ML20148L643
| ML20148L643 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/30/1987 |
| From: | Thornton A SOUTHWEST RESEARCH INSTITUTE |
| To: | |
| Shared Package | |
| ML20148L561 | List: |
| References | |
| PROC-871130, NUDOCS 8801280202 | |
| Download: ML20148L643 (83) | |
Text
PROGRAM PLAN FOR THE SECOND INSPECTION INTERVAL i Om FOR CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 i i
SwRI Project 171168 j l
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Prepared for Baltimore Gas and Electric Company Nuclear Energy Division Calvert Cliffs Nuclear Power Plant, Units 1 and 2 l Lusby, Maryland 20657 l l
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O Prepared by l
Nondestructive Evaluation Science and Technology Dhision Southwest Research Institute l
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November 1987 )
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l Approved by Unit 1 Commercial Operation - A. R Thornton, General Supenisor i May 8,1975 Plant and Project Engineering Senices Nuclear Engineering Services Department Unit 2 Co:nmercial Operation .
O April 1,1977 Nuclear Energy Dhision Baltimore Gas and Electric Company 8801280202 880114 PDR ADOCK 05000317 G PDR e
A TABLE OF CONTENTS J
em
- 1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Gen eral . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.2 Applicable Documents. . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.2.1 ASME Boiler and Pressure Vessel Code. . . . . . . . . . . . . . . . I 112 U.S. NRC Regulatory Guides .................... I 113 Technical Speci5 cations . . . . . . . . . . . . . . . . . . . . . . . 2 114 Regulatory Guide 1.147 Approved ARMR Section XI Code Cases . . . . 2 1.2.5 Relief Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.3 Responsibility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.4 Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.5 Rra mi nation Methods . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.5.1 Visual Ernmination Method . . . . . . . . . . . . . . . . . . . . . 2 1.5.2 Surface Rwamination Method . . . . . . . . . . . . . . . . . . . . 3 1.5.3 Volumetric R1a=In= Hon Method. . . . . . . . . . . . . . . . . . . 3 1.6 Inspection Intervals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1.7 Clamfication of Components. . . . . . . . . . . . . . . . . . . . . . . . . 4
- 2. CLASS I PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2.1 Rada for Preparation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2.2 Components Subject to Fr==Ination . . . . . . . . . . . . . . . . . . . . . 5 2.2.1 Vaaaala. .............................. 5 212 Piping . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2.2.3 Pumps............................... 5 l 214 Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 l 2.3 Exa m ption Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 I 2.4 Selection and Framination of Class 1 Piping Catqgory B-J . . . . . . . . . . . 6 2.5 CCNPP Technical Speci5 cation ....................... 6 2.6 Inservice Inspection Program Plan Tables . . . . . . . . . . . . . . . . . . . 6 1
- 3. CLASS 2 PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 3.1 Basis for Preparation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 l 3.2 Components Subject to Ernmination . . . . . . . . . . . . . . . . . . . . . 21 311 Vessels . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 312 Pi ping , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 il 1
m TABLE OF CONTENTS (Cont'd)
J Eun 3.3 Exemption Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 3.4 Selection of Ermmination of Class 2 Piping . . . . . . . . . . . . . . . . . . 22 3.5 Augmented ISI Program for Main Stnam and Main Feedwater Piping . . . . . . 22 3.6 Inservice Inspection Program Plan Tables . . . . . . . . . . . . . . . . . . . 23
- 4. CLASS 3 PROGRAM . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . 32 l
l 4.1 Basis for Preparation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 4.2 Components Subject to Ernmination . . . . . . . . . . . . . . . . . . . . . 32 4.3 Exem ption Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 4.5 Inservice Inspection Program Plan Tables . . . . . . . . . . . . . . . . . . . 33
- 5. CLASS 1, CLASS 2, AND CLASS 3 COMPONENT SUPPORTS . . . . . . . . . . . 36 5.1 Basis for Preparation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 )
5.2 Components Subject to R1=mination . . . . . . . . . . . . . . . . . . . . . 36 1 5.2.1 Plate and ShcIl Type Supports . . . . . . . . . . . . . . . . . . . . 36 i 5.2.2 Linear-Type Supports . . . . . . . . . . . . . . . . . . . . . . . . 36 5.2.3 Component Standard Supports. . . . . . . . . . . . . . . . . . . . 36 5.3 Exemptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36
, 5.4 Inaarvice Inspection Program Plan Tables. . . . . . . . . . . . . . . . . . . 36
- 6. BRTJEF REQUESTS AND CODE CASES . . . . . . . . . . . . . . . . . . . . . 39 6.1 Relief Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 6.2 ASME Code r.awa ............................. 39 1
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3 1. INTRODUCTION (Q
1.1 General This Program Plan outlines the second inspection interval inservice examination (ISI) requirements for Class 1, Class 2, and Class 3 systems and components for Baltimore Gas &
Electric Company's (BG&E) Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2. The second inspection interval begins on April 1,1987, for both units. As permitted by Paragraph BVA.2400 of ASME Code Section XI, the Unit 2 first interval conduded at the end of the spring 1987 refueling outage.
This plan was developed in accordance with the documents identified in Section 1.2 and prosides summary information outlining the ISI program for CCNPP for the second inspection interval.
This summaryinformation includes:
. Class 1, Class 2, and Class 3 systems e ASME Section XI aramination requirements of Subsections BVA, BVB, BVC, BVD, and nVF e Method and extent of nondestructive ernminations e Exemptions e Relief requests D e Special requirements 1.2 Applicable Documents BG&E has adopted the following documents as the basis for the second inspection interval and is committed to satisfying their requirements. This plan was developed in accordance with these documents:
1.2.1 ASME Boiler and Pressure Vessel Code Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,'
1983 Edition with Addenda through Summer 1983; the 1974 Edition with Addenda through Summer 1975 was used for selecting the extent of Class I piping welds only.
1.2.2 U.S. NRC Regulatory Guides i
e 1.14, Rev.1, "Reactor Coolant Pump Flywheel Integrity
- e 1.26, Rev. 3, ' Quality Group Classi6 cations and Standards for Water , Steam ,
and Radioactive-Waste-Containing Cornponents of Nuclear Power Plants'
. 1.147, "Inservice Inspection Code Case Acceptability ASME Section XI, Divi.
sion l' 1
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- e 1.150, Rev.1, ' Ultrasonic Testing of Reactor Vessel Welds During Presenice i and Insenice Examinations' 1.2.3 TechnicalSipecsl1 cations Paragraphs 4.0.5, 4.4.10.1.1, and 4.4.10.1.2 of the Technical Speci8 cations for Calvert Cliffs Units 1 and 2.
1.2.4 Regulatory Guide 1.147-Approved ASME Section XI Code Cases I
Code cases that will be utilized are contained in Section 6 of this document.
1.2.5 RelufRequests Proposed Relief Requests from ASME Code Section XI requirements are contained in Section 6 of this document.
1.3 Responsibility As speci8ed in Paragraph IWA 1400 of ASME Section XI, BG&E bears the overall respon-sibility for implementation of an ISI program. Quality Assurance Procedures, Calvert Cliffs '
Instructions, and NDE Programs and Plans are in place to control and implement these insenice inspection requirements.
1.4 Records Ernmination records and documentation of resulta provide the basis for evaluation and .
facilitate comparison with previous results and subsequent inspections. In accordance with Section XI, IWA 6000, these records will be maintained for the plant life.
1.5 Rraminatlan Methods Eramination methods which will be used to satisfy Code aramination requirements have ,
been listed for nonexempt Class 1, Class 2, and Class 3 components, as applicable. Provided l below is a brief explanation of the methods which will be performed to satisfy the Code requirements. Personnel performing nondestructive ernminations will be qualided in accordance with written procedures prepared as required by Paragraph IWA 2300 of ASME Code Section XI.
Methods of examination will be further described in the Long Term and Outage Examination ISI plans based on ernmination requirements, examination area access, joint configurations, and
, materials scheduled for examination.
1.5.1 visualEmmination Method Visual examinations (VT) will be performed in accordance with IWA 2210 of ASME Section XI. IWA 2210 dennes the four types of VT examinations as fo'!aws: l j I (1) VT 1 examinations are conducted to determine the condition of the part, component, or surface examined. The examination shall determine condi. .
tions such as cracks, wear, corrosion, erosion, or physical damage on the l surfaces of the part or components. This type of examination may be l performed by direct or remote methods as de6ned in IWA 2211.
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p (2) VT 2 araminations are conducted to detect leakage (or abnormal leakage) from pressure retaining components during system pressure or functional V tests as defined in nVA-2212.
(3) VT-3 oraminations are conNeted to determine general mechanical and structural conditions of components and their supports such as the presence of loose parts, debds, or abnormal corrosion products, wear, erosion, corro-sion, and the loss of integdty at bolted or welded connections as deuned in RVA-2213.
(4) VT-4 axaminations are conducted to determine conditions related to opera-bility of components or devices, such as mechanical and hydraulic snubbers, components, supports, pumps, valves, and spring loaded and constant weight hangers as defined in IWA 2214.
1.5.2 Surfaa Exammation Method A surface aramination is performed to detect the presence of surface cracks or discontinuities. Techniques for surface examination include either magnetic particle (MT) or liquid penetrant (PT) techniques where the surface conditions, material, and accessibility permit.
Surface examinations will be conducted as denned in IWA 2220.
1.5.3 Volumetric Examination Method A volumetric e.rnmination is performed to detect discontinuities in the volume of a material. Such volumetric examinations include radiographic (RT), ultrasonic (UT), and eddy
/G current (ET). Volumetric examinations will be conducted as defined in nVA 2230, b For volumetric examinations of piping and vessel components, use of the UT method is emphasized over RT for the following reasons:
(1) RT imposes restrictions that UT does not. For example, radiation levels associated with RT often necessitate evacuation of the examination area.
This can extend outage time significantly.
(2) In many locations, background radiation levels would preclude RT examination.
(3) Preservice examinations (PSI) were conducted utilizing UT techniques. In order to correlate PSI data with ISI data, the same examination method should be used.
(4) UT examination provides more spacial information relative to determining flaw aspect ratios.
The UT examinations may be performed by utilizing either manual or mechanized UT (Mech UT) techniques.
1.6 Inspection Intervals The examinations and system pressure testa required by BVA, BVB, BVC, and RVD shall be completed during each inspection interval for the service lifetime of CCNPP. In accordance 3
with IWA-2400, BG&E has elected to perform these examinations under Inspection Program B of O IWA 2420. This inspection program is de5ned as follows:
1st inspection Interval 10 years following initial start of power unit commercial operation 2nd Insnection Interval 10 yean following the 1st inspection interval 3rd insoection intenal 10 years following the 2nd inspection interval 4th Insoection Interval 10 years following the 3rd inspection interval It should be noted that the nrst inspection interval for Unit I was extended to April 1, 1987. The purpose of the extension was to place the ISI programs of both units on the same year and addenda of Section XI.
Each inspection interval may be decreased or extended (but not cumulatively) by as much as one year. If CCNPP is 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.
1.7 Cimanification of Components The program plan components and piping have been classided by BG&E for purposes of inservice inspection based on de5nitions contained in 10CFR50.2 and Regulatory Guide 1.26, Rev. 3.
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m 2. CLASS 1 PROGRAM L
2.1 Basis for Preparation Preparation of the Class 1 ISI program was based on the requirements of Articles BVB 1000 and IWB-2000 of Section XI. These articles provide rules and guidelines for exemp-tions, inspection schedules, and examination requirements for Class 1 pressure retaining compo-nents and their integral attachments.
2.2 Components Subject to Examination Based on the requirements of Section XI, the following Class 1 systems' nonexempt pressure retaining components and their integral attachments will be subject to examination dudng the second inspection interval:
2.2.1 Vessels Reactor Pressure Vessel Pressurizer Steam Generators (Primary Side) 2.2.2 Piping Reactor Coolant System Pressurizer Surge Line O Shutdown Cooling System O SafetyInjection System Pressurizer Spray System Pressurizer Safety and Relief System Charging Lines Letdown Lines Drain Lines 2.2.3 Pumps l
Reactor Coolant Pumps 1 2.2.4 Vahes Safety Injection System Pressurizer Spray System Shutdown Cooling System Pressurizer Safety and Relief System Charging Lines Letdown Lines 2.3 Exemption Criteria In accordance with BVB 1220, certain Class 1 components are exempt from examination.
The following criteda were applied to exempt components from surface and volumetric examina- ,
tions in accordance with Section XI:
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Exemotion Critelia Code Refetente
( Piping of 1 inch nominal pipe IWB.1220(b)(1) size (NPS) and srnaller, except for steam generator tubing Components and their connections IWB.1220(b)(2) i in piping of 1 inch NPS and smaller 2.4 Selection and R===ia-don of Class 1 Piping Category B4 i
, As permitted by 10CFR50.55a(b)(2)(ii), pressure retaining welds in Class 1 piping will be selected in accordance with the 1974 Edition of ASME Secdon XI with Addenda through Summer 1975. This provision provides facilities with construction permita docketed prior to July 1, 1978, the ability to retain continuity in ongoing insenice inspection programs to an extent considered practical and acceptable. j l
Welds selected to be examined will satisfy the extent required by the enteria in ASME l i Section XI 1974 through Summer 1975. Newly adopted enteria will be considered and may be i utilized provided they are consistent with ASME Section XI 1974 through Summer 1975 and the :
Class 1 pressure boundary piping rules and regulations applied during construction and previous inspections of Calvert Cliffs.
This provision does not apply to other areas of Section XI such as exemption criteria, !
examination methods, or acceptance standards; these areas will be governed by ASME Section XI i 1983 through Summer 1983 Addenda. l 2.5 CCNPP Tachnie=1 E=aina=+ian Requirements In accordence with Paragraph 4.4.10.1.1 of the CCNPP Technical Specifications, the Reac. !
tor Coolant Pump Flywheels shall be examined per the recommendations of Regulatory Position i C.4.b of Regulatory Guide 1.14, Rev.1. These examinations shall be scheduled in the Class 1 section of the ISI program.
2.6 Inservice Inspection Program Plan Tables I 1
Provided in Table 1 are examination requirements for Class 1 components per the 1983 l Edition of Section XI with Addenda through Summer 1983. These requirements shall be satisfied
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during the second inspection interval. Preceding Table 1 is an explanation of the table. i
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l Table I i SCIIIIMH CODE CIASS t Iscm Examination Canponents and Parts To Be Examination Examination Requirements for Examination Technique / Examination j k Category Examined Method Second Inspection interval Arca Comments ;
4
- he ASME Section XI Each type of examination area De NDE method his column prondes information regarding the num- His column prondes information specific to cxamina-
]
-- required to be 3 Item h and Category is lated in this column. required to satisfy ber and/or percent of c. tion techniques and examination areas.
of the componer,: are Code requirements performed for the inspection interval 3 lated in those columns. is listed in this column. ,
t a ,
b -
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t I
1
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k i t 6
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D Tabic 1 INSERVICE INSPECllON PROGRAM CIASS I COMPONINIS Isem Enamenasion Components and Paris To He Essaunasion Esammation Requerennenes for P===a==sion Technique /Esammatson No. Category Esamsoed Method Second inspecison Interval Arca Cosiments 1
RI%r*fDR PRI SSIIRl8 VIMI I,
]
i Bl.10 It-A Grcumferential and Imag audinal Voluenetric 100% of one ciscuanfercatial and one longptudinal Examination of longitudinal and circumferential shcE 151.1 1 ShcIl Welds weW so be esamseed at structural descontinuity in welds will be performed with Ur techniques.
Bl.12 the IWa=e region. Esasnimations miay be perfonned at or scar the cad of the inspection interval.
Bl_20 RA Oscuanferential and Meridsonal Volumetric ' Die accessable Icagth of one ascridional and one immer head and closure head wcWs will be examiiaco i Hl.21 ficad Wclds circusefcreatial weld of each Inced so be c===aaed utikring Ur acchniques.
, 31.22 t'=-=* ions may be performed at or near the end of each inspection interval for the lower Incad.
111.30 B-A Shell-to-Hange WeW Voluenetric 100% of the acid to be esamened. At least 50% of "Die shen to flangeweld will be examined froen the she weW shall be esasmened isoen the flange face by vessel scal surface and frosn the vessel waB inside the cod of the first inspectson period and the sistface with UT. ,
remnasader by the end of the third inspection period.
om Bl.40 B-A Head-so-Hange WeW Volusmetric and 100% of the weW to be czamuned. ' Die head-so-flange wcld will be exaansned with Ur Surface and surface e=-maios seclineques when the head is removed.
Bl.50 B-A Repair Welds N/A No repair welds at Calvent Oiffs.
Bl.51 50 30 &D Norric-so-Vesel Welds and Volemmetric 10D%of nozzles. At least 25% but not anose than "Die norzie-so-vessel welds and nozzle inside radius . i 10.100 ED Nozzle Inside Radius Sectson 30% of the =ar*= shall be esammaed by the end of sectsons will be c=h wah Ur. First period t;ne first period and the re===ader by the cod of the requeremocnes satisfacd desting the first interval 10-year inserval. esaamanation.
t IM.10 BE Partial Peaceration Welds: Visual (VT-2) At least 25% of each group of wehls of .- , _
F===.masion win be perfornied during the syseesa IM.II Vessel Norries size and functson to be czanniacd. hydsostatic test. VTer . hions will be perfonned 84.12 Coatsel Rod Drive Nozzles in accordance with IWA-5240. 'Diere are eo partial IM.13 lastruancesasion Nozzles peaceration vessel mozzle wcids at Calvert Ostfs.
'n45.10 B-l' Pressure-Retaining Denssesler N/A No danssauler mictal welds on RPV at Calvert Ostfs.
115.2 0 Metal Welds H5.30 1 6.10 EG-1 Oosuse liced Nues >2 Inches in Surface 100% of nues so be emaeused. F=m=amasaw many be Nues win be exanniacd with Mrwhen removed for Deasncter perfonned at or near the cod of the inspection refueling, interval.
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Tabic 1 INSERVICE INSPECHON PROGRAM CIASS 1 COMPONENI5 (Cont'd) face Ihamination Cosnponents and Parts To Be lhamination Esamination Requirements for Esamination Technique /thamination Na Category Ihamined Mctiums Second Inspection Interval Arca Comments Rf:ArinH PRI'NslTRI? VI'SSf 7I (Cont'd)
IE20 nG-1 Ckmure IIcad Studs,In Place, Volumetric 100% of studs to be emanuncd. Esamination may be Oosure stud c h may be performed *an
>2 Inches in Diameter performned at or near the end of the inspection place." Ihannimations should be scheduled when studs interval are removed to reduce radiation exposure and allow the anost thorough examination. Code Case N-307-1 shall apply. See Scctma &
IEJO ILG-1 Osure ficad Studs,When Volumetric and 100% of studs to be cansmened. F=amamation may be De studs will be examaned with IIT and Mr. Code Recnowd, >2 Inches in Diameter Surface perfonned at or acar the end of the inspection Case N-307-1 shall apply. Sec Section &
interval IE 40 ILG.1 Dreadsin Hange >2 lachesin Volumetric 100% of thecaded hoics to be emannimed. Examination De threads in flange will be czamined from the Diameter snay be performed at or near the cod of the flange face with LTr.
inspectson interval 50 RE.50 IkG-1 Pressure-Retaining Ooss e Vasual(VT-1) AM washers and bushings to be cza.msned upon stud Washers and Bushings >2 Inches resnovel. Esamanation samy be perforened at or acar in Diameter the end of the inspection interval B7.10 IkG.2 Pressure-Petaining Botting Vasumi (VF-1) AM bolts, studs, and nuts to be esamused. De botting sney be enamined in place under acasaan 12 Inches in Diameter or whcm A<Md or renwwed.
B7.Ito IkG-2 CRD Ilousings Holts, Studs, and N/A No pressuse-r-*aining CRD housing bolting at Calvert Nuts Omffs.
HR.10 Ikli InteFral Attachments for RPV N/A No integrally welded attachancats on RPV at Calvert Chffs that unect the requirements of Category B-II.
B1110 IkN-l VesscIInterior Visual (VT-3) Accessibic areas to be czaw duringcach inspection period.
Bl3 0 IkN-2 Interior Attachaients Wiehin Visual (VT-1) Accessibic attachment welds to be esamened.
DcIslanc Region F=-sions may be cosapleted at or near the cad of -
the inspection interval H1360 ikN-2 laterior Attachancats Beyond Vasual (VT-3) Accessable attachancat welds to be cumanened.
Dculane Region F==== anions aney be conspicted at or near the cad of the insp-ction interval i
. _ _ _ _ _ . .-. . __ ___ _ . _ _ _ . _ . . . . _ . . . _ _ _ _ _ _ _ . _ m . _ _ _ _ _ _ _ _ . _ _ _ ___ _ _ . __
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Table 1 1
INSERVICEINSPFfi1ON PROGRAM CIASS I COMPONINI5 (Cont'd) .
Item !!aamination Camponcats and Parts To Itc Esamenation F=-ion Requircaments for l' -ion Tectanique/I'ammination No. Category Esamined Method Second Inspection Interval Arca Commcats FIMrinR PRIMURI' VI5Wf, fCorit'd) -!
l i B13.">0 RN.3 Core-support Structure Visual (VT-3) with cose-support structure reasoved,aN accessable ;
surfaces to be c====w. F=-ions may bc l 1 cosapleted at or near the end of the inspection [
t intervat.
4 B14.10 15- 0 Control Rod Drive floussag Welds Voluenetric or Welds in 10% of the peripheral CRD bousangs to be line CRD boissang welds will be esaaniced with Fr.
Surface esasnined. F ' - anay be performed at or See Reisef Request No. 3 to perform equivalcat length >
near the end of the inspection inscrual. ofweld.
i HIS to ILP All Pressure-Retaining IL ==i= ries Visual (VT-2) All components to be e=w during syssese leakage VTe - ' - will be performed in accontence i
for Vessel Composeents test. s'- - ' - to be performed in accordance with IWA-5240.
with IWE5221 prior to plaat startup after cach refaccias outase-i y H15.11 EP All Preuere-Retaining Houndaries Visual (VT-2) AN compoecess to be examened during system Vre- ' - will be perfornacd in accordance o for Vesact Comepoacnes hydsessatic test. Famamammaions to be perfornoed in with IWA-52CO.
accosdance with IWES222 at or near the end of the -
inspection interval P
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Table 1 INSERVICE INSFECI1ON PROGRAM CIASS 1 COMPONINI5 (Cont'd)
Inca Examination Gunponents and Parts To He Faamunation Esamunation Requisements for F===== tion Technique /I'samination Nou Casegory Esamened Mc hod $ccond Inspection laserval Area Commcats PRfMURI7FR 112.10 iH Circoniferemaial and longitudenal Volumetric 'Ile upper and louer het welds to be F===nsassion will be perfonned with IR techniques.
B2.11 Shcu-no-licad Wclds essaused. One foot of one longisudunal weld
, 112.1 2 insenecting each head-toebell weld to be exannened.
152.2 0 BB Grcusnferential and Meridional Volumetric One cascumferential and one mesidaa==a weld on Fa== man =eion will bc pedonned with IR scchasques.
112.21 licad Welds cach head.
112.2 2 R1110 H-D Nor21e-to-Vessel Welds and Voluencarie All nourie-so weasel welds and inside radius sections F=======sions will be perfonned with IR techniques.
Bil20 Nor21e laside Radius Sections so be esanused. At least 25% but not miose than 50%
of the actries shall be c=h try the end of the first period and slie remanader by the cad of the inspection imeesval.
U B4.20 B-H IIcascr Fenetration Welds Vinesi (Vr-2) AN psessunser hesser penetration welds messal be VTc
- wiu be pedonned in accosdance with t eh during syneem '_,2 sest in accosdesce IWA-5240.
! with IWB-5222 at or scar the end of the inspection imeesval B5.40 B-F Norrie-to6sfc End Diesasneler Surface and AM best weeds so be e======ed F ' - will be perfonned with Fr a.ad LK Metal Welds 14 Inches NPS Volissneeric w' ,
H5 5C H-F Norric-to-Safe End Dessamuler Surface AN butt melds so be esamuned. Esmansnations will be perforened with Fr acchasques.
Metal Welds <4 Inches NPS R$ho B-F Norrle-to-Safe End Socket Welds N/A No dessamster sectal socket welds on pressunzer at Calvert Cliffs.
H660 B41-1 Fressure-Retaining Hotting N/A No bolting os pressanser >2 inches is diammeter at
! IE70 >2 Inches in Diameter Calvert Cliffs.
D6.80 H7.20 B41-2 Boats,Souds,and Nuts <2 laches Visual (Vr-1) Am boar ., useds, and muss so be esmanened. Boliing e % may be performed in place in Dianneser under session or when d===esibled or removed.
. IslL20 B-Il leecgraNy Wclded Attacismenes Volumectric or Psessenser support skist so be e=M F=======eion wiu be perfonned per Hgure Surface IWB-250014.
4 I
4 i +
._, _ _ . _ _ . , _ , _ _ . ~ . _ - . _ , - . . , . _ . _ .
. - - -- . - . - . . _ . _ _ . _ . - . . .. ~ - - _ - . . .-. - . . . - - -
4 L
Table 1 ,
i 1
INSERVICEINSPECIlON PROGRAM l C1 ASS I COMPONIINI5(Get'd)
Incen Esamination Components and Paits To lie Examination I'=awion Requirements for Emanunation Technique /lbasination No. Category Esamined Method Second Inspection Interval Arca Comments t
j PRIMUR f7FR (Cont'd)
Illi20 BP Premure-Retaining Iloundancs %sual(VT-2) AN presseruct componenes so be c=*d during Vressmanation will be perfornico in accordance with for Vesact Components sysica IcaLage ecst. Emanunation so be performed in IWB-5240.
accordance with IWB-5221 prior to plant stastup ;
afect cach refuchng outage.
i 151121 Il-P Pressure-Retaining floundaries Visual (VT-2) All pressurizcr componenes to be examsned dunng Vrenamenation will be performed in accordance with f
for Vessci Cornponents system hydsostseie test Esamination to be performed IWA-5240.
in accordance wish IWB-5222 as or near the end of the inspection interval I
i 1
M 23 I
i l
4 i
i L
k 1
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i, I
3 _ _ _ _ _ __ _ _ _ - - - __ _ _. -__ _ _ . .. .. -- ._- - - .- -
w w d
Table 1 INSERVICE INSPECI1ON PROGRAM ,
CIASS I COMPONENIS(Cont'd) lica Examination Consuments and Parts To De F.samunation Esamenation Requirements for Emannimation Technique / Examination Na Cairgory Esamined Methant Sccond Inspection Interval Arca Comments EIFAM Gf NFRA1DRS H230 Ikil Circumicreatial and Merkleonal Voluenctne One cascunnicreasial and one meridional wcld was be Examinations wiH be pedonned with ITT techniques.
H231 WeIJs is abe louver IIcad c= ====ed he c- - ' -
4= win be linoised to one 18232 of the two sacans generators per unit.
82.40 1L18 Tubcshect-to-1Icad Wckt Volumetric De tubenhect-to-head weld wiu be czannened. De F-asion wdl be pedonned with ITT scchniques.
c- ' - will be knused to one of the two secam generosors per unit.
E11130 ILi) Norrie-so-Vessel Welds and Volumesric Au nozzle-coalmen welds and norde inside radius Esaminations wis be perfonned with 170 techasques.
B1140 Nozzle Inside Radsus Sections acetions will be e====ed At least 25% but not mosc than 50% of the nozzles shaN be czannened by the end of the first inspection period and the semanider by the end of the inspectson interval U H5MO ILF Nozzic-so-Safe End Dissimilar N/A No desanneler smetal norde welds on steam generasors B520 Metal Wchts at Calvert Omffs.
H5.90 i
IE90 IL G 1 Pressure-Retaining Boliing N/A No boleing on secam generators >2 inches in diameter IE100 >2 Inches in Diameter , at Calvert Osils.
Int 10 H730 ILG-2 Iblis,Seuds, an1 Nues12 Inches Visual (VT.I) AE hotts, studs, and nues wal be emaassmed. Femmaamsinna may be pesionned in place under tension in Dianneter or when removed.
H830 ILII lasegrally Wclded Attachenenes Surface De weasel support skist wiR be esammened. De Emanunations win be perforuned per Figure e- ^ ' - will be lismised to one sacans generator. IWB-2500-13.
I81530 H-P Pressure-Retaining Boundaries Visual (VT-2) All secans genersoor components so be czamined VTe ' - win be performed in accordance denng syssem leakage test. Enamenations to be with IWA-5240.
perfonised in accordance with IWB-5221 prior to plant startup after cach sefuehag outagc.
H1531 ILP Pressure. Retaining Houndaries Visual (VT-2) AE *== generseer cosaponents to be c===amed VTc '= will be pedonned in accordance with during sysica hydsontanic test. F - - C o t be IWA-5240.
pedonned in accoedanne wish IWB-5222 at or near the end of the inspection interval.
H16.20 B0 Sacam GcacrosorTubing Voeusnetric De tubing in the hot leg side, t.Muend portion, and Framammaana requirements, examinatson method,and opsiamany cokt leg sade will be evannened. Else entent and frequency of examinatiosi shau be ia accordance with plant Tcchnical Speciracations.
i
. . . . . _ . _ _ _ . - __ .__ . _ . _ - -_ _ .m___ .
_ ._._ _ m _ . _ . _ _ . _ ._ .
I i
1 4
i Tabic 1
} INSERVKE LNSPPCI1ON PROGRAM s
] CIASS 1 COMPONIWI5 (Cont'd) 4 Item I'armination Consponcats and Parts To He Esamsameion n- a= " , --t for Essassention Techasque/Emmassation Na Casegory Esassened Method Secued Inspection Ineerval Asca Cusamcats lil'ATI'XOIANGFRS H2.50 H-H licad Wclds N/A No Osas I heat enchampes at Calvert OJfs. Sacasa H2.51 yacrosorsac acparately.
H2.52 H240 H-H Tubcabecteliced Welds N/A NOsas I heat e * . --at Calvert CMis.
H2.70 H-B I.ongituJsaal Welds N/A No Omss 1 kat enchangers at Calvert Odts.
H2.80 ILH Tubenhect-soShell Welds N/A N Osas I heat eschemyss at Cnevert Odts.
H3.150 H-D Noorte-so.Venact Welds N/A No Osas I heat enchampes at Calvert Odfs.
H3.160 Il-D Norrie lanide Radeus Sectina N/A N Osas I heat enchemyss at Calvert Odts.
Z H5.300 Il-P Pressere.Renasmeng Denssaanier N/A N Osas 1 heat enchangers at Calvert Odts H5.110 Metal Welds H5.13
~
le6.120 BG.I Pressurc-Retasasag Holesag N/A No Osas I best enchenprs at Caevert Odis.
D6.130 >2 Inches in Dammeser 146.140 B7.40 H-G.2 Holes, Stude, and Nets 12 laches N/A No Osas I heat cachemyrs at Calvert Odfs.
in Dammeter Hs.40 EII lasegrally Weided Attachascoes N/A No Osas I heat enchampes at Calvert Odis.
Il15 40 Ikr Fucanure-Retasseng Houndernes N/A N Oscs I heat enchanyss at Calvert Ostfs.
Ht5.41 4-
_ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ . . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . . _ . _ - _-_ _ _ _-m _-_._._.____._-_.___ _ _ _ _ .m-m______ -
___-__m-__---___m___.m. _ _ _ _ _ _ . _ _ _____
O J Table 1 l
INSERVICE INSPECI1ON PROGRAM CIASS 1 COMPONINIS (Cont'd)
Item Examination Components and Parts To Bc Examination Examination Requirements for Examination Technique / Examination No. Category Examined Method Second Inspection Interval Area Comments
, PIPING B1130 ILP Dissimilar Metal Welds 24 Inches Volumetric and All butt welds to be examined. 'Ihc welds will be examiacd with UF and IT.
NPS Surfxe B5.I40 B-F Dissimilar Metal r/clJs <4 Inches Surface All butt welds to be examined. 'Ihc welds will be examined with FT.
NPS B1150 IkF Dissimilar Metal Socket Welds N/A No dis 6imilar metal socket welds at Calvert Chrts.
14 150 B-G-1 Pressure-Retaining Bolting N/A No pressure-retaining botting >2 inches in diameter 14160 >2 Inchesin Diameter at Calvert Cliffs.
IE 170 B7.50 IkG-2 Pressure-Retaining Bolting Visual (VF-1) All bolts, studs, and nuts to be examined. 'Ihe botting may be exa,ined in place under acasion 12 Inches in Diameter or when disassembled or removed.
cn B9.10 IFJ Circumferential Pipe Welds Volumetric and 25% of the required circumferential butt welds to be "Ihc piping welds will be examined with UT and FT IW.11 14 Inches NPS Surface examined. See Note 1 at end of Tabic 1 for selection or Mras appbcable. Sec Relici Requrst Nou 1 for !
criteria. welds in reactor vessel annulus area.
B9.12 ILJ longitudinal Pipe Wclds14 Inches Volumetric and longitudinal welds that adjoin scheduled 'Ihc piping wclds will be exammed with Ur and FT NPS Surface circurnferential welds are to be examined. One pipe or Mras applicable. See Relief Request No.1 for diameter not to exceed 12 inches of each longitudinal welds in reactor vessel annulus area.
wcld length required.
IW.20 B.J Circumferential Welds <4 Inches Surface 25% of the required circumferential butt welds to be 'Ihc piping welds will be examined with FTor MT as B9.21 NPS examined. See Note 1 at end of Table 1 for selection applicabic.
j criteria.
IW.22 B.J tongitudinal Pipe Welds <4 Inches Surface longitudinal welds that adjoin scheduled 'Ihc piping welds will be examined with FTor lWI'as NPS circumferential welds are to be examined. One ppe applicabic.
diameter of each longitudinal wcld length required.
11930 lbJ Branch Pipe Connection Welds Volumetric and 25% of the required branch conne'1 ion joints to be 'Ihc branch connection welds will be cza.nined with B931 14 Inches NPS Surface exanuned. See Note 1 at end ofTabic 1 for selection Urand Fror MTas applicable.
criteria.
B932 B.J Branch Pipe Connection Welds Surface 25% of the required branch connection joints to be The branch connection welds will be cramined with
<4 Inches NPS examined. See Note I at end of Tabic 1 for selection FTor Mras applicable. j i
criteria. -
IW.40 Ib3 Socket Welds Surface 25% of the required socket welds to be examined. 'Ihc socket welds will be examined with Tor MT as See Note I at end of Table 1 for selection criteria. applicable.
L-___--___- - . _ _ _ - _ _ _ - _ _ _ - - - _ _ _ _ _ _ _ _ . .__ _ - _ _ __ _ _ _ _ _ _ - _ __.__ __ __ - _ _ _ _ _ _ __ __ _ - _ __ _ _ - __ _ _ _ _ _ _ _ _ - - _ . _
i T
a 1
Table 1 INSERVICE INSPECITON PROGRAM CIASS I COMPONFETS(Cont'd) ;
Item Examination Components and PartsTo Be Examination Examination Requirements for Emamination Technique / Examination Na Category Examined Method Second Inspection Interval Arca Comments i
PIPING (Cont'd)
B10.10 IFK-1 Integrally Weided Attachments Volumetric or All required supports te be examined. See Note 2 at The integrally welded attachments will be examined Surface end of Tabic 1 for selection criteria. with FT, MT, or UT as applicabic. l j BI530 B-P All Pressure-Retaining Boundaries Visual (VT-2) All components to be examined during system leakage VT examination vill be performed in accordance with ,
] for Piping Components test. Examination to be performed in accordance IWA-5240.
with IWB-5221 prior to plant startup after cach rcfueling outage.
BI531 lbP Ali Pressure-Retaining Iloundaries Visual (VT-2) All components to be examined during system Vrenamination will be performed in accordance with !
- for Piping Components hydrostatic test. Examination to be performed in IWA-5240.
accosdance with IWB-5222 at or near the end of the inspection interval l
1 M I as I
i r 1
t 4
N
, V d Table 1 INSERVICE INSPECI1ON PROGRAM C1 ASS 1 COMPONINI5(Cont'd)
Item Examination Cornponents and PartsTo De Examination Examination Requirements for Examination Technique / Examination No. Category Examined Method Second Inspection Interval Arca Comments Pt NPS l IE 180 141 Bolas and Studs, >2 Inches in Volon tric A!! bolts and studs to be examined. The botting wiu be examined with UT. Code Case Diameter N-307-1 shall apply. Sec Section ik "Ihc botting may be examined in place unden tension or when ,
disassembled or =cmoved.
IE190 141 121ange S2. face for Boldag Visual (VT-1) Examination includes 1 inch annular surface of flange
>I Inches in Diameter When around each stud hole surface when dkaternbied.
Connection Is DisassemS!cd IE200 B-G-1 Nuts, Bushings, and Washers Visual (VT-1) All nuts, bushings, and washers to be examined when
>2 Inchesin Diameter ^<=urmbled.
H7.60 B-G-2 Prenure-Retaining Botting Visual (VT-1) All bolts, studs, and nuts to be examined. The botting may be examined in place under tension
~<2 inches in Diameter or when disassembled or removed.
w q
U10.20 D-K-1 IntegrallyWeided Attachments Volumetric or AI! required attachments to be examined. See Note 2 Weided attachments win be examined with I'T, MF, Surface at end of Table 1 for selection criteria. or UT as applicabic-D12.10 IL1-1 Pulip Casing Welds Surface and Reactor coolant pump casing welds excmpt from "Ihe suppicmental examinations will be performed Visual See volumetric czamination. See Relief Request h 2. with VT and I'T techniques. See Rchef Requcs:
Relief Request A supplemental visual and surface examination will No.2.
M 3. be performed on one pump.
H12.20 B.I-2 Internal Surfaces of Pump Visual (VT-3) One reactor coolant pump to be examined when Pump casing internal surface will be examined with Casings disassembled. See Relief Request h 2. visual techniques when dk=nembled. A best possible inspection will be performed recognizing that the configuration obstructs visualinspection. See Relici Request & 2.
B1514 B-P Pressure-Retainicag Boundarecs Visual (VT-2) All components to be examined during system leakage Vrexaminations will be performed in accordance for Pump Componcets test. Examination to be performed in accordance with IWA 5240.
with IWB-5221 prior to plant startup after cach refucting outage.
D15 61 B-P Pressure-Retaining Hotadarics Visual (VT-2) All components to be examined during system VT examinations will be performed in accordance for Pump Components hydrostatic test. Examination to be performed in with IWA.5240.
accordance with IWB-5222 at or near the end of the inspection interval 1
. l l
Cw Table I LNSERVICE INSPECIlON PROGRAM CIASS I COMPONINIS (Cont'd)
Item Examination Conponents and Pans To Ee Examination Examination Requirements for Examination Technique / Examination No. Category Enamined Method Second Inspection laterval Area Comments PI JMPS (Cont *J)
N/A N/A Pump flywbecis Surface and Each reactor coolant pump flywhcci to be examined Examinations will be performed with MF and UT Volumetric per CCNPPTechnical Specification (see 2.4 of techniques.
Program Plan). Iligh-stress areas to be examined each period with full examination at the end of interval 5
l
s Table 1 INSERVICEINSPECI1ON PROGRAM CIASS 1 COMPONFNI5(Cont'd)
I l Item Examination Components and PartsTo Bc Examination Examination Requirements for Exammation Techniquefthamination
. No. Category thamined Method Second InspectKm Interval Area Comments J
VAI, VIN IM.210 IkG-1 Bolting >2 Inches in Diameter N/A No valve bolting >2 inches in diameter at Calvert IM.220 0 ffs.
B&230 B7]O ILG-2 Botting <2 Inches in Diameter Visual (VT-1) AII bolts, studs, and outs to be examined. The bolting may be examined in place under tension or when disassembled or removed.
B1030 ILK-1 IntegrallyWelde.d Attachments Volumetric or All required attachments to be examined. See Note 2 Welded attachments will be examined with FT, MT,
, Surface at end of Table 1 for selection criteria. or UT as applicabic.
B12.30 ikM-1 Pressurc-Retaining Welds in Surface One valve in cach group of valves that is of the Valve welds will be examined with FTor MT as Valve Ilodies <4 Inches NPS same construction and similar function to be applicabic.
examined.
5 B12.40 B-M-1 Pressure-Retaining Welds in N/A No pressure-retaining wclds in valw bodics >4 inches Valve Bodies >4 Inches NPS NTS at Calvett Oaffs.
B1230 B-M-2 Internal Surfaces of Valve Dodies Visual (VT-3) One valve in cach group of valves that is of the on Valves >4 Inches NPS same construction and similar function to be examined.
B15]O B.P AllPressure-RetainingBoundaries Visual (VT-2) All components to be examined during system Icakage VT cxaminations will be performed in accordance for Valve Caunponents test. Examination to be performed in accordance with IWIL5240.
with IWB-5221 prior to plant stattup after cach refueling outage.
B15.71 ikP AII Pressurc-Retaining Boundaries Visual (VT-2) All components to be examined during system VT czaminations will be performed in accordance for Valve Components - hydrostatic test. Examination to be performed in with IWA-5240.
accordance with IWB.5222 at or near the end of the inspection interval I
9
h i 1
l 1 Table 1 - norms (1) Examinations shall be datnbuted throughout the piping system to satisfy the extent required by ASME Section XI 1974 Edition with Addenda through Summer 1975 as permitted by 10CFR5035a(b)(2)(ii). Examinations selected shall be distributed in such a mannct to include:
, (a) Terminal ends in cach pipe or branch run connected to vessels.
- i (b) Terminal ends and joints in cach pipe or branch run connected to other components.
(c) All arcas where preservice examination revealed analytically acceptable flaw indications.
(d) All areas where inscrwice examination revealed additional analytically acceptable flaw indications.
(c) Additional piping welds so that the total number of circumferential butt welds (or branch connection or socket welds) selected for examination equals 25% of the circumferential butt welds (or branch connection or socket welds) in the reactor coolant piping system. This total does not include welds excluded by IWB-1220. These additional welds will bc ,
dhtributed between the loops.
(2) Examination is limited to those integrally wcIded attachments that meet the following ~~klaac I
(a) the attachment is on the outside surface of the pressure-retaining component; (b) the attachment psovides component support as defined in NP-11I&,
(c) the attachment base material design thickness is 5/8 inch or gres* ; and (d) the attachment wcid joins the attachment either directly to the su. face of the component or to an integrally cast or forged attachment to the component. i o
Examinations include the wclded attachments of piping required to be examined by Examination Category B-J and the wclded attachments to associated pumps and valves integral to such piping, t-4 d
l O 8. c'^ss 2 raoonix 3.1 Basis for Preparation l
Preparation of the Class 2 ISI program was based on the requirements of Articles BVC-1000 and BVC-2000 of Section XI, Code Case N-408, and Plant Technical Specifications.
These documents provide rules and guidelines for exemptions, inspection schedule, and examina-tion requirements for Class 2 pressure-retaining components and their integral attachments.
3.2 Components Subject to Framination Based on the requirements of Section XI, nonexempt pressure-retaining components and their integral attachments for the following Class 2 systems will be subject to volumetdc and/or surface examination dudng the second inspection interval:
3.2.1 Vessels Steam Generators (Secondary Side)
Shutdown Cooling Heat Exchanger Regenerative Heat Exchanger 3.2.2 Piping Safety Injection System Containment Spray System O Shutdown Coo'Jng System V Main Steam Symm Feedwater System 3.3 Exemption Cdteria nVC-1220 of Section XI provides the exemption critada for Class 2 components. Code Case N 408 will be implemented, which provides alternative exemptions for Class 2 components and replaces BVC-1220. The following critena were used to exempt Class 2 components from surface and volumetric examinations in accordance with Code Case N-408.
3.3.1 The following components (or parts of components) of Residual Heat Removal (RHR), Emergency Core Cooling (ECC), and Containment Heat Removal (CHR), systems (or por-tions of systems) are exempt from the volumetdc and surface a:nmination requirements of RVC 2500:
(1) vessels, piping, pumps, valves, and other components 4 inches NPS and smaller in all systems except in high pressure safety injection systems of pressunzed water reactor plants; (2) vessels, piping, pumps, valves, and other components 11/2 inches NPS and smaller in high pressure sefety injection systems of pressurized water reactor plants; (3) component connections 4 inches NPS and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other b
21 l
I l
l components of any size in all systems except in high pressure safety injec-tion systems of pressurized water reactor plants; (4) component connections 11/2 inches NPS and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size in high pressure safety injection systems of pressurized water reactor plants; (5) vessels, piping, pumps, valves, other components, and component connections of any sizo in statically pressudzed, passive (i.e., no pumps) safety injection systems of pressurized water reactor plants; (6) piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions.
3.3.2 The following components (or parts of components) of systems (or portions of systems) other than RHR, ECC, and CHR systems are exempt from the volumetric and surface ornmination requirements of RVC 2500:
(1) vessels, piping, pumps, valves, and other components 4 inches NPS and smaller; (2) component connections 4 inches NPS and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size; V (3) vessels, piping, pumps, valves, other components, and component connections of any size in systems or portions of systems that operate (when the system function is required) at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200 F; (4) piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions.
3.4 Selection and R=nination of Class 2 Piping Selection and ornmination of Class 2 piping will be in accordance with the requirements of Code Case N 408. These requirements are outlined as follows:
3.4.1 For welds in austenitic stainless steel or high alloy piping, the requirements of Table 1, Eramination Category C-F 1, ' Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping," shall be used as an alternative to the requirements of Table BVC-2500-1 Category C F.
3.4.2 For welds in carbon or low alloy steel piping, the requirements of Table 2, Exam-ination Category C-F-2, "Pressure Retaining Welds in Carbon or Low Alloy Steel Piping,'shall be used as an alternative to the requirements of Table IWC-2500-1 Category C.F.
O .
22
l l
l p l t 3.5 Augmented ISI Program for Main Steam and Main Feedwater Piping In accordance with the Technical Specifications for CCNPP, an augmented ISI program will be implemented for Main Steam and Main Feedwater Piping. This program requires examination of the unencapsulated welds greater tha,n 4 inches NPS located outside the containment and traversing safety areas.
The required welds will be ernmined in accordance with the rules of the 1983 Edition of Section XI with Addenda through Summer 1983, except that 100 percent of the welds will be scheduled for ernmination during each interval. If araminations reveal rejectable indications, an additional one-third of the welds shall be aramined. If additional rejectable indications are revealed in the second sample, the remainder of the welds shall be examined. The inspection schedule for repaired welds shall revert to the original program. The examinations performed by this augmented program shall not be used to satisfy allocations of ASME Section XI required examinations on other portions of the system.
3.6 Inservice Inspection Program Plan Tables Provided in Table 2 are aramination requirements for Class 2 IWC components per the 1983 Edition of Section XI with Addenda through Summer 1983 and CCNPP Technical Specifica-tions. These requirements shall be satisfied during the second inspection interval. Preceding Table 2 is an explanation of the table format.
(D V
l l
O v
23 l
%s Table 2 SOIEME 4 !
CODE C1 ASS
. Item Examination Components and Parts To Bc Examination Examination Requirements for Examination Technique / Examination h Category Examined Method Second Inspection Interval Arca Comments i.
] The ASMEScction XI Each type of examination area De NDE method his column provules information regarding the num- This column provules information specific to examina-j Item h and Category is Insted in this column. required to satisfy ber and/or percent of examinations required to be tion techniques and examination areas.
of the component ase Code requirements performed for the inspection interva!.
Inted in these columns. is listed in this column.
f 1
l N 6 A
- 1 L
I, l
- l j i s
i i
4
we r ,
Tabic 2 INSERVICE INSPECI1ON PROGRAM f
i CIASS 2 COMPONTNIS Item Exac'ination Components and Parts To Be Examination Examination Requirements for Examination Techniquc/ Examination No. Category Examined Method Second Inspection Interval Arca Comments j PRFSNURI? VIMSFIS C1.10 C.A ShcIl Circumfercatial Welds Volumetric 100% of cach wcld to be examined (applies only to The welJs will be examined with IJr.
wekts at gross structural discontinuitics). For multi-plc vessels of similar design size and service, exam-inations may be limited to one vesscL C120 C.A IIcad CircumferentialWelds Volumetric 100% of cach head-to4hcIl wcld to be examined. For 'Ihc welds will be examined with IJr.
multiple w:ssels of similar design size and service, examinations may be limited to one vesset C130 CA Tubcsheet-to-ShcIl Weld Volumetric 100% of each wcid to be examined. For multiple The welds will be examined with IJr.
vessels of similar design size and service, cramina-tions may be tunited to one vesscL C2.10 CD Nozzics in Vessels 11/2-Inch Surface All nozzles at terminal ends of piping runs which are The welds will be examined with Mror Fr as to C2.11 Nominal'Ihicioness Nozde-to- sciccted for examination under Categories CF-1 and applicable.
- CF-2.100% of each wcld to be examined. Manways ShcIl(or IIcad) Weld and hand holes excluded. For multipic vessels of similar design, size, and service, examinations may be limited to one vesscL C2.20 GB Nozzics Without Reinforcing Surface and All nozzles to be selected at terminal ends of piping The welds will be examined with IIT and MT or rr C2.21 Plate in Vessels >1/2-Inch Nomi- Volumetric runs selected for examination under Categories CF-1 as applicabic.
nalThickness Nozzle-to ShcIl and CF-2.100% of each wcld to be examined.
(or IIcad) Wcid Manways and hand hoics excluded. For multiple vessels of similar design, size, and service, cramina-tions may be limited to one vesscL
.i e C2.22 GB Nozzle Inside Radius Section Volumetrie 100% of each arca to be examined. Manways and The nozzle inside radius section will be examined i
hand hoics are excluded. For multipic vessels of with (Jr.
similar design, size, and service, examinations may be limited to one vesscL C230 GB Nozzles with Reinforcing Plate in N/A There are no nozzics with reinforcing plate in vessels C2.31 Vessels > t/2-Inch Nominal >1/2. Inch nominal thickness at Calvert C1Rs.
C232 'Ihickness !
C233
a
\
, % )
Table 2 INSERVICE INSPECI1ON PROGRAM CIASS 2 COMPONINIS (Cont'd)
Item Examination Components and Parts To Be Examination Examination Requirements for Examination Technique / Examination Na Category Examined Method Second Inspection Interval Area Comments PRf'SNI JR13 VI SSI'I S (Gmt'd)
C3.10 GC Integrally Wckled Attachments Surface 100% of each wekt to be examined. Attachments 'Ihc wekled attachments will be examined with MT whose base m :crialis 3/4 inch or greater to be or PT as applicabic.
selected. Wlwre multipic vessels are provated with a number of similar attachments, the attachments may be distributed among the vcascis. For multiple vessels of similar design and service, examinations may bc limited to onc vesscL C4.10 CD Pressure-Retaining Bolting N/A No pressure-retaining vessel botting >2 inches in
>2 Inches in Diameter diameter at Calvert Chffs.
C7.10 C-II Pressure-Retaining Components Visual (VT-2) All pressure-retaining boundaries for vessels to be Vrexaminations will be performed in accordance examined during system pressure test. Examinations with IWA4240.
to be performed in accordance with IWC 5221 for y each inspection period.
C7.20 C-II Pressur> Retaining Components Visual (VT-2) All pressure-retaining boundaries for vessels to be Vrexaminations will be performed in accordance examined during system hydrostatic test. Examina- with IWA-5240.
tions to be performed in accordance with IWC-5222 at or near the end of cach inspection interval or during same inspection periods of each interval
\
Table 2 INSERVICEINSPECI1ON PROGRAM CIASS 2 COMPONINIS (Cont'd)
Item !!xamination Components and PartsTo Be Examination Examination Requirements for Examination Technique / Examination No. Category Examined Nethod Second Inspection Interval Arca Comments PIPING l O .20 GC Integrally Wcided Attachments Surface 100% of each wcld to be examined. Attachments ne welds will be examined with MTor IT as whose base material is 3/4 inch or greater to be applicable.
selected. Selection limited to those components selected under Examination Categories GF-1 and GF-2.
C4.20 CD Pressure-Retaining Bolting N/A No pressure-retaining bolting > 2 inches in diameter
>2 Inches in Diameter at Calvert Giffs C110 G F-1 Piping Wclds in Austenitic Stain- Surface and 100% of each circumferential and 23 of each longi- He welds will be examined with IIT and PT, Scice-C5.11 less Stect or Ifigh-Alloy Piping Volumetric tudinal wcld requiring examination. See Note I at tion and examination will be in accordance with O .12 3 1/8-Inch Nominal WaIIDickness cad of Table 2 for scicction criteria. Code Case N40iL See Section 6.
for Piping >4 NPS,Grcumferen-tialand Longitudinal
-a C120 C F-1 Piping Welds in Austenitic Stain- Surface and 100% of cach circumferential and 2.5t of each longi- %c welds will be examined with UT and Fr. ScIcc-C121 less SacciorIligl> Alloy Piping Volumetric tudinal weld requiring examination. See Note 1 at tion and cammination will be in accordance with C5.22 11/5-Inch Nominal WalI%ickness end ofTable 2 for selection criteria. Code Case N-408. Scc Section 6.
for Piping 12 NPS and 54 NPS, Greumferentialand longitudinal C130 C F-1 Socket Wclds in Austenitic Stain- Surface 100% of each wcld requiring examination. See Note 1 %c welds will be examined with PT. Selection and Icss Stect or Iligh-Alloy Piping at end of Table 2 for selection criteria. cxamination will be in accordance with Code Case N40tL See Section 6.
C140 GILI Pipe Ilranch Connections in Surface 100% of cach circumferential and 25t of each longi- He welds will be czamined with PT. Selection and C141 Austenitic Stainicas StecI or tudinal wcld requiring examination. See Note 1 at examination will be in acconsance with Code Case N-C5.42 Iligh-Alloy Piping 12 NPS, Gr- cad of Table 2 for selection criteria. 408. See Section &
cumferential and longitudinal C5.50 G F-2 Piping Wckts in Carbon or low- Surface and 100% of each cinumferential and 2.5t of each longi- %c welds will be examined with UTand MT. Scice-C5.51 Alloy Sacell3/8-Inch Nominal Volumetric tudinal wcld requiring examination. See Note 2 at tion and curmination wdl be in accordance with C5.52 WallThickness for Piping >4 cad of Tabic 2 for selection criteria. In addition, Code Case N-40tL See Section 6.
NPS, Greumferential and longi- 100% of the main steam and main feedwater welds tudinal located outside containment and traversing safety areas shall be examined per CCNPP Technical SpeciG-cations (see 2.4 of Program Plan).
I O N s I
v Tabic 2 INSERVICE INSPECITON PROGIbut CIASS 2 COMPONENIS (Cont'd)
Item Examination Components and Parts To Uc Examination Examination Rcquirements for Examination Technique / Examination No. Category Examined Method Second Inspection Interval Arca Comments PIPING (Cont'd)
O 60 CF-2 Piping Welds in Carbon or low- N/A Selection and examination wn!! be in accordance C541 Alloy Stect >l/5-Inch Nominal with Code Case N-40tL See Section 6. Nocarbon or C542 Wall 1hickness for Piping 22 low-alloy stect nonexempt wekss in this categosy at NPSand <4 NPS,Circumferen:ial Calvert Cliffs.
and longitudinal C5]O CF-2 Socket WelJs in Carbon or low- N/A Selection and czamination will be in accordance with Alloy Secci Code Case N-40tL See Section 6. No carbon or low-alloy secci nonexempt welds in this category at Calvert Oiffs.
C5.80 CF-2 Pipe tiranch Connections in Surface 100% of cach circumferential and 2.5 of each longi- "Ihc welds will be examined with IWF. Sclection and C5.81 Carbon or low-Alloy Stect12 tudinal wekt requiring examination. See Note 2 at examination will be in accordance with Code Case C5.82 NPS, Greumferential and longi- cod of Table 2 for selection criteria. N-40tL See Section &
@ tudinal C730 CII Pressure-Retaining Components Visual (VT-2) A!! pressure-rctaining boundaries for piping to be VT cxaminations will be performed in accordance examined during system pressure test. Examination with IWA-5240.
to be performed in accordance with IWC5221 for cach inspection period.
C7.40 CII Pressurc-Retaining Components Vaual(VT-2) AII pressure-retaining boundarics for piping to be VT czaminations will be performed in accordave examined during system hydrostatic test. Examination with IWA-5240. Reference Relief Request No. 4.
to be performed in accordance with IWC5222 at or See Section &
near the end of each inspection interval or during same inspection periods of each intervat
)
- Table 2 INSERVICE INSPECIlON PROGRAM i CIASS 2 COMPONFNI3 (Cont'd) r I
- Incm Examination Components and Parts To Inc Examination Examination Requirements for Examination Technique / Examination i No. Category Examined Method Secom. wction Interval Arca Comments ,
i PtNis ;
C330 C-C Integrally Wclded Attachments N/A 100% of each wcld to be examined. Attachments whose base material is 3/4 inch or greater to be
. selected. Scicction limited to those components selected under Examination Category CG. No pumps ,
meet this criteria at Calvert Oiffs. !
3 C430 CD Pressure-Retaining Bolting N/A No pressure-retaining pump botting >2 inches in [
>2 Inchesin Diameter diameter at Calvert Ostfs.
C&l0 CG Pressure-Retaining Welds in N/A No pressure-retaining pump welds at Calvert 0 ffs.
Pump Casings ,
i C7.50 CII Pressure-Retaining Components Visual (VT-2) All pressure-retaining boundaries for pumps to be VT examinations will be performed in accordance examined during pressure test. Framinerinn go be with IWA-5240.
@ performed in accordance with IWCS221 for each inspection period.
C720 Cll Pressure-Retaining Components Visual (VT-2) AII pressure-setnining boundanes for pumps to be VTexaminations will be performed in accordance examined during system hydrostatic test. Examination with IWA-5240.
fj to be performed in accordance with IWC5222 at or near the end of each inspection interval or during same inspection periods of each interval 1
e i 4
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i i
N % O s J U '
Table 2 INSERVICE INSPECIlON PROGRAM CIASS 2 COMPONENI5(Cont'd)
Item Examination Components and PartsTo Be Examination Examination Requirements for Examination Technique / Examination ;
No. Category Examined Method Second Inspection Interval Area Comments VAI VFS i
- CL40 GC IntegrallyWclded Attachments Surface 100% of cach weld to be examined. Attachments The welds will be examined with MI' or IT as I
whose base material is 3/4 inch or greater to be applicabic.
selected. Selection limited to those components selected under Examination Category GG.
C4.40 CD Pressurc-Retaining Botting N/A No pressure-retaining bolting > 2 inches in diameter
>2 Inchesin Diameter at Calvert Cliffs.
C&20 GG Pressure-Retaining Welds in Surface 100% of welds in components in cach piping run The welds will be examined with MT or IT as Valve Hod.cs examined under Examination Categories GF-1 and applicabic.
GF-2. In case of multiple valves of similar design, size, function, and service in a system, the examination of only one valve is required.
c4 C730 GII Pressure-Retaining Components Visual (VT-2) All pressure-retaining boundaries for valves to bc VT examinations will be performed in accordance O i cramined during system pressure test. Examination with IWA-5240. '
to be pciforracd in accordance with IWG5221 for cach inspection period.
C180 GII Pressure-Retaining Components Visual (VT-2) All pressure-retaining boundaries for valves to be VT cxaminations will be performed in accordance examined during system hydrostatic test. Examination with IWA-5240.
to be performed in accordance with IWG5222 at or near the end of cach inspection interval or during sarne inspection periods of each interval.
J V v
)
Tabic 2 - NOTES (1) "Ihc welds selected for caamination sha!I include 75%, but not Icss than 28 welds, of all austenitic stainicss steel or high-alloy welds not exempted by this Case. (Some welds not exempted by this Case are not required to be nondestructively examined per Examination Category CF-1. 'Ihese welds, however, shall be included in the total wcld count to which the 73% sampling rate is applied.) 'Ihc examinations shall be distnbuted as follows (a) the examinations shall be distnbuted among the Class 2 sprems prorated, to the degree practicabic, on the number of nonexempt austenitic stainless steel or high-alloy welds in cach system (i c.,if a system contains 30% of the nonexcmpt welds, then 30% of the nondestructive examinations required by Examination Category CF-1 should be performed on th.st spacm);
(b) within a system, the examinations shall be distnbuted among terminal ends [see Note (3)] and structural discontinuities [sce Note (4)] prorated, to the degree practicabic,on the nunaber of nonexempt scrminal ends and structural discontinuitics in that system; and (c) within cach system, examinations shall be distnbuted betweca line sizes prorated to the degree practicabic.
(2) 'Ihc wclds selected for examination shall include 73%, but not less than 28 welds, of a!! carbon or low-alloy welds not exempted by this Case. (Some welds not exempted by this Case are not required to be nondestructively cramined per Examination Category CF-2. 'Ihese wclds, however, shall be included in the total wcld count to which the 73% sampling rate is app!kd.)
"Ihe examinations shall be dhtributed as follows-(a) the examinations shall be dhtnbuted among the Class 2 systems prorated, to the degree practicable, on the number of nonexcmpt carbon or low-alloy welds in cach system (i.c.,if a system contains 30% of the nonexempt welds, then 30% of the nondestructive examinations required by Examination Category CF-2 should be performed on that system);
(b) within a system, the craminations shall be dhtributed among terminal ends [sce Note (3)] and structural discontinuitics [see Note (4)] prorated, to the degree practicabic, on the number of nonexcmpt terminal ends and structural ducontinuitics in that system; and (c) within cach system, examinations shall be distributed between linc sizes prorated to the degree practicabic, s-a (d) Only those wclds showing reportable preservice transverse indications need to be examined for transverse reflectors.
(3) Terminal ends are the extremitics of piping runs that connect to structures, components (such as vessels, pumps, valves), or pipe anchors, cach of which acts as a rigid restraint or pro-vides at least two degrecs of transitional restraint to piping thermal expansion-(4) Structural discontinuitics include pipe wcld joints to vessel nozzscs, valve bodies, pump casings, pipe fittings (such as cibows, tees, reducers, flanges, cie., conforming to ANSI B16.9), and pipe branch connections and fittings.
- 4. CLASS 3 PROGRAM O
4.1 Basis for Preparation Preparation of the Class 3 ISI program was based on the requirements of Articles BVD-1000 and nVD-2000 of Section XI. These articles provide rules and guidelines for exemp-tions, inspection schedules, and examination requirements for Class 3 pressure-retaining compo-nents and their integral attachments.
4.2 Components Subject to Rnmination Based on the requirements of Section XI, pressure-retaining components and their integral attachments for the following Class 3 systems will be subject to examination during the second inspection interval:
Auxiliary Feedwater System Shutdown Cooling System Component Cooling System Service Water Cooling System Salt Water System Spent Fuel Pool Cooling System 4.3 Exemption Criteria In accordance with nVD 1220, certain Class 3 components are exempt from examination.
The following exemption criteda were applied to Class 3 systems as specified in IWD 1220:
Exemntion Criteria Section XI Reference Integral attachments of supports and restraints to compo. IWD-1220.1 nents that are 4 inches NPS and smaller within the system boundaries of Enmination Categories D A, D-B, and D-C shall be exempt from the VT-3 examination, except for Auxiliary Feedwater.
Integral attachments of supports and restraints to compo- nVD-1220.2 nents exceeding 4 inches nominal pipe size may be exempted from the visual examination VT-3 of Table nVD-2500-1 provided:
(a) the components are located in systems (or portions of systems) whose function is not required in support of reactor residual heat removal, contain-ment heat removal, and emergency core cooling; and (b) the components operate at a pressure of 275 psig or less and at a temperature of 200 degrees F or less.
O V
32
l 4.5 InserviceInspeedon % Plan Tables O
I Provided in Table 3 are examination requirements for Class 3 IWD componente per the- l 1983 Edition of Section XI with Addenda through Summer 1983. These requiremants shall be satisfied during the second inspection interval. Preceding Table 3 is an explanation of the table format.
l 1
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1 Tabic 3 SCIIEME
- CODE CIASS Item Examination Components and PartsTo De Examination Examination Requirenwnts for Examination Technique / Examination
& Category Examined Method Second Inspection Interval Area Comments ne ASMESection XI Each type of examination area De NDU method his column prtmdes information regarding the num- his column provides information specific to examina.
, item h and Category is listed in this column. required to satisfy ber and/or percent of czaminations required to be tion techniques and examination areas.
of the ccmponent are Code requirements performed for the inspection interval Inted in theu: columns. is listed in this column.
i i
t 2
l 4
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Table 3 i
INSERVICE INSPECI1ON PROGRAM CLASS 3 COMPONENIS Item Examination Cornponents and Parts To Be Examination Examination Requirements for Examination Technique / Examination Not Category Examined Method S%.cond Inspection Interval Area Comments 1
D1.10 D-A Pressure-Retaining Con;ponents Visual (VF-2) All components to be examined during system picssure VT cxaminations will be performed in accordance D110 D-Il or sysicm hydrostatic test. Examination to tm per- with IWA-5240. Sec Relief Request No.5 for modirmed D110 D-C formed in accordance with IWD-5221 for cach inspec- system inservice pressure test in lieu of system tion period and performed once cach interval in hydrostatic test for some systems.
accordance with IWD-5221 DI.20 D-A Integral Attachments of Supports Visual (VT-3) All required attachments to be examined during cach The integral attachments will be examined.
through and Restraints,Ilydraulic Snub- inspection interval For multipic components in a Dl/4 bcrs, Spring, Constant Imad, system of similar design, function, and service, the '1 D120 IKil and Shock Absosters integral attachment of only one of the multipic com-through ponents shall be examined. The integral attachments D240 selected shall correspond to those support components D120 D-C selected for exarnination in accordance with through IWF-2510(b).
D360 4
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p 5. CLASS 1, CLASS 2, AND CLASS 3 COMPONENT SUPPORTS V
5.1 Basis for Preparation Preparation of the component support ISI program was based on the requirements of Articles IWF.1000 and IWF-2000 of Section XI. These articles provide rules and guidelines for exemptions, inspection schedules, and examination requirements for Class 1, Class 2, and Class 3 component supports. Inservice test requirements for snubbers shall be conducted in accordance with Technical Specifications which shall supersede the requirements of Article IWF-5000. The snubber inservice test program is excluded from this Program Plan; it is addressed in other surveillance test programs.
5.2 Components Subject to Rramination Based on the requirements of Section XI, no;> exempt component supports for the Class 1, Class 2, and Class 3 systems identified in Sections 2.2, 3.2, and 4.2 of this plan will be subject to examination dudng the second inspection interval. The component supports requiring exami-nation shall be classified as follows:
5.2.1 Plate and Shell Type Supports Supports which are fabricated from plate and shell elements, such as vessel skirts and saddles, and are normally subjected to a biaxial stress.
5.2.2 knear-Type Supports Supports acting under essentially a single component of direct stress. Such elements may also be subjected to shear stress. Examples of cuch structural elements are:
tension and compression struts; beams and columns subjected to bending; tnisses; frames; arches; )
rings; and cables.
5.2.3 Component Standard Supports A support assembly consisting of one or more generally mass-produced units usually referred to as catalog items. Enmples of such items are shown in Figure IWF 1210-1 of Section XI.
5.3 Exemptions ASME Section XI,1983 Edition with Addenda through Summer 1983, does not contain defined exemption criteria for component supports.
5.4 Inservice Inspection Program Plan Tables Provided in Table 4 are examination requirements for Class 1, Class 2, and Class 3 compo-nent supports per the 1983 Edition of Section XI with Addenda through Summer 1983. These requirements shall be satisfied during the second inspection interval. Preceding Table 4 is an explanation of the table format, a
36
1, 1
't i
l Table 4 J
j SCIIEME CODE CIASS Item Examination Componepts and Parts To Ile Examination Examination Requirements foc Examination Technique /Examin. tion
& Category Eumined Method Second Inspection Interval Arca Comments i
The ASMESection XI Each type of examination area De NDE method his column petmdes information regarding the num- his column provides information specific to examina-
! Item % anJ Category is lated in this column. required to sathfy Int and/or percent of examinations 1: quired to be tion techniques and examination areas.
l of the component are Code requirements performed foc the inspection interval 4
Ihted in thcac columns. is lated in this column.
n i
?
1 T
Ca3
+ 4 i
O I
I E
1 l
4 1
4 i
i i
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Table 4
- INSERVICE INSPECITON PROGRAM I
CIASS 1, CIASS 2 AND CIASS 3 COMPONINF SUPPOKIS Inca Examination Componcats and PartsTo lle lhamanation Eramination Requirements for Examination Techniqu-/ Examination No. Category Examined Method Second Inspection Interval Area Comments il PI KIU AND SilFI f.TYPf! St IPPOKIX I INFAR "IYPE SUPPORT 3. AND COMPONPNT STANDARD SUPPORIS
, Ft.10 F-A Mcchanical Connections to Pres- Visual (VT-3) Component supports to be selected for examination Functional testing of snubber type support components l through se6re-Retaining Cosnponents and and for spring, are the supports of the nonencept Class 1,2, and 3 shall be performed in accordance with Technical FIA0 liusading Structure; Weld Connec- constant load, components scheduled to be examined. Examination Specifications under a separate surveillance program.
12.10 F-il tions to Building Structure, Wcld shock and snubber boundaries established in accordance with IWF-1300.
through and Mechanical Connections at type Examinations may be performed during normal system F2A0 Intermediate Joints in Multi- Visual (VT-4) operation or plant ousages.
I").10 F-C connected Integral and Non-thsuugh integral Supports; and Component 1150 Displacement Scttings of Guides and Stops, Misalignment of Supports, Assembly of Support Items; SpringType Supports; Constant load Type Supposts; Shock Absosbers;IlydraulicType Snubbers l
4 1
i 4
.l
)
l 4
i 1
i
. _ _ . - . _ - . _ . _ . _ _ . _ _ . . - . _ _ _ . _ _ _ - - _ _ _ . . _ _ . _ _ _ _ _ _ _ _ . - . _ - _ _ _ - a_ _ _ _ . _ _ _ _ _ _.
- 6. RELIEF REQUESTS AND CODE CASES 6.1 ReliefRequests In accordance with 10CFR50.55a(g)(5)(iv), BG&E has requested relief from those AShE Section XI requirements that have been determined impractical for certain areas. This. section summarizes each Relief Request submitted to the NRC for consideration. Each request provides information on the component for which reliefis requested, ASME requirements, proposed alter-nate method, and other pertinent information, as needed. Additional Relief Requests will be submitted to the NRC as appropriate, Table 5 presents a summary of the enclosed Reliet Requests.
6.2 ASME Code Casm In accordance with 10CFR50.55a, footnote 6, ASSE Section XI Code Cases referenced in Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability-AShE Section XI, Disi-sion 1,' may be incorporated into the Calvert Cliffs ISI Program. Those Code Cases included in Regulatory Guide 1.147 that will be irnplemented at Calvert Cliffs are identified in this sec-tion. Each Code Case is preceded by information on the applicable component / area, ASAE requirements, and how the Code Case will be implemented. Additional Code Cases will be included as appropriate.
Table 6 presents a summary of Regulatory Guide 1.147 Code Cases that will be used.
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T Table 5 ,
SUMMARY
OF RELIEF REQUESTS Relief ASME Requirement Proposed Request Section XI for Which Relief Reason for Alternate Number Reference Component Is Recuested Relief Recuest Eramination 1 IWB-2500-1 42* and 30' Reactor Surface Dimcult access Surface examination Cat.B,J Coolant Pipe Welds from the outside using UT technique in Reactor Vessel surface and pro- from inside surface.
Annulus hibitive radiation environment.
2 IWB 25001 Reactor Coolant Pump Volumetric of mse Pump conaguration Hydrostatic test, sur.
Cat. B-1,1, Case Welds and welds and visual of and material face, and visual examina B-I,2 Internals internals tions of outside surface of one pump.
3 IWB-2500-1 Welds in CRD Housings 10% (three) peripheral Portions of all CRD Surface examinadon on Cat.B-O CRD housings (surface) housing welds are nye CRD housing welds inaccessible due to to compensate for inac-closure head mn. cessible portions.
Oguration-4 IWA-5000, Portions of Class 2 Class 2 Hydrostatic Some Class 2 por. Perform hydrostatic IWC-5000 HPSI, Aux HPSI, and Pressure Test every tions annot be iso- pressure testa to LPSI 10 years lated from Class 1 Class Ihydrostatic due to check valve pressure requirements.
Isolations.
5 IWA 5200, Class 3 Portions of Hydrostatic Test every These systems can. Perform system IWD-5200 Component Cooling, 10 years not be practically . inservice pressure Service Water, and Isolated. testing annually in lieu Salt Water Coollrg of hydrostatic test.
O 40
l ISI RELIEF REQUEST 1 RELIEF FROM SURFACE EXAMINATION ON SPECIFIED B-J PIPfNG WELDS LOCATED IN REACTOR VESSEL ANNULUS ,
1 L Components for Which ReliefIs Requested The components for which relief is requested consist of the 42* and 30' Reactor Coolant System piping welds that are scheduled to be examined using mechanized UT and are located in i the reactor vessel cavity annulus. These pipe welds are identified below:
UNIT 1 Line Weld Typs 42 RC-11 1 Nozzle-to-Transition Piece 42 RC-11 2 Transition Piece-to-Pipe 42 RC 11 2 LD 1 Longitudinal Scam 2 LD-1 Longitudinal Seam l 42-RC-12 1 Nozzle to-Transition Piece 1 42 RC 12 2 Transition Piece-to Pipe l 42-RC-12 2 LD-1 Longitudinal Scam 42 RC-12 2 LD-2 Longitudinal Seam 30-RC-11 A 12 LU 1 Longitudinal Seam ,
12 LU-2 Longitudinal Seam i 12 Elbow to Transition Piece 13 Transition Piece to-Nozzle 30-RC 11B 12 LU 1 Longitudinal Seam 12 LU 2 Longitudinal Seam 12 Elbow to-Transition Piece 13 Transition Piece to-Nozzle 1
30-RC-12A 12 LU 1 Longitudinal Seam 12 LU 2 Longitudinal Seam ,
12 Elbow to-Transition Piece l 13 Transition Piece-to-Nozzle 30 RC-12B 12 LU 1 Iongitudinal Scam 12 LU 2 Longitudinal Seam 12 Elbow-to-Transition Piece 13 Transition Piece-to Nozzlo O i 41 1
E .2 Line Weld Tyng 42 RC-21 1 Nozz'e-to-Transition Piece 42 RC-21 2 Transition Piece-to-Pipe 42 RC-21 2 LD 1 Longitudinal Seam 42-RC-21 2 LD 2 Longitudinal Seam 42-RC-22 1 Nozzle-to-Transition Piece 42 RC-22 2 Transition Piece-to-Pipe 42-RC-22 2LD1 Longitudinal Seam 42 RC-22 2 LD 2 Longitudinal Seam 30-RC-21A 12 LU 1 Longitudinal Seam 12 LU-2 Longitudinal Seam 12 Elbow to-Transition Piece 13 Transition Piece-to-Nozzle 30-RC-21B 19LU1 Longitudinal Seam 12 LU-2 Longitudinal Seam 12 Elbow to-Transition Piece 13 Transition Piece-to-Nozzle 30-RC-22A 12 LU 1 Longitudinal Seam 12 LU 2 Longitudinal Seam 12 Elbow-to-Transition Piece d 13 Transition Piece-to Nozzle 30-RC-22B 12 LU 1 Longitudinal Seam 12 LU-2 Longitudinal Seam 12 Elbow to Transition Piece 13 Transition Piece-to-Nozzle These welds are to be examined in accordance with the 1983 Edition of Section XI with Addenda through Summer 1983.
IL ASME Requirement from Which ReliefIs Requated The welds identified are classified as item B9.11 (Circumferential) and B9.12 (Longitudin-al), Category B-J. In accordance with Table IWB 2500-1, these welds require both a surface and volumetric examination of the areas shown in Figure IWB-2500-8. To perform the required surface examination on the weld crown and heat-affected zone, the examiners must gain access to the reactor vessel annulus area housing these reactor coolant piping welds. These areas are extremely difficult to enter, provide marginal room for mobility, and are very high radiation areas. It has been determined that a surface method examination of these welds, such as mag-netic particle (MT), is not practical and that an alternate method should be used. -
IIL Proposed Alternate Method
( As an alternate to performing a surface examination (MT), BG&E proposes to perform a 45-degree shear wave UT examination of the outside surface by utilizing mechanized ultrasonic 42
A techniques from the inside of the pipe or component. This examination has been qualified for i detection of unacceptable outside surface Daws that would otherwise be detected using MT.
tQ This will allow anmination of the entire circumference of the outside surface of the weld ,
while saving a significant amount of radiation exposure. -l In order to qualify this technique for Calvert Cliffs, Southwest Research Institute (SwRI) developed a mock up of the nozzle and pipe welds and induced cracks at specific locations on the inside and outside surfaces. The lengths and depths of these cracks were tightly controlled in order to allow the cracks to be used for qualification purposes Crack depths ranged from i 1/2 the maximum allowable Code flaw depth for the pipe thickness to the maximum allowable l Code Gaw depth. All Ga vs were less than the largest acceptable surface Gaw in length. The ;
cracks were then investigated with UT techniques (performed by SwRI) to the satisfaction of '
BG&E personnel to demonstrate that the largest acceptable surface Gaw could be detected with l this technique. l 1
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ISI RELIEF REQUEST 2 RELIEF FROM VOLUMETRIC AND VISUAL EXAMINATION OF REACTOR COOLANT PUMPS (Granted during FirstInterval)
(Ref: NRC approvalletter dated November 6,1985, from Mr. E. J. Butcher of the NRC to Mr. A. E. Lundvall of BG&E) 1 L Component for Which ReliefIs Requested ;
A NameandNumber Calvert Cliffs Unit i reactor coolant pumps #11A, #11B, #12A, and #12B and Calvert ;
Cliffs Unit 2 reactor coolant pumps #21A, #21B, #22A, and #22B. All pumps are identical in 1 design and function and are Byron-Jackson Type DFSS Reactor Coolant Pumps, Serial Numbers 681 N-0437 through 44, Size 35 X 35 X 43.
l B. Function Each Calvert Cliffs unit has four reactor coolant pumps which are welded to the 30' ,
l recirculation loop. These pumps function during normal reactor operation to provide forced recirculation through the core.
C Mh CurrentISI Class: Class 1 I
Original Design: ASME Code Section III,1965 Edition with Addenda through l Winter 1967, Class 1 IL Code Requirement from Which Relid Is Requested ASME Code Section XI 1983 Edition with Addenda through Summer 1983 examination categories B L 1 and B-L 2 require volumetric examination of casing welds and visual anmina-tion of internal pressure boundary surfaces of one pump casing in each of the pump groups performing similar system functions each inspection irterval. These enminations are impractical for the reactor coolant pumps at Calvert Cliffs Unita 1 sud 2 and reliefis, therefore, requested.
A SupportingInformation
- 1. The design configuration of the pump corresponds to a Type E pump illustrated I in Figure NB-3442.5-1 (1977 Edition, ASME Code Section III). No practical technique current]y exists to perform inservice inspection radiographic examina-tion (RT) or ultrasonic examination (UT) of this pump type.
- 2. The presence of the diffuser vanes precludes conventional RT. The vanes prevent placement of the RT film cassettes inside the pump (as does the radiation field In terms of radiographic film and personnel radiation exposure). Placement of the film on the outside of the pump is feasible, but there is no radiographic O. source suitable for placement inside the pump. Standard isotopic radiation 44
ISI RELEF REQUEST 2 RELEF FROM VOLUhETRIC AND VISUAL EXAMINATION OF REACTOR COOLANT PUMPS (Granted during First Interval)
(Ref: NRC approvalletter dated November 6,1985, from Mr. E. J. Butcher of the NRC to Mr. A. E. Lundvall of BG&E)
L Component for Which ReliefIs Requested A NameandNumber Calvert Cliffs Unit I reactor coolant pumps #11A, #11B, #12A, and #12B and Calvert Cliffs Unit 2 resctor coolant pumps #21A, #21B, #22A, and #22B. All pumps are identical in design and function and ara Byron-Jackson Type DFSS Reactor Coolant Pumps, Serial Numbers 681 N-0437 through 44, Size 35 X 35 X 43.
B. Function Each Calvert Cliffs unit has four reactor coolant pumps which are welded to the 30' recirculation loop. These pumps function during normal reactor operation to provide forced recirculation through the core. .
C Mh Current ISI Class: Class 1 Original Design: AShE Code Section E,1965 Edition with Addenda through Winter 1967, Class 1 IL Code Requirement from Which ReliefIs Requested AShE Code Section XI 1983 Edition with Addenda through Summer 1983 namination categories B-L 1 and B-L-2 require volumetric ernmination of casing welds and visual examina-tion of internal pressure boundary surfaces of one pump casing in each of the pump groups performing similar system functions each inspection interval. These examinations are impractical for the reactor coolant pumps at Calvert Cliffs Units 1 and 2 and reliefis, therefore, requested.
A SupportingInformation
- 1. The design configuration of the pump corresponds to a Type E pump illustrated in Figure NB-3442.5-1 (1977 Edition, ASME Code Section m). No practical technique currently exists to perform inservice inspection radiographic examina-tion (RT) or ultrasonic examination (UT) of this pump type.
- 2. The presence of the diffuser vanes precludes conventional RT. The vanes prevent placement of the RT film cassettes inside the pump (as does the radiation field in terms of radiographic film and personnel radiation exposure). Placement of p the Sim on the outside of the pump is feasible, but there is no radiographic source suitable for placement inside the pump. Standard isotopic radiation u
p)
ISI RELIEF REQUEST 2 RELIEF FROM VOLUMETRIC AND VISUAL EXAMINATION OF REACTOR COOLANT PUMPS (Granted during First Interval)
(Ref: NRC approvalletter dated November 6,1985, from Mr. E. J. Butcher of the NRC to Mr. A. E. Lundvall of BG&E)
L Component for Which ReliefIs Requested A NameandNumber Calvert Cliffs Unit I reactor coolant pumps #11A, #11B, #12A, and #12B and Calvert Cliffs Unit 2 reactor coolant purnps #21A, #21B, #22A, and #22B. All pumps are identical in design and function and are Byron-Jackson Type DFSS Reactor Coolant Pumps, Serial Numbers 681 N.0437 through 44, Size 35 X 35 X 43.
B. Functwn Each Calvert Cliffs unit has four reactor coolant pumps which are welded to the 30" recirculation loop. These pumps function during normal reactor operation ta provide forced recirculation through the core.
O
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C. Code Class Current ISI Class: Class 1 Original Design: ASME Code Section III,1965 Edition with Addenda through Winter 1967, Class 1 IL Code Requirement from Which ReliefIs Requested ASME Code Section XI 1983 Edition with Addenda through Summer 1983 examination categories B L 1 and B-L 2 require volumetric examination of easing welds and visual examina-tion of internal pressure boundary surfaces of one pump casing in each of the pump groups performing similar system functions each inspection interval. These examinations are impractical for the reactor coolant pumps at Calvert Cliffs Units 1 and 2 and reliefis, therefore, requested.
A SupportingInformation
- 1. The design configuration of the pump corresponds to a TyTe E pump illustrated in Figure NB-3442.51 (1977 Edition, ASME Code Section IID. No practical technique currently exists to perform inservice inspection radiographic examina-tion (RT) or ultrasonic examination (UT) of this pump type.
- 2. The presence of the diffuser vues precludes conventional RT. The vanes prevent placement of the RT film cassettes inside the pump (as does the radiation field in terms of radiographic film and personnel radiation exposure). Placement of O the film on the outside of the pump is feasible, but there is no udiographic source suitable for placement inside the pump. Standard isotopic radiation 44
A sources are too weak to penetrate the thick casting, and background radiation
(') from the inside surface of the pump would diminish sensitivity. Special strong isotopic soure.es would be impractical to handle and position inside the pump due to personnel radiological exposure from the radiographic source itself. The recently developed Miniature Linear Accelerator (MINAC) was considered, but the Type E pump design precludes positioning of the accelerator inside the pump. Double-wall radiography utilizing the MINAC has also been considered with some hope of attaining meaningful radiographs of a portion of the casing welds. This technique has not been qualified to date and appears to be some time off,if at all possible.
- 3. The coarse grain structure inherent in thick stainless steel castings precludes the use of conventional UT. Future developments in ultrasonic techniques may '
provide a method to examine thick stainless steel casting, and, if developed, this would be preferred over the difficulties and dangers of thick wall radiog-raphy. We are hopeful that the Ultrasonic Data Recording and Processing system (UDRPS) technology may provide some breakthrough to stainless steel casting UT.
- 4. The pump casing is fabricated from cast stainless steel (ASTM A351, Grade CF8M). The materialis essentially a cast type 316 stainless steel. This material is widely used in the nuclear industry, and no industry failures of this type material in reactor coolant pumps have been noted. The presence of delta i ferrite (typically 15% or more) imparts increased resistance to intergranular l stress corrosion cracking GGSCC). The delta ferrite also improves resistance to pitting corrosion.
- 5. Report Number ERP 06-102, Revision 0, August 1983, prepared for the Electric Power Research Institute by NUTECH Engineers, Incorporated, concludes that:
- a. Based on the generic pump casing analysis, there is justification for the extension of the pump-casing mmination up to 15 years,
- b. Plant unique analysis will show greater margins of safety.
- c. The tearing modulus analysis shows that large, final Daw sizes can be tolerated in the pump casing before fracture is predicted,
- d. The recent 10-year inservice inspection of several pump casings (Type F) indicates no detectable Gaw growth from baseline inspections, which cor-roborates the above analytical conclusion.
- 6. Pump disassembly for the sole purpose of conducting a very limited visual mmi.
nation of the interior pressure boundary surfaces of a reactor coolant pump which, for the most part, has an as-cast surface texture is fruitless, particularly in light of the man hours and radiation exposure that would be expended.
- 7. Over 700 man hours and over 20 person-rem is estimated to disassemble, visu-ally inspect, and reassemble one reactor coolant pump. The man hour estimate is based only on onsite outaga work performed by maintenance, operations, and nondestructive testing personnel. The estimate does not include engineering O time or preoutage job planning. Additionally, man-hours and person-rem will be expended by radiation protection personnel providing direct coverage. The time 45
required to perform the disassembly and inspection would be approximately O 2 weeks of critical path time. Most of the work would be performed under full face mask conditions.
IIL Proposed Alternate Method As an alternative to the examinations required by Section XI, BG&E proposes to implement the followinginspection program:
A. The pump interior will be inspected to the extent practical (in recognition of the vanes therein) should the pump be disassembled for any other reason.
B. The reactor coolant pumps shall be hydrostatically tested per the requirements of ASAE Code Section XI.
C. A surface examination of one RCP in each unit shall be performed on the exterior casing weld surface areas by the liquid penetrant method once per interval.
D. A visual examination of one RCP in each unit shall be performed on the exterior pump case surfaces once per interval.
O O
46
ISI RELIEF REQUEST 3 ALTERNATIVE EXAMINATION FOR SURFACE EXAMINATION ON CONTROL ROD DRIVE HOUSING WELDS (Granted during FirstInterval)
(Ref: NRC approvalletter dated May 11,1987, from Mr. Robert A. Capm of the NRC to Mr. J. A. Tiernan of BG&E)
L Compotsats for Which ReliefIs Requested The components for which relief is requested are the Control Rod Drive Housing Welds located in the RPV Closure Heads.
IL AWR Requirement from Whleh RelidIs Requested Table IWB 2500-1, Examination Category B-0, requires that 10% of the peripheral CRD Housing welds be examined by either surface or volumetric methods (due to design geometry and limited accessibility, BG&E has elected surface examination).
There are 28 peripheral housings on each RPV at Calvert Cliffs; therefore, three housings are required to be examined. However, only a portion of each of these three welds is accessible due to the configuration of the Closure Head. These welds are partially obstructed because they extend into the Closure Head (reference CE drawing E233-415, attached). For this reason, reliefis requested from the requirement to examine 100% of three housings.
IIL Proposed Alternate Method In order to meet the intent of the ASME requirements, BG&E proposes to aramine addi-tional CRD Housing welds to satisfy the equivalent of 100% of three welds. This will be done by examining 75% of three welds and 50% of two welds.
47
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ISI RELIEF REQUEST 4 RELIEF FROM HYDROSTATIC TESTING ON SPECIFIED CLASS 2 LINES (Granted during FirstIntervaD (Ref: NRC approvalletter dated November 14,1985, from Mr. Harold R. Denton of the NRC to Mr. A. E. Lundvall of BG&E)
I- Components for Which ReliefIs Requested The components for which relief is requested are the following portions of Class 2 piping from the High Pressure Safety Injection (HPSD, Auxiliary HPSI, and Low Pressure Safety Injec-tion (LPSD Loop Isolation MOVs to the Reactor Coolant System (RCS). (Reference Sketches #1 and #2.)
UNIT 1 UNIT 2 ,
F_rnni T_.g Line Nos. E.tgm Ig Line Nos.
1-SI 118 1-SI 615-MOV 6' CC-13-1001 2-SI 118 2-SI 615-MOV 6* CC-13-2001 1-SI 616 MOV 2' CC-13-1019 2-SI-616-MOV 2' CC-13-2019 1 SI 617 MOV 3' CC 13-1014 2-SI 617-MOV 3* CC 13-2014 2" CC 13-1005 2' CC 13-2005 2' CC-6-1002 2' CC-6-2002 1-SI 128 1 SI 625 MOV 6' CC-13-1002 2-SI 128 2-SI 625-MOV 6' CC 13-2002 !
1-SI-626-MOV 2' CC-131018 2-SI 626-MOV 2' CC-13-2018 1-SI 627 MOV 3' CC-13-1015 2-SI 627 MOV 3' CC 13 2015 :
2' CC 13-1006 2' CC-13 2006 l 2' CC-6-1004 2' CC-6-2004 l l
I-SI-138 1 SI 635-MOV 6' CC-13-1003 2 SI 138 2-SI-635-MOV 6' CC 13-2003 1-SI 636 MOV 2' CC 131016 2-SI-636-MOV 2' CC 13-2016 1-SI 637 MOV 3* CC-13-1021 2-SI-637 MOV 3* CC 13-2021 l 2' CC-13-1007 2' CC 13-2007 2' CC-6-1005 2' CC-6-2005 1-SI-148 1-SI-645-MOV 6' CC 13-1004 2-SI 148 2-SI 645 MOV 6' CC 13-2004 1 SI 646 MOV 2' UC-13-1017 2-SI 646 MOV 2" CC-13-2017 1-SI-647 MOV 3' CC-13-1020 2-SI 647 MOV 3' CC 13 2020 2* CC-13-1008 2' CC-13-2008 2* CC-6-1006 2' CC-6-2006 II. ASME Requirement from Which Relief Is Requested IWA 5000 and IWC-5000 of Section XI require a hydrostatic pressure test of all Class 2 pressure-retaining components. The test pressure requirement for Class 2 is 1.25 times the Design Pressure, Po, for systems with design temperature above 200*F. This test pressure
/'
exceeds the hyd 'ostatic pressure test requirements of the Class 1 system (1.02 times the Operating Pressure, Po) downstream of the check valve. A breakdown of the pressure 49
. - . ~ - - _ . - - . - . . -. .. . - - - - - - - - _ _ _ -
~l requirements is provided below.
O Class 1 Portion Class 2 Portion Design Temperature 650 650 Operating Temperature 550 294 Design Pressure 2485 2485 Operating Pressure 2235 2235 Class 1 Hydro Pressure (1.02 Po) 2280 N/A Class 2 Hydro Pressure (1.25 PD) N/A 3106 Thus, the hydrostatic test pressure for the Class 2 side (3106 psi) exceeds the hydrostatic test pressure for the Class 1 side (2280 psi) by 826 psi. Because the Class 1 side of this piping cannot be isolated from the Class 2 side, the higher pressure requirements of Class 2 cannot be accomplished. In addition, the following portions of this piping cannot be pressurized due to the inability to align the charging pumps and the operating requirements of these portions when the RCS is pressurized.
UNIT 1 UNIT 2 ,
l Etsm T2 Line Nos. EI2m T2 Line Nos.
1 SI 114 1 SI 615-MOV 6' CC-IS1001 2-SI 114 2-SI-615 MOV 6' CC-13-2001 1 SI 124 1-SI-625-MOV 6' CC-131002 2-SI 124 2 SI 625-MOV 6* CC-13-2002 1 SI 134 1-SI 635-MOV 6' CC 131003 2-SI 134 2-SI 635 MOV 6' CC-13 2003 l 1 SI 144 1-SI-645-MOV 6* CC 13-1004 2 SI 144 2 SI 645 MOV 6* CC-13 2004 BG&E therefore requests relief from the Class 2 hydrostatic pressure test requirements for the portions of Class 2 systems identified in I. above.
III. Proposed Alternate Method As an alternative, BG&E proposes to implement the following program for pressure testing:
A. Perform a hydrostatic presnre test of the piping listed in Section I (excluding the piping listed in Section II) to the pressure test requirements of IWB-5000 for Class 1 piping. This piping can be pressurized via alignment of the charging system to the i Auxiliary HPSI header to obtain the required test pressure ofIWB-5000.
B. During each refueling cycle, a leakage test of the piping listed in Section II will be l performed in accordance with Technical Specification 6.14. In this test, the piping l listed in Section II will be pressurized to LPSI pump discharge pressure, and a visual examination for leakage will be conducted.
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^ 2'-CC-6-iOO2 e 1-SI-61 N I I m ,, ,, SI TANK N AUX HPSI 2- -25 i 2'-CC-13-iOO5 1-SI-616-MOV sammen muuna numm 2' C-13-lOi9
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( i-SI-217 1-SI414 e i_g7_iig i-SI-114 1-SI-615-MOV 4 V '
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'E W 2'-CC-13-1018 HPSI SI-123
$ i-SI-227 1-SI-624-MOV 1-SI-128 1-SI-124 1-SI-625-MOV u
< 'd '/ 6*-CC-13-iOO2 M LPSI HPS SI TANK 8 1-SI-235 3'-CC-13-iO21 2'-CC-13-iOO7 @ 1-SI-636-n0V a- 2'-CC-13-1016 N wSI r 1-SI-237 1-SI-634-MOV 1-SI-134 a 1-SI-635-n0V 1-SI-138 O < M '
/ '/ LPSI E 6*-CC-13-iOO3 2*-CC-6-1006 = i-SI-647-MOV SI TANK AUX W SI 1-SI-245 3'-CC-13-iO20 " i-SI m 2'-CC-13-iOO8 HPSI 2'-CC-13-1017 i-SI-247 SI-644-MOV 1-SI-148 1-SI-144 1-SI-64!H OV k
4 / 6"-CC-13-iOO4 LPSI TEST EQUIEENT (IWB-5000) m CLASS 1 CLASS 2 m TEST EQUIREMENT (IWC-5000) 1.02 X 1005 OP PESSUE AT 500' F 1.25 X DESIGN PESSLE AT 100' F CALVERT CLIFFS UNIT i SKETCH i
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, CLASS i CLASS 2 m p=-CC-6-2002 2-SI-617 e I I , ,, ,, SI TANK ** "I 2-51-215 3'-CC-13-2014 2"-CC-13-2005 a 2-SI-616-Nov
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( 2-SI-614-MOV "
2-SI-217 2-SI-HB 2-SI-114 2-SI-61540v 2 f I
'/ 6'-CC-13-2001 f LPSI 2-SI-627-Nov 2"-CC-6-2004 ** "I SI TANK 2-SI-225 3'-CC-13-2015 g. CC-13-2006
- 2-SI-626+0V g 2'-CC-13-2018 SI-123 HPSI
$ 2-SI-227 2-SI-624 e 2-SI-128 2-SI-124 2-SI-625-Mov u
l '/ 6'-CC-13-2002 A
' LPSI 2"-CC-6-2005 g 8 2-SI-235 3*-CC-13-2021 2'-CC-13-2007 2-SI-636+0V C 2'-CC-13-2016 HPSI SI-133 S 2-SI-237 2-SI-634-M0v 2-SI-138 2-SI-134 " 2-SI-63540v S q f f j' [
f
'[ LPSI
@ 6"-CC-13-2003 2'-CC-6-2006 = 2-SI-647-May SI TANK AUX HPSI 2-SI-245 3'-CC-13-2020 " 2-SI-646 e 2'-CC-13-2008 2*-CC-13-2017 HPSI SI-143 2-SI-247 2-SI-644-M0v 2-SI-144 2-SI-148 2-SI 6 (4 [ 6*-CC-13-2004 LPSI TEST EQUIEMENT (IWB-5000) m CLASS i CLASS 2 m TEST EQUIEENT (IWC-5000)
' ^ 8 1.02 X 1001 OP PESSWE AT 5008 F 1.25 X DESIGN PESSWE AT 100 F CALVERT CLIFFS UNIT 2 SKETCH 2
ISI RELIEF REQUEST 5 RELIEF FROM HYDROSTATIC TESTS ON SPECIFIED CLASS 3 SYSTEMS (Granted during First Interval)
(Ref: NRC approvalletter dated January 24,1983, from Mr. Robert A. Clark of the NRC to Mr. A. E. Lundvall, Jr. of BG&E for Component Cooling and NRC approval letter dated December 13,1982, from Mr. Robert A. Clark of the NRC to to Mr. A. E. Lundvall, Jr. of BG&E for Saltwater and Service Water)
L Components for Which ReliefIs Requested The components for which relief is requested include the Class 3 portions of Component Cooling, Service Water, and Saltwater Cooling Systems.
IL ASME Requirement from Which ReliefIs Requested Subarticles IWA-5200 and IWD-5200 require that Class 3 systems receive a system hydro- i static test. Paragraph IWD-5223(a) specifies that the hydrostatic test pressure shall be at least 1.10 timec the system pressure for systems with design temperatures of 200 degrees F or less.
On the main headers of the listed systems, where butterfly valves are installed, sufficient seal to maintain hydrostatic pressure on isolated portions cannot be achieved. For this reason, the elevated pressure hydrostatic test cannot be completed.
IIL Proposed Alternate Method As an alternative, BG&E proposes to perform a system insenice pressure test on an annual. basis for portions of these systems outside containment and on a refueling outage basis for systems located inside containment to verify system integrity, b) c.
53
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l l
Table 6
SUMMARY
OF REGULATORY GUIDE 1147 CODE CASES l
Code Reason for Case Section XI Section XI Implementing Code Case Number Reference Component / Area Reauirement Code Case Imolementation N 3071 IWB 25001 Studs and Bolts with 100% Volumetric More critical exam- Volumetric examination Cat B G 1 Hester Holes ination of the postu- utilizing Code Case
- lated flaw regions is N 307 L achieved utilizing Code Case N-307 L N 408 IWC 25001 Class 2 Piping Surface and/or Volu- Code Case N-408 surface and/or volu-Cat. C F metric per IWC-25001 provides supple- metric in accordance requirements mental requin- with Code Case N-408.
ments adopted by later editions of ;
ASME Section XL N 416 IWA-4400 Any repaired or System Hydrostatic In the event a Deferral of system replaced Class 2 piping Test in accordance Class 2 systemis hydrostatic testing in component that cannot with IWA 5000 follow- repaired or replaced accordance with Code be isolated by valves ing weld repair or and cannot be iso. Case N 416.
or requires securing replacement lated for a hydro.
O- safety /reliefvalves static test, BG&E '
may elect to defer the test until the next scheduled I
hydrostatic test-N-424 IWA 2300 Qualification of Visual ANSI N45.2.61973 BG&E's Calvert Visual examination per-(3)(c) Examination Personnel Clifts Instructions sonnel shallbe qualified for qualifying visual in accordance with ANSI examination person. N45.2.61978.
net are written to j ANSI N45.2.6-1978.
l I
i O
54 l
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CODE CASE N 3071 FOR EXAMINATION O OF CLASS 1 BOLTING WITH HEATER HOLES L Applimble Components The components for which this Code Case shall be used are the Reactor Vessel Closure Head studs and Reactor Coolant Pump studs, which can be ultrasonically arnmined from the heater hole.
IL ARME Requirement Table IWB 2500-1, Ernmination Category B G 1, requires that the aramination of studs and bolts include 100% of the volume. Since cracking in studs and bolts is most likely to occur in the areas of high stress, it is more practical to concentrate the examination on the thread root area and surface of the heater hole. For this reason, Code Case N 3071 will be implemented.
IIL Code CaseImplementation '
Code Case N 3071, ' Ultrasonic Ernmination Volume for Class 1 Bolting," limits the UT examination of studs and bolts to 1/4 inch beyond the thread root and requires a supplemental examination of the heater hole surface. Since this Code Case allows what is considered a more sensitive nunmination to the areas of interest, BG&E will use this Code Case in lieu of the Section XI requirements. A copy of this Code Case is attached.
O '
55 i
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- __. .. --- 1
CA5E N-307-1 CASES OF ASME BOILER AND PRESSL'RE VESSEL CODE V
Approval Date: December 5,1984 See Numeric index for expiration and any reaffirmation dates.
Case N 3071 records shall be retain-d for the service life of the bolt or Revised Ultrasonic Examination Volume for Class 1 stud examined. The CertiScation Report shallinclude at Bolting, Table IWB 25001, Examination Category least the following items:
B G 1, When the Examinations Are Conducted From the (a) identiScation of procedure qualified; Center Drilled Hole (b) personnel performing and witnessing the Section XI, Division 1 qualification tests; (e) description and drawingsof thequalifica-Inquiry: When ultrasonic examinations are conducted tion specimens and the calibration blocks, as applicable; from the center drilled hole of Class 1 bolta or studs to (d) calibration and sensitivity details; satisfy the examination requirements of Section XI, (e) methods of identifying flaw indications Division 1, Table IWB-25001, Examination Category and discriminating between flaw indications and non-B-G 1, may the examination volume be limited to the relevant indications such as indications from probe lift-cylindrical region defined by A.B.C.D.E F A in Fig. l? off, plating thickness changes, or permeability changes in ferromagnetic material; J Reply: It is the opinion of the Committee that, when ~ (f) procedure for interpretation of results; conducting ultrasonic examinations from the center- (g) qualification results; and
)
O drilled hole of Class 1 bolts or studs to satisfy the exami-nation requirements of Section XI, Dhision 1, Table IWB 2500-1, Examination Category B-G 1, the examina.
(h) signature of the Authorized Nuclear Inservice Inspector (ANII).
(2) Eddy current examinations shall be per-i tion volume may be limited to the cylindrical region formed in accordance with a written procedure. Each defined by A.B-C D E.F.A in Fig.1 if the center bore procedure shallinclude atleast the followinginformation:
hole surface is examined with a qualified supplemental (a) bolt or stud configuration to be exam-ultrasonic, surface, or eddy current procedure. The ined, including, as applicable, lengths, diameters, thread examination procedure shall be qualified to cover the sizes, plating and base materials, and product forms (e.g.,
entire inner bore surface. If eddy current examination is forging, bar, bolt or stud, rolled or cut threads);
used, the following requirements shall apply. (b) surface condition requirements and any (a) The procedure qualification shall demonstrate the applicable preparation methods; ability to detect and measure the length of the maximum (c) sizes and types of probes, including allowable flaws of IWB-35151. Qualification of the description and part or drawing numbers, and lengths of procedure shall include detection of at least one crack in probe cable; each material type (ferromagnetic or nonferromagnetic) (d) manufacturers and models of eddy cur-to be examined. The length of the crack open to the rent equipment qualiSed; surface shall not exceed the maximum allowable length (e) data recording equipment and methods; of IWB-35151 for nonaxial Saws The crack shall be (f) examination frequencies; located in a bore hole surface and oriented circumferen- (g) maximum scanning speed permitted and tially. Alternatively, the crack may be located in a block demonstrated by procedure qualification; with different geometryif the qualiGention demonstrates (h) calibration procedure and calibration cracks can be detected in bore holes. Demonstration standards; may be performed by showing equivalent response in (i) examination technique (e.g., scanning both geornetries (bore hole and block) using calibration instructions, hand probe, and mechanized probe desice);
discontinuities specified by the qualiSed procedure. (f) reportinginstructions; (1) The procedure qualification shall be docu- (k) personnel qualification requirements; mented in a Certification Report. Procedure qualification (I) reference to the CertiScation Report.
555 56
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CASE (continuod)
CASES OF ASME BOILER AND PRESSL'RE VESSEL CODE scanned from center drill hole I
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556 57 1
%4 CODE CASE N 408 FOR SELECTION O AND EXAMINATION OF CLASS 2 PIPING L Applicable Components The components for which this Code c' ase shall be used include all Class 2 piping compo-nents required to be examined e accorance with Table IWC 2500-1, Category C F, of ASME Section XI.
IL ARME Requirement Table IWC 25001, Examination Category C-F, for pressure-retaining welds in piping.
IIL Code ClassImplementation Class 2 pressure retaining piping welds will be examined in accordance with Code Case N-408, "Alternative Rules for Examination of Class 2 Piping." This Code Case provides sup-plemental exemption and examination requirements for Class 2 piping. A copy of Code Case N 408 is attached.
I O l
CA5E N-408 CASES OF ASME BOILER AND PRESSURE YESSEL CODE Approval Date: July 12,1984 See NumericalIndex for expiration and any reaffirmation dotes.
Case N 408 cally pressurized, passive (Le., no pumps) safety injection 8
Alternative Rules for Examination of Class 2 Piping systems of pressurized water reactor plants;Section XI, Division 1 (6) piping and other components of any size be-yond the last shutoff valve in open ended portions of Inquiry: When determining the components subject systems that do not contain water during normal plant to examination and establishing examination require- operating conditions.8 ments for Gass 2 geiping under Section XI, Division 1, (b) The following components (or parts of compo-what alternative emnptions to those stated in IWC 1220 nents) of systems (or portions of systems) other than and what alternative examination requirements to those R11R, ECC, and CliR systems are exempt from the stated in IWC 2500; Category C.F, may be used? volumetric and surface examination requirements of IWC-2500:
Reply: It is the 4 pinion of the Committee that the (1) vessels, piping, pumps, valves, and other com-following alternativs rules may be used for determining ponents NPS 4 and smaller; components subject to examination and for establishing (2) component connections NPS 4 and smaller examination requirer: ents for Gass 2 piping under Sec. (ir.cluding nozzles, socket fittings, and other connections) tion XI, Division 1. in vessels, piping, pumps, valves, and other components (a) The following components (or parts of compo. of any size; nents) of RilR, ECC, and CllR systems (or portions of (3) vessels, piping, pumps, valves, other compo--
systems)8 are exempt from the vcsumetric and surface nents, and component connections of any size in systems examination requirements oil %L2500: or portions of systems that operate (when the system (1) vessels, piping, pumps, valves, and other com- function is required) at a pressure equal to or leu than ponents NPS 4 and smaller in all systems except in high 275 psig and at a temperature equal to or less than 200*F; pressure safety injection systems of pressurized water (4) piping and other components of any size be-reactor plants; yond the last shutoff valve in open ended portions of (2) vessels, piping, pumps, valves, and other com- systerns that do not contain water during normal plant ponents NPS In and smaller in high pressure safety operating conditions.
injection systems of pressurized water reactor plants; (c) For welds in austenitic stainless steel or high (3) component connections NPS 4 and smaller alloy piping, the requirements of Table 1, Examination ,
(including nozzles, socket fittings, and other connections) Category C F 1, Pressure Retaining Welds in Austenitic j in s essels, piping, pumps, valves, and other components Stainless Steel or liigh Alloy Piping, shall be used as an i of any size in all systems except in high pressure safety alternative to the requirements of Table IWC-25001.
injection systems of pressurized water reactor plants; (d) For welds in carbon or low alloy steel piping, the (4) component connections NPS 1h and smaller requirements of Table 2, Examination Category C.F.2, (including nozzles, socket fittings, and other connections) Pressure Retaining Welds in Carbon or Low Alloy Steel in vessels, piping, pumps, valves, and other components Piping, shall be used as an alternative to the requirements of any size in high pressure safety injection systems of of Table IWC 25001.
pressurized water reactor plants; StaticaDy pressurized, passive safety trdeetion systems of pres-(5) vessels, piping, pumps, valves, other compo* surized water reactor plants are typically called by such names as-nents, and component connections of any size in stati. accumulator tank and associated system, safety lidection tank and associated system, and core flooding tank and associated system.
8RHR, ECC, and CHR systems are Residual Heat Removal, ' Normal plant operatir.: conditiens include reactor startup, Emergency Core Cooling, and Containment Heat Removal sys- operation at power, hot standby, and reactor cooldown to told te ms, respectively. shutdown conditions, but do not include test conditions.
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r kJ % %l TABLE 1 EXAMINATION CATEGORY C-F-1, PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL OR HIGH ALLOY PIPING Examination Q
Item JA
- No. Paris Examined' flequirements/ Examination Acceptance O" Fig. No.* Method Standard' Extent of Examination
- E xamination* @7 O C5.10 Piping welds > % in. nominal wall thickness 3 for piping > NPS 4 =e C5.11 Circumferential weld IWC-2500 7 Surf ace and IWC-3514 100% of each weld requiring Each inspection volumetric examination interval g C5.12 Longitudmal weld IWC 2500'7 Surface and IWC-3514 2.5t - et the intersecting Each inspection g, volumetric :ircumferential weld Interval V C5.20 Piping welds > 7, in. nomenal wall thickness a
for piping > NPS 2 and < NPS 4 C5.21 Circumferential weld IWC 2500L7 M
Surface and IWC 3514 100% of each weld requiring Each inspection @
volumetric examination interval C5.22 t ongitudmal weld IWC 2500 7 Surface and IWC-3514 2.5t - at the intersecting Each inspection volurnetric circumferential weld interval $
C5.30 E
Socket welds IWC-2500L7 Surface IWC-3514 100% of each weld requiring examination Each inspection $
interval F M
- c 3 CSAO o
Pipe branch connections of branch piping
> NPS 2
$ C5.41 Circumferential w=ld IWC 25009 to Surface IWC-3514 100% of each weld requiring Each inspection tj
-o
-13, inclusive examination interval in C5.42 Longitudinal weld WC-2500-12 and -13 Surface IWC-3514 2.5t - at the intersecting Each inspection $
circumferential weld interval $
NOTES: *
(Il flequirernents for eartrnination of welds in piping < NPS 4 apply to PWR high pressure safety injection systems in accordance with E' re, the exemption criteria of this Case.
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r (2) The welds selected for examination shall include 7.5%, but not less than 26 welds, of all austenitic stainless steel or high alloy welds o not exempted by this Case. (Some welds not exempted by this Case are not required to be nondestructively examined per Examina-tion Category C F-1. These welds, however, shall be included in the total weld count to which the 7.5% sampling rate is applied.) @
en The examinations shall be distributed as follows:
(a) the examinations shall be distributed among the Class 2 systems prorated, to the degree practicable,on the number of non-exempt austenitic stainless steel or high alloy welds in each system (i.e.,if a system contains 30% of the nonenempt welds, then 30%
of the nondestructive examinations required by Examination Category C-F 1 should be performed on that syst m);
(b) within a system, the examinations shall be distributed among terminal ends [see Note (3)] and structuras discontinuities [see Note (4)) prorated, to the degree practicable, on the number of nonenempt terminal ends and structural discontinuities in that system;and (c) within each system, enaminations shall be distributed between line sites prorated to the degree practicable.
(3) Terminal ends are the extremities of piping runs that connect to structures, components (such as vessels, pumps, valves), or pipe anchors, each of which acts as a rigid restraint or provides at least two degrees of translational restraint to piping thermal expansion.
(4) Structuras discontinuities include pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees, seducers, flanges, etc., conforming to ANSI 816.9), and pipe branch connections and fittings.
(5) The ws4ds selected for examination shall be reexamined during subsequent inspection intervals over the service lifetime of the piping component.
(6) Figure numbers and acceptance standards refer to those in Section XI, Winter 1983 Addenda.
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- A TABLE 2 EXAMINATION CATEGORY C-F-2, PRESSURE RETAINING WELDS IN CARBON OR LOW ALLOY STEEL PIPING Examination item Requirements / Examinatiois Acc.eptance Frequency of No. Parts Examined' Fig No.' Method Standard' Extent of Examination ** Examination' C5.50 Piping welds > */, in. nominal wall thickness for piping > NPS 4 C5.51 IWC-25047 Surface and IWC-3514 100% of each weld requiring Each inspection Circumferential weld volumetric examination interval C5 52 tongitudinal weld IWC-2500 7 Surf ace and IW C3514 2.St - at the intersecting Each inspection volumetric circumferential weld interval C5 60 Piping welds > '/, in. nominal wall thickness O
for piping > NPS 2 and < NPS 4 C5.61 Circumferential weld IWC-25007 Surf ace and IWC-3514 100% of ,each weld requiring Each inspection b volumetric examination Interval E C5.62 Longitudmal weld IWC25047 Surface and IW C3514 2.St - et the Intersecting Each inspection O volumetric circumferential weld interval g E
100% of each weld requiring Each inspection "
C530 Socket welds IWC25047 Surface IWC 3514 examination interval o m
C5 80 Pepe branch connections e f tsanch piping :o g > NPS 2 y e ~ C5.81 Circumferential weld IWC-2500 9 to Surface IWC-3514 100% of each weld requiring Each inspection C
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-13 inclusive examination interval @
C5 82 Longitudinal weld IWC-2500-12 Surface IWC-3514 2.St - at the intersecting Each inspection Q and -13 circumferential weld interval E
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) NOTES: ,,-
(1) Hequirements for examination of welds in piping < NPS 4 apply to PWH high pressure safety injection systems in accordance with the esemption criterla of this Case. g (2) The welds selected for enamination . hall include 7.5%, but not less than 28 welds, of all carbon or low alloy welds not exempted by t-this Case. (Some welds not exempted by this Case are not required to be nondestructively examined per Examination Category C-F-2. O g
These welds, however, shall be included in the total weld count to which the 7.5% sampling rate is applied.) The examinations shall c M
be distributed as follows:
(a) the enaminations shak %stributed among the Class 2 systems prorated, to the degree practicable, on the number of non-exempt carbon or low alloy ww i each system (i.e., if a systern contains 30% of the nonexempt welds, then 30% of the nonde- n structive enaminations required by Esemination Category C-F-2 should be performed on that system); y (0) within a system, the examinations shall be distributed among terminal ends (see Note (3)] and structural discontinuities [see y Nete (41] prorated, to the degree practicable, on the number of noneuempt terminal ends and structural discontinuities in that gun system; and n (c) wethin each system, emaminations shall be distributed between line sites prorated to the degree practicable. es (3) Terminal ends are the extre;nities of piping runs that connect to structures, components (such as vessels, pumps, valves), or pipe O anchors, each of which acts as a rigid restraint or provides at least two degrees of translational restraint to piping thermal expansion. 3
- 14) Structoral discontinuities include pipe weld joints to vessel norries, valve bodies, pump casings, pipe fittings (such as elbows, tees. 1 reducers, flanges, etc., conforming to ANSI B16.9), and pipe beanch connections and fittings.
(5) The welds selected for examination shall be reexamined during subsequent inspection intervals over the service lifetime of the piping Z.
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C component. Q (6) for welds in carbon or low alloy steels, only those welds showing reportable preservice transverse indications need to be examined @v for transverse reflectors.
(7) F kyne nunters and acceptance standards refer to those in Section XI, Winter 1983 Addenda.
p CODE CASE N-416 FOR HYDROSTATIC TESTING OF CLASS 2 REPAIR OR REPla\ CEMENT %TLDS L Application Code Case N-416 will be used, at BG&E discretion, to defer the IWA 4000 hydrostatic testing of Class 2 piping that has been repaired or replaced and cannot be isolated by existing valves or that regul~res securing safety or relief valves.
II. ASME Requirement IWA-4400 and IWA 4600 of Section XI state that a system hydrostatic test shall be per-formed in accordance with IWA-5000 following repairs or replacements by welding on a pressure-retaining boundary. However, in some Class 2 systems, it may not be practical to isolate a system for testing by existing valves or by taking safety or relief valves out of service. Code Case N 416 allows hydrostatic testing in this instance to be deferred until the next regularly scheduled test.
III. Code CaseImplementation In the event a Class 2 system is repaired or replaced at Calvert Cliffs, BG&E may elect to exercise Code Case N-416 to defer the system hydrostatic test until the next regularly sched- ,
uled test for that system. BG&E may defer this test provided the following conditions are met: l (a) A VT 2 for leakage shall be performed during the system functional or inservice test. This test shall be performed prior to or immediately upon return to service.
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(b) The repair or replacement welds shall be aumined with volumetric techniques for full penetration welds or surface techniques for partial penetration welds.
A copy of Code Case N 416 is attached.
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CA5E
, N-416 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Approval Date: December 5,1984 See Numeric Indes for expiration and any reaffirmation dates.
Case N416 of Class 2 piping that cannot be isolated by existing Alternative Rules for Hydrostatic Testing of Repair or valves or that requires securing safety or relief valves Replacement of Class 2 Piping for isolation may be deferred until the next regularly Section XI, Division 1 scheduled system hydrostatic tests (WC 5000), pro-vided both of the following conditions are met.
Inquiry: For Section XI, Division 1, repair or replace-ment of Class 2 pipmg that cannot be tsolated by exist- (a) Prior to or immediately upon return to service, mg valves or that requires securing safety or relief valves a visual examination (VT 2) for leakage shall be con-for isolation, may the system hydrostatic test required ducted during a system functional test or during a sys-by IWA4400 (MA4210 in earlier Code editions) be de-I'" N,ervice test in the repaired or replaced portion of ferred until te next regularly scheduled system hydro- the piping system.
static test (IWC-5000) for that system? (b) The repair or replacement welds shall be ex-amined in accordance with IWA4000 and IWA 7000 Reply: It is the opinion of the Committee that the using volumetric examination methods (IWA.2230) for system hydrostatic test required by IWA4400 (IWA- full penetration welds or surface examination methods 4210 in earlier Code editions) for repair or replacement (IWA 2200) for partial penetratica welds.
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CODE CASE N-424 FOR QUALIFICATION OF VISUAL EXAMINATION PERSONNEL L Application Code Case N 424 shall be used for qualifying BG&E personnel performing VT 2, VT 3, and VT-4 visual examinations.
II. ASME Requirement IWA 2300(3)(c) of Section XI states that personnel performing VT 2, VT 3, and VT-4 eraminations shall be qualified in accordance with ANSI N45.2.61973. However, BG&E's Calvert Cliffs Instructions for qualifying visual eramination personnel are written in accordance with the 1978 edition of this ANSI document (ANSI N45.2.6-1978).
Code Case N 424 permita BG&E to qualify visual examination personnel to the require-ments of ANSI N45.2.6-1978.
IIL Code Case Implementation BG&E personnel performing VT 2, VT 3, and VT-4 examinations during the Second Interval will be qualified in accordance with ANSI N45.2.6-1978, as permitted by Code Case N-424. A copy of this Code Case is attached.
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CA5E f N-424 CASES OF ASME BOILER AND PRESSURE VESSEL CODE .
i Approval Date: July 18,1986 See Numeric Index for expiration and any reaffirmation dates, Case N-424 ,
Qualification of Visual Examination Personnel Section XI, Division 1 Inquiry: When qualifying personnel to perform visual examinations VT-2, VT 3, and VT 4 in r.ccordance with IWA 2300 of Section XI, Division 1, may ANSI /
ASME N45.2.61978 be used instead of ANSI N45.2.6-1973?
Reply: It is the opinion of the Committee that ANSI /
ASME N45.2.61978 may be used instead of ANSI N45.2.61973 when qualifying examination personnel to perform VT 2, VT 3, and VT-4 visual examinations for Section XI, Division 1.
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