ML20097C905
| ML20097C905 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/02/1996 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20097C888 | List: |
| References | |
| PROC-960202, NUDOCS 9602120078 | |
| Download: ML20097C905 (663) | |
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i INSERVICE INSPECTION PLAN l
FOR l THE COMMONWEALTH EDISON COMPANY
! LASALLE COUNTY NUCLEAR STATION
, UNITS 1 & 2
- SECOND TEN-YEAR INSERVICE
! INSPECTION INTERVAL i
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[ REVISION 1
! 02-02-96 i
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sY ~cm = n m "N aea asco . .ce = a me= = s TABLE OF CONTENTS
- TITLE PAGE Page TP-1
. TABLE OF CONTENTS Page TOC-1
- SECTION 1 - ISI PLAN
SUMMARY
Pages 1-1 thru 1-5
+ SECTION 2 - INTRODUCTION Pages 2-1 thru 2-5
- SECTION 3 - DRAWINGS Pages 3-1 thru 3-4 SECTION 4 - UNIT 1 ISI
SUMMARY
TABLE Pages 4-1 thru 4-10
- SECTION 5 - UNIT 2 ISI
SUMMARY
TABLE Pages 5-1 thru 5-8
- SECTION 6 - UNIT 1 COMPONENT SUPPORT INSPECTION
SUMMARY
TABLE Pages 6-1 thru 6-2
- SECTION 7 - UNIT 2 COMPONENT SUPPORT l INSPECTION
SUMMARY
TABLE Pages 7-1 thru 7-2 l
i SECTION 8 - ISI COMPONENT REllEF 0
REQUESTS Page 8-1 thru 8-37
. SECTION 9 - UNIT 1 PRESSURE TESTING
SUMMARY
TABLE Page 9-1 thru 9-5
- SECTION 10 - UNIT 2 PRESSURE TESTING
SUMMARY
TABLE Pages 10-1 thru 10-5 i
- SECTION 11 - PRESSURE TESTING RELIEF REQUESTS Page 11-1 thru 11-20 j
. SECTION 12 - CODE CASES Pages 12-1 thru 12-4
- SECTION 13 - REFERENCES Pages 13-1 thru 13-3
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i SECTION 1 ISI PLAN
SUMMARY
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1.0 DESCRIPTION
S OF PLAN CONTENTS 4
- 1.1 Title Page
, Provides the title, current revision and issue date for the Inservice j inspect!on (ISI) Plan.
1.2 TabM of Contents i
- Provides the organizational format for the ISI Plan.
l 1.3 Section 1 - ISI Plan Summary i Provides an overview of the contents of the ISI Plan.
1.4 Section 2 - Introduction i
l Provides the scope and bases for the ISl Plan including information on
- j. the classification of systems and augmented inspection requirements.
i 1.5 Section 3 - Drawings
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O Provides a tabular summary of the applicable ISI Piping and instrument Diagrams (P&lD's) and the ISI isometric Drawings.
i 1.6 Sections 4 & 5 - Units 1 & 2 ISI Summary Tables l
The Unit 1 & 2 ISI Summary Tables provide the following information:
1.6.1 Examination Category
- Provides the Examination Category as identified in the l American Society of Mechanical Engineers Boiler &
Pressure Vessel Code (ASME)Section XI, Tables IWB-l 2500-1, lWC-2500-1 and IWD-2500-1. Only those l categories applicable to LaSalle County Nuclear Station are identified.
1.6.2 Item Number and Description Provides the item Number and Description as defined in ASME Section XI, Tables IWB-2500-1, lWC-2500-1 and i IWD-2500-1. Only those items applicable to LaSalle l County Nuclear Station are identified.
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1.6.3 Number of Components lO j
Provides the population of components potentially subject to examination. The number of components actually
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examined during the inspection interval will be based on the
- ASME Section XI Code requirements for the subject item Number.
j l 1.6.4 Exam Requirements 1
Provides the examination method (s) required by the l applicable ASME Section XI Item Number.
1.6.5 Relief Request / Code Case 1
- identifies by numoer the Relief Request (s)/ Code Case l applicable to the subject item Number, if any, if a Relief Request is identified, the details can be found in Section i 10, ISI RELIEF REQUESTS.
l 1.7 Sections 6 & 7 - Units 1 & 2 Component Support inspection Summary l
Tables 4
O o ia mi < t" u it 1 & 2 Compon.n Su,po,t Summ.,y Tabl.s is based on ASME Section XI, Code Case N-491. The tables provide the following information:
1.7.1 Examination Category i
[ Provides the Examination Category as identified in ASME
- Section XI, Table IWF-2500-1. Only those categories l applicable to LaSalle County Nuclear Station are identified.
! I l 1.7.2 Item Number and Description
! Provides the item Number and Description as defined in i i ASME Section XI, Table IWF-2500-1. Only those items ;
j applicable to LaSalle County Nuclear Station are identified.
i 1.7.3 Number of Components ;
! Provides the population of components potentially subject j to examination. The number of components actually j examined during the inspection interval will be based on the
- ASME Section XI Code requirements for the subject item j Number. l i
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! 1.7.4 Relief Request / Code Case i
! Identifies by numoer the Relief Request (s)/ Code Case applicable to the subject item Number, if any. If a Relief
- Request is identified, the details can be found in Section
- j. 10, ISI RELIEF REQUESTS.
- l. 1.8 Section 8 - ISI Component Relief Requests
! This section contains Relief Requests written in accordance with 10 CFR 50.55a (g)(5) when specific ASME Section Xl ISI requirements are considered impractical. The enclosed Relief Requests are subject to change throughout the inspection interval. If any examination i requirements are determined to be impractical during the course of the
! inspection interval, additional or modified Relief Requests will be submitted in accordance with 10 CFR 50.55a (g)(5).
1
- 1.9 Sections 9 & 10 - Units 1 & 2 Pressure Testing Summary Tables
) The Unit 1 & 2 Pressure Testing Summary Tables provide the following information:
l 1.9.1 Examination Category Provides the Examination Category as identified in ASME
- Section XI, Tables IWB-2500-1, lWO-2500-1 and IWD-2500-1. Only those categories applicable to LaSalle County Nuclear Station are identified.
l 1.9.2 Item Number and Description
! Provides the item Number and Description as defined in
- ASME Section XI, Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1. Only those items applicable to LaSalle i -
County Nuclear Station are identified.
i 1.9.3 Relief Request / Code Case identifies by number the Relief Request (s)/ Code Case applicable to the subject item Number, if any. If a Relief Request is identified, the details can be found in Section 10, ISI RELIEF REQUESTS.
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l smaa.ewrom. ws cranm 1.10 Section 11 - Pressure Testing Relief Requests j
O This section contains Relief Requests, specifically related to the pressure testing program, written in accordance with 10 CFR 50.55a (g)(5) when
! specific ASME Section XI ISI requirements are considered impractical.
! The enclosed Relief Requests are subject to change throughout the ,
inspection interval. If any examination requirements are determined to be impractical during the course of the inspection interval, additional or l l
modified Relief Requests will be submitted in accordance with 10 CFR j 50.55a (g)(5).
! 1.11 Section 12 - Code Cases i 1
i This section contains the Code Cases listed in Regulatory Guide 1.147, l Inservice inspection Code Case Acceptability ASME Section XI Division 1, applicable to LCNS that are, or may be, utilized in the implementation
. of this ISI Plan.
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- 1.12 Section 13 - References t
! This section provides a listing of the documents utilized in the i preparation of this ISI Plan.
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4 SECTION 2 i
INTRODUCTION i
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! 1.1 This ISI Plan outlines the applicable rules and requirements for the Non- i l
Destructive Examination (NDE) of ISI Class 1, 2 and 3 (Equivalent to !
{ Quality Groups A, R and C) pressure retaining components and their i j supports at LaSalle County Nuclear Station Units 1 & 2 (LCNS). !
l j 1.2 This ISI Plan will be in effect for the entirety of the ISI Program second i l ten-year inspection interval at LCNS. The effective dates fer each unit ;
i are as follows: I I I
! Unit 1 - November 23,1994 through November 22, 2004. l I
l Unit 2 - October 17,1994 through October 16, 2004.
l 1.3 The sections that follow present a summary of the documents and i actions required for the execution of the ISI Plan. The details of tha ISI 1 i Program are contained in other documents which are available at LCNS. l l
l 1.4 The inservice Testing (IST) of pumps and valves is addressed in e l
! separate Plan, i
!O 2.0 181 PLAN BASES f
l 2.1 This Plan was developed in accordance with the requirements of 10 CFR
- 50.55a including all published changes through November 22,1993 and .
October 16,1993 for Units 1 and 2 respectively, and the 1989 Edition of I
! ASME Section XI. This Plan addresses Subsections lWA, lWB, lWC, i i IWD and IWF of ASME Section XI, and utilizes inspection Program B as l j defined therein.
The commercial service dates for LCNS Units 1 and 2 are January 1, I 2.2 f
1984 and October 17,1984 respectively. At the end of the first fuel
- - cycle, Unit i endured a refueling outage that lasted 329 consecutive
! days. Paragraph IWA-2430(e) of ASME Section XI allows an inspection l interval to be extended for a period of time equivalent to the duration of a
- continuous outage that exceeds six months. Therefore, the start date of l j the Unit 1 second inspection interval reflects an extension of the first !
i inspection interval by 329 days. !
J 2.3 The following documents present detailed bases for the contents of this I Plan:
2.3.1 BASES DOCUMENT FOR LASALLE COUNTY STATION UNITS .
I 2-2 !
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1 & 2 SECOND INTERVAL INSERVICE INSPECTION
!h PROGRAMS
- 2.3.2 PIPING & COMPONENT SUPPORT AND INTEGRAL ATTACHMENT BASES DOCUMENT FOR LASALLE COUNTY STATION UNITS 1 & 2 SECOND INTERVAL INSERVICE lNSPECTION PROGRAMS ,
l 3.0 SYSIERCLASSIELCAIlON 3.1 The construction permits for LCNS Units 1 and 2 were issued on
{ September 10,1973. The construction codes utilized are identified in the 4
LCNS Final Safety Analysis Report (FSAR), Section 3.2, Tables 3.2-2,
- 3.2 3 and 3.2-4 for general categories of components.
3.2 The system classifications used for the ISI Program are based on 10 CFR 50 and Regulatory Guide 1.26, Revision 3. These classifications were developed for the sole purpose of assigning appropriate ISI ;
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requirements for water, steam and radioactive waste containing components.
3.3 Components within the reactor coolant pressure boundary, as defined in !
- 10 CFR 50.2, are designated as ISI Class 1. Other safety related !
components are designated as ISI Class 2 or 3 in accordance with i Regulatory Gus.le 1.26, Revision 3. Pursuant to 10 CFR 50.55a, j paragraph (a)(1), the ISI requirements of ASME Section XI, are assigned J to these components within the constraints of existing plant design. I 3.4 The LCNS P&lD's show the classification boundaries. The LCNS ISI Program includes color coded Classification Boundary Drawings (CBD's) which show the ISI classification boundaries. A listing of the ISI Class 1, i 2 and 3 systems, including acronyms, and their associated CBD's can be l I found in Section 3 of this Plan.
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) 3.5 The LCNS ISI Isometric Drawings show the location of piping and i
- components subject to ISI. A listing of these drawings can be found in 4
Section 2 of this Plan.
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! 4.0 AUGMENTED ISI REQUIREMENTS O 4.1 Augmented inspections are those which fall outside the scope of ASME i
Section XI requirements, but which are included in the scope of the ISI Program due to licensing and regulatory commitments.
4.2 The augmented inspections that will be performed in the second ISI j
interval belong in one of the three following categories:
- A'. Altemative examinations imposed by Relief Requests.
B. Augmented inspections required by the commission (i.e.
Generic Letters and NUREG's).
C. Miscellaneous docketed commitments. :
l Category A above is addsessed elsewhere in this ISI Plan. The
- Category B and C augmented inspections are summarized in the j following paragraphs 4.3 LCNS is complying with the following augmented ISI requirements in accordance with the latest pertinent licensing agreements
n 4.3.1 Generic Letter 88-01, NRC Position on IGSCC in BWR Austenitic l ') (
Stainless Steel Piping.
l 4.3.2 LaSalle FSAR responses to NRC questions 111.72 and 111.81, 3 Examination of the High Energy Line Break (HELB) Exclusion Region.
' 4.3.3 NUREG-0519, Safety Evaluation Report Related to the Operation l 4
of LaSalle County Station Units 1 and 2, Examination of the l Reactor Building Closed Cooling Water System.
4 4.3.4 NUREG-0619, Examination of Feedwater Nozzles.
4.3.5 1.E. Bulletin No. 80-13, Examination of High and Low Pressure Core Spray Spargers.
4.3.8 Examination of Reactor Core isolation Coolant lines exempt per ASME Section XI, Subsection IWC, Paragraph 1220(b).
l 4.3.7 NUREG-0800, Examination of Class D+ pressure retaining components, LaSalle Main Steam lines from the first outside containment isolation valves to the turbine stop valves. l 2-4 4
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saxne.mmm E - nm i 4.3.8 NUREG-CR-3052, Closeout of I.E. Bulletin 8047: Jet Pump l
- Assembly Failure. Ultrasonic Examination of jet pump hold down 1 beams once each ISI Interval.
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SECOND IWIWrvAL MEWMrE INSPECm0N PL#f f
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LAsutscouwn wucasuisimou nonsowi ascono m erva mensenowetAn SECTION 3 - DRAWINGS
- O LASALLE COUNTY NUCLEAR STATION ISI CLASSlFICATION BOUNDARY DRAWINGS
, SYSTEM UNIT 1 UNIT 2 ACRONYM j DWG. NO. DWG. NO.
MAIN STEAM M-55 M-116 MS EXTRACTION STEAM M-56 M-117 ES i FEEDWATER M-57 M-118 FW DRYWELL PNEUMATIC M46 M46 IN I CYCLED CONDENSATE STORAGE M-74 M-127 CY CLEAN CONDENSATE STORAGE M-75 M-75 MC INSTRUMENT AIR M-81 M41 lA SERVICE AIR M42 M42 SA DIESEL GENERATOR AUXIUARY M43 M-83 DG DIESEL OIL M-85 M-132 DO M46 VP
'O PRIMARY CONTAINMENT CHILLED M-133 WATER i
CSCS EQUIPMENT COOUNG WATER M47 M-134 REACTOR BUILDING CLOSED COOUNG M-90 M-136 WR WATER REACTOR BUILDING EQUIPMENT M-91 M-137 RF DRAINS PRIMARY CONTAINMENT VENT AND M-92 M-138 VQ
- PURGE l NUCLEAR BOluNG AND REACTOR M-93 M-139 NB & RR RECIRCULATING
- LOW PRESSURE CORE SPRAY M-94 M-140 LP,LPCS HIGH PRESSURE CORE SPRAY M-95 M-141 HP,HPCS RESIDUAL HEAT REMOVAL M-96 M-142 RH,RHRS l REACTOR WATER CLEANUP M-97 M-143 RT FUEL POOL COOUNG AND M-98 M-98 & FC DEMINERAUZING M-144 STANDBY UQUID CONTROL M-99 M-145 SC CONTROL ROD DRIVE HYDRAUUCS M-100 M-146 RD REACTOR CORE ISOLATION COOLANT M-101 M-147 Rl, RCIC 3-2 l
f 1 LAGALLE COLMTy am mM tiTAfl0N fWvtWON 1 UMTS142 GMB40 auxne wreevat mSBMCE DGPECDON PUW i
i SYSTEM UNIT 1 UNIT 2 ACRONYM j DWG. NO. DWG.NO.
1 CONTAINMENT COMBUSTIBLE GAS M-130 M-130 HG l
- CONTROL l j CONTAINMENT MONITORING M-156 M-158 CM l
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V samanas sempre memenn suerse amessem i erse a e a enge-as seman n- ummernes summerne sim T nent.Y2 COUNTE NUCIERR STATIM IsI IsCBETRIC DRMrINSS UNIT 1 UMT2 SYSTEM DRAWING NUMBER (S) DRAWING NUMBER (S)
FUEL POOL COOLIIIS Att DBEINERALIEIROS IST-FC-1029 ISI-WC-2006, 2007 FRENELTER ISI-FW-1001 TWtOUSE ISI-Ftr-1003 ISI- N-2001, 2, 4, 5 RISE Pammerm CostE SPUIAY 181-57-10G1 T w enamISI-EP-1007 181-57-2001 T - SI-EP-2004 ,
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Z81-985-1901 T=='r 181-885-1010, 181-905-2001 T""= ISI-tes-2004, ,
1012,1014,1016,1018,1019,1022,1024, S,6,7,9,9,10,12,14,16,10,20,22,24,24, 1026,1029,1030,1032,1034. 28,30,32,34 181-95-1936 TWIDUEE ISI-tes-1044 181-805-2034 T M 181-35-2046 ISI-TAB-1049 TWIDOWE 181-405-1949 151-05-2048 T m 181-05-2049 181-905-1051 Tamarar 181-005-1055 181-808-20S1 T - ISI-ten-2058 !
man E0ILEBL ISI-IS-1001 Tamamm 181-05-1902 ISI-te-2001 T - 181-55-2002 ISI-Rpt-1001 TWWUeE ISI-35L-1003 ISI-BWL-2001 T=== ISI-35L-2003 i ISI-55L-1905 Tum'ar= ISI-EWL-lete ISI-Bet-2005 T - *'m ISI-35L-2010 i EtEACTOOL CaptB ISOBATIcet C00BA30T ISI-5LI-1001 Tman= " ISI-RI-1003 ISI-BLI-2001 T=m ISI-BLI-2003 8
BSACTOBL DELTEBL CIAABEUF ISI-Otf=1001 ISI-It2-2001 ISI-mE-1001 T===<== ISI-se-107e ISI-se-2001 T-== ISI-se-20s4 ISI-35-1124 T"ar= 181-55-1128 IIft-55-2098 TWIOUEE 181-55-2003 i
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!1 UNIT 2 ISI
SUMMARY
TABLE 1
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, tMTS 1 & 2 ONHS SECOHO INTINIVAL IMelifMCE IMAPECTION PLAN i
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1 UNIT 1 COMPONENT SUPPORT INSPECTION
SUMMARY
TABLE I
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TABLE j
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SECTION 8 l
< l O ISI COMPONENT RELIEF REQUESTS l
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unaus y suam nevu a escae nsnumseux camm.m SECTION 8 - RELIEF REQUESTS
,O ISI COMPONENT RELIEF REQUEST INDEXISUMMARIES RE pE . # PAGE(S) REV. DATE
SUMMARY
CR-01 8-4 thru 8-8 1 02 02-96 Inaccessible welds located at containment penetration assemblies CR-02 8-9 thru 8-11 1 02-02-96 Inaccessible branch pipe connections located under reinforced saddle CR-03 8-12 10-17-94 WITHDRAWN during 02 96 Revision 1 submittal, CR-04 8-13 thru O 10-17-94 Expansion criteria for welds 8-14 governed by Generic Letter 1 88-01 and NUREG-0313 CR-05 8-15 0 10-17-94 WITHDRAWN during 02 (] 96 Revision 1 submittal CR-06 8-16 thru O 10-17-94 Use of alternative examination 8-17 aquirements, examination method, and acceptance standarrt for the reactor vessel closure head nuts CR-07 8-18 thru 0 10-17-94 Reactor vessel closure stud 8-20 examination requirements CR-08 8-21 thru 0 10-17-94 Exemption of piping, valves, 8-22 and fittings 1" NPS and smaller and their associated supports from the requirements of Article IWA-4000 CR-09 8-23 thru f 0 10-17-94 Examination of Head Spray, 8-24 Head Vent, and Spare Nozzle l Inner Radii CR-10 8-25 0 10-17-94 WITHDRAWN during 02 96 Revision i submittal 8-2 l
= . - -
=
m 10 ""W";
E. exas aav. Dars su==^av CR-11 8-26 thru 0 10-17-94 Use of Technical 8-27 Specifications for visual examination of Code Class i Snubbers CR-12 8-28 thru 1 02-02-96 Examination of component 8-29 supports located in the Suppression Pool CR-13 8-30 10-17-94 DELETED 1 1
CR-14 8-31 thru 0 10-17-94 WITHDRAWN during 02 i 8-32 96 Revision 1 submittal CR-15 8-33 thru 0 10-17-94 Examination of Longitudinal i 8-35 Welds in Piping CR-16 8-36 thru 0 10-17-94 Examination of CRD Housing 8-37 Bolting 9
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RELIEF REQUEST CR-01
! REVISION 1
- (Page 1 of 5)
COMPONENT lDENTIFICATION i
i Code Cass: 1 and 2
}
References:
- Table IWB-2500-1, IWC-2500-1 Examination Categories: B-J, C-F-2
- Item Numbers
- B9.11, B9.12, C5.51, C5.52
Description:
Inaccessible Welds Located at Containment Penetration i Assemblies I Component Numbers: See Table CR 01.1 ,
CODE REQUIREMENT lWB-2500 and IWC-2500 state that components shall be examined and tested as j j specified in Table IWB-2500-1 and IWC-2500-1, respectively, i
i Table IWB-2500-1 requires volumetric and surface examination to be performed on t
circumferential and longitudinal welds 4" NPS and larger, and surface examination to be performed on circumferential welds less than 4" NPS.
Table IWC-2500-1 requires volumetric and surface examination to be performed on j circumfe.rential and longitudinal welds on piping that has nominal well thickness
[ greater than or equal to %" and diameter greater than 4" NPS.
! BASIS FOR RELIEF l
- Each of the lines identified in Table CR-01.1 penetrates the primary containment, j secondary containment, or wall by means of a penetration assembly similar in design i to those shown in Figure CR-01.1 or CR-01.2. These lines, due to the design of the 1
penetration assembly, have one circumferential pressure retaining weld that is inaccessible for surface and volumetric examination.
[ As stated in 10 CFR 50.55a(g)(4), throughout the service life of a boiling or pressurized water-cooled nuclear facility, ASME Class 1,2, and 3 components must meet the requirements set forth in the applicable ASME Section XI to the extent practical within the limitations of design, geometry and materials of construction of the components.
l
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secaewrammesmas ecmnm T5 RELIEF REQUEST CR-01
'O REVISION 1 (Page 2 of 5)
- Figure CR-01.1 and CR-01.2 dearly illustrate the design constraints which make the
- subject welds inaccessible for examination by surface or volumetric examination technique.
i Based on the above reasons, LaSalle Station requests relief from the ASME Section i XI requirements for surface and volumetric examination of the subject welds.
PROPOSED ALTERNATE EXAMINATION As an altamate examination, LaSalle Station will perform a VT-2 examination of the i annular area of each of the subject penetration assemblies in conjunction with the i
Class 1 or Class 2 pressure tests, whichever is applicable.
l APPLICABLE TIME PERIOD l Relief is requested for the second ten-year interval of the Inservice inspection Program for LaSalle Units 1 and 2.
O l,
.O 8-5
ewus g= wuoi neveme RELIEF REQUEST CR-01
~O REVISION 1 1
j
- TABLE CR-01.1 l INACCESSIBLE CONTAINMENT PENETRATION WELDS i
j' SYSTEM CLASS LINE NUMBER PENETRATION FIGURE Main Steam 1/2MS01EA-26" M-1 CR-01.1 f 1 Main Steam 1 1/2MS01EB-28" M-2 CR-01.1
! Main Steam 1 1/2MS01EC-26" M-3 CR-01.1 Main Steam 1 1/2MS01ED-26" M-4 CR-01.1 l
Main Steam 2 1/2MS01BA-28" N/A CR-01.1
- Main Steam 2 1/2MS01BB-28" N/A CR-01.1 l l Main Steam 2 1/2MS01BC-26" N/A CR-01.1 Main Steam 2 1/2MS01BD-26" N/A CR-01.1 '
! Feedwater 1 1/2FW02FA-24" M-5 CR-01.1 a
j Feedwater 1 1/2FW02FB-24" M-8 CR-01.1
! RCIC (RI) 1 1/2R101-10" M-15 CR-01.2 i
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i RELIEF REQUEST CR-01
- Q REVISION 1 (Page 4 of 5) i
' i FIGURE CR-01.1 CONTAINMENT / WALL PENETRATION 4
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, sum.o wram umoms m ps: Tow etu.
, RELIEF REQUEST CR-01 aavisioa $
iO
'; (Page 5 of 6) i
- FIGURE CR-01.2 i CONTAINMENT / WALL PENETRATION i
i CDWTAINNT WALL , DRTWEli PfMETMil0R SLttyt
! PENETRATIM PIPE ,
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RELIEF REQUEST CR-02 vO;
<esas , or n REVISION 1 .
l COMPONENT IDENTIFICATION i !'
Code Class: 2 i
References:
IWC-2500 i i Table IWC-2500-1 l Examination Category: C-F-2 ;
l Item Numbers: C5.81, C5.82 i
Description:
Branch Connection Wolds Designed with 1 Reinforcing Plates 4
Component Numbers: Class 2 Main Steam Header Branch Connection i j Welds l
j CODE REQUIREMENT
- IWC-2500 states that components shall be examined and tested as specified in Table ;
i IWC-2500-1. J
- Table IWC-2500-1 requires surface examination to be performed on branch pipe
! connection wolds greater than 2" NPS.
l l BASIS FOR RELIEF 1
- The design of ten (10) Class 2 branch pipe connection welds calls for the use of l
reinforcing saddles. These saddles are fillet welded over the actual pressure retaining l branch pipe-to-main pipe weld, completely encasing it as illustrated on Figures CR-i 02.1. These designs preclude any type of surface or volumetric examination from i being performed on the pressure retaining branch connection weld. However, l additional assurance of the integrity of these joints is afforded by the fact that the j reinforced saddle strengthens the joint and reduces the stresses on the internal weld.
l Based on the above reasons, LaSalle Station requests relief from the ASME Section i XI requirements for the surface and volumetric examination of Class 2 branch pipe j connection welds that are designed with a reinforcing saddle.
PROPOSED ALTERNATE EXAMINATION i
As an alternate examination, LaSalle Station will perform a VT-2 examination of these !
Joints in conjunction with the required Class 2 System Pressure Tests.
lO 8-9 1
1
lASALLE COUNTY 14JCLEAft STATION IEVISION 1 LNTS 1 & 2 034 4 seCO=0 menvAt -Imcc-senOu a l
1 i
RELIEF REQUEST CR-02 l
.O
< P..e 2 .< >> ;
j REVISION 1 1
i
- APPLICABLE TIME PERIOD !
! Relief is requested for the second ten-year interval of the inservice Inspection l l Program for LaSalle Units 1 and 2.
i 1
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8-10
3 LASALLE COUNTY NUCLEMt STATION fERSON1 UlsTS 1 & 2 034340 SECOND sfrstvAL INSEf4WICE INSPECTION PLAN RELIEF REQUEST CR-02 i (Page 3 of 3)
- REVISION 1 1
i
- Fillet Welds a
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- Retaining g
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8-11
. - . - - - - .. .. . --. . . _ _ . - , - . -. . - _ . . . . . . ~ _ -. . . . . . -- - . _ . _ .
d LAAALAR COLMfY NJCIAAft STATION IWWISION 1 ,
LAST S1&2 EMMb l o wrewat m x m-senONauf
\
a 4
d RELIEF REQUEST CR-03
- (Page 1 of 1) i ,
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RELIEF REQUEST DELETED i
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1 RELIEF REQUEST CR-04 (Page 1 of 2) i i COMPONENT IDENTIFICATION I
j Code Class: 1
References:
IWB-2430 i Examination Categories: B-F, B-J
- Item Numbers: B5.10, B5.130, B9.11, B9.31
Description:
Expansion Criteria for Wolds Govemed by Generic Letter
, 88-01 and NUREG-0313 Rev. 2 '
4 Component Numbers: All full penetration circumferential and branch pipe
- connection welds in austenitic stainless steel piping that is i
4" NPS or larger and contains reactor coolant at a temperature greater than 200 dog F during power operation
, CODE REQUIREMENT l
l IWB-2430 outlines the additional examinations that must be performed when
- indications are found that exceed the acceptance standards of IWB-3000.
BASIS FOR RELIEF
!O i Each of the subject welds fall under the augmented inspection program required by l Generic Letter 88-01 and NUREG-0313, Rev. 2. This program governs examination j methods, examination frequency, and sample expansion. The sample expansion l requirements of this program are designed such that additional examinations are limited to welds that have the same susceptibility to intergranular Stress Corrosion
outage, while not requiring expenditure of the Man-Rom and outage time associated l with examining additional low risk welds.
' in many instances, the examinations performed to meet the requirements of Generic Letter 88-01 are also applied to the percentages required by ASME Section XI. In these cases it is not practical to apply the expansion criteria of both Generic Letter 88-
, 01/NUREG-0313 and ASME Section XI when unacceptable IGSCC flaw indications l are identified.
l Based on the above, LaSalle Station requests relief from the ASME Section XI
, requirements for additional examinations when unacceptable flaw indications are
- identified in the subject welds.
i.
I O
l 8-13
,m,. .__. _ _ ,
u.m cann esco.e .n = =
_ 7== m .cra m w RELIEF REQUEST CR-04 (Page 2 of 2)
PROPOSED ALTERNATE PROVISIONS LaSalle Station will perform sample expansions as required by Generic Letter 88-01 and NUREG-0313, Rev. 2 when unacceptable IGSCC flaw indications are identified in the subject welds.
APPLICABLE TIME PERIOD Relief is requested for the second ten-year interval of the Inservice inspection program for LaSalle Units 1 and 2.
O i
i l
l O
- 8-14
LAS4UK COUNM NUCLEAR STAfl0N 1EMWON1 UpsTS 1 & 2 I 084He SE00pm INTWtvAL IMagMM IMAPECTION PLAN l l
1 4
i r RELIEF REQUEST CR-05 4 (Page 1 of 1) j i
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, RELIEF REQUEST DELETED 1
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.sco wrmim ans w a uneenownm 1
RELIEF REQUEST CR-06
- O < < r =>
l COMPONENT IDENTIFICATION 1
I Code Class: 1
References:
- Table IWB-2500-1 i Examination Category: B-G-1 4 Item Number: B6.10
Description:
Use of Alternative Examination l Requirements, Examination Method, and Acceptance Standard for the Reactor l Vessel Closure Head Nuts j CODE REQUIREMENT i
- IWB-2500 states that components shall be examined and tested as specified in Table IWB-2500-1.
i l Table IWB-2500-1 requires a surface examination to be performed on reactor vessel
! dosure head nuts.
O BASIS FOR RELIEF j Table IWB-2500-1 of the 1989 Edition of ASME Section XI requires a surface
! examination to be performed on the reactor vessel closure head nuts. However, Table IWB-2500-1 does not provide the corresponding " Examination j Requirements / Figure Number" and " Acceptance Standard". These provisions were j stillin the course of preparation.
The incomplete set of rules for the examination of reactor vessel closure head nuts j does not allow LaSalle Station to implement an inspection program to verify the
! integrity of this pressure retaining bolting.
l
! The 1989 Edition of ASME Section XI, Category B-G-1, requires a VT-1 examination i for closure nuts associated with heat exchangers, piping, pumps, and valves (item j numbers B6.140, B6.170, B6.200, and B6.230, respectively). These Category B-G-1 requirements also provide an acceptance standard, IWB-3517, for the VT-1 l examinations. Accordingly, these rules are deemed by LaSalle Station as an l acceptable and complete to assure the integrity of the reactor vessel closure nuts.
Based on the above, LaSalle Station requests relief from the requirements specified in l Table IWB-2500-1 of the 1989 Edition of ASME Section XI for reactor vessel closure i
head nuts.
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LAAALLE COUMW MJQ.EAft STATION MVISOM 1
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RELIEF REQUEST CR-06 (Page 2 of 2) 1 PROPOSED ALTERNATE POSITIONS As an altemate examination, LaSalle Station will perform a VT-1 examination of the j surface of all reactor closure head nuts, utilizing the acceptance criteria of IWB-3517, as delineated in the 1989 Edition of ASME Section XI.
APPLICABLE TIME PERIOD Relief is requested for the second ten-year interval of the Inservice Inspection g Program for LaSalle Units 1 and 2.
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tAnnus couwry armou neneau i smooiewrewau wiesme ectiona RELIEF REQUEST CR-07 (Page 1 of 3)
! COMPONENT IDENTIFICATION li Code Class: 1
References:
Table IWB-2500-1 lWB-2430 j Examination Category: B-G-1
- Item Number- B6.20 (in Place)
B6.30 (When Removed)
Description:
Reactor Pressure Vessel (RPV) Closure i Stud Examination Requirements
! l j CODE REQUIREMENT
- l Table IWB-2500-1 requires a volumetric examination of reactor vessel dosure studs if !
j left in place, or a surface and volumetric examination of reactor vessel dosure head l studs when removed from the flange. Removal is not a requirement at any time. l l IWB-2430 requires additional examinations to be performed during the current outage if examinations performed in accordance with Table IWB-2500-1 reveal indications i exceeding the acceptance standards of Table IWB-3410-1. If indications exceeding i the acceptance standards of Table IWB-3410-1 are found as a result of the additional l examinations, lWB-2430 requires examinations to be further extended in the current outage to indude "the remaining number of similar components ... within the same l category ..."
i j BASIS FOR RELIEF 1
Commonwealth Edison Company (CECO) discovered extensive stress corrosion cracking (SCC) in two reactor vessel dosure studs at Dresden Unit 2 in late 1988.
- CECO is pursuing a proactive program of enhanced stud inspections, which exceeds I the requirements of Section XI and the recommendations of General Electric Nudear i l Energy (GE) Rapid information Communication Services Information Letter (RICSIL) i 055, Revision 1, " Reactor Pressure Vessel Head Stud Cracking," dated September 30, 1991. The CECO orogram is also intended to indude some of the additional
! recommendations o.' Qegulatory Guide 1.65. 1 j GE RICSIL 055 recommends that enhanced and shot ultrasonic testing (UT) be j
- performed on "at least five RPV head studs either during the next refueling outage or )
! at the next available opportunity." However, for the second ten-year interval LaSalle i
Station plans to perform the enhanced end shot UT on all RPV dosure head studs (68 In Unit 1,76 in Unit 2). The enhanced end shot UT technique developed by CECO
.O
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- oona.mmm == menow-RELIEF REQUEST CR-07 (Page 2 of 3) i 3.5 MHz or 5 MHz; the sensitivity of the examination is maximized by setting the background noise level at about 5% full screen height. This technique reliably detects
, bore probe UT technique developed by CECO reliably detects a 0.1" deep saw cut 4 I
l notch.
At each refueling outage LaSalle Station also plans to remove, if practicable, I i approximately 12 of the total number of RPV studs (i.e.12 in Unit 1,13 in Unit 2)
are normally removed each outage to allow for the installation of the " Cattle Chute" l will be excluded from the sample because they are not exposed to water at the end of 1
- a refueling outage. ,
i There are several reasons for removing a sample of studs during the second ten- year
- interval for surface examination:
J I To provide data on incipient of stud cracking.
l To allow for additional metallurgical evaluation of cracking mechanisms and i potential embrittlement phenomena, if cracked studs are found and j replaced.
To provide a correlation between the enhanced and shot UT, bore probe UT, j and MT results, if cracked studs are found.
i i This information is necessary to make informed decisions on long-term j inspection / replacement strategies.
1
! Code structural margins will be assured through the enhanced and shot UT of all
] studs, and bore probe UT sizing of all cracked studs. Enhanced end shot UT and i bore probe UT results will be evaluated in accordance with " Fracture Mechanics i Based Structural Margin evaluation for Commonwealth Edison BWR Reactor Pressure l Vessel Head Studs", GE Nuclear Energy Report GE-NE-523-93-0991, DRF 137-0010, September 1991 [ submitted with a M. H. Richter (CECO) letter to T. E. Murley (NRC) dated October 3,1991). The GE structural margin evaluation is based on a conservative fracture mechanics methodology and actual fracture toughness testing of material from one of the low-toughness Dresden Unit 2 studs. If the end shot UT is i found to be nonconservative, then an expanded sample with more sensitive bore probe U,T will be performed. This approach will assure that Code structural margin
- are maintained without expanding the MT sample.
Results of the enhanced end shot UT, bore probe UT, and MT will be compared in j order to benchmark the minimum detection limit of the enhanced and shot UT 8-19
umasone == wnm newsm esco .ns== sma enoww RELIEF REQUEST CR-07 l (Page 3 of 3) i technique. The minimum detection limit of the enhanced and shot UT technique will l be judged against a conservative, bounding maximum allowable flaw size (established
examinations will be performed in lieu of the Section XI required MT sample
}'
expansion.
Expanding the MT sample if unacceptable surface indications are found would greatly l ' increase the critical path time and radiation exposure burden during the outage. And, l as other utilities have found, it may be impossible to remove the desired sample of l i studs, without damage, within the constraints of a refueling outage. It is estimated :
! that complete removal of all studs, assuming no stuck studs, would take 8 additional l critical path days and expend 7 additional person-rom. I i !
i The proposed program is highly proactive, in that Section XI only requires a normal I
{ sensitivity and shot UT to be performed in place, and RICSIL 055 only recommends l enhanced and shot UT of at least 5 studs, in accordance with Section XI, structural
much essential information could be gained by surface examination of a limited O ai <id r r ia <
expansion requirements of Section XI IWB-2430.
.cec<a
- r ii < <r - ** a r ai-4 j PROPOSED ALTERNATE EXAMINATION i
In lieu of the ASME Section XI requirements for items B6.20 and B6.30, at each i refueling outage each RPV closure stud will be will be examined in place using
!- enhanced end shot UT. Any flaws detected with the enhanced and shot UT will be sized using the bore probe UT. If an MT examination of a sample of studs reveals indications which are found by bore probe UT to exceed the maximum allowable flaw size, and were not detected by the enhanced end shot UT, then sample expansion will
. proceed using the bore probe UT in lieu of the ASME Section XI required MT sample i expansion.
l APPLICABLE TIME PERIOD
- Relief is requested for the second ten-year interval of the Inservice inspection Program for LaSalle Units 1 and 2.
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unamon
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I RELIEF REQUEST CR-08 i (Page 1 of 2)
- COMPONENT IDENTIFICATION 4
i Code Class: 1, 2., and 3 i
References:
IWA 4000 i IWA-7000 I Examination Category: Not Applicable j ltem Number: Not Applicable
Description:
Exemption of Piping, Valves, and Fittings 1" NPS
- and Smaller and Their Associated Supports from the
. Requirements of Article IWA-4000, Repair
! Procedures.
i
{ CODE REQUIREMENT )
i i Repair activities on piping, valves, and fittings 1" NPS and smaller must meet the l requirements of Article IWA-4000.
! BASIS FOR RELIEF i
4 The rules goveming the Repair Procedures, IWA-4000, allow repairs to be performed in accordance with the Owners Design Specifications (ODS) and the Original
, Construction Code (OCC) in lieu of the rules of Section XI as detailed in IWA-4120.
]
l When repairs are performed on ASME Section XI Class 1,2, and 3 components in
! accordance with the ODS/OCC, the requirements of IWA-4130, Repair Program; IWA-
! 4140, inspection; IWA-4600, Preservice Examination; IWA 4700, Pressure Test; and i IWA-4800, Records, remain applicable. At LaSalle Station, the repairs performed to j rules of the ODS/OCC and associated procedures are subject to equivalent
! requirements as the rules of paragraphs IWA-4200, Material; IWA-4300, Defect i Removal; IWA-4400, Welding and Walder Qualifications; and IWA-4500, Repair l Welding.
Repairs performed on ASME Section XI Class 1,2, and 3 components that are 1" l NPS and smaller are neither subject to the preservice examination requirements of i IWA-4600 (per IWB-2200, IWC-2200, and IWD-2200) nor to the pressure test
! requirements of IWA-4700.
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! RELIEF REQUEST CR-08
- (Page 2 of 2) l l i Consequently, if repairs on ASME Section XI Class 1,2, and 3 components that are 1" NPS or smaller are not subject to the repair procedures of IWA-4000, the only requirements not being addressed are IWA-4130, Repair Program; IWA-4140,
! Inspection (Authorized inspection Agency involvement); and IWA-4800, Records.
, implementation of the requirements listed in this paragraph only creates an additional administrative burden that does not provide a compensating increase in j the level of quality or safety. This is illustrated by the fact that the corresponding
- ASME Section XI rules for replacement of IWA-7000 allows the Owner to replace the
! same piping, valves, fittings, and associated supports (i.e.1" NPS and smaller) without being subject to similar ASME Section XI requirements.
l Based on the above reasons, LaSalle Station requests relief from the requirements of l
! IWA-4000 when performing repair activities on 1" NPS and smaller piping, valves, fittings, and associated supports.
, PROPOSED ALTERNATE EXAMINATION i i !
j LaSalle Station will perform and document repairs on 1" NPS and smaller piping, valves, fittings, and associated supports in accordance with the Commonwealth Edison Company Quality Assurance Program, which implements the criteria of 10CFR50, Appendix B, applicable Design Specifications and Construction Codes.
! APPLICABLE TIME PERIOD i
! Relief is requested for the second ten-year interval of the inservice inspection
- Program for LaSalle Units 1 and 2.
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asooie wesemE.meerion a RELIEF REQUEST CR-09 (Page 1 of 2) l i
- COMPONENT IDENTIFICATION i
j Code Class: 1 .
References:
IWB-2500 Table IWB-2500-1 j Examination Category: B-D i item Number: B3.100 l
Description:
Examination of Head Spray, Head Vent, and Spare l
Nozzle Inner Radii -
l Component Numbers: N7, N8, and N18 :
l CODE REQUIREMENT IWB-2500 states that components shall be examined and pressure tested as specified l In Table IWB-2500-1.
Table IWB-2500-1 requires a volumetric examination to be performed on the inner j radius section of all reactor vessel nozzles each inspection interval. ;
}
BASIS FOR RELIEF l
The subject nozzles are located on the reactor vessel head. Access to the inner f
, radius section of these nozzles is possible because the reactor vessel head is removed each refueling outage.
! Service induced flaws are expected to initiate and grow from the inside surface of the
- nozzle inner radius section. Therefore, a surface examination performed on the j nozzle inner radius section surface is judged to be more sensitive than a volumetric examination performed from the outside surface of the nozzle.
i Based on the above, LaSalle Station requests relief from the volumetric examination i requirement specified in Table IWB-2500-1 of the 1989 Edition of ASME Section XI for
- the subject nozzle inner radius sections.
- PROPOSED ALTERNATE EXAMINATION
- LaSalle Station will perform a surface examination of the nozzle inner radius surface j at the same examination frequency specified by Table IWB-2500-1 for Category B-D.
The surface examination area will be area "MN" as described in ASME Section XI, Figure IWB-2500-7. -
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3 LAAALLS COUNTY 0&K15 Aft STJ.ft0N fWWISON 1 4 UNITS 1 & 2 GB4340 coe wre n m a =enom a j RELIEF REQUEST CR-09 2
(Page 2 of 2)
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APPLICABLE TIME PERIOD 1
j Relief is requested for the second ten-year interval of the inservice inspection j Program for LaSalle Units 1 and 2.
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LASALLE COUNTY NUC1EMt STATION SEWIDON 1 i UMTS 1 & 2 mm smocnewrs=AL emce senaNw 4
1 i RELIEF REQUEST CR-10 l5 (Page 1 of 1) 4 1
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LAAALLE f%BitY Nut 15AR sfATION IWASON 1 como wr m o E menon -
4 RELIEF REQUEST CR-11 (Page 1 of 2)
! COMPONENT IDEN11FICATION Code Class: 1,2,3
{
Reference:
IWF-5200(a)
J IWF-5300(a) i Examination Category: Not Applicable
! Item Numbers: Not Applicable
Description:
ISI Snubbers included in the Technical Specification i Snubber Visual and Functional Examination Program.
l CODE REQUIREMENTS
' Preservice examination per IWF-5200(a) and Inservice examination per IWF-5300(a) in accordance with the first addenda to ASME/ ANSI OM-1987 Edition, Part 4, i
published in 1988 (OMa-1988, Part 4, per 10CFR50.55a, paragraph (b)(2)(viii),
! published August 6,1992).
- BASIS FOR RELIEF i
l The current LaSalle Technical Specifications (TS) include comprehensive program for
. visual examination and functional testing of all safety related hydraulic and mechanical 1
l Of the approximate total of 240 safety related snubbers per unit, approximately 215 i are Code Class. The overlap of the visual examination and functional test programs
- per ASME Section XI and Technical Specifications for Code Class snubbers presents
- an unnecessary redundancy without a compensating increase in the level of quality l and safety. 1 i ,
! The TS snubber visual examination program requires a sample size of 100% of all !
, safety related snubbers and incorporates the altemate snubber visual examination
- delineated in US NRC Generic Letter (GL) 90-09. As determined by the NRC Staff, ;
1 the attemate schedule of GL 90-09 maintains the same confidence level of quality and safety as the previous TS schedule, which was very similar in content to that of OMa- ;
1988, Part 4.
1 The GL 90-09 altamate schedule is based on the number of unacceptable snubbers found during the previous examination in proportion to the sizes of the various j snubber populations or categories. The altamative examination interval is based on a
- fuel cyde of up to 24 months and may be as long as two fuel cycles, depending on the number of unacceptable snubbers found during the previous visual examination.
i b"2b
l sW secae wrenw asemca mancem u "amA c
l RELIEF REQUEST CR-11 (Page 2 of 2) l l The TS snubber functional test program contain the sampling plans described in OMa-1988, Part 4. In the event of a snubber fails to meet the functional test acceptance criteria, the TS required additional testing samples and required corrective actions are
- equal to or more conservative than those specified in OMa-1988, Part 4.
! Based on the reason that the TS anubber visual examination and functional test programs maintain the same or better levels of quality and safety as that of OMa-1988, Part 4, LaSalle Station requests that the TS visual examination and functional test programs for snubbers be used in lieu of the OMa-1988, Part 4 visual examination j and functional test programs required by ASME Section XI, Subartides IWA-5200(a)
- and IWA-5300(a).
1 l PROPOSED ALTERNATE PROVISIONS 1
- LaSalle Station will perform visual examinations and functional tests of Code Class l snubbers in accordance with the snubber examination and test programs contained in j the latest approved revision the Technical Specifications in lieu of the OMa-1988, Part i 4 visual examination and functional test programs required by Subartides IWF-5200(a) i and IWF-5300(a).
iO
- Visual examiners, who are qualified to the applicable rules of ASME Section XI Artide IWA-2000, will perform the examinations Code Class snubbers. Visual examination j and functional test results of Code Class snubbers will be recorded and reported in j accordance with the applicable rules of ASME Section XI Artide IWA-6000.
APPLICABLE TIME PERIOD l Relief is requested for the second ten-year interval of the Inservice inspection
] Program for LaSalle Units 1 and 2.
]
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LAGAM COLWTY 94K15 Aft MADON IWWIm0N 1
.mx =v wl." MEA! cnow-in U RELIEF REQUEST CR-12 REVISION 1
- (Page 1 of 2)
! COMPONENT IDENTIFICATION Code Class: 2&3
References:
Code Case N-491 IWF-2000 Code Case N-491 Table IWF-2500-1
)l Examination Categories:
Code Case N-491 IWF-2430 F-A i
- Item Numbers
- F1.10 through F1.40
Description:
Examination Component Supports
!' Component Numbers: HPCS, LPCS, RHR, RCIC Class 2 MS Class 3 Component Supports in Suppression Pool
, CODE REQUIREMENT IWF-2500 of Code Case N-491 states that component supports shall be examined in
'. accordance with Table IWF-2500-1.
Table IWF-2500-1 of Code Case N-491 requires a VT-3 examination on 15% of Class j 2 component supports.
l Table IWF-2500-1 of Code Case N-491 requires a VT-3 examination on 10% of Class l 3 component supports.
j IWF-2430 of Code Case N-491 requires examination on additional component j supports when corrective measures in accordanc6 with IWC-3000 or IWD-3000 is required on component support.
l BASIS FOR RELIEF
! There are a number of guides and rigid struts on the subject systems that are located
- in the Suppression Pool. In order to perform a meaningful VT-3 examination in accordance with ASME Section XI on these supports, removal of surface residues would be necessary prior to examination.
The cleaning process would be relatively involved and would present safety and l contamination hazards to personnel involved. The Suppression Pool would most likely need to be drained and scaffolding erected for this cleaning process. Therefore, a VT-l 3 examination on these components is considered to be impractical.
!O 8-28
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LASALLE COUNTY DAJCLEAR STATION REvteON 1 i aeCo.e u n m E . w ecriON u RELIEF REQUEST CR-12 iO REVISION 1 (Page 2 of 2) l Based on the above reasons, LaSalle Station requests relief from the ASME Section XI/ Code Case N-491 requirements for the VT-3 examination of the subject component i
supports.
j PROPOSED ALTERNATE EXAMINATION
! LaSalle Station will perform a general visual inspection of the Suppression Pool
,, internal structural elements for evidence of apparent changes in proper pipe support orientation. This inspection will not be a VT-3 examination that is defined by ASME Section XI. The general visual inspection will be performed during reactor shutdown prior to each Type A Containment Leak Rate Test, thus exceeding the examination frequency of ASME Section XI/ Code Case N-491.
APPLICABLE TIME PERIOD l Relief is requested for the second ten-year interval of the Inservice inspection
- Program for LaSalle Units 1 and 2.
- O I
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. u.aur eauNrv ama == - .o ,
umsien on.asas MIC0pm WrplVAL INGSIVICE INSPEC"flON PLAN l l
i
' RELIEF REQUEST CR-13 1 (Page 1 of 1) i I
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asco.owrew u em m aw ecra eum RELIEF REQUEST CR-14 (Page 1 of 2)
COMPONFNT IDENTIFICATION l Code Class: 1
References:
IWB-2500 Table IWB-2500-1
- Figure IWB-2500-14 Examination Category: B-H d
item Numbers: 88.10
Description:
Examination of Reactor Vessel Support Skirt to
, Reactor Vessel Bottom Head Weld.
I Component Number: Unit 1: IVS-1 l Unit 2: IVS-1 CODE REQUIREMENT IWB-2500 states that components shall be examined and tested as specified in Table
i
, Table IWB-2500-1 requires a surface examination to be performed on areas A-B and C-D of Figure IWB-2500-13.
l BASIS FOR RELIEF l
The vessel support skirt is attached to the reactor vessel bottom head by means of a full penetration butt weld. Access to the root area of the weld is limited because of
, (1) a severe angle between the vessel bottom head and vessel support skirt and (2)
! close proximity of the control rod drive housings to the inner surface of the vessel l support skirt. Therefore, the surface examination requirements of Figure IWB-2500-13 i (examination area C-D) cannot be met due to the lack of accessibility.
Based on the above reasons, LaSalle Station requests relief from the ASME Section XI, surface examination requirements of Figure IWB-2500-13, examination area C-D.
i I
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SEcose INTWEVAL INSPECTION PLAN i
RELIEF REQUEST CR-14 lO < =< >>
PROPOSED ALTERNATE EXAMINATION LaSalle Station will perform a surface examination on the accessible side of the
, subject weld (examination area A-B).
- APPLICABLE TIME PERIOD J
Relief is requested for the second ten-year interval of the Inservice inspection j Program for LaSalle Units 1 and 2.
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(Page 1 of 3) i COMPONENT IDENTIFICATION i
Code Classes: 1 and 2
References:
IWB-2500 Table IWB-2500-1
! Table IWC-2500-1 Examination Category: B-J C-F-1, C-F-2 1
Item Numbers: B9.12, B9.22 1 C5.12, C5.22, C5.42, C5.52, C5.62, C5.82 '
j
Description:
Examination of Longitudinal Wolds in Piping.
Component Number: Various
! CODE REQUIREMENT l
l IWB-2500 states that components shall be examined and pressure tested as speedied in Table IWB-2500-1.
- Table IWB-2500-1 requires surface and volumetric examinations (piping welds 4" NPS j or larger) or surface examination (piping welds less than 4" NPS) of at least a pipe-
). diameter length but no more than 12" of each longitudinal weld intersecting the circumferential welds.
i IWC-2500 states that components shall be examined and pressure tested as specified j in Table IWC-2500-1.
! Table IWC-2500-1 requires surface and volumetric examinations (piping welds piping j j welds 2" NPS or larger) or surface examination (pipe branch connections 2" NPS or larger) of 2.5t length from the intersecting circumferential weld.
! BASIS FOR RELIEF
! At each LaSalle unit, there are approximately 100 Class 1 longitudinal welds and 28 Class 2 longitadinal welds that are subject to surface and volumetric examinations.
Examining 100 Class i longitudinal welds would incur approximately 140 man-rom per interval, assuming the average exposure rate of 100 mR/hr. Similarly, examination of 28 Class 2 longitudinal welds would incur approximately 5.6 man-rom por interval,
- assuming the average exposure rate of 20 mR/hr.
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- esco .mswausasummeeenoweva l RELIEF REQUEST CR-15 I (Page 2 of 3) l
examinations were also performed under more favorable conditions. This further I l
increases the confidence level for longitudinal welds.
, To date, there are no evidence of significant loading conditions or imown material )
degradation mechanisms which specifically relate to longitudinal welds. Longitudinal
< weld examinations at LaSalle Units 1 and 2 have not detected any defects compromising piping integrity. This experience is further supported by an industry-l wide survey that found no evidence of longitudinal weld defects compromising safety at nuclear generating facilities. This survey was conducted recently by the ASME 1 j Section XI Task Group on Optimization of ISI.
i Ultrasonic and/or surface examinations of longitudinal welds to the extent required by i' ASME Section XI create radiation and cost burdens without generating significant l added safety benefits.
}O i
Based on the above reasons, LaSalle Station requests relief from the volumetric and/or surface examination requirements specified in Table IWB-2500-1 and IWC-l l 2500-1 of the 1989 Edition of ASME Section XI for the subject longitudinal welds.
! PROPOSED ALTERNATE EXAMINATION
- I LaSalle Station will perform the following: i i
- 1. Surface examination on portions of the longitudinal welds that fall within the !
l examination boundaries of intersecting circumferential welds when only a !
surface examination is required.
i 2. Surface and volumetric examinations on portions of the longitudinal welds that I fall within the examination boundaries of intersecting circumferential welds when j both surface and volumetric examinations are required, provided that:
) (a) Where longitudinal welds are specified, and locations are known, examination requirements will be met for transverse and parallel flaws at the intersection of the welds and for that length of the longitudinal weld j within the circumferential weld examination volume.
!O 8-34 I l
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! (b) Where longitudinal welds are specified, but locations are unknown, or
! the existence of the longitudinal welds is uncertain, the examination requirements will be met for both transverse and parallel flaws within the entire examination volume of the intersecting circumferential welds.
APPLICABLE TIME PERIOD 1 Relief is requested for the second ten-year interval of the inservice Inspection j Program for LaSalle Units 1 and 2.
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1 RELIEF REQUEST CR-16 (Page 1 of 2)
COMPONENT IDENTIFICATION i
Code Class: 1
References:
! Table IWB-2500-1 Examination Categories: B-G-2 4
ltem Numbers: B7.80
)'
Description:
Examination of CRD Housings Bolting l l Component Numbers: N/A i i l
l CODE REQUIREMENT l IWB-2500 states that components shall be examined and pressure tested as specified i in Table IWB-2500-1.
Table IWB-2500-1 requires a VT-1 examination to be performed on CRD housing j bolting when disassembled.
BASIS FOR RELIEF O During each refuel outage a number of control rod drives are disassembled for maintenance. CRD bolts disassembled during these maintenance activities are either discarded or saved for subsequent refurbishment. New bolts are used when the control rod drives are replaced.
f Replacing of CRD bolting is a more conservative approach in assuring the structural i integrity of the CRD mechanical connections than rousing bolting that was examined
- by VT-1 method. This approach removes any possible service induced degradation .
' mechanisms that may exist, therefore, it assures structural integrity of CRD mechanical connection.
- New CRD bolts used for replacement are subject to a surface examination in l accordance the procurement specification.
. For the above reasons, LaSalle Station requests relief from the requirements of ASME Section XI,1989 Edition, Table IWA-2500-1 for examination of CRD Housing botting.
b f 8-36 i
LAAALAR COUNTY NUCLEAft STAftDN IWyggOpq 1 MCCec letrWtvAL espWCTION PLAN l
RELIEF REQUEST CR-18 (Page 2 of 2) l PROPOSED ALTERNATE EXAMINATION i
CRD cap screws at LaSalle Station will be replaced without being subject to a VT-1 examination every time a CRD housing is disassembled and reassembled.
1 APPLICABLE TIME PERIOD Relief is requested for the second ten-year interval of the Inservice inspection
- Program for LaSalle Units 1 and 2.
i V
- l 1
4 9
1-l 1
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B-37
LAGALE 00UlffY DGREMI MATION MV0 ION 1 UB 034l148 j
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SECTION 9 O UNIT 1 PRESSURE TESTING
SUMMARY
TABLE l
l l
I O
9-1
. _ .. . . . - . _ _ _ _ . . _ _ _ . . _ . . _ . _ . _ . . . . . _ _ _ _ _ . . . . _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ . . . . _ . _ . - _ . . .___...-_m.._m._.._.. . _ . _ . _ _ . _ . . . .._._._m . . _ _ .-
-- l i suRTs 1 2 te-et-M smense ammmunr. zuumma --- suur UNIT 1 PRESSURE TESTING
, SUte(ARY TABLE RELIEF EXAMINATION ITEM EXAMINATION ITEM NtMBER DESCRIPTION SYSTEM (S) REQUESTS /
CATEGORY NUMBER REQUIREMENTS CODE CASE ALL PRESSURE RETAINING CCBIPOMEIFFS i PR-01 '
B15.10 FW PR-05 REACTOR VESSEL PR-06 315.11 EP i
LP B15.50 ass PIPING B15.51 na B-P VISUAL, VT-2 RE B15.60 RI PUMPS .
315.61 RR l:
6 315.70 sc '
VALVES B15.71 t
9-2 i
w Ite L s qq.qq.eg 85GIEDIMWuthL M _ ree rum UNIT 1 PRESSURE TESTING SUteRRY TABLE EXAMINATION ITEM EXAMINATION ITEM NT.MBER DESCRIPTION SYSTEM (S) REQUEST 8/
- CATEGORY NUMBER REQUIREMENT 8 CODE CASE ,
ALL PRESSUBtB RETADIDOS cCBWOME3rFS i
PR-05 c7.10 Es P5t-06
, ,, PR-04 See Note 2 c7.20 yW EP C7.30 LP
. PIPING ,
C7.40 3gs l C-H VISUAL, VT-2 nun c7.50 so c7.60 RE KZ c7.70 stR l c7.so sc 9-3 ,
r
___. . . _ . _ , _ - . _ _ - - - .----- ~ . - - -
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smoue zurumor. zumerum museerzas esas UNIT 1 PRESSURE TESTING SUbMARY TABLE EXAMINATION ITEM RELIEF EXAMINATION CATEGORY NUMBER ITEM NUMBER DESCRIPTION SYSTEM (S) REQUESTS /
REQUIREMENTS CODE CASE PR-05 D-A D1.10 ~
PR-02 See mote 4 DG PR-03 See mote 3 PC EP D-B D2.10 ALL PRESSURE RETAINING CX3EPONENTS VIstELL, VT-2 LP MS 4
D-C D3.10 mm NOTES: 1. SEE LIST or cad's IN SECTICM 2 PoK DESCRIPTION OF SYSTEM ACRONDAIS
- 2. PR-04 APPLIES TO REACTOR VESSEL EEAD PIJGIGE SEAL IAAR DETECTION SYSTEM..
9-4
O O unrs 1 a e IstmuumL N BusstrELW sunt O.--
er-ee-es UNIT 1 PRESSURE TESTING SUM 4ARY TABLE RELIEF EXAMINATION ITEM ITEM NtMBER DESCRIPTION SYSTEM (S) REQUESTS /
CATEGORY NUMBER REQUIREMENTS @E N
- 3. PR-03 APPLIES TO BELIN STEAtt
- SAFETY 5tELIEF YALVE DIS N km LINES.
i
- 4. PR-02 APPLIES TO EtB EEAT EXCEANGER TURES l
l t
i 9-5 [
i i
_._.-_.-____--_ _ _ . _ - _ _ _ - _ -- _ _ _ _ _ =-___---._r -- -- - - - . - - . _ _ _ - - _ _ _ _ _
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4 i SECTION 10
!O i
UNIT 2 PRESSURE TESTING j
SUMMARY
TABLE i
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4 l
i i
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10-1
__ . . _ _ __.. __ _ .___. _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ . _ _ _ - . _ _ . _ _ _ _ _ _ _ . - . . . _ . _ . _ . . _ . _ _ _ _ . _ _ . . . . _ _ _ . _ _ _ ___m____.
- - ==s- t SOMB 3WEWEEEL M IEEEWLTIW WEAS UNIT 2 ,
PRESSURE TESTING SUtemRY TABLE EXAMINATION ITEM RELIEF EXAhTNATION ITEM NIS4BER DESCRIPTION SYSTEM (8) REQUEST 8/
CATEGORY NUMBER REQUIREMENTS CODE CASE ALL PRESSURE RETAINING COMPONENTS i I l PR-01 B15.10 FW PR-05 mEncTom vassEx. *m-** ,
B15.50 RI l M i
! Bis.El am i
f 315.70 sc VALVES B15.71
. 4 10-2 -
i
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sman numana,memwxm masuna sum UNIT 2 PRESSURE TESTING SIM4ARY TABLE EXAMINATION ITEM RELIEF EXAMINATION ITEM NtMBER DESCRIPTION SYSTEM (S) REQUESTS /
CATEGORY NtMBER REQUIREMENTS CODE CASE ALL PRESStBE RETAIEmeG COBEPOBENTS PR-05 C7.10 ES PR-06 PR-04 See Note 2 PRESSimE VESSELS C7.20 NW EP C7.30 LP PIPING C7.40 383 C-H VISUAL, VT-2 ma C7.50 3D C7.60 33 RI C7.70 ER VALVES C7.80 SC 10-3
. ~. .... . . . . . . . . . - . . - - . . . - . . . . - . . . . . - - . _ . . . - - . . _ . ~ -..-.--...~-- - -. ...--... - .. -- - . .
.i o A surre a a m Erfumet m Imusscram pus
.- 9-.ee.es.,e UNIT 2 PRESSURE TESTING SUteOJW TABLE i
EXAMINATION ITEM RELIEF EXAMINATION CATEGORY NUMBER ITEM NIMBER DESCRIPTION SYSTEM (S) REQUESTS /
REQUIREMENTS CODE CASE PR-05 CSCS PR-06 D-A D1.10 PR-02 See Note 4 M PR-03 See Note 3 K
- 2. PR-04 APPLIES TO REACTOR VESSEL EEAD FIAME SEAL LEAK DETECTION SYSTEM..
10-4
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PRESSURE TESTING l
I St2 MARY TABLE i EXAMINATION ITEM RELIEF EXAMINATION CATEGORY NUMBER ITEM N R DESCRIPTION SYSTEM (S) REQUESTS /
' REQUIREMENTS code CASE
- 3. PR-03 APPLIES TO MAIN STEAM SAPETE RELIEF VALVE DISCEARIE LINES.
! 4. PR-02 APPLIES TO RE REAT EXCEANGER TURES i
r 10-5
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SECTION 11 O PRESSURE TESTING RELIEF REQUESTS O
11-1
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1 j
O =v='== "a===u a= '==aa RELIEF REQUEST INDEX/ SUMMARIES 1
PAGE(S) REV. DATE-
SUMMARY
RE #
j PR-01 1-3 thru 0 10-17-94 System Leakage Test i 11-4 pressure for the disassembly and reassembly of mechanical j; joints i PR-02 11-5 thru O 10-17-94 Altemate testing for the i 11 6 Residual Heat Removal Heat Exchanger tubes.
- {
j PR-03 11-7 thru O 10-17-94 Functional and Hydrostatic ,
- 11-8 pressure testing for the Main Steam Safety Relief Valve discharge lines.
l l PR-04 11-9 thru O 10-17-94 Exemption from pressure 11-12 testing Reactor Vessel Head 1 l
j Flange Seal Leak Detection !
System. !
- l l PR-05 11-13 thru O 10-17-94 Use of altamative Rules for l i
l 11-15 the 10 year Hydrostatic testing i of Class 1,2 & 3 Systems.
l PR-06 11-16 thru O 10-17-94 Use of altamative Rules for l 11-18 Hydrostatic testing
- requirements, after Repair or ;
! Replacement of Class 1,2 &
i 3 Components. ,
l PR-07 11-19 thru O 02-02-96 Altemative Rules for l
11-20 Corrective Action Resulting ,
from Leakage at Bolted l
, Connections. l l
! l l
L l
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11-2
+
us.usg y swa enne m miennena euxneueramm i
l RELIEF REQUEST PR-01 l j (Page 1 of 2) l
- COMPONENT IDENTIFICATION I J
l
[ Code Class: 1
)
i
References:
IWA-5211(a), IWB-5221(a) :
j Examination Categories: B-P l J ltem Numbers: B15.10, B15.71
Description:
System Leakage Test Pressure for the Disassembly and
- Reassembly of Mechanical Connections.
Component Numbers: Various 3
CODE REQUIREMENT IWA-5211(a) requires a system leakage test to be conducted followireg the opening j and re-closing of a component in the system after pressurization to romir.sl operating pressure.
l IW3-5221(a) states that the system leakage test shall be conducted at a test pressure
, not toss than the nominal operating pressure associated with 100% rated reactor power.
'O l BASIS FOR RELIEF The nombat operating pressure associated with 100% rated reactor power is 1,020
- psig. Near the end of each refueling outage, a system pressure test of all Class 1 pressure retaining components is conducted at 1,020 psig.
l Subsequent to the system pressure test conducted during a refueling outage, or i
during forced maintenance outages which can occur during an operating cycle, it may l become necessary to disassemble and reassemble Class 1 mechanical connections 1 that are located in the drywell and cannot be isolated from the reactor vessel. For i these situations, the performance of a Class 1 system leakage test at 1,020 psig l would have a significant impact on the unit's critical path outage time and personnel radiation exposure.
J l
The nominal Claso 1 system pressure test, which is performed with the vessel flooded i up, requires numerous equipment outages (e.g., 380 valves must be taken out-of-l service). Performance of the system leakage test, takes approximately 5 days (3
, shifts per day) with a total personnel exposure of approximately 2.5 Man-Rem. )
O i 11-3 L -_-. .- ._ _ _ _ _ _ - _ _ _ _ O
I unaux couwn muasan erariou ninvi.ou i l
< enconowrow2J"" a menousua i
j RELIEF REQUEST PR-01 1 (Page 2 of 2)
]
i; i 1
i i
- Performance of a system leakage test during normal startup is possible, however the l j test cannot be performed at 10,020 psig. During unit startup, the Electro Hydraulic j
Control System precludes a reactor pressure above 950 psig without significant increases in reactor power. In order to achieve a pressure of 1,020 psig, the reactor
- would have to be at approximately 100% rated power. The radiation levels at this power level are prohibitive, and prevent drywell entry by plant personnel. ,
- A drywell entry to inspect for leakage can be performed at greater than, or equal to 1 920 psig, wb.kh is associated with approximately 15% reactor power. Performance of i the leakage test in this manner would have an insignificant impact on the ability to detect leakage from a reassembled mechanical connection. It would also significantly reduce the personnel exposure and critical path outage time required for the test.
J j Based on the above, LaSalle County Station requests relief from the ASME Section XI
- requirements for the system leakage test pressure when performing pressure testing i
of reassembled, unisolable Class 1 mechanical connechons.
PROPOSED ALTERNATE EXAMINATION O As an alternate examination, LaSalle County Station will perform a system leakage l test at greater than, or equal to 920 psig during unit outages when an unisolable Class i 1 mechanical connection in the drywell has been disassembled and reassembled either.
i l 1) Subsequent to performance of the system pressure test conducted near the end of
! each refueling outage; or l
- 2) During a forced maintenance outage in the course of an operating cycle.
APPLICABLE TIME PERIOD Relief is requested for the second ten-year interval of the Inservice Inspection Program for LaSalle Units 1 and 2.
I i 11-4 l 5 l l
6AGELE COLMfY MATION MWISON
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escon0wreva =m en0Neum 5
l 4
RELIEF REQUEST PR 02
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l l COMPONENT IDENTIFICATION i
J Code Class: 2
References:
lWA-5241(b) j Examination Categories: C-H e
item Numbers: C7.10, C7.11
Description:
Alternate testing for Residual Heat Removal Heat Exchanger Tubes.
! Component Numbers: Unit 1: 1E12-B001 A,1E12-B001B l Unit 2: 2E12-B001 A, 2E12-B001B l
l CODE REQUIREMENT l
! IWA-5241(b) states that the VT-2 examination of inaccessible components shall
- consist of an examination of the surrounding area, including floor areas or equipment surfaces located underneath the components, for evidence of leakage.
!O
=^='seoa =='i -
l The tubing inside the Residual Heat Removal (RHR) Heat Exchanger is inaccessible.
- A visual examiner cannot enter the RHR Heat Exchanger to perform an examination j of the tubes or their surrounding areas during operational or hydrostatic testing of the j tube side of the Heat Exchanger.
l The shell side of the Heat Exchanger could be pressurized with the tube side drained.
i Evidence of leakage could then be observed from the shell side to the tube side.
However, this requires the removal of the Heat Exchanger Channel Cover flange.
Access to the tube side of the vertically mounted Heat Exchanger is from the bottom.
The Channel Cover flange weighs approximately 3,500 pounds. Proper alignment of i the relatively thin metallic gasket material is difficult to obtain, especially down the
- center of the Channel Partition Plate. The torquing sequence requires one complete
- application up to the final torque value while cold, and another complete pass once the Heat Exchanger comes up to normal operating temperature. Past history of this disassembly and reassembly process has proven to cause leaks in this flanged i
connection that are troublesome to repair while trying to bring the unit back on-line at the end of an outage. As this method can create more leaks than would be found by the inspection, it is considered to create an undo hardship.
4 p Based on the above, LaSalle County Station requests relief from the ASME Section XI
- requirements for performing a VT-2 examination of the RHR Heat Exchanger tubing during hydrostatic and operational pressure tests.
~
11-5 6
y, . . .., -.m
. -.. - - . -- - .- . . ~ . . ~ . . . . . - . . . .-.
LAGAu2 COLMTV feJCLEAft STATION IWWISON 1 SECOND INTWWAL INSPECTION PLAN RELIEF REQUEST PR-02 (Page 2 of 2)
PROPOSED ALTERNATE EXAMINATION 1
- Monitoring of radiation levels in the tube side cooling water will be performed during i the shell side pressure test as an alternate method of verifying tube integrity.
Radiation levels within Technical Specification limits will be considered acceptable.
, When the Heat Exchanger Channel Cover flange is removed for other reasons (i.e.
j maintenance, repair, or modification work), a VT-2 examination will be performed while
not be removed for the sole purpose of performing a VT-2 examination.
APPLICABLE TIME PERIOD l Relief is requested for the second ten-year interval of the Inservice inspection j Program for LaSalle Units 1 and 2.
- O l
i i
- O 11-6 l
sumsun.
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_ 7 ==
escow ammu.n aams neeca nm RELIEF REQUEST PR-03 (Page 1 of 2)
' l i COMPONENT IDENTIFICATION I i
Code Class: 3 i
References:
IWD-5223(f)
Examination Categories: D-B ltem Numbers: D2.10 I
Description:
Exemption From Pressure Testing Piping Beyond me Last
- Safety or Relief Valve which Discharges into the Suppression Pool.
Component Numbers: Various l
< l 1 l CODE REQUIREMENT l l l ASME Section XI 1989 Edition, IWD-5223(f) states "For safety or relief valve piping i I
j which discharges into the containment pressure suppression pool, a pneumatic test (at l a pressure of 90% of the pipe submergence head of water) that demonstrates leakage
- Integrity shall be performed in lieu of the system hydrostatic test."
BASIS FOR RELIEF l
LaSalle County Station has eighteen Main Steam Relief Valves with associated j discharge lines and vacuum breakers. The discharge lines run down through the j drywell and discharge into the Suppression Pool.
l i The provisions of IWD-5223(f) call for a pneumatic test at a test pressure of 90% of
! the pipe submergence head of water to be performed. The design of the Main Steam l Relief Valves and associated discharge piping at LaSalle County Station does not
- allow for a test to be performed which would demonstrate leakage integrity. No test taps are available on these discharge lines which would allow for the proper pressurization of the system. The pressure associated with 90% submergence head
- in these discharge lines relates to approximately 3-5 psig, while the design pressure of
' the lines is 600 psi. At this low test pressure, the vacuum breakers are not designed to provide a leak tight seal and would provide a leak path which would prevent verification of leakage integrity. Imposition of the Code Requirement would present i
undo hardship and difficulty to LaSalle County Station in that it would require that test taps be provided, a change in the design of the Main Steam Relief Valves, and a change in the design of the vacuum breakers. Per 10CFR50.55a section (g)(4), Code Class components shall meet the requirements of ASME Section XI to the extent
- practical within the limitations of design, geometry, and materials of construction of the components.
11-7 1
namo umus cou_m 7 suno I I RELIEF REQUEST PR-03 (Page 2 of 2)
Additionally, normal plant operation does not require the actuation and lifting of these
- relief valves. The valves are only required to operate during accident and transient conditions. The relief valves could be lifted at power, but this practice not only j challenges equipment important to safety, but also contributes to degradation of the seating surfaces of the valves leading to leakage and subsequent elevated
- suppression pool temperatures during the fuel cycle. The lifting of these valves during l power operation is considered to present an undue challenge to equipment important
, to safety, which at the Code Required test pressure of 3-5 psi does not provide a commensurate increase in the level of safety gained by the imposition of the Code l Requirement.
i j Based on the above, LaSalle County Station requests relief from the ASME Section XI i requirements for performing a VT-2 under normal operating conditions, and from the
- hydrostatic test requirements to perform a pneumatic test at 90% of pipe submergence i head once each inspection interval.
- PROPOSED ALTERNATE EXAMINATION ,
4 i
l No altamative examinations are proposed.
APPLICABLE TIME PERIOD Relief is requested for the second ten-year interval of the Inservice inspection
- Program for LaSalle Units 1 and 2.
i l
i i
i 1
- O 11-8 1
L__ _ _ _ . _ .__
unauxcoump swa newem esco.o wre m mes a rs cno m
]
RELIEF REQUEST PR-04 j (Page 1 of 4) l COMPONENT IDENTIFICATION i Code Class: 2
References:
IWC-5210(a)(2) l
- Table IWC-2500-1 l Examination Categories: C-H i C7.60, C7.80 item Numbers:
Description:
Exemption From Pressure Testing Reactor Vessel Head j- Flange Seal Leak Detection System.
] Component Numbers: Various l CODE REQUIREMENT 4
- IWC-5210 (a)(2) requires that the pressure retaining components within each system
! boundary be subjected to a system hydrostatic pressure test.
BA818 FOR RELIEF l The Reactor Vessel Head Flange Leak Detection Line is separated from the reactor
, pressure boundary by one passive membrane, a silver plated 0-ring located on the
! Indicate failure of the inner flange seal O-ring. Failure of the O-ring would result in a
! High Pressure Alarm in the Main Control Room.
i
! The configuration of this system precludes hydrostatic testing while the vessel head is I removed. As figure PR-04.1 portrays, the odd configuration of the vessel tap, )
, combined with the small size of the tap and the high test pressure requirement (1000 .
l psig minimum), prevents the tap from being temporarily plugged. Also, when the vessel head is installed, an adequate pressure test cannot be performed due to the j
fact that the inner 0-ring is designed to withstand pressure in one direction only.
Resulting from the groove that the O-ring sits in and the pin / wire clip assembly (See Figure PR-04.2), pressurization in the opposite direction could damage the O-ring and thus result in further damege to the O-ring and vessel flange itself from steam cutting.
t O 1 11-9 j
~ %ET """
esame.ne= = sex = semm a
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i RELIEF REQUEST PR-04 (Page 2 of 4) j
! Pressure testing of this line during the Class 1 System Leakage and/or Hydrostatic
- Test is precluded because the will only be pressurized in the event of a failure of the
- inner 0-ring. Purposely falling the inner 0-ring to perform the Code Required test
- would require purchasing a new set of O-rings, additional time and radiation exposure
- to detension the reactor vessel head, install the new O-rings, and then reset and
- retension the reactor vessel head. This is considered to impose an undue hardship j and burden on LaSa!!e County Station.
1 Based on the above, LaSalle County Station requests relief from the ASME Section XI requirements for static and operational pressure testing of the Reactor Vessel Head i Flange Seal Leak Detection System.
PROPOSED ALTERNATE EXAMINATION A VT-2 examination will be performed on the line during a refueling outage. The hydrostatic head developed with the leak detection line filled with water up to the j vessel flange will allow for the detection of any gross indications in the line. This examination will be peiformed with the frequency specified by Table IWC-2500-1 for
. an IWC-5221 test (once each inspection period).
. APPLICABLE TIME PERIOD i
- Relief is requested for the second ten-year interval of the Inservice Inspection Program for LaSalle Units 1 and 2.
I i
L i .
1 11-10 i
- s. r,
LAAALAK OQUWTV 8AJCLAAft NATION IWWIsION 1 LJIMS 1 & 2 85648 smooiewnswAt snameweenannAn RELIEF REQUEST PR-04 2 (Page 3 of 4)
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FIGURE PR-04.1 FLANGE SEAL LEAK DETECTION LINE DETAIL i
O 11-11
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! I RELIEF REQUEST PR-04 I
- (Page 4 of 4) c..........
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FIGURE PR-04.2 0-RING CONFIGURATION f
a 11-12
1 LAsAllE COLMfY 8AJE15AR STATICM MVimCN 1 I smooie wrenvAt mesi /c5 menentm u I REWEF REQUEST PR45 i (Page 1 of 3) l COMPONENT IDENTIFICATION j
- Code Class
- 1,2, and 3 i
References:
- IWD-5000, Table IWB-2500-1, Table IWC-2500-1, Table IWD-2500-1 Examination Categories
- B-P, C-H, D-A, D-B, D-C i item Numbers: B15.ST, C7.ST, D1.10, D2.10, D3.10
Description:
Alternate Pressure Testing of Class 1,2 and 3 Systems in lieu of the Ten-Year Hydrostatic Pressure Test.
j Component Numbers: All Class 1,2, and 3 pressure retaining components subject to Hydrostatic Testing per IWA-5000.
i CODE REQUIREMENT
]
! ASME Section XI, Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1 require Class 1,
! 2 and 3 pressure retaining components to be VT-2 examined while the system (s) is l subjected to an elevated pressure hydrostatic test at or near the end of each i inspection interval.
- O i ASME Section XI, IWB-5222 states the Class 1 system hydrostatic test may be i conducted at any test pressure specified in Table IWB-5222-1. The test pressure ,
I range is 1.02xP, to 1.10xP, (where P,is the nominal operating pressure corresponding j with 100% rated reactor power) and is determined as a function of the test
! temperature. ASME Section XI IWC-5222 and IWD-5223 state that the system i hydrostatic test pressure shall be at least 1.10 times the system pressure P,, for
! systems with a design temperature of 200*F or less, and at least 1.25 times the i system pressure P,, for systems with a design temperature above 200*F. The system l pressure, P,,, is the lowest pressure setting among the safety or relief valves provided i for overpressure protection within the boundary of the system to be tested. For test i systems not provided with safety or relief valves, the system design pressure P, shall be substituted for P,,,
l BASIS FOR RELIEF
)
Hydrostatic tests, are difficult to perform and represent a true hardship to LaSalle l County Station . Some of the difficulties associated with hydrostatic testing include the following:
-Hydrostatic testing often requires complicated or abnormal valve line-ups in order to properly vent, fill and isolate the system or component (s) being tested.
11-13
i b
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I RELIEF REQUEST PR-05 (Page 2 of 3) 1 i
- -Relief valves with setpoints lower than the hydrostatic test pressure must be gagged or removed and blind flanged thus deliberately defeating their intended i overpressure protection function. In some cases this function is intended to protect equipment important to safety. The gagging, or blinding process also i requires the draining and refilling of the system, which increases the radiation
{ exposure burden.
3
-Valves that are not normally used for isolation (e.g., normally open pump 3
discharge valves) are often required to provide pressure isolation for a j hydrostatic test. These valves frequently require time consuming seat j maintenance in order to allow for pressurization and isolation.
! The difficulties in performing a hydrostatic pressure test are prohibitive when weighed l against the benefits. Industry experience, which is corroborated by LaSalle County l Station's experience, shows that most through wall leakage is detected during system operation as opposed to during elevated pressure tests such as ten-year hydrostatic
- tests.
- Little benefit is gained from the added challenge to the piping system provided by a hydrostatic test (when compared to an operational test), especially when considering 4 that the piping stress experienced during a hydrostatic test does not include the
- significant stresses affiliated with thermal growth and dynamic loading associated with l deWgn baWs evenh.
l LaSalle County Station believes that the imposition of the Code Required hydrostatic 1 testing presents undue hardships which do not provide a commensurate increases in !
- the level of safety which may be gained by performing the Code Requirement.
i I
- These arguments are supported by the approval of Code Case N-498-1 on May 11, 1994. This code case permits hydrostatic testing at nominal operating pressure in lieu ,
of the elevated pressures currently required j
! Based on the above, LaSalle County Station requests relief from the ASME Section XI requirements for performing the ten-year hydrostatic tests at elevated pressures for
- Class 1,2 and 3 systems.
l
!O 11-14
?
umusax e y erno.
saxne - = mcs r.cro.nu l RELIEF REQUEST PR-05 (Page 3 of 3)
\
PROPOSED ALTERNATE EXAMINATION I A VT-2 examination will be performed during a system hydrostatic test which is :
conducted using the rules of Code Case N-498-1.
APPLICABLE TIME PERIOD Relief is requested for the second ten-year interval of the Inservice inspection
- Program for LaSalle Units 1 and 2.
i .
4 1
4 3
O O
11-15
unaus ymm - man seco.ewrewaumeswa cnoma RELIEF REQUEST PR-04 (Page 1 of 3)
COMPONENT IDENTIFICATION Code Class: 1, 2, and 3
References:
IWA-4700(a), IWB-7400, IWC-7200, lWC-7200, lWA-5214 l Examination Categories: B-P, C-H, D-A, D 8, D-C ltem Numbers: 815.ST, C7.ST, D1.10, D2.10, D3.10
Description:
Alternative Pressure Test Requirements for Welded Repairs and installation of Replacement items by Welding on Class 1,2, and 3 Pressure Retaining components.
Component Numbers: All Class 1,2, and 3 pressure retaining components subject to Hydrostatic Testing per IWA-4700.
CODE REQUIREMENT IWA-4700(a) requires a hydrostatic test to be performed after repairs by welding, or the installation of replacement items by welding on the pressure retaining boundary of Class 1,2, and 3 components, except as exempted by IWA-4700(b).
BASIS FOR RELIEF Hydrostatic tests are difficult to perform and often represent a true hardship. Some of the difficulties associated with hydrostatic testing include the following:
-Hydrostatic testing often requires complicated or abnormal valve line-ups in order to properly vent, fill and isolate the system or component (s) being tested.
-Relief valves with setpoints lower than the hydrostatic test pressure must be gagged or removed and blind flanged. This process requires the draining and refilling of the system.
! -Valves that are not normally used for isolation (e.g., normally open pump
,. discharge valves) are often required to provide pressure isolation for a hydrostatic test. These valves frequently require time consuming seat
{ maintenance in order to allow for pressurization and isolation.
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~ RELIEF REQUEST PR-06 (Page 2 of 3) i
-The radiation exposure required to perform a hydrostatic pressure test is high l (in comparison to operational pressure testing) due to the large amount of time i
- required to prepare the volume for testing (i.e., installing relief valve gags, performing appropriate valve line-ups, etc.).
i The difficulties in performing a hydrostatic pressure test are prohibitive when weighed against the benefits. Industry experience, which is corroborated by LaSalle County Station's experience, shows that most through wall leakage is detected during system operation as opposed to during elevated pressure tests such as ten-year hydrostatic tests.
j Little benefit is gained from the added challenge to the piping system provided by a l hydrostatic test (when compared to an operational test), especially when considering i that the piping stress experienced during a hydrostatic test does not include the
- significant stresses affiliated with thermal growth and dynamic loading associated with j design basis events.
]'
The acceptability of performing nominal operating pressure tests in lieu of hydrostatic tests is also supported by the recent approval by the Board of Nuclear Codes and l Standards (BCNS) of Code Case N-416-1, " Alternative Pressure Test Requirements j for Welded Repairs or Installation of Replacement items by Welding", for Class 1,2,- l
- and 3 Systems, ASME Section XI, Division 1. This Code Case allows a system l l pressure test at nominal operating pressure and temperature (in accordance with IWA- ;
j' 5000 of the 1992 Edition of ASME Section XI) to be used in lieu of a hydrostatic test, !
, l i Based on the above, LaSalle County Station requests relief from the ASME Section XI j requirements for performing hydrostatic tests after repairs by welding, or the i
installation of replacement items by welding, on the pressure retaining boundary of
{ Class 1,2, and 3 components.
i PROPOSED ALTERNATE EXAMINATION As an alternate to the existing ASME Section XI requirements, LaSalle County Station i will adopt the provisions of Code Case N-416-1 along with the following additional NDE requirements.when performing repairs by welding or installing replacement items by welding on the pressure retaining l
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RELIEF REQUEST PR-08 (Page 3 of 3) boundary of Class 3 components, NDE shall be performed in accordance with the methods and acceptance criteria of Subsection ND of the 1992 Edition of ASME Section Ill, in addition, when the surface examination method is used in accordance with ND-5222 for a butt weld, an additional surface examination shall be performed on the root (pass) layer.
APPLICABLE TIME PERIOD Relief is requested for the second ten-year interval of the Inservice inspection Program for LaSalle Units 1 and 2.
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umus y sunow =voon mooiems== ews cnow ua REUEF REQUEST PR47 ,
jQ (Page 1 of 2) 4 COMPONENT IDENTIFICATION J Code Class: 1,2 and 3
References:
IWA-5250(a)(2), IWB-2430, IWC-2430 Examination Categories: N/A Item Numbers: N/A 4
Description:
Altemative rules for Corrective Action Resulting from Leakage at Bolted Connections.
]
CODE REQUIREMENT IWA-5250(a)(2) states, "if leakage occurs at a bolted connection, the bolting shall be .
- removed, VT-3 visually examined for corrosion, and evaluated in accordance with l IWA-3100." !
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! IWB-2430, IWC-2430 ' Additional Examinations" ;
i BASIS FOR RELIEF
!O Relief is requested on the basis that the proposed attematives would provide an
- acceptable level of quality and safety.
1
. As an attemative to the requirements of IWA-5250(a)(2), LaSalle Generating Station i proposes the rules stated below. These rules will provide reasonable assurance that the safety and integrity of Class 1,2, and 3 bolted connections will be maintained.
PROPOSED ALTERNATE EXAMINATION
- As an altamate to the existing requirements, an evaluation to determine the j susceptibility of the bolting to corrosion by an evaluation that considers as a minimum
a) Type and location of the leakage
- b) Historicalleakage c) Materials of the leaking component d) Visual evidence of corrosion i
e) Corrosiveness of the process fluid f) History of the bolt material degradation due to corrosion in similar environments g) Other components (and materials) in the vicinity of the leaking comporient including consideration of leak path, insulation effects, etc.
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unaus y m== - mam esco.e wraw= an= = ecum u RELIEF REQUEST PR-07 (Page 2 of 2)
If any of the above parameters indicates a need for further evaluation, the bolt closest to the source of leakage shall be removed, receive a VT-1 Examination, and be evaluated in accordance with IWA-3100(a). If the leakage is identified when the bolted connection is in service, and the information in the evaluation is supportive, the removal of the bolt has evidence of degradation, all remaining bolting shall be removed, VT-1 examined, and evaluated in accordance with IWA-3100(a).
The additional examinations of IWB-2430 and IWC-2430 will not be performed unless the need is established by the above evaluation.
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LAGALLE COUDfrY u n m STATION llEVISON 1 l UpsTS 9 & 2 OHMS 4 N00se OffWEVAL SeSERWW SGPECfl0H PLAN i-d 1
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! CODE CASES 4
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=,r -- = l seco.e mauemmes-a l SECTION 12 - CODE CASES 1.0 The following ASME Section XI, Division 1, Code Cases are listed in paragraph C., REGULATORY POSITION, of Regulatory Guide 1.147, INSERVICE INSPECTION CODE CASE ACCEPTABILITY ASME SECTION XI DIVISION 1, as being acceptable to the NRC staff for implementation in the inservice inspection of components and supports, within any limitations stated in this Reg.
Guide or the individual Code Case. The Code Cases listed are only those that apply, or may apply, to LCNS. LCNS may not currently utilize all of the Code Cases listed here, but reserves the right to use any of these Code Cases when applicable.
1.1 N-98 Calibration Block Tolerances.
1.2 N-211 Recalibration of Ultrasonic Equipment Upon Change of Personnel.
1.3 N-235 Ultrasonic Calibration Checks per Section V.
I 1.4 N-236-1 Repair and Replacement of Class MC Vessels.
i 1.5 N-278 Attemative Ultrasonic Calibration Block Configuration 1-3131
.' GO and T-434.3 1.6 N-307-1 Revised Ultrasonic Examination Volume for Class 1 Bolting, i
Table IWB-2500-1, Examination Category B-G-1, When the Examinations Are Conducted From the Center Drilled Hole.
, 1.7 N-335-1 Rules for Ultrasonic Examination of Similar and Dissimilar
- Metal Piping Welds.
1.8 N-408-2 Altemative Rules for Examination of Class 2 Piping.
1.9 N-409-2 Procedure and Personnel Qualification Requirements for Ultrasonic Detection and Sizing of Intergranular Stress Corrosion Cracking in Austenitic Piping Welds.
1.10 N-415 Aftemative Rules for Testing Pressure Relief Devices.
, 1.11 N-416 Altemative Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping.
i 1.12 N-419 Extent of VT-1 Examinations, Category B-G-1 of Table IWB-2500-1, 12-2
! " T ,"3 "" " "
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smoono mswa mesmensenow-i
- 1.13 N-426 Extent of VT-1 Examinations, Category B-G-2 of Table :
f 1.14 N-427 Code Cases and Inspection Plans i
1.15 N-429-1 Altemative Rules for Ultrasonic instrument Calibration.
! 1.18 N-432 Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding (GTAW) Temportead Technique.
l 1.17 N-435-1 Altemative Examination Requirements for Vessels With .
1 Wall Thickness 2 in. or Less, I
j 1.18 N-437 Use of Digital Readout and Digital Measurement Devices
- for Performing Pressure Tests.
! 1.19 N-457 Qualification Specimen Notch Location for Ultrasonic j Examination of Bolts and Studs.
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1.20 N-458 Magnetic Particle Examination of Coated Materials.
! 1.21 N460 Altemative Examination Coverage for Class 1 and Class 2
! Welds.
O 1.21 N-461 Altemative Rules for Piping Calibration Block Thickness.
1 1.22 N-463-1 Evaluation Procedures and Acceptance Criteria for Flaws in Class 1 Ferritic Piping that Exceed the Acceptance Standards of IWB-3514.2.
1.23 N-465 Altemate Rules for Pump Testing.
- 1.24 N-472 Use of Digital Readout and Digital Measurement Devices for Performing Pump Vibration Testing.
1.25 N-479-1 Boiling Water Reactor (BWR) Main Steam Hydrostatic Test.
! 1.26 N-481 Altemative Examination Requirements for Cast Austenitic l Pump Casings.
i 1.27 N-485-1 Eddy Current Examination of Coated Ferritic Surfaces as an j Altemative to Surface Excmination.
1.28 N-489 Altemative Rules for Level lli NDE Qualification jd Examinations.
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1.29 N-490-1 Altemative Vision Test Requirements for Nondestructive Examiners.
1.30 N-491 Altemative Rules for Examination of Class 1,2, 3, and MC Component Supports of Light-Water Cooled Power Plants.
1.31 N-494 Pipe Specific Evaluation Procedures and Acceptance Criteria for Flaws in Class 1 Ferritic Piping that Exceed the Acceptance Standards of IWB-3514.2 1.32 N 495 Hydrostatic Testing of Relief Valves.
1.33 N-496 Helical-coil Threaded inserts.
1.34 N-498 Altemative Rules for 10-Year Hydrostatic Pressure Testing for Class 1 and 2 Systems.
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SECTION 13 n
i REFERENCES i
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SECTION 13 - REFERENCES
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- 1.0 Code of Federal Regulations, Part 10, Paragraph 50.55a, Codes and Standards.
2.0 American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components,1989 Edition.
3.0 Regulatory Guide 1.147, inservice inspection Code Case Acceptability ASME Section XI Division 1, 4.0 Generic Letter 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.
5.0 NUREG-0519, Safety Evaluation Report Related to the Operation of LaSal!e County Station Units 1 & 2.
6.0 NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Retum Line Nozzle Cracking.
7.0 NUREG-0800, Standard Review Plan for Review of Safety Analysis Reports for Nuclear Power Plants.
8.0 1.E.Bulletin 80-13, Examination of High and Low Pressure Core Spray Spargers.
9.0 LaSalle County Station Units 1 & 2 Technical Specifications.
10.0 LaSalle County Station Final Safety Analysis Report.
11.0 LaSalle County Station Updated Final Safety Analysis Report.
12.0 Bases Document for LaSalle County Station Units 1 & 2 Second Interval inservice inspection Programs.
13.0 Piping & Component Support and integral Attachment Bases Document for LaSalle County Station Units 1 & 2 Second Interval inservice inspection Program, j 14.0 LaSalle County Station P&lD's.
15.0 LaSalle County Station Line List.
O 1. 0 ' e S eiie C o etr S tatio a S # a n ort Li 1.
13-2
LASNAE CX3LMyy p n man grAgog g
\MTS 1 S 2 m seemewrammes=m senawnum 17.0 LaSalle County Station First interval ISI Program.
18.0 LaSalle County Station Classification Boundary Drawings.
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i Commonwealth Edison Company
! LaSalle Generating Station i
ASME SECTION XI CALIBRATION STANDARDS O comed ID MATERIAL SCHEDULE NOMINAL THICHNESS HEAT I
01-36-01 SA-15MCF70 / SA-516 WA 1.5" Muel 802E31130 i GR70 HT-D 01 28-01 SA-155-KCF70 / SA-516 WA 1.1" Musi 811829170 l GR70 HT-D 01-26-01 SA-15MCF70 WA 1.25" Muel PQC-353 / 355 01 26 02 SA-155 KCF70 WA 1.062" Mual EHCT 01-26-04 SA-508 WA 1.5" Mual Q2082QT
, 01-24-01 SA-358 GR. 304 80 1.219" PQC-523
, 01-24-02 SA-106 GR. B 40 .688" N33432 01-24-03 SA-106 GR. B 20 .375" N14608 01-24-04 SA-106 GR. B 100 1.531" L2373 01-24-05 SA-155 140 2.062" 67293
! 01-24-07 SA-182-F304 100 1.531" 624108 4
01 24-08 SA-358 GR. 304 60 .969" F83910
! 01-20 01 SA-106 GR. B 40 .594" LO244
01-20-04 SA-333 GR. 6 100 1.281" J6252
! 01-16-01 SA-106 GR. B 40 .562" L21681 j 01-18-02 SA-106 GR. B 100 1.156" L2401 i 01-18-03 SA-106 GR. B 80 .938" N12383 l 01-18-04 SA-358 TP. 304 40S .375" 19397 01 18-05 SA-106 GR. B STD. .375" 80922 l 01-16-01 SA-106 GR. B 40 .500" 46461
! 01-16-02 SA-106 GR. B 100 1.031' N13433
- SA-358 GR. 304 / SA-240 01-16-04 TP. 304 HT-D 60 .656" F81321 l
i 01-16-05 SA-358 GR. 304 100 1.031" 19638 0 01-14-01 SA-106 GR B 30 .375" 150038 01-14-02 SA-106 GR. B 100 .920" LO4563
] 01 14-03 SA-106 GR. B 40 .438" 43378 i 01-14-04 SA-508 100 .920" Unimown 01-12-01 SA-106 GR. B 40 .406" N33751
- 01-12-02 SA-333 GR. 6 100 .844" 65235 l 01-12-03 SA-333 GR. 6 120 1.00" 45067 01 12-04 SA-106 GR. B 100 .844" N11774 01-12-05 SA-106 GR. B STD .406" 252594 01-12-06 SA-312 TP. 304 100 .844" 7332 0 01 12-07 01 12-08 SA-358 SA-335 80 80
.688"
.688" 61372 F8543 Page 1 -
- - - . - - -- .- . = . _ - - . - - _ - _ _ _ . - _ _ ..
- commonwealth Edison Company LaSaue Generatin9 station iO ComEDID ASME SECTION XI CALIBRATION STANDARDS MATERIAL SCHEDULE NOMINAL THICHNESS HEAT 01-12-09 SA-182 N/A 1.00" 78158 01-10 01 SA-106 GR. B 100 .719" 152177
) 01-10 02 SA-106 GR. B 40 .365" 252374 i 01-10-03 SA-333 GR. 6 100 .719" 182482
{ 01-1044 SA-106 GR. B 80 .594" C.O.C.
- 01-06-01 SA-106 GR. B 160 .906" PQC-355 / 353
- 01 06-02 SA-106 GR. B 40 .322" 152069 01-0644 SA-106 80 .500" 151967 01-06-01 SA-106 GR. B 40 .280" L20194 01-06-02 SA-106 GR. B 120 .562" N12121
! 01-06-03 SA-333 GR. 6 120 .562" LO3849 j 01-04-04 SA-333 GR. 6 120 .438" 77607 01-04-05 SA-376 80 .337" 2P4894 i 01-03-03 SA-335 80 .300" 3P6428 014001 SA-193 GR. 7 N/A 3.25" Diameter 11762 l
0140-02 SA-540 CL3 GR. B-23 N/A 2.25" Diameter 45380
]
014003 SA-193 GR.B-7 N/A 2.75" Diameter 11782 j 0140-04 SA-193 GR.B 7 N/A 2.0" Diameter 11762
{ 0140-05 AISI 4340 N/A 1.5" Actual Unknown 2
0141-01 SA-540 GR. B-24 CL1 N/A 6.25" Diameter 15352' 0142-01 SA-540 GR. B-24 CL1 N/A 6.00" Diameter 15352
! 01-70-01 SA-508 / SS-166 N/A .77" / .500" PQC-349 I 1.316"/ 1.316" AGE /RF 01-70-02 SA-508 G.2 / SB-106 N/A
! 01 70 03 SA-508 / SS-304 N/A 1.35" /1.6" AV3929 9E-910 /
{
01-7044 SB 166 / SA-508 N/A 1.1" NX7785 / 522308 01-70-05 SA-508 CL2 / SA 182 N/A 0.640" Actual / 0.840" Actual AV-3929-9E-9210 /
F304 S21014BLB l
j 01 70-06 SA-508 / SA-182 N/A 0.089"/1.08" Actual Unknown
! 01-71-01 SB 166 / SA-508 N/A .65" Actual PQC-916
! 01-72-02 SA-508 / SA-182 N/A 1.25"/1.25" 224887 /78158
! 01 91 03 SA-533 GR. B N/A 7" Nominal PQC-448
! 01 91-04 SA-533 GR. B N/A 4.75" PQC-448
- 01 91-05 SA-533 GR. B N/A 4.2" PQC-448
- 01 91-06 SA-516 GR. 70 / 304L N/A 1.18" 811T20750 CLAD 01-91-07 SA-516 GR. 70 / 304L 0.81" 422A9521 CLAD N/A 01-91-08 SA-508 N/A 1.5" Actual Unknown
- 01-92-01 SA-533 N/A 6.8" PQC-867 01-92-02 SA-508 / SA-541 N/A 12.75" Actual PQC-867 l
l Pa9e 2
Commonwealth Edison Company LaSalle Generating Station !
l ASME SECTION XI CALIBRATION STANDARDS comed ID MATERIAL SCHEDULE NOMINAL THICHNESS HEAT 01-92-03 SA-533 GR.B N/A 7.45" PQC-867 ,
01-92-04 SA-533 N/A 5.4" Actual PQC-867 l 01-92-05 SA-533 N/A 3.8" Adual PQC-867 01-92-06 SA-533 N/A 6.85* PQC-867 01-92-07 SA-533 / GR.B N/A 8.45" PQC-867 CRO Retum SA-533 / 508 N/A 8.45' ZV6908 l Line Nozzle !
Unciad FW SA-533 / 508 N/A 8.45" 91569 Nozzle Clad FW SA-533 / 508 N/A 8.45" ARP Nozzle l
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COMMONWEALTE EDESON COMPANY Lasalle comity station mait 1 '
Legeme Ceemmey Nedeer ha.- Unas I & 2 m section n htien categomy B-A CERWERIEFF ITBt WRID BShTL. TRIS. CM.. AE(DSS) DWS. - WWDC.
I.D. U0. NO. TTFE SFBC. (IN) STD. No. ELV(WT) NO. 6 30.
4.2 01-91-05 1006 W-0 m .
0-360 IES-1-AA Bl.11 V1 SA-533 & M -45 m . m+30 766 8.45 01-92-07 GEL-1109 UT-60 DEG.
0-360 -0 m .
IES-1-AB Bl.11 V6 SA-533 7 NCM. 01-91-03 GEL-1109 UT-45 DEG. m -C-30 *
- 176 f UT-60 DEG.
0-360 -0 m.
LCS-1-AC Bl.11 V6 SA-533 7 NOM. 01-91-03 GEL-1109 UT-45 DEG. NDT-C-30 785 UT-60 DEG.
0-360 -0 m.
LCS-1-AD Bl.11 V6 SA-533 7 NOM. 01-91-03 1109 W-45 m. m + 30 795 UT-60 DEG.
0-360 -0 m.
LCS-1-AE Bl.11 V6 SA-533 7 NOM. 01-91-03 - 09 W -45 m . m -C-30 806 UT-60 DEG.
75 W-0 m.
LCS-1-BA Bl.12 V6 SA-533 8.45 01-92-07 h 1109 W-45 DEG. M -C-30 773 UT-60 DEG.
195 W-0 m.
IES-1-BB Bl.12 V6 SA-533 8.45 01-92-07 GEL-1109 UT-45 DEG. NDT-C-30 770 UT-60 DEG.
315 W-0 m.
LCS-1-BC Bl.12 V6 SA-533 8.45 01-92-07 77g GEL-1109 UT-45 DEG. NDF-C-30 UT-60 DEG.
50 W -0 m .
IES-1-BD Bl.12 V6 SA-533 7 NOM. 01-91-03 7,g GEL-1109 UT-45 DEG. NDF-C-30 UT-60 DEG.
170 W-0 m.
IES-1-BE Bl.12 V6 SA-533 7 NOM. 01-91-03 1109 W-45 m. m + 30 770 UT-60 IEG. .
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_ - . _ ________.m._ _ _ . - _ _ _ _ _ - - _ . - _ _ _ _ . . . - _ _ . ____-_._____________._m.--_ ____ _.s _1 __ _ _ . - . _ _ _ _ _ - _
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o COMMONWEALTE EBISSN COMPANY Lasalle county station omit i n.m.n. c mmey Nees.or asessen Umsee s a 2 asus section n m tion category a 4 COBEWIWIT ITWE WEla amTL. T Ett:St. CRL. AE(DOS) DNS. ermas WWWC.
1.D. tuo. No. Tr7E sFSC. (Ilf) STD. 300. ELT(FT) 10 0 . 6 310 .
290 UT-0 DEG.
LCS-1-BF Bl.12 V6 SA-533 7 Nm. 01-91-03 GEL-1109 UT-45 DEG. NDT-C-30 7,g UT-60 DEG.
G UT-0 DEG.
- LCS-1-BG Bl.12 V6 SA-533 7 NN. 01-91-03 GEL-1109 UT-45 DEG. NDT-C-30 7g5 r UT-60 DEG.
140 -0 E .
LCS-1-BH Bl.12 V6 SA-533 7 NW. 01-91-03 GEL-1109 UT-45 DEG. NDT-C-30 7g, UT-60 DEG.
UT-0 DEG.
LCS-1-BJ Bl.12 V6 SA-533 7 Nm. 01-91-03 GEL-1109 UT-45 DEG. NUT-C-30 7
UT-60 DEG.
LCS-1-BK V6 60 Bl.12 SA-533 7 NN. 01-91-03 79, GEL-1109 UT-45 DEG. NDF-C-30 UT-60 DEG.
1 180 -0 M .
LCS-1-Int Bl.12 V6 SA-533 7 Nm. 01-91-03 L- 09 W-4 5 m. M + 30 795 UT-60 DEG.
300 -0 M .
- LCS-1-BN Bl.12 V6 SA-533 7 NN. 01-91-03 79, M -1109 W-4 5 M. M -C-30 UT-60 DEG.
33 UT-0 DEG.
LCS-1-BP Bl.12 V6 SA-533 7 NN. 01-91-03 , GEL-1109 UT-45 DEG. NDT-C-30 UT-60 DEG.
l l
' g53 W-0 M.
LCS-1-BR Bl.12 V6 SA-533 7 NN. 01-91-03 gg GEL-1109 UT-45 DEG. NDF-C-30 t l UT-60 DEG. [
l i UT-0 DEG.
273 l LCS-1-BS Bl.12 V6 SA-533 7 NW. 01-91-03 ggg E b1109 W -45 M . M -C-30 j
( UT-60 DEG. i BA-2
. - . - - . - . . - - _ - - . - ---.---.-- . -- . -. .. - - . . . - . - -~ - --
s COMMONWEALTH EDESSN COMPANY 3' sane comty steuen wt 1 um commmey n-.a.- m.esom Umsee a a 2 m s euen n ==-4==uem category a-A CatecesasT ITat WRID 15WL. TRICK. CAL. AE(DBS) DWW. ENRhi 3 ROC.
T.D. NO. NO. TYPE SFBC. (IN) STD. NO. BLV(FT) NO. 6 150 .
0-360 0 E.
GEL-1006-AH Bl.21 V3 SA-533 7.45 1-92-03 ,
GEL-1006 UT-45 DEG. NDT-C-30 INACCESSIBLE UT-60 DEG.
0-360 7.45 1-92-03 GEL-1006 UT-0 DEG.
GEL-1006-AJ Bl.21 V2 SA-533 G. -0 0-360
/ 4.2 1-91-05 ,
GEL-1006 UT-60 DEG.
0-360 -0 W.
GEL-1009-AK Bl.21 V9 - SA-533 4.75 01-91-04 ,
GEL-1009 UT-45 DEG. NDT-C-30 UT-60 DEG.
0-360 -0MG.
. GEL-1009-AL B1.21 V8 SA-533 4.75 01-91-04 ,
GEL-1009 UT-45 DEG. NDT-C-30 UT-60 DEG.
9 UT-0 DEG.
GEL-1006-CA Bl.22 V4 SA-533 7.45 1-92-03 ,
GEL-1006 UT-45 DEG. NDT-C-30 PARTIALLY INACCESSIBLE UT-60 DEG.
58 -0 E.
GEL-1006-CB Bl.22 V4 SA-533 7.45 1-92-03 ,
GEL-1006 UT-45 DEG. NDT-C-30 PARTIALLY IMACCESSIBM UT-60 DEG.
l l .
0 UT-0 DEG.
GEL-1006-CC
- Bl.22 V4 SA-533 7.45 1-92-03 GEL-1006 UT-45 DEG. NDT-C-30 PARTIALLY INACCESSIB M UT-60 DEG.
161 -0 E.
CEL-1006-CD Bl.22 V4 SA-533 7.45 1-92-03 ,
GEL-1006 UT-45 DEG. NDT-C-30 PARTIALLY IMACCESSIBLE UT-60 DEG.
UT-0 DEG.
GEL-1006-CE Bl.22 V4 SA-533 7.45 1-92-03 GEL-1006 UT-45 DEG. NDT-C-30 PARTIALLY INACCESSIBLE UT-60 IEG.
266 -0 E .
GEL-1006-CF Bl.22 V4 SA-533 7.45 1-92-03 ,
GEL-1006 UT-45 DEG. NDT-C-30 PARTIALLY INACCESSIBLE UT-60 DEG.
BA-3
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