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{{#Wiki_filter:;,~ | {{#Wiki_filter:;,~ | ||
Q | Q | ||
.fd 9,. | |||
Be ver VaHey Power Station Stuppmgport, PA 15077-0004 - | Be ver VaHey Power Station Stuppmgport, PA 15077-0004 - | ||
; CN. Nic.. o,.o, March 13, 1990 U. S. Nuclear Regulatory Commission Attn: | |||
U. S. Nuclear Regulatory Commission | Document Control Desk m | ||
Washington, DC. 20555 | |||
==Reference:== | ==Reference:== | ||
Beaver Valley Power Station, Unit.No. 2 Docket No. 50-412, License No. NPF-73 Correction to Unit No. 2 Ten Year ISI Program; Relief Request BV2-C6.10-1 Gentlemen: | Beaver Valley Power Station, Unit.No. 2 Docket No. 50-412, License No. NPF-73 Correction to Unit No. 2 Ten Year ISI Program; Relief Request BV2-C6.10-1 Gentlemen: | ||
This submittal forwards a correction to the Beaver Valley Unit No. 2 First Ten Year Inservice Inspection Program (Rev. 1). | This submittal forwards a correction to the Beaver Valley Unit No. 2 First Ten Year Inservice Inspection Program (Rev. 1). | ||
Specifically, relief request BV2-C6.10-1, Rev. 1 was submitted on January: 5, | Specifically, relief request BV2-C6.10-1, Rev. 1 was submitted on January: 5, 1990, in response to your request for additional information dated November 20, 1989. | ||
should have used the term surface examination. | Upon additional in-house review it was determined that the referenced relief request incorrectly included reference:to volumetric examination in the Basis for' Relief and Alternative Examination. | ||
These two parts of the relief request should have used the term surface examination. | |||
l-Additionally,-we have also included a revised Page II-1,-Relief | 1 Please discard relief' request BV2-C6.10-1 Rev. | ||
Eaggpst Index, which should replace the existing Page II-1 in the | 1, (pages 1 and 2) | ||
H L | |||
L | presently contained in the Unit No. 2 Inservice Insoection Ten Year Plan for the First Insoection Interval (Rev. 1) and insert the attached two pages in their place. | ||
l-Additionally,-we have also included a revised Page II-1,-Relief Eaggpst Index, which should replace the existing Page II-1 in the above referenced program. | |||
(p, . D . Sieber Wice President Nuclear Group l | If you have.any questions regarding this revision, please contact me or members of my staff. | ||
L Sincerely, l | |||
(p,. D. Sieber Wice President Nuclear Group l | |||
l | l | ||
[ | [ | ||
Mr. R. Saunders_ (VEPCO) | cc: | ||
Mr. J. | |||
Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr. | |||
P. Tam, Sr. Project Manager | |||
( | |||
Mr. R. Saunders_ (VEPCO) | |||
, $k I | |||
9003280087 900313 k) | |||
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PDR ADOCK 05000412 | |||
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DUQUESNE LIGff (IMPANY. | |||
Recirculation Spray Iunp (2RSS*P21A) - Punp Casing Welds' (see list below) . | Beaver Valley Power Station Unit No.2 | ||
Drawirn No. . | - REIJEF REQUEST NO. BV2-C6.10-1, Rev. 2 Ca@cnent v | ||
Recirculation Spray Iunp (2RSS*P21A) - Punp Casing Welds' (see list below). | |||
Drawirn No.. | |||
- RSSP21 RO i | |||
Section XI Reauirement' (83S83) | Section XI Reauirement' (83S83) | ||
Item C6.10 (IWC-2500-1, Category C-G) requires surface examination. | Item C6.10 (IWC-2500-1, Category C-G) requires surface examination. | ||
' Basis for Relief Surface examination of the required area is limited due to the following: | |||
1 Scan | 1 Scan Ittroentage Weld No. | ||
. DirectioD of Exam cmoleted Interferirn Condition d | |||
'0*-- | |||
0% | |||
Weld configuratioygussets | |||
2RSS-P22A-W-18 | -2RSS-P21A-W 45' Axial 50% | ||
Weld configuratioWgussets 45'' Circ. | |||
10% | |||
Weld configuration / gussets- | |||
.2RSS-P21A-W-9 0' | |||
0% | |||
Weld configuratioygussets 45' Axial 50% | |||
Wald configuratioygussets 45* Circ 10% | |||
Weld configuratioygussets 2RSS-P21A-W O' 0% | |||
Weld configuratioygussets 45' Axial 50% | |||
Weld configuratioygussets 45' Circ. | |||
10% | |||
Weld configuratioygussets i | |||
2RSS-P21A-W-17 0* | |||
0% | |||
Wald configuration / gussets | |||
- 45' Axial | |||
-50% | |||
Weld-configuration / gussets 45' Circ-10% | |||
Weld configuratioy gussets. | |||
+ | |||
2RSS-P22A-W-18 0* | |||
0% | |||
Weld configuratioygussets 45* Axial 50% | |||
Weld configuratioygussets 45' cire. | |||
10% | |||
Weld configuration / gussets 2RSS-P21A-W-19 0' | |||
0% | |||
Weld configuration 45' Axial 50% | |||
Ueld configuration 45' Circ 10% | |||
Weld configuration | |||
) | |||
1 | 1 | ||
.a. | |||
Page No. 2 | |||
; Relief Roquest No. BV2-C6.10-1, Rev. 2 r< | |||
2RSS*P21A W-12 | Basis for Relief - Limited Exam Weld No. | ||
2RSS*P21A-W-13 | Permnt Damined Interferirn Condition 2RSS*P21A-W-11 0% | ||
L | Inaccessible due to concrete floor sleeve. | ||
2RSS*P21A-W-16 | 2RSS*P21A W-12 0% | ||
2RSS*P21A-W-21 | Inaccessible due to concrete floor sleeve. | ||
H | 2RSS*P21A-W-13 0% | ||
Inaccessibic due to concrete floor sleeve. | |||
sunp. | L 2RSS*P21A-W-15 0% | ||
2RSS*P21A-W-25 | Inaccessible due to concrete floor sleeve. | ||
Alternative Examination Perform- | 2RSS*P21A-W-16 20% | ||
Weld continues Into floor sleeve. | |||
2RSS*P21A-W-21 0%- | |||
Inaccessible due to being in punp sump. | |||
H 2RSS*P21A-W-23 0% | |||
Inaccessible due to being in'punp suny. | |||
2RSS*P21A-W-24 0% ' | |||
Inaccessible due to being in punp sunp. | |||
2RSS*P21A-W-25 0% | |||
Ina-c:ible due to being in punp sunp. | |||
Alternative Examination Perform-surface examimtion on ao ssible area to the, mximum extent l | |||
practical.. Perform VI-2 during each inspection period. | |||
j i | |||
. ( | |||
1 | 1 | ||
.I e | |||
am mm. | |||
1 | 1 | ||
,a ys a | |||
a | 2TYPP-1c Page II-1 l | ||
2TYPP-1c | ~Rev. 1 l | ||
BELTEF REEUEST INDEX l | |||
BV2-B2.11-1 | 5 | ||
< RELIEF j | |||
REDUEST NO. | |||
CC2GONENT BEY. | |||
BV2-B2.11-1 Pmssurizer Circ Weld 2RCS* PRE-C-1 0 | |||
g i | |||
BV2-B2.12-1 Pressurizer Iag Weld 2RCE* PRE-Ie6 0 | |||
BV2-B3.100-1 Ranctor V - 1 Nozzle Inside Radius Sections O | |||
BV2-B3.110-1 Pressurizer Nozzle-to-Vessel Weld 2RCS* PRE 21-N-09 0 | |||
1 BV2-B3.120-1 Pressurizer Nozzle Inside Radius Sections (WTIH mAWN) | |||
NA BV2-B3.140-1 Steam Generators Nozzle Inside Radius Sections O | |||
BV2-B5.70-1 Steam Generator Nozzle-to-Safe End Butt Welds O | |||
BV2-B8.20-1 Pressurizer Support Skirt Weld 2RCS* PRE 21-C-8 0 | |||
BV2-B9.11-1 Pressure Retaining Welds 1 | |||
BV2-B9.31-1 Pressure Retaining Welds O | |||
BV2-B12.10 RCS Punps Casirg Welds arxl Internal Surfaces O | |||
BV2-B12.50-1 Class 1 Valve Bodies O | |||
BV2-C1.10-1 Reactor Coolant Filter and Seal Water Heat Exchanger 0 | |||
Shell Cire Welds L | |||
BV2-C1.10-2 Regen Heat Exchangers Shell Circ Welds O | |||
BV2-C1.10-3 Recire Spray Punp Shell Circ Welds (WTIETAWN) | |||
NA BV2-C1.20-1 Non-Regen Heat Excharger Head Circ Weld 2CHS*E22-W-1 | |||
'0 BV2-C1.20-2 Residual Heat Excharger Head Circ Weld 2RHS*E21A-W-2 0 | |||
BV2-C1.20-3 Seal Water Heat Excharger and Reactor Coolant 0 | |||
' Filter Head Circ Welds BV2-C1.20 Volume Control Tank Head Circ Weld 2CES*TK22-W-2 0 | |||
l BV2-C1.20-5 Seal Water Filter Head Circ Weld 2CES*FLT24A-W-2 0 | |||
1 L | |||
BV2-C1.30-1 Recire Spray Cooler Tubesheet-to-Shell Weld 0 | |||
2RSS*E21A-W-11 BV2-C2.21-1 Residual Heat Exchanger Nozzle-to-Shell Welds 0 | |||
2RilS*E21A-W-3 and -4 BV2-C2.21-2 Seal Water Filter Nozzle-to-Shell Welds 0 | |||
2WS*FIH'24A-W-3 and -4 BV2-C2.22-1 Steam Generator Main Steam arxl Feedwater Nozzle 0 | |||
Inside Radius Sections BV2-C3.20-1 Piping Integrally Welded Attachments O | |||
BV2-C3.30-1 Charging Punps Integrally Welded Attachments 0 | |||
BV2-C3.30-2 Recirc Spray Punp Integrally Welded Attachment 0 | |||
2RSS*P21A-WS-2 BV2-C5.11-1 Pressure Retaining Welds 0 | |||
BV2-CS.21-1 Pressure Retaining Welds O | |||
BV2-C6.10-1 Recire Spray Pump Casing Welds 2 | |||
BV2-IWF-1 Equipnent Supports 0 | |||
-BV2-IWF-2 Pipirq Supports 1 | |||
-}} | |||
Latest revision as of 03:00, 21 December 2024
| ML20012D580 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/13/1990 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9003280087 | |
| Download: ML20012D580 (4) | |
Text
- ,~
Q
.fd 9,.
Be ver VaHey Power Station Stuppmgport, PA 15077-0004 -
- CN. Nic.. o,.o, March 13, 1990 U. S. Nuclear Regulatory Commission Attn
Document Control Desk m
Washington, DC. 20555
Reference:
Beaver Valley Power Station, Unit.No. 2 Docket No. 50-412, License No. NPF-73 Correction to Unit No. 2 Ten Year ISI Program; Relief Request BV2-C6.10-1 Gentlemen:
This submittal forwards a correction to the Beaver Valley Unit No. 2 First Ten Year Inservice Inspection Program (Rev. 1).
Specifically, relief request BV2-C6.10-1, Rev. 1 was submitted on January: 5, 1990, in response to your request for additional information dated November 20, 1989.
Upon additional in-house review it was determined that the referenced relief request incorrectly included reference:to volumetric examination in the Basis for' Relief and Alternative Examination.
These two parts of the relief request should have used the term surface examination.
1 Please discard relief' request BV2-C6.10-1 Rev.
1, (pages 1 and 2)
H L
presently contained in the Unit No. 2 Inservice Insoection Ten Year Plan for the First Insoection Interval (Rev. 1) and insert the attached two pages in their place.
l-Additionally,-we have also included a revised Page II-1,-Relief Eaggpst Index, which should replace the existing Page II-1 in the above referenced program.
If you have.any questions regarding this revision, please contact me or members of my staff.
L Sincerely, l
(p,. D. Sieber Wice President Nuclear Group l
l
[
cc:
Mr. J.
Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr.
P. Tam, Sr. Project Manager
(
Mr. R. Saunders_ (VEPCO)
, $k I
9003280087 900313 k)
( g\\\\
PDR ADOCK 05000412
^i
\\\\
A.
PDC R
p
- o C
6 %
DUQUESNE LIGff (IMPANY.
Beaver Valley Power Station Unit No.2
- REIJEF REQUEST NO. BV2-C6.10-1, Rev. 2 Ca@cnent v
Recirculation Spray Iunp (2RSS*P21A) - Punp Casing Welds' (see list below).
Drawirn No..
- RSSP21 RO i
Section XI Reauirement' (83S83)
Item C6.10 (IWC-2500-1, Category C-G) requires surface examination.
' Basis for Relief Surface examination of the required area is limited due to the following:
1 Scan Ittroentage Weld No.
. DirectioD of Exam cmoleted Interferirn Condition d
'0*--
0%
Weld configuratioygussets
-2RSS-P21A-W 45' Axial 50%
Weld configuratioWgussets 45 Circ.
10%
Weld configuration / gussets-
.2RSS-P21A-W-9 0'
0%
Weld configuratioygussets 45' Axial 50%
Wald configuratioygussets 45* Circ 10%
Weld configuratioygussets 2RSS-P21A-W O' 0%
Weld configuratioygussets 45' Axial 50%
Weld configuratioygussets 45' Circ.
10%
Weld configuratioygussets i
0%
Wald configuration / gussets
- 45' Axial
-50%
Weld-configuration / gussets 45' Circ-10%
Weld configuratioy gussets.
+
0%
Weld configuratioygussets 45* Axial 50%
Weld configuratioygussets 45' cire.
10%
Weld configuration / gussets 2RSS-P21A-W-19 0'
0%
Weld configuration 45' Axial 50%
Ueld configuration 45' Circ 10%
Weld configuration
)
1
.a.
Page No. 2
- Relief Roquest No. BV2-C6.10-1, Rev. 2 r<
Basis for Relief - Limited Exam Weld No.
Permnt Damined Interferirn Condition 2RSS*P21A-W-11 0%
Inaccessible due to concrete floor sleeve.
2RSS*P21A W-12 0%
Inaccessible due to concrete floor sleeve.
2RSS*P21A-W-13 0%
Inaccessibic due to concrete floor sleeve.
L 2RSS*P21A-W-15 0%
Inaccessible due to concrete floor sleeve.
2RSS*P21A-W-16 20%
Weld continues Into floor sleeve.
2RSS*P21A-W-21 0%-
Inaccessible due to being in punp sump.
H 2RSS*P21A-W-23 0%
Inaccessible due to being in'punp suny.
2RSS*P21A-W-24 0% '
Inaccessible due to being in punp sunp.
2RSS*P21A-W-25 0%
Ina-c:ible due to being in punp sunp.
Alternative Examination Perform-surface examimtion on ao ssible area to the, mximum extent l
practical.. Perform VI-2 during each inspection period.
j i
. (
1
.I e
am mm.
1
,a ys a
2TYPP-1c Page II-1 l
~Rev. 1 l
BELTEF REEUEST INDEX l
5
< RELIEF j
REDUEST NO.
CC2GONENT BEY.
BV2-B2.11-1 Pmssurizer Circ Weld 2RCS* PRE-C-1 0
g i
BV2-B2.12-1 Pressurizer Iag Weld 2RCE* PRE-Ie6 0
BV2-B3.100-1 Ranctor V - 1 Nozzle Inside Radius Sections O
BV2-B3.110-1 Pressurizer Nozzle-to-Vessel Weld 2RCS* PRE 21-N-09 0
1 BV2-B3.120-1 Pressurizer Nozzle Inside Radius Sections (WTIH mAWN)
NA BV2-B3.140-1 Steam Generators Nozzle Inside Radius Sections O
BV2-B5.70-1 Steam Generator Nozzle-to-Safe End Butt Welds O
BV2-B8.20-1 Pressurizer Support Skirt Weld 2RCS* PRE 21-C-8 0
BV2-B9.11-1 Pressure Retaining Welds 1
BV2-B9.31-1 Pressure Retaining Welds O
BV2-B12.10 RCS Punps Casirg Welds arxl Internal Surfaces O
BV2-B12.50-1 Class 1 Valve Bodies O
BV2-C1.10-1 Reactor Coolant Filter and Seal Water Heat Exchanger 0
Shell Cire Welds L
BV2-C1.10-2 Regen Heat Exchangers Shell Circ Welds O
BV2-C1.10-3 Recire Spray Punp Shell Circ Welds (WTIETAWN)
NA BV2-C1.20-1 Non-Regen Heat Excharger Head Circ Weld 2CHS*E22-W-1
'0 BV2-C1.20-2 Residual Heat Excharger Head Circ Weld 2RHS*E21A-W-2 0
BV2-C1.20-3 Seal Water Heat Excharger and Reactor Coolant 0
' Filter Head Circ Welds BV2-C1.20 Volume Control Tank Head Circ Weld 2CES*TK22-W-2 0
l BV2-C1.20-5 Seal Water Filter Head Circ Weld 2CES*FLT24A-W-2 0
1 L
BV2-C1.30-1 Recire Spray Cooler Tubesheet-to-Shell Weld 0
2RSS*E21A-W-11 BV2-C2.21-1 Residual Heat Exchanger Nozzle-to-Shell Welds 0
2RilS*E21A-W-3 and -4 BV2-C2.21-2 Seal Water Filter Nozzle-to-Shell Welds 0
2WS*FIH'24A-W-3 and -4 BV2-C2.22-1 Steam Generator Main Steam arxl Feedwater Nozzle 0
Inside Radius Sections BV2-C3.20-1 Piping Integrally Welded Attachments O
BV2-C3.30-1 Charging Punps Integrally Welded Attachments 0
BV2-C3.30-2 Recirc Spray Punp Integrally Welded Attachment 0
2RSS*P21A-WS-2 BV2-C5.11-1 Pressure Retaining Welds 0
BV2-CS.21-1 Pressure Retaining Welds O
BV2-C6.10-1 Recire Spray Pump Casing Welds 2
BV2-IWF-1 Equipnent Supports 0
-BV2-IWF-2 Pipirq Supports 1
-