B15266, Notifies NRC of Inability to Completely Satisfy Requirements for Second 10-yr ISI Augmented Exam of Reactor Pressure Vessel at Millstone Unit 2 & Requests Authorization to Not Perform Any Addl or Alternative Exams
| ML20085F670 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/09/1995 |
| From: | Debarba E, Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B15266, NUDOCS 9506190356 | |
| Download: ML20085F670 (31) | |
Text
.
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107 Selden Street, Berun, CT 06037 g
3-Utilities System Nonbemt Unudes Sente Company P.O. Bas 270 '
Ilartford, CT M141-0270 (203) 665-5000 June 9, 1995 Docket No. 850-336 B15266 Re: 10CFR50.55a(g)(6)(ii) i U.S. Nuclear Regulatory Commission Attention:
Document Control Desk l
Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 2 l
Second 10-Year Interval Inservice Inspection Anamented Rwamination of Ranctor Pressure Vammal The purpose of this letter is to notify the NRC Staff of the inability to completely satisfy the requirements for the augmented reactor pressure vessel (RPV) shell weld examinations at Millstone Unit No.
2, and to request authorization to not perform. any additional or alternative examinations.
f Northeast Nuclear Energy Company (NNECO) has recently completed the Second 10-Year Interval Inservice Inspection (ISI) of its RPV in accordance with the requirements of ASME B&PV Code Section XI 1980 i
- Edition, including the 1981 Winter
- Addenda, augmented by j
10CFR50.55a, paragraph (g) (6) (ii) (A).
These examinations were performed using automated ultrasonic testing (UT) equipment and l
automated ultrasonic examination. data recording and analysis systems.
The augmented examination, however, was unable to obtain the.
l
" essentially 100%" (i.e., >90%) volumetric coverage of each weld as e
required by 10CFR50.55a, paragraph (g) (6) (ii) (A) (2).
The lack of j
coverage exists on two Code Item Bl.11 circumferential welds (#HS-1 and #SC-2) and three Code Item Bl.12 longitudinal welds (#LSL-1,
- MSL-1, and #USL-3).
The examination limitations are attributed to the following internally-mounted components of the RPV:
l Hot Leg Nozzle Extensions Irradiation Specimen Tube Holders Flow Skirt Anti-rotation Lugs These limitations are consistent with those experienced by other utilities with Combustion Engineering designed RPVs.
provides a report of the affected welds, the coverage limitations, weld figures, andithe palculated percentage of UT volume for each weld examined.
ADLUCI 9506190356 950609 PDR ADOCK 05000336 O
PDR l
oom arv.m 1
1 U.S. Nuclear Regulatory Commission B15266/Page 2 June 9, 1995 The results of the Second 10-Year Interval ISI detected indications in the Code Item Bl.11 RPV circumferential welds (/SC-1 and /SC-2) and Code Item Bl.12 RPV longitudinal welds (/USL-1, #USL-2, and
- USL-3).
Based on sizing data, these indications are code allowable in accordance with IWB-3500 of ASME Section XI.
In addition, RPV welds outside the scope of Code Item Bl.10 were also examined and indications were found that are also determined to be Code allowable per IWB-3500.
This is the third ultrasonic examination of the RPV at Millstone Unit No.
2.
In 1975, preservice UT examinations were conducted from the outside diameter (OD) of the RPV utilizing a remote tracking tool.
All of the RPV shell welds were examined and received essentially a 100%
volumetric exam.
In this case, full coverage was possible since access to the OD was not hampered by a high radiation environment.
As a result of the high radiation environment, the industry has replaced OD UT systems with volumetric UT examinations from the inside diameter (ID) of RPVs.
In
The ID exams were performed to the applicable requirements of the ASME B&PV Code Section XI 1974 Edition, including the 1975 Summer Addenda.
Consistent with the requirements at that time, onlv 5% of the volume of each circumferential and 10% of the volume of each longitudinal RPV shell weld located within the beltline region was examined.
NNECO chose, however, to exceed these requirements and examined a portion of all the RPV shell welds listed under Code Categories B-A and B-B.
In 1994, NNECO performed the Second 10-year Interval ISI Program RPV examinations.
This program was developed to meet the requirements of the ASME B&PV Code Section XI 1980 Edition, up to and including the Winter 1981 Addenda.
The requirements for RPV 1
welds in this version of the Code were redefined under a revised Code Category B-A,
" Pressure Retaining Welds in Reactor Vessels."
The new requirements for these RPV shell welds states that one Code Item Bl.11 circumferential and one Code Item Bl.12 longitudinal weld within the beltline region must be examined.
In addition, a note is provided in the IWB-2500 table which indicates that j
essentially 100% of the weld length shall be examined.
As in 1983, NNECO chose to exceed the ISI requirements and included all of the RPV shell welds in the Second 10-Year Interval ISI Program.
NNECO has reviewed the 1994 UT results and concludes that the UT performed is adequate to confirm an acceptable level of quality and safety, and no further examination is warranted.
In particular, no UT of the RPV OD is justified.
This conclusion is based on the following:
U.S. Nuclear Regulatory Commission B15266/Page 3 June 9, 1995 After 12 operating cycles, the OD surface condition of the RPV would likely not be conducive to a direct coupled UT technique without extensive surface preparation.
This preparation would unnecessarily expose personnel to e
high radiation environment.
The radiation levels betVacQ the biological chield insulation and the vessel middle saat/.on are estimated to be in the range of 5 to 15 R/hr.
Thus, full compliance to the augmented requirements of 10CFR50.55a from the OD surface of the RPV would result in unnecessary personnel exposure without a commensurate increase in the level of reliability, quality, or safety over the partial examinations reported in.
All of the indications that were detected within the weld volumes examined are acceptable without analytical evaluation.
Therefore, it is unlikely that the unexamined sections would not be acceptable for continued service.
The cumulative total volume of welds examined was 91.5% of the i
Millstone Unit No.
Although this cumulative total cannot be used to meet the RPV augmented requirements, this percentage supports the fact that the in-vessel examination covered a significant volute of the RPV shall welds.
Based on the above, NNECO is not planning to perform any additional examinations on any of the RPV shall
- welds, and requests authorization of this alternative to the examination requirements by the Director of the Office of Nuclear Reactor Regulation pursuant to 10CFR50.55a, paragraph (g) (6) (ii) (A) (5).
If you have any questions on this submittal, please contact Mr. Mario Robles, Jr. at (203) 440-2073.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: J.
F. Opeka Executive Vice President BY:
E. A. DeBarba Vice President Attachment cc:
See Page 4 I
1 U.S. Nuclear Regulatory Commission B15266/Page 4 June 9, 1995 cc:
T. T. Martin, Region I Administrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 P.
D. Swetland, Senior Resident Inspector, Millstone Unit Nos.
1, 2, and 3 6
)
I j
-4_.
Docket No. 50-336 B15266 l
1 i
Millstone Nuclear Power Station, Unit No. 2 Second 10-Year Interval In Service Inspection Augmented Examination of Reactor Pressure Vessel l'
l l
i t
t f
k June 1995 l
1 APPENDIX F EXAMINATION AREA COVERAGE REPORT FOR MILLSTONE NUCLEAR POWER STATION, UNIT 2 This appendix describes the ultrasonic (UT) examination coverage obtained and examination limitations encountered during the 1994 inservice examination of the Millstone Nuclear Power Station, Unit 2, reactor pressure vessel (RPV) welds and selected com>onents. The examinations were performed by Southwest Research Institute using automated scanning equipment and automated ultrasonic (AUT) examination data recording and analysis systems in accordance with a Scan Plan and procedures approved by Northeast Nuclear Energy Company (NNECO). These procedures comply with requirements of the 1980 Edition with Addenda through Winter 1981 of the American Society of Mechanical Engineers (ASME)Section XI and United States Nuclear Regulatory Commission Regulatory Guide 1.150, Revision 1, Appendix A.
The scope of the AUT examinations included all RPV shell, lower head, and nozzle weld areas for 100 percent of the accessible weld lengths, and the scope of the AUT examinations of the piping butt welds included the inlet nozzle to-elbow, elbow-to-pipe, and elbow longitudinal welds.
The examination coverage for the RPV welds was determined in accordance with the requirements of Section V, T-441.4.3, T-441.5. T-441.6, and T-441.7. These requirements are as follows:
(1)
Reflectors Oriented Parallel to the Weld (a)
The inner 25%t including the weld metal and adjacent base metal for 1/2t either side of the weld fusion line (volume A in the attached figures) must be completely scanned with the 50D0 search unit aimed at right angles to the weld axis. Scanning shall be performed in two directions 180 degrees to each other.
(b)
The weld metal in the outer 75%t (volumo B in the attached figures) must be completely scanned by two angle beams,(45 and 60 degrees) with the search units
=
aimed at right angles to the weld axis. Scanning shall be performed in two directions 180 degrees to each other.
(c)
The adjacent bue metal in the outer %0 for 1/2t either side of the weld fusion line (volumes C and D in the attached figures) must be completely scanned by two angle beams (45 and 60 degrees), but need not be completely scanned by both angle beams from both directions (any combination of two angle beams will satisfy the requirement).
(d)
For those examinations performed from the nozzle bores and flange seal surface, the ultrasonic beams must be directed essentially perpendicular to the plane of the weld to detect reflectors parallel to the welds. The beam angles used must be sufficient to provide complete coverage of the required volumes from one direction.
(2)
Reflectors Driented Transverse to the Weld (a)
The inner 25%t including the weld metal and adjacent base metal for 1/2t either side of the weld fusion line (volume A in the attached figures) must be scanned with the 50D0 search unit beam directed parallel to the weld axis. Scanning shall be performed in two directions 180 degrees to each other to the extent possible. Areas blocked by geometric conditions shall be exammed from at least one direction.
F-1
I (b)
The weld metal and adjacent base metal in the outer 75%t for 1/2t either side of the weld fusion line (volumes B, C, and D, in the attached figures) must be scanned 3
with the 45-and 60 degree search unit beams directed parallel to the weld axis.
Scanning shall be -- 'wed in two ducctions 180 degrees to each other to the extent le. Areas bloc $ed by geometric conditions shalbe *ramine from atleast one j
(3)
! *=in*r Reflectors The base material through which the angle beams pass must be scanned with a straight-beam l
search unit to detect laminar reflectors which might affect interpretation of angle-beam results. The required volume to be eramineA is limited to only those volumes that receive coverage with angle beams. This could be all, or any part of the ABCDEF volumes shown in the anached Egures.
-(4)
Planar Reflectors Straight-beam scanning for planar reflectors must be perfonned on the entire weld and l
adjacent base material (volumes A, B, C, and D in the anached figures).
The examination coverage for nozzle-to-elbow and elbow-to-pipe welds was determined in accordance with the requirements of NNECO Request for Relief No. RR-10. As an alternative to the surface examination of requirements of Section XI, a full volumetric ernmination of the weld and heat-affected zone was performed as described below:
(1)
Reflectors Parallel to the Weld I
The weld and adjacent base metal for 1/2 inch either side of the weld fusion line (volume i
shown in Figure 9) must be examined from two sides of he weld using the SLIC-40 search unit. The ultrasonic beam must pass through the volume in two opposing duections.
(2)
Reflectors Transverse to the Weld The weld and adjacent base metal for 1/2 inch either side of the weld fusion line (volume shown in Figure 9) must be examined with the SLIC-40 search unit. The ultrasonic beam is directed parallel to the weld to detect reflectors transverse to the weld. The ultrasonic beam must pass through the volume in two opposing directions.
The integral extensions, the irradiation specimen holders, the core stabilizing lugs, and the flow skirt 4
on the lower head limited scannmg accessibility to the full length and/or width of some areas from the inside surface. Figure 1 provides information on the locations of these areas.
The examination coverage obtained is compared to the weld and base metal volumes identi5ed as the examination areas in Figures 2 through 9 contained in this report. The ASME Code-specified techniques for AUT RPV examinations were augmented by special, SwRI-qualified techmques to obtain complete and highly sensitive coverage of the underclad and near-surface material volumes.
AUT examinition coverage tables in this appendix quantify the volume of material examined with each ultrasonic technique for each examination area. Additional parallel examinations were performed frorn the vessel wall for the r shell-to-flange welds and were not factored into the examination tables since the complete coverage was obtained from the vessel flange seal surface. The parallel examinations from the vessel wall were limited due to the inside flange taper.
The parallel examination coverage obtamed from the vessel wall is:
F-2
_ _=.
Vol Anales -
hm Covearne A
50n0 2 Dir 66 %
B 45/60 2 Dir 34 %
C 45/60 1 Dir 100 %
D 45/60 1 Dir 88 %
The following contains an explanation of each item listed in the Exammation Coverage Tables.
Summary Number
- The examination Summary Sheet Number that is assigned to each particular weld.
Weld Number
- The specific weld identification number as supplied by NNECO.
Exam Area Identification - Description of the weld type or component identification.
Exam Volume and Figure - The specific volume as identified in ASME Section XI, Regulatory Guide 1.150, and Figures 2 through 9.
Beam Angle (s)
- The refracted longitudinal-or shear-wave angles used for the examination.
Exam Type
- As defined in Article 4 of ASME Section V, the type of flaw that each examination is intended to detect, e.g., flaws transverse or parallel to the weld, straight beam for planar or laminar flaws etc.
Beam Direction (s)
- For each volume, the number of directions that the beam was directed to detect the type of flaw (parallel or transverse to the weld).
Code Coverage
- The Percent of coverage for each volume, as a function of beam angle (s), exam type, and beam direction (s) combined.
Remarks
- This section is used to explain the source or cause of any limitations encountered.
j NOTES:
- 1. The Average shown as a percent is a simple average of the coverage for all required examinations performed.
2.
All straight-beam (0 degree) examination directions are listed as "N/A" because a straight beam can only be introduced into the volume in a single direction.
- 3. The examination limitations report and coverage tables are restricted to examinations performed by SwRI, and do not reflect limitations from examinations performed by others during previous inservice inspections, or exammations that have been deferred.
4.
The required volume for straight-beam lamination examinations is defined as only the area through which the angle beam (s) pass.
F-3
Millstone Nuclear Power Station, Unit 2 1994 Reactor Vessel inservice inspection Examination Coverage Tables 33tgygry
? ! e.. _ ? i 13B*asaApga.
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. / Enant
& M '?
{. Cetit
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- fc w*
Number 4M.
lalentitlection Volume Fleure Angle (sh
'I Type Direition(s)
Coverage T UM 002000 BHC-1 Bottom Head to A
1&2 50/70 Parallet 2 Directions 100 %
(item No. B1.21)
Peel Segment A
50f70 Transverse 2 Directions 100 %
Torus B
45 & 60 Parallel 2 Directions 100 %
BCD 45 & 60 Transverse 2 Directons 100%
C 45 & 60 Parallel 1 Direction 100%
D 45 & 60 Para!!el 1 Direction 100%
ABCDEF 0
Lamination N/A 100%
ABCD 0
Planar (Weld)
N/A 100 %
Average 100 %
T 002100 HS-1 Lower She!!
A 1&2 50/70 Parallel 2 Directions 82 %
Limited (Item No. B1.11) to A
50f70 Transverse 2 Direchons 88 %
examination Bottom Head B
45 & 60 Parallel 2 Directions 73 %
due to the BCD 45 & 60 Transverse 2 Directions 79 %
flow skirt and C
45 & 60 Parallel 1 Direction 95 %
anti-rotation D
45 & 60 Parallel 1 Direction 95 %
lugs.
ABCDEF 0
Lamination N/A 100 %
ABCD 0
Planar (Weld)
N/A 98 %
Average 89 %
002200 BHV-1 Peel Segment A
1&3 50/70 Parallel 2 Directions 50 %
Limited l
(Item No. B1.22) at30*
A 50/70 Transverse 2 Directions 47%
examination B
45 & 60 Parallel 2 Directions 31 %
due to the BCD 45 & 60 Transverse 2 Directions 35 %
flow skirt.
C 45 & 60 Parallel 1 Direction 31 %
D 45 & 60 Parallel 1 Direction 31 %
ABCDEF 0
Lamination N/A 100 %
ABCD 0
Planar (Weld)
N/A 35 %
Average 45%
O 5
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Millstone Nuclear Power Station, Unit 2 1994 Reactor Vessel inservice inspection Examination Coverage Tables (Cont'd)
F/ l,C.f.; 3 i wWW5 9 /+:
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Exteti Beer 6 '
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6..'
v Number I Number
identtfleetion Volume Figure Angle (s)
Type W s)
Coverage "M
002300 BHV-2 Peel Segment A
1&3 50/70 Parallel 2 Directions 48 %
Limited (item No. B1.22) at 90*
A 50/70 Transverse 2 Directions 47%
examination B
45 & 60 Parallel 2 Directions 48 %
due to the BCD 45& 60 Transverse 2 Directions 35 %
flow skirt.
C 45 & 60 Parallel 1 Direction 48 %
D 45 & 60 Parallel 1 Direction 48 %
ABCDEF 0
Lamination N/A 100%
ABCD 0
Planar (Weld)
N/A 40 %
Average 52 %
- r1 002400 BHV-3 Peel Segment A
1&3 50/70 Parallel 2 Directions 50 %
Umited (item No. B1.22) at150*
A 50/70 Transverse 2 Directions 47%
examination B
45 & B0 Parallel 2 Directions 31 %
due to the BCD 45 & 60 Transverse 2 Directions 35 %
flow skirt.
C 45 & 60 Parallel 1 Direction 31 %
D 45 & 60 Parallel 1 Direction 31 %
ABCDEF 0
Lamination N/A 100 %
ABCD 0
Planar (Weld)
N/A 35 %
Average 36 %
002500 BHV-4 Peel Segment A
1&3 50/70 Parallel 2 Directions 48 %
Umited (Item No. B1.22) at210*
A 50/70 Transverse 2 Directions 47%
examination B
45 & 60 Parallel 2 Directions 48 %
due to the BCD 45 & 60 Transverse 2 Directions 35%
flow skirt.
C 45 & 60 Parallel 1 Direction 48 %
D 45 & 60 Parallel 1 Direction 48 %
ABCDEF 0
Lamination N/A 100 %
ABCD 0
Planar (Weld)
N/A 40 %
Average 52%
Q E1
Millstone Nuclear Power Station, Unit 2 1994 Reactor Vessel inservice inspection Examination Coverage Tables (Cont'd)
L.7.i,
W lEneT.Aree
'Enam :
Seem _
Ettam BeM
- v. Code;i
@? y i
- I5 r
1 Numtw
" Number e identification Volume Figure.Ans(s)
Type Directiorde)
' Cc...
x.i.is-002600 BHV-5 Peel Segment A
1&3 50/70 Parallel 2 Directions 50 %
Limited (item No. B1.22) at 270' A
50/70 Transverse 2 Directons 47%
examination B
45 & 60 Parallel 2 Directions 31 %
due to the BCD 45 & 60 Transverse 2 Directions 35 %
flow skirt.
C 45 & 60 Parallel 1 Direction 31 %
D 45 & 60 Parallel 1 Direction 31 %
ABCDEF 0
Lamination N/A 100%
ABCD 0
Planar (Weld)
N/A 35%
Average 45 %
73 002700 BHV-6 Peel Segment A
1&3 50/70 Parallel 2 Directions 58 %
Umited (item No. 81.22) at 330' A
50/70 Transverse 2 Directions 44 %
examination B
45 & 60 Parallel 2 Directions 58 %
due to the BCD 45 & 60 Transverse 2 Directions 33%
flow skirt.
C 45 & 60 Parallel 1 Direction 58 %
D 45 & 60 Parallel 1 Direction 58 %
ABCDEF 0
Lamination N/A 100 %
ABCD 0
Planar (Weld)
N/A 33%
1 Average 55%
002800 FS-1 Upper Shell ABCD 1&4 1,6,& 12 Parallel N/A 100 %
in addition.
(Item No. B1.30) to Flange A
50/70 Transverse 2 Directions 100 %
parallel BCD 45 & 60 Transverse 2 Directons 100 %
examinations ABCDEF 0
- f. amination N/A 100 %
were performed ABCD 0
Planar (Weld)
N/A 100 %
from the Average 100%
vesselwall.
This information is contained in the text of this Q
appendix.
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1 Millstone Nuclear Power Station, Unit 2 1994 Reactor Vessel inservice inspection Examination Coverage Tables (Cont'd) i:..f.. ',
VWel5?W taafft Aree '
Etem
~ ' '
Seem
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Y COdd 1 *cB #'M J%
I f M.'i./ 4 *_'
Number
~MD iden#fleetion Volume Figure Angle (s)
Type Dir W s)
Coverage 002900 SC-1 Middle to Upper A
1&5 50/70 Parallel 2 Directions 100 %
Limited (item No. B1.11)
Shell A
50/70 Transverse 2 Directions 100%
examination B
45 & 60 Parallel 2 Directions 96 %
due to the BCD 45 & 60 Transverse 2 Directions 100%
outlet nozzle C
45 & 60 Parallel 1 Direction 100%
integral D
45 & 60 Parallel 1 Direction 10C%
extension.
ABCDEF 0
Lamination N/A 100%
ABCD 0
Planar (Weld)
N/A 100 %
Average 99 %
- n 003000 SC-2 Lower to Middle A
1&5 50/70 Parallel 2 Directions 87 %
Limited (Item No. B1.11)
Shell A
50/70 Transverse 2 Directions 87%
examinetton B
45 & 60 Parallel 2 Directions 87%
due to the BCD 45 & 60 Transverse 2 Directions 87%
inadiation c t
C 45 & 60 Parallel 1 Direction 87 %
specimen tube D
45 & 60 Parallel 1 Direction 87 %
holders.
ABCDEF 0
Lamination N/A 100 %
ABCD 0
Planar (Weld)
N/A 87 %
Average 89 %
i 003100 LSL-1 Lower Shell A
1&3 50f70 Parallel 2 Directions 51 %
Limited l
(ftem No. B1.12) longitudinal A
50f70 Transverse 2 Directions 81 %
examination at 90*
B 45 & 80 Parallel 2 Directions 12 %
due to the BCD 45 & 00 Transverse 2 Directions 80%
irradiation l
C 45 & 60 Parallel 1 Direction 100 %
specimen tube D
45 & 60 Parallel 1 Direction 100 %
holders.
ABCDEF 0
Lamination N/A 100%
ABCD 0
Planar (Weld)
N/A 91 %
Average 77 %
Q s1
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Millstone Nuclear Power Station, Unit 2 1994 Reactor Vessel inservice Inspection Examination Coverage Tables (Cont'd) 30.TCy "firti8 e -
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Bearn:
w Etern Beern
. ' Code ' '
JT 1-P4 umber
'b.
Identification
. Volume Figure ArWe[
. Type W s) kn.sd l' huik '
r 003200 LSL-2 Lower Shell A
1&3 50/70 Parallel 2 Directions 100 %
(item No. B1.12)
Longitudinal A
50/70 Transverse 2 Directons 100%
at 210' B
45 & 60 Parallel 2 Directions 100 %
BCD 45 & 60 Transverse 2 Directons 100%
C 45 & 60 Parallel 1 Directen 100%
D 45 & 60 Parallel 1 Directon 100 %
ABCDEF 0
Lamination N/A 100 %
ABCD 0
Planar (Weld)
N/A 100 %
Average 100 %
71 003300 LSL-3 Lower Shell A
1&3 50/70 Parallet 2 Directions 100 %
(ltem No. B1.12)
Longitudinal A
50/70 Transverse 2 Directions 100%
at 330' B
45 & 60 Parallel 2 Directions 100 %
BCD 45 & 60 Transverse 2 Directions 100 %
C 45 & 60 Parallet 1 Direction 100 %
D 45 & 60 Parallel 1 Direction 100%
ABCDEF 0
Lamination N/A 100%
ABCD 0
Planar (Weld)
N/A 100%
Average 100%
003400 MSL-1 Middle Shell A
1&3 50/70 Parallel 2 Directions 22%
Limited (Item No. B1.12)
Longitudinal A
SW70 Transverse 2 Directions 44 %
examination at 90' B
45 & 60 Parallel 2 Directions 25 %
due to the BCD 45 & 60 Transverse 2 Directions 66 %
irradiation C
45 & 60 Parallel 1 Directen 67 %
specimen tube D
45 & 60 Parallel 1 Direction 61 %
holders.
ABCDEF 0
Lamination N/A 100%
ABCD 0
Planar (Weld)
N/A 51 %
Average 55 %
9 51 w
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e Millstone Nuclear Power Station, Unit 2 1994 Reactor Vessel inservice inspection Examination Coverage Tables (Cont'd) 02 Try
--. WOWrP Essen Arte'
- Etant
< - Beem.
Enam ^
. Beest -
Code:;
21
' ~
Number '"NumbeM Identtrication Volume Figure nele(s)
JS Type ' D W s)
Coverage
~- ' Nederks 003500 MSL-2 Middle Shell A
1&3 50/70 Parallel 2 Directions 100%
(item No. B1.12)
Longitudinal A
50/70 Transverse 2 Directions 100%
at 21(7' B
45 & 60 Parallel 2 Directions 100 %
BCD 45 & 60 Transverse 2 Directions 100 %
C 45 & 60 Parallel 1 Direction 100 %
D 45 & 60 Parallel 1 Direction 100%
ABCDEF 0
Lamination N/A 100%
ABCD 0
Planar (Weld)
N/A 100%
Average 100 %
?!
003600 MSL-3 Middle Shell A
183 50/70 Parallel 2 Directions 100 %
(item No. B1.12)
Longitudinal A
50/70 Transverse 2 Directions 100 %
at330" B
45&60 Parallel 2 Direchons 100 %
BCD 45 & 60 Transverse 2 Directions 100%
~
C 45 & 60 Parallel 1 Direction 100 %
D 45 & 60 Parallel 1 Direction 100 %
ABCDEF 0
Lamination N/A 100 %
ABCD 0
Planar (Weld)
N/A 100%
Average 100%
l 003700 USL-1 Upper Shell A
1&3 50/70 Parallel 2 Directions 100%
(
(ltem No. B1.12)
Longitudenal A
50/70 Transverse 2 Directions 100%
at 90' B
45 & 60 Parallel 2 Directions 100 %
BCD 45 & 60 Transverse 2 Directions 100 %
C 45 & 60 Parallel 1 Direction 100 %
D 45 & 60 Parallel 1 Direction 100%
ABCDEF 0
Lamination N/A 100 %
ABCD 0
Planar (Weld)
N/A 100 %
Average 100%
Q
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Millstone Nuclear Power Station, Unit 2 1994 Reactor Vessel inservice inspection Examination Coverage Tables (Cont'd)
Z 1y PJ W eld P JEue.T Areal
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~?
a Beem '
- u Esash m BesM ::
. CdG4
"" r e ma > ~
' Number hNumber identification Volume Figure A W s)
TypeI Otraction(s)
Coverage
~ Noenerks 003800 USL-2 Upper Shell A
1&3 50/70 Parallel 2 Directions 87%
Limited (1 tem No. B1.12)
Longitudinal A
50/70 Transverse 2 Directions 100 %
examination at 210*
B 45 & 60 Parallel 2 Directions 59 %
due to the BCD 45 & 60 Transverse 2 Directions 100 %
integral C
45 & 60 Para!Iel 1 Directen 100 %
extension on D
45 & 60 Parallel 1 Direction 100 %
outlet ABCDEF 0
Lamination N/A 100%
nozzle NS-4.
ABCD 0
Planar (Weld)
N/A 100 %
Average 93%
?E 003900 USL-3 Upper Shell A
1&3 50/70 Parallel 2 Directions 68 %
Limited (Item No. B1.12)
Longitudinal A
50/70 Transverse 2 Directions 100 %
examination at330*
B 45 & 60 Parallel 2 Directions 37%
due to the BCD 45 & 60 Transverse 2 Direchons 100 %
integral C
45 & 60 Parallel 1 Direction 100%
extension on D
45 & 60 Parallel 1 Direction 100 %
outlet ABCDEF 0
Lamination N/A 100%
nozzle NS-1.
ABCD 0
Planar (Weld)
N/A 100 %
Average 88 %
004000 NS-1 Outlet Nozzle A&B 1&6 5 & 45 Parallel 1 Direction 100 %
Limited (Item No. B3.90) to Shell at 0*
B 50/70 Transverse 2 Directions 5%
examination A
45 & 60 Transverse 2 Directions 13%
due to the A&B 0
Lamination N/A 100 %
integral A&B 0
Planar (Weld)
N/A 12 %
extension.
Average 46%
9 s
2 w
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Millstone Nuclear Power Station, Unit 2 1994 Reactor Vessel inservice inspection Examination Coverage Tables (Cont'd) 8dedlery
, Wel5 x t Enam Arte. ^
Enami i e
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." Code..
s, p~"qs4 Ow Number
- dumiser ' -
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' Angle (s) iType6 Direcdon(4)
Coverage idihe E
004100 NS-2 In!et Nozzle A&B 1&7 5 & 45 Parallel 1 Direction 100 %
(Item No. B3.90) to Shell at 60*
B 50/70 Transverse 2 Directions 100 %
A 45 & SO Transverse 2 Directions 100 %
A&B 0
Lamination N/A 100%
A&B 0
Planar (Weld)
N/A 100%
Average 100%
004200 NS-3 Inlet Nozzle A&B 1&7 5 & 45 Parallel 1 Direction 100 %
(ftem No. B3.90) to Shell at 120' B
50/70 Transverse 2 Directions 100%
[
A 45 & 60 Transverse 2 Directions 100 %
A&B 0
Lamination N/A 100 %
A&B 0
Planar (Weid)
N/A 100 %
Average 100 %
004300 NS-4 Outiet Nozzle A&B 1&6 5 & 45 Parallel 1 Direction 100 %
Umited (item No. B3.90) to Shell at 180*
B 50/70 Transverse 2 Directions 5%
examination A
45 & 60 Transverse 2 Directions 13%
due to the A&B 0
Lamination N/A 100%
integral _
A&B 0
Planar (Weld)
N/A 12%
extension.
Average 46 %
004400 NS-5 Inlet Nozzle A&B 1&7 5 & 45 Parallel 1 Direction 100 %
(Item No. B3.90) to Shell at 240' B
50/70 Transverse 2 Directions 100 %
A 45 & 60 Transverse 2 Directions 100 %
A&B 0
Lamination N/A 100 %
A&B 0
Planar (Weld)
N/A 100 %
Average 100 %
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Millstone Nuclear Power Station, Unit 2 1994 Reactor Vessel inservice inspection Examination Coverage Tables (Cont'd) sumery w" kmbE ~ * 'l identl6 cation Volume Figure A W s)
-Type DirMs) di.dd NemM6i.: _..
w.u n th Ares :
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Number 005800 P-9-L-4 Pipe LS far side A-B-C-D 9
SLIC-40 Parallel 2 Directions 100%
(Item No. 89.12) from P-9-C-2 A-B-C-D SUC-40 Transverse 2 Directions 100%
Average 100 %
005900 P-9-C-2 Pipe to Elbow A-B-C-D 9
SLIC-40 Parallel 2 Directkxts 100%
(Item No. 89.11)
A-B-C-D SLIC-40 Transverse 2 Directions 100%
Average 100 %
006000 P-9-L-1-A Elbow LS long A-B-C-D 9
SUC-40 Parallel 2 Directions 100 %
[
(liem No. 89.12) side A-B-C-D SLIC-40 Transverse 2 Directions 100 %
w from P-9-C-2 Average 100%
006100 P-9-L-2-A Elbow LS short A-B-C-D 9
SUC-40 Parallel 2 Directions 100 %
(ftem No. 89.12) side A-B-C-D SUC-40 Transverse 2 Directions 100 %
from P-9-C-2 Average 100%
006200 P-9-L-1 Elbow LS long A-B-C-D 9
SUC-40 Parallel 2 Directions 100%
(item No. B9.12) side A-B-C-D SUC-40 Transverse 2 Directions 100 %
from P-9-C-1 Average 100 %
006300 P-9-L-2 Elbow LS short A-B-C-D 9
SLIC-40 Parallel 2 Directions 100 %
(l'em No. B9.12) side A-B-C-D SUC-40 Transverse 2 Direchons 100 %
from P-9-C-1 Average 100 %
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Mill;tane Nuclear Power Station, Unit 2 1994 Reactor Vessel inservice inspection Examination Coverage Tables (Cont'd)
SWhefidry WOWW& DEkelen Ates :
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006400 P-9-C-1 Elbow to Reactor A-B-C-D 9
SLIC-40 Parallet 2 Directons 100 %
(item No. B9.11) Vessel Extension A-B-C-D SUC-40 Transverse 2 Directions 100 %
Average 100%
006500 P-14-L-3 Pipe LS far side A-B-C-D 9
SLIC-40 Parallel 2 Directions 100%
(Item No. 89.12)
P-14-C-2 A-B-C-D SLIC-40 Transverse 2 Directions 100 %
Average 100 %
006600 P-14-L-4 Pipe LS far side A-B-C-D 9
SUC-40 Parallel 2 Directions 100%
(ftem No. 89.12)
P-14-C-2 A-B-C-D SUC-40 Transverse 2 Directions 100%
[
Average 100 %
A 006700 P-14-C-2 Pipe to Elbow A-B-C-D 9
SUC-40 Parallet 2 Directions 100%
(item No. B9.11)
A-B-C-D SUC-40 Transverse 2 Directions 100 %
Average 100%
006800 P-14-L-1-A Elbow LS long A-B-C-D 9
SUC-40 Parallel 2 Directions 100%
(item No. B9.12) side A-B-C-D SUC-40 Transverse 2 Directions 100 %
from P-14-C-2 Average 100%
1 006900 P-14-L-2-A Elbow LS short A-B-C-D 9
SLIC-40 Parallel 2 Directions 100 %
i (item No. 89.12) side A-B-C-D SLIC-40 Transverse 2 Directions 100 %
from P-14-C-2 Average 100%
l l
007000 P-14-L-1 Elbow LS long A-B-C-D 9
SUC-40 Parallel 2 Directions 100%
(item No. 89.12) side A-B-C-D SLIC-40 Transverse 2 Directions 100%
from P-14-C-1 Average 100 %
9 s
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SLIC-40 Parallel 2 Directions 100 %
l (Item No. B9.12) side A-B-C-D SLIC-40 Transverse 2 Directions 100%
l from P-14-C-1 Average 100 %
l l
007200 P-14-C-1 Elbow to reactor A-B-C-D 9
SLIC-40 Parallel 2 Directions 100 %
(Item No. 89.11) vessel extension A-B-C-D SLIC-40 Transverse 2 Directions 100 %
Average 100%
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