ML20215C010
| ML20215C010 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/24/1986 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20215C008 | List: |
| References | |
| NUDOCS 8610100033 | |
| Download: ML20215C010 (26) | |
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1 of 26 i
VERMONT YANKEE NUCLEAR POWER CORPORATION 1985 INSERVICE INSPECTION
SUMMARY
REPORT i
SEPTEMBER 21, 1985 THROUGH JULY 2, 1986 i
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2 of 26 TABLE OF CONTENTS 1.
Introduction 2.
Examination Methods 3.
Evaluation of Data 4.
Examination Results 5.
Conclusions Attachment A:
Form NIS-1, Owners' Data Report for Inservice Inspections Attachment B:
Form NIS Additional Inspections and Results for the Recirc/RHR Pipe Replacement Project Attachment C:
Form NIS Additional Inspections and Results for the Seismic Reanalysis Project
r 3 of 26 VERMONT YANKEE NUCLEAR POWER CORPORATION 1985 INSERVICE INSPECTION
SUMMARY
PEPORT SEPTEMBER 21, 1985 THROUGH JULY 2, 1986
-1.
INTRODUCTION The attached Form NIS-1, " Owners' Data Report for Inservice Inspection" describes the inservice inspections performed during 1985-1986 at the Vermont Yankee Nuclear Power Station, Vernon, Vermont. The examinations performed were those of the second outage of the first period of the second 10-year interval. The non-destructive examination procedures used for inservice inspection were in accordance with the ASME Boiler and Pressure Vessel Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components" 1980 edition with addenda through and including the winter of 1980 as required by 10 CFR 50.55A(g)(2) for Vermont Yankee. The areas subject to examination and the methods used were in accordance with the Vermont Yankee Inservice Inspection Program and the plant Technical Specifications.
This report summarizes the components examined, the types of examination, the non-conforming conditions noted, and the corrective actions taken. Ultrasonic, radiographic, liquid penetrant, magnetic particle and visual examination techniques were employed to perform the required examinations. Additionally, inspections in accordance with Section XI were performed in concert with the replacement of Reactor Recirculation System piping and the Seismic Reanalysis Project. These inspections and results are summarized on the NIS-1 Form in Attachments B and C.respec-tively.
2.
EXAMINATION METHODS Non-destructive examinations were performed in accordance with the procedures contained in the Yankee Atomic Electric Company, Engineering Guidelines, Book III, " Inservice Inspection NDE Procedures", or vendor procedures reviewed and approved by Yankee Atomic Electric Company.
The examination procedures were reviewed and approved by personnel qualified to SNT-TC-1A Level III. These procedures conform to the requirements of ASME Section XI (W'80) and the referenced portions of ASME Section V (W'80) The inservice examinations were performed and evaluated by personnel qualified to SNT-TC-1A as modified by Section XI.
The procedures used for these examinations are listed in Section 10 of the NIS-1 Form attachments.
3.
EVALUATION OF DATA The examination results were reviewed at the site by personnel qualified to at least SNT-TC-1A Level II.
Indications were evaluated to the acceptance standards defined in Section XI.
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EXAMINATION RESULTS j
A list of the examinations that were performed is contained in Section 10 of the NIS-1 Form. The detailed examination data along with the calibration records, procedures, equipment certifications and personnel certifications are maintained at the plant site. Upon completion of the corrective actions detailed in Section 12 of the NIS-1, there were no remaicing unacceptable conditions. No continuing or follow-up items resulted from mandatory examinations performed under ASME Section XI.
Augmented examination of core spray safe-end welds resulted in repair and will require follow-up examina-tions. See Section 12 of Attachment 2 for details.
5.
CONCLUSIONS 2
The inspections accomplished during the 1985/86 Inservice Inspection consisted of all scheduled inspections not in conflict with the extensive reactor recirculation system piping replacement.
Those inspections which were unavailable have been rescheduled in accordance with Vermont Yankee-Inservice Inspection Program and are to be evaluated in light of the inspec-tions accomplished as a result of the recirculation piping replacement.
In addition, the scheduled inspections of Period 1 Intervc1 2 exceed 1/3 of the total number of inspections required.
Revision 9 to the V.Y. I.S.I. Program will reflect those items required to meet V.Y.'s remaining Period 2 commitments, i
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r-5 of 26 ATTACHMENT A FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 7. Components Inspected Manufacturer National Component or or Installer State or Board Appurtenance-Manufacturer or Installer Serial No.
Province No.
No.
Safety Class 1 Reactor Vessel 6 CRD Bottom Head Penetrations Chicago Bridae and Iron B4698 N/A 1 Vessel Level Inst.
Nozzle Welds Chicaao Bridae and Iron B4698 N/A 2 Vessel Closure Studs Chicago Bridae and Iron B4698 N/A 24 Vessel Closure Nuts Chicaao Bridae and Iron B4698 N/A 25 Vessel Closure Washers, Bushinas Chicago Bridae and Iron B4698 N/A Safety Class 1 Pipina i
11 Pipe Welds Ebasco N/A N/A
[
97 Support l
Components Ebasco N/A N/A i
6 of 26 ATTACHMENT A FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 1. Owner Vermont Yankee Nuclear Power Corp, R.D. 5, Box 169, Ferry Road, Brattleboro,~VT 05301
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 7. Components Inspected Manufacturer National Component or or Installer State or Board Appurtenance Manufacturer or Installer Serial No.
Province No.
No.
Safety Class 2 Vessels 1 Shell Weld SWECO N/A N/A 1 Nozzle to Shell Weld SWECO N/A N/A 1 Welded Attachment SWECO N/A N/A Safety Class 2 Pipina 34 Pipe Welds Ebasco N/A N/A 7 Welded Attachments Ebasco N/A N/A 5 Welded Attachments (IWF Portion)
Ebasco N/A N/A 25 Non-Welded
_ Support Components Ebasco N/A N/A 1 Pump Welded Attachments Ebasco N/A N/A 1 Pump Welded Attach.
(IWF Portion)
Ebasco N/A N/A I
7 of 26 ATTACHMENT A FORM NIS-1 (back) 8.
Examination Dates 9/21/85 to 7/2/86 9.
Inspection Interval from pf17/83 to 6/17/93
- 10. Abstract of Examinations.
Include a list of examinations and a statement concerning status of work required for current interval.
See Pages 8
Through 12
- 11. Abstract of Conditions Noted See Page 13
- 12. Abstract of Corrective Measures Recommended and Taken See Page 14 We certify that the statements made in this report are correct and the examinations cnd corrective measures taken conform to the rules of the ASME Code,Section XI.
Vermont Yankee Nuclear M%
198 Signed Power Corporation by(
Date Certificate of Authorization No. (if applicable) xpiration Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid conmission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of Vermont and employed by Hartford Steam Boiler I+I Co. of Hartford, Connecticut have inspected the components described in'this Owners' Data Report during the period 21 September, '85 to 2 July, '86, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective meas-ures described in this Owners' Data Report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or proper-tv damage or a loss of ary kind arising from or connected with this inspection.
Date),
t4 M 198 Commissions NA boda
$630 A, / a tt s w
Idspector's Signature National Board, State, Province and No.
8 of 26 ATTACHMENT A FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules n=========================================================================================
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None n=========================================================================================
- 10. Abstract of Examination A.
Nondestructive Examinations C9tegory Component Description
- of Items Examination Status B-E CRD Bottom Head Penetrations 6
VIS/VT-2 100% Complete B-E Vessel Level Instrument Nozzle Welds 1
VIS/VT-2 100% Complete B-G-1 RPV Closure Studs 2
VOL/SUR 100% Complete B-G-1 RPV Closure Head Nuts 24 SUR 100% Complete B-G-1 RPV Closure Washers 25 VIS/VT-1 100% Complete B-J Circumferential and Main Steam 3
- VT-2 100% Complete Longitudinal Pipe Main Steam 2
VOL/SUR/VIS 100% Complete Welds RHR 2
VOL/SUR/VIS 100% Complete HPCI Main Steam 4
VOL/SUR/VIS 100% Complete BL-2 Pump Casing Internal Recirculation
- 2 VIS/VT-3 100% Complete Surfaces BM-2 Valve Body Internal Recirculation
- 4 VIS/VT-3 100% Complete Surfaces RHR
- 6 VIS/VT-3 100% Complete F-B Linear Type Main Steam 24 VIS/VT-3 100% Complete Supports Feedwater 22 VIS/VT-3 100% Complete Core Spray 2
VIS/VT-3 100% Complete HPCI 4
VIS/VT-3 100% Complete RCIC 3
VIS/VT-3 100% Complete F-C Component Standard Main Steam 20 VIS/VT-4 100% Complete Supports Feedwater 16 VIS/VT-4 100% Complete Core Spray 2
VIS/VT-4 100% Complete HPCI 2
VIS/VT-4 100% Complete RCIC 2
VIS/VT-4 100% Complete C-A Shell Circumferential RHR Heat 1
VOL 100% Complete Welds Exchanger B C-B Nozzle to Shell Weld RHR Heat 1
SUR/VIS 100% Complete Exchanger B
- Exceeds requirement per code, however examination fulfills relief request.
E 9 of 26 ATTACHMENT A FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 10. Abstract of Examination A.
Nondestructive Examinations Category Component Description
- of Items Examination Status C-C Integrally Welded RHR Heat 1
SUR 100% Complete Attachments Exchanger A C-F Circumferential RHR 10 SUR/VIS 100% Complete Butt Welds C-G Circumferential HPCI Main Steam 3
VOL/SUR/VIS 100% Complete Butt Welds HPCI 2
VOL/SUR/VIS 100% Complete HPCI 1
SUR/VIS 100% Complete HPCI Booster Pump to Main Pump 1
SUR/VIS 100% Complete Core Spray 1
VOL/SUR/VIS 100% Complete RHR 13 SUR/VIS 100% Complete CRD 2
SUR/VIS 100% Complete RCIC 1
SUR/VIS 100% Complete C-C Integrally Welded RHR 1
SUR/VIS 100% Complete Attachments RHR 1
SUR/VIS 100% Complete RHR 4
VIS 100% Complete Core Spray 1
SUR/VIS 100% Complete F-A IWF Portion of HPCI 1
VIS/VT-3 100% Complete F-B Welded Attachments RHR 3
VIS/VT-3 100% Complete F-C Core Spray 1
VIS/VT-3 100% Complete F-A Non-Welded Support HPCI 1
VIS/VT-3 100% Complete F-B Components HPCI 1
VIS/VT-3, VT-4 100% Complete F-C HPCI Main Steam i
VIS/VT-3 100% Complete CRD 2
VIS/VT-3 100% Complete RHR 11 VIS/VT-3 100% Complete RHR 1
VIS/VT-3, VT-4 100% Complete RCIC 1
VIS/VT-3, VT-4 100% Complete Core Spray 5
VIS/VT-3 100% Complete Core Spray 1
VIS/VT-3, VT-4 100% Complete Core Spray 1
VIS/VT-4 100% Complete
10 of 26 ATTACHMENT A FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 10. Abstract of Examination A.
Nondestructive Examinations Category Component Description
- of Items Examination Status C-C Pump Integrally RHR 1
VIS/VT-3 100% Complete Welded Attachments F-A IWF Portion of Core Spray 1
VIS/VT-3 100% Complete F-B Welded Attachments F-C to Pumps
.-----------__-.__-.____________________u
11 of 26 ATTACHMENT A FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules 1, Owner Vermont Yankee Nuclear Power Corp, R.D. 5, Box 169, Ferry Road, Brattleboro, VT 05301
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 10. Abstract of Examination B.
Hydrostatic Tests 1.
A Class 1 Hydrostatic Pressure Test, in accordance with IWB-5222, was performed and accepted prior to plant startup.
NO. OF CATEGORY ITEM COMPONENT ITEMS METHOD STATUS BP 15.11 Reactor Pressure Vessel 1
VIS/VT-2 100% Comp.
BP 15.51 Class 1 Piping All VIS/VT-2 100% Comp.
BP 15.61 Class 1 Pumps All VIS/VT-2 100% Comp.
BP 15.71 Class 1 Valves All VIS/VT-2 100% Comp.
2.
New Safety Class 2 tubing for North / South Post Accident Sampling System reroute was pneumatically tested and accepted following installation (Ref. EDCR 85-01).
3.
A Class 2 Hydrostatic Pressure Test, in accordance with IWC-5222, for the Condensate Storage Tank was performed and accepted prior to plant startup.
12 of 26 ATTAC'iMENT A FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 10. Abstract of Examination C.
Ultrasonic Examination Procedures 1.
YA-UT-1, Rev. 3, Ultrasonic Examination - General Requirements.
2.
YA-UT-7, Rev. 2, Ultrasonic Examination of Boltir.g 3.
YA-UT-9, Rev. 2, EN#85-4-VY, Ultrasonic Examination of Piping Ferritic Welds.
4.
YA-UT-19, Rev. O, Component Profile Procedure Using the Pulse Echo Ultrasonic Technique 5.
YA-UT-116, Rev. O, Ultrasonic Examination of Full Penetration Welds 6.
YA-UT-112, Rev. 1, Thickness Measurement by Ultrasonics D.
Liquid Penetrant Examination Procedures 1.
YA-PE-2, Rev. 5, EN#85-1-VY, Liquid Penetrant Examination E.
Maanetic Particle Examination Procedures 1.
YA-MP-111, Rev. O, Magnetic Particle Examination (1980 ASME Code)
F.
Visual Examination Procedures 1.
YA-VT-11, Rev. 1, EN#85-2-VY, Visual Examination.
G.
Radioaraphic Examination Procedure 1.
YA-RT-111, Rev. 1, Radiographic Examination H.
Repair Precedure 1.
V.Y.G.P. 4026, Rev. O, Pressure Boundary Repair 4
i 13 of 26 ATTACHMENT A FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/3C/72
- 6. National Board Number for Unit None
- 11. Abstract of Conditions Noted A.
Category C-G 1.
Surface examination of S13 on HPCI Main Steam Line 4B revealed surface indications.
Indications were determined to be construction related.
Therefore, no additional inspections were performed.
2.
Surface examination of F6A on RHR Line 6 revealed surface indications.
Indications were determined to be construction related. Therefore, no additional inspections were performed.
B.
Cateaory F-A, F-B, F-C 1.
Visual examination of CS HD 86C on RHR line 20 revealed snubber binding on pipe clamp. As required by IWF-2430, additional components were inspected with no rejectable conditions discovered.
2.
Visual Examination of HD 26 on RHR line 40 revealed undercuts on weld. As required by IWF-2430, additional components were inspected with no rejectable conditions discovered.
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14 of 26 ATTACHMENT A 1
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules 2
1
'1. Owner Vermont Yankee Nuclear Power Corp, R.D. 5, Box 169, Ferry Road, Brattleboro, VT l
05301 3
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None 12.
Abstract of Corrective Measures Recommended and Taken A.
Cateaory C-G 1.
Weld S13 on the HPCI Main Steam Line was repaired utilizing V.Y.0.P. 4026.
2.
Weld F6A on the RHR Line 6 was repaired utilizing V.Y.O.P. 4026.
B.
Category F-A, F-B, F-C 1.
The snubber binding on CS HD 86C was adjusted, visually re inspected nnd accepted prior to plant startup.
2.
The undercuts on HD 26 were repaired by removing stress risers and grind > ;
existing welds.
A surface exam was then performed and accepted prior f; p!w.).
startup.
F L
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15 of 26 ATTACHMENT B FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None I
- 7. Components Inspected Manufacturer National Component or or Installer State or Board Appurtenance Manufacturer or Installer Serial No.
Province No.
No.
Reactor Vessel Manufacturer: Hitachi, LTD Recirculation Installer: Morrison -
1
_ System Safe-Ends Knudsen EDCR 85-1 N/A N/A Recirculation Manufacturer: Hitachi, LTD.
System Installer: Morrison-Knudsen EDCR 85-1 N/A N/A Residual Heat Manufacturer: Hitachi, LTD.
_Removat System Installer: Morrison-Knudsen EDCR 85-1 N/A N/A Reactor Water cleanup System Morrison-Knudsen EDCR 85-1 N/A N/A Reactor Bldg. Closed Coolina Water System Morrison-Knudsen EDCR 85-1 N/A N/A Reactor Vessel Core Spray System Safe-Ends Mercury Co.
EDCR 85-1 N/A N/A 4
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N 16 of 26 ATTACHMENT B FORM NIS-1 (back) 8.
Examination Dates 9/21/85 to 7/2/86 9.
Inspection Interval from to
- Examinations reported under this attachment were as provided for in Section XI paragraph IWA A500(a).
Interval dates are not applicable to these examinations.
- 10. Abstract of Examinations.
Include a list of examinations and a statement concerning status of work required for current interval.
See Pages 17 Through 19
- 11. Abstract of Conditions Noted See Page 20
- 12. Abstract of Corrective Measures Recommended and Taken See Page 21 We certify that the statements made in this report are correct and the examinations End corrective measures taken conform to the rules of the ASME Code,Section XI.
Vermont Yankee Nuclear I
Date.I d, R 4,.
19 8 Signed Power Corporation by,b_
Certificate of Authorization No. (if applicable)
Txpiration Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of Vermont and employed by Hartford Steam Boiler I+I Co. of Hartford, Connecticut have inspected the components described in this Owners' Data Report during the period 21 Sept.,'85 to 2 July,'86, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures des-cribed in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective meas-ures described in this Owners' Data Report.
Furthermore, neither the Inspector nor his' employer shall be liable in any mainer for any personal injury or proper-ty damage or a loss of any kind arising fram or connected with this inspection.
Date c74/
19M 0nxo. A. }ladsAa/
Commissions.VlA Y 0 ed u b 03 O Idspector's Signature National Board, State, Province and No.
17 of 26 ATTACHMENT B FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1
4, Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 10. Abstract of Examination The examinations reported in this summary are those required of Vermont Yankee through the plant's commitments to A.S.M.E. Code Section XI 1980 Edition with addenda through and including the winter 1980 addenda and plant technical specifications. This report documents only those examinations required by paragraphs IWA 4400 and IWA 4500 as performed subsequent to piping replacement activities detailed in Engineering Design Change (EDCR) 85-1.
These examinations were performed outside the scope of revision 8 of the Vermont Yankee Inservice Inspection Program (VYISIP).
Examinations requir ed to comply with the VYISIP are abstracted in a separate report.
NO. OF CATE00RY ITEM COMPONENT ITEMS METHOD STATUS BF B5.10 RPV Nozzle 12 VOL/ SURF /VIS 100% Comp.
To SE Weld BF B5.50 RHR Piping i
VOL/ SURF /VIS 100% Comp.
BG2 B7.50 Recirc. Sys. 48 VOL/ SURF /VIS 100% Comp.
BJ B9.11 Recire. Sys. 68 VOL/ SURF /VIS 100% Comp.
RHR Sys.
32 VOL/ SURF /VIS RWCU Sys.
10 VOL/ SURF /VIS CS Sys.
2 VOL/ SURF /VIS BJ B9.21 RWCU 1
VOL/ SURF /VIS 100% Comp.
BJ 89.31 Recirc Sys.
6 VOL/ SURF /VIS 100% Comp.
RHR Sys.
1 VOL/ SURF /VIS BJ 89.32 Recirc. Sys.
1 VOL/ SURF /VIS 100% Comp.
i 18 of 26 ATTACHMENT B FORM NIS-1 OWNERS' OATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
I 05301 l
- 2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, Vermoat 05354
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 7. Components Inspected NO. OF CATEGORY ITEM COMPONENT ITEMS METH00 STATUS BJ 89.40 Recire. Sys.
20 Vis.
100% Comp.
RWCU Sys.
4 Surf.
RBCCW Sys.
14 BK1 810.10 Recirc.Sys.
23 Surf.
100% Comp.
100% Comp.
Recirc. Sys.
12 CS Sys.
2 BP B15.51 Recirc., RHR All Vis.
100% Comp.
RWCU Piping BP B15.61 Recire. Paps.
2 Vis.
100% Comp.
BP B15.71 Recire. Vivs.
6 Vis.
100% Comp.
RHR Vivs.
6 RWCU Vivs.
2 FB F1,F2, Recire. Sys.
48 Vis.
100% Comp.
F3 RHR Sys.
5 RWCU Sys.
15 FC F4 Recirc. Sys.
30 Vis.
100% Comp.
RHR Sys.
3 RWCU Sys.
2
19 of 26 ATTACHMENT B FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 10. Abstract of Examination C.
Ultrasonic Examination Procedures 1.
YA-UT-1, Rev. 3, Ultrasonic Examination - General Requirements.
2.
YA-UT-9, Rev. 2, EN#85-4-VY, Ultrasonic Examination of Piping Ferritic Welds.
3.
YA-UT-19, Rev. O, Component Profile Procedure Using the Pulse Echo Ultrasonic Technique 4.
YA-UT-85-1-1, Ultrasonic Examination of Dissimilar Metal Welds 5.
YA-UT-85-1-2, Straight Beam Method for Weld Overlay Clad Bond 6.
YA-UT-85-1-3, Angle Beam Method for Weld Overlay Clad Flaw Indications 7.
ITL-UT-A-4 Revs. 1, 2, 3, P-Scan Angle Beam Examination D.
Liquid Penetrant Examination Procedures 1.
YA-PE-2, Rev. 5, EN#85-1-VY, Liquid Penetrant Examination 2.
FQP9.2 Rev. 2, Liquid Penetrant Examination (Morrison-Knudsen)
E.
Magnetic Particle Examination Procedures 1.
YA-MP-111, Rev. O, Magnetic Particle Examination (1980 ASME Code)
F.
Visual Examination Procedures 1.
YA-VT-11, Rev. 1, EN#85-2-VY, Visual Examination.
G.
Radioaraphic Examination Procedure 1.
YA-RT-111, Rev. 1, Radiographic Examination 2.
FQP9.4, Rev. 2, 1 Radiographic Examination (Morrison-Knudsen)
H.
Repair Procedure 1.
V.Y.0.P. 4026, Rev. O, Pressure Boundary Repair a
(
l
20 of 26 ATTACHMENT B FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS
.As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 11. Examination of the following items revealed conditions as noted.
Items not identified below were found acceptable to the rules of Section XI of the ASME Code.
A.
The two core spray system safe-end to nozzle welds (cr.tegory BF, Item 85.10) were examined both ultrasonically and with liquid penetrant techniques. Both the A and B nozzles were found by ultrasonics to contain axially oriented planar flaws which could not be verified as smaller than the Code allowable size.
Liquid penetrant indications in the weld required volume of both nozzle to safe-end welds, exceeding the Code allowable limits were also detected.
B.
A short linear liquid penetrant indication was detected on the existing valve casting, within the weld required volume of weld RHR 32-5 (category B), Item B9.11). The indication exceeded the limits of the Code.
C.
Component supports were examined visually following installation, at several stages. Qualified examiners performed VT-3 and 4 examination prior to hydrostatic test, post hydrostatic test and to the maximum extent possible at rated pressure and temperature.
The pre and post hydrostatic test examinations resulted in minor adjustments to supports.
Documentation of final acceptance of all conditions is on file with all PSI data at V.Y.
The examinations at pressure and temperature resulted in one condition. Recirc pump support RR-17 was found in contact, restricted from movement with adjacent structural steel.
I 21 of 26-ATTACHMENT B FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
?
-2.
Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, Vermont 05354
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None l
- 12. The following corrective actions were taken in response to those items abstracted in section 11 of this attachment.
i A.
Both Core Spray safe-end to nozzle welds were repaired using weld overlay repair techniques. Detailed discussion of the repair is contained in EDCR 85-1 on file at Vermont Yankee. Overlays were preservice examined using both surface and volumetric (ultrasonic) examination techniques.
Liquid penetrant indications were removed with light surface conditioning (flapping) to the nozzle 0.D.
B.
The indicated area, adjacent to weld RHR 32-5 was repaired with light surface preparation (flapping). Base material reduction, in way of the indication was 4
minimal. Design wall thickness was maintained.
C.
Structural steel interfering with RR-17 was removed by grinding thereby allowing j
movement.
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22 of 26 ATTACHMENT C FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 7. Components Inspected Manufacturer National Component or or Installer State or Board Appurtenance Manufacturer or Installer Serial No.
Province No.
No.
SAFETY CLASS 1 1 Welded Attachment Mercury Company EDCR 84-402 N/A N/A 2 Non-welded Attachments Mercury Company EDCR 84-402 N/A N/A SAFETY CLASS 2 9 Welded Attachments Mercury Company EDCR 84-402 N/A N/A 118 Non-welded Attachments Mercury Company EDCR 84-402 N/A N/A f
23 of 26 ATTACHMENT C FORM NIS-1 (back) 8.
Examination Dates 9/21/85 to 7/2/86 9.
Inspection Interval from to
- Examinations reported under this attachment were as provided for in Section XI paragraph IWA 4500(a).
Interval dates are not applicable to these examinations.
- 10. Abstract of Examinations.
Include a list of examinations and a statement concerning status of work required for current interval.
See Page 24
- 11. Abstract of Conditions Noted See Page 25
- 12. Abstract of Corrective Measures Recommended and Taken See Page 26 We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASHE Code,Section XI.
Vermont Yankee Nuclear S, b M,.
19ff Signed Power Corporation by ' O- -A
.s8 Date 7
Certificate of Authorization No. (if applicable)
Expiration Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of _ Vermont and employed by Hartford Steam Boiler I+I Co. of Hartford, Connecticut have inspected the components described in this Owners' Data Report during the period 21 Sept.,'85 to 2 July,'86, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures des-cribed in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate, neither the Inspector nor his employer makes any warranty, exprecced or implied, concerning the examinations and corrective meas-ures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or proper-ty damage or a loss of any kind arising from or connected with this inspection.
Date
. ed.//
19 dd a
dw Commissions 9)a had d630 Wspector's Signature National Board, State, Province and No.
24 of 26 ATTACHMENT C FORM NIS-1 CWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
- 7. Components Inspected
==============================================================================
- 10. Abstract of Examination The examinations reported in this summary are those performed under Design Change EDCR 84-402 to upgrade VY baseplates in conformance to NRC I/E Bulletin 79-02.
All examina-tions reported in this attachment were performed through the plant's commitments to A.S.M.E. Code Section XI 1980 Edition with Addenda through and including the Winter 1980 Addenda. These examinations were performed outside the scope of Revision 8 of the Vermont Yankee Inservice Inspection Program (VYISIP) and those examinations required to comply with the VYISIP are abstracted in Attachment A.
CategorV Component Description
- of Items Examination Status F-A, F-B IWF Portion of Welded RHR 1
SURF, VIS 100% Complete F-C Attachments C-C Integrally Welded HPCI 1
VIS 100% Complete Attachments RHR 4
VIS 100% Complete RHR 2
SUR, VIS 100% Complete MS 1
SUR, VIS 100% Complete SLC 1
VIS 100% Complete F-A, F-8 Non-Welded RHR 49 VIS 100% Complete F-C Support Components CS 18 VIS 100% Complete HPCI 24 VIS 100% Complete RHR 1
SUR, VIS 100% Complete RCIC 3
VIS 100% Complete SGT 1
VIS 100% Complete i RCW 1
VIS 100% Complete RMISP 7
VIS 100% Complete RSW 1
VIS 100% Complete FDW 2
VIS 100% Complete MS 10 VIS 100% Complete HPCI 1
SUR, VIS 100% Complete
25 of 26 ATTACHMENT C FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules i
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
==============================================================================
- 11. Abstract of Conditions Noted The portion of those supports effected by the EDCR showed no supports as defective, however, 2 supports were noted to have inservice defects as follows:
A.
Cateaory C-C 1.
RHR hanger HD-36 on RHR 40 was found to have a bent rod.
B.
Category F-A, F-B, F-C d
1.
RHR hanger HD-1308 on RHR 3A was found to have gaps between the base plate and the concrete and spalled concrete around one anchor bolt.
4 i
l l
26 of 26 ATTACHMENT C FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 3. Plant Unit l'
- 4. Owner Certificate of Authorization (if required) None
- 5. Commercial Service Date 11/30/72
- 6. National Board Number for Unit None
=======================================================================.,=====
- 12. Abstract of Corrective Meapurcs Recommended and Taken A.
Catenary C-C 1.
The bent rod was eplaced, visually inspected and accepted. Additional sup-ports as required by IWF 2430 were inspected and are included in Item 10.
No further discrepancies were noted.
B.
Category F-A, F-8, F-C 1.
The base plate was removed, the grout repaired, and the base plates re-installed, visually inspected, and accepted. Additional supports as required by IWF 2430 were inspected and included in Item 10.
No further discrepancies were noted.