ML20005G236
| ML20005G236 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/05/1990 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9001180317 | |
| Download: ML20005G236 (12) | |
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- r Va tey Power Station SNppqport, PA 15077-0004 -
JoMN D.sitetn WI MW vie. ><.. ni woe
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January 5, 1990
.c U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC' 20555
Reference:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Response to ISI Program Request for Additional Information Gentlemen:
j This submittal-is in response to you'r request for additional i
information dated November 20, 1989, regarding the Beaver Valley Unit No.
2 Inservice Inspection Program.
The following includes i
i the NRC questions and our responses to each.
Enclosed are pages to be inserted into the BV-2 ISI Program which was submitted on August 11, 1989.
ouestion A:
Provide isometric drawings showing the piping welds and 1
supports that Section XI of the ASME Code requires to be examined during the.first 10-year interval.
These drawings, j
along with' the weld listing provided in the August 11, 1989 submittal, will permit the staff to determine'if the extent.of ISI examinations meets the applicable Code requirements.
Resoonse:
j A
complete set of - marked-up' drawings (approximately 500 drawings) were' submitted to the NRC-in June, 1988.
Based on recent conversations with Mr.. George Johnson of your staff, he will attempt to= locate these drawings and it is not necessary j
at this time to provide another set.
We will provide-additional information if required following your review.of these drawings.
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Benvar VallGy Power StGtion, Unit No. 2 Docket No. 50-412, License No. NPF-73 Response to ISI Program Request for Additional Information Page 2 Ouestion B:
Paragraph 10 CFR
- 50. 55a (b) (2) (iv) requires that ASME Code Class 2
piping welds in the Residual Heat Removal (RHR),
Emergency Core Cooling (ECC),
and Containment Heat Removal (CHR) systems shall be examined.
These systems should not be completely exempted from inservice volumetric examination based on Section XI exclusion criteria contained in IWC-1220.
From the information submitted in the August 11, 1989 submittal, the staff has not identified any CHR welds receiving ISI examinations during the first 10-year inspection interval.
Verify that the CHR system has not been completely exempted from ISI examinations and that a
representative sample of welds in this system will receive examination during the first 10-year inspection interval.
l Resoonse:
The Containment Heat Removal Systems at Beaver Valley are considered the Recirculation Spray System and the Quench Spray i
System.
Representative samples from each of these systems have been scheduled for examination during this inspection interval.
Question C:
i Relief Requests BV2-B3.140-1 and BV2-B8.20-1:
Both of these requests for relief reference attached drawings, which are blank pages indicating Westinghouse proprietary drawings. -The August 11, 1989 cover letter states that these two drawings will be transmitted to the NRC under a separate cover letter.
These drawings are required in order for the staff to evaluate the relief requests and determine if an impracticality _ exists.
Response
This item was discussed with Mr. George Johnson and agreement was reached that the subject drawings would'be acceptable to the NRC if the dimensions were removed from the Westinghouse proprietary drawings.
This also removes the proprietary nature of the drawings based on documentation from the Westinghouse Electric Corporation.
Therefore, please find enclosed the drawings supporting the referenced relief requests.
These drawings should be inserted in their respective locations in the ISI Program for completeness.
j
B cvar Valloy Pow 3r Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Response to ISI Program Request for Additional Infa nation Page 3 Question D:
Relief request BV2-B3.120-1 (Pressurizer Nozzle Inside Radius Sections) and Relief Request BV2-B3.140-1 (Steam Generator Nozzle Inside Radius Sections):
The Licensee has requested total relief from volumetric examination of the Clacs 1
Pressurizer and Steam Generator nozzle inside radius sections.
Although the Licensee may not have confidence in this examination for determining the condition of the subject components, it has not supplied enough information to establish that the code-required volumetric examination is impractical to perform.
If relief is to be considered, sufficient technical justification demonstrating impracticality must be provided.
What attempts have been made to obtain construction
- drawings, select transducers, and-perform the Code-required volumetric examination of the nozzle inner radius sections?
If the full Code-required volumetric examination cannot be completed, describe a
"best cffort" volumetric examination that could be performed.
j Resnonse:
Relief Request BV2-B3.120-1:
Since our submittal of this relief
- request, we have evaluated specialized techniques (as was committed to in DV2-B3.120-1) and have determined that with newly purchased qualification / calibration blocks combined I
with specialized search units and procedures, the required i
examinations can be performed.
We, therefore, withdraw this relief request from our program.
This has been noted on the enclosed Relief Request Index page II-1.
Please insert this page in place of the existing page in the BV-2 ISI Program.
Relief Request BV2-B3.140-1:
Ultrasonic (UT) examination of the Steam Generator Nozzle Inner Radius Section is considered totally impractical due to the conditions noted in the original submittal.
The impracticality of performing UT s
examinations from the outside surface of the channel head was 1
demonstrated during pre-service examination for the following reasons:
l 1.
The as-cast surface does not permit consistent coupling, i
The search unit movement is also obstructed by insulation attachment pads.
1 2.
A calibration standard is not available to encompass the l
constantly changing metal
- path, contact surface l
curvature, and the calibration reflector.
The only i
meaningful qualification / calibration standard envisioned would be an actual channel head of the same design with calibration reflectors installed in the Code-required j
volume.
BacvGr Valloy Powar Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Response to ISI Program Request for Additional Information Page 4 Based on the above, a "best-effort" examination would not be sufficiently meaningful to justify the radiation dose associated with this examination.
The remote visual examination proposed as an alternative has provided high-resolution video images of the Inside Radius surfaces.
Our earlier submittal did not mention that we had attempted to conduct this examination during pre-service examinations.
Based on our conversation with Mr. George Johnson, the fact that we attempted this examination during our pre-service examination effort provides sufficient additional information to address.this question.
Ouestion E:
Relief Request BV2-C1.10-3 (Recirculation Spray Pump - Shell Circumferential Welds) and Relief Request BV2-C6.10 (Recirculation Spray Pump Pump Casing Welds):
Please provide clarification with regard to why welds 2RSS-P21A-W-5, l
l
-9,
-10,
~17,
-18, and -19,oin Relief Request BV2-C1.10-3,_ are l
considered by the Licensee to be Class 2
vessel welds requiring volumetric examination, while welds 2RSS-P21A-W-11,
-12,
-13,
-15,
-16,
-21,
-23,
-24, and -25 in Relief Request BV2-C6.10-1, are considered by the Licensee to be Class 2 pump casing welds requiring surface examination.
l l
Response
-9,
-10,
-17,
-18, and
-19, were j
mistakenly categorized as C1.10.
These welds are Class 2 Pump l
Casing Welds (C6.10).
Therefore, these welds have been added to Relief Request BV2-C6.10-1, Rev.
1.
Replacement pages are l
located in the Enclosure.
Relief request BV2-C1.10-3 is hereby withdrawn from the Program.
These changes are included on the Relief Request Index page II-1 in the Enclosure.
Ouestion F:
Relief Request BV2-B9.31-1:
Examination Category B-J, Item B9.31, requires both 100% surface and volumetric examinations of Class 1
branch connection welds NPS 4-inch or larger.
Confirm the relief is being requested for a partial volumetric examination only and that the Code-required surface examination will be performed.
Resoonse:
It is confirmed that relief is requested for a
partial volumetric examination only and that the Code-required surface-examination will be performed.
I
Betv0r Vclloy Powcr Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Response to ISI Program Request for Additional Information Page 5 i
Ouestion G:
Relief Request BV2-C3.30-1:
Provide an estimate of the percentage of the Code-required surface examination that can and will be performed on the subject charging pump integrally welded attachments during the first 10-year inspection intertid -
Respo_ngg Seventy-seven percent (77%)
of each weld, 2CHS-P21A-WS-1 and
-WS-2, can be examined and will be examined during this interval.
If you have any questions regarding this submittal, please contact me or members of my staff.
i Very truly yours, I
fr;.
D. Sieber Wice President Nuclear Group 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) i I
L i
ENCLOSURE Includes:
Relief Request Index, page II-1 Relief Request BV2-C6.10-1, Rev. 1 (3 pages)
Drawing for Relief Request BV2-B3.140-1 Drawing for Relief Request BV2-B8.20-1 Instructions:
The following changes to the BV-2 ISI Program submitted on i
August 11,
- 1989, should be made utilizing the pages in this enclosure:
1.
Replace Relief Request Index, page II-1 2.
Replace Relief Request BV2-C6.10-1, Rev. 0 3.
Insert drawing for Relief Request BV2-B3.140-1 4.
Insert drawing for Relief Request BV2-BC.20-1 l
_ _ _ __ _ __ _ __- - a
2TYPP-1 Page II-1 Rev. 1 RFLTEF REQUEST INDEX RFLIEF REDUEST NO.
CQtPONQE EDT.
DV2-B2.11-1 Pressurizer Circ Weld 2IKS* PRE-C-1 0
BV2-B2.12-1 Pressurizer Lorg Weld 2RCS* PRE-Ir6 0
BV2-B3.100-1 Reactor Vessel Nozzle Inside Radius Sections O
BV2-B3.110-1 PItssurizer Nozzle-to-Vessel Weld 2RG* PRE 21-N-09 0
BV2-B3.120-1 Pressurizer Nozzle Inside Radius Sections (WIIHWAWN)
NA l
BV2-B3.140-1 Steam Generators Nozzle Inside Radius Sections O
BV2-B5.70-1 Steam Generator Nozzle-to-Safe Erd Butt Welds -
0 BV2-B8.20-1 Pressurizer Support Skirt Weld 2RCS* PRE 21-C-8 0
1 1
DV2-B9.11-1 Pressum Retainirq Welds 1
BV2-B9.31-1 Pressure Retaining Welds O
BV2-B12.10-1 RG Punps Casing Welds and Internal Surfaces O
BV2-B12.50-1 Class 1 Valve Bodies O
BV2-C1.10-1 Reactor Coolant Filter and Seal Water Heat Excharger 0
Shell Circ Welds BV2-C1.10-2 Regen Heat Exchangers Shell Circ Welds O
BV2-C1.10-3 Recirc Spray Punp Shell Circ Welds (WrIHORAWN)
NA BV2-C1.20-1 Non-Regen Heat Exchanger Head Cire Weld 2GS*E22-W-1 0
)
BV2-C1.20-2 Residual Heat Exchanger Head Circ Weld 2RHS*E21A-W-2 0
BV2-C1.20-3 Seal Water Heat Exchanger and Reactor Coolant-0 Filter Head Cire Welds BV2-C1.20-4 Volume Control Tank Head Circ Weld 2 GS*TK22-W-2 0
BV2-C1.20-5 Seal Water Filter Head Circ Weld 2GS*FIK24A-W-2 0
BV2-C1.30-1 Recirc Spray Cooler '1bbesheet-to-Shell Weld 0
2RSS*E21A-W-11 BV2-C2.21-1 Residual Heat Exchanger Nozzle-to-Shell Welds-0 2RHS*E21A-W-3 and -4 BV2-C2.21-2 Seal Water Filter Nozzle-to-Shell Welds 0
q 2 GS*FLT24A-W-3 and -4
)
BV2-C2.22-1 Steam Generator Main Steam ard Feedwater Nozzle 0
l Inside Radius Sections l
BV2-C3.20-1 Piping Integrally Welded Attachments O
BV2-C3.30-1 Charging Pumps Integrally Welded Attachments 0
BV2-C3.30-2 Recirc Spray Pump Integrally Welded Attachment 0
2RSS*P21A-WS-2 BV2-CS.11-1 Pressure Retaining Welds O
BV2-C5.21-1 Pressure Retainirq Welds 0
Bv2-Cs.10-1 Recirc Spray Pump Casing Welds 1
BV2-IWF-1 Equipment Supports 0
BV2-IWF-2 Piping Supports 1
)
IUQUESNE LIGfT CIMPANY Beaver Valley Power Station Unit No.2 Ra m REQUEST NO. BV2-C6.10-1. Rev. 1 Cmnonent Recirculation Spray Emp (2RSS*P21A) - PLmp Casing Welds (see list below).
Drawirn No.
RSSP21 R0 Section XI Reauirement (83S83)
(
Item C6.10 (IWC-2500-1, Category C-G) requires surface examination.
Basis for Relief Volumetric examination of the required volume is limited due to the following:
Scan Percentage Weld No.
Direction of Exam Cmoleted Interferirn Condition 2RSS-P21A-W-5 0'
0%
Weld configuratioygussets 45' Axial 50%
Weld configuratioygussets 45' Circ.
10%
Weld configuratioy gussets 2RSS-P21A-W-9 0'
0%
Weld configuratioygussets 45' Axial 50%
Weld configuratioygussets 45' Cire 10%
Weld configuratioygussets 2RSS-P21A-W-10 0'
0%
Weld configuratioy gussets 45' Axial 50%
Weld configuratioygussetr 45' cire.
10%
Weld configuratioygussets 2RSS-P21A-W-17 0'
0%
Weld configuratioygussets 45' Axial 50%
Weld configuratioy gussets 45' Circ 10%
Weld configuration / gussets 2RSS-P21A-W-18 0'
0%
Weld configuratioy gussets 45' Axial 50%
Weld configuratioygussets 45' Circ.
10%
Weld configuratioygussets 2RSS-P21A-W-19 0*
0%
Weld configuration 45' Axial 50%
Weld configuration 45' Circ 10%
Weld configuration
m Page No. 2 Relief Roquest No. DV2-C6.10-1, Rev.1 Basis for Pelief - Limited Exam Weld No.
Percent Examined Interferirn Condition 2RSS*P21A-W-11 0%
Inamalble due to concrete floor sleeve.
2RSS*P21A-W-12 0%
Inammible due to concre^w floor sleeve.
2RSS*P21A-W-13 0%
Inaccessible due to c.uhd.e floor sleeve.
2RSS*P21A-W-15 0%
Inamaible due to concmte floor sleeve.
2RSS*P21A-W-16 20%
Weld continues into floor sleeve.
2RSS*P21A-W-21 0%
Inammible due to being in punp sunp.
2RSS*P21A-W-23 0%
Inaccessible due to being in punp sunp.
2RSS*P21A-W-24 0%
Inaccessible due to being in punp sunp.
2RSS*P21A-W-25 0%
Inamelble due to being in punp j
sunp.
l I
Altermtive Examination l
Perform volumatric examination on a m aible area to-the maxinum extent g
practical. Perform Vr-2 during each inspection period.
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