ML19257C507

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Inservice Insp Examination Rept,790924-1104.
ML19257C507
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 01/18/1980
From:
VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML19257C505 List:
References
NUDOCS 8001290254
Download: ML19257C507 (39)
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INSERVICE INSPECTION EXAMINATION REPORT VERMONT YANKEE NUCLEAR POWER CORPORATION SEPTEFBER 24, 1979 TilROUCil NOVDiBER 4,1979 e

1840 124

TABLE OF_ CONTENTS PAGE NIS-1 OWNER'S DATA REPORT 1

SUMMARY

REPORT

1.0 INTRODUCTION

26 1.1 Examination Methods 1.2 26 Evaluation of Data 27 1.3 Examination of Results 27 2.0

SUMMARY

OF EKAMINATIONS 28 2.1 Reactor Vessel Data 2.2 26 Piping Data 2.3 30 Piping Welds - Augmented Inspections of IGSCC 33 2.4 Pumps 33 2.5 . Valves 34 3.0 SYSTEM PRESSURE TEST 35

4.0 CONCLUSION

S 36 4

PREFACE This report cove rs the inservice inspection of Vermont Yankee Nuclear

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Power Station during the period September 24, 1979 through November 4, 1979.

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.

0 1840 126

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., 77 Grove Street, 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
4. Owner Certificate of Authorization (if required) DPR-26
5. Commercial Service Date

. 11/30/726. National floard Number for Unit None._ -

7. Components inspected l

Component or Manufacturer l Manufacturer or Installer ltem Appurtenance State or National or Installer Serial No. Province No. Iloard No.

12 Nozzle 1 Inner Radii Chicago Bridge & Iron B4698 3 Nozzle to N/A N/A 2

Safe-end Welds Chicago Bridge & Iron B4698 1 Nozzle to N/A N/A 3 Safe-end Weld Mercurv Co. N/A 2 Vessel N/A N/A 4 Clad Patches Chicano Bridve & Iron B4698 N/A 1 Piping Safe Per attached Isometrics N/A 5 end Weld Ebasco N/A 60 Pipe N/A N/A 6 Welds Per attached Isometrics Ebasco N/A 20 Supports / Per attached Isometrics N/A  !!/A 7 Hangers Ebasco N/A N/A N/A 8 Per attached Isometrics 92 < 2" Bolts Ebasco N/A N/A N/A Per attached Isometrics 9 8> 2" Bolts Evron Jackson 671 4 -1109 N/A 1 < 6" Branch Per attaches Isometrics N/A 10 rnnnerrinn rhnscn N/A N/A N/A Page 1 of 36 Note: Supplemental sheets in form of lists, detches, or drawings may be used provided (1) size is 8% in x ! I in (2) information in items I through 6 on this data report is mcluded on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

This form (E00029) rnay be obtained from the Order Dept., ASVE, 345 E, 47th St., New York, N.Y. 10017 s

1840 127

1. Owner Vermont Yankee Nuclear Power Corp., 77 Grove Street, 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 DPR-28 (if required) _

5.

Commercial Service Date 11/30/72 6.

National Board Number for Unit None

, 10. Abstract of Examinations Category No. of Components Examined Examination Reactor D 12 Nozzle Inner Radii UT, PT F

3 Nozzle to Safe-end Welds RT, PT, VT 1 Nozzle to Safe-end Weld RT, UT, PT, VT I

2 Vessel Cladding Patches VT Piping F 1 Piping-to-Safe-end Weld UT, PT, VT G-2 36 Flange Bolts and Corresponding Nuts VT J 58 Piping Welds UT, VT 2 Piping Welds RT, VT 1 <6" Branch Connection Weld PT, VT K-1 3 Integrally-welded Supports PT, VT K-2 16 Non-welded Supports VT Pumps G-1 8 Cover-to-Casing Bolts UT K-2 1 Non-welded Support VT Valves G-2 56 Bolts and Corresponding Nuts VT (in place)

. Notes: 1.

The CRD hydraulic return line was rerouted, and the nozzle was capped.

The nozzle-to-cap weld received radiographic examination in accordance with Code requirements. Ultrasonic and surface baseline examinations were also performed. An ultrasonic calibra-tion standard accurately matching the diameter and thickness of '

the carbon-side base material was not available, therefore the CS-side UT exam was considered "best effort". A re-examination of this weld will be performed during the next refueling outage, when it is anticipated that this standard will be on hand. A hydrostatic test Page 3 of 36 1840 128

1. Owner Vermont Yankee Nuclear Power Corp., 77 Grove Street, Rutland, Vt. 05701 (Name and Address of Owner)
2. Plant Vermont Yankee Nuclear Power Station, P. O. Box 157, Vernon, Vt. 05701 (Name and Address of Plant)
3. Plant Unit 1 4. Owner r atificate o1 methorization DPR-28 (if required)
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None to the requirements of IWB 5000 was performed in accordance with VY procedure OP4101.
2. Instrument lines on jet pump risers A, D, F and H were cut and capped, and the weld joints were hydrostatically tested in accordance with the requirements of IWB 5000 and OP4101.

3.

22 of 61 Category J welds were examined in accordance with Proposed Change 70 to Tech. Specs. for augmented inspection of service-sensitive lines.

4. All examination procedures are Yankee Atomic Procedures except where otherwise noted.

Ultrasonic Examination Procedures YA-UT-1 Ultrasonic Examination - General Requirements YA-UT-7 Ultrasonic Examination of Bolting YA-UT 9 Ultrasonic Examination of Piping - Ferritic Welds YA-UT-10 Ultrasonic Examination of Piping - Austenitic Welds (incl. Appendix A)

YA-UT-ll Ultrasonic Examination of Piping - Dissinilar Metal Welds YA-UT-14 Ultrasonic Examination of Piping - base Material and Weld Heat - Affected Zone YA-UT-15 Ultrasonic Examination of Piping Straight Eeam Method when used for Weld and Heat Affected Zone Examination 80A3223 Nuclear Energy Services, Manual Ultrasonic Examination Procedure for Reactor Pressure Vessel Nozzle Inner Radius Area Liquid Penetrant Examination Proccdures YA-PE-2 Liquid Penetrant Examination QCP 3104 Mercury Co., Liquid Penetrant Examination

. Radiographic Examination Procedures PTM 3.20.A.1-2 Peabody Testing, Radiographic Examination of Welds Visual Examination Procedures YA-VT-1 Visual Examination Procedure OP4101, Rev. 7 Vermont Yankee, RPV Operational Hydro Test

11. Abstract of Conditions Noted:

A. During liquid penetrant and visual examinations of Reactor Vessel Head Nozzle to safe-end weld N6B-SE, a depression 3/64" deep x 9/16" long x 1/8" wide was noted and recorded.

""*" ' ' 36 1840 129

1. Owner Vermont Yankee Nuclear Power Corp., 77 Grove Street, Rutland, Vt 0570 (Name and Address of Owner)
2. Plant Vermont Yankee Nuclear Power Station, P. O. Box 157, Vernon, Vt. 0570 (Name and Address of Plant)
3. Plant Unit 1
4. Owner Certificate of Authorization DPR-28 (if required)
5. Commercial Service Date 11/30/72 6. National Board Number for Unit none
11. Abstract of Conditions Noted: (Cont'd)

B.

During Ultrasonic Examination of the inner radius surfaces of Reactor Vessel Nozzles, the following indications were recorded:

Nozzle No. of Indications N2D 2

N4A 2

N4B 7

N4C 4

N4D 3

N5A 2

NSB 3

C.

During Visual Examination of snubber MS-32 on Main Steam Line D, it was noted that one bottom nut was loose.

12.

Abstract of Corrective Measures Recommended and Taken A.

Visual evaluation of the depression on weld N6B-SE has determined that it is actually located in the base metal. It is very shallow with gentle tapers, and is therefore considered acceptable. No further action is deemed necessary.

B.

The ultrasonic indications recorded by the examiners were reviewed by the YAEC UT Level III. The review criteria were:

a. when manually plotted, did the indications fall within the area of interest?
b. were they located with both the CCWand CW scans?
c. did they coincide with known depressions?

When the above criteria were applied, it was determined that there were no nozzle inner radius indications. The reflectors were in areas of manual cladding or were from depressions caused by previous grind-outs.

' The above conclusions were drawn prior to a liquid penetrant exam of the nozzle inner radii. This liquid penetrant exam confirmed the fact that there was no evidence of nozzle inner radius cracking.

C.

The loose nut on snubber MS-32 has been tightened, and re-evaluation was performed by qualified Maintenance Department personnel. No further action is deemed necessary.

ISOMETRICS 1840 130 Attached Note: Inspected components have been circled, with explanations included as necessary.

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DRW9. B-2A I - 120 Page 25 of 36 1840 150

SUMMARY

REPORT 1.0 INTRODUCT ION

, This report describes the inservice inspections performed during 1979 at the Ve rmont Yankee Nuclear Power Station, Vernon, Verment.

The examinations perforced are those of the second 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 XI, " Rules for Inservice Inspection of Nuclear Reactor Coolant S y s t e ms , " zis re f e ren ce d by the plant technical specifications. The areas subject to examination and the methods used were in accordance with the plant technical specifications. Pressure boundary 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 pe rmit ted . All limited scans are described in the data. Th is report s umma rizes the areas examined, the type of examinations , the results of the test data, evaluations and repairs. Ultrasonie, radiographic, liquid penetrant, magne tic p art icle , and visual examination techniques were erployed to pe rfo rm the required examinations.

1.1 Examination Methods Non-dest ructive examinations were performed in accordance with the procedures contained in the Yankee Atomic Elect ric Cotpany, Engineering Guidelines , Book III, " Inservice Inspection NDE Procedure" or Vendor Procedures reviewed and approved by Page 26 of 36

Yankee Atomic Electric Company per the Engineering Department Quality Assurance Manual. The examination procedures were re viewe d and approved by pe rsonnel 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 whe re these editions are in conflict with the technical speci ficat ion re qui re men t s , i.e., for Category B-F and B-J,Section XI S'76 Addenda Appendix III and appropriate Acceptance Criteria. The inse rvice examinations were pe rformed and evaluated by personnel qualified to the 19 75 Edition of SNT-TC-1A.

The procedures ueed for these examinations are listed in Section 10 of the NIS-1 form.

1.2 Evaluation of Date The examination results were reviewed at the site by personnel qualified to SNT-TC-1A Level III. Indications we re evaluated to the acceptance standards as defined in the Ve rmont 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 data along with the calibration reco rd , p roced ures ,

equipment ce rtifications and personnel quali fications are maintained at the plant site.

1840 152 Page 27 of 36

2.0

SUMMARY

OF EXAMINATIONS

. This section summarizes the inservice inspection data for the 19 79 ref ueling ou. age at Ve rmont Yankee Nuclear Power Station. For clarity, the results are summarized in accordance with the examination categories of Section X1.

2.1 Reactor Vr ssel Data Category B-D - Nozzle to Vessel Welds Ultrasonic examinations were performed on Reactor Vessel Nozzle Inne r Radii. The nozzle inner radii examined were:

Re c t re Inlet - N-2C, N-2D, N-2G Main Steam - N-3A, N-3B Feedwater - N-4A, N-4B, N-4C, N-4D Core Spray - N-5A, N-SB CRD Return - N9 The nozzle to vessel welds were examined during the 1978 outage.

Liquid Penetrant Examinations were performed on the feedwater and CRD return nozzle inner radii from the vessel ID.

The work was performed by General Electric I6SE to their procedures.

No indications were found on the feedwater or CRD return nozzles.

Ultrasonic indications were recorded on the nozzle inner radii as follows:

N2D 2 indications N4A 2 indications N4B 7 indications N4C 4 indications Page 28 of 36

N4D 3 indications NSA 2 indications NSB 3 indications Evaluation of the indications recorded by the examiners was performed on full scale, graphic representat ions of the nozzles. It was concluded that the majority of indications were f rom the area of man;al cladding over the nozzle to vessel weld. This indicates the roughness of the clad to base metal interf ace in this area. Evaluation also indicated reflectors appearing in the area of previous grind outs. No indication was seen from two directions (clockwise and counter clockwise scan) . It was concluded that there were no indications on the nozzle inner radii. In the case of the CRD and feedwater nozzles, th is fact was later confirmed by Liquid Penetrant Examinations. Category B-F - Nozzle to Safe-End Welds Three nozzle to safe-end welds on the vessel head were examined using Radiographic, Liquid Pene trant , and Visual techniques. Radiography was used instead of ultrasonic techniques because the geome t ry did no t permit meaningful ultrasonic results. No indicatiot.s were found on N-7SE and N6BSE. A visual indication was noted on N-6ASE in the base metal adj acent to the weld. Evaluation of the indication was, "a shallow depression , of minimal depth, smoothly blended." It was considered acceptable as fo un d . No further action is required. Page 29 of 36 1840 154

The nozzle to safe end weld on the CRD cap was examined as a best effort baseline exam from the nozzle side and a code complying exam on the cap side. The CRD nozzle cap was installed and radiog raphed per the requirer'ents of ASME Sect ion III NB, during this outage. The required caliabration block is currently being fabricated. The examination will be performed as soon as possible. Category B-I Vessel Cladding Two 6 x 6 vessel clad areas were visually examined by direct means when the vessel level was lowered for examination of feedwater nozzles. No indications we re found. 2.2 Piping Data Ca t e go ry F - Pi pe to Safe-End Welds Ultrasonic, visual, and liquid penetrant examinations were pe rformed on one (1) pipe to safe-end weld. The examination was performed on RHR - line 28, weld #13. No recordable indications we re fo un d. Category G Pressure Retaining Bolting Less than 2" Diamater Pressure relief valve flange to nipe bolting was examined visually on the following main steam line components.

1. Main Steam B a.

RV-70B - 12 bolta cnd nuts examined when removed

b. SR2-71B - 12 bolts and nuts a miner in place
2. Main Steam D u.

SR2- 71D - 12 bolts and nuts examined when removed No recordable indications we re fo und . Page 30 of 36 1840 155

Category J - Piping Welds , Fifty-eight (58) piping welds were visually and ultrasonically examined on the following systems:

a. RHR-A Line 32 6 welds
b. Feedwater A - Line FDW-19 7 welds Line FDW-21 2 welds
c. Feedwater B - Line FDW-20 2 welds Line FDW-18 6 welus
d. Head Spray - Line RHR-19 11 welds
c. Core Spray B - Line CS-4A 4 welds
f. Main Steam A 1 weld
g. Main Steam B 1 weld
h. Main Steam C 7 welds
i. Main Steam D 7 welds
j. HPSI - Line MS-4A 4 welds Total SS welds The examinations above included twelve (12) inches of intersecting longitudinal seams where applicable. No recordable indications were found.

Category J - Piping Welds Two (2) welds were radiographed and visually examined. Radiography was performed because access for proper ultrasonic scanning was not available. The welds examined were F9A, F9B on line RHR-19. No recordable indications were found. Page 31 of 36 1840 156

Category J - Branch Connections less than 6" Branch connection weld #3 on line RHR-32 (RHR-A) was examined using visual and penetrant techniques. Ns recordable indications were found. Category K Integrally Welded Supports Three (3) integrally welded supports were examined using liquid penetrant and visual examination techniques. The supports were:

a. Feedwater line A support FW-4
b. RilR line A - support RilR- 1
c. RHR line B - support RIIR-6 No recordable indications were found.

Category K Non-Integral Supports Sixteen (16) non-welded hangers and supports were visually examined in the following systems:

a. Recire. Risers - RR-36, RR-S6, RR-61 3
b. Recirc Loop A -RR-1 1
c. Recirc Loop B - RR-65, RR-74, RR-89, RR-93 4
d. Main Steam A - MS-3 1
c. Main Steam B - MS-14 1
f. Main Steam D - MS-32 1
g. Feedwater B - FW-18, FN-19 2
h. HPSI - IIPSI-2,IIPSI-4 2
i. RCIC - RCIC-2 1 Total 16 MS-32 on Main Steam D is a hycraulic snummber which was found to have a loose nut. Independently, plant maintenance had identified this Page 32 of 36 184 57

condition and corrected it prior to start-up. The item is considered , resolved. Recommendation is provided in maintenance files. No othe r recordable conditions we re found. 2.3 Piping Welds - Augmented Inspections for ICSCC Examination of Category i tzelds for Intergranular St ress Corrosion Cracking (IGSCC) was developed as a result of NUREG-0313 and Vermont Yankee Proposed Change 70 to technical specifications. Proposed Change 70 was submitted on December 29, 1977. Twenty-two (22) of the Sixty-one (61) welds defined in Category J were examined because of the requirements of the proposed change. In the two yea rs following the first issue of NUREG-0313, the IGSCC phenomenon has changed its compicxion. Therefore, based on internal memorandum addressing these changes, an additional sample of approximately 30 welds was included in the 1979 outage These additional welds are not included in the Category J paragraphs of this repo rt . All doc urae n t a t i on is on file at the plant site. The examinations of 304 type stainless steel were pe r fo rme d 

.       using the EPRI/SWRi techniques.       These techniques include the use of dual element, zone foc use d , 1. 5 MHz sea rch units.

2.4 Pumps Category G Pressure Retaining Bolting greater than 2" Di imeter. Eight (8) bonnet bolts on Recirc Pump P-18-1B (Loop B) were examined ul trasonically in place. No re co rdable indications we re found. Page 33 of 36 kh

2.5 Valves a Category G Pressure Retaining Bolting less than 2" Diameter Visual examination was perforned in place on the bolting of 3 valves indicated below. 1he total bolts numbered 56. System Val ve Bolts / Studs and Nuts

a. Recirc A V2-53A 24
b. Recire B V2-43B 24
c. Fee dwa t e r A V2-2 7A 8 No recordable indications were found.

Page 34 of 36 1840 159

3.0 SYSTDi PRESSURE TEST The reactor coolant system was given a system pressure test at ope rating pressure pe r IWB-5221 and Ve rmont Yankee OP4101. The reacto r vessel, tecirculation risers and non-isolable portions of the reactor coolant boundary received a system hydrostatic leak test per the requirements of IWB-5222. The system hydrostatic leak test was perforned as required by IWA-4210, which requies a p ressure test af te r welded repairs. The s ul;j .: : t repairs were the CRD nozzle cap and the cutting and capping of the i ns t rumen t lines on recric rise rs A, D, F, and II. No leakage (other than normal controlled leakage) was detected in either test. Page 35 of 36

4.0 CONCLUSION

S The examina' c lons pe rformed during this outa!;e conclude those required for the second period of the first inspection interval. There are no unacceptable conditions and no continuing or follow-up items. 4 1840 161 Page 36 of 36}}

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