 FPC Correspondence 3F1097-37, Inspection of High !
Pressure / Makeup Line Nozzles !
l 2.26 FPC Correspondence 3F0797-03, Degradation of Control Rod
.. Drive Mechanism Nozzle and Other Vessel Closure Head j
, Penetrations.
2.27 NRC Informaulon Notice - IN 90-10, Primary water Stress Corrosion Cracking (PWSCC) of Inconel 600 i
2.28 NRC Information Notice - IN 96-11, Ingress of Demineralizer l Resins Increases Potential for Stress Corrosion Cracking of j Control Rod Drive Mechanism Penetrations )
i 2.29 Generic Letter 90-09, Alternate Requirements for Snubber Visual Inspection Intervals and Corrective Actions.
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Power ASME Section XI Inservice Inspection Program 3.0 ASME CODE CASE APPLICABILITY t fhI I
3.1 Regulatory Guide 1.147 The following listing of ASME Code Cases are to be applied to the CR-3 Third Inspection Interval in accordance with the 1989 Edition of the ASME Section XI Code. The first part of the list is composed of Code Cases that have been approved by the NRC for use as identified in NRC Regulatory Guide lh 1.147, Revision 11. The second part of the list represents ASME Code Cases l that are not yet approved for use and require requests for relief to obtain NRC approval for use l in the Third Inspection Interval. However, some Code Cases l
listed in the second part are included in the Draft Revision 12 of Regulatory Guide 1.147 When Revision 12 is approved, l
relief requests for use of those Code Cases may be withdrawn.
3.1.1 Regulatory Guide 1.147, Revision 11 Approved Code Cases
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a) N-460 Alternative Examination Coverage for Class 1 and
- Class 2 Welds.
l b) N-461 Alternative Rules for Piping Calibration Block l Thickness.
c) N-463-1 Evaluation Procedures and Acceptance Criteria for Flaws in Class 1 Ferritic Piping That Exceed the Acceptance Standards of IWB-3514.2.
d) N-491 Alternative Rules for Examination of Class 1, 2, h and 3 and MC Component Supports of Light Water Cooled Power Plants. l l
3.1.2 Not Approved for Use by NRC The following ASME Code Cases are not contained in
.3 Regulatory Guide 1.147, Revision 11 and require a Relief (i Request prior to implementation. See Section 5.0 of this manual for the applicable relief requests.
a) N-416-1 Alternative Pressure Test Requirements for Welded Repairs or Installation of Replacement Items by Welding, Class 1, 2, and 3.
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Crystal River Unit #3 ASME Section XI b Inservice inspection Program l 3.1.2 Not Approved for Use by NRC (cont) b) N-498-1 Alternative Rules for 10-Year Hydrostatic Testing for Class 1, 2, and 3 Systems.
c) N-509 Alternative Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded Attachments. I grp 1
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d) N-522 Pressure Testing of Containment Penetration Piping.
e) N-524 Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping.
f) N-533 Alternative Requirements for VT-2 Visual Examination of Class 1 Insulated Pressure-Retaining Bolted Connections.
g) N-566 Corrective Action for Leakage Identified at Bolted .
Connections. j i
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_ y . . .o. .w. .e. . .r. ASME Section XI Inservice Inspect. ion Program 4.O ASME SYSTEMS & EXAMINATION BOUNDARIES 4.1 This section defines those systems that are designated as ASME Class 1, 2, or 3 and provides justification for their inclusion or exclusion within the Third Inspection Interval ISI Ten Year Program. Several of CR-3's systems or portions of systems are excluded from system and component NDE as j allowed by Articles IWB-1200, IWC-1200, and IWD-1200.
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However these systems are not excluded from the pressure testing requirements of ASME Code,Section XI. The Code pressure testing requirements have been modified by application of ASME Code Cases N-416, N-498-1, and N-522.
l See sectior.s 3.0 and 5.0 of this manual for details. This l information is provided in Table 1, CRYSTAL RIVER UNIT 3
, ASME CODE CLASS SYSTEMS. The 1989 Edition of the ASME Code, j Section XI defines the inspection requirements for each of the ASME Code Classes within the third inspection interval, which begins August 14, 1998.
4.2 Per IWA-1400(a) of the 1989 Edition of Section XI, it is the
- & owner's responsibility to determine the appropriate Code l
, Classes for each component and to identify the system l boundaries subject to inspection. IWA-1400(a), footnote 2, l states that classification criteria are specified in l 10CFR50. This reference is to footnote 9 of 10CFR50.55a l which references Regulatory Guide 1.26 and Section 3.2.2 of i NUREG-0800.
l 4.3 The component classifications of the ASME Code (Class 1, 2, j or 3) determine the rules and requirements for inspection -
and define the Section XI examination boundaries. Because early vintage nuclear plants were designed and constructed l
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l before Section III of the ASME Boiler and Pressure Vessel Code was incorporated into 10CFR50.55a, the ASME Section XI Code classifications for ISI may differ from the original {
design classifications. Therefore, while the ASME Code l c1cssifications determine the rules for repairs and l replacements and the component inspection requirements,
! repairs and replacements are generally performed to meet the specifications of the original design code. ,
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g Crystal Rivsr Unit #3 Power ASME Section XI Inservice Inspection Program m,
4.O ASME SYSTEMS & EXAMINATION BOUNDARIES (cont) h.'[)
4.4 The 1997 Code of Federal Regulations provides criteria for the classification of Quality Group A components. In previous issues of 10CFR, this criteria was provided in section 50. 2 (v) . Regulatory Guide 1.26, Quality Group Classifications and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power
, Plants, provides criteria for the classification of Quality (f,i Group B, C, and D components. Regulatory Guide 1.26 was used for ASME Code,Section XI component classification at CR-3.
4.5 The ASME Code class 1, 2, and 3 systems required to be examined in accordance with ASME Code,Section XI, 1989 Edition, are identified on color coded isometric drawings.
These drawings are located in the section of the ISI Ten Year Program manual entitled Component & Isometric Drawings.
4.6 A review of ISI boundaries for application of the ASME Code,Section XI, was conducted by FPC to assure proper Class 1,
(,
2, and 3 boundaries prior to updating the Inservice Inspection Program to the 1989 Edition of ASME Code,Section XI Code for the Third Inspection Interval.
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[#'N g Crystal River Unit #3 ASME Section XI (b-)" Power" " " "
Inservice inspection Program e
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TABLE 1 CRYSTAL RIVER UNIT 3 ASME CODE CLASS SYSTEMS SYSTEM SYSTEM ASME INSPECTION (P&ID #) DESIGNATOR CODE REQUIREMENTS
,, CLASS l fi 'Beactor Coolant RC 1 IWB-2000 FD-302-651 IWB-5000 t
Decay Heat Removal DH 1, 2, 3 IWB-2000, 5000 FD-302-641 IWC-2000, 5000 IWD-2000, 5000 i f
Makeup and Purification MU 1, 3 IWB-2000, 5000 FD-302-661 2,
IWC-2000, 5000
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IWD-2000, 5000 Core Flooding CF 1, 2 IWB-2000, 5000 FD-302-702 IWC-5000 l CLASS 2 NDE EXEMPT
(- IWC-1222(e)
Main and Reheat Steam MS, RH 2, 3 IWC-2000, 5000 FD-302-011 IWD-2000, 5000 Feedwater EW 2, 3 IWC-2000, 5000 FD-302-081 IWD-2000, 5000 J
Emergency Feedwater EF 2, 3 IWC-2000, 5000 j FD-302-082 IWD-2000, 5000 )
Nuclear Services Closed Cycle SW 2, 3 IWC-2000, 5000 Cooling IWD-2000, 5000
/*, - FD-302-601 Y l'Y t
Reactor Building Leak Rate LR 2 NOT REQUIRED Test & Post Accident Hydrogen Reg. Guide Purge 1.26 FD-302-722 Post Accident Sampling System CA 2, 3 IWC-5000, IWD-5000 FD-302-700 NDE EXEMPT IWC-1222 (a) , (b)
IWD-1220.1 i
,Eeactor Building Spray FD-302-711 BS 2, 3 IWC-2000, 5000 IWD-2000, 5000
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Post Accident Venting System LR 2 NOT REQUIRED FD-302-723 Reg. Guide 1.26 1
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[ % Crystal River Unit #3 ASME Section XI DgPower ""*"""
Inservice Inspection Program
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TABLE 1 CRYSTAL ~ RIVER UNIT 3 ASME CODE CLASS SYSTEMS SYSTEM SYSTEM ASME INSPECTION (P&ID #) DESIGNATOR CODE REQUIREMENTS CLASS
,,. Auxillary Steam AS 3 IWD-2000, 5000
(;3 FD-302-051 Emergency Diesel Generator DF 3 IWD-5000 Fuel Oil Transfer NDE EXEMPT FD-302-281 IWD-1220.1 Emergency Diesel Generator EG 3 IWD-5000 Compressed Starting Air and NDE EXEMPT Ingine Exhaust IWD-1220.1 FD-302-282 Diesel Jacket Cooling DJ 3 IWD-5000 FD-302-283 NDE EXEMPT IWD-1220.2 Diesel Air Cooler Coolant DJ 3 IWD-5000 FD-302-284 NDE EXEMPT IWD-1220.2 Nuclear Service and Decay Heat RW 3 IWD-2000 l Seawater IWD-5000 l FD-302-611 l Spent Fuel Cooling SF 3 IWD-5000 l FD-302-621 NDE EXEMPT I IWD-1220.2 j
' Decay Heat Closed Cycle DC 3 IWD-2000 Cooling IWD-5000 FD-302-631 fr~~4; Q, h111ed Water CH 3 IWD-5000 FD-302-756 NDE EXEMPT IWD-1220.2 Fire Service Water FS 2 APPENDIX J CODE CASE N-522 FD-302-231 EXEMPT IWC-1222(a), (b) I 1
Instrument Air and Station Air IA, SA 2 APPENDIX J CODE CASE N-522 FD-302-271 NOT REQUIRED BY Reg. Guide 1.26 EXEMPT IWC-1222(a), (b)
Liquid Sampling CA 2 APPENDIX J CODE CASE N-522 FD-302-672 NDE EXEMPT IWC-1222(a), (b) 15
h, % Crystal River Unit #3 ijL'""*""*'
iPower ASME Section XI Inservice inspection Program
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cco A TABLE 1 CRYSTAL RIVER UNIT 3 ,
ASME CODE CLASS SYSTEMS l
SYSTEM SYSTEM ASME INSPECTION (P&ID #) DESIGNATOR CODE REQUIREMENTS l CLASS Nitrogen and Hydrogen NG, HY 2 APPENDIX J CODE CASE N-522 FD-302-673 NOT REQUIRED l by Reg. Guide 1.26 i EXEMPT IWC-1222(a), (b)
Liquid Waste Disposal WD 2 APPENDIX J CODE CASE N-522 '
FD-302-681 NDE EXEMPT IWC-1222(a), (b) l Gas Waste Disposal WD 2 APPENDIX J CODE CASE N-522 ,
FD-302-691 NOT REQUIRED l by Reg. Guide 1.26 1 EXEMPT IWC-1222(a), (b)
Containment Monitoring WS 2 CANNOT TEST OPEN ENDED SYSTEM i l FD-302-693 NOT REQUIRED by Reg. Guide 1.26 EXEMPT IWC-1222(a), (b)
Reactor Building Pressure BS 2 CANNOT TEST OPEN ENDED SYSTEM Sensing & Testing NOT REQUIRED I FD-302-712 by Reg. Guide 1.26 l EXEMPT IWC-1222(a), (b)
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Reactor Bldg. Fuel Handling AM 2 APPENDIX J CODE CASE N-522 and Aux. Bldg l NOT REQUIRED 1 FD-302-751 by Reg. Guide 1.26 Industrial Cooler Water CI 2 IWC-5000
, FD-302-762 NDE EXEMPT l
IWC-1222(a), (b) l Control Complex EFIC Room CH 3 IWD-5000 FD-302-765 NDE EXEMPT IWD-1220.1 Reactor Building Airlock RA 2 APPENDIX J CODE CASE N-522 FD-302-772 NOT REQUIRED by Reg. Guide 1.26 EXEMPT IWC-1222(a), (b)
Domestic Water DO 3 IWD-5000 FD-302-211 NDE EXEMPT IWD-1220.2 i
Waste Gas Samp11mg WD 3 IWD-5000 ,
FD-302-692 NDE EXEMPT )
l IWD-1210.1 j l '
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[N g Crystal River Unit #3 pgj] Power ASME Section XI inservice Inspection Program 5.0 RELIEF REQUESTS
!O 5.1 Title 10 of the Code of Federal Regulations, Article
- 50. 55a (a) (3) states that alternatives to 10 CFR 50. 55a (g) may be used, when authorized by the NRC, if (i) the proposed l alternatives would provide an acceptable level of quality l and safety, or (ii) compliance with the specified
- requirements would result in hardship or unusual difficulty j(Q without a compensating increase in the level of quality and l
safety.
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5.2 Pursuant to 10 CFR 50.55a (a) (3) , the Relief Requests shown in Table 2 of this manual shall amend the inspection and testing requirements of ASME Code,Section XI, 1989 Edition 1 and are applicable to the Third Inspection Interval. )
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5.3 Copies of the Relief Requests and the associated NRC Safety l Evaluation Reports are cc,ntained within this section of the l ISI Program Manual.
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FLORIDA POWER CORPORATION CRYSTAL' RIVER UNIT 3 INSERVICE INSPECTION RELIEF REQUEST # 98-001-11 THIRD TEN-YEAR INTERVAL REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI,1989 Edition, h I. System / Component (s) for Which Relief is Requested:
Name of Component:
Core Flood Nozzle to Safe End Welds. Florida Power Corporation examination identification numbers B1.6.1 (UT) and 81.6.2 (PT): located on the "W" axis of the Reactor Vessel, and B1.6.3 (UT) and 81.6.4 (PT);
located on the "Y" axis of the Reactor Vessel.
Function:
} .{; The Core Flood Nozzle to Safe End weld attaches the Core Flooding system
'j (CF) to the Reactor Vessel Nozzle. This system provides the reactor reflooding capability after a Loss Of Coolant Accident.
5 ASME Code Class:
/gg Code Class 1
'y3 wjg O ASME Section XI Examination Category:
^)N Category B-F, Pressure Retaining Dissirnilar Metal Welds, item Number
- f. r 85.10.
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- bw; ll. Current Code Requirement and Request for Relief:
(( The ASME B&PV Code,Section XI,1989 Edition, Table IWB-2500-1, Category B-F, yg Pressure Retaining Dissimilar Metal Welds, item B5.10, requires 100% volumetric l/ and surface examination of all reactor vessel nozzle to safe end welds > 4" during
( the inspection interval.
M j Relief is requested from performing the Code required surface examination on the
! specified welds.
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l 111. Alternate Examination:
Florida Power Corporation will perform a full volumetric examination of both Core Flood Nozzle to Safe End welds from the inside diameter using the enhanced ultrasonic technique as described in Babcock and Wilcox Owners Group (BWOG) t?'??
Topical Report BAW 2228P, Revision 1. This ultrasonic examination technique has been qualified to detect outside diameter surface cracking, t
IV. Basis for Relief:
l As an alternative to performing the surface examination on the core flood nozzles, i p' ,' FPC will perform an automated volumetric examination of the outside surface from l the inside diameter of the nozzle. BWOG -Topical Reports, BAW-2228-A and ]
BAW-2228P, Revision 1, describes a modified fracture mechanics analysis applied j to postulated outer surface, semi-elliptical circumferential reactor vessel nozzle to {
pipe weld flaws. It demonstrates that adequate margins exist between the revised I bounding allowable limit flaw size and the minimum flaw that was detected and sized during the Babcock and Wilcox Nuclear Technologies (BWNT) demonstration, i
FPC has previously reviewed both Topical Report BAW-2228 A and Topical Report I BAW-2228P, Revision 1, for applicability to Crystal River Unit 3. FPC confirmed that the input stresses under normal / upset and emergency / faulted conditions shown in BAW-2228P, Revision 1, are applicable to CR-3 and that the material is A508
{ ;, . Class 2, carbon steel.
t The proposed alternative examination provides an acceptable level of quality and safety as defined by 10CFR50.55a (a)(3)(i).
The NRC has reviewed the BWOG Topical Report, BAW-2228P, Revision 1, and j issued a Safety Evaluation Report, dated March 21, 1996. The NRC approved a '
similar relief request (Relief Request 95-010) for the second inservice inspection interval.
V. Implementation Schedule:
h The alternative exarninations of both core flood nozzles will be conducted during the reactor vessel 10 year examination scheduled near the end of the third inspection interval.
I l
FLORIDA POWER CORPORATION l CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION RELIEF REQUEST # 98-002-11 THIRD TEN YEAR INTERVAL G
REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI,1989 Edition.
I b 1. System / Component (s) for Which Relief is Requested:
Name of Component:
l Reactor Coolant Pumps RCP-1 A, RCP-18, RCP-1C, and RCP 1D. The Florida Power Corporation examination identification numbers are 85.6,01, B5.6,02, (RCP-1 A): 85.6,03, B5.6,04, (RCP-18); B5.6.05, B5.6.06, (RCP 1C);
B5.6.07, and B5.6,08 (RCP-1 D).
Function:
F The Reactor Coolant Pumps are used to circulate reactor coolant through the reactor coolant system removing heat from the reactor and transferring it the steam generators.
ASME Code Class:
Code Class 1.
ASME Section XI Examination Category:
The reactor coolant pump casing welds are designated as ASME Section XI examination Category B-L-1, Pressure Retaining Welds in Pump Casings,
(,') Item Number B12.10.
II. Current Code Requirement and Hequest for Relief:
The ASME B&PV Code,Section XI,1989 Edition Table IWB-2500-1, Category '
B-L-1, item Number 812.10, requires a volumetric examination of Class 1 pump 4-s casing welds on at least one pump in each group of pumps performing similar functions in the system, e.g., recirculating coolant pumps. I Relief is requested from conducting the volumetric examination on reactor coolant pump casing welds for the third inspection interval.
l 1 of 2 RR 98 002-11
ll1. Alternate Examinatior' Visual (VT-2) examinations will be performed during system leakage tests conducted prior to plant startup following each refueling outage. VT-3 examination 4h will be conducted on the internal surface of at least one pump if disassembled for maintenanca during the interval, as required in Category B-L-2.
A surface examination will be performed on 25% of the length of both the upper and lower pump case scroll welds on one pump (RCP-1 A) during the third inspection interval. The 25 % segment selected for inspection will be a segment that has not been previoucly inspected during the first or second inspection intervals.
h IV. Basis for Relief:
Conducting volumetric examination of reactor coolant pump casings would involve significant radiation exposure without an increase in quality or safety.
The pump casings are 316 cast stainless steel. There have been no reported instances of pump casing weld degradation in the nuclear industry.
The alternative examinations were performed during the second inspection interval and no unacceptable indications were noted.
L . .;
' A similar relief request was granted for the second inspection interval (Relief Request 90-050).
The proposed alternative examination provides an acceptable level of quality and safety as defined by 10CFR50.55a (a)(3)(i).
V. Implementation Schedule:
The alternative examination requirements will be incorporated into Florida Power i Corporation's inservice inspection program for the third inspection interval.
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2 of 2 RR 98-o0211
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION RELIEF REQUEST # 98-003-11 THIRD TEN-YEAR INTERVAL h
REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI,1989 Edition.
th 5
0 1. System / Component (s) for Which Relief is Requested:
Name of Component:
Reactor Vessel Support Skirt. Florida Power Corporation examination identification number B1.12.1. -
Function:
The Reactor Vessel Support Skirt provides structural support for the reactor vessel.
g, ASME Code Class:
Code Class 1.
ASME Section XI Examination Category:
Category F-A, Supports, item Number F1.30.
II. Current Code Requirement and Request for Relief:
th The ASME B&PV Code,Section XI,1989 Edition , Table IWF 2500-1, Category F-A, item F1.30, requires supports be examined (VT-3) each inspection interval.
Relief is requested from performing a VT-3 examination (100%) of the reactor t- vessel support skirt surface.
111. Af ternate Examination:
g [\
W VT-3 examination will be performed on 10% of the interior of the reactor vessel l support at three positions along the circumference of the support. The same segments of the support skirt, located 120* apart, that were previously examined in the first and second inspection intervals, will be examined in the third inspection interval.
1 of 2 RR 98 o03-11 '
1 IV. Basis for Relief:
Relief is requested based on the radiation conditions below the reactor vessel which (p would result in significant radiation exposure to personnel. In order to perform a 100% visual examination, significant preparatory work involving erection of temporary lighting, scaffolding, surface preparation, etc. would be required. This j work would be conducted around the entire circumference of the reactor vessel support skirt interior. Based on previous exposure levels, it is estimated that radiation dose for all personnelinvolved could exceed 30 person REM q
p Previous visual examinations performed during the first and second inspection W intervals indicated no degradation of the support skirt. The locations selected (approximately 120o apart) are the least restrictive in providing access to the support skirt weld area without creating a potential for damage to the incore guide tubes. Examinations performed at these locations will adequately reveal the condition of the reactor vessel support skirt without subjecting personnel to unnecessary radiation exposure.
The proposed alternative examination provides an acceptable level of quality and safety as defined by 10CFR50.55a (a)(3)(i).
A similar relief request was granted for the second inspection interval. (Relief
(>. Request #90-060)
,a V. Implementation Schedule:
Examination of the reactor vessel support skirt will be conducted during the third inspection interval .
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I 2 of 2 RR 98 003-11
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION RELIEF REQUEST # 98-004-1l THIRD TEN-YEAR INTERVAL REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI,1989 Edition.
- 1. System / Component (s) for Which Relief is Requested:
Name of Component:
Control Rod Drive Mechanism Housing (CRDM).
Function:
The CRDM housing provides the physical structure for the control rod drive motor and is ASME Class 1 pressure boundary component. This device is used to position the reactors control rods; regulating the amount of negative
(, reactivity within the core at any time.
ASME Code Class:
The welds contained within the Control Rod Drive housing are Code Class 1. 4 ASME Section XI Examination Category:
Category B-0, Pressure Retaining Welds in Control Rod Housings, Item '
Number B14.10.
- 11. Current Code Requirement and Request for Relief:
The ASME B&PV Code,Section XI,1989 Edition Table IWB-2500-1, Category B-0, requires welds in 10% of peripheral CRDM housings be examined (volumetric or surface) during the inspection interval, p Relief is requested from performing volumetric or surface examination on 10 % of j the peripheral CRDM housings.
1 1 of 2 RR 98 004-11
111. Alternate Examination:
A volumetric or surface examination will be conducted on six CRDM housings that are removed from the reactor vessel head for maintenance during the third inspection interval.
IV. Basis for Relief:
There are 24 peripheral Control Rod Drive Mechanisms on the CR-3 reactor vessel head. Examination of 10 % of these CRDMs, would require three CRDM housing receive either a volumetric or surface examination. Each CRDM housing contains five category B-O welds, three above the reactor vessel to CRDM mating flange and D, two below. A total of 15 welds would be examined in accordance with the current Code requirements. The proposed alternative examination of performing a volumetric or surface examination on six CRDM housing removed from the reactor vessel head would yield a total of 18 welds examined in the third inspection j interval. This is a net increase above minimum code requirements of three welds or '
20 %.
By performing the CRDM weld examination on drive assemblies removed from the l l
reactor vessel head for scheduled maintenance, the occupational exposure to J personnelis greatly reduced. A saving of approximately 12 REM would be achieved over the ten year inspection interval.
f'l ,
The proposed alternative examination provides an acceptable level of quality and .
safety as defined by 10CFR50.55a (a)(3)(i) and 10CFR50.55a (a)(3)(ii). I A similar request for relief was granted by the NRC for the second inspection interval (Relief Request 93-010).
l V. Implementation Schedule: l Six CRDM housings will be examined when removed for maintenance during the
,.g third inspection interval.
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t ,.y 2 of 2 RR 98 004-11
I FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION RELIEF REQUEST # 98-005-II THIRD TEN YEAR INTERVAL REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI,1989 Edition.
b' l. System / Component (s) for Which Relief is Requested:
A complete listing of the affected welds is contained in the Crystal River Unit 3 ASME Section XI 10-Year Inservice Inspection Program for the third inspection interval.
Name of Component:
Longitudinal piping welds specified in Table IWB-2500-1, Examination Category B-J and Table IWC-2500-1, Examination Category C-F-1 and C-F-2.
Function:
(l'.
- 3 These welds provide pressure boundary integrity in ASME Section XI Class 1 and Class 2 piping ASME Coda Class:
Class 1 and Class 2.
1 ASME Section XI Examination Category:
Examination Category B-J, Pressure Retaining Welds in Piping (Class 1); Items No.
() B9.12 and B9.22 Examination Category C-F-1, Pressure Retaining Welds in Austenitic Steel or High Alloy Piping (Class 2); Items No. C5.12, C5.22, and C5.42.
Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low Allow Steel j Piping (Class 2); Items No. C5.52, C5.62, and C5.82. 1
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j 1 of 3 RR 98-o05-1l
l 11. Current Code Requirement and Request for Relief:
The ASME B&PV Code,Section XI,1989 Edition Table IWB-2500-1, Examination Category B-J requires surface and volumetric examination for piping 2 4" and surface examination only for piping < 4"; of at least one pipe diameter length but not mo.re than 12 h_ inches of each longitudinal weld in piping intersecting circumferential piping welds required to be examined by Examination Categories B-F and B-J.
l Table IWC-2500-1, Examination Category C-F-1 and C-F-2, require surface and volumetric examination for piping 2 3/8 inch nominal wall thickness and > 4 NPS; and for piping > 1/5 inch nominal wall thickness and 2 2 NPS and $ 4 NPS. Category C-F-1 and C-F-2 also require surface examination for branch connections 2 2 NPS branch pipe size. The extent of
!A examination includes at least the length of longitudinal welds equal to 2.St, at the intersection
'd of the circumferential weld, where "t" is a measure of the pressure boundary thickness.
Relief is requested from performing the Code-required examination for longitudinal welds in Class I and 2 piping.
Ill. Alternate Examination:
The following alternative examination requirements will be performed as defined in ASME Code Case N-524: '
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a) When only a surface examination is required, examination of longitudinal piping welds is not required beyond those portions of the welds within the examination boundaries of intersecting circumferential welds.
b) When both surface and volumetric examinations are required, examination of l longitudinal piping welds is not required beyond those portions of the welds within
! the examination boundaries of intersecting circumferential welds provided the ,
following requirements are met:
l 1) Where longitudinal welds are specified and locations are known, examination requirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of longitudinal weld within the j-gd circumferential weld examination volume; j
- 2) Where longitudinal welds are specified but locations are unknown, or the existence oflongitudinal welds is uncertain, the examination requirements shall be met for both transverse and parallel flaws within the entire examination volume of intersecting circumferential welds.
(..
2 of 3 RR 98-oo5-H
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l IV. Basis for Relief: l l
FPC is requesting relief from the above stated requirements based on ASME Code Case N-524 l which has been issued by the American Society of Mechanical Engineers and has been included in the 1995 Addenda cf Section XI. Code Case N-524 defines alternative examination fD '
requirements that may be applied to surface and volumetric examination of longitudinal welds in Class 1 and Class 2 piping and provides an acceptable level of quality and safety as defined by 10CFR50.55a (a)(3)(i).
Code Case N-524 directs examination efforts at the high risk area at weld intersections. By eliminating the low risk areas of longitudinal welds from examination, the time requirements and radiation exposure of personnel are significantly reduced. The expected dose savings is estimated to be 1.6 to 2.0 man-Rem per weld with a projected outage savings of 12.8 to 16.0 I9 man-Rem based on examination of eight longitudinal welds. Compliance with the existing ASME Section XI requirements, in lieu of Code Case N-524, would result in unnecessary exposure without a compensating increase in the level of quality or safety.
Longitudinal welds are produced during pipe fabrication, as opposed to circumferential welds which are field produced. The ASME Code contains requirements for characteristics and performance of materials and components, and for examination of longitudinal piping welds during fabrication. Additionally, the ASME Code specifies the minimum chemical and physical properties of the material to ensure structural integrity of the longitudinal welds at the time of pipe fabrication.
, The preservice, and inservice examinations conducted during the first inspection interval provide assurance of longitudinal weld structural integrity for the service life of the plant to date.
Experience within the United States reveals that ASME Code longitudinal welds have not experienced degradation warranting inservice examination beyond that required to meet the circumferential weld examination requirements. To date, no significant loading conditions or material degradation mechanisms have become evident that specifically relate to longitudinal {
seam welds in nuclear power plant piping. If degradation of a longitudinal weld was to occur, i it is expected to be located at an intersection with a circumferential weld, which is inspected in !'
accordance with Code Case N-524. Therefore, the health and safety of the public will continue to be maintained while implementing the alternative examination requirements of Code Case k[.fi N-524.
A similar relief request was granted for the second inspection interval (Relief Request #
96-001-II) l V. Implementation Schedule:
4( -
The alternative examination requirements of ASME Code Case N-524 will be incorporated into Florida Power Corporation's Inservice Inspection Program for the third inspection interval .
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3 of 3 RR 98 oo5-il l
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION )
RELIEF REQUEST # 98-006-11 !
THIRD TEN YEAR INTERVAL
@ l i
REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and j Pressure Vessel Code (B&PV),Section XI,1989 Edition, f 1
- 1. System / Component (s) for Which Relief is Requested:
Name of Component: l A listing of the affected integral attachment welds is contained in the Crystal River Unit 3, ASME Section XI, Ten-Year Inservice inspection Program for the )
third inspection interval. '
Function:
Integrally Welded Attachments to piping as specified in Table IWC-2500-1,
{'j' Category C-C (ltem C3.20); and Table IWD-2500-1, Categories D-A, D-B, and D-C (Items for piping integral attachments only).
ASME Code Class:
These welds attach load bearing members to ASME Section XI Class 2 and Class 3 pressure boundary components.
ASME Section XI Examination Category:
Class 2 and Class 3 k3 Category:
Examination Category C-C, " Integral Attachments for Vessels, Piping, Pumps, and Valves" (Class 2). This Relief Request is applicable to Item No. C3.20 piping only.
Examination Category D-A, " Systems in Support of Reactor Shutdown Function" l
(Class 3): Items No. D1.20, D1.30, D1.40, D1.50, D1.60.
(
Examination Category D 8, " Systems in Support of Emergency Core Cooling, Containment Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal" (Class 3): Items No. D2.20, D2.30, D2.40, D2.50, D2.60.
1 of 4 RR 98 006-11
Examination Category D-C, " Systems in Support of Residual Heat Removal from Spent Fuel Storage Pool" (Class 3); Items No. D3.20, D3.30, D3.40, D3.50, D3.60.
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, 11. Current Code Requirement and Request for Relief:
The ASME B&PV Code,Section XI,1989 Edition requires 100% of integral attachment welds meeting the criteria defined in the following paragraphs, be examined over a Ten-Year interval.
Examination Category B-K-1, Integral " Attachments for Piping, Pumps, and
- g. Valves" (Class 1) are not required to be examined during the third or fourth
_. inspection intervals when following Inspection Program B as defined in ASME Section XI 1989 edition, article IWB-2412.
Application of ASME Code Case N-509 for Class 1 Integral Attachments, B-K-1:
is not requested as the Crystal River Unit 3 Inservice inspection Program for the '
Third Inspection Interval follows Inspection Program B.
Table IWC-2500-1, Examination Category C-C requires 100% surface ;
examination of the required areas of each welded attachment that meet the i following conditions:
gl', The attachment is on the outside surface of the pressure retaining component:
The attachmont provides component support as defined in NF-1110:
The attachment base material design thickness is 3/4 inch or greater: and The attachment weld joins the attachment either directly to the surface of I the component or to an integrally cast or forged attachment to the component. *
,,., Table IWD-2500-1, Examination Categories D-A, D-B, and D-C require that in 1,jj the case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
Relief is requested from the Code requirements for Class 2 and 3 integrally welded attachments to piping as defined in ASME Section XI, Articles IWC, and IWD of the ASME Boiler and Pressure Vessel Code,1989 Edition.
2 of 4 RR 98 00611
lli. Alternate Examination:
i The following alternative examination requirements will be implemented as defined by ASME Code Case N-509, exclusive of the selection criteria which is defined below:
ASME Code Case N-509 and Table 25001, Examination Category C-C, shall be used for Class 2 integrally welded attachments to piping as defined by Examination Category C-C of ASME Section XI, Article IWC.
ASME Code Case N 509 and Table 2500-1, Examination Category D-A, shall be used for Class 3 integrally welded attachments to piping as defined by Examination Categories D-A, D-8, and D-C of ASME Section XI, Article IWD.
(m, in addition to the requirements of ASME Code Case N-509, the extent of scheduled examination shall be a minimum of 10% of the total population (no thickness exemption) of integral attachments in non-exempt Code Class 2 and 3 systems.
IV. Basis for Relief:
FPC is requesting relief from the above stated requirements based on ASME Code Case N-509 which has been issued by the American Society of y Mechanical Engineers and has been included in the 1995 Addenda of Section XI.
At CR-3 component supports are selected for examination per ASME Code Case N 491 which was adopted by the 1990 Addenda to ASME Section XI, Subarticle IWF-2510. Application of Code Case N-509 defines alternative examination requirements that may be applied to ASME Code Class 1, 2 and 3 i integrally welded attachments. The extent of examination as stated in Note 5 l of Table 2500-1, Examination Categories B-K, C-C, and D A of Code Case '
N-509 reduces the required examinations to 10% of the integral attachments associated with component supports selected for examination under the 1990 g Addenda to Section XI, paragraph IWF-2510. 1 q:
CR-3 will schedule a minimum of 10% of the total population of integral '
attachments to piping in non-exempt Code Class 2 and 3 systems. This approach is conservative and would provide an acceptable level of quality and safety, i
Examination of some Class 2 integrally welded attachments can result in radiation exposure of 1.6 to 2.0 mrem per examination. By limiting examinations to 10% of the total population of integral attachments to piping in non-exempt Code Class 2, and 3 systems, the time requirements and the radiation exposure of personnel would be reduced. Therefore, compliance with l the existing ASME Section XI 1989 requirements would result in higher exposure without a compensating increase in the level of quality or safety.
3 of 4 RR 98 006-il
1 Industry experience in the United States has also shown that ASME Code integral attachment welds have not experienced degradation that would warrant I continued examination to the extent required by the 1989 edition of ASME Section XI. To date, no significant loading conditions or known material l';$) degradation mechanisms have become evident that specifically relate to integral attachment welds in nuclear power plant piping. Should a service induced defect be detected in these welds, ASME Code Case N-509 specifies I examination expansion criteria to ensure degradation in other attachment welds would be detected. Therefore, the health and safety of the public will continue to be maintained while implementing the alternative examination requirements of Code Case N-509. 1 A similar relief request was granted for the second inspection interval (Relief Request # 97-001-11).
I V. Implementation Schedule:
I The alternative examination requirements of ASME Code Case N-509 will be incorporated l into Florida Power Corporation's Inservice Inspection Program for ASME Section XI third inspection interval
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l FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION REllEF REQUEST # 98-007-ll THIRD TEN YEAR INTERVAL h
REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI,1989 Edition.
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- 1. System / Component (s) for Which Relief is Requested:
l
! Name of Component:
i Reactor Vessel Category B-D, Full Penetration Welds of Nozzles in Vessels; Nozzle to Vessel Welds and Nozzle inside Radius Sections.
Function:
t Reactor coolant system pressure boundary.
g.,,
ASME Code Class:
Code Class 1.
! ASME Section XI Examination Category:
These welds are Examination Category B D, Full Penetration Welds of Nozzles in Vessels, item Numbers B3.90 and B3.100.
II. Current Code Requirement and Request for Relief:
{p The ASME B&PV Code,1989 Edition,Section XI, Table IWB-2500-1 Examination Category B-D, requires that volumetric examinations of reactor vessel nozzle-to-vessel welds and their inside radius sections be performed once each Ten-Year inspection interval. Note (2) of Table IWB 2500-1, Examination Category ;
B-D states that at least 25 percent, but not more than 50 percent (credited), of the j nozzles shall be examined by the end of the first inspection period and the l remainder by the end of the last inspection period, of the respective intervals. l l
O Relief is requested from the requirement to perform a volumetric examination .of a minimum of 25 percent, but not more than 50 percent (credited), of the reactor i vessel nozzle-to-vessel welds and their inside radius sections by the end of the first inspection period and to defer these examinations to the end of the interval. ;
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l 1 of 5 i RR 98-o07-11
1 This Relief Request is for the deferral only of the Code required examination of 2 Nozzle to-Shell welds and their respective Nozzle-Inner-Radii; it does not exempt them from the Code required examination as defined in Section XI. These welds and Nozzle-Inner-Radius sections are to be examined near the end of the third Ten-Year inspection interval during the last inspection period coincident with the 10 j f,.} year inspection of the reactor vessel. The last refueling outage will occur in approximately 2008. {
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l 111. Alternate Examination:
Florida Power Corporation will perform the examinations, as required by Category B-D on all required reactor vessel Nozzle-to-Shell welds and their b- ' Nozzle-inside-Radius sections by the end of the inspection interval.
IV. Basis for Relief:
The Crystal River Unit 3 reactor vessel has a total of eight nozzles that are classified as Category B-D. The Code requires that a minimum of 25% of these nozzles be examined by the end of the first period of the third interval. The reactor vessel design only permits examination of the two outlet nozzles without removal of the Core Support . Assembly (CSA). This examination is also limited to scanning from the nozzle bore due to interference with the CSA.
I Although the scheduled welds and inside radius sections are to be examined with automated ultrasonic equipment, an additional four person-rem of radiation exposure and one to two cubic feet of radioactive waste is expected.
The reactor vessel nozzles are located above the beltline region and are not subject to the majority of neutron flux escaping from the core.
Six of the eight reactor vessel nozzle-to-shell welds and their inside radius sections were last examined in 1996 with acceptable results. Supplemental examinations were also performed on the two outlet nozzles during the 1996 examination. This examination consisted of scanning the weld from the reactor vessel shell inside (p'. diameter. No indications associated with material degradation were identified during these examinations. The acceptable results of these past examinations are
~'
considered to be representative of the present reactor vessel nozzle weld conditions at Crystal River Unit 3.
' The amendment to 10CFR50.55a, published in the Federal Register on January 31, 1991, contains augmented examination requirements for reactor vessel shell welds, i
Essentially 100 percent of all the reactor vessel shell welds at Crystal River 3 were examined during the second inspection interval.
l 2 of 5 RR 98-007-11
It is more efficient to combine all automated reactor vessel examinations into one outage from both ALARA cd cost considerations. Using the same vendor,
! equipment, personnel, and procetures to examine all the welds at the same time j will enhance the repeatability and quality nf the examination results.
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4' V. Implementation Schedule:
These welds and Nozzle-Inner-Radius sections are to be examined near the end of the third Ten Year inspection interval during the last inspection period coincident l with the 10 year inspection of the reactor vessel. The last refueling outage will l occur in approximately 2008.
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TABLE 1 h Welds and Radius Sections Description Years Examined Results Year Tentatively Scheduled (Nozzle to-Vessel) RPV B 1.4.3 A Inlet 1985,1996 Acceptable 2006 (Inside Radius) "W X" Axis 81.4.3B From *B" Pump 1985,1996 Acceptable 2006 (Nozzle to Pipe) 84.5.221 1996 Acceptable Not Scheduled
{'.)4, (Nozzle-to-Vessel) RPV B1.4.7A Outlet "X" 1985,1990"81993:2' Acceptable 2001*
(Inside Radius) Axis to "A" B1.4.78 OTSG 1990 Acceptable 2001'"
l' (Nozzle to-Vessel) RPV B1.4.4 A inlet 1985,1996 Acceptable 2006 (Inside Radius) *X-Y" Axis 81.4.48 From "A" Pump 1985,1996 Acceptable 2006
' AT'.)
l (Nozzle to Vessel) RPV l B1.4.5 A Inlet 1985,1996 Acceptable 2006 (Inside Radius) "Y-Z" Axis l B1.4.5 8 From "C" Pump 1985,1996 Acceptable 2006 l
l (Nozzle-to-Vessel) RPV l B1.4.8 A Outfet 1985,1990"'*1996'2' Acceptable 2001*
(Inside Radius) *2' Axis to "B" B1.4.88 OTSG 1985,1990 Acceptable 2001* j (Nozzle -to -Pipe) j
,. B4.5.198 1996 Acceptable Not Scheduled
- 4 (Nozzle-to-Vessel) RPV B1.4.6 A Inlet "Z-W" Axis 1985,1996 Acceptable 2006 (Inside Radius) From "D" Pump 81.4.68 1985,1996 Acceptable 2006 I
'S" ' (Nozzle to Vessel) RPV B1.4.1 A Core Flood 1985,1996 Acceptable 2006 (Inside Radius) *W" Axis From B1.4.18 *A* Tank 1985,1996 Acceptable 2006 (Nozzle-to-Safe End)
B1.6.1 1985,1996 Acceptable 2006 4 of 5 ,
RR 98-007.li
TABLE 1
.. Welds and Description Years Results Year Tentatively
((.} Radius Sections Examined Scheduled-(Nozzle-to-Vessel) RPV B1.4.2 A Core Flood 1985,1996 Acceptable 2006 (Inside Radius) "Y" Axis From B1.4.1 B "B" Tank 1985,1996 Acceptable 2006 (Nozzle to-Safe End)
B1.6.3 1985,1996 Acceptable 2006
Note (2): Nozzle-to-Shell welds examined from the vessel shell to supplement the examinations performed from the nozzle bore.
Note (3): If this relief request is granted, these welds and inside radius sections will be examined coincident with the other reactor vessel nozzle examinations during Refuel 14, currently scheduled for 2006.
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5 of 5 RR 98 007-1l
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION RELIEF REQUEST # 98 008-11 THIRD TEN YEAR INTERVAL 0
REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI, t 989 Edition.
(e 7# 1. System / Component (s) for Which Relief is Requested:
Name of Component:
Reactor Vessel closure head nuts, Category B-G 1, Pressure Retaining Bolting, Greater Than 2 in. In Diameter.
Function:
Reactor coolant pressure boundary - Reactor Vessel Closure Head.
ASME Code Class:
({
Code Class 1.
ASME Section XI Examination Category:
Category B-G-1, Pressure Retaining Bolting, Greater Than 2 in. In Diameter; Item B6.10, Closure Head Nuts.
- 11. Current Code Requirement and Request for Relief:
The ASME B&PV Code,1989 Edition,Section XI Code, Table IWB-2500-1 Examination Category B-G-1, requires that a surface examination be performed on each Reactor Pressure Vessel (RPV) closure head nut once each Ten-Year inspection interval.
Relief is being requested to substitute a visual (VT-1) examination for the required surface examination of each RPV closure head nut during this inspection interval.
,n lli. Alternate Examination:
A visual examination will be performed on all RPV closure head nuts once during this inspection interval, as allowed in the 1989 Addenda of Section XI.
1 of 2 RR 98 oo8-11
IV. Basis for Relief:
The ASME Code Committee has recognized that a surface examination is an excessive examination technique to be applied to RPV nuts. The 1989 Addenda of Section XI has changed the requirement from a surface examination to a Visual VT-1 examination.
Extensive cleaning of these nuts is required for a surface examination to be performed. This excessive cleaning results in, additional radioactive waste, additional costs and the inefficient g, use of available manpower resources. The cleaning materials and the wet magnetic particle test G, solution results in " mixed waste", i.e., contaminated and hazardous material that can not be economically processed. The unnecessary generation of " mixed waste" is not consistent with the Radioactive Waste Management Program at CR-3. To continue to perform the required surface examinations of these nuts will not provide any potential increases in plant safety margins and the additional costs for these examinations are no longer warranted based on the changes now published in the 1989 Addenda of ASME Section XI.
V. Implementation Schedule:
The VT-1 examination of all RPV nuts will be conducted during inspection interval 3 as t...,
c) required by the ASME Section XI Code.
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l FLORIDA POWER CORPORATION ;
CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION l REllEF REQUEST # 98-001 PT THIRD TEN-YEAR INTERVAL REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI,1989 Edition.
I h I. System / Component (s) for Which Relief is Requested:
Name of Component:
ASME Section XI Code Class 1,2, and 3 systems and components .
Function: i Pressure retaining components in ASME Section XI Code Class 1, 2 and 3 systems
{') ASME Code Class:
Code Class 1,2 and 3.
ASME Section XI Examination Category:
The systems and components are pressure tested in accordance with examination categories B-P, C-H, D-A, D-B, and D-C.
I
- 11. Current Code Requirement and Request for Relief:
The ASME B&PV Code,1989 Edition,Section XI, Table IWB-2500-1, Category B-P, Table IWC-2500-1, Category C-H, and Table IWD-2500-1, Category D-A, D-8, and D-C, require hydrostatic tests on Class 1,2, and 3 systems and components during the 10 year inspection interval.
, Relief is requested from the requirements to perform hydrostatic tests on Class 1,
!:4 2, and 3 systems and components during the 10 year inspection interval.
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RR 98 ool-PT
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l lit. Alternate Examination:
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FPC will perform inservice leak tests or functional leak tests in accordance with the j requirements of ASME Code Case N-498-1. l k) IV. Basis for Relief:
i The system hydrostatic test required by ASME Section XI is not a test of structural integrity of the system but rather an enhanced leakage test. Piping and l components are designed for a number of loadings that are postulated to occur
- l. under the various modes of plant operation. Hydrostatic testing subjects the piping
!n f and components to only a small increase in pressure over the design pressure and, J
}Uh therefore, does not present a significant challenge to pressure boundary integrity.
l Piping dead weight, thermal expansion, and seismic loads typically present a far i
greater challenge to the structural integrity of a system and are not part of the loading imposed during a hydrostatic test. Hydrostatic testing is primarily a means to enhance leak detection.
In lieu of hydrostatic pressure testing at or near the end of the inspection interval, !
ASME Code Case N-498-1 requires a VT-2 visual examination at nominal operating pressure and temperature.
The proposed alternative examination provides an acceptable level of quality and
( safety as defined by 10CFR50.55a (a)(3)(i).
A similar relief request was granted for the second inspection interval (Relief Request #95-020.)
j V. Implementation Schedule:
i I
The requirements of ASME Code Case N-498-1 will be implemented during the third j inspection interval.
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3
)
INSERVICE INSPECTION RELIEF REQUEST # 98 002 PT THIRD TEN YEAR INTERVAL i@
REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and l Pressure Vessel Code (B&PV),Section XI,1989 Edition.
k) 1. System / Component (s) for Which Relief is Requested:
Name of Component:
ASME Section XI Code Class 1,2, and 3 systems and components.
Function:
Pressure retaining components in ASME Section XI Code Class 1, 2 and 3 systems.
ASME Code Class:
{i Code Class 1,2 and 3.
ASME Section XI Examination Category:
There is no specific Section XI examination category. This relief request is
- addressing those hydrostatic pressure tests required by ASME Section XI, Article IWA-4700, " Pressure Tests" for repairs and replacements by welding.
h II. Current Code Requirement and Request for Relief:
ASME B&PV Code,1989 Edition, Section Xl , IWA-4000, requires hydrostatic I pressure testing be conducted on systems and components after repair by welding i or installation of replacement items by welding in accordance with IWA-5000.
1 Relief is requested from the existing Code requirement for conducting hydrostatic t
- testing as stated above, for ASME Section XI Class 1, 2, and 3 systems and components.
1 of 2 RR 98 002-PT
l l 111. Alternate Examination:
The following alternative examination requirements will be implemented as defined by ASME Section XI Code Case N-416-1, " Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement items by Welding, Class 1, 2, and
(.g 3 Section XI".
A system leak test with associated VT-2 examinations will be conducted in lieu of performing the hydrostatic pressure test.
l NDE shall be performed in accordance with methods and acceptance criteria of the apolicable sub-section of ASME B&PV Code, Section 111,1992 Edition.
I Prior to or immediately upon return to service, a visual examination (VT-2) shall be performed in conjunction with a system leakage test, ASME B&PV Code,1992 Edition,Section XI, in accordance with paragraph IWA-5000, at nominal operating prest.;re and temperature.
Use of this Code Case shall be documented on an NIS-2 Form.
l IV. Basis for Relief:
FPC is requesting relief from the above stated requirements based on ASME Code (g>; Case N 416-1 which has been issued by the American Society of Mechanical Engineers.
l Piping components are designed for a number of loadings that would be postulated to occur. under the various modes of plant operation. Hydrostatic testing only i subjects the piping to a smallincrease in pressure over operating pressure and does not present a significant challenge to pressure boundary integrity. Accordingly, l hydrostatic pressure testing is primarily regarded as a means to enhance leakage l detection during the examination of components under pressure, rather than solely as a measure to determine structuralintegrity of the component.
The proposed alternative examination provides an acceptable level of quality and l(h safety as defined by 10CFR50.55a (a)(3)(i) and 10CFR50.55a (a)(3)(ii).
l V. Implementation Schedule:
The requirements of ASME Section XI Code Case N-416-1 will be implemented during the third inspection interval.
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q 2 of 2 RR 98 Oo2-PT L____.. .
i FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION RELIEF REQUEST # 98 003-PT I
THIRD TEN-YEAR INTERVAL k#
l REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI,1989 Edition.
h$' l. System / Component (s) for Which Relief is Requested:
Name of Component:
Piping, components, and isolation valves that are part of the Class 2 l containment system, and the balance of the piping system is outside the scope j of Section XI l
l Function:
l The subject containment penetrations provide ASME Cbss 2 pressure boundary
,rg) integrity. t i
ASME Code Class: I Code Class 2. I l
ASME Section XI Examination Category:
Examination Category C-H, All Pressure Retaining Components (Class 2); Items No. C7.30 and C7.70.
g 11. Current Code Requirement and Request for Relief:
ASME Section XI 1989 Edition, Table IWC 2500-1, Examination Category C-H requires pressure tests for all Class 2 pressure retaining components.
Relief is requested from performing the ASME Code required pressure tests for piping that penetrates the reactor containment, when the piping and isolation valves that are part of the containment system are Class 2 but the balance of the piping system is
(,'y outside the scope of Section XI.
1 of 2 RR 98 Oo3-PT
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! lll. Alternate Examination:
The following attemative examination requirement will be performed as defined in ASME Code Case N-522.
j q} FPC will comply with 10CFR50, Appendix J, Option 8 testing requirements.
IV. Basis for Relief:
Florida Power Corporation is requesting relief from the above stated requirements based on ASME Code Case N 522 which allows Appendix J testing of the subject
,, penetrations as an alternative to the Code required Category C-H pressure tests.
d 3,i Appendix J leakage tests are performed at a test pressure of 54.2 psig, which is the peak calculated containment intemal pressure for the design basis loss of coolant accident. The containment design pressure is 55 psig. It is expected that leakage due to through wall flaws would be greater than the Appendix J leakage acceptance criteria.
Thus, Appendix J testing should be acceptable for locating and detecting through wall flaws.
The ASME Code Committee evaluated the proposed alternative testing requirements and determined them to be acceptable for ensuring the required integrity of the subject l Class 2 penetrations. Pursuant to the requirements of 10CFR50.55a(a)(3)(i), the '
,. implementation of Appendix J requirements ensures an acceptable level of quality and safety and does not decrease the margin of public health and safety.
V. Implementation Schedule:
The altemative examination requirements of ASME Code Case N-522 will be incorporated into Florida Power Corporation's Inservice Inspection Program for the third inspection interval.
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION RELIEF REQUEST # 98-004-PT THIRD TEN YEAR INTERVAL REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI,1989 Edition.
O t .3 1. System / Component (s) for Which Relief is Requested:
Name of Component:
ASME Class 1,2, and 3 bolted connections.
Function:
The bolted connections provide ASME Class 1,2, and 3 pressure boundary integrity.
( < j) ASME Code Class:
The subject bolted connections are classified as ASME Class 1,2, and 3.
ASME Section XI Examination Category:
IWA-5250(a)(2); Corrective measures for leakage detected at bolted connections during the conduct of a system pressure test.
II. Current Code Requirement and Request for Relief:
hh ASME B&PV Code,1989 Edition,Section XI, Subparagraph IWA-5250(a)(2) requires that if leakage occurs at a bolted connection, the bolting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-3100.
{
Relief is requested from removing botting and performing VT-3 examinations at pressure retaining bolted connections when leakage is detected during performance of ASME Section XI pressure tests and incorporate Code Case N-566.
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111. Alternate Examination:
Florida Power Corporation will comply with the requirements of ASME Code Case N-566.
() IV. Basis for Relief:
Florida Power Corporation is requesting relief from the above stated requirements based on ASME Code Case N-566. Code Case N-566 specifies alternative corrective action when leakage is detected at bolted connections during performance of ASME Section XI pressure tests.
g The requirements of IWA-5250(a)(2) could cause a plant transient. Some restrictions with C IWA-5250(a)(2) are:
- 1. The requirement does not allow engineering judgment of tightening undertorqued bolts.
2 The requirement for bolt removal is without regard to amount of leakage.
- 3. The Code does not require the Owner to stop leakage. j
- 4. VT-3 inspection of the bolting is not necessarily going to stop the leak. i S. IWA-3100 does not provide an acceptance standard for VT-3 bolt examinations.
- 6. The requirement increases radiological dose to workers for leaks that may not have any operational or structural impact.
- 7. The leakage will likely increase, if system conditions allow, when removing one bolt at a time.
(k" The ASME Code Committee evaluated the proposed alternatives contained in Code Case N-566 and determined that they are acceptable for corrective action for leakage at bolted connections.
Code Case N-566 resolves the implementation problems associated with IWA-5250(a)(2) and allows two alternatives as corrective action for leaks at bolted connections. The first option is to stop the leak, and review the bolting and component material for joint integrity. This review will document inspection results of the bolted connection for corrosion and other signs of degradation. The second option is, if the leakage can not be stopped, the joint shall be evaluated in accordance with IWB-3142.4 for joint integrity. This evaluation shall consider the number and condition of bolts, the leakage medium, the bolt and component material, the system function, and the monitoring of leakage.
h' The implementation of Code Case N-566 pursuant to 10CFR50.55a(a)(3)(i) ensures an acceptable level of quality and safety and does not decrease the margin of public health and safety. Implementation of the alternative corrective measures will reduce costs, personnel radiation dose, and outage time. 4 i
V. Implementation Schedule: j
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The alternative corrective measures of ASME Code Case N-566 will be incorporated into Florida Power Corporation's Inservice inspection Program for ASME Section XI for the third inspection interval il 2 of 2 (
RR 98 oo4-PT J
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 )
INSERVICE INSPECTION I RELIEF REQUEST # 98-005-PT THIRD TEN YEAR INTERVAL REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, (B&PV),Section XI,1989 Edition, gg 1. System / Component (s) for Which Relief is Requested:
w+
Name of component:
l ASME Section XI Class 1 bolted connections.
Function:
The bolted connections provide ASME Class 1 pressure boundary integrity.
ASME Code Class:
([, . The subject bolted connections are classified as ASME Class 1.
ASME Section Xi Examination Paragraph: i IWA 5242(a): Visual examination of insulated components in systems borated for the purpose of controlling reactivity.
l 11. Current Code Requirement and Relief Request:
l ASME Section XI 1989 Edition, subparagraph IWA-5242(a) requires for systems i borated for the purpose of controlling reactivity, insulation shall be removed from Ih7 pressure retaining bolted connections for visual examination VT 2.
Relief is requested from removing insulation from Class 1 pressure retaining bolted connections to perform a VT-2 visual e.xamination.
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Iof3 RR 96@3-PT
111. Alternate Examination:
Florida Power Corporation will comply with the requirements of ASME Section XI Code Case N-533. The following requirements will be met for systems borated for the purposes of controlling reactivity.
h.
a) A system pressure test and VT-2 visual examination will be performed each refueling outage without removal of insulation.
b) Each refueling outage the insulation will be removed from the bolted connection, and a VT-2 visual examination will be- performed. The connection is not required to be pressurized. Any evidence of leakage will be evaluated in accordance with IWA-5250, p::,
a IV. Basis for Relief:
Florida Power Corporation is requesting relief based on ASME Section XI Code Case N-533 which specifies an alternative to the requirements of IWA-5242(a) which requires removal of insulation from Class 1 pressure retaining bolted connections to perform a VT 2 visual examination.
The ASME Code Committee evaluated the proposed alternative contained in Code Case N 533 and determined that the alternative requirements for VT-2 visual f i) examination of Class 1 insulated pressure retaining bolted connections was acceptable. Code Case N-533 resolves the implementation problem associated with IWA-5242(a) and allows alternative requirements, both of which will be met.
The first requirement is to perform a system pressure test and VT-2 visual examination each refueling outage without removal of the insulation. The second requirement is to remove the insulation from each bolted connection and perform a VT-2 visual examination each refueling outage. The connection for this examination is not required to be pressurized, and any evidence of leakage is to be evaluated in accordance with IWA-5250.
i IWA-5242(a) requires that components be pressurized and insulatien be removed (for systems that are borated for the purpose of controlling reactivity) during the
$gg..
) visual examination VT-2. The insulation removal requirement causes significant maintenance problems when the Class 1 system is at normal operating pressure and temperature. Removal of insulation on hot components can also cause significant stress on the pressure boundary that may not have been analyzed. The additional l
effort required to replace insulation on hot components will delay plant startup.
{", The implementation of Code Case N 533 pursuant to 10CFR50.55a(a)(3)(i) ensures an acceptable level of quality and safety and does not decrease the margin of public 1 health and safety, implementation of the alternative requirements will reduce personnel radiation dose, nnwa$n I
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V. Implementation Schedule: .
The alternative requirements of ASME Code Case N-533 will be incorporated into Florida Power Corporation's Inservice Inspection Program for the Third Inspection Interval.
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1 3 of 3 RR #00SFT l
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r FLORIDA POWER CORPORATION l CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION RELIEF REQUEST # 98-001-SS THIRD TEN YEAR INTERVAL REFERENCE CODE: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV),Section XI,1989 Edition.
h I. System / Component (s) for Which Relief is Requested:
Name of Component:
All safety-related snubbers i
Function:
! The snubbers provide restraint to a component or system during a sudden j application of forces, but allows essentially free motion during thermal j
! movement.
ASME Code Class:
Code Class 1,2, and 3.
ASME Section XI Examination Category:
No examination category, (IWF-5000) l l 11. Current Code Requirement and Request for Relief: j l
h ASME B&PV Code,1989 Edition,Section XI, Article IWF-5000, requires snubbers to be examined and tested in accordance with the 1988 Addenda to ASME/ ANSI l
OM-1987, Part 4. Section 2.3.2.2 of Part 4 requires snubbers to be examined every 18 months (i 25%) and functionally tested every refueling outage.
l Relief is requested from performing examination and testing of snubbers in accordance with the 1988 Addenda to ASME/ ANSI OM-1987, Part 4 for the third inspection interval.
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111. Alternate Examination:
Florida Power Corporation proposes to use Subsection ISTD of ASME OMb Code, 1996 Addenda to ASME OM Code,1995 Code for Operation and Maintenance of Nuclear Power Plants, for the third inspection interval. This edition of the code
(.3 includes the recommendations of Generic Letter (GL) 90-09.
IV. Basis for Relief:
The schedules for visual examinations and functional testing listed in Part 4 of the 4... 1988 Addenda to ASME/ ANSI OM-1987 assumes that refueling intervals will not 5.9, exceed 18 months. The refueling interval for Crystal River Unit 3 is 24 months.
Recognizing the inspection schedule required by Part 4 was excessively restrictive, the NRC staff developed GL 90-09 to provide an alternate acceptable examination and testing schedule. Subsection ISTD of the 1996 Addenda to ASME OM-1995 incorporates the requirements of GL 90-09. The use of Subsection ISTD of ASME OM Code-1995 provides an acceptable level of quality and safety, and will have no adverse impact on public health and safety. !
V. Implementation Schedule:
FPC will inspect and test the snubbers in accordance with ISTD, Table 6.5.2-1, j Refueling Outage Based Examinations. J l
i l
c l
A 2 of 2 RR 98 001-SS
g Crystal River Unit #3 g']J/
i Power ASME Section XI j 'U " " * " " " Inservice Inspection Program i @6.0 ASME SECTION XI APPLICATION CRITERIA 6.1 The following provides a summary of the application of ASME Code, Section XI, 1989 Edition to the CR-3 ISI Ten Year l Program for the Third Inspection Interval. The application and distribution of examinations for this interval is based upon utilizing Inspection Program B as defined by Articles IWB-2412, IWC-2412, and IWD-2412 of the Code.
l The results of this application are summarized by ASME l Category and Item number and are contained within Table 3.
These tables only contain those ASME Item numbers that are l relevant to CR-3.
l 6.2 CATEGORY B-A - PRESSURE RETAINING WELDS IN REACTOR VESSEL l
Reactor vessel examinations were conducted on the CR-3 l vessel to meet the 1989 Edition of the ASME Code,Section XI as required by 10CFR50.55a, augmented examination requirements, during the second inspection interval.
l Article IWB-2420 in the 1989 Edition of ASME Code, Section i XI requires that the sequence of component examinations be repeated during each successive inspection interval, to the extent practical. Therefore, similar examinations will be scheduled for the Third Inspection Interval. At least 50%
of the shell to flange weld will be examined by the end of l the first inspection period as required by Table IWB-2500-1, Category B-A, note 4. The remainder of the reactor vessel shell welds will be examined near the end of the inspection interval. This meets reactor vessel examination l s requirements in the 1989 Edition of Section XI.
lV5) l 6.3 CATEGORY B-B - PRESSURE RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS l The 1989 Edition of Section XI, Category B-B requires that l pressurizer and primary side of steam generators be examined
! r. during the inspection interval. The examinations may be l' limited to one of a group of vessels with similar function.
The initially selected welds are to be examined in the same sequence during successive inspection intervals, to the extent practical.
21
t'~T Crystal Rivar Unit #3 (b/ " )" " ' "" ASME Section XI Inservice Inspection Program I
6.3.1 STEAM GENERATORS
@ There are two Class 1 Category B-8, welds on each steam generator. Table IWB-2500-1, Category B-B, Note (1) allows the examination be limited to one vessel among a group of vessels performing a similar function. There are two tube sheet to head welds on the OTSG's at CR-3. Both welds on '1 one steam generator are scheduled for examined during the Third Inspection Interval. During the second inspection !
(,i interval, 1/3 of one weld was examined during each of the
^'
first 2 periods. The remaining 1/3 plus the other entire weld was examined during the third period. For the Third Inspection Interval, 1/2 of one weld will be examined during each of the first two periods and the entire second weld will be examined during the third period. This will meet the percentage requirements of inspection program B in Table IWB -2412-1.
PRESSURIZER
- - Section XI requires examination of both shell to head welds and one foot of one intersecting longitudinal weld per head.
During the second inspection interval, 1/3 of each head weld was examined during each inspection period. FPC determined this inspection schedule to be inefficient. Scaffolding, j lighting, and insulation removal was required on portions of 1 each weld during each period. During the Third Inspection )
Interval, 1/2 of one weld will be examined during each of j the first two periods and the entire remaining weld will be examined during the third period. This will meet the percentage requirements of inspection program B in Table IWB-2412-1.
.~
6.4 CATEGORY B-D - FULL PENETRATION WELDS OF NOZZLES IN VESSELS l l
This category applies to the reactor vessel, pressurizer, and steam generators. ASME Code,Section XI does not allow the deferral of these examinations, except for nozzle to reactor vessel welds. Table IWB-2500-1, Category B-D, Note
. 3, allows partial deferral during the third and fourth intervals if the examinations are conducted from inside the component and the nozzle weld is examined by straight beam UT from the nozzle bore, the examinations required to be conducted from the shell inside diameter may be performed at or near the end of the interval.
22
f ,T Crystal River Unit #3 V)%
h . Power
""*""" ASME Section XI Inservice Inspection Program 6.4 CATEGORY B-D (cont)
("T Relief Request 98-007-II modifies these requirements to allow deferral of the reactor vessel outlet nozzle examinations to coincide with the 10-year examination of the vessel at or near the end of the third inspection interval.
6.5 CATEGORY B-E - PRESSURE RETAINING PARTIAL PENETRATION WELDS
('r ' IN VESSELS Visual examinations (VT-2) are to be conducted on pressurizer heaters, control rod drive nozzles, and incore instruments during inservice leak tests performed in lieu of system hydrostatic tests, per the requirements of ASME Code Case N-498-1. Application to use ASME Code Case N-498-1 is documented in Relief Request 98-001-PT. (See Section 5.0 and Table 2) 6.6 CATEGORY B-F - PRESSURE RETAINING DISSIMILAR METAL WELDS g,
This Category addresses Nozzle-to-Safe End Welds and Piping Welds. Category B-J also contains examination requirements for examination of piping dissimilar metal welds. Later editions of the Section XI Code do not include piping dissimilar metal welds as Category B-F. Therefore, with guidance from later Section XI Editions, piping dissimilar metal welds are treated as Category B-J welds in the CR-3 ISI Program. All other dissimilar metal welds will be examined as required by the 1989 Section XI Code, Category B-F.
h% 6.7 CATEGORY B-G PRESSURE RETAINING BOLTING, GREATER THAN 2" IN DIAMETER At CR-3, components with bolting greater than 2" in diameter include the reactor vessel, pressurizer, and reactor coolant pumps. Examinations will be conducted as required in Table IWB-2500-1 in the 1989 Edition of Section XI, as modified by
, Relief Request 98-008-II.
o 23
/ g Crystal River Unit #3 hV ""
]'JPower ASME Section XI Inservice Inspection Program l
6.8 CATEGORY B-G PRESSURE RETAINING BOLTING 2" AND LESS IN ,
DIAMETER
{
This category includes control rod drive (CRDM) holdown ) '
bolting, pressurizer heater bolting and nuts, relief valve bolting, steam generator bolting, flange bolting in piping, reactor coolant pump bolting, valve bolting in the makeup, decay heat,. and reactor coolant systems. Bolting will be selected for examination in accordance with ASME Code,
(.D Section XI, 1989 Edition, Table IWB 2500-1.
- ),
6.9 CATEGORY B-H - INTEGRAL ATTACHMENTS FOR VESSELS Examination category B-H as defined in ASME Code,Section XI, 1989 Edition, does not require examination of Integral Attachments during the third or fourth inspection intervals for ASME Class 1 systems when following Inspection Program B. No Integral Attachments in ASME Code Class 1 systems are selected for examination in the third Inspection Interval.
B' -
6.10 CATEGORY B-J - PRESSURE RETAINING WELDS IN PIPING 10CFR50. 55a (c) (2) (ii) states that if a plant application for construction permit was docketed prior to July 1, 1978, the extent of examination for Class 1 piping welds may be determined by the requirements of Table IWB-2500 and Table IWB-2600, Category B-J from the 1974 Edition with the Summer 1975 Addenda of Section XI. The 1974 Edition of the ASME Code, Table IWB-2500-1, for Category B-J welds, states that "The examinations performed during each inspection interval shall cover all of the area of 25% of the circumferential em, joints including the adjoining 1 ft sections of longitudinal SJ joints and 25% of the pipe branch connection joints".
The requirements from the ASME Code, 1974 Edition, Summer 75 Addenda, was used for examination Category B-J weld j selection for the Third Inspection Interval ISI Program, j except as amended by the following statements. '
- ~ Essentially the same 25% of Class 1 welds examined in the second interval were selected for examination during the Third Inspection Interval to the extent practical as stated j in the 1989 Edition of Section XI, IWB-2420 (a) .
24
l
)
g' g Crystal Rivar Unit #3 tiD ]) Power ASME Section XI Inservice Inspection Program I l
6.10 CATEGORY B-J (cont)
'(p/ The referenced tables in the ASME Code, 1974 Edition, Summer 1975 Addenda, do not address which 25% are to be examined when applying the 1974 Edition of the ASME Code in conjunction with an update to the 1989 Edition of Section XI. Some changes may be made due to limited access, ALARA, etc.
n3 Table IWB-2600-1 in the ASME Code 1974 Edition, Summer 1975
Addenda, address examination method and not extent of examination. Examination method in this ISI Program meets the 1989 Section XI Code and in some cases exceeds the requirements of the ASME Code 1974 Edition, Summer 1975 Addenda, in that surface and volumetric examinations are required on NPS 4 and larger piping and branch connections.
Table IWB-2500-1 for Category B-J contains examination requirements for longitudinal welds. Relief was granted during the second inspection interval to use Code Case N-524. A similar relief is requested for the Third Inspection Interval. The examination requirement is reduced to only cover the volume of longitudinal weld that intersects with circumferential welds required to be examined, provided that other requirements of the Code Case ,
are met. (See Relief Request 98-005-II and Table 2) '
6.11 CATEGORY B-K INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES Examination category B-K-1 of the ASME Code Section XI, 1989 Editirn, does not require examination of Integral
- ;O, Attachments durin7 the Third or Fourth Inspection Intervals
- > in ASME Class 1 .. stems when following Inspection Program B.
No Integral Attachments in ASME Code Class 1 systems are selected for examination in the third Inspection Interval. '
i I
1 25 t
[m3%
(
Crystal Rivsr Unit #3 l
E jlPower ASME Section XI !
V "" * """ Inservice inspection Program I 6.12 CATEGORY B-L-1 AND B-L PRESSURE RETAINING WELDS IN PUMP CASINGS, AND PUMP CASINGS f)
This Category involves reactor coolant pumps and requires volumetric examination on pump casing welds and visual examination of pump internals when disassembled. The reactor coolant pumps are the only Code Class 1 pumps at CR-3.
( Relief Request 98-002-II modifies the Code requirement to permit a 25% surface examination of each scroll weld per interval on one pump only in lieu of the Code required volumetric examination. (See Relief Request 98-002-II and Table 2) 6.13 CATEGORY B-M-1 AND B-M PRESSURE RETAINING WELDS IN VALVE BODIES, AND VALVE BODIES This Category only involves Decay Heat system (DH) and Core Flood system (CF) valves. Examinations will be conducted as
(, ,
required in Table IWB-2500-1. There are a total of eight valves that fall into this examination category. DHV-3/4, DHV-1/2, CFV-1/3, and CEV-2/4 are considered to be groups of valves as defined by Note 3 of examination Category B-M-1/B-M-2, One valve per grouping of valves will be examined over the interval when disassembled for routine maintenance.
6.14 CATEGORY B-N INTERIOR OF REACTOR VESSEL These examinations will be conducted each inspection period
, as required.
)
6.15 CATEGORY B-N INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSEL These examinations will be deferred until the third period as allowed in Table IWB-2500-1.
6.16 CATEGORY B-N REMOVABLE CORE SUPPORT STRUCTURES These examinations will be conducted during the third period to coincide with the 10 year inspection of the reactor vessel. l l
l l
26 l
[ % Crystal River Unit #3 bU ""]'JPower ASME Section XI Inservice Inspection Program 6.17 CATEGORY B-O - PRESSURE RETAINING WELDS IN CONTROL ROD HOUSINGS The ASME Code,Section XI, 1989 Edition, requires volumetric l or surface examination of 10 % of peripheral control rod i drive (CRDM) housings during the inspection interval.
During the second inspection interval, relief from the Code was granted by the NRC to allow volumetric or surface examination of any 6 CRDM housings which had been removed for maintenance and is approximately 10% of all CRDM
{
('Z, housings. Relief Request 98-004-II provides the same alternate examination criteria that will be applied to the l Third Inspection Interval.
{
6.18 CATEGORY B-P - ALL PRESSURE TESTING COMPONENTS The pressure testing program at CR-3 meets the requirements of ASME Code,Section XI, 1989 Edition for Class 1 systems, as revised by Relief Requests 98-001-PT, 98-002-PT, and j 98-003-PT. Relief Request 98-001-PT incorporates the {
requirements of ASME Code Case N-498-1. Relief Request
(' ' 98-002-PT incorporates the requirements of ASME Code Case l
N-416-1. Relief Request 98-003-PT incorporates the requirements of ASME Code Case N-522.
6.19 CATEGORY B-G - STEAM GENERATOR TUBING The Steam Generator Tube inspection program at CR-3 requires j plugging or repair of indications greater than or equal to !
40% through-wall, consistent with tne requirements of IWB-3521 and CR-3 Improved Technical Specifications. The fg extent and frequency of examinations is governed by CR-3 Improved Technical Specification 5.6.2.10. Mandatory Appendix IV of Section XI is implemented, as are the requirements of Section V of the 1989 Edition. l 6.20 CATEGORY C-A - PRESSURE RETAINING WELDS IN PRESSURE VESSELS I
This category applies to the steam generators and decay heat coolers. Note (2) in Table IWC-2500-1, Category C-A only requires examination of welds at gross structural discontinuities, such as, junctions between different thickness, shell to flange welds, cylindrical shell to conical shell, and head to shell welds. Note (3) states that "In the case of multiple vessels of similar 27
l
% Crystal River Unit #3
[]Gpower y, ASME Section XI l V* " " " * " " Inservice Inspection Program l
i l 6.20 CATEGORY C-A (cont) l
! 7 I D. design, size, and service, the required examinations may be l limited to one vessel or distributed among the vessels."
l
(
! 6.21 CATEGORY C-B - PRESSURE RETAINING NOZZLE WELDS IN VESSELS l This Category applies to steam generators and decay heat ,
coolers. Note (1) in Table IWC-2500-1, Category C-B, 4 i @b excludes manways and handholes. Note (3) requires that nozzles selected initially for examination shall be l reexamined over the service life of the component. Note (5) l l allows that in the case of multiple vessels of similar l design, size, and service the required examinaticas may be i i
limited to one vessel or distributed among the vessels.
6.22 CATEGORY C-C - INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, l PUMPS, AND VALVES
- 1. The examination requirements of the 1989 Edition of ASME l -
Code,Section XI will be used for all non-exempt integral attachments on pumps and valves during the third inspection interval.
l ASME Code Case N-509 requires that integrally welded attachments for vessels be examined during each inspection interval and allows, in note (4), only one of multiple vessels to be selected for examination. For piping Code Case N-509 only requires a sample of 10% of the welds l associated with the component supports selected for l examination under the 1990 Addenda. FPC will examine a
! .o. minimum of 10% of the total number of Class 2 integrally jd welded piping attachments. (See Relief Request 98-006-II and Table 2) l 6.23 CATEGORY C-D - PRESSURE RETAINING BOLTING GREATER THAN 2" IN DIAMETER Several studs on main steam isolation valves (MSIV's) were replaced with oversized studs during 1997 due to thread damage. The replacement studs are over 2" in diameter and are included in the ISI Program. There are no other Class 2 bolting greater than 2" in diameter at CR-3.
28 L __ . _ _ - _ _ .
% Crystal River Unit #3
[3) Power (V "" * """
ASME Section XI J Inservice Inspection Program )
q l
l 6.24 CATEGORY C-F PRESSURE RETAINING WELDS IN AUSTENITIC y STAINLESS STEEL OR HIGH ALLOY PIPING 10CFR50. 55a (b) (2) (iv) (B) allows that, for a plant whose construction permit was docketed prior to July 1, 1978 when applying the 1983 Edition with the Summer 1983 Addenda of the ASME Section XI Code, the 1974 Edition with the Summer 1975 Addenda can be applied for extent of examination of Class 2 piping welds. The regulation does not address use (T') of other Editions or Addenda for Class 2 piping when
"~ updating to the 1989 Section XI Code. Therefore, Class 2 j piping welds will be examined to the requirements of the '
1989 Section XI Code for inspection interval 3 at CR-3.
Table IWC-2500-1, Category C-F-1, Note (1) requires that Class 2 piping welds s 4" NPS in high pressure injection systems in PWRs be examined in accordance with exemption criteria in IWC-1220. IWC-1221(b) only exempts 1 - U2 " NPS and smaller in high pressure injection systems of pressurized water reactor plants. At CR-3, Class 2 High ,
l Pressure Injection system suction and discharge piping and '
!('- components greater than 1-1/2" NPS have been included in the
, ISI program as required. Additionally, any piping that l supports the emergency function of the HPI system have been l
included. A minimum of 7.5% of the welds in the High j Pressure Injection system greater than 1 1/2" NPS and $ 4" NPS are scheduled for examination during the Third !
Inspection Interval.
l The selection criteria specified in Table IWC-2500-1, ;
Category C-F-1, will be applied to the remaining Class 2 {
piping and components as required in the 1989 Edition of
.m ASME Code,Section XI. Table IWC-2500-1, Category C-F-1, i.O Item C5.10 under the column on parts examined, requires that piping welds 2 3/8" nominal wall thickness and piping > 4" NPS; receive volumetric and surface examination. The table does not require any examination on piping > 4" NPS if the i nominal wall thickness is < 3/8" (.375") Note 2 in the i table states that "Some welds not exempted by IWC-1220 are not required to be nondestructively examined per Examination 6
Category C-F-1. These welds, however, shall be included in the total weld count to which the 7.5% sample is applied."
Category C-F-1 welds greater than 4" NPS with nominal wall thickness less than 3/8" will be included in the total weld 1 count and will not be chosen for examination during the l Third Inspection Interval. {
)
i 29 l
%% Crystal River Unit #3 x:- JP ASME Section XI L # "ower Inservice Inspection Program 6.24 CATEGORY C-F-1 (cont)
(T)
FPC recognizes the importance of conducting nondestructive examinations of austenitic stainless steel piping in safety systems as part of an ISI program. Therefore, a volumetric examination of an additional sample of 7.5% of Category C-F-1 piping welds that are greater than 4" NPS and less than 3/8" (.375") wall thickness. This sample will be treated as augmented and will be examined in addition to (7 '
Section XI requirements. Included are Building Spray (total of 75 welds < 3/8 in, wall thickness), Decay Heat (total of 207 welds < 3/8 in, wall thickness), and Makeup (total of 91 welds < 3/8 in, wall thickness) of which 7.5% will be volumetrically examined during the Third Inspection Interval.
6.25 CATEGORY C-F PRESSURE RETAINING WELDS IN CARBON OR LOW ALLOY STEEL PIPING The requirements for this Category are similar to those in l.c
- , . Category C-F-1 in the 1989 Edition of ASME Code,Section XI, and will be complied with as required. A portion of the j service water piping that supplies the containment coolers is Code Class 2 piping. This is the only Class 2 Category C-F-2 piping that is greater than 4" NPS and less than 3/8" wall thickness. These welds will be included in the total number of Category C-F-2 welds used to determine the 7.5%
sample as required by ASME Code,Section XI and will not be selected for examination. Augmented examination of these welds is not planned since they are in carbon or low alloy steel piping, are not in a high energy system, and are y included in the Section XI pressure testing program.
%'lU 6.26 CATEGORY C-G - PRESSURE RETAINING WELDS IN PUMPS AND VALVES There are no Class 2 pressure retaining welds in pumps and valves at CR-3.
s,.. 6.27 CATEGORY C-H - ALL PRESSURE RETAINING COMPONENTS The pressure testing program at CR-3 meets the requirements of ASME Code,Section XI, 1989 edition for Class 2 systems as revised by Relief Requests 98-001-PT, 98-002-PT, and 98-003-PT.
30
% Crystal Rivar Unit #3 Power ASME Section XI Inservice Inspection Program 6.27 CATEGORY C-H (cont)
Relief Request 98-001-PT incorporates the requirements of ASME Code Case N-498-1. Relief Request 98-002-PT l incorporates the requirements of ASME Code Case N-416-1.
Relief Request 98-003-PT incorporates the requirements of ASME Code Case N-522.
6.28 CATEGORY D-A - SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION Visual (VT-2) examination of pressure retaining Class 3 systems will be performed in accordance with ASME Code,Section XI, 1989 edition as modified by Relief Requests 98-001-PT, 98-002-PT, and 98-003-PT. Relief Request 98-001-PT incorporates the use of ASME Code Case N-498-1.
Relief Request 98-002-PT incorporates the requirements of ASME Code Case N-416-1. Relief Request 98-003-PT incorporates the requirements of ASME Code Case N-522.
" , Visual (VT-1) examination of the integral attachments will be performed in accordance with ASME Code,Section XI, 1989 Edition as modified by application of the rules from ASME Code Case N-509 and Relief Request 98-006-II.
6.29 CATEGORY D-B - SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, AND REACTOR HEAT REMOVAL Visual (VT-2) examination of pressure retaining Class 3 e systems will be performed in accordance with ASME Code, D Section XI, 1989 edition as modified by Relief Requests 98-001-PT, 98-002-PT, and 98-003-PT. Relief Request 98-001-PT incorporates the use of ASME Code Case N-498-1.
Relief Request 98-002-PT incorporates the requirements of ASME Code Case N-416-1. Relief Request 98-003-PT incorporates the requirements of ASME Code Case N-522.
( " ' -
Visual (VT-1) examination of the integral attachments will be performed in accordance with ASME Code,Section XI, 1989 Edition as modified by application of the rules from ASME Code Case N-509 and Relief Request 98-006-II.
31
fgg Crystal Rivar Unit #3 E 1 ASME Section XI
'O) Power Inservice inspection Program 6.30 CATEGORY D-C - SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL POOL
. Q'1, Visual (VT-2) examination of pressure retaining Class 3 systems will be performed in accordance with ASME Code,Section XI, 1989 edition as modified by Relief Requests 98-001-PT, 98-002-PT, and 98-003-PT. Relief Request 98-001-PT incorporates the use of ASME Code Case N-498-1.
Relief Request 98-002-PT incorporates the requirements of i p ASME Code Case N-416-1. Relief Request 98-003-PT i incorporates the requirements of ASME Code Case N~-522. I Visual (VT-1) examination of the integral attachments will be performed in accordance with ASME Code,Section XI, 1989 ,
Edition as modified by application of the rules from ASME Code Case N-509 and Relief Request 98-006-II. j I
6.29 CATEGORY F-A - SUPPORTS ASME Code Case N-491, Alternative Rules for Examination of l- Class 1, 2, and 3 and MC Component Supports of Light Water Cooled Power Plants, will be applied to this Category during the Third Inspection Interval. The ASME Code Case contains only one category for supports rather than the three contained in the 1989 Edition of Section XI. The ASME Code l Case requires 25% of Class 1, 15% of Class 2, and 10% of l Class 3 non-exempt supports to be examined during the inspection interval.
The examination and testing of snubbers (pin to pin only) is performed in accordance with the requirements of Subsection ISTD of the 1997 Addenda to the 1995 ASME OM Code. (See r: Relief Request 98-001-SS)
@N The reactor vessel support skirt will be examined by ASME Section XI 1989 Edition under examination category F-A as amended by Relief Request 98-003-II.
32
A S Crystal River Unit #3
[ " " " " "
ASME Section XI Inservice inspection Program 7.O AUGMENTED INSERVICE INSPECTION PROGRAM 69 "
7.1 Thin Wall Class 2 (C-F-1) Austenitic Piping The 1989 Edition of ASME Code,Section XI does not require {
examination of Class 2 piping welds > 4" NPS and a wall I thickness.< 3/8". There is a significant amount of Class 2 austenitic stainless steel piping in safety systems at CR-3 l that is not required to be examined under the requirements }
of ASME Code,Section XI, 1989 Edition. FPC recognizes the 1 importance of conducting NDE of austenitic stainless steel piping in safety systems as part of an Augmented Inservice )
Inspection Plan.
To assure the integrity of piping not required to be examined under the 1989 Edition of ASME Code,Section XI, an '
additional sample of 7.5% of Category C-F-1 piping welds that are > 4" NPS and < 3/8" wall thickness will be volumetrically examined.
! (~h This sample will consist of 28 additional welds which will be distributed among all pipe sizes and systems involved.
The systems from which these weld examinations will be selected are Decay Heat, Makeup & Purification, and Building l Spray.
l l 7.2 Volumetric Examination of Class 1 Piping, ASME Examination l Category B-J, < 4" NPS 2 2" NPS in HPI system l
l The 1989 edition of ASME Code,Section XI for Category B-J, requires only surface examination on Class 1 piping welds j hh_ less than 4" NPS. Class 2 HPI piping 2 2" NPS and s 4" NPS l receive both a surface and volumetric examination. FPC '
recognizes the importance of conducting volumetric examinations on austenitic stainless steel piping in PWR High Pressure Injection Systems.
Therefore, volumetric examination in addition to the Code required surface examination will be performed on all Class
.. 1 HPI system welds selected for examination under Category B-J.
i i
l 33 i
1 1
[%,
A Crystal Rivar Unit #3 g; 4 ASME Section XI x
s w / ..........r. ,
Inserv. ice Inspection Program 1
7.3 High Pressure Injection Thermal (HPI) Thermal Sleeve Gb W An augmented Inservice Inspection schedule will be conducted on the High Pressure Injection and Normal Makeup nozzle areas as recommended in the Babcock & Wilcox 177 Fuel Assembly Owner's Group report, Document Number 77-1140611-
- 00. As of Refueling Outage 10, all 4 of the thermal sleeves have been replaced with the new design sleeve and as such, the inspection schedule for a repaired nozzle of new design i will be followed. This schedule entails the following:
(]
MAKE UP NOZZLES
- RT during the first refueling . outage after repair to ensure that the thermal sleeve is in the proper location and no gap has formed.
t l e UT safe end, cold leg ID nozzle knuckle transition, and l l
adjacent piping / valve during the first refueling outage '
after repair to ensure no cracking exists.
f_
- RT and UT again at the third and fourth refueling outages after repair and every fifth outage thereafter.
i i
l HPI NOZZLES i a RT during the first refueling outage after repair to ensure that the thermal sleeve is in the proper location and no gap has formed. RT during third and fifth refueling outages and every fifth refueling outage j thereafter. l rn
- UT the ID nozzle / cold leg transition knuckle area during D the first refueling outage after repair to ensure that no cracking is present. UT during the third and fifth ,
refueling outages thereafter. l l
The thermal sleeves associated with the A2 and B1 loops were '
replaced with the new design thermal sleeve during the R10 outage (1996). The Al nozzle thermal sleeve was replaced in fi 1982 and the B2 thermal sleeve was replaced in 1994.
34
I I
1 Crystal River Unit #3 l
[0- ,'z % ASME Section XI l
l l
tv,! --.P.o...w..e. ..r.
1 i
Inserv. ice Inspect. ion Program j i
j 7.4 GENERIC LETTER 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations
(.
a)
Florida Power Corporation responded to Generic Letter 97-01 ,
by letter dated July 29, 1997 (3F0797-03) from Mr. Roy
{
Anderson to the NRC Document Control Desk. Three commitments were made in Attachment A to the response. )
- An inspection will be conducted from beneath the vessel head while the head is removed from the vessel.
(JG ' This !
will include a one time effort to inspect a minimum of 25 CRDM housing nozzles (24 outer most nozzles and the '
one center nozzle without a CRDM).
1
- Details of the planned inspection will be submitted to the NRC at least 30 days before the start of the refueling outage.
- A summary of the inspection results will be included with the 90 day outage summary report.
('
- \
7.5 Augmented Examination of Inconel 600 l l
In response to an industry wide concern with Inconel 600 cracking in PWR applications (Information Notice 90-10 Prituary Water Stress Corrosion Cracking of Inconel 600), FPC has included within the ISI Augmented Inspection Plan, those locations within the reactor coolant system that are most prone to Primary Water Stress Corrosion Cracking (PWSCC).
The identification of Inconel 600 locations and application l of the risk factors was performed by the Babcock & Wilcox '
.e Owners Group. The report limited the areas of concern to D only the pressurizer and the hot legs.
conservatism, As an additional FPC elected to include the cold leg drain nozzles.
The Inconel 600 locations will receive a visual (VT-2) examination. An equal number of locations will be scheduled for examination each period of the Third Inspection
. Interval. A visual (VT-3) examination of the pressurizer spray nozzle will be performed only when the pressurizer manway is opened for scheduled maintenance.
7.6 Reactor Coolant Pump Motor Flywheel Inspections The Reactor Coolant Pump Motor flywheels will be inspected as required by CR-3 Improved Technical Specifications.
35
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( JP """'" ASME Section XI
()/ "ower Inservice inspection Program 8 LISTING OF ABBREVIATIONS l (g w . 0 l 8.1 SYSTEM ABBREVIATIONS FOR ASME CLASS 1, 2, AND 3 SYSTEMS SYSTEM ABBREVIATIONS SYSTEM / COMPONENT l
AS Auxillary Steam System BS Building Spray Spray CF Core Flooding System l CH Chilled Water System System DC Decay Heat Closed Cycle Cooling System 7 , DH Decay Heat Removal System DO Domestic Water System EF Emergency Feedwater System FW Feedwater System MS Main Steam System MU Make-up & Purification System RC Reactor Coolant System RW Raw Water Cooling System SF Spent Fuel Cooling System i
SW Nuclear Services Closed
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57
l C*stal Rivar Unit #3
@ Florida Power ASME Section XI Inservice inspection Program 8.2 ISI PROGRAM DATA BASE ABBREVIATIONS
(-
l TABLE 4 INSERVICE INSPECTION DATA BASE ABBREVIATIONS
() ABBREVIATION DESCRIPTION ABBREVIATION DESCRIPTION A ANCHOR N NOZZLE
]
ATT ATTACHMENT WELD NIR NOZZLE INNER RADIUS BDL BUNDLE NT NUT l l
BR BRANCH OAE LLBOW OUTSIDE ARC SEAM BLT BOLTING OAT TEE OUTSIDE ARC SEAM BHD BOTTOM HEAD P PIPE 80 BOSS PEN PENETRATION 000 00DY PU PUMP C CIRCUM FER ENTI A L PR PRES $URIZER CLS CLOSURE STUD PT PENCTRANT TEST CLN CLOSURE NUT R REDUCER CLW CLOSURE WASHER RPV REACTOR PRESSURE VESSEL CLB CLOSURE BUSHING S SHELL CONN CONNECTION SE SAFE END CP CAP SK SKIRT CONTPOL ROD CRIVE CROM MECHANISM SN SNUBBER
(/*' N,I CS CIRCUMFERENTIAL SEAM SP SPRING CSS CORE SUPPORT STRUCT'JRE ST STUD E ELBOW SUP SUPPORT EVI EXPCSED VESSEL INTERIOR SW SWEEPOLET F FLANGE SG STEAM GENERATOR FE FLCW ELEMENT T TEE G GUIDE T-C-M TOP CASING WELD HD HEAD TK TANK HDR EXPOSED VESSEL INTERIOR THD TOP HEAD HP! HIGH PRESSURE INJECTION TS TUBE SHEET HTR HEATER TYP TYPICAL 58 1
1 CUstal Rivar Unit #3 8 Florida Power ASME Section XI Inservice inspection Program
.. I TABLE 4 INSERVICE INSPECTION DATA BASE ABBREVIATIONS ABBREVIATION DESCRIPTION ABBREVIATION DESCRIPTION INTEGRAL ATTACHMENT WITHIN IAWB BELTLINE UT ULTRASONIC TEST
'* INTEGRAL ATTACHMENT BEYOND IABR BE LT LINE UTS UPPER TUBE 3HEET I-3 INTERIOR SUR FACE UH UFPER HEAD IAC ELBOW INSIDE ARC SEAM V VALVE IAT TEE IN3fDE ARC GEAM VE VE3SEL IIN INCORE INSTRUMENT U U-BOLT LIG LIGAMENT WD WELOOLET LG LONG3EAM LH LOWER HEAD _
LT3 LCWER TURE SHEET MK MARK MT MAGNETIC PARTICLE TE3T MW MANWAY 3 ,
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59 l
g Crystal Rivsr Unit #3 L[']'! Power
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ASME Section XI Inservice inspection Program 9.0 LISTING OF ASME CALIBRATION BLOCKS
& l TABLE 5 CR-3 ASME CALIBRATION BLOCKS BLOCK BLOCK DESCRIPTION MATERIAL APPROXIMATE TYPE DIMENSIONS (TsNUMBER 40701 ARIS CAL STD #0001 CS/SS 12" x 8" x 3" CLAD 40702 ARIS CAL STD #0002 CS 23" x 12" x 12" 40703 ARIS CAL STD #0003 CS/SS 25" x 12" x 8" I CLAD !
40704 ARIS CAL STD #0004 CS/SS 21" x 9" x 8" CLAD j 40705 ARIS CAL STD #0005 CS/SS 12" x 11-1/2" x 10-1/2" CLAD f l
(.40706 ARIS CAL STD #0006 CS/SS 16" x 15" x 5" CLAD 40707 PRESSURIZER VESSEL STD CS/SS 21" x 7" x 7" CLAD 40708 8-in CARBON STEEL CAL CS/SS 18-5/8" x 8" x 4" STD CLAD 40709 5-in CARBON STEEL CAL CS/SS 18" x 5" x 4" STD CLAD 40710 PIPING CAL STD 'A' SS 1-1/2" x 0.281" 40711 PIPING CAL STD 'B' SS 2" x 0.344" Ihf3'40712 PIPING CAL STD 'C' SS 2-1/2" x .0375" 40713 PIPING CAL STD 'D' SS 3" x 0.438" 40715 PIPING CAL STD 'G' SS 6" x 0.280" 40716 PIPING CAL STD 'H' SS 8" x 0.322" 40717 PIPING CAL STD 'J' SS 10" x 1.000"
, .. 40718 PIPING CAL STD 'J1' SS 10" x 0.375"
'40719 PIPING CAL STD 'K' SS 12" x 0.375" i 40720 PIPING CAL STD 'L' SS 12" x 1.312" 40721 PIPING CAL STD 'M' SS 14" x 1.250" 1
40722 PIPING CAL STD 'O' CS 6" x 0.280" 40723 PIPING CAL STD 'P' CS 6" x 0.432" 60 l l
I R
- ' Crystal Rivsr Unit #3 r ASME Section XI
(# "" * " "" inservice Inspection Program i
f ,,Jy t
TABLE 5 CR-3 ASME CALIBRATION BLOCKS-l BLOCK BLOCK DESCRIPTION MATERIAL APPROXIMATE l
NUMBER TYPE DIMENSIONS l 40724 PIPING CAL STD 'R' CS 10" x 0.500"
{T40725 PIPING CAL STD 'S' CS 10" x 0.719" 40726 PIPING CAL STD 'T' CS 18" x 0.938" ;
40727 PIPING CAL STD 'U' CS 18" x 1.156" 40728 PIPING CAL STD 'W' CS 24" x 0.969" l 40729 PIPING CAL STD 'X' SS 14" x 0.250" l 40730 3/4-in CARBON STEEL CAL CS 7" x 1" x 3/4" STD l 40731 1-1/2 in CARBON STEEL CS 12" x 1-1/2" x 1-1/2" f CAL STD 40732 CLOSURE STUD CAL 9TD CS 30" x 5.750" f.- egi 40734 3-in STAINLESS STEEL SS 12" x 3" x 3" CAL STD 40735 3/4-in STAINLESS STEEL SS 7" x 1" x 3/4" CAL STD 40736 1-1/2 in STAINLESS SS 8" x 1-1/2" x 1-1/2" STEEL CAL STD 40737 PIPING CAL STD 'Y' SS 14" x 0.440" 40738 CLOSURE STUD CAL STD CS 5" x 5.750"
, 'B' 40739 14-in STEEL CAL STD CS 14" x 0.750" 40740 18-in STAINLESS STEEL SS 18" x 0.750" CAL STD 40741 5-in BRANCH FW HEATERS CS 5" x 0.750" 40742 6-in SCH 160 CAL STD CS 6" x 0.750" 40743 RCP MOTOR FLYWHEEL CS 36" x 24" x 7" I 40744 WELDOLETS ON DRAINS SS 2.8" x 0.750" 40745 14-in SCH 80 CAL STD SS 14" x 0.750" 40746 MSIV BONNET STUD CS 13-1/2" x 2" 40747 6-in PIPING CAL STD CS 6" x 1.500" 40752 3-in CARBON STEEL CAL CS 7" x 4.4" x 3" 61
f( '3 g Crystal Rivsr Unit #3 Power ASME Section XI C'v} "" * """ Inservice inspection Program 4.
TABLE 5 V CR-3 ASME CALIBRATION BLOCKS BLOCK BLOCK DESCRIPTION MATERIAL APPROXIMATE NUMBER TYPE DIMENSIONS 40753 CARBON STEEL CAL STD CS/SS 12" x 6" x 3"
, CLAD 40754 OTSG SHELL TO TUBESHEET CS 21" x 7" x 7" ,
40755 OTSG SHELL TO SHELL CS 15" x 5" x 5" 40756 ARIS NOZ TO VES/FLG TO CS/SS 36" x 12" x 8" I VES CLAD 40756 ARIS NOZ TO VES/FLG TO CS/SS 36" x 12" x 8" VES CLAD 40757 ARIS NOZ TO VES/FLG TO CS/SS 45" x 18" x 8-1/2" VES CLAD 40761 REACTOR COOLANT PUMP CS 34" x 4.8 STUD 7'
40762 NEAR SURFACE CAL STD CS/SS 14" x 6" x 4" 5"-9" THK CLAD 40763 NEAR SURFACE CAL STD CS/SS 14" x 6" x 4" 12" THK CLAD 40764 PRESSURIZER MANWAY STUD CS 15" x 2.8" 40765 2-in HEATER BUNDLE STUD CS 16" x 2" 120526 PIPING CAL STD 'E' SS 4" x 0.750" 7
500-1 PIPING CAL STD SS 3" x 0.438
.[{}502-1 MSIV STUD CAL STD CS 2.25" x 14.5"
[503-1 PIPING CAL STD SS 2.5" x 0.375 62
Crystal River Unit #3
[., ,)J %
Pw ASME Section XI tv y ...o.... e...r.
Inservice Inspection Program 10 .O RECORDS AND REPORTS h
10.1 Records and reports for the Inservice Inspection Program, outage examination schedules, examination results, procedures, certifications, test, repairs, and replacements are maintained in accordance with FPC procedures, and meet the requirements of ASME,Section XI, Article IWA-6000. The ISI summary reports are prepared in accordance with Article
( '
IWA-6220 and submitted to the Nuclear Regulatory Commission (
within 90 days following each refueling outage. The ISI summary report shall contain, as a minimum, refueling outage number, Owners Report for Inservice Inspections (Form NIS-1), and Owners Report For Repairs or Replacements (Form NIS-2).
10.2 The implementing procedure for preparation of the ISI Summary Report is SP-215, ASME Section XI Nondestructive Examination.
('
, 10.3 Preparation of the 90 day Summary Report for the steam generator tube inspection is performed by SP-305, OTSG Inservice Inspection.
c .?
( s-i 63
.fr s,,
Crystal Rivar Unit #3 g' ASME Section XI Inserv,ce Inspection Program i
11.O COMPONENT & ISOMETRIC DRAWINGS 11.1 The Component and Isometric drawings contained within this section. of the Ten-Year Program, identify the welds and components required to be examined under the rules of ASME Code,Section XI, 1989 Edition. The ISI sketches contained within this document will be used to locate each examination item. Plant controlled drawings and the ISI NDE data base will be used when additional information is required.
The Code boundaries shown on these sketches were obtained from the plant controlled P&ID drawings.
I I
i i
64 k.
i Crystal Rivar Unit #3 j',~ ,jD Flodda MJ
'i ASME Scotion XI v Inservice inspection Program q i
l l
COMPONENT DRAWING INDEX Drawing Title l Revision l
t
! SK-I AC.1 Reactor Pressure Vessel (layout) 1
! SK-I AC.2 Reactor Pressure Vessel (section) 0 SK-1 AC.3 Reactor Top Head (closure hardware) 0 SK-1 AC.4 Reactor Top head (CRDM & hardware) 1 SK-1 AC.5 RCP Seal Cooler Welds 0 SK-1 AC.6 Steam Generator "A" 0 SK-1 AC.7 Steam Generator "B" 0 SK-1 AC.8 Pressurizer (section) 0 SK-1 AC.9 Pressurizer (closure hardware) 1 SK-1 AC.10 (
Feedwater Header to Steam Generators (RCSG-1 A/lB) 0 SK-1 AC.11 Decay Heat Cooler A & B 0 SK-1 AC.12 Reactor Coolant Pump (section) 0 SK-1 AC.13 Reactor Vessel Head Stand Pipe Assembly 0 SK-1 AC.14 Letdown Coolers 0 l
SK-1 AC.15 Main Steam Isolation Valves 0 I SK-1 AC.16 Integral Attachments (SWHE-1 A, IB, IC,lD) 0 i
SK-1 AC.17 Integral Attachments (DCHE-1 A,lB) 0 SK-1 AC.18 Integral Attachments (DHHE-1 A, IB) 0
^^
[ "'N % Crystal Rivsr Unit #3 E P ASME Section XI Ed ""ower *"""
Inservice inspection Program l
COMPONENT DRAWING INDEX Drawing Title Revision l
SK-1 AC.19 Integral Attachments (DCT-1 A) 0 SK-1 AC.20 Integral Attachments (DCT-1B) 0 SK-1 AC.21 Integral Attachments (SWT-1) 0 i
SK-1 AC.22 Integral Attachments (EFT-1) "
SK-1 AC.23 Integral Attachment (DCP-1 A, IB, SWP-1 A, IB, IC) **
l l SK-1 AC.24 Integral Attachment (RWP-1,2A,2B,3A,38) "
i l
NOTE ** Indicates Drawing In Course of Preparation
( % Crystal Rivsr Unit #3
!/ ) ASME Section XI '
(# ""* """r Inservice inspection Program i
CLASS 1 PIPING INDEX Drawing Title Revision l
l SK-l .1 12" Decay Heat 0 S K-3.1 10" & 14 " Core Flood (A Train) 1 l
SK-3.2 10" & 14 " Core Flood (B Train) 1 S K-4.1 21/2" High Pressure Injection (RCP-1 A) I 1
SK-5.1 21/2" High Pressure Injection (RCP-1B) 0 SK-5.2 21/2" High Pressure Injection (RCP-1B) I i
S K-6.1 21/2" High Pressure Injection (RCP-lC) 0 I I
SK-6.2 21/2" High Pressure Injection (RCP-lC) 1 SK-7.1 21/2" High Pressure Injection (RCP-ID) O S K-7.2 21/2" High Pressure Injection (RCP-1D) 1 SK-8.1 Pressurizer Valves (PORV & Code Safety) 1 S K-9.1 21/2" Suction to Letdown Coolers 0 SK-9.2 21/2" Suction to Letdown Coolers 0 S K-9.3 21/2" Suction to Letdown Coolers 0 SK- 10.1 21/2" Letdown Cooler Outlet (MUHE-1 A,18, IC) 0 S K- 10.2 21/2" Letdown Cooler Outlet (MUHE-1 A, IB, IC) 0 SK-10.3 21/2" Letdown Cooler Outlet (MUHE-1 A, IB, IC) 0 S K-11.1 28" Reactor Coolant Cold Leg (Loop A1) 0
,/7% % Crystal River Unit #3
(- Et Power ASME Section XI L v '""""" Inservice Inspection Program CLASS 1 PIPING INDEX Drawing Title Revision SK-12.1 28" Reactor Coolant Cold Leg (Loop A2) 0 S K-13.1 28" Reactor Coolant Cold Leg (Loop B1) 0 S K-14.1 28" Reactor Coolant Cold Leg (Loop B2) 0 SK 15.1 36" Reactor Coolant Hot Leg (Loop A) 0 ;
l SK-15.2 36" Reactor Coolant Hot Leg (Loop B) 0 SK-15.3 Reactor Coolant to Steam Generators (Details) 0 3 l
\
SK-16.1 Cold Leg Cross Over From OTSG "B " to Pump B1 (RCP-lC) 0 l SK-16.2 Cold Leg Cross Over From OTSG "B" to Pump B2 (RCP-ID) 0 SK-17.1 Cold Leg Cross Over From OTSG "A" to Pump A1 (RCP-I A) 0 i SK-17.2 Cold Leg Cross Over From OTSG "A" to Pump A2 (RCP-1B) 0 SK-18.1 10" Surge Line 0 l
SK- 19.1 21/2" Pressurizer Spray Line 0
- SK-20.1 Reactor Coolant Drain From RCP-:A 0 SK-20.2 Reactor Coolant Drain From RCP-1B 0 l
S K-20.3 Reactor Coolant Drain From RCP-lC 0
l Crystal Rivar Unit #3
(('~%, FloridaV)("ower
- P " " " " ASME Section XI Inservice inspection Program l
CLASS 2 PIPING INDEX i
Drawing Title Revision SK-101.1 24" Main Steam From OTSG "A" to Pen. # 106 0
{
SK-101.2 24" Main Steam From Pen. # 106 to MSV-412 0 l
SK-102.1 I 24" Main Steam From OTSG "A " to Pen. # 105 0 SK-102.2 24" Main Steam From Pen # 105 to MSV-411 0 SK-103.1 24" Main Steam From OTSG "B" to Pen # 107 0 SK-103.2 24" Main Steam From Pen # 107 to MSV-414 0 S K-104.1 24" Main Steam From OTSG "B" to Pen # 201 0 SK-104.2 24" Main Steam From Pen # 201 to MSV-413 0 SK-105.1 Feedwater to OTSG "A" 0 j SK-105.2 Feedwater to OTSG "A" 0 SK-105.3 Feedwater to OTSG "A " 0 ,
l SK-106.1 Feedwater to OTSG "B" 0 )
SK-106.2 Feedwater to OTSG "B " 0 l
SK-106.3 Feedwater to OTSG "B" 0 SK-107.1 Emergency Feedwater to OTSG "A" 0 l l
SK- 107.2 Emergency Feedwater to OTSG "A" 0 SK-107.3 Emergency Feedwater to OTSG "A" 1 SK- 108.1 Emergency Feedwater to OTSG "B" 0 SK-108.2 Emergency Feedwater to OTSG "B" 0
/"% Crystal River Unit #3
' L) pow ASME Section XI (V ""*"e ""
Inservice inspection Program CLASS 2 PIPING INDEX Drawing Title Revision SK-108.3 Emergency Feedwater to C4TSG "B" 1 SK-109.1 14" Decay Heat (A Train) 1 SK-109.2 14" Decay Heat (A Train) 0 SK 110.1 14" Decay Heat (B Train) 0 SK-110.2 14" Decay Heat (B Train) 1 SK-111.1 8" Decay Heat 0 SK-111.2 14" Decay Heat 0 {
l SK-112.1 10" Decay Heat (A Train) O SK-l l2.2 10" Decay Heat (A Train) 1 l
SK-112.3 10" Decay Heat (A Train) 0 SK-113.1 10" Decay Heat (B Triin) 0 SK-113.2 10" Decay Heat (B Train) i 1 1
SK- 113.3 10" Decay Heat (B Train) 0 SK-114.1 8" Decay Heat (A/B Train) 0 SK-115.1 6" Makeup 1 !
SK-115.2, 6" Makeup 0 l
SK-115.3 4" Decay Heat to DHV-11 (Piggy Back mode) O SK-115.4 6" Makeup 0 SK Il6.1 6" Makeup 1
[ Crystal Rivar Unit #3
'v " " * " " " Inservice inspection Program CLASS 2 PIPING INDEX l
Drawing Title Revision SK-116.2 6" Makeup 1 l
l SK-116.3 4" Decay Heat to DHV-12 (Piggy Back mode) 0 l SK-117.1 14" Core Flood 0 SK-118.1 14" Core Flood 0
! SK-119.1 5" hiakeup 1
(
l SK-120.1 10" Building Spray to BSP-l A 0 SK-120.2 10" Building Spray From BSP-1 A to Pen # 340 0 SK-121.1 10" Building Spray to BSP-1B 0 SK-121.2 10" Building Spray From BSP-1B to Pen # 341 0 SK-122.1 14" Decay Heat From BWST "A" Train 0 SK-122.2 6" MU Pump Suction From BWST "A" Train 0 SK-122.3 14" Decay Heat From BWST "B" Train 0 SK-122.4 6" MU Pump Suction From BWST "B" Train 0 SK-123.1 4" Makeup Recire Line O SK-123.2 4" Makeup Recirc Line O SK 124.1 2" Makeup Recire Line From MUP 1 A. O SK-125.1 2" Makeup Recirc Line From MUP-1B 0 SK-126. I 2" Makeup Recire Line From MUP-lC 0 SK-127.1 10" Decay Heat From BWST to SFV-13 0
i r'"N Crystal Rivar Unit #3
[ ASME Section XI O " " * " "" inservice Inspection Program CLASS 2 PIPING INDEX l Drawing Title Revision SK-127.2 10" Decay Heat From BWST to SFV-13 0 l
l SK-128.1 21/2" Makeup to RCS O SK-128.2 21/2" Makeup to RCS 0 l
SK-128.3 21/2" Makeup to RCS 0 l SK-128.4 21/2" Makeup to RCS 0 SK-129.1 4" Makeup to MUV-18 0 SK-129.2 21/2" Makeup to MUV-18 0 SK-129.3 21/2" Makeup to MUV-18 0 SK-129.4 21/2" Makeup to MUV-18 0 SK-129.5 21/2" Makeup Bypass for MUV-452 0 SK-129.6 21/2" Makeup Bypass for MUV-452 0 SK-130.1 4" Makeup Discharge Header 0 SK-130.2 3" Makeup From MUP-lC Discharge 0 SK-130.3 4" High Presure injection 0 SK-130.4 3" Makeup to RC Injection 0 SK-130.5 3" Makeup to RC Injection 0 SK-131.1 4" Makeup Header 0 l SK-131.2 3" Makeup From MUP-1B Discharge 0 SK-131.3 3" Makeup From MUP-1 A Discharge 0
"b -
Crystal River Unit #3 h[O)""*"""
Powe ASME S ction XI inservice inspection Program CLASS 2 PIPING INDEX Drawing Title Revision SK-131.4 4" High Pressure Injection 0 SK-131.5 3" Makeup to RC Injection 0 SK-131.6 3" Makeup to RC I njection 0 SK-132.1 3" Makeup Recirc to RB Sump 0 SK-132.2 3" Makeup Recirc to RB Sump 0 SK-132.3 3" Makeup Recirc to RB Sump 0 SK-132.4 3" Makeup Recirc to RB Sump 0 1
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