ML19259A773
| ML19259A773 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/04/1979 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML19259A764 | List: |
| References | |
| PROC-790104, NUDOCS 7901100281 | |
| Download: ML19259A773 (41) | |
Text
{{#Wiki_filter:. INSERVICE INSPECTION E WIINATION REPORT VERMONT YANKEE NUCLEAR POWER CORPORATION JULY 12, 1978 TilROUGli OCTOBER 7,1978 790110da9 /
PREFACE This report covers the inservice inspection of Vermont Yankee Nuclear Power Station during the period July 12, 1978 through Oc tobe r 7, 19 78. This period includes the 1978 refueling outage and the unscheduled shutdown of July 1, 1978. Included in this report is the Form NIS-1 as required by the provisions of ASME Section XI and a Summary Report of the examinations performed, conditions observed, and corrective measures taken. TABLE OF CONTENTS PAGE NIS-L OWNER'S DATA REPORT 1
SUMMARY
REPORT 27
1.0 INTRODUCTION
27 1.1 Examination Methods 27 1.2 Evaluation of Data 28 1.3 Examination of Results 28 2.0
SUMMARY
OF EXAMINATIONS 29 2.1 Reactor Vessel Data 29 2.2 Piping Data 32 2.3 Pumps 34 2.4 Valves 35 3.0 SYSTEM PRESSURE TEST 37
4.0 CONCLUSION
S 38 e FORA 1 NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASSIE Ccde Rules
- 1. Owner Vermont Yankee Nuclear Power Corp., 77 Crove St., Rutland. Vt. 05701 (Name and Address of Owner)
- 2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, Vt. 05354 (Name and Address of Plant)
- 3. Plant Unit 1 4. Owner Certificate of Authorization (if required) DPR-28
- 5. Commercial Service Date 11/30/72 6. National Board Number for Unit None
- 7. Components inspected Manufacturer Item Component or Manufacturer or Installer State or National Appurtenance or Installer Seria! No. Province No. Board No.
11 Vessel Seam 1 u n lae Chicano Bridee & Tron B-4698 NA NA 8 Nozzle to 2 Vessel Welds Chicano Bridce & Tron B 46o8 NA NA 9 LRD 3 Penetrations Chicano Bridee & Tron B-4698 NA NA 3 Nozzle to 4 Safe-end Welds Chicaco Bridee & Tren B 4698 NA NA 16 Vessel 5 Studs & Nuts Chicago Bridge & Tron B-4698 NA NA 2 Vessel Head 6 Patches - Chicago Bridee & Tron B-4698 NA NA 3 Piping Safe- per attached Isometrics 7 end Welds Ebasco NA NA NA per attact.ed Isometrics 8 87 Pioe Welds Ebasco NA NA NA per attached Isometrics 9 160 <T' Bol ts Ebasco NA NA NA 22 Supports / per attached Isometrics 10 Hangers Ebasco NA NA NA 11 3 >2" Bolts Bvron Jackson 671-S-1108 NA NA per attached Isometri;s 12 2 Valve Bodies Ebasco NA NA NA 32 Instrument 13 Lines Ebasco NA NA NA Note: Supplemer.tal sheets in form of lists, sketches. or drawings may be used provided (1) size is 8% in. x 11 in.. (2) information in items 1 through 6 on this data report is included on each sheet, and (3) eack sheet is numbered 2.11 the number of sheets is recor fed at the top of this form. This forrn (E00029) rray be obtained frorn the Order De;:t., ASVE, 345 E. 47th St., New York, N.Y. 10017
~ FORM NIS-1 (back)
- 8. Examination Dates I[12/IO to 10/7/7h 9. Inspection interval fromli /30 !72 to 11 ! ?n '?
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.
See attached Page 3.
- 11. Abstract of Conditions Noms See attached Page 5.
- 12. Abstract of Corrective Measures Recommended and Taken
~
See attached Page 5. We certify that the statements made in this report are correct and the examinations and corrective mea-sures taken conform to the rules of the ASMI' ode, Section XI, Summer 1975 Add nda and Sumner 1976 Appen x III for Piping Examination . jy
$ Signed f/K'in up t/b[ e i y W Date 19 '
M[V A [wner Plant Superinten Certificate of Authorization No. (if applicable) DPR-28 Expiration Date December 11. 2007 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 Co .v 4 , and employed by MJO 7t7 of
//7Er/' Cr e e have inspected the components described in this Owners' Data Report during the period 7// 2/ 7 < to /077 / 7?f . 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, Sum. 1975 Ad. & Sum. 1976 App. III for F Lping Ex.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personan injury or property damage or a loss of any kind arising from or connected with this inspection. , Date Tc A) . Od 19 79 d# C4
~
Wommissior.s 1 Bd. 3 National Board, State, Province and No. Inspector's Signatu're Page 2
- 1. Owner Vermont Yankee Nuclear Power Coro.. 77 Grove St.. Rutland. Vt. 05701 (Name and Address of Owner) 2.
Plant Vermont Yankee Nuclear Power Station. P.O. Box 157. Vernon. Vt.. 05354 (Name and Address of Plant)
- 3. Plant Unit 1 4. Owner Certificate of Authorization (if required)DPR-28
- 5. Commercial Service Date 11/30/72 6. National Board Number for Unit None
- 10. Abstract of Examinations Category No. o' Components Examined Examination Reactor B 6 Closure Head Meridional Welds UT 1 Closure Head Circumferential Weld UT 2 Vessel Longitudinal Welds UT C 1 IIcad to Flange Weld UT 1 Vessel to Flange Weld UT D 8 Nozzle to Vessel Welds UT 9 CRD Penetrations & CRD Pressure Ecundrary Welds VT F 3 Nozzle to Safe-end Welds UT, PT, VT G-1 16 Reactor Vessel Studs and Nuts UT, VT Corresponding Ligament Areas UT 16 Corresponding Bushings VT 32 Washers for Studs VT C-2 8 Flange Bolts and Corresponding Nuts VT I 2 Vessel Head Cladding Patches PT, VT Piping F 3 Safe-end Welds UT, PT, VT G-2 8 Flange Studs and Corresponding Nuts VT J 54 Piping Welds UT, VT 2 Piping Welds UT, PT, VT 2 Piping Welds VT, PT 29 Piping Welds PT 32 Instrument Lines VT K-1 2 Integrally Welded Supports VT, PT K-2 14 Ilangers and Supports VT Pumps G-1 8>2" Bolts VT K-1 2 Integrally Welded Supports UT, PT, VT 4 Integrally Welded Supports PT, VT Page 3 of 38
- 1. Owner Vermont Yankee Nuclear Power Corp.. 77 Crove St.. Rutland. Vt. 05701 (Name and Address of Owner)
- 2. Plant Vermont Yankee Nuclear Power Station. P.O. Box 157. Vernon. Vt_ 0535'.
(Name and Address of Owner)
- 3. Plant Unit 1 4. Owner Certificate of Authorization (if required;DPR-28
- 5. Commercial Service Date 11/20/72 6. National Board Number for Unit None
- 10. Abstract of Examinations (Cont'd)
Category No. of Components Examined Examination Valves C-2 146 Bolts and Corresponding Nuts (in place) VT M-2 2 Valve Bodies VT NOTES: 1. In piping, Category J, weld F3B on Line CS-4A and weld F3B on Line CS-4B were inaccessible on one side for ultrasonic examinations so liquid penetrant examinations were performed.
- 2. In piping, Category J, weld F4 on Line CS-4A and weld F4 on Line CS-4B were inaccessible for ultrasonic examinations so liquid penetrant examinations were performed.
- 3. All examination procedures are Yankee Atomic Procedures er.ept OP 4101 which is a Vermont Yankee Procedure.
Ultrasonic Examination Procedures YA-UT-1 Ultrasonic Examination - General Requirements YA-UT-2 Ultrasonic Examination of Vessels-Circumferential, Longitudinal, Meridional and Flange Welds YA-UT-4 Ultrasonic Examination of Vessels - Nozzle to Vessel Welds YA-UT-6 Ultrasonic E xamination of Flange Ligaments YA-UT-7 Ultrasonic E xamination of Volting YA-UT-8 Ultrasonic Examination of Reactor Closure Nuts YA-UT-9 Ultrasonic Examination of P iping - Ferritic Uelds YA-UT-10 Ultrasonic E xamination of P iping Autstenetic Welds YA-UT-ll Ult r,senic E xamination of P iping - Dissimilar Metal Welds YA-UT-14 Ult: asonic Examination of P iping - Base Material and Weld Heat Af fected Zones YA-UT-15 Ultrasonic Examinction of Piping - S traight Beam Method When Used for Weld and Heat Af fected Zone Examination Idquid Penet rant Examination Procedures YA-PE-2 Liquid Penetrant Examination Page 4 of 38
- 1. Owner Vernont Yankee Nuclear Power Coro.. 77 Grove St.. Rutland. Vt. 05701 (Name and Address of Owner)
- 2. Plant Vernont Yankee Nuclear Power Station. P.O. Box 157. Vernon. Vt. 05354 (Neme and Address of Plant)
- 3. Plant Unit 1 4. Owner Certificate of Authorization (if required DPR-28
- 5. Commercial Service Date 1 6. National Board Number for Unit None
- 10. Abstract of Examinations (Cont'd)
Visual Examination Procedures YA-VT-1 Visual Examination Procedure OP 4101, Rev. 7, RPV Operational Hydro Test
- 11. '.b s t rac t of Conditions Noted During ultrasonic examination of nozzle to vessel weld NSA an indication was noted and recorded. In addition, several indications were found on nozzle to vessel weld N2C and were recorded. During ultrasonic examination of Reactor Vessel Head Longitudinal welds, indications were noted and recorded for welds 31, B5 and B6.
During visual examinations of valves, several recordable conditions were noted. During inspection of valve bolting (in place) on Valve V2-65B, slight corrosion was noted and recorded. An inspection of valve bodies, internal, revealed slight corrosion on Valve V10-46A and slight corrosion and wear on Valve V2-96A. Liquid Penetrant Examination of weld F1 on the 2 inch CUW-19 line revealed a linear indication on the body of the tee. Visual and liquid penetrant examinations of integrally welded supports RR-80, RR-81 and RR-82 on recirculation pump P-18-1B revealed several indications on each of these supports. During visual examination of hanger CU-8 on the CUW-18 line it was noted that the hanger was loose at the clevis. Upon visual examination of support RHR-3, on the RHR A line, it was noted that a nut was missing from the pipe clamp bolting.
- 12. Abstract of Corrective Measures Rec >mmend,;. and Taken The indication found on nozzle to vessel weld NSA is a plate lamination and falls within the acceptance criteria as defined in IWB-3511.2, therefore there was no need for further evaluation or additional examinations. The reflectors on nozzle to vessel weld N2C v .e small in size with no length and displa- . no amplitudes that were recordable. All of the indications are acceptable.
Page 5 of 38
- 1. Owner Vermont Yankee Nuclear Power Corp., 77 Grove St., Rutland, Vt. 05701 (Name and Address of Owner)
- 2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, Vt. 05354 (Name and Address of Plant)
- 3. Plant Unit ___1 /. Owner Certificate of Authorization (if required DPR-28
- 5. Commercial Service Datell/30/72 6. National Board Number for Unit Nonc _
- 12. Abstreut of Corrective Measures Recommended and Taken (Cont'd)
The indications noted on Reactor Vessel Head Welds B1, R5 and B6 all fell within acceptance criteria. No further examinations or evaluations are necessary. The slight corrosion noted on Valves V2-65B and V10-46A and the slight corrosion and wear on Valve V2-96A were determined not to cause any deterioration of the components on degradation of the systems. No further evaluations or examinations are decmed necessary. Indications found on weld F1 (CUW-19 line) and integrally welded supports RR-80, RR-81 and RR-82 were repair ground in accordance with Vermont Yankee Operating Procedures 6023 Rev. 4. Repairs were initiated and performed in accordance with MR 78-976 for weld F1 and MR 78-977 for integrally welded supports. The bolting for the clevis on hanger CU-8 was tightened an. the nut was replaced on support RilR-3. NOTE: The referenced repair procedures and maintenance requests are filed at the plant site with the 1978 ISI paperwork. Page 6 of 38
- 1. Owner Vermont Ya akee Nuclea r Power Corp. , 77 Grove St.. Rutland. Vt. 05701 (Name and Address of Owner)
- 2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernen, Vt. 05354 (Name and Address of Plant)
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (if required) DPR-28
. Commercial Service Date _11130/ 72 6. National Board Number for Unit None IS0 METRICS Not2: Visual examination performed on bolting of circled valves with t3e exception of valve V2-96A on the Feedwater "B" Line and valve V10-46A on the RHR "C" Line. A visual examination of the valve body was performed on these two valves.
Page 7 of 38
LEGEND ? O ner Vermont Yankee Nuclear Power Corp. 77 Crove St. Rutland. Vt. 05701 6 SPRING HANGAR CR SUPPCRT (Name anJ AJJresa of Omner)
& I G W LDED S# RING MANGAR OR SUNRY
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- 5. Commercal Servar Date ll / 3 0 / 7 2 6. N ational BoarJ Number for Unit
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I I. Owner Vermont Yankee Nuclear Power Corp. 77 Crove St. Rutland. Vt. 05701 (Name asd AJJress of Owner)
- 2. Plan Vermont Yankee Nuclear Power Station, P.O. Box 157. Vernon. Vt. 05354 (Name and AdJress of Plant)
- 3. Plant Unit '
- 4. Owner Certificate of Authoeimation (if required) CPR-28 p- (4) 5. Commercial 5ervwe Date 11/30/726.Nanonal soarJ Number for Unia NO"'
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- 1. O ner Vermont Yankee Nuclearl ower Corp., 77 Crove St. Rutland. Yt. 05701 (Name anJ AJJrcu of Omner) 2 Plant vermont Yankee Nuclear Power Station. P.O. Box 157 Vernon. Ve. 05354 (Name and AJJrea of Manil 3 Plane Uner I DPR-28 4 o.ne, cerg,r,c,i, at a uc h.,,,,,,,, g,g ,,q,,,,q ,
, S. Commerc:al Serv ><e Date _11))'),#12 6. National Board Number for Unit None F2A
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- 1. Owner _ Vermont Yankee Nuclear Power Corp., 77 Crove St. Rutland. Vt. 05701 (Name and AJJress of Owner)
- 2. Plan Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon. Vt. 05354
, (Name and AdJtess of Plant)
- 3. Plant Unit I 4. Owner Certificate nf Authonration tef requsred) DPR-28 FSA-SA j
g5a.5g 5. Commercial 5ervice Dare 11/30/776 Neuonal Board Number for Unit None j - --
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- 1. Owner Vermont Yankee Nuclear Povet Corp., 77 Crove St . Rutland. Vt. ^5701
'.Narne anJ AJ jress of Owner)
- 2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 15 7. Vernon. Vt . 05354 (Name and AJJress of Plant)
- 3. Plane Uns 1
- 4. Owner Ceresfacate of Authorinaric7 (if requered) DPR-29
- 5. Commercial Service Date 11/ 30/ 72 6. National Board Number for Unit None e7 RHR-33 m
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3 Owner Ve rmorit Yar.kee Nuclear Pcwer Corp. 77 Crove St. Rutland. Vt. M701 (Name and AJJtess of Owneer
- 2. Pf ant Ve rrx.n t Yankee Nuclear Power Station, P.O. Box 157. Vernon. Vt. % 3 5_A (Name and AJJress of Plann 3 Pians L'n:t I 4 0.ner cered.casc o( Aurno..aanon (.f reqvweJr UIR-26 RHR-30 C""*"'" 5""" D *
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A ~ A P. -
- 1. Owner Vermont Yankee Nuclear Power Corp., 77 Crowe St. Rutland. Yt. 05701 (Name and AJJeess of Owner)
- 2. Plant Vermont Yankee Nuclea: Power Station, P.O. Box 157. Vernon. Vt. 053$4 Mame anJ AJJress of Plant)
I 4. Owner Certificate of Authorisation (if required) DPR-28
- 3. Plant Unit None
!. Comme.ast Service Date 11130/72 6. National Board Number for Unit N5A NSASE F6A
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- 1. Owne, _ Vermont Yankee Nuclear Power Corp., 77 Crove St.
(Name and AJJecss of Owner) Rutland. Yt. 0570L
- 2. Plan Vermont Yankee Nuclear Power Station. P.O. Box 157. Vernon. vt. 05354 (Name and AJJtess of Pland 3 Plane Unit 1 4 Owner Certificate of Authorisaren (.f required DPR-28 S. Commercial Service Dave _11/ 30 / 7 2 6. National BoarJ Number for Uner None FS8 FSC .
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LEGEND
- l. Owner Vermont Yankee Nuclear Power Corp. 77 Crove 9t. Rutland. Vt. 05701 & SPRING HANGAR OR SUPPORT (Name anJ AJJress of Owners
- 2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157. Vernon. Vt. 05354 , ,
(Name and AJJress of Plant) e INTEGR ALLY wtLCEO RIGIO hah 0AR, SUPPORT OR RESTR AINT
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SUMMARY
REPORT
1.0 INTRODUCTION
This report describes the in- vice inspections performed during 1978 at the Vermont Yankee Nuclear Power Station, Vernon, Vermont. The examinations performed are those of the first outage of the second period of the first 10 year interval. The non-destructive examination procedures used for inservice inspection were in accordance with the ASME Boiler and Pressure Vessel Code, Section X'.,
" Rules f or Inservice Inspection oi Nuclear Reactor Coolant Systems,"
as referenced by the plant technical specifications. The areas subject to examination and the methods used were in accordance with the plant technical specifications. Pressure beundary welds, and integrally welded supports and adjacent base metal were examined as required by Section XI to the extent that the system design and non-destructive testing technology permitted. All limited scans are described in the data. This report summarizes the areas examined, the type of examinations, the results of the test data, evaluations and repairs. Manual ultrasonic testing techniques were employed in conjunction with visual and liquid penetrant examinations. 1.1 Examination Methods All 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." The examination procedures were reviewed and Page 27 of 38
approved by personnel qualified to SNT-TC-1A Level III. These procedures conform to the requirements of ASME Section XI (S-75) and the referenced parts of ASME Section V (S'75) except where these editions are in conflict with the technical specification requirements, i.e., for Category B-F and B-J, Section XI S' 76 Addenda Appendix III and appropriate Acceptance Criteria. The inservice examinations were performed and evalurted by personnel qualified to the 1975 Edition of SNT-TC-1A. The procedures used for these examinations are listed in Section 10 of the NIS-1 form. 1.2 Evaluation of Data The examination results were reviewed at the site by personnel qualified to SNT-IC-1A Level III. Indications were evaluated to the acceptance standards as defined in the Vermont Yankee Nuclear Power Station Technical Specifications. 1.3 Examination Results Summaries of all the examinations that were performed are contained in Sections 2, 3, and 4 of this report. The detailed examination dr ta along with the calibration record, procedures, equipment certifications and personnel qualifications are maintained at the plant site. Page 28 of 38
2.0 SLTtARY OF EXAMINATIONS This section summarizes the inservice inspection data for the 1978 ref ueling outage at Vermont Yankee Nuclear Power Station. For clarity, the results are summarized in accordance with the examination categories of Section XI. 2.1 Reactor Vessel Data Category B-B - Longitudinal and Circumferential Reactor Vessel Welds Closure head circumferential weld AB was examined ultrasonically from 4" left of weld Bl to 9" past Bl. No recordable indications were found. Closure head meridional welds, B1, B-2, B-3, B-4, B-5, B-6 were examined ultrasonically. The examination volume was defined by a surface distance of 5 inches. Recordable indications were found with straight beam (0 ) techniques o o in welds B1, B5 and C. Angle beam scans of 45 and 60 shear wave produced no indications. The indications were evaluated as spot type in the base metal adjacent to the weld. There was no through wall depth or measurable size. The amplitudes did not exceed 100% DAC. Longitudinal welds D1 and D2 on the reactor vessel upper shell course were ultrasonically examined. Examination of D1 started 3" below weld CD and proceeded 1.5' toward weld DE. Examination of D2 started at weld CD and proceeded 1.5' toward weld DE. No recordable indications were found. Page 29 of 38
Category B-C - llead to Flange and Vessel to Flange Welds The closure head to flange weld, BC, was examined ultrasonically o o o starting at weld BS (270 Az) and continuing 90 to 0 , a distance of 14 feet. No recordable indications were found. The vessel to flange weld, CD, was examined ultrasonically starting at Azmith 180 ,14 feet to approximately 260 Azmith. The scan was complete on the )teer side of the weld, but limited to 2" of base metal on the upper side by the refueling bellows. No recordable indications were found. Category B-D - Nozzle to Vessel Welds Ultrasonic examinations were performed on Reactor Vessel Nozzles. The nozzles examined were: Rec irc Inlet - N-2C, N-2D, N-2G Main Steam - N-3A, N-3B Core Spray - N-5A, N-5B CRD Return - N9 The nozzle to vessel weld was examined during this outage. Nozzle inner radii will be examined during the 1979 ou tage. Visual examination was performed on: (1) the accessible portions of the thermal sleeve of nozzle N-9 with underwater video cameras; and (2) nine (9) CRD penetrations and CRD pressure boundary welds during leak test. Page 30 of 38
Nozzle N-2C had recordable indications found with the straight beam scan on the vessel base metal adjacent to the weld. No indication exceeded 100% DAC. No indications were o o found using 45 and 60 shear techniques. All N-2C indications were spot type with no through wall depth. Nozzle N-5A had a plate lamination adjacent to the weld of approximately 4 square inches. This was determined to be acceptable per lWB-3511.2 and Table IWB-3511.3. No recordable indications were found in N-2D, N-3A, N-3B, N-5B, N-9, and CRD penetrations. Category B-F - Nozzle to Safe End Welds Reactor recire. nozzle to safe end welds N2C-SE, N2D-SE and N2G-SE were examined through ultrasonic, visual and liquid
,enetrant methods. No recordable indications were found.
Category B-G.1 - Closure Studs Sixteen (16) Closure Studs were examined ultrasonically and visually. There were no recordable indications. Category B-G.1 - Closure Nuts Sixteen (16) Closure Nuts were examined visually and ultrasonically. No recordable indications were found. Category B-G.1 - Closure Washers and Bushings Sixteen (16) sets of closure washers and corresponding bushings were visually examined. No recordable indications were found. Category B-G.1 - Liagments between Threaded Stud Holes The flange ligaments between stud holes 12-1^, 20-22, 36-39, 50-53, 58-60 were ultrasonically examined. No recordable indications were found. Page 31 of 38
Category C Pressure Retaining Bolting Less Than 2" Diameter Visual examination was performed on eight (8) bolts and corresponding nuts or the (RHR-19) head spray flange. No recordable indications were found. Category B-I-l - Closure Head Cladding Two (2) Closure Head patches were examined with liquid penetrant and visual methods. No recordable indications were found. 2.2 Piping Data Category F - Safe End Welds Ultrasonic, visual and liquid penetrant examinatione were performed on the three (3) safe-end welds listed below:
- a. RilR piping Line "A" - Weld 8
- b. RHR piping line "B" - Weld 10
- c. Head Spray Piping - Line RHR-18-2 Weld F4A No recordable indications were found.
Category G Pressure Retaining Bolting Less Than 2" Diameter Visual examination was perforned on bolting of flange B on Recirculation Loop "B" Line. Eight (8) studs and corresponding nuts were examined. No recordable indications were found. Category .1 - Circumferential Pipe Welds Visual examination was performed during system leak test on thirty-two (32) instrument lines, in accordance with re ference drawings Gl9126 7-R + and Gl91167-R15. No recordable indications were found. Page 32 of 38
C. 3 _te gory J - Socket Welds Twenty-nine (29) socket welds were examined by liquid penetrant methods on the following systems:
- a. Reactor Cleanup Piping (CCW-19) - 18 Welds
- b. Reactor Cleanup Piping (CUW-400)- 11 Welds Examination of weld F1 on the 2" CCW-19 line revealed a linear indication en the body of the tee. The indication was due to original manufacturing. It was repair ground in accordance with Vernont Yankee Operating Procedure 6023 Rev. 4 (MR78-976).
No recordable indications were found. Category J - Circt:ferential Pipe Welds - 8" Core Spray Line Visual and liquid penetrant examination was performed on two (2) welds of the CS-4B and CS-4A core spray line. Weld F4 on Core Spray "A" and weld F4 on Core Spray "B" were examined with no recordable indications. Category J - Circunferential and Longitudinal Welds Fif ty-four (54) piping welds were visually and ultrasonically examined on the following systems:
- a. RHR-18-2 - 1
- b. RHR-19 - 14
- c. Main Steam MS-7A and FG-7B - 8
- d. Recire. Riscrs (N2C, D, G) - 12
- e. Core Spray "A" and "B" - 14
- f. Reactor Cleanup (CUW-18) - 3
- g. Core Spray ASB - Welds F3B - 2 Also liquid penetrant exam.
No Recordable indications were found. Page 33 of 38
Category K Integrally Welded Supports Two (2) integrally welded supports RR-27 (Recire. Loop "A") and RHR-9 (Head Spray Piping, RHR-19) were examined with visual and liquid penetrant methods. No recordable indications were found. Category K Hangers and Supports Fourteen (14) hangers and supports were visually examined in the f ollowing systems :
- a. Recire. Loop "A" -5
- b. Main Steam -
- c. Feedwa t e r " A" -2
- d. RHR Line "A" - 1
- e. Reactor Cleanup Line - 2
- f. CRD Retu rn -1
- g. Head Spray Line - 1 Examination revealed hanger CU-8 on the CUW-18 line was loose at the clevis. Also, it was noted that a nut was missing from the pipe clamp bolting on RHR-3 support (RHR A Line).
The bolting for the clevis on hanger CU-8 was tightened and the nut was replaced on support RH R-3. 2.3 Pumps Category C-l - Pressure Retaining Bolting Less Than 2" Diameter All bonnet bolting on Recirculating Pump P-18-18 was exanined visually. No reportable indications were found. Page 34 of 38
Category K Integrally Welded Supports Two (2) integrally welded supports, RR80 and RR 81, on pump P-18-1B were examined through ultrasonic, visual and liquid penetrant methods. Visual and liquid penetrant examination of support RR82 was also perf ormed. The liquid penetrant and visual examinations revealed several indications on each of these supports; however, no indications were in the pump pressure boundary. Indications were evaluated as original manuf acturing defects. They were repair ground in accordance with Vermont Yankee Operating Procedures 6023 Rev. 4 and MR 78-977. Three (3) integrally welded support RR-12, RR-13 and RR-14 were examined through visual and liquid penetrant methods on recirculation pump (P-18-1A) . No recordable indications were found. 2.4 Valves Category G Pressure Retaining Bolting Less Than 2" Diameter Visual examination was performed on 146 bolts and corresponding nuts on the fc11owing valves: System Valve Bolts, Studs, & Nuts
- a. Recire. Header V2-65B 24
- b. CRD V3-113 16
- c. Head Spray V10-32 2
- d. Co re Spray "B" V14-13A 16
- e. Core Spray "B" V14-14A 4
- f. RHR "B" V10-46B 24
- g. Main Steam "C" V2-80C 18
- h. Main Steam "B" V2-80B 18
- 1. RH R "C" V10-81A 24 Page 35 of 38
Slight corrosion and light surface rust were noted and recorded on valve V2-65B. There was no evidence of component degradation. The components were found acceptable with no further action required. Category M Valve Bodies Visual examination was performed on two (2) valve bodies in the following systems:
- a. Feedwater Piping Line "B" - V2 96A
- b. RHR Piping Line "C" - V10-46A Light rust was noted and recorded on valve bodies V2-96A and V10-46A. It was determined that no degradation to the prima ry pressure boundary was evident. The components were found acceptable with no further action required.
Page 36 of 38
3.0 SYSTEM PRESSURE TEST The reactor coolant system was given a system pressure leak test per Vermont Yankee OP4101. No leakages (other than normal controlled Icakage) were detected on the final system leak test. Page 37 of 38
4.0 CONCLUSION
S The examinations performed during this outage begin the second period of the first interval. The 1979 otstage will complete the second period. There are no unacceptable conditions. Page 38 of 38}}