ML20247R659
| ML20247R659 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/30/1989 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-01, GL-88-1, NUDOCS 8906070285 | |
| Download: ML20247R659 (36) | |
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PHILADELPHIA ELECTRIC COMPANY 23D1 M ARKET STREET P.O. BOX 8699 PHILADELPHIA A. PA.19101 (215)84l4000 May 30, 1989 Docket Nos. 50-352 L
50-353 License No. NPF-39 Construction Permit No. CPPR-107 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Limerick Generating Station, Units 1 and 2 Revised Response to Generic Letter 88-01, "NRC Positl7n on IGSCC in BWR Austenitic Stainless Steel Piping"
Dear Sir:
The purpose of this letter is to revise our response to Generic Letter 88-01 to reflect recent integranular stress corrosion cracking (IGSCC) mitigation' efforts performed at Limerick Generating Station (LGS), Units 1 and 2.
Philadelphia Electric Company (PECo) has implemented the stress improvement option identified in our original response dated August 2, 1988, under the heading " Future Actions to be Taken" on selected Unit 2 welds.
Additionally, although not an IGSCC mitigation activity, the Residual Beat Removal (RHR) Head Spray piping inside primary containment on Unit 1 was removed during the second refueling outage.
Also, we are taking this opportunity to include minor editorial changes, re-categorize certain welds to IGSCC resistant due to acquisition of material certification not available at the time of our original response, upgrade IGSCC categories to reflect the results of ultrasonic testing performed during the Unit 1 second refueling outage, and incorporate a previous revision of our response to Generic Letter 88-01 which was submitted to the NRC by our letter dated April 28, 1989.
This previous revision withdrew our commitment to change the Technical Specifications as described in Generic Letter 88-01.
A brief description of the stress improvement and removal of RHR Head Spray piping is provided below.
Aool 8906070285 890530 ADOCK0500gg{2
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' Docupent Control Desk May 30, 1989 Page 2 Mechanical Stress Improvement Process (MSIP)
The MSIP was performed on 18 welds inside primary containment on Unit 2, 16 of which were reactor pressure vessel nozzle to safe-end welds.
The post-MSIP weld inspections recommended by NUREG 0313, Revision 2, were perforced to establish a baseline for future examinations.
Apparent differences between the 1989 post-MSIP ultrasonic test (UT) results and the 1987 preservice inspection results initiated additional evaluations.
A diversified team composed of PECo, the inspection contractor (General Electric Co.), the stress improvement contractor (O'Donnel & Associates, Inc.), the general contractor (Bechtel), and members from the Electric Power Research Institute's (EPRI's) Nondestructive Evaluation and Repair Application Center was assembled to evaluate the apparent differences in the examination results and resolve any inconsistencies.
Rigorous evaluation of the 1987 versus 1989 inspection results, coupled with pre-and post-MSIP ultrasonic examinations performed on mockups of reactor vessel nozzle to safe-end components simulating LGS Unit 2 conditions, concluded that the weldments were acceptable as-is.
Differences in examination results were attributed to metallurgical structure, minor acceptable imperfections typical of these type of weldments, and the accumulation of many minor influences that included typical variations in equipment, technique, and dimensional changes.
Deletion of the RHR Head Spray Piping Inside Containment The RHR Head Spray piping inside primary containment on Unit 1 was removed during the second refueling outage.
Removal of this piping results in descriptive changes to portions of our original response, and deletion of welds from the accompanying tables.
Specific changes to our original response, including revised IGSCC categories, are provided in the attached revised response.
Changes to the original response are identified by a vertical bar in the right hand margin.
The improvements described previously were integrated with the Inservice Inspection (ISI) activities performed during the Unit 1 second refueling outage, and will be integrated with the Unit 1 and 2 ISI Program activities that will be performed during fiture outages.
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- May.30, 1989
.Page.3
. If-you have any questions concerning our revised. response, pleasei<do not hesitate to contact us.
- r Very truly~yours,
. d. d.
G.A.Hungep,r..
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Director-Licensing Section Nuclear-Support Division k
Attachment.
y cc W. T. Russell, Administrator, Region I, USNRC T. J. Kenny, USNRC Senior Resident Inspector, LGS
'T. M. Gerusky, Commonwealth of Pennsylvania
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Attachment page 1 of'15 REVISED RESPONSE-TO NRC GENERIC LETTER 88-01 LIMERICK CENERATING STATION 50-352/353 DESCRIPTION OF THE LINERICK COMPONENTS WITHIN' THE SCOPE OF NRC GENERIC LETTER.88-01 NRC Generic Letter 88-01. applies to piping system portion:: that meet the following criteria:
o austenitic stainless steel',
-o" four inches or larger in nominal diameter, and.
o contain reactor coolant at a temperature above 200 F during power.
operation.
Thefollowingpipingsystemshaveportionswhichmeetthene'criteriaandlare therefore within~the; scope of NRC Generic Letter 88-01:
o Reactor' Recirculation System o
Residual Heat-Removal (RHR) System o.
. Core Spray System
.o.
Reactor Water. Clean-up (RWCU) System o
Reactor Core Isolation Cooling (RCIC) System
'o Jet Pump Instrumentation System The NRC: Generic Letter also applies to reactor pressure vessel (RPV)
-attachments: and appurtenances such as jet pump. 4 instrumentation penetration assemblies, and-head spray and vent components.
Thelfollowing reactor vessel attachments and appurtenances have portions which are within the scope of_NRC Generic Letter 88-01.
oi Reactor Vessel Stainless Steel Safe-Ends The.following is a detailed definition of the NRC Generic Letter 88-01 scope for Limerick:
Reactor Recirculation System (loops A and B)
Reference:
LGS 1 & 2 P&ID M-43 Sheet 1 28" nominal pipe size (NPS) Reactor Recirculation Pumps A and B o
suction piping, from the RPV N1 nozzle safe-end to pipe welds, through and including the Recirculation Pump suction nozzle welds.
o 28" NPS Reactor Recirculation Pumps A and B discharge piping, from
-the Recirculation Pump discharge nozzle welds, through the 22" NPS headers, and including the 12" NPS piping from the headers to the RPV N2 nozzle safe'-end to pipe welds.
o Connections to the 20" NPS RHR piping on the B pump suction piping, and to the 12" NPS RHR piping on the A and B pump discharge piping.
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1 Revised Attachment Page 2 of 15 Residual Heat Removal System (RHR) i
Reference:
LGS 1 & 2 P&ID's M-51 sheets 1 and 3 20" NPS RHR supply p$ ping, fiam Reactor Recirculation pump B suction o
piping inside containment, to inboard isolation valve F077 (ref.:
line number DCA-105/205).
o 12" NPS RHR return piping, from valves HV-F050 A and B, to Reactor Recirculation pump discharge lines (ref.: line number DCA-104/204).
o 6" NPS RPV head spray piping, including the piping from valve F019 to the RPV head spray flange (ref.: line number DCA-103), was removed during the Unit 1 second refueling outage, and is therefore not in the scope of this response.
o 12" NPS RHR LPCI injection piping, from valves F065 A, B, C, and D, to and including the RPV nozzle N17 safe-end to pipe welds (ref.:
line number DCA 318/418).
Core Spray System
Reference:
LGS 1 & 2 P&ID M-52 Sheet 1 12" NPS Core Spray sparger supply piping, from inboard valve F007 o-A and B, up to and including the 10" NPS RPV N5 nozzle safe-end to pipe welds (ref.: line number DCA-319/419, and 320/420)
Reactor Water Clean-Up System
Reference:
LGS 1 & 2 P&ID's M-44 sheets 1, 2, 3 and 4 o
6" NPS RWCU pump suction piping inside containment, including the connection at the recire suction line and primary containment penetration X-14 (ref.: line number DCA-101/201).
6" NPS RWCU pump suction piping outside containment (ref.: line o
number DCB 102/202, DCB-102/202, DCC-103/203.
4" NPS RWCU pump discharge piping, from the 4" x 3" reducers in the o
RWCU pump discharge header, to the tube side inlet of the Non-Regenerative heat exchanger (ref.:
line number DCC-101/201).
RWCU piping from the tube side outlet of the Regenerative heat o
exchanger to the tube side inlets of the Non-Regenerative heat exchanger (ref.:
line number DCC-102/202).
RWCU return piping from the shell outlet of the Regenerative heat o
exchanger to RWCU valve HV-F039 (ref.:
line number DCC-104/204, ECC-105/205).
s Rezised Attachment Page 3 of 15 Reactor Core Isolation Cooling System
Reference:
1CS1&2 P&ID's M-49 sheets 1 and 2 o
The welds at the pipe connection to the stainless steel flow element FE-NOl6 (ref.:
line number DBA-107/207).
Jet Pump Instrumentation System
Reference:
LGS 1 & 2 P&ID's M-42 sheets 1 and 2 The circumferential welds greater than 4" NPS between the RPV nozzle o
NB and the jet pump instrumentation penetration seal.
Reactor Vessel Stainless Steel Safe-Ends The RPV attachments and appurtenances within the scope of this response are limited to stainless safe-ends attached to RPV nozzles.
o The stainless steel safe-ends and the nozzle to safe-end welds for RPV nozzles N1, N2, N5, N8, N9, N10, Nil, N12, N16, and N17.
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Twvised Attachment Page 4 of 15 RESPONSE TO TTEMS IN NRC GENERIC 12TTER 88-01 ITEM 1 0F NRC GENERIC LETTER 88-01 "Your current plans regarding pipe replacement and/or other measures taken or to be taken to mitigate IGSCC and provide assurance of continued long term piping integrity and reliability.
RESPONSE TO TTEM 1 Plans Regarding Piping Replacement The focus of the IGSCC mitigatior program at Limerick has been to minimize the amount of susceptible piping originally placed in the plant.
This approach has obviated the need for any large scale replacement effort. With only three exceptions, the materials used in the Limerick Generating Station are resistant due to their chemical composition.
Additionally, all of the longitudinal seam welds in the resistant piping have been solution heat treated. The exceptions to the use of resistant I
material are:
o certain welds involving RPV safe-ends o
Two welds involving a flow element in the RCIC system, o
and Unit 1 RWCU beyond the outer containment isolation valve.
IGSCC mitigation activities for these non-resistant welds are discussed below, and conformance to the staff positions on inspection schedules, methods and personnel, and sample expansion are included in the response to Item 2 of the Generic Letter.
Current IGSCC Mitigation Efforts Current mitigation measures include water chemistry control, stress improvement, inspections, and leakage detection.
The PECo BWR water chemistry control program is detailed in Rev. O of nniladelphia Electric Company's NGAP-NPC-1, " Interim Nuclear Group Administrative Procedure - Chemistry Control Program", effective date August 22, 1988. The water chemistry control requirements in this program are in accordance with the BWR Owners' Group and Electric Power Research Institute (EPRI) Water Chemistry Guidelines, existing General Electric Chemistry recommendations, and INPO recommendations.
The Mechanical Stress Improvement Process (MSIP) was performed on 18 welds insid2 containment on Unit ?, of which % were reactor pressure vessel nozzle to safe-end welds. The post MSIP weld inspections required by NUREG 0313, Revision 2, were performed to establish a baseline for future examinations.
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4 Revised Attachment Page 5 of 15 Details concerning the augmented inspection program and leakage detection I
program are discussed in this response under their applicable NfC Generic f
Letter 88-01 item numbers.
I RHR Head Spray piping inside containment was removed on Unit 1 during the second refueling outage. Although this pipe removal was not performed as an IGSCC mitigation effort, a consequence of this pipe removal is a reduction in the number of RHR IGSCC Category A welds in the scope of Generic Letter 88-01.
Future Actions to be Taken For the few welds at Limerick which are not IGSCC Category A, stress improvement and replacement are options that remain open at this time.
Reclassification of IGSCC categories resulting from remedial actions or aquisition of additional information will be incorporated in the Inservice Inspection Program to assure continued conformance to the staff positions on inspection schedules, methods and personnel, and sample expansion.
ITEM 2 OF NRC GENERIC LETTER 88-01 "An Inservice Inspection (ISI) Program to be implemented at the next refueling outage for austenitic stainless steel piping covered under the scope of this letter that conforms to the staff positions on inspection schedules, methods and personnel, and sample expansion included in this l o tter. "
RESPONSE TO ITEM 2 Augmented ISI Plan for detecting IGSCC The Augmented ISI Plan requirements for the individual Limerick Unit 1 and 2 weldments within the scope of this NRC Generic Letter are given as Appendices A and B of this document for LGS 1 & 2 respectively. These requirements have been integrated with the inservice inspection activities performed during the Unit I second refueling outage, and will be integrated with the Unit 1 & 2 Inservice Inspection Program to be implemented at future refueling outages. The information provided for each weld in the appendices includes the system, piping isometric, weld j
number, description, and the applicable IGSCC Examination Category according to the requirements of Table I of NUREG 0313, Revision 2.
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It should be noted that since Limerick Unit 2 is not yet operational, the IGSCC Classification of cll Unit 2 welds is preliminary only. The IGSCC l
welds which are not Catngory A may be upgraded by stress improvement or replacement. The preliminary IGSCC Categorization Sannaries for all LGS 2 welds within the scope of NRC Generic Letter 88-01 are given as Tables 3 and 4 of this response for Item 2 of the Generic Letter.
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Revised Attachmens 4
1 Page 6 of 15 Inspection Schedules The inspections will be performed at frequencies which will be in conformance.with the Staff Position on Inspection Schedules for the piping welds within the scope of Generic Letter 88-01.
The IGSCC categories for these welds are given in the tables contained in Appendies A and B for LGS 1 and 2.
A weld count summary of these tables is provided for LGS I and 2 in Tables 1, 2, 3, and 4 of this response. The summary indicate? the distribution of welds in each IGSCC Category for the secpe systems.
Inspection Methods and Personnel PECo is committed to complying with the NRC Staff positions on inspection methods and personnel as delineated in NRC Generic Letter 88-01.
For ultrasonic testing (UT) of UT inspectable ASME Class 1 and 2 welds, the IGSCC inspections will generally be performed in accordance with the requirements contained in the applicable edition and addenda of ASME Section XI for the ASME class of the weldment. For UT inspectable ASME Class 3'and non-class welds, the requirements in Section XI for Class 2 welds will apply. Details of the volumetric examination method may be upgraded as practical to ensure that the examinations will be effective.
The integrity of ASME Class 1, 2, and 3 welds that are not UT inspectable will be verified by the applicable ASME Section XI pressure test program.
The consideration of pressure tests for welds that are not UT inspectable is allowed by Note 3 to Table 1 in NUREG 0313 Revision 2.
The Reactor Water Clean-up System outside of containment is the only system with significant portions within the scope of the Generic Letter that are presently considered to be UT uninspectable. The integrity of Non-ASME Class welds that are not UT inspectable will be verified by pressure tests in accordance with the requirements of ASME Section XI Article IWB, IWC, or IWD - J000.
The edition and addenda of ASME Section XI used for determining these requirements will be as dictated by paragraph (g) of 10 CFR 50.55a.
The personnel performing the IGSCC volumetric inspections will be qualified for such inspections by a formal program approved by the NRC.
Sample Expansion If one or more Category A, B, or C welds are found to be cracked, or if additional cracks or significant crack growth is discovered in a Category E weld during the ISI interval, a sample expansion plan will be invoked.
1 The sample expansion plan utilized will be as put forth in the Staff l
Position on Sample Expansion contained in NRC Generic Letter 88-01.
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-Attachment Page 7aof 15
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Categorization Summaries 2
,k The following' Tables 1, 2,-3, and 4 provide a system by syst.m summary resulting from.the' categorization'of the weldments within the scope of
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ithis response for each unit. ~ This summary is included to facilitate
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- assessment of the~ Limerick status with regard to'IGSCC. Scheduling of
[T j the'IGSCC examinations for these weldments shall'be as specified in Table r^-
T of NUREG 0313 Rev. 2.
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.It should be noted that Unit 1 welds which were originally assigned to
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Category G have been' upgraded-to Category D since being UT inspected at gr
- the second refueling outage.
r TABLE 1:- Categorization Summary for IES 1 Piping
-Reactor Recirculation (Category A Welds:
239*
Category B Welds:
0
' Category.C~ Welds:
0 g
Category D Welds:
0 f
' Category E Welds:
O Category F. Welds:
0
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Category G Welds:
0 gy
239
- The two recirculation outlet nozzle N1 sa' 1 -end to pipe welds have been upgraded from IGSCC. Category G based on verification of material properties.
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- Residual Heat Renoval 3
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_ Category A Welds:
81*
?
~ Category B Welds:
0 s.
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Category C Welds:
0 f
Category D Welds:
0 Category E Welds:.
O Category.F Welds:
O Category G Welds:
_0 g
81
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.N37 involve nickel alloy forgings. NRC Generic Letter l
88-01 allows evaluation on a case by case basis.
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.Categoris#
my.for IES 1 Piping (Continued)
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_ Core Spray i
Catego.,
, _ Welas:
26*
'.y-Category B Welds:
0 Category C Welds:
0
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Category D. Welds:
0 Category E Welds:
0 Category F Welds:
0
_ Category G Welds:
0 4
Total 1GSCC Melds:
26
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- The two safe-end to. pipe welds at the N5 inlet nozzle involve nickel alloy forgings. NRC Generic letter l
88-01~' allows evaluation a case by case basis.
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. Reactor Water Clean-Up (RHR to cuter containment isolation valves)
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- Category A Welds:
29
-Category.B Welds:
0
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55
~ Category C. Welds:
0
' Category D Welds:
0 N
Category E Welds:
0-
. Category F Welds:
'O-
- Category G Welds:
0 1
JTotal 1GSCC Welds:
29 l
' Reactor Water Clean-Up (beyond outer containment
. isolation valve)-
Category A Welds:
O Category B Welds:
0 Category C Welds:
O Category D Welds:
O Category E Welds:
0 Category F Welds:
0
-Category G Welds:
195*
195
- These weldments are constructed of non-resistant base materials and they have not yet been inspected for IGSCC in accordance with the requirements of NRC Generic Letter 88-01.
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l l-Revised Attachment Page 9 of 15 TABLE 1: Categorization Summary for LCS 1 Piping (Continued)
Reactor Core Isolation Cooling Category A Welds:
O Category B Welds:
O Category C Welds:
O Category D Welds:
2*
Category E Welds:
O Category F Welds:
O Category G Welds:
0 Total ICSCC Welds:
2
- The two Category D Welds are to a high carbon stainless steel flow element, and have been upgraded from IGSCC Category G based on UT examinations performed during the becond refueling outage.
Jet Pump Instrumentation Category A Welds:
4*
Category B Welds:
O Category C Welds:
O Category D Welds:
O Category E Welds:
O Category F Welds:
O Cat egory G Welds:
0 Total ICSCC Welds:
4
- The two safe-end to seal extension welds and the two seal extension to seal welds have been upgraded from IGSCC Category D based on verification of material properties.
TABIE 2: Categorization Summary for LCS 1 RPV Attachments (nozzle to safe end welds)
RPV NOZZLE NUMBER N1 N2 N5 N3 N9 N10 N11 N12 N16 N17 Category A Welds:
0 0
0 0
0 0
2 4
4 0
Category B Welds:
O O
O O
O O
O O
O O
Category C Welds:
0 0
0 0
0 0
0 0
0 0
Category D Welds:
2 10 2
2 1
0 0
0 0
4 Category E Weldc:
0 0
0 0
0 0
0 0
0 0
Category I' Welds:
0 J
0 0
0 0
0 0
0 0
Category G Wolds:
0 0
0 0
0 1
0 0
0 0
2 10 2
2 1
1 2
4 4
4 Note:
Except for N10, which is not UT inspectable, non resistant RPV nozzle to saf e-end welds were assigned to IGSCC Category D in lieu of Category G based on the following:
4 Revised Attachment Page 10 of 15' o These welds were examined during preservice inspection (PSI) using the most. updated UT techniques available (ref.: procedure LIM-UT-3 vendor print 8031-M-246B-56).
o No cracks were reported during the PSI examinations.
o The Unit 1 ISI program requires certification in accordance with the EpRI program for IGSCC detection.
TABI2 3: Categorization Sunnary for LGS 2 Piping Reactor Recirculation Category A Welds:
239*
Category B Welds:
O Category C Welds:
O Category D Welds:
O Category E Welds:
O Category F Welds:
C Category G Welds:
239
- The two recirculation outlet nozzle N1 safe-end to pipe welds have been upgraded from from IGSCC Category D based on verification of material properties.
Residual Heat Removal Category A Welds:
7B*
Category B Welds:
O Category C Welds:
O Category D Welds:
O Category E Welds:
O Category F Wolds:
O Category G Welds:
78
- The four nafe-end to pipe welds at the LPCI N17 inlet nozzle involve nickel alloy forgings. NRC Generic Letter 88-01 allows evaluation on a case by case basis.
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F Revised Attachment Page 31 of 15 TABLE 3: Categorization Sununary for IES 2 Piping (Continued)
Core Spray Category A Welds:
24*
Category B Welds:
O Category C Welds:
O e
Category D Wolds:
O Category L Welds:
0 Category F Welds:
O Category G Welds:
_O Total ICSCC Welds:
24
- The two safe-end to pipe welds at the NS inlet nozzle involve nickel alloy forgings. NRC Generic Letter 88-01 allows evaluation on a case by case basis.
Reactor dater Clean-Up'(RHR to outer containment isolation valves)
Category A Welds:
47 Category B Welds:
O Category C Welds:
O Category D Wolds:
O Category E Welds:
O Category F Welds:
O Category G Wolds:
47 Reactor Water Clean-Up (beyond outer containment isolation valve)
Category A Welds:
181 Category B Welds:
O Category C Welds:
O Category D Yelds:
O Category E Welds:
O Category F Welds:
O Category G Welds:
381
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Attachment Page 12 of 15 TABLE 3: Categorization Sunanary for IES 2 Piping (Continued)
Reactor Core Isolation Cooling Category A Welds:
O Category B Welds:
2*
Category C Welds:
O Category D Welds:
O Category E Welds:
0
, Category F Welds:
O Category G Welds:
2
- The two Category B welds are to a high carbon stainless steel flow element, and have been upgraded from IGSCC Category D because of implementation of MSIP.
Jet Pump Instrumentation Category A Welds:
4*
Category B Welds:
O Category C Welds:
O Category D Welds:
O Category E Welds:
O Category F Welds:
O Category G Welds:
4
- The two safe-end to seal extension welds and the two seal extension to seal welds have been upgraded from IGSCC Category D based on verification of material properties.
TABLE 4: Categorization Summary for IES 2 RPV Attaclunents (nozzle to safe-end welds)
RPV NOZZLE NUMBER N1 N2 NS N8 N9 NIO N11 N12 N16 N17 Category A Welds:
2 0
0 2
1 0
2 4
4 0
Category B Welds:
0 10 2
0 0
0 0
0 0
4 Category C Welds:
0 0
0 0
0 0
0 0
0 0
Category D Welds:
0 0
0 0
0 0
0 0
0 0
I Category E Welds:
0 0
0 0
0 0
0 0
0 0
f Category F Welds:
0 0
0 0
0 0
0 0
0 0
Category G Welds:
0 0
0 0
0 3
0 0
0 0
Total 1GSCC Welds:
2 10 2
2 1
1 2
4 4
4 Note:
Except for N10, which is not UT inspectable, non resistant RPV nozzle to safe-end welds are assigned to IGSCC Category B because of implementation of MSIP.
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9 Revised Attachment i
Page 13 of 15 ITM 3 OF NRC GENERIC LETTER 88-01 "A change to the Technical Specifications to include a statement in the section on ISI that the Inservice Inspection Program for piping covered by the scope of this letter will be in conformance with the staff positions on schedule, methods and personnel, and sample expansion included in this letter (see enclosed model BWR Standard Technical Specification).
It is recognized that the Inservice Inspection and Testing section may be removed from the Technical Specifications in the future in line with the Technical Specification Improvement Programs.
In this case, this requirement shall remain with the ISI section when it is included in an alternative document.
RESPONSE TO ITEM 3 Inserting the reconenended statement into Section 4.0.5 of the Limerick Technical Specifications, which contains surveillance requirements, is not consistent with the philosophy of the Technical Specifications Improvement Program which encourages the relocation of various specifications to other licensee controlled documents. As stated in the response to Item 2 of the Generic Letter, the staff positions on IGSCC will be incorporated into the ISI Program. Documentation in the ISI Program, coupled with the FSAR statement described below, satisfies the commitment for documenting conformance to the staff positions on IGSCC.
The ISI program for Limerick is described in the FSAR. A revision has been made to the FSAR, Section 5.2.4, (for Class 1 components) and Section 6.6 (for Class 2 & 3 components) reflecting the following intent:
"The Inservice Inspection (ISI) Program for weldments in piping identified in accordance with the criteria of HRC Generic Letter 88-01 shall be performed in accordance with the NRC staff positions addressed in this Generic Letter. Details for schedule, methods, personnel, and sample expansion are included as augmented inspection requirements in the ISI program.
1 TEM 4 of NRC GENERIC LETTER 88-01
" Confirmation of your plans to ensure that the Technical Specification related to leakage detection will be in conformance with the staff position on leak detection included in this letter.
RESPONSE TO ITEM 4 It is Philadelphia Electric Company's position that the existing Technical Specifications are in conformance with the staff position on leak detection, and therefore a change to the Technical Specifications is not required. A review of the Limerick Technical Specifications identified the following:
O v
Revised Attachment page 14 of 15 o
The drywell floor drain sump and drywell equipment drain tank monitoring system is designed to meet the intent of Regulatory Guide 1.45 for quantifying leakage, o
The Technical Specifications require that Reactor Coolant unidentified leakage shall be limited to 5 gpm or the unit will be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
o The Technical Specifications require that Reactor Coolant total leakage be limited to 30 gpm or the unit will be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, o
The Technical Specifications require that the drywell floor drain sump and drywell equipment drain tank flow rate are monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
o The Technical Specifications require that the drywell floor drain sump and drywell equipment drain tank flow monitoring system are required to be operable or the unit will be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
o In addition, reactor coolant leakage is detected by the primary containment atmosphere gaseous radioactivity monitoring system, the drywell unit coolers condensate drain flow monitoring system and the primary containment pressure and temperature monitoring systems.
These systems are also addressed in the Technical specifications.
ITEM S OF NRC GENERIC LE' ITER 88-01 "In accordance with 10 CFR 50.55a(g), your plans to notify the NRC of any flaws that do not meet IWB-3500 criteria of Section XI of the Code for continued operation without evaluation, or a change found in the condition of welds previously known to be cracked, and your evaluation of the flaws for continued operation and/or your repair plans."
RESPONSE TO ITEM 5 NRC Notification Philadelphia Electric Company plans to adopt the staff position on notification.
If any flaws are identified which do not meet the referenced criteria for continued operation, the NRC will be duly notified of the disposition of the affected flaws. NRC approval of the disposition for each flaw exceeding the criteria will be obtained before operation is resumed.
Flaw Evaluation Flaws exceeding the acceptance criteria of IWB-3500 of ASME Section XI will be either repaired, replaced or evaluated. Repairs or replacements will be documented in the Owners Report for Repairs and Replacements as required by ASME Section XI.
Evaluations of flaws for continued operation will be performed in accordance with the criteria in IWB-3600 of ASME Section XI.
For aspects of flaw evaluaticn which are not
7
)
[.
4 Revised Attachment s
Page 15 of.35 contained in IWB-3600, the specif.ications in NUREG-0313 Revision 2 will be used in conjunction with IWB-3600.
L The above referenc $ criteria for accep*tance and evaluation are found in the 1986 Edition of ASME Section XI.
CGSO428.3
+
4.-
1 l-APPENDIX A Listing ach IGSCC Classifications of LGS 11 nit 1 items Requiring IGSCC Augmented Inspections Note: ISI weld numbers replace the " Weld No's" of Appendices A and B in the ISI Program Revised Appendix A Tables are dated 05/05/B9. Only the following Appendix A pages which are affected by the 05/05/89 revision are included with the revised Generic Letter 88-01 response:
Page No.'s 5, 6, 18, and 29
-.~,_----w-------
z----x----.
-.----------_..----~.--u_------._------_--,.----_.-----------------------_--_.-..-,-,---------------.----.----------_---------------aa-
- - - - --.---w----a
E I
e.
- Page No. 5
'05/05/89 i
LIMERICK UNIT 1 WELDS l
SYSTEM ISO MEID NO DESCRIPTION IGSCC CATEGORY Core Spray EBB-131-1-3 FW50 12" Pipe to Pipe, N/A Bimetallic RCIC DBA-107-1-9 FW4 4" FE IN016 to Pipe, D
Bimetallic RCIC DBA-107-1-9 FW54 4" Pipe to FE IN016, D
Bimetallic 1
RtlR DCA-103-1-10 FW54 6" Elbow to Pipe N/A RHR DCA-103-1-14 FW55 6" Pipe to Flange N/A RHR DCA-103-1-14 FW56 6" Flange to Pipe N/A RHR DCA-103-1-15 FW57 6" Pipe to Valve N/A HV-1F022 RHR DCA-103-1-7 FW53 6" Elbow to Pipe N/A RER DCA-103-1-7 SW2 6" Pipe to Elbow N/A RHR DCA-103-1-7 SW3 6" Elbow to Pipe N/A RHR DCA-103-1-7 SW4 6" Pipe to Elbow N/A RHR DCA-103-1-7 SW6 6" Pipe to Elbow N/A RHR DCA-103-1-7D FW63 6" Pipe to Pipe N/A RHR DCA-103-1-7E FW64 6" Pipe to Pipe N/A RHR DCA-103-1-B FW3 6" Elbow to Pipe N/A RHR DCA-103-1-8 SW1 6" Pipe to Elbow N/A RHR DCA-103-1-B SW2 6" Elbow to Pipe N/A RHR DCA-103-1-8 SW3 6" Pipe to Elbow N/A RHR DCA-103-1-8 SW6 6" Pipe to Pipe N/A RHR DCA-103-1-9 FW4 6" Valve 1F019 to N/A Pipe RHR DCA-103-1-9 FW5 6" Pipe to Valve N/A IF019 RER DCA-103-1-9 FW51 6" Pipe to Elbow N/A
7--
- Page No. 6 05/05/89 LIMERICK UNIT 1 WEIBS SYSTEM ISO WELD NO DESCRIPTION IGSCC CATEGORY RHR DCA-103-1-9 FW62 6" Pipe to Pipe, N/A Bimetallic RHR DCA-103-1-9 SW1 6" Elbow to Pipe N/A L
RHR DCA-104-1-1 FWll 12" Pipe to Pipe N/A RHR DCA-104-1-1 SW1 12" Elbow to Pipe N/A RHR DCA-104-1-1A FW1 12" Flued UD. (X-13B)
N/A to Valve HV-1F015B RHR DCA-104-1-1A FW3 12" Pipe to Flued N/A Head (X-13B)
RHR DCA-104-1-1A SW1 12" Elbow to Pipe N/A RHR DCA-104-1-1A SW2 12" Pipe to Elbow N/A RHR DCA-104-1-1B FW10 12" Pipe to Pipe N/A RHR DCA-104-1-2 FW4 12" Pipe to Elbow N/A RHR DCA-304-1-2 FW5 12" Valve HV-1F050B N/A to Pipe RHR DCA-104-1-2 SW 12" Pipe to Pipe N/A RHR DCA-104-1-2 SW1 12" Pipe to Elbow N/A RHR DCA-104-1-2 SW2 12" Elbow to Pipe N/A RHR DCA-104-2-1 FW10 12" Pipe to Pipe N/A RHR DCA-104-2-1 FW11 12" Pipe to Pipe N/A RHR DCA-104-2-1A FW1 12" Flued HD. (X-13A)
N/A to Valve HV-1F015A RHR DCA-104-2-1A FW3 12" Pipe to Flued N/A Head (X-13A)
RHR DCA-104-2-1A SW1 12" Pipe to Elbow N/A RHR DCA-104-2-1A SW2 12" Elbow to Pipe N/A RHR DCA-104-2-1A SW4 12" Pipe to Pipe N/A RHR DCA-104-2-1B SW1 12" Elbow to Pipe N/A Note: The four N17 pipe to safe-end welds are excluded from this detailed list; however, they are classified as IGSCC Category A.
b
'S
'Page No. 18 05/05/89 LIMERICK UNIT 1 WELDS SYSTEM TSO WEID NO DESCRIPTION IGSCC CATEGORY RR RD-1-A6 SEAM 12" Pipe Seam
.A RR RD-1-A6' SEAM 12" Pipe Seam A
RR RD-1-A6 SEAM 12" Elbow Seam, A
Maximum RR RD-1-A6 SEAM 12" Elbow Seam, A
Minimum RR RD-1-A6 SEAM 12" Pipe Seam A
RR RD-1-A6 SEAM 12" Pipe Seam A
RR RD-1-A6 SEAM 12" Elbow Seam, A
Maximum RR RD-1-A6 SEAM 12" Elbow Seam, A
Minimum RR RD-1-A6 SWB 12" Pipe to Elbow A
RR RD-1-A6 SWC 12" Elbow to Pipe A
RR RD-1-A7 FWWA14 22" x 12" Sweepolet A
to 12" Pipe RR RD-1-A7 SEAM 12" Pipe Seam A
RF RD-1-A7 SEAM 12" Pipe Seam A
RR RD-1-A7 SEAM 12" Elbow Seam, A
Maximum RR RD-1-A7 SEAM 12" Elbow Seam, A
Minimum RR RD-1-A7 SEAM 12" Pipe Seam A
RR RD-1-A7 SEAM 12" Pipe Seam A
RR RD-1-A7 SEAM 12" Elbow Seam, A
Maximum l
RR RD-1-A7 SEAM 12" Elbow Seam, A
M]nimum RR RD-1-A7 SWB 12" Pipe to Elbow A
RR RD-1-A7 SWC 12" Elbow to Pipe A
Note: The two N1 pipe to safe-end welds are excluded from this detailed list; l
however, they are clag:nified as 1GSCC Category A.
a
s:
i.
Page No. 29 05/05/89 LIMERICK UNIT 1 WELDS r
SYSTEM ISO WELD NO DESCRIPTION ICSCC CATECORY
_RWCU DCA-101-5-24 FW53 4" Pipe to Elbow N/A RWCU DCA-101-5-24 FW68 4" Tee to Pipe N/A
!=
RWCU DCA-101-5-24 SW57 4" x 6" Reducer to N/A 6" Valve HV-1F100 RWCU DCA-101-5-24 SW58 6" Valve HV-1F100 N/A 6" x 4" Reducer RWCU DCA-101-5-24 SWX20 6" x 4" Reducer to N/A Pipe RWCU DCA-101-5-24 SWX29 4" Pipe to 4" x 6" N/A Reducer RWCU DCA-101-5-6 FW69 4" Tee to Cap N/A RWCU DCA-101-5-6 SW17 2 1/2" x 4" Reducer N/A to 4" mee RWCU DCB-102-1-1 FW1 6" Valve HV-1F040 to N/A 6" Pipe RWCD DCB-102-1-1 FW2 6" Pipe to Valve N/A HV-1F040 RWCU DCC-103-1-1 FW1 6" Valve HV-1F040 to N/A Pipe
-RWCU DCC-103-1-4A SW1 6" Pipe to Elbow N/A RWCU DCC-103-1-4A SW2 6" Elbow to Pipe N/A RWCU SP-DCA-113-El FW401 2" Pipe to Pipe N/A Bimetallic Note: The two jet pump safe-end to seal extension welds and the two neal extension to seal welds (4 total) are excluded from this detailed Idst; however, they are classified as IGSCC category A.
The nozzle to safe-end welds are excluded from this detailed list for N1, N2, N5, NB, N9, N10, N11, N12, N16, and N17; however, the classifications are included in Table 2.
i l
l
?.
"- ' h
!f.
.(
n
~.;,
.i j:
p.3. L I
i'-
APPENDIX B Listing and IGSCC Classifications of LGS. Unit 2 items Requiring ICSCC Augmented-Inspections Note: ISI weld numbers replace the " Weld No.'s" of Appendices A and B in the ISI Program
(.
Revised Appendix B tables are dated 05/05/89. Only the following Appendix B pages which are affected by the 05/05/89 revision are included with the revised Generic Letter 08-01 response:
Page No.'s 1, 7, 8, 9, 10, 12, 13, 10, 22, 26, 27, and 29
--_x--_-_--------------
.---------x-
'\\
+
'Page No. 1 05/05/89 LIMERICK UNIT 2 WFJ E S SYSTEM ISO WELD HO DESCRIPTION IGSCC CATECORY MS APE-2MS-LA N3A Nozzle to Safe End N/A (GE) ( AZ. 72)
MS APE-2MS-LA WA01 Safe End to Pipe (GE)
N/A (AZ. 72)
MS APE-2MS-LB N3B Nozzle to Safe End N/A (GE) (AZ. 108)
MS APE-2MS-LB WB01 Safe End to Pipe N/A (GE) (AZ. 108)
MS APE-2MS-LC N3C Nozzle to Safe End N/A (GE) (AZ. 252DEG)
MS APE-2.MS-LC WC01 Safe End to Pipe N/A (GE) (AZ. 252DEG)
MS APE-2MS-LD N3D Nozzle to Safe End N/A (GE) (AZ. 286DEG)
~ d to Pipe N/A MS APE-2MS-LD WD01 Saf(
u (GE) (AZ. 286DEG)
RCIC DBA-207-1 FW11 4" Pipe to FE-2N016 B
(Birnetallic)
RCIC DBA-207-1 FW4 4" FE-2N016 to Pipe B
(Bimetallic) l RWCU D^.A-2 01-1 FW1 20" x 6" Sweepolet A
to 6" Pipe RWCU DCA-201-1 FW10 6" Pipe to Valve A
HV-2F105 RWCU DCA-201-1 FW11 Valve HV-2F105 A
l to 6" Pipe RWCU DCA-201-1 FW12 6" Pipe to A
6" x 6" x 6" Tee l
RWCU DCA-201-1 FW13 6" x 6" x 6" Tee A
to 6" Pipe RWCU DCA-201-1 FW14 G" Pipe to Elbow A
RWCU DCA-201-1 FW15 6" Elbow to Pipe A
RWCU DCA-201-1 FW16 6" Elbow to Pipe A
L. *
- Page No. 7 05/05/89 LIMERICK UNIT 2 WELDS SYSTEM ISO WEID NO DESCRIPTION 1GSCC CATEGORY RHR DCA-205-3 -2 SW1 20" Pipe to 20" x 6" A
Sweepolet RHR DCA-205-3 -3 FW4 LU Elbow Seam Minimum A
RHR DCA-205-3 -3 FW4 0 Elbow Seam Maximum A
RHR DCA-205-3 -3 FW5 LD Elbow Seam Minumun A
RHA DCA-205-3 -3 FW5 LD Elbow Seam Maximum A
RHR DCA-205-3 -4 FWS LU Pipe Seam A
RHR DCA-205-3 -4 FW6 LD Pipe Seam A
RHR DCA-418-1 FW1 12" Pipe to Safe End A
(GE) (AZ. 135 DEG.)
RHR DCA-418-1 FW2 12" Pipe to Pipe A
RHR DCA-418-1 FW3 12" Elbow to Pipe A
RHR DCA-418-1 FW4 12" Valve 2F065D A
to Elbow RHR DCA-418-1 FWS 12" Pipe to Valve N/A 2F065D RHR DCA-418-1 FW6 12" Elbow to Pipe N/A RHR DCA-418-1 N17B Safe End to Nozzle B
(GE) (AZ. 135 DEG.)
RHR DCA-418-1 -1 FW3 LU Elbow Seam Minimum A
RHR DCA-418-1 -1 FW3 LU Elbow Seam Maximum A
RHR DCA-418-1 -1 FW4 LD Elbow Seam Minimum A
RHR DCA-418-1 -1 FW4 LD Elbow Seam Maximum A
RHR DCA-418-1 -2 FW6 LU Elbow Seam Minimum N/A RHR DCA-418-1 -2 FW6 LU Elbow Scam Maximum N/A RHR DCA-418-1 -2 SW1 12" Pipe to Elbow N/A
1
- Page No. 8 i
_05/05/89 LIMERICK UNIT 2 WELDS EYSTEM I SO..
WELD NO DESCRIPTION ~
IGSCC CATEGORY RHR DCA-418-1 -2 SW1 LD Elbow Seam Minimum N/A RHR DCA-418-1 SW1 LD Elbow Seam Maximum N/A KHR DCA-418-1 -2 SW1 LU Pipe Seam N/A RHR DCA-418-1 -2 SW3 12" Pipe to Pipo N/A (Bimetallic)
RHR DCA-418-1 -2 SW3 LD Pipe Scam N/A RHF DCA-418-1 -3 FW2 LU Pipe Seam A
RHR DCA-418-1 -3 FW3 LD Pipo Seam A
RHR DCA-418-1 -4 FWS LU Pipe Seam N/A RHR DCA-418-1 -4 FW6 LD Pipe Seam N/A RHR DCA-418-1 -5 FW1 LU Pipe Seam A
RHR DCA-418-1 -5 FW2 ID Pipe Seam A
RHR DCA-418-2 FW1 12" Pipe to Safe End A
(GE) (AZ, 45 DEG.)
RHR DCA-418-2 FW2 12" Pipo to Pipe A
RHR DCA-418-2 FW3 12" Elbow to Pipe A
RHR DCA-418-2 FW4 12" Valve 2F065B A
to Elbow RHR DCA-418-2 FW5 12" Pipe to Valve N/A 2F065B RHR DCA-418-2 FW6 12" Elbow to Pipe N/A RHR DCA-418-2 N17A Safe End to No::zle B
(CE) (AZ. 45 DEG.)
RHR DCA-418-2 -1 FW3 LU Elbow Seam Minimum A
RHR DCA-418-2 -1 FW3 LU Elbow Seam Maximum A
RHR DCA-438-2 -1 FW4 LD Elbow Seam Minimum A
RHR DCA-418-2 -1 FW4 LD Elbow Seam Maximum A
RHR DCA-418-2 -2 FW6 LU Elbow Seam Minimum N/A
[:
4 9.
l
- PaheNo.9.
05/05/89 LIMERICK UNIT 2 WELDS SYSTEM ISO WELD NO-DESCRIPTION 3GSCC CATEGORY RHR.
DCA-418-2
-2.
FW6 LU Elbow Seam Maximum N/A RHR DCA-418-2 -2 SW1 12" Pipe to Elbow N/A j
l.
RHR DCA-418-2 -2 SW1 LD Elbow Seam Minimum N/A RHR-DCA-418-2 -2 SW1 LD Elbow Seam Maximum N/A RHR DCA-418-2 -2 SW1 LU Pipe Seam N/A l
RHR DCA-418-2 -2 SW3 12" Pipe to Pipe N/A (Bimetallic)
RHR DCA-418-2 -2 SW3 LD Pipe Seam N/A RHR DCA-418-2 -3 FW2 LU Pipe Seam A
RHR DCA-418-2 -3 FW3 LD Pipe Seam A
RHR DCA-418-2 -4 FW5 LU Pipe Seam N/A
- RHR DCA-418-2 -4 FW6 LD Pipe Soam N/A RHR DCA-418-2 -5 FW1 LU Pipe Seam A
RHR DCA-418-2 -5 FW2 LD Pipe Seam A
RHR DCA-418-3 FW1 12" Pipe to Safe End A
(GE) (AZ. 225 DEG.)
RHR DCA-418-3 FW2 12" Pipe to Pipe A
RHR DCA-418-3 FW3 12" Elbow to Pipe A
RHR DCA-418-3 FW4 12" Vals9 2F065A A
to Elbow RHR DCA-418-3 FW5 12" Pipe to Valve N/A 2F065A RHR DCA-418-3 FW6 12" Elbow to Pipe N/A RHR DCA-418-3 N17C Safe End to Nozzle B
(GE) (AZ. 225 DEG.)
RHR DCA-418-3 -1 FW3 LU Elbow Seam Minimum A
RHR DCA-418-3 -1 FW3 LU Elbow Seam Maximum A
RHR DCA-418-3 -1 FW4 LD Elbow Seam Minimum A
l
.s
- Page No. 10 05/05/89 LIMERICK UNIT 2 WEIDS SYSTEM ISO WEID NO DESCRIPTION ICSCC CATEGORY RHR DCA-418-3
-l' FW4 LD Elbow Seam Maximum A
v RilR DCA-418-3 -2 FW6 LU Elbow Seam Minimum N/A RHR DCA-418-3 -2 FW6 LU Elbow Seam Maxinum N/A RHR DCA-418-3 -2 SW1 12" Pipe to Elbow N/A RHR DCA-418-3 -2 SW1 LD Elbow Seam Minimum N/A RHR DCA-418-3 -2 SW1 LD Elbow Seam Maximum N/A RHR-DCA-418-3 -2 SW1 LU Pipe Seam N/A RHR DCA-418-3 -2 SW3 12" Pipe to Pipe N/A (Bimetallic)
RHR DCA-418-3 -2 SW3 LD Pipe Seam N/A RHR DCA-418-3 -3 FW2 LU Pipe Seam A
RHR DCA-418-3 -3 FW3 LD Pipe Seam A
RHR DCA-418-3 -4 FWS LU Pipe Seam N/A RHR DCA-418-3 -4 FW6 LD Pipe Seam N/A RHR DCA-418-3 -5 FW1 LU Pipe Seam A
RHR DCA-418-3 -5 FW2 LD Pipe Seam A
RHR DCA-438-4 FW1 12" Pipe to Safe End A
(GE) (AZ. 315 DEG.).
RHR DCA-418-4 FW2 12" Pipe to Pipe A
RHR DCA-418-4 FW3 12" Elbow to Pipe A
RHR DCA-418-4 FW4 12" Valve 2F065C A
to Elbow RHR DCA-418-4 FW5 12" Pipe to Valve N/A 2F065C RER DCA-418-4 FW6 12" Elbow to Pipe N/A RHR DCA-418-4 N1'70 Safe End to Nozzle B
(GE) (AZ. 315 DEG)
RHR DCA-418-4 -1 FW3 LU Elbow Seam Minimum A
).
e q.
- Page No. 12 05/05/89 LIMERICK UNIT 2 WELDS SYSTEM ISO WELD NO DESCRIPTION ICSCC CATEGORY CS DCA-419-1 FW7 12" Elbow to Pipe N/A CS DCA-419-1 NSA Safe End to Nozzle B
c (GE) (AZ.60 DEG.)
CS DCA-419-1 -1 FW7 LU Elbow Seam Minimum N/A CS DCA-419-1 -1 FW7 LU Elbow Seam Maximum N/A CS DCA-419-1 -1 SW1 12" Pipe to Elbow N/A (Bimetallic Weld)
CS DCA-419-1 -1 SW1 LD Elbow Seam Minimum N/A CS DCA-419-1 -1 SW1 LD Elbow Seam Maximum N/A CS' DCA-419-1 -2 FW3 LU Pipe Seam N/A CS DCA-439-1 -2 FW4 LD Pipe Seam N/A CS DCA-419-1 -2 SW1 12" Elbow to Pipe N/A CS DCA-419-1 -2 SW1 LD Pipe Seam N/A CS DCA-419-1 -2 SW1 LU Elbow Seam Minimum N/A CS DCA-419-1 -2 SW1 LU Elbow Seam Maximum N/A CS DCA-419-1 -2 SW2 12" Pipe to Elbow N/A CS DCA-419-1 -2 SW2 LD Elbow Seam Minimum N/A CS DCA-419-1 -2 SW2 LD Elbow Seam Maximum N/A CS DCA-419-1 -2 SW2 LU Pipe Seam N/A CS DCA-419-1 -2 SW5 12" Pipe to Pipe N/A I
CS DCA-419-1 -2 SW5 LD Pipe Seam N/A CS DCA-419-1 -2 SW5 LU Pipe Seam N/A CS DCA-419-1 -3 FW2 LU Pipe Seam N/A CS DCA-419-1 -3 FW3 LD Elbow Seam Minimum N/A CS DCA-419-1 -3 FW3 ID Elbow Seam Maximum N/A CS DCA-419-1 -3 SW1 12" Pipe to 12" x 10" A
ECC. Reducer
= _ - - _ _ _ _ _ - - _ - _ -
4 e
9...
e-
- Page No. 13-05/05/B9 l
LIMERICK UNIT 2 l
WEIDS SYSTEM ISO WEID NO DESCRIPTION 3GSCC CATEGORY g
CS DCA-419-1 -3 SW1 LD Reducer Seam A
CS DCA-419-1 -3 SW1 LU Elbow Seam Minimum A
CS DCA-419-1 -3 SW1 LU Elbow Seam Maximum A
CS DCA-419-1 -3 SW2 12" x 10" Eccentric A
Re:3 to Pipe CS DCA-419-1 -3 SW2 ID Pipe Seam A
C3 DCA-419-1 -3 SW2 LU Reducer Seam A
CS' DCA-419-1 -4 FW1 LU Pipe Seam A
CS DCA-419-1 -4 FW2 LD Pipe Scam A
CS DCA-419-1 -5 FW4 LU Pipe Seam N/A CS DCA-419-1 -5 FW6 LD Pipe Seam N/A CS DCA-419-1 -6 FW5 LU Pipe Seam N/A CS DCA-419-1 -6 FW7 ID Pipe Seam N/A CS DCA-420-1 FW1 10" Pipe to Safe End A
(GE) (AZ. 300 DEG.)
CS DCA-420-1 FW10 10" Pipe to Pipe A
CS DCA-420-1 FW11 10" Pipe to Pipe A
CS DCA-420-1 FW3 12" Pipe to Elbow N/A CS DCA-420-1 FW4 12" Pipe to Pipe N/A CS DCA-420-1 FW5 12" Valve 2F007A to N/A Pipe CS DCA-420-1 FW6 12" Pipe to Valve N/A 2F007A CS DCA-420-1 FW7 32" Elbow to Pipe N/A CS DCA-420-1 NSB 10" Safe End to Nozzle B
(GE) (AZ. 300 DEG.)
CS DCA-420-1 -1 FW7 LU Elbow Scam Minimum N/A CS DCA-420-1 -1 FW7 LU Elbow Seam Maximum N/A
p,
3'
!. ~..
- Pige No. 18 l
.05/05/89 IIMERICK UNIT 2 WELDS E
VRR-2RD-2A N2G Safe End to Nozzlo B
(GE) (AZ. 240)
RR VRR-2RD-2A N2H Safe End to Nozzle B
(GE) (AZ. 270)
RR VRR-2RD-2A N2J Safe End to Nozzle B
(GE) (AZ. 300)
RR VRR-2RD-2A N2K Safe End to Nozzle B
(GE) (AZ. 330)
RR VRR-2RD-2A WA10 22" x 12" Sweepolet to A
12" Pipe RR VRR-2RD-2A WA31 22" x 12" Sweepolet to A
12" Pipe RR VRR-2RD-2A WA12 28" x 32" Reducer to A
32" Pipe RR VRR-2RD-2A WA13 28" x 12" Sweepolet to A
32" Pipe RR VRR-2RD-2A WA14 28" x 12" Sweepolet to A
32" Pipe RR VRR-2RD-2A WA15 Pipe to Safe End A
(GE) (AZ. 210)
P,R VRR-2RD-2A WA16 Pipe to Safe End A
(GE) (AZ. 240)
RR VRR-2RD-2A WA17 Pipe to Safe Fed A
(GE) (AZ. 270)
RR VRR-2RD-2A WA18 Pipe to Safe End A
(GE) (AZ. 300)
RR VRR-2RD-2A WA19 Pipe to Safe End A
(GE) (AZ. 330)
RR VRR-2RD-2A WA44 28" x 22" Cross to 22" A
Pipe RR VRR-2RD-2A WA6 Rocire. Pump 2AP-201 A
to 28" Pipe
a F
j e-
- Page No. 22 05/05/09 LIMERICK UNIT 2 i
l WEIDS l
SYSTEM ISO WELD NO DESCRIPTION ICSCC CATEGORY RR VRR-2RD-2A-20 WA6 LD Pipe Seam A
RR VRR-2RD-2A-20 WA7 LU Pipe beam A
RR VRR-2RD-2A-21 WAllLD Pipe Seam A
RR VRR-2RD-2A-21 WA68LU Pipe Seam A-RR VRR-2RD-2B N2A Safe End to Nozzle B
(GE) (AZ. 30)
RR VRk-2RD-2B N2B Safe End to Nozzle B
(GE) (AZ. 60)
RR VRR-2RD-2B N2C Safe End to Nozzle B
(GE) (AZ. 90)
RR VRR-2RD-2B N2D Safe End to Nozzle B
(GE) (AZ. 120)
RR VRR-2RD-2B N2E Safe End to Nozzle B
(GE) (AZ. 150)
RR VRR-2RD-2B WB10 22" x 12" Sweepolet A
to 12" Pipe RR VRR-2RD-2B WB11 22" x 12" Sweepolet A
to 12" Pipe RR VRR-2RD-2B WB12 28" x 12" Concentric A
Reducer to 12" Pipe RR VRR-2RD-2B WB13 22" x 12" Sweepolet A
to 12" Pipe RR VRR-2RD-2B WB14 22" x 12" Sweepolet A
to 12" Pipe RR VRR-2RD-2B WB15 Pipe to Safe End A
(GE) (AZ. 30)
RR VRR-2RD-2B WB16 Pipe to Safe End A
(GE) (AZ 60)
RR VRR-2RD-2B NB17 Pipe to Safe End A
(GE) (AZ. 90)
RR VRR-2RD-2B WB18 Pipe to Safe End A
(GE) (AZ.120)
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- P[ge No. 26
-05/05/89 LIMERICK UNIT 2 WELDS SYSTEM ISO WELD NO DESCRIPTION 3GSCC CATEGORY RR VRR-2RD-2B-21 SWA 28" x 22" Cross to A
22" Pipe RR VRR-2RD-2B-21 SWA LD 22" Pipe Seam A
RR VRR-2RD-2B-21 SWB 28" x 22" Cross to A
28" x 12" Concentric Reducer RR VER-2RD-2B-21 SWC 22" Pipe to Cap A
RR VRR-2RD-2B-21 SWC LU 22" Pipe Seam A
RR VRR-2RD-2B-21 SWD 22" Pipe to 22" x 12" A
Sweepolet RR VRR-2RD-2B-21 SWE 22" Pipe to 22" x 12" A
Swcepolet RR VRR-2RS-2A NIA Hozzle to Safe End A
(GE) (AZ. ODEG.)
RR VRR-2RS-2A WA1 Safe End to Pipe A
(GE) (AZ. ODEG.)
RR VRR-2RS-2A WA2 28" Pipe to Pipe A
RR VRR-2RS-2A WA3 2B" Elbow to Valve A
HV-2F023A RR VER-2RS-2A WA4 26" Valve HV-2F023A A
to Pipe ER VRR-2RS-2A WA43 28" Pipe to Pipe A
RR VRR-2RS-2A WAS 28" Elbow to Recirc A
Pump 2AP-201 RR VRR-2RS-2A-4 SWA 2B" Elbow to Pipe A
RR VRR-2RS-2A-4 SWA LD Pipe Seam A
RR VRR-2RS-2A-4 SWA LU Elbow Soam Minimum A
RR VRR-2RS-2A-4 SWA LU Elbow Seam Maximum A
RR VRR-2RS-2A-4 SWB 28" Pipe to Elbow A
RR VRR-2RS-2A-4 CWB LD Elbow Seam Minimum A
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- Pdge No. 27 i
05/05/89 j
LIMERICK UNIT 2 l'
WELDS SYSTEM 1SO WEID NO DESCR1pT10N IGSCC CATFLORY RR VRR-2RS-2A-4 SWB LD Elbow Seam Maximum A
RR VRR-2RS-2A-4 SWB LU Pipe Seam A
RR VRR-2RS-2A-4 WA1 LD Pipe Seam A
RR VRR-2RS-2A-4 WA2 LU Pipe Seam A
RR VRR-2RS-2A-5 WA2 LD Pipe Seam A
l RR VRR-2RS-2A-5 WA43LU Pipe Seam A
RR VRR-2RS-2A-6 SWA 28" Pipe to Elbow A
RR VRR-2RS-2A-6 SWA ID Elbow Seam Minimum A
RR VRR-2RS-2A-6 SWA LD Elbow Seam Maximum A
RR VRR-2RS-2A-6 SWA LU Pipe Seam A
RR VRR-2RS-2A-6 WA3 LU Elbow Seam Minimum A
RR VRR-2RS-2A-6 WA3 LU Flbow Seam Maximum A
RR VRR-2RS-2A-6 WA43LD Pipe Seam A
RR VRR-2RS-2A-7 SWA 28" Pipe to Elbow A
RR VRR-2RS-2A-7 SWA LD Elbow Seam Minimum A
RR VRR-2RS--2A-7 SWA ID Elbow Seam Maximum A
RR VRR-2RS-2A-7 SWA LU Pipe Seam A
RR VRR-2RS-2A-7 WA4 LD Pipe Seam A
RR VRR-2RS-2A-7 WA5 LU Elbow Seam Minimum A
RR VRR-2RS-2A-7 WAS LU Flbow Seam Maximum A
RR VRR-2RS-2B N3B Nozzle to Safe End A
(GE) (AZ. 180DEG.)
RR VRR-2RS-2B WB1 Safe End to Pipe A
(GE) (AZ. 180DEG.)
RR VRR-2RS-2B WB2 28" Pipe to A
28" x 28" x 20" Tee RR VRR-2RS-2B WB3 28" Elbow to Valve A
HV-2F023B
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PLE,Je No. 49 l
05/05/89 LIMERICK UNIT 2 WEIDS SYSTEM ISO WEID NO DESCRIPTION IGSCC CATECORY RR VRR-2RS-2B-7 SWA LD Elbow Seam Minimum A
RR VRR-2RS-2B-7 SWA LD Elbow Seam Maximum A
RR VRR-2RS-2B-7 SWA LU 28" Pipe Seam A
RR VRR-2RS-2B ~7 WB4 ID 28" Pipe Seam A
KR VER-2RS-2B-7 WBS LU Elbow Seam Minimum A
RR VRR-2RS-2B-7 WB5 LU Elbow Seam Maximum A
Not e: The two jet pump safe-end to coal extension welds and the two seal extension to seal welds (4 total) are excluded from this detailed list; however, they are classified as 1GSCC Category A.
The nozzle to safe-end welds are excluded from the detailed list for NB, N9, NIO, N11, N12, and N16; however, the classifications are included in Table 4.
CGS 0504.1
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