ML20140F189
| ML20140F189 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/30/1997 |
| From: | Ewing E ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3F1-97-0069, W3F1-97-69, NUDOCS 9705020142 | |
| Download: ML20140F189 (13) | |
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- y Ent rgy Operitioni,Inc.
Killona. LA 70066 Tel 504 739 6242 r
C. Ewing, lil Nu ear Safety & Regulatory Affairs W3F1-97-0069 A4.05 PR April 30,1997 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Subjec.t:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Inservice Inspection (ISI) Relief Request 1S1-001, Revision 6 Limited Examination of Welds / Components Gentlemen:
Enclosed for your review in Attachment 1 is Revision 6 to ISI Relief Request 1S1-001. contains a listing of items (Table 1) that fall into one of two categories:
(1) items previously granted relief (e.g., items that have an SER approval date) and (2) items for which Waterford 3 currently seeks relief (e.g., items that do not have an SER j approval date). Also enclosed are Attachments 2 through 4 which are provided as aids to clarify the scope of examinations added and deleted.
I in accordance with the Code of Federal Regulations 10CFR50.55a(g), " Inservice p
inspection Requirements", licensees must perform Inservice Inspection of certain ASME Code Class 1,2, and 3 pressure-retaining components. The inspection requirements for Waterford 3 SES are contained in the ASME Boiler and Pressure Vessel Code,Section XI,1980 Edition with addenda through Winter 1981.Section XI stipulates the amount of examination required for each component.
Whenever complete coverage, as defined by Section XI, is not attainable due to
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component design or configuration, the limitations to the required examinations must j
be submitted to the NRC per 10CFR50.55a(g)(5)(iii). In compliance with these regulations, Waterford 3 submitted Relief Request ISl-001, Revision 0, as h
9705020142 970430 PDR ADOCK 05000382 l
I N,
ISI Relief Request 1S1-001, Revision 6 W3F1-97-0069 Page 2 April 30,1997 part of the original First Ten Year interval Inservice inspection Program at the beginning of this interval. The information contained in Rev. O of this Relief Request was based on the Preservice Examination conducted prior to commercial operation of the plant. As ISI examinations have been performed during the current Interval, the
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list of components receiving limited or partial examinations has been continually updated. Consequently, Waterford 3 has continued to revise Relief Request 1S1-001. to this letter is Revision 6 of Relief Request 1S1-001 and contains the most current list of Limited Examinations, " Table 1 Limited Examinations." This list has been developed by reviewing all examinations performed during this Interval and contains a listing of all items that did not receive essentially 100% examination coverage. Per Regulatory Guide 1.147, which endorses Code Case N-460, greater than 90% coverage is equivalent to essentially 100% coverage. The items for which Waterford 3 currently seeks relief are those which do not have an NRC SER Approval Date listed.
As an aid to understand the addition and deletion of examinations proposed in this revision of Relief Request ISI-001, we have included Attachments 2 through 4. lists components for which relief was previously granted by the NRC in Safety Evaluation Report (SER) dated November 8,1993, but which have been removed from Relief Request ISI-001, Revision 6, based on the following:
1.
Components which have received ISI examinations with greater than 90%
Code coverage are noted as " inspected @ 100%".
2.
Components which have not been selected for examination during this current Interval are noted as "not inspected".
3.
Components which are examined as part of an augmented program rather than Section XI are noted as " augmented". Per the SER, relief is not required for non-Section XI examinations. However, the NRC has been informed of the limited examination.
4.
Welds that are determined not to exist in the plant are noted as "no weld".
5.
Reactor Vessel shell welds have been removed from the list and have been noted as " revoked by 10CFR50.55a(g)(6)(ii)(A)" since these items have been i
identified in the Code of Federal Regulations and all previous relief has been revoked.
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l lSI Relief Request ISI-001, Revision 6 l
.Page 3 i
April 30,1997 1
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- Attachment 3 lists components that were denied relief by the NRC, as documented in l
the Safety Evaluation Report dated November 8,1993, and have been removed from Relief Request 1S1-001 Revision 6. Relief was denied due to inadequate information.
l Examinations were typically described as " partial". Components which have received ISI examinations with greater than 90% Code coverage are noted as " inspected @
100%". Components which were not selected for examination duririg the current Interval are noted as "not inspected". Components which have not been examined yet, but are scheduled for examination during RFO8, are noted as "not examined".
l lists components that were granted relief by the NRC, as documented in l
the Safety Evaluation Report dated November 8,1993, but did not receive the Code i
coverage that was estimated in Revision 5 of the Relief Request. The actual l
percentage of completion has been added in this Revision of the Relief Request and l-relief for these items is again being requested for the percent coverage listed.
Even with these changes, the number of examinations performed at Waterford 3 i
during the current Interval complies with or exceeds the minimum requirements of l
In summary, Waterford 3 requests relief for all items listed in Attachment 1, Taole 1, that do not have an NRC SER approval date. Attachments 2 through 4 are not a part of that relief request. Instead, they are provided to clarify the scope of examinations added or deleted.
i If there are any questions, please contact Kevin Hall at (504) 739-6423 or me at (504) 739-6242.
' Very truly yours,
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E. C. Ewing Director Nuclear Safety & Regulatory Affairs ECE/DMU/tjs j
Attachments i
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ISI Relief Request ISI-001, Revision 6 i
W3F1-97-0069 Page 4 April 30,1997
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E.W. Merschoff, NRC Region IV C.P. Patel, NRC-NRR A.L. Garibaldi R.B. McGehee l
N.S. Reynolds NRC Resident inspectors Office Administrator - LRPD t
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Relief Request ISI-001, Rev. 6 Component Classification Class 1 and 2, Examination Categories B-A, B-B, B-F, B-J, B-L-2, C-A, C-B, C-C, C-F Examination Requirement For each code item requiring a surface or volumetric examination, the examination tables in the Waterford 3 Ten Year inservice inspection Program identify a figure which illustrates the examination requirement for a specific code item. These figures were derived from those shown in IWB-2500-1 through 20 and IWC-2500-1 through 13 of Section XI and have been enhanced to show exact weld configuration as it exists at Waterford 3.
Relief Requested Waterford 3 is requesting that relief be given in reference to obtaining 100% coverage when examining the items contained in Table 1.
Basis for Relief Class 1 and 2 piping and components are designed with welded joints such as nozzle-to-pipe, pipe-tc c! bow and reducer-to-tee which physically obstruct all or part of the required examination. Every effort was made when selecting welds to minimize the number of welds requiring relief. Additionally, multiple angles, search units, extended Vee paths and other techniques (i.e., Refracted L waves) were used to provide additional coverage j
where practical. To Perform the Code-required examination, modification and/or replacement of the component would be required. The examinations performed on the subject welds in addition to the examination of similar welds contained in the program would detect generic degradation, if it existed, therefore demonstrating an acceptable level of integrity.
Waterford 3 has generated a detailed summary of the ASME Code Class 1 and 2 piping l
and component welds / areas which received a limited or partial examination. The summary identifies the specific weld / area and the specific cause for the partial examination. The listing of welds receiving a partial exam is attached (Table 1) to this I
relief request.
l Schedule for Implementation First 10 year interval l
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Relief Request ISI-001, Rev. 6 Table 1 Limited Examinations Page 1 of 4 Weld!! tem Exam Code Exam Percent NRC SER Designation Category item Method Coverage Description of Limitation Approval Date 04-032 B-B B2.310 UT 89 Nozzle taper causes 11% loss of coverage for 45* and 60* scans.05-011 B-D B3.110 UT 75 Nozzle configuration causes 25% loss of coverage for 45' and 60* scans.05-012 B-D B3.110 UT 75 Nozzle confguration causes 25% loss of coverage for 45* and 60* scans.05-015 B-D B3.120 UT 70 Nozzle confguration causes 30% loss of coverage for 60" and 70* scan of inner radius.05-018 B-D B3.120 UT 54 Nozzle confguration causes 46% loss of coverage for 60* and 70* scan of inner radius.04-010 B-D B3.130 UT 75 Nozzle confquration prevents scanning from the nozzle side restricting c[.erage to 75%
04-011 B-D B3.130 UT 72 Nozzle confgaration restricts coverage to 72%
04-012 B-D B3.130 UT 72 Nozzle confguration restncts coverage to 72%
07-017 B4 B9.11 UT 43 Nozzle taper and adjacent Weld 07-016 prevent coverage of $7% of weld 25-029 B-F B5 40 UT 82 Nozzle confguration restncts coverage to 82%
26-006 B-F B5.40 UT 69 Nozzle and elbow configuratscn restrict coverage to 69%
09-002 B-J 89.11 UT 43 Nozzle taper and adjacent Weld 09-001 prevent coverage of 57% of weld 11-016 B4 89.11 UT 52 Loss of transducer contact due to contour of weld prevents coverage of 48% of the required volume 11-018 B4 89.11 UT 88 Loss of transdu r contact due to contour of weld prevents coverage of 23% of the required volume 19-006 B-J 89.11 UT 75 Valve to pipe confguration limits coverage to one sede only 25-020 B-J 89.11 UT 87 Eibow radius of curvature prevents examinat!on of 50% of the required volume on the elbow side of the weld 25-021 84 89 11 UT 87 Tee radius of curvature prevents examination of 50% of the required volume on the tee side of the weld 25-022 B-J B9.11 UT 75 Tee radius of curvature prevents examination of the required volume on the elbow side of the weld 25-030 B-J 89.11 UT 87 Tee radius of curvature prevents examination of 50% of the required volume on the tee side of the weld 25-031 B4 89.11 UT 87 Reducer taper prevents the axial scan on the reducer side of tne weld 22-023 B-J B9.11 UT 80 Scanning is partial in the upstream direction due to whip restraint from 16* to 35*. Overall loss of coverage is approx. 20%.13-002 B-J B9.11 UT 77 Nozzle taper and adjacent Weld 13-018 prevent coverage of 23% of the required volume 13-018 B-J 89.11 UT 85 Adjacent Weld 13-002 and elbow confguration prevent coverage of 15% of weld 08-008 B-J 89 31 UT 78 Loss of transducer contact due to contour of nozzle to pipe weld prevents coverage of 22% of the required volume 12-008 B-J 89.31 UT 43 Overall loss of coverage as approx. 57%, due to nozzle configuration (nozzle is skewed approx. 45*).04-061 C-C C3.10 MT 85 Approx.15% loss of coverage due to Steam Generator hydrauhc snubber blocking access.04-062 C-C C3.10 MT 85 Approx.15% loss of coverage due to Steam Generator hydraube snubber blocking access.
43-WS-4 C-C C3.20 MT 50 Approx. 50% loss of coverage due to whip restraint near welded support. Can not be
t Relief Request ISI-001, Rev. 6 Table 1 Limited Examinations Page 2 of 4 Weld / Item Exam Code Exam Percent NRC SER Designation Category item Method Coverage Description of Limitation Approval Date adequately cleaned for PT exam due to restraints.
i 49-065 C-C C3.30 PT 64 Approx. 36% loss of coverage drie to pump configuration. Weld on bottom of lug could not be examined 49-066 C-C C3.30 PT 64 Approx. 36% loss of coverage due to pump confguraton. Weld on bottom of lug could not be examined.
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49-067 C-C C3.30 PT 64 Approx. 36% loss of coverage due to pump confquration. Weld on bottom of lug could not be examined.
t 42-001 C-F C5.21 UT 65 Approx. 35% loss of coverage due to nozzle-to-reducer confguraton 56-038 C-F C5.21 UT 43 Approx. 57% loss of coverage due to valve-to-reducer configuration.55-068 C-F C5.21 UT 43 Approx. 57% loss of coverage due to valve-to-reducer confguration.56-068 C-F C5.21
-UT 43 Approx. 57% loss of coverage due to valve-to-reducer confguration.55-038 C-F C5.21 UT 43 Approx. 57% loss of coverage due to valve-ta-reducer configuration.03-032 B-B B2.31 UT Partial Weld geometry and confguration 6/6/89 04-008 B-B B2.31 UT 75 3/4-inch instrument nozzles at 21*,33* 327*, and 339*; two 24-inch manways at 0* and 112*-.
6/6/89 nozzle at 180*: and weld 04-009 13-016 B-F B5.130 UT Partial OD mismatch 6/6/89 l
14-002 B-F B5.130 UT Partial OD mismatch 6/6/89 06-006 B-F B5.130 UT 90 Nozzle confguration 6/6/89 I
07-002 B-F B5.130 UT Partial OD mismatch 6/6/89 t
08-014 B-F B5.130 UT 65 Weld confguration and adjacent weld 6/6/89 10-002 B-F B5.130 UT 65 Weld confguration and adjacent weld 6/6/89 i
11-002 B-F B5.130 UT Partral OD mismatch 6Mi/89 12-009 B-F B5.130 UT Partial OD mismatch, shrinkage, and nozzle confguration 6/6/89 i
12-012 B-F B5.130 UT Partial OD mismatch 6/6/89 I
25-029 B-F B5.40 UT 90 Weld crown and nozzle confguration 6/6/89 I
26-010 B-F B5.40 UT 90 Nozzle confguraton 6/6/89 f
13-017 B-J B9.11 UT Partial OD mismatch 6S89
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13-018 B-J B9.11 UT 70 Downstream direction 45" scan is partial due to O D. geometry and weld 13-002. Overall loss 6/6/89 r
of coverage is approx. 30%.
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21-066 B-J 89.11 UT Partial Weld geometry and confguration 6/6/89 21-068 B-J 89.11 UT Partial Weld geometry and confquration 6/6/89 13-001 B-J B9.11 UT 3
Nozzle confguraton and adjacent weld 6/6/89
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14-001 B-J B9.11 UT Partial OD mrsmatch 6/6/89 07-001 B-J B9.11 UT 82 OD mismatch and 1-inch nozzle 6/6/89 f
07-017 B-J 89.11 UT 65 OD geometry 6/6/89 08-015 B-J 89.11 UT 65 Weld confquration and adjacent weld 6/6/89 09-001 B-J B9.11 UT Partial OD geometry 6/6/89
(10-001 B-J 89.11 UT 65 Weld confguratron and adjacent weld 6/Gl89
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10-013 B-J 89.11 UT Partial Weld confguration, OD mismatch and support lug 6/6/S9 11-001 B-J 89.11 UT Partial DD mismatch,1-inch line 6/6/89 11-017 B-J 89.11 UT 3
Nozzle ccnfgur# ion and adjacent weld 6/6/89 12-001 B-J B9.11 UT 70 Nozzle configuration and support lug 6/6/89 L
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1 Relief Request ISI-001, Rev. 6 Table 1 Limited Examinations i
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Weld /ttem Exam Code Exam Percent NRC SER Designation Category item Method Coverage Description of Limitation Approval Date 12-003 B-J 89.11 UT Partial OD mismatch 65/89 08-008 B-J 89 31 UT 89 Weld configuration 6/6/89 1
10-007 B-J B9.31 UT 70 Weld configuration 6/6/89 i
54-074 C-A C1.10 UT Partial Flange radius and weld geometry 6/6/89 7
04-026 C-A C1.10 UT 57 Weld confguration and insulation support ring 6/6/89 04-027 C-A C1.10 UT Partial Insulation pads 6/6/89 04-029 C-A C1.20 UT Partial Instrument nozzles at 40*, 80*,120*,160*. 200*, 280*, 320*, 360*
6/SB9 54-075 C-A C1.30 UT Partial Flange radius and weld geometry 6/618 9 1
62-078 C-F C5.11 UT 50 Weld confguration 6/6/89 f
62-089 C-F C5.11 UT SG Weld confguration 6/6/89 i
L 41-020 C-F C5.21 UT 80 Weld geometry and penetration 6/S 89 41-022 C-F C5.21 UT 65 Weld geometry 6M/89 j
43-079 C-F C5 21 UT 70 Weld confguration 6/6/89
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43-082 C-F C5.21 UT 70 Weld confguration 6/6/89 i
51-018-900 C-F C5.21 UT Partial Weld confguration and geometry 6/6/89 52-019-900 C-F C5.21 UT Partial Weld confguration and geometry 6/EV89 l
55-040 C-F C5.21 UT 85 Weld geometry and adjacent drain hne 6/6/89
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55-051 C-F C5.21 UT 70 Weld confguration 6/6/89 t
55-066 C-F C5.21 UT Partial Weld confguration and geometry 6$/89
(55-070 C-F C5.21 UT Partial Adjacent drain hne 6/6/89 t
55-075 C-F C5.21 UT Partial Weld confguraten 6/6/89 55-078 C-F C5.21 UT Partial Weld confguraten 6/6/89 56-040 C-F C5.21 UT 15 Weld confguration and geometry 6/6/89 56-047 C-F C5.21 UT 80 Weld geometry and penetraton 6/6/89 56-050 C-F C5.21 UT Partial Weld configuration 6/6/89 56-ON)
C-F C5.21 UT Partial Weld confguration and geometry 66/89 i
41-001 C-F C5.21 UT 85 Weld confguraton 6/6/89 43-001 CF C5.21 UT Partial Adjacent pipe 6/6/89 L
51-004 C-F C5.21 UT Partial Weld confguration 6/6/89 l
51-009 C-F C5.21 UT Partial Weld confguration 6/6/89
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52-004 C-F C5.21 UT Partial Weld confquration 6/6/89 52-009 C-F C5.21 UT Partial Weld confguration 6/6/89 j
43-005LA C-F C'L22 UT 5
Approx. 5% coverage for all 45* scans due to 2 whip restraint bars (4* wide) which cross the 6!6/89 i
weld.
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02-010 B-A B1.11 UT 0
Weld completely inaccessible due to shroud covering entire weld length 11/8/93
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02-002 B-A B1.21 UT 24 Six-inch wide hfting lugs at 15*,75*,105*, and 345*; and the shroud 11/8/93 j
02-003 B-A B1.21 UT 24 Six-inch wide hfting lugs at 15*,75*,105*, and 345*; and the shroud 11/8/93
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02-004 B-A B1.22 UT 30 Six-inch wide Irfting lugs at 165*,195*,255*, and 285*; shroud; and adjacent weld 02-001 11/8/93 02-005 B-A B1.22 UT 30 Six-inch wide hfting lugs at 165*,195*,255*, and 285*; shroud; and adjacent wsid 02-001 11/8/93
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02-001 B-A B1.40
- PT Partial Six-inch wide hfting lugs at 15*, 45*, 75*,105*,135*,165*,195*, 225*, 285*, 315*, and 345*;
11/8/93
- UT 50 shroud 8 inches from the toe of the weld on cw side; and the flange 5 inches from the toe on i
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Relief Request ISI-001, Rev. 6 Table 1 Limited Examinations Page 4 of 4 Weld /ttem Exam Code Exam Percent NRC SER Designation Category item Method Coverage Description of Limitation Approva1 Date the other side 03-002 B-B B2.31 -
UT 27 Base support confquration 3/4-inch instrument nozzles at 21*. 33*,327* and 339*
11/8/93 04-002 B-B B2.31 UT 27 Base support confguration 11/8/93 03-005 B-B B2.32 UT 87 Nozzle confguration 11/8/93 i
03-007 B-B B2.32 UT 82 Manway nozzle confguration and adjacent 1-inch instrument hne 11/8/93 04-009 B-B B2.40 UT 65 Weld configuration and adjacent welds04-009 and 04-024 11/8/93 01-027 B-D B3.100 UT 73 Core banet and nozzle taper 11/8/93
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01-030 B-D B3.100 UT 68 Core barrel and nozzle taper 11/8/93 17-017 B-J B9.11 UT 90 OD geometry 11/8/93 09-016 8-F B5.130 UT 65 Weld confguration and adjacent weld 11/8/93 13-018 B-J B9.11 UT Partial OD geometry 11/8/93 l
i 17-030 B-J B9.11 UT 64 Weld geometry and confguration 11/8/93 18-022 B4 B9.11 UT 50 Weld confguration 11/8/93 18-027 B-J 89.11 UT 50 Weld confguration 11/8/93 i
22-023 B-J 89.11 MT Partial Whip restraint 11/8/93 i
UT Partial f
f 09002 B-J 89.11 UT 90 OD geometry 11/8/93 09008 B4 89.11 UT Partial Weld geometry 11/8/93 09-017 B-J 89.11 UT 65 Weld configuration and adjacent weld 11/8/93 I
11-016 B4 B9.11 UT 90 OD geometry 11/8/93
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11-018 B-J B9.11 UT 90 OD geometry 11/8/93 09-019LB B4 B9.12 UT
<50 OD geometry 11/8/93 09-020LA B-J 89.12 UT
<50 OD geometry 11/8/93 i
51-033 C-F C5.11 UT 25 Weld confguration 11/8/93 f
52-027 C-F C5.11 UT 25 Weld confquration 11/8/93
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52-066 C-F C5.11 UT 43 Weld confguration 11/8/93 L
51-005 C-F C5.11 UT 25 Component confguration 11/8/93
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52-005 C-F C5.11 UT 25 Weld configuration 11/8/93 f
43-049LA C-F C5.22 UT 84 Adjacent whip restraints 11/8/93 i
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Page 1 of 2 The following table is a list of components that were granted relief by the Nuclear Regulatory Commission as documented in Safety Evaluation Report dated November 8,1993, but are removed from the ISI Relief Request ISI-001 revision 6.
COMPONENT #
REASON UNLISTED 01-008 revoked by 10 CFR 50.55a(g)(6)(ii)(A) 01-012 revoked by 10 CFR 50.55a(g)(6)(ii)(A) 04-011 inspected @l00%
04-012 inspected @l00%
l 04-024 inspected @100%
04-025 inspected @100%
l 04-028 inspected @100%
04 032 inspected @l00%
05-002 inspected @100%
05-003 inspected @l00%
07-010 not selected 07-019LA inspected @100%
07-020LB inspected @100%
1 09-019LA inspected @l00%
10-009 not selected 10-012 inspected @l00%
Il-010 not selected 11-019LA inspected @l00%
j 12-002 inspected @l00%
13-019LB inspected @l00%
13-020LB inspected @l00%
l 17-016 not selected j
17-032 inspected @l00%
18-025 not selected 18-059 inspected @l00%
19-026 not selected 19-027 not selected 19-055 inspected @l00%
20-016 not selected 20-025 not selected 20-029 inspected @l00%
20-056 not selected
(20-056 not selected 22-053 not selected 22-053 not selected 1
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Page 2 of 2 25-009 inspected @100%
25-015 inspected @l00%
25-024 inspected @l00%
25-025 no weld 25-026 inspected @l00%
j 25-027 inspected @100%
25-028 inspected @l00%
25-028 inspected @100%
26-002 inspected @IJO%
26-003 not selected 26-006 inspected @l00%
26-007 inspected @l00%
26-008 inspected @100%
26-009 inspected @100%
42-001 inspected @100%
42-005 inspected @100%
42-011 inspected @.100%
l 42-024 inspected @100%
43-004 inspected @l00%
43-089 augmented 44-026LA inspected @l00%
44-086LA inspected @100%
44-089 inspected @100%
l 45-019 inspected @l00%
l 46-021 inspected @l00%
47-034 augmented 50-023 inspected @l00%
1 51-003 inspected @l00%
l 55-042 inspected @l00%
56-042 inspected @100%
l 56-070 inspected @l00%
56-072 inspected @100%
i 60-098 augmented 60-131 augmented 61-05I inspected @l00%
61-071 inspected @100%
61-073 inspected @100%
61-080 inspected @l00%
62-047 inspected @l00%
62-094 inspected @100%
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1 Page 1 of 1 The following tabl is a list of components that were denied relief by the Nuclear Regulatory Commission as documented in Safety Evaluation Report dated November 8,1993, and are not listed in ISI j
Relief Request ISI-001 revision 6 l
i COMPONENT #
REASON UNLISTED 06-005 not selected j
07-018 inspected @100%
09-008 not s, elected 09-018 inspected @100%
11-020LB inspected @100%
13-008 not selected 15-007 not selected 16-001 inspected @l00%
16-002 inspected @l00%
16-003 inspected @l00%
16-006 inspected @100%
16-007 inspected @l00%
16-008 inspected @100%
16-011 inspected @l00%
16-016 inspected @l00%
17-003 inspected @100%
17-014 not selected 17-023 not selected 18-008 not selected 18-042 not selected 19-002 not selected 19-008 not examined (scheduled for next outage-April 97)19-024 not selected 19-038 not selected 19-042 not selected 22-004 not selected l
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Page 1 of 1 The following table is a list of components that were granted relief by the Nuclear Regulatory Commission as documented in Safety Evaluation Report dated November 8,1993, and did not receive the coverage that was estimated in ISI Relief Request 1S1-001 revision 6:
COMPONENT #
% estimated
% actual 04-0l1 91 72
(04-012 91 72 07-017 65 43 08-008 89 78 l
09-002 90 43 11-016 90
$2 11-018 90 88 25-029 90 82 l
26-006 93 69 42-001 90 65 l
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