ML20246B063
| ML20246B063 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/30/1989 |
| From: | Michael Ray TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-01, GL-88-1, TAC-61094, NUDOCS 8907070189 | |
| Download: ML20246B063 (16) | |
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TENNESSEE VALLEY AUTHORITY
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CH ATTANOOGA. TENNESSEE 37401 SN 1578 Lookout Place
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JUN 301989 1
l U.S. Nuclear Regulatory Commission
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ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
l In the Matter of
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Docket Nos. 50-259 Tennessee Valley Authority
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50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - SUPPLEMENTAL RESPONSE TO GENERIC LETTER (GL) 88-01 (TAC 61094)
Reference:
TVA letter to NRC dated January 12, 1989, " Response to Request for Additional Information on the Intergranular Stress Corrosion Cracking (IGSCC) Program,"
The purpose of this letter is to provide the results of the' weld examinations on the remaining post-Induction Heating Stress Improvement (IHSI) welds, and to provide supplementary information on the IGSCC program for BFN unit 2.
1 Enclosure I contains a supplemental response to GL 88-01 that includes a list l
l of the eight post-IHSI welds of which eight were found to have IGSCC indications. It was determined that five of the eight welds had IGSCC indications sufficient to require repair.
The analysis of the remaining three welds indicated that they were acceptable for continued operation.
The I-calculations for these welds are available for NRC review at TVA offices in Rockville. Enclosure 2 contains a list of welds with their inspection schedule and a brief summary of~IGSCC mitigation used.
1 This letter along with the above referenced submittal have completed the actions requested by NRC in its Safety Evaluation (SE) on GL88-01 for unit 2.
TVA requests the issuance of a SE documenting the resolution of this issue for restart.
If you have any questions on this matter, please call Patrick P. Carier, BFN, (205) 729-3570.
I Very truly yours, l
TENNESSEE VALLEY AUTHORITY i
8907070189 890630
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PDR ADOCK 05000259 8
P PNU l
Manager /, Nuclear L censing l
and Regulatory Affairs
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Enclosures cc:
See page 2 g30 I
i An Equal opportunity Employer
i hhh$Qjggg-U.S. Nuclear Regulatory Commission cc (Enclosures):
Ms. S. C. Black, Assistant Director i
for Projects l
TVA Projects Division i
U.S. Nuclear Regulatory Commission l
One White Flint, North i
11555 Rockville Pike i
Rockville, Maryland 20852 Nr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division i
U.F. Nuclear Regulatory Commission Reoi.on II-101 Harietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 i
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4 SUPPLEMENTAL RESPONSE TO GENERIC LETTER C -01 REPORT OF INSPECTION, REPAIR AND MITIGATION PLANS FOR -
BROWNS FERRY UNITS 1, 2, AND 3, IGSCC-SUSCEPTIBLE PIPING l
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t INTRODUCTION Generic Letter 88-01 (GL 88-01) "NRC Position on IGSCC In BWR Austenitic Stainless Steel Piping" was issued on January 25, 1.988 to distribute and
'j release NUREG 0313,R.2 " Technical Report On Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping." GL 88-01 requested a response to the following five specific items:
1.
Plans regarding log-term mitigation of IGSCC.
2.
Inservice Inspection Program plans.
3.
Demonstration of conformance to the ISI requirements of GL 88-01.
4.
Technical Specification (TS) conformance to staff positions on leak detection.
5.
Plans to notify the NRC of flaws.
In response to the GL 88-01 request, TVA submitted a response to the NRC on August 1,1988 which addressed these 5 items. On December 8, 1988 NRC provided TVA a Unit-2 Safety Evaluation (SE) based on the above referenced response. These included a request to address additional concerns prior to unit-2 restart. The concerns were as follows:
1.
That TVA provide confirmation that the weld sample expansion requirements comply with the " Staff Position" on sample expansion established in GL B8-01.
2.
That TVA address post-IHSI inspection of the remaining uninspected Unit-2 welds prior to Unit-2 restart.
3.
That TVA provida TS changes to reflect leak detection requirements i
specified in GL 88-01.
On January 12, 1989 TVA submitted a response to NRC which addressed items 1 and 3.
The TS for leak detection requirements of GL 88-01 were approved and issued by NRC on May 19, 1989.
The post-IHSI inspections required in item 2 were completed in March 1989 and are included in this supplement.
Since the August 1, 1988 submittal there have been changes in the scope and category of IGSCC susceptible weldments as defined in TVA's previous GL 88-01 response.
This enclosure also includes informaticia on these changes.
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. UNIT-2-POST-IHSI INSPECTION:
- In March, 1989'the post-IhSI examination of 66 unit-2 welds was completed.
The previous-88-01' response had listed 71 welds as requiring post-IHSI.
Linspection..A review of plant-inspection records indicated that 8 of the 71
- Welds-had received a documented post-IHSI-IGSCC inspection and should have-been classified'as category,"C".
This review also indicated that 3 welds.
classified as category "C" should'have been classified category "G".
These~3,
. welds'had.. received a code examination instead'of.a. post-IHSI IGSCC.
. Inspection. These changes in. numbers provided a total of 66 welds which required post-IHSI inspection. As follows:
F 71 welds in previous response
- 8 welds misclassified as "G"
+ 3 welds' reclassified as "G" i'
66 welds post-IHSI inspected The results of the post-IHSI inspection of the 66 welds revealed 8 welds with IGSCC indications. A summary of the welds with indications is as follows:
. Number Of Max Weld ID System Indications Depth GR-2-59 Recir 6 Circumferential 40%
GR-2-61 Recir'-
-16.Circumferenttal 40%
GR-2-53 Recir 1 Circumferential 16%
GR-2-45~
Recir 3 Axlal DRHR-2-22 RHR I Circumferential 18%
DRHR-2-9 RHR 1 Circumferential 16%
DSRWC-2-4' RWCU 3 Axial DSRWC-2-3 RWCU 4 Axial Note:
- There is no industry accepted method for sizing axial indications.
Structural analysis was performed on all 8 welds per the guidance provided in GL'88-01 c.td NUREG 0313,R.2.
This analysis indicated that indications in
' welds GR-2-53, DRHR-2-22, and DRHR-2-9 are accepteble for continued operation M
until the next scheduled exam period required per GL 88-01..
The three welds.
have received IHSI and crack' growth is estimated to be minimal.
The five remaining welds were determined to require repair.
Welds GR-2-59 and GR-2-61 are being repaired by the application of " full structural" weld overlays as provided under Design Change Notice (DCN) H 4972.
Welds GR-2-45, DSRWC-2-4, and DSRWC-2-3 are being repaired by the application of " design" weld overlays as provided under DCN H 5077.
The design of all 5 weld overlays was accompitsbed using the guidance provided in-NUREG 0313,R.2.
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REACTOR. WATER CLEANUP (RWCU) PIPING OUTSIDE THE DRY WELL As a result of an on-site NRC inspection conducted during January 30 -
February 2,1989, an unresolved item was issued concerning the scope of weldments included in TVA's August 1, 1989 GL 88-01 response.
This item centered around the interpretation of the requirements in GL 88-01, which was:
"The Generic Letter applies to all BWR piping made of austenitic stainless steel that is four inches or larger in nominal diameter and contains reactor coolant at a temperature above 200*F during power operation regardless of Code classification."
Specifically, weldments in RWCU Piping outside the drywell were not included in the GL 88-01 response because the piping is classified as "noncode class".
TVA interpreted the phrase "regardless of Code classification" as meaning the i
piping had to have a code classification to be included within the scope of GL 88-01. Subsequent discussions with NRC established that this piping was to be included within the scope. As a result of these events, TVA presented a plan to NRC which provided for replacement of the RWCU piping during the unit-2 cycle 6 outage, and replacement of RWCU the subject piping on units 1 and 3 prior to their restart.
This plan was verbally accepted by NRC and was also documented in a TVA response to the NRC dated May 22, 1989. As a result of these actions, approximately 77 RWCU welds have been added to the scope for unit-2.
DISPOSITION OF BIMETALLIC WELDS In the previous GL 88-01 response, plans to stress improve 6 unit-2 Core Spray carbon steel to stainless steel weldments were discussed.
These welds involve l
carbon steel pipe welded with 309 weld metal to cast stainless steel valve bodies. There are also 3 RHR weldments in the same configuration which are welded with 308/309 weld metal which were not included in the previous GL 88-01 response. The following is a listing of the subject unit-2 welds.
Core Spray System Welds RHR System Welds TCS-2-426 DRHR-2-11 TCS-2-421 DRHR-2-2 TCS-2-406 TRHR-2-191 TCS-2-422 TCS-2-410 1C5-2-405 It is TVA's position that these 9 weldments be classified as (GL 88-01) category "A" weldments and are listed as such in the unit-2 summary table.
Because of this classification there will be no stress improvement applied.
For units 1 and 3, a similar classification will be applied to the subject welds. Justification for the "A" classificatW is based on (1) NUREG
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i 0313,R.2 interpretations, (2) me';allurgical ce- :derations and (3) field l
experience as follows:
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- NUREG 0313,R.2 Interpretations -
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i Paragraph 2.1, page 2.2 of the NUREG, states that carbon steels are considered j
l immune to the problem of sensitization and resultant IGSCC.
Paragraph 2.1.1, l
page 2.3 States that weld joints between resistant piping and cast valve or pump bodies are special cases and are covered in the Staff Position on Inspection Schedules. Although paragraph S.1 of the NUREG does not apply to P-1 carbon steel, paragraph 5.3.1.1, page 5.3, defines welds joining cast pump and valve bodies to resistant piping as Category "A" weldments.
Thus the NUREG implies that the weld heat affected zone (HAZ) of cast valve bodies and of adjacent resistant piping is not a basis for excluding the subject welds from Category "A".
Furthermore, the classification as Category "A" appears to be exclusive of the type of austenttic weld filler used between the cast valve and the resistant piping.
- Metallurgical Considerations and Field Conditions -
These weldments are welded with 309 and 308 weld metal which is a stainless steel material with a high resistance to IGSCC. Although the pickup of carbon in the weld metal adjacent to the carbon steel is generally undesirable with respect to IGSCC resistance, industry experience indicates that the dilution zone in the weld metal tends to become more like a low alloy steel.
In general, a ferritic low alloy steels (which the dilution zone tends toward) are considered relatively resistant to IGSCC.
Additionally BWR field experience with dissimilar metals in this application appears to be quite good.
To date the performance of 308 and 309 weld buttering on carbon steel reactor vessel nozzles indicates that these weldments have been immune to IGSCC, as compared to other materials used such as Inconel 182 which has exhibited cracking problems.
INSTALLATION OF LEAK DETECTION ON PENETRATION PIPING WELDS In the August 1988, submittal TVA stated that inaccessible piping welds in the RHR and RWCU systems will either be removed, have corosion resistant clad applied, or have local leak detection applied.
For unit-2 this was to be performed during the cycle 6 outage and for units 1 and 3 was to be applied prior to restart.
The subject inaccessible welds are located inside containment piping penetrations and are listed as follows.
Reactor Water Cleanup Welds RHR System i
DRWC-?
DRHR-2-38 DRHR-2-138 DRHR-2-12 DRHR-2-3
4 During unit-2 cycle 6 TVA is committed to implement one of the 3 listed i
options for the RNCU penetration weld because this weld is within the regime for IGSCC as defined in GL 88-01 (contains reactor coolant at a temperature above 200*F during power operation).
For the RHR penetration welds, an engineering calculation has been performed which shows that the welds do not experience a temperature greater than 200*F during power operation.
The calculation indicates that the RHR welds experience temperatures higher than 200*F for only a brief period (1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) during unit shutdown cooling.
This condition therefore does not support the need for implementation of these requirements.
The unit-2 accessible welds directly adjacent to these penetration welds have been and will be continued to be inspected as part of the GL 88-01 inspection plan.
To date inspection of these welds has not revealed any indications.
The unit-2 summary list wlli continue to list the RHR penetration welds as category "G," however no additional leak detection requirements beyond those required by Technical Specifications will be implem.ented for these welds. A similar approach will be applied to the RHR penetration welds for units 1 and 3.
UNIT-2 WELDMENT
SUMMARY
BASED ON THE PREVIOUSLY STATED CHANGES NUREG INSPECTION PIPING WELDS NUMBER CATEGORY Resistant welds 47 A
Welds with SI after 2 years operation 116 C
Cracked welds with SI or weld overlay 14 E
Uninspected nonresistant welds 82*
G TOTAL 259
- NOTE: This number includes an estimated 77 RWCU welds which are scheduled for replacement during the unit-2 cycle outage, 4 inaccessible RHR welds, and 1 inaccessible RWCU weld.
RECIRCULATION INLET SAFE ENDS Resistant Components 10 A
JET PUMP INSTRUMENTATION SAFE ENDS Resistant Components 2
A The following is a detailed explanation of the differences in the number of welds listed in the previous submittal and this supplemental response for unit-2, August 1,1989 Nuober In This Category GL 88-01 Submittal Supplement Response A
38 47 B
0 0
C 54 116 0
6 0
E 6
14 F
0 0
Explanation of changes for category "A" welds 38 welds in August,1988 Submittal
+3 carbon to SS welds added from the RHR system
+6 carbon to SS welds changed from category "D" to "A" in CS system 47 Total category "A" welds Explanation of changes for category "C" welds 54 welds in August, 1988 submittal
- I weld was found not to exist in RWCU system
- 3 welds mistakenly classified as
C" reclassified to "G"
+ 8 welds mistakenly classified as "G" welds reclassified to "C"-
+58 welds reclassified as "C" as a result of post-IHSI inspection 116 Total category "C" welds Explanation of changes for category "E" welds 6 welds in August, 1988 submittal
+ 8 welds with indications that are stress improved or weld overlayed 14 Total category "E" welds Explanation of changes for category "G" welds 76 welds in August, 1988 submittal
+77 welds in RWCU system added as category "G"
+ 3 welds mistakenly classified as "C" reclassified to "G"
- 8 welds mistakenly classified as "G" reclassified to "C"
-66 welds which received post-IHSI insgection 82 Total category "G" welds FUTURE INSPECTION PLAN As previously committed in the August 1, 1988 response, a;' welds will be inspected on each unit based on their respective category per the guidance provided in NUREG 0313,R.2.
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Notes to Table 1 1.
ISI dates may not be exact for each weld, but instead may reflect the ending date of_the latest ISI effort in which the weld was inspected.
2.
The 'atal number of welds listed in Table i does not include approximately 77,teactor water. cleanup welds, which are classified as category "G".
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IGSCC INSPECTION AND MITIGATION l
SUMMARY
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-- UNIT-2'WELDMENTS -
IGSCC.INDPECT1CN AND MITGATION
SUMMARY
DATE.0F WELD ID PIPE PIPING IGSCC POST IHS1 NUl!EG NUMBER' S1ZE. SYSTEM'CONFIG MITIGATION-EXAMINATION CATEGORY
'3 DCS-2-4 12 CS P-P IHS1 12/22/88
-C
-2 DCS-2 12 CS P-E.
IHSI 01/31/85
.C
- 3. DCS 13 A 12.
CS' P-P-IHSI.
06/09/86 C.
4 DCS-2-5.
12 CS P-V-1HSI-01/31/85 C
t 1b TCS-2-426 12-C3 EV NONE
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A 6 ; TCS-2-4 21 12 CS
.R-V
-NONE
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A-7 DSCS-2-9 3P CS.
P-E IHS1 02/15/89 C
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-8 TCUa2-406~
12 CS V-P NONE
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" A' 9 DCS-2-13 32 CS P-P IHSI' 01/31/85 C-10 TCS 2-422 12 CS V-P.
'NONE
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A 31 TCS-2-410 12 CS' E-V NONE-
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A 12.TCS-2-405' 12 CS' H-V NONE
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A 3J3 DCS-2-14 12-CS P-V IHSI 02/15/09 C
14 TCS-2-403-12 CS-SE P IHS1 09/18/86 C
15 TCS-2-40L 22 CS SE-N 1HS1 08/20/87 C
36,DSCS-2-2 12 CD P-E' IHSI 02/15/89
'C'
'37_DSCS-2-1.
12 CS.
E-P IHSI' 12/22/88 C
'18 TCS-2-417
i.39 TSCS-2-418
20"JPr2-1A JPI REPLACED 316NG 05/16/85 A
1!1 JP-2 1B JPI-REPLACED 316NG 05/15/85 A
l 22 XR-2-4D 6X28 RECIR P-FLN 'IHSI 02/01/89 C
?23 KR-2-53' 6:
RECIR P-FLN JHS1 01/30/89 C
' 24 GR 63B:
SK2a RECTR WOL P-IHSI 02/01/89 C
25 GR-2-63A'
-5' RECIR WOL-C IHUI 02/01/89 C
26 KR-2-23'
'4820 RECIR. P-WOL IHSI:
09/02/87
.C
- 27 GR-2 4K28 RECIR WOl. - C 'IHSI 09/18/87 C
' 28. GR-2 -7
'4K2B RECIR WOL-C IHSI=
09/18/87 C
1!9 KR-2-26 4k26 HECIR P-WOL IHSI-09/02/87 C
30'KR-2-4 4K28 RECIR WOL.P IHSI 09/02/87 C
31 KR-2-1 4K20 HEC 1R WOL-P IHSI 09/02/87 C
' 32 GR 33 4
'RECIH WOL-U 1HSI 09/17/87 C
33 GR-2-30 4
RECIR WOL-C 1HUI 09/17/87 C
34'GR 2 59-20 REC 1R SE-P IHSI + OVERLAY 02/07/89 E
R 35.KH-2-46 28-RECJR T-P IHSI 02/11/89 C
'35LNIA-2 28 REClR-N-HE 3HS1 08/14/87 C
37 GH->!-50 20 RECIR P-T IHS]
02/11/89 C
-30 KR-2 48 2D RECIR P-E IHSI 01/23/89 C
/39 N1B-2 2D REclR N-SE 1118 1-08/17/87 C
40 KR-2-50 2D JRECIR P-E 1HH1 02/20/89 C
41 KR-2-52 20 REC 1R P-8 IHSI 02/20/89 C
L42 GR-2-64 28 RECIR E-PMP IHSI 03/12/8S C
43 GR 2-63 2B REC 1R V-P IHSI 01/29/89 C
44 GR-2-62.
2(4 RECIR E-V IHS1 03/12/85 C
L 45.GR-2-28 20
. REC]R P-V IllSI 01/30/89 C
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TAELE 1 l
UNIT-2 WELDMENTS 1GSCC INDPECTICN AND MITGATION
SUMMARY
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l DATE OF WELD'1D-FDFE 1 h PING IGSCC-POST IHSI NUHEG NtJMBER SIZE SYSTEM CONFIG MITIGATION EXAMINATION CATEGORY 46 GR-2 27 2;3 RECIR PMP-P IHSI' 01/29/89 C
47 KR-2-24 23 RECIR-E-P IHS1 01/28/09 C
4U KR 2 51 2B RECIR P-E INDI 02/21/89 C
-49.GR-2-29 20 RECIR V-E IHHI 01/25/89 C
SU GH-2 34
'2B RECIR T-X INSI 12/18/86 C
~51;GR-%-61 2b RECIR P-P IHS1 + OVERLAY 02/17/89 E
$2 KR-2-25 2b RECIR P-T Ills) 02/16/89 C
.S3 KR-2-3
'2 3 RECIR P-T IHSI 02/1.1/89 C
54 GR-2-57 2 3 RECIR V-P IDSI 01/16/89 C
55 KH--2-2 2D RECIR
'E-P IHSI 03/12/85 C
JS6 GR-2-60 2h RECIR E-P
'1HSI 03/26/85 C
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'!V/ GR 2-66.
2p RECIR E-V IHSI 01/30/89 C
58 GR-2-2 2B RECIR P-V IHSI 02/15/89 C
59 KR-2-47 2D RECIR P-E 1HUJ
-01/26/89 C
{
60 GR-2 58.
. 2l3 RECIR E-FMP' IHSI 01/25/89 C
61.GR 2 3 23 RECIR-V-E IHSI 01/28/89 C
62 GR 2 2B RECIR PMP-P IHSI 02/26/85 C
63 GR-2-8
'2p RECIR T-X JH3) 10/25/86 C-64 GR-2-54 2 3 RECIR E-P IHSI 02/08/89-C 65 KR-2-45 23 RECIR P-E JHS) 02/15/85 C
66'G~-2-53
.2 3 RECIR SE-P IHSI 02/13/89 E
67 Kn-2-14
~2 2 RECIR P-SOL 1HSI 02/27/85-E 68 GR-2 18 20 RECIR X-P IHSI 03/06/05 C
tio KR-2"20 2p RECIR P-SOL INSI 10/27/86 C
o 70 KR-2-15.
20 RECIR P-C IHDI 02/27/85 C
71 KR-2 -35' 2p RECIR-P-SOL IHSI
_04/08/85 C
43 KR 2437 2p RECIR P-C INSI 04/02/85 E
73 KR-2 36 2'2 RECIR P-SOL INDI 04/08/85 E
74 ER-2-44 2 2 RECIR X-P IHSI 02/11/89 C
75 KR 34 2p RECIR X-P IHSI 03/06/85 C
76 KR-2 33 20 REClR X-R IHOI 10/23/86 C
4 77 GR-2-51 22 RECIR P-V IHSI 02/28/85 C
i 78 KR-2-41 2 2 RECIR P-SOL IHSI 02/27/85 E
79 KR-2-42 2 2 RECIR P-SOL IHS) 10/20/86 C
00c GR-2 -25 2 2 REC 1H P-V INSI 10/25/86 C
'81 GR-2 52 2D RECIP V-P IHSI 02/10/89 C
- 02 GR-2-26 20 RECIR V-P INSI 02/10/89 C
83 KR-2-19 2p RECIR P-SO1.
IHSI 10/20/86 C
04 KR 12 2p RECIR X -P IHSI 10/26/86 C
85 KR-2-I3 22 RECIR P-DOL IHSI 10/24/86 C
06 KR-2-13 2 2 RECIH X-R IHSI 10/22/86 C
87 2RC5 12 RECIR P-E REPLACED t IHSI 07/30/87 A
1
- 88 2RD6 It RECIR P-SE ltEPLACED + IHSI 08/24/87 A
l 89'2RD5'
'1 2 RECIR P-E REPLACED + IHSI 07/31/87 A
90 GR-2 45' f2 RECIR SOL-P 11WI+0VERLAY 02/24/89 E
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TABLE 1 UNIT-2 WELDMENTS -
IGCCC INCPECTION AND MITGATION
SUMMARY
DATE OF WELD ID P2PE PIPING IGSCC POST IHSI NUl!EG NUMBER S5ZE SYSTEM CONFIG MITIGATION EXAMINATION CA*.*EGORY i
93 2RE5 12 RECIR P-E REPLACED 4 IHS1 07/31/87 A
92 2RK5 12 RECIR P-3 REPLACED 4 IHSI 07/28/87 A
93 GR-2 41 12 RECIR R-P 1HSI 02/2b/89 C
94 GR-M-48 12 RECIR SOL-P 1113 1 02/26/89 C
l 95 2RE6 12 REC 1R P-SE REPLACED + IJISI 08/24/87 A
l 96 2RK6 12 RECIR P-GE REPLACED + IHSI 08/24/87 A
97 2RH6 12 REClR P-SE REPLACED + IHSI 08/23/87 A
98 2RHS 12 RECIR P-E REFLACED + IH91 07/29/87 A
99 GR-2-38 12 REC 1R SOL-P IHSI 02/25/89 C
200 2RC6 12 REClR P-SE REPLACED 4 IH91 08/24/87 A
101 2RB5 12 REClR P-E REPLACED + IH3I 07/30/87 A
102 GR-2 35 12 RECIR SOL-P IHul 02/26/89 C
103 2RA5 12 RECTR P-E REPLACED + IHSI 07/30/87 A
104 2RB6 12 RECIR P-SE REPLACED + IHSI 08/24/87 A
10D GR 2-22 12 RECIR SOL-P 1HUI 02/26/89 C
106 2RF5 12 RECIR P-E REPLACED + IHSI 07/29/87 A
107 2RA6 12 REC}R P-SE REPLACED + IHSI 08/24/87 A
100 GR 19 12 RECIR SQL -P IHS1 02/25/89 C
109 2RG5 1?
RECIR P-E REPLACED + IHSI 07/29/87 A
110 2RF6 12 RECIR SE-P REPLACED + IMSI 08/24/87 A
111 GR-2-12 12 RECIR SOL-P IHSI 02/26/85 C
122 2RA1 12 RECIR N-SE REPLACED + IHSI 08/25/87 A
133 2RB1 12 HECIR N-SE REPLACED + IHSI 08/18/87 A
114 2RC1 12 RECIR N-SE REPLACED + IMSI 08/23/87 A
135 2RD1 1?
REC 1R N SE REPLACED + IHSI 08/19/87 A
116 2RE1 12 RECIR N-SE REPLACED + IHSI 08/24/87 A
117 2RF3 12 RECIR N-SE REPLACED + IHSI 08/24/87 A
118 'RG1 12 RECIR N-SE REPLACED + IHSI 08/25/87 A
119 GR-2-09 12 HEC 1R SOL-P JHSI 02/26/85 C
120 2RJG 12 RECIR P-SE REPLACED + IHSI 08/23/87 A
123 2HJb 12 REC 1R P-E REPLACED + IHS! 07/29/87 A
122 2RH1 32 REC 1R N-SE REPLACED + IHSI 08/25/87 A
123 2RG6 12 RECIR P-DE REPLACED + lHS! 08/24/87 A
124 GR-2-15 12 REC]R R-P IMSI + OVERLAY
/
/
E 125 2RK1 12 RECIR N-SE REPLACED + IHSI 08/29/87 A
125 2RJ1 12 REClR N -SE REPLACED + IHSI 08/31/87 A
127 DRHR-2"3D 24 RHR P-P NONE
/
/
G 120 DRHR-2-13B 24 RHR P-P NONE
/
/
G 129 DRHR-2-12 24 RHR P-V NONE
/
/
U 130 DRHR-2-3 24 RHR P-V NONE
/
/
G 231 DSRHR-2-5A 24 RHR E-P IHSI 05/31/85 C
j 132 DSRHR-2-5 24 RHR E-P JHUJ 04/19/85 C
133 DSRHR-2-4A 2h RHR E-E IHSI 02/15/89 C
i 134 DRHR 9 2h RHR T-P IHS1 02/15/89 E
135 DSRHR-2-2 2h RHR E-P IHSI 02/15/89 C
l
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- P [dagolo.
. 14 O'
M --
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.t06/22/89l.
~
-TABLE ~1 j
H F'
- UNIT WELDMENTS - -
i
~
,IGCCC INSPECTICN AND MITGATION j
-UUMMARY m
j l
DATE OF WELD 14 P3PE PIPING-IGSCC POST IHSI NUREG NUMBEh '
SIZE DYSTEM CONFIG M1TIGATION EXAMINATION CW'EGORY.
y Y
(136 DRHR-2-14
'1137 DRHR-2-13 24
02/15/89 C
'138 DSRIIR-2-1
-24 RHH E-P IHSI 02/15/89?
C
!1391DSRHR-2-4' 24 RHR-E-P IHSI 03/27/85 C
'140.DRHR 2 24-
- RHR V-P
'IHS1 02/24/89 C
141JDRHR22-7
'24 Ri!R ^
V -P IHSI 02/15/89 C
242 DRHR-2-3 24L RHR E-V IHSI 02/16/89-C
? 143, DSRIIR 3 ;
24
- RIIH P-P IHSI 02/22/89 C
1144-DRHR-2-6 24 RHR-V~P IHSI 04/19/85 C
g
'4
'145' DRHR -17 24 RHR V-P -
IHDI 04/10/85 C
146-DRHR 2.24L RHR E-P IHSI 04/12/85 C'
- 147-L DRHR-2-18 :
?1491DHHR-2-16 24' RIIR V-P IHSI 02/01/89 C
%150:DSRHR-2 '//
24
151;DRHR-2-8 24 RHR-V-P.
1118 1 02/11/89 C
51b2_ DRilR 11.
/ ' :/.
A
' :153 DRHR-2-~2 24
.RHR P-V.
NONE
/
/
A 154 TRHR-2 -191 20 RHR V-P NONL'
'/
/'
A
-155 DSRHR-2-9 20 RHR~
E-P IHS1 04/12/85 C
156'DRHR-2-23
+20
'RHR V-E' 1113 1 02/15/89 C
2 107,DRHR 2n19' 20-RHH
'T-P-IHSI 02/16/89
.C "158 DSRHR,2r10' 20' RHR E-P 1RSI 02/20/89 C
'159 DSRHR-2 -8 20 RHR SOL-P IHCI 04/11/85
.C
. :160 DR!lH 2 22-20' RHR V-P IHSI 02/24/09 E
s h
161.DSRHR-2-]1' 20- : R'!R '
E-P JHSI.
02/22/89 C
'162 DRHR-2-23 20 EHR V-P IHSI 02/20/89 C
163 DSRW&-2 4-6 RWCU P-E IHSI + OVERLAY 02/25/89 E
164'.DSDWC-2-6.
6
.RWCU P-E 1HSI 4 OVERLAY 05/22/87 E
16b DSRWC-2-G 6
RWCU~
P-E IHSI 02/24/89 C
i3 306 DHWC-2 7B^
6 RWCU P-P HSW
/
/
A 167 DSRWC-2-2A 6'
RWCU P-3 1HS1 11/06/86 C
i
' ' 168 DRWC-2-4B-6 RWCU P -P HSW
/
/
A 169 DRWC 2-4A.
6 RWCU P4P HSW
/
/
A 3 701 DRWC-2-4X '
6 RWCU P-E HSW
/
/
A l
' 171 DRWC-2-5A
.6
.RWCU P-FH IMSI 03/29/85 C
{
, ' 172 DRWC-2--SD 6
RWCU V-P JHS1 11/09/86 C
' 173 DSHWC-2 3 6
RWCU P -E IHSI + OVERLAY 02/26/89 E
L 13 74 ' DSRWC 2 6-RWCU P -E 3HSI 01/25/85 C
L'1175 DSRWC-2-1;
.6-RWCU E -P IHSI 01/25/85 C
176.DRWC 2 3-6 RWCU P-V lHD1 11/06/86 C
7177 DRWC 2 6
RWCU V -3 1HS1 11/06/86 C
178 DRWC--2-1 6'
RWCU P--V - -
IMSI 01/25/85 C
i
- 179 DRWC-2-1 A 6
i L
160 -DRWC-2 -7A 6
RWCU P-P HIM
/
/
A
'Q l
l-.
-7 m=_
O n
- P~g6 No.
3 0.6/32/89 TADLE 1 UNIT-2 WEl.DMENTS -
IGSCC INDPECTION AND MITGATION
SUMMARY
DATE OF WELD ID P2PE F1FING IGSCC POST 1HSI NUitEG NUMBER G77: SYSTEM CONVJO MITIGATION EXAMINATION CATEGORY 282 DRWC-?
5 RWCU PP NONE
/
/
G i
182 DSRWC-2-7X-6 RWCU P-E HSW
/
/
A
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