ML17264A946
| ML17264A946 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/20/1997 |
| From: | Klepachi F ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17264A947 | List: |
| References | |
| PROC-970620, NUDOCS 9707170020 | |
| Download: ML17264A946 (90) | |
Text
INSERVICE INSPECTION p.$
Revision
{ISI} PROGRAM 1 of 8 j4.:'age INSERVICE INSPECTION {ISI} PROGRAM Effective Date: 30 June 1997 Prepared by: Date: <hairy Reviewed by: Date:
Approved y: Date: 4 "ao -P7 Record Category: 15.22.3 9707170020 970708 eon hooch osoo02ee(
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li INSERYICE INSPECTION p$
Revision (ISI) PROGRAM Page 2 II;:
of 8 Table of Contents Section 1 Inservice Inspection Program: Rev. 0 1.0 Introduction, 1.1 General 1.2 Applicable Documents 1.3 Inspection Intervals 1.4 Classification of Components 1.5 Responsibility 1.6 Records 1.7 Examination Methods and Requirements 1.8 Repair Requirements 1.9 Replacement Requirements 1.10 System Pressure Testing 2.0 Class 1 Program Plan 2.1 Basis for Preparation 2.2 Components Subject to Examination 2.3 Extent and Frequency of Examinations 2.4 Exemption Criteria 2.5 Examination of Reactor Coolant Pump Flywheels 2.6 Inservice Inspection Program Plan 3.0 Class 2 Program Plan 3.1 Basis for Preparation 3.2 Components Subject to Examination 3+3 Extent and Frequency of Examinations 3.4 Exemption Criteria 3.5 Inservice Inspection Program Plan 4.0 Class 3 Program Plan 4.1 Basis for Preparation 4.2 Components Subject to Examination 4.3 Extent and Frequency of Examinations 4,4 Exemption Criteria 4.5 Inservice Inspection Program Plan
e INSERVICE INSPECTION Revision <4::
(ISI) PROGRAM Page 3 of 8 Section 1 (Contd. )
- 5. 0 Class 1, 2 & 3 Component Supports
- 5. 1 Basis for Preparation
- 5. 2 Components Subject to Examination
- 5. 3 Extent and Frequency of Examinations
- 5. 4 Exemption Criteria
- 5. 5 Inservice Inspection Program Plan Section 2 Relief Requests: Rev. ~:,:,:.>1 1.0 Introduction 1.1 General Section 3 P&ID Boundary Drawings: Rev. 0 1.0 General P&ID Boundary Drawings Section 4 Code Tables: Rev. 0 1.0 General Table 1, Class 1 Table 2, Class 2 Table 3, Class 3 Table 4, Class 1, 2, & 3 IWF Component Supports Section 5 Line List: Rev. 0 1.0 General Line List
I NSERVICE I NSP ECTION p:
Revision <<0:
{ISI} PROGRAM Page 4 of 8 Section 6 Allocation Tables: Rev. 0 1.0 General ASME Code Requirements Class 1 Class 2 Class 3 Class 1,2, & 3 Supports Augmented Reactor Coolant Pump Flywheel Program Reactor Vessel Augmented Program, Category B-A High Energy Program Snubber Program Seismic Support Program Section 7 UT Calibration Blocks: Rev. 0 1.0 General UT Calibration Blocks Section 8 High Energy Program: Rev. 0 1.0 General 2.0 Examination Requirements 3.0 Examination Methods 4.0 Frequency of Examination 5.0 Examination Evaluation 6.0 Repair & Testing Requirements 7.0 Replacement & Testing Requirements 8.0 Scheduling 9.0 Reports & Records Table 1 High Energy Welds & Component Support Identification.
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INSERVICE INSPECTION Revision ~4:.:
{ISI} PROGRAM Page 5 of 8 Section 9 Snubber Program: Rev. 0 1.0 General 2.0 Examination, Testing & Monitoring Requirements 3.0 Examination & Testing Methods 4.0 Examination & Testing Frequency 5.0 Examination, Testing & Monitoring Evaluation 6.0 Repair, Replacement & Modification Requirements 7.0 Scheduling 8.0 Reports & Records Section 10 Seismic Support Program: Rev. 0 1.0 General 2.0 Examination Requirements 3.0 Examination Methods 4.0 Frequency of Examination 5.0 ~ Examination Evaluation 6.0 Repair & Testing Requirements 7.0 Replacement & Modification, Testing Requirements 8.0 Scheduling 9.0 Reports & Records Table 1
. Seismic Category I Supports
INSERVICE INSPECTION Isss Revision (ISI) PROGRAM L5:::
Page 6 of 8 Section 11 Additional Programs: Rev. gi.
1.0 General 2.0 Steam Generator Tube Inspection Program 2.1 General 2.2 Inspection Program 2.3 Examination Method 2.4 Frequency of Examinations.
2.5 Examination Evaluation 2.6 Repair, Replacement & Testing Requirements 2.7 Scheduling 2.8 Reports & Records 3.0 Reactor Coolant. Pump Flywheel Program 3.1 General 3.2 Examination Requirements 3.3 Examination Method 3.4 Frequency of Examinations 3.5 Examination Evaluation 3.6 Repair, Replacement & Testing Requirements 3.7 Scheduling 3.8 Reports &'Records II 4.0 Reactor Vessel Augmented Program, Category B-A 4.1 General 4.2 Examination Requirements 4.3 Examination Method 4.4 Frequency of Examinations 4.5 Examination Evaluation 4.6 Repair, Replacement & Testing Requirements 4.7 Scheduling 4.8 Reports & Records
INSERVICE INSPECTION $
Revision g (ISI) PROGRAM Page T of 8 Section 12 Repg,':x'~jpa'nd",':.::Re~3:a'cemeii~Pi~gipm'0 Rev. 1>
1.0 Purpose 2.0 Reference 3.0 Definitions 4.0 Code Applicability 5.0 Responsibilities 6.0 R~$ :. Exemptions 6.1 f Replacement g.-':i'qc3:g'5xm j'j::.859'i XCit-,:,i~OK)".
Exemptions
'6. 2 Repair Exemptions 6.3 Hydrostatic Testing Exemptions for Repairs 7.0 General RYR Program Requirements Initiation/Disposition A~>YA'rogram 8.0 8.1 Program Initiation 8.2 Disposition 9.0 Repair Requirements 9.1 Repair Applicability 9.2 Additional Requirements 9.3 ANII Notification 9.4 Repair Welding/Metal Removal Requirements 9.5 Leakage Testing 9.6 Preservice/Examination Requirements 9.7 Repairs Records 10.0 Replacement (and Modification) Requirements 10.1 10.2 Additional Requirements 10.3 FR~e,':3."@cern'ingp,:Pig,grym 10.4 ANII Notification 10.5 Applicable Code Requirements
INSERVICE INSPECTION Revision $'::
(ISI} PROGRAM Page 8 of 8 Section 12 (Contd. )
10.6 Verification of Acceptability 10.7 Fabrication and Examination Requirements 10.8 Leakage Testing 10.9 Preservice Examination Requirements 10.10 Replacement (:.XnefuCh'~0+ Modi fication) Records SUPPLEMENT 1 TO THE INSERVICE INSPECTION PROGRAM "Inservice Inspection Program Plan" (Separate Document controlled by Laboratory 8 Inspection Services-available upon request. )
SECTION 11 ADDITIONAL Pageos Revision ~1.::
PROGRAMS of 9 General:
The purpose of this section is to provide information and clarification on additional inspection programs being performed at R. E. Ginna Nuclear Power Plant.
These inspection programs may be due in part to ASME Section XI program requirements or to other commitments made by Rochester Gas and Electric.
The following list identifies additional inspection programs being performed at R. E. Ginna Nuclear Power Plant:
Steam Generator Tube Inspection Program Reactor Coolant Pump Flywheel Program
- Reactor Vessel Augmented Program, Category B-A Steam Generator Tube Inspection Program:
General:
The Steam Generator Tube Inspection Program incorporates the requirements of ASME Section XI Code, under Category B-Q, Item Number B16.20. The Code requires that Steam Generator tubing in U-Tube Design be volumetrically (Eddy Current) examined" to the extent and frequency governed by the plant Technical Specifications. In accordance with this Code requirement and R. E. Ginna Station Technical Specifications, eddy current examinations shall be gU.3.~,-'wens"'olly performed. Steam Generator Tubing shall be examined their full length, at least once every 56>,'..";6Rfect'i::ve':-
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1 SECTION 11 ADDITIONAL Revision ~4':.
PROGRAMS Page 2 of 9 2.1.2 The Steam Generator Tube Inspection Program also incorporates the requirements of USNRC Regulatory Guide 1.83, Revision 1, dated July, 1975, "Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes" and the recommendations of the Electric Power Research Institute (EPRI) PWR Steam Generator Inspection Guidelines, R'ivy%),,iraqi~'4'~+orrmlatest approved revision.
2.2 Inspection Program:
2.2.1 The program for each inspect'ion Ishall include, as a minimum, the following requirements of tubes shall be wasp'eiged within sf fiptx~e i 03) ~;.",,powei~mc i~i:::h'd Pj~100%
. . fjghe ii~)%iirix'n'sp'so'ta'o'n L". is+ erformetd~iin'ib'll> iei s:"th'::"'aiin'f-'.",20% sample of all Si~gtubes for their full length will be examined
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- 2. p!00%.",:,.'of!'iReysilredyjtubes hrs, all'-, hjfi~npp "et,:cide:"tagbh e than:-.'ii~$ 20% sample" of each type of 8'epiii'<i'e'd tube
~lii1kiiibi"m: -. i !es!!I PiagpogYa'.::,ag.,:':;..:,examine)'atj,,q Bends'.
+4'!'-.: All operational tubes that had a previously identified service induced degradation of greater than 208 through wall to the extent of previously identified degradation. However, if after two (2) consecutive inspections these tubes have not had greater than 10% further penetration, the inspection frequency on these tubes may be extended to 40 months.
SECTION 11 ADDITIONAL Revision z4 PROGRAMS Page 3 of 9 2.2.2 Other tubes may be added to the program each inspection cycle as necessary to meet other concerns and are classified as "owner elected". "Owner Elected" examinations are not mandatory and may be performed as determined by the owner.
2.2.3 The Ginna Steam Generator Reliability Committee may change the aforementioned plan to meet outage schedules, provided that the changes meet the requirement of Regulatory Guide 1.83 and Supplement 1 the Inservice Inspection Program Plan.
2.3 Examination Method:
2.3.1 Eddy Current (Volumetric) Examination techniques shall be employed to perform the required examinations on Steam Generator tubes.
2.4 Frequency of Examinations:
2.4.1 Examinations shall be performed every inspection cycle to the extent required and specified within 2.2, as a minimum.
2.5 Examination Evaluation:
2.5.1 Eddy Current evaluation shall be performed in-accordance with approved procedures.
I I
e ADDITIONAL PROGRAMS SECTION 11 Revision Page 4 of 9
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2.6 Repair, Replacement and Testing Requirements 2.6.1 Repair criteria for steam generator tubes is based on the requirements of'Regulatory Guide 1.121, "Bases for Plugging Degraded PWR Steam Generator Tubes".
2.6.1.1 Steam generator tubes that have imperfections greater than 40 percent through-wall as indicated by eddy current, shall be repaired by plugging or sleeving.
- 2. 6.1.2 Steam generator sleeves that have imperfections greater than 30 percent through wall as indicated by eddy current shall be repaired by plugging.
- 2. 6.2 Repairs by welded plugs and sleeves shall be performed in accordance with Section 12.
2.7 Scheduling
2.7.1 Eddy Current examination schedules of Steam Generator Tubes shall be established within Supplement 1, the Inservice Inspection Program. Plan.
2.8 Reports and Records:
2.8.1 Applicable records shall be maintained as specified within Section 1 and Section 12.
2.8.2 Within 15 days following the completion of the evaluation of each inservice inspection of tubes, the number of tubes required bysteam'enerator Paragraph 2 '.1 above to be plugged or sleeved in each steam generator shall be reported to the NRC in a Special Report.
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SECTION 11 ADDITIONAL Revision 5:
PROGRAMS Page 5 of 9 The complete results of the steam generator tube inservice inspection shall be submitted to the NRC in a Special Report within 12 months following the completion of the inspection. This Special Report shall include:
(a) Number of tubes inspected and extent to which inspected.
(b) Location and percent of wall-thickness penetration for each indication of an imperfection, and (c) Identification of tubes plugged or sleeved.
If the number of tubes in a generator falling into categories (a) or (b)- below exceeds the criteria, then results of the inspection shall be considered a Reportable Event pursuant to 10 CFR 50.73. Oral notification to the NRC Staff shall be accomplished within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, but no sooner than the next normal working day after the final review of the eddy current results. A written follow-up report shall. provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to preclude recurrence. .Categories (a) and (b) are:
(a) More than 10 percent of the total tubes inspected are degraded (imperfections greater than 20 percent of the nominal wall thickness). However, previously degraded tubes must exhibit at least 10 percent further wall penetration to be included in this calculation.
(b) More than 1 percent of the total tubes inspected are degraded (imperfections greater than the repair limit).
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SECTION 11 ADDITIONAL Revision g.::
PROGRAMS Page 6 of 9 3.0 Reactor Coolant Pump Flywheel Program:
3.1 General
The e'x'ig'in+% augmented inservice inspection program for Reactor Coolant Pump ."fR'C~P:: Flywheels incorporated the requirements of the USNRC Regulatory Guide 1.14, Revision 1, dated August. 1975, entitled "Reactor Coolant Pump Flywheel Integrity".
3.2 Examination Requirements:
3.2.1 Examinations shall be performed on 'all jn~S:,,:;alrieel Reactor Coolant Pump j(ROP)> Flywheels"p.fitns:('alii":dl~RGP; 3.3 Examination Method:
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3.3.1 Reactor Coolant Pump Flywheels shall be examined using Ultrasonic p'i~~VjOfi~tia'soli'c>IIIa'nd Sur face 'examination techniques.
3.3-I Examinations dj'Six'~'dpi'~~@'Steg~j3F~Y~ii"'shall conform to and be performed in accordance 'with Section 1 of, this program.
SECTION 11 ADDITIONAL Revision
$A 1.::
PROGRAMS Page 7 of 9 3.4 Frequency of Examinations:
3.4.1 Examinations shall be performed
. on all e$ %Ka~X1ed Reactor Coolant Pump Flywheel s once Ive'r!y.".~10.,-,";.ye~a'>~+~M 3.5 Examination Evaluation:
-3.5.1 Examination evaluations shall be performed in accordance with Section 1 of this program.
3.5.2 Unacceptable examinations shall be reported for evaluation and appropriate corrective action.
3.6 Repair, Replacement and Testing Requirements 3.6.1 Repairs and Replacements shall be performed in accordance with Section 12, as applicable.
3.7 Scheduling
.3.7.1 Examination schedules shall be established within Supplement 1, the Inservice Inspection Program Plan.
3.8 Reports and Records:
3.8.1 Applicable records shall be maintained as specified in Section 1 and Section 12.
bJ SECTION 11 ADDITIONAL Revision <7 PROGRAMS Page 8 of 9 4.0 Reactor Vessel Augmented Program, Category B-A:
4.1 General
As specified within the Federal Register, 10 CFR Part 50, Vol. 57, No. 152 dated August 6, 1992, a specific augmented examination program is required for ASME Section XI Category B-A, Shell Welds of "Pressure Retaining Welds in Reactor Vessel".
4.2 Examination Requirements:
4.2.1 Examinations shall be performed on all ASME Section XI Category B-A, Item B1.0, Shell Welds of "Pressure Retaining .Welds in Reactor Vessel" that are not e 4.3 required by the Code.
Examination Method:
I 4.3.1 Ultrasonic examinations shall conform and be performed in accordance with Section 1 of this program.
4.4 Frequency of Examinations:
4.4.1 Examinations shall be performed once during the Inspection Interval.
4.5 Examination Evaluation:
4.5.1 Examination Evaluations shall be performed in accordance with Section 1 of this program.
4.5.2 Unacceptable examinations shall be reported for evaluation and appropriate corrective action.
SECTION 11 ADDITIONAL Revision .::
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PROGRAMS Page 9 of 9 4.6 Repair, Replacement and Testing Requirements
- 4. 6.1 Repairs and Replacements shall be performed in accordance with Section 12, as applicable.
4.7 Scheduling
4.7.1 Examination schedules shall be established within Supplement 1, the Inservice Inspection Program Plan.
4.8 Reports and Records:
4.8.1 Applicable records shall be maintained as specified within Section 1 and Section 12.
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