ML20041E272

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VT Yankee Nuclear Power Corp 1981 Inservice Insp Summary Rept,811017-811201
ML20041E272
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 03/05/1982
From:
VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20041E269 List:
References
NUDOCS 8203100313
Download: ML20041E272 (28)


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.I VERMONT YANKEE NUCLEAR POWER CORPORATION 1981 INSERVICE INSPECTION

SUMMARY

REPORT

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OCTOBER 17, 1981 THROUGH DECEMBER 1, 1981 1

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PREPARED BY [

PLAN [INsERVICEIpECTIONCOORDINATOR j

APPROVED BY k

I ENGINEERING SUPPORT SUPERVISOR I

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8203100313 820305 PDR ADOCK 05000 G

Page 1 of 27

t TABLE OF CONTENTS j

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1.

Introduction 2.

Examination Methods 3.

Evaluation of Data 4.

Examination Results i

5.

Conclusions Attachment A:

Form NIS-1, Owners' Data Report for Inservice Inspections l

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Page 2 of 27 i

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VERMONT YANKEE NUCLEAR POWER CORPORATION 1981 INSERVICE INSPECTION

SUMMARY

REPORT OCTOBER 17, 1981 THROUGH DECEMBER 1, 1981 1.

INTRODUCTION The attached Form NIS-1, " Owners' Data Report for Inservice Inspection" describes tne inservice inspections performed during 1981 at the Vermont Yankee Nuclear Power Station, Vernon, Vermont. The examina-tions performed were those of the second outage of the third 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 Systems," as referenced by the plant Technical Specifications. The areas subject to examination and the methods used were in accordance with the Vermont Yankee Inservice i

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 I

techniques were employed to perform the required examinations.

1 2.

EXAMINATION METHODS I

Non-destructive examinations were performed in accordance with the procedures contained in the Yankee Atomic Electric Company, Engineering Guidelines, Book II, " Inservice Inspection NDE Procedures," or vendor

(

procedures reviewed and approved by Yankee Atomic Electric Company per l

the Engineering Department Quality Assurance Manual. The examination j

procedures were reviewed and 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 portions of ASME Section V (S'75) except where these editions are in conflict with Technical Specifi-cation requirements. The inservice examinations were performed and evaluated by personnel qualified to the 1975 edition of SNT-IC-1A.

Page 3 of 27

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The procedures used for these examinations are listed in Section 10 of the NIS-I Form.

3.

EVALUATION OF DATA The examination results were reviewed at the site by personnel qualified to SNT-TC-1A Level III.

Indications were evaluated to the acceptance standards defined in the Vermont Yankee Nuclear Power Station Technical Specifications.

4.

EXAMINATION RESULTS A list of all 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. No rejectable conditions other than those described in Section 11 of the NIS-1 Form were noted during these examinations. Upon completion of the corrective '

actions detailed in Section 12 of the NIS-1 Form, there were no remaining unacceptable conditions and no continuing or follow-up items.

l CONCLUSIONS Th e scheduled inspections accomplished during the 1981 Inservice Inspection constitute an additional 1/3 of the total number of inspections required to be completed during Period 3 of the first Inservice Inspection Interval. Upon completion of the 1981 Inservice Insepetion, approximately 90% of all inspec-tions required for this inspection interval had been performed.

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Page 4 of 27

FORM NIS-1 (back)

8. Examination Dates 10/17/81 12/1/81
9. Inspection Interval from 11/30/72 to 11/"tn/g?

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10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current i. terval.

See attached pages.

I1. Abstract of Conditions Noted See attached pages.

12. Abstract of Corrective Measures Recommended and Taken g

See attached pages.

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 ASME Code Section XI.

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Vermont Yankee Nuclear [/

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6 CW Power Corporation Date 19 igned ny"' Plant 7

Manager Owner December 11, 2007 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 M4 SS-and employed by /-/ l B T 4.7 (*o of

///Wff42.

  1. f have inspected the components described in this owners' Data Report during the period

/C/G/9/

to /2 / / /I/

. 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 avarranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data Report. Furthermore, neither the inspector nor his employer shall be liabic in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

Date f/AA I

19 W%

& N-Commissions M-/A 55 *

/ / <i2-Inspector's Signature National Board, State, Province and No.

ATTACHMENT A FORM NIS I OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner Vermont Yankee Nucienr Poucr Corp _; 77 nrnun Stroor. nurinna, 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) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None
7. Components Inspected 4

i Manufacturer Component or Manufacturer or installer State or National Appurtenance or Installer Serial No.

' Province No.

Board No.

Safety Class 1 l Nozzle to Safe-end Weld Chicago Bridge & Iron B 4698 N/A N/A 9 Vessel Closure Studs Chicago Bridge & Iron B 4698 N/A N/A 13 Vessel Closure Nuts Chicago Bridge & Iron B 4698 N/A N/A 9 Vessel Flang<

Ligaments Chicago Bridge & Iron B 4698 N/A N/A 10 Vessel Closure Washern Chicago Bridge & Iron B 4698 N/A N/A 9 Vessel Clo-sure Bushings Chicago Bridge & Iron B 4698 N/A N/A 4 Vessel Stabi-lizer Brackets Chicago Bridge & Iron B 4698 N/A N/A 2 Vessel Clad Patches Chicago Bridge & Iron B 4698 N/A N/A j

3 CRD flousing Welds Chicago Bridge & Iron B 4698 N/A N/A 2 Piping Safe-Per referenced isometric o end Welds EBASCO N/A N/A N/A L Piping Safe-Per referenced isometric:

end Weld Mercury Co.

N/A N/A N/A 20 Pipe Welds OAb N/A N/A N/A Per referenced isometrics 6 Pine Welds Mercurv cn.

M/A N/A N/A l<6" Branch Per referenced isonetric:

Connect Weld Mercury Co.

N/A N/A N/A 23 Supports /

Per referenced isometrics llangers pnAsco N/A N/A N/A Note: Supplemental sheets in form of lists sketches, or drawings may be used provided (1) size is 8% in. x 11 in.,

(2) information in items I through 6 on this data report is included 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) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017 Page 5 of 27 1

6 FORM NIS.I OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules Vermont Yankee Nuclear Power Corp., 77 Grove Street, Rutland, VT 05701

1. Owner (Name and Address of Owner)
2. Plant Vo mn n t Ynnkoo Nncione Pnuor (enr4nn, p_n gn,- 13 7, yg g,,g.,, VT 05154 (Name and Address of Plant)
3. Plant Unit 1
4. Owner Certificate of Authorization (if required) DPR-28 11/30/72 6. National Board Number for Unit None
5. Commercial Service Date
7. Components inspected l

Manufacturer l

Component or Manufacturer or installer State or National j

Appurtenance or Installer Serial No.

Province No.

Board No.

l "a

4>2" Bolts Byron Jackson 671-S-1108 N/A N/A Per referenced isometrics 168 <2" Bolts EBASCO N/A N/A N/A 2 Valve Internals Anchor Darling N/A N/A N/A t

Safety Class 2 l

1 Vessel Suoport Sweco Company N/A N/A N/A l

Per referenced isometrics 9 Pipe Welds EBASCO N/A N/A N/A j

Per referenced isometrics 2 Pipe Welds Mercury Co.

N/A N/A N/A Per referenced isometrics 5 831" Bolts EBASCO N/A N/A N/A 39 Supports /

Per referenced isometrics Hancers EBASCO N/A N/A N/A Safety Class 3 21 Supoorts/

Per referenced isometrics Hancers FBA9c0 N/A N/A N/A Supplemental sheets in form of lists, sketches or drawings may be used provided (1) size is 8% in. x 11 in..

Note:

(2) information in items 1 through 6 on this data report is included on each sheet, ar.o (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

10017 This form (E00029) may be obtained from the Order Cent., ASME. 345 E. 47tn St., New York, N.Y.

Page 6 of 27

1. Owner Vermont Yankee Nucienr Power cnrp._ 77 cenuo Serape n,,e i na tr e nq701 (Name and Address of Owner)

Vermont Yankee Nuclear Power Station, P.O. Box 157 Vernon. Vt 05354

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 10.

Abstract of Examination A.

Nondestructive Examinations Component Component Category Description Identification Examination Isometric (1)

Safety Class 1 Reactor l

B-F Nozzle to Safe-N2B-SE UT, PT, VT H-1 end Weld B-G-1 Vessel Closure 27 through 35 UT, PT H-21 Studs Vessel Closure 27 through 35 UT, PT H-21 Nuts 7, 9, 10, 11 Vessel Flange 27 through 35 UT H-21 Ligaments Vessel Closure 27 through 35 VT H-21 Washers 11 Vessel Closure 27 through 35 VT H-21 Bushings B-H Vessel Stabilizer B at 90*

MPT, VT None Brackets D at 270*

MPT, VT None A at 0" VT None C at 180*

VI None l

B-I-2 Vessel Cladding 0* Top VT H-24 l

Patches 90* Bottom VT H-24 i

B-0 CRD Housing to 18-03 UT, VT H-25, H-26 l

Flange Welds 22-03 UT, VT H-25, H-26 l

26-03 UT, VT H-25, H-26 i

Page 7 of 27

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1. Owner Vermotit Yankee Nucient **ga.,cnrn._

77 crmr. Sernae unetenA ve n5701 (Ncme ano sMess of Owner)

2. Plant Vermont Yankee Nuclear Power gagion, P.O. Box 157, Vernon. Vt 05354 (Name and Addfw H Plant) 1
4. Owner Certificate of.u.tixication (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Numb " e Unit None i

10.

Abstract of Examination (Continued) i A.

Nondestructive Examinations (Continued)

Component Component Category Description Identification Examination Tsometric (1)

Safety Class 1 Piping B-F Piping to Safe-Line CS-3A UT (2)

H-12 1

l end Welds Weld F3A j

Line CS-3B Weld F3A UT (2)

H-ll l

s.

Line CS-4B Weld MF6A UT, PT, VT H-ll i

B-G-2 Flange Bolts &

Line MS-7A Corresponding Blank Flange "A" VT H-14 Nuts (12 bolts in place)

Relief Valve VT H-14 g

SR2-71A (12 bolts in place) t B-J Circumferential Recire Riser N2B

& Longitudinal Weld 40 UT, VT (3)

H-1 Welds Weld 40A UT, VT (3)

H-1 Recire Riser N2F Weld 24A UT, VI (3)

H-1 Line RHR-33 Weld 12 UT, VT H-4 Weld 13 UT, VT H-4 Line RHR-30 Weld 1 UT, VT (3)

E-6 Weld 2 UT, VT (3)

H-6 Weld 6 UT (4)

H - t.

Weld 7 UT (4)

H-6 Page 8 of 27 l

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1. Ownrr Vermoitt Yankee Nuclear Pcwer cnrn.

77 cenuo s e ro,. n,, e t,,, a tr e n5701 (Name and Address of' Owner)

Vermont Yankee Nuclear Power Station, P.O. Box 157. Vernon. Vt 05354

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None i

10.

Abstract of Examination (Continued)

A.

Nondestructive Examinations (Continued)

Component Component Category Description Identification Examination Isometric (1)

Safety Class 1 4

Piping B-J Circumferential &

Line RHR-28 Longitudinal Welds Weld 17 UT, VT H-6 Weld 18 UT, VT H-6 Weld 19 UT, VT H-6 Line FDW-16 Weld MF7 UT, VT (5)

H-7 Weld MF7A UT, VT (5) 4-7 f

Line FDW-17 Weld MF4 UT, VT (5)

H-8 Weld MF4B UT, VT (5)

H-8 Line FDW-20 Weld F2 UT, VT H-8 Weld F2A VT (6)

H-8 Weld F3-SA UT, VT H-8 Line MS-7A Weld A4A UT, VT H-14 Line MS-7B l

Weld B4 UT, VT H-15 Weld B4A UT, VT H-15 Line MS-5A Weld FlB UT, VT H-19 Weld FlC UT, VT l

Page 9 of 17 m..,. _ _

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1. Owner Vermont Yankee Nuclear Pet.ror cnrn._ 77 cenua Sernae Duel-A

'? * " 701 (Nams and Address of Owner)

Vermont Yankee Nuclear Power Stat 1on, P.O. Box 157, Vernon. Vt 05154 l

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None i

10.

Abstract of Examination (Continued)

A.

Nondestructive Examinations (Continued)

Component Component Category Description Identification Examination Isometric (1)

Safety Class 1 Piping B-J Circumferential &

Recire. "A" Bypass Longitudinal Welds Weld C7B RT, VT H-2 Weld C7C RT, VT H-2 Branch Connections Recirc "A" Bypass

<6" Weld C7A PT, VT H-2 B-K-1 Integrally Welded Line CS-4B Supports Support CS-1 PT, VT H-11 Line CS-4A Support CS-2 PT, VT H-12 B-K-2 Non-welded Recire Ring Supports Header Support RR-39 VT H-1 Support RR-42 VT H-1 Recirc Loop "A" Support RR-2 VT H-2 Support RR-5 VT H-2 Support RR-23 VT H-2 Line FDW-19 Support W-1 VT H-7 Support FW-5 VT H-7 Line FDW-21 Support W-7 VT H-7 Page 10 of 27 4

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1. Owner Vermotit Yankee Nuclear Power cnrn., 77 ccmra S t r a a t-n iv e 1,rs A Ve A5701 (Name and Addr:ss of Owner)

Vermont Yankee Nuclear Power Station, P.O. Box 157. Vernon. Ve 05354

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 10.

Abstract of Examination (Continued)

A.

Nondestructive Examinations (Continued)

Component Component Category Description Identification Examination Isometric (1)

Safety Class 1 Piping B-K-2 Non-Welded Line FDW-18 Supports Support FW-18 VT H-8 Line FDW-20 Support W-16 VT H-8 Support W-12 VT H-8 Line CUW-18 Support CU-6 VT H-13 Line MS-7A Support MS-1 VT H-14 Support MS-2 VT H-14 I

Line MS-7B Support MS-12 VT H-15 Support MS-13 VT H-15 i

Line MS-7D Support MS-30 VT li-17 Support MS-31 VT H-17 Line MS-SA Support RCIC-1 VT H-19 Pumps Cover to Casing Pump P-18-1A B-G-1 Bolts &

Bolt No. 1 UT, VT H-2 Corresponding Bolt No. 5 UT, VT H-2 Nuts Bolt No. 9 UT, VT H-2 l

Bolt No. 13 UT, VT H-2 l

(in place) l l

Page 11 of 27 l

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1. Owner Vermotit Yankee Neclear Pcver Cnrn, 7 7 c rmin S t ro n t-nurt,nA. "t 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) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 10.

Abstract of Examination (Continued)

A.

Nondestructive Examinations (Continued)

Component Component Category Description Identification Examination Isometric (1)

Safety Class 1

.l Pumps B-K-1 Integrally Welded Pump P-18-1A 4

Supports Support RR-15 PT, VT H-2 i

B-K-2 Non-Welded Pump P-18-1A Supports Support RR-18 VT H-2 Valves Valve Bolts &

Recire Loop "A"

[

B-G-2 Corresponding Valve V2-43A VT H-2 l

Nuts (28 bolts in place)

Line RHR-31 I

Valve V10-81B VT H-5 (24 bolts in place)

Line RHR-30 Valve V10-46A VT H-6 (20 bolts in place, 4 removed)

Line FDW-16 Valve V2-27A VT (5)

H-7 (8 bolts removed)

Line FDW-17 Valve V2-96A VT (5)

H-8 (8 bolts removed)

Page 12 of 27 s

1. Owner Vermont Yankee Nuclear Pouer ('nrn, 77 crnvo Strnae nuel,nA t' e n5701 (Name and Address of Owner)

Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon. Vt 05354

2. Plant (Name and Address of Plant) 4 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None i

10.

Abstract of Examination (Continued)

A.

Nondestrur:tive Examinations (^ atinued)

Component Component Category Description Identification Examination Isometric (1)

Safety Class 1 Valves B-G-2 Valve Bolts &

Line CS-4B Corresponding Valve V14-14B VT H-ll Nuts (4 bolts in place)

Line MS-7A Valve V2-86A VT H-14 (18 bolts in place)

VT H-14 Valve SR2-71A (12 bolts in place)

Line MS-7B Valve V2-86B VT H-15 (18 bolts in place)

B-M-2 Valve Body Line FDW-16 Internal Surfaces Valve V2-27A VT (5)

H-7 Line FDW-17 Valve V2-96A VT (5)

H-8 t

Safety Class 2 Vessels l

C-C RHR Heat RHR HX "A" Exchanger Support RHR-CC-2 MPT,VT I-21 Supports i

i f

Page 13 of 27 l

I I. Ownee Vermoitt Yankee Nuclear E m er corn, 77 crnun stroor g net,na, ve n5701 (Name and Address of Owner)

Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon. vt 05354

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Bo2rd Number for Unit None

)

10.

Abstract of Examination (Continued)

A.

Nondestructive Examinations (Continued)

Component Component Category Description Identification Examination Isometric (1)

Safety Class 2 Piping C-D Flange Bolts &

Line MS-4B l

Corresponding 8" Blind Flange VT I-2 Nuts (12 bolts in place)

C-E-1 Integrally Welded Line MS-4B Supports Support H-6 MPT, VT I-2 Line HPCI-15B Support H-32 MPT, VT I-4 Line HPCI-2 Support H-24 MPT, VT I-5 t

I Line CS-2A Support H-90 MPT, VT I-6A Line RHR-1A Support H-181 MPT, VT I-7A Support H-128 MPT, VT I-7A l

Line RHR-2B Support HD-127J MPT, VT I-9 Line RHR-2D Support HD-127H MPT, VT I-9 i

Page 14 of 27

1. Owner Jermoist Yankee Nuclear Po.ror enrn.. 77 c rmm Stroor RtF 1, A, t't __05701 (Name and Address of Owner)

Vermont Yankee Nuclear Pcwer Station, P.O. Box 157. Vernon. Vt 05354

2. Plant (Name ari Address of Plant)

DPR-28 1

4. Owner Certificate of Authorization (if required)__
3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None i

i 10.

Abstract of Examination (Continued) q A.

Nondestructive Examinations (Continued)

Component Component Category Description Identification Examination Isometric (1)

Safety Class 2 Piping C-E-1 Integrally-Welded Line RKR-6 Supports Support HD-189A MPT, VT I-12 Line RHR-7 Support H-186 MPT, VT I-13 Line RHR-1 Support E-191 MPT, VT (7)

I-15 Line RHR-14 Support H-101 MPT, VT I-16 Line RHR-40 Support HD-201B MPT, VT (7)

I-17 Support HD-32 MPT, VT I-17 C-E-2 Non-Welded Line MS-4B Supports Support HD-102B VT I-2 Support HD-8A VT I-2 Line HPCI-3 Support H-39 VT I-3 Line CS.3A Support H-47 VT I-6A Line RHR-2B Support HD-127I VT I-9 Page 15 of 27

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1. Owner Vermotit Yankee Nuclear Power Cnrn.

77 cem n Strone riu r t,n a el? 05701 (Name and Address of Owner)

Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon. Vt 05354

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None I

10.

Abstract of Examination (Continued)

A.

Nondestructive Examinations (Continued)

Component Component Category Description Identification Examination Isometric (1)

Safety Class 2 Piping C-E-2 Non-Welded Line RHR-3D Supports Support H-129 VT I-10B Line RHR-5A Support HD-187B VT I-ll Line RHR-5B

{

Support HD-188D VT I-ll Line RHR-7 Support HD-129A VT I-13 Line RHR-9 Support H-191 VT I-15 Support HD-87 VT I-15 Support HD-194C VT I-15 Support HD-192 VT I-15 Line RHR-12 Support CS-HD-86B VT I-16 Line RHR-14 Support HD-87C VT I-16 Support HD-87D VT I-16 Support CS-H-87 VT I-16 Page 16 of 27

1. Owner Vermont Yankee Nuclear Peuer cnrn._ 77 crnen Strone_ thi r i n n a tr e-n5701 (Name and Address of Owner)

Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon. Vt 05354

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

CPR-23

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None

]

10.

Abstract of Examination (Continued) i A.

Nondestructive Examinations (Continued) 4 Component Component Category Description Identification Examination Isometric (1)

Safety Class 2 Piping C-E-2 Non-Welded Line RHR-17 Supports Support CS-HD-54B VT I-15 l

Line RHR-40 Support HD-201B VT I-17 l

Suppott HD--8 VT I-17 Support H-160 VT I-17 1

Line CRD-5 Support H-23 VT I-22 Line CRD-5A Support H-29 VT I-22 Support H-27 VT I-22 i

Line CRD-6A Support H-17 VT I-22 Support H-15 VT I-22 Line CRD-7 Support H-36 VT I-22 C-F Pressure Retaining Line RHR-1A I

Welds in Piping Weld S-4 UT I-7A l

Which Circulates Reactor Coolant Line RHR-3C Weld F-6 UT I-10A j

Line RHR-6 Weld F-5 U1 1-12 i

Page 17 of 27 t

1

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l. Owner Vermont Yankee Nuclear Power enrn._ 77 crnun Stroor nivel,na, ve ns701

[

(Name and Address of Owner)

2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon. Vt 05354 (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 10.

Abstract of Examination (Continued)

A.

Nondestructive Examinations (Continued)

Component Component Category Description Identification Examination Isometric (1) j Safety Class 2 Piping C-G Pressure Retaining Line HPCI-2 Welds in Non-Weld S-10 UT I-5 l

Reactor Coolant i

Piping Line CS-2A Weld S-3 UT I-6A Line RHR-2A Weld S-5 UT I-8 Line RHR-9 Weld S10C UT I-15 Line RHR-15 Weld S-6 UT I-16 Line RHR-40 Weld FIA UT I-17 i

Line FDW-16 Weld MF6 UT (5)

I-4 Line FDW-17 Weld MF3 UT (5)

I-19 Page 18 of 27

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1. Owner Vermont Yankee Nuclear Pm.rer cnrn., 77 crnvo Strone h e 1,na, t?"

05701 1

(Name and Address of Owner) j Vermont Yankee Nuclear Power Station, P.O. Box 157. Vernon. Vt 05354

2. Plant (Name and Address of Plant) i 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit 5 Commercial Service Date 11/30/72 6. National Board Number for Unit None l

10.

Abstract of Examination (Continued)

)

A.

Nondestructive Examinations (Continued)

Component Component Category Description Identification Examination Isometric (1)

Safety Class 2 Pumps i

C-D Pump Bolts &

HPCI System Corresponding Pump P-44-1B VT I-4 Nuts (36 bolts in place)

Valves C-D Valve Bolts &

Line FDW-17 l

Corresponding Valve V2-27B VT, MPT I-19 Nuts (10 bolts in place, 3 removed) 4 Safety Class 3 Hangers and Line SW-18A IWD-2410(c)

Supports >4" Support H-59 VT D-1 NPS Support H-191 VT D-1 s

Support H-23 VT D-2 Support RSW-HD-218C VT D-4 Support RSW-HD-216D VT D-3 Line SW-18B Support HD-79C VT D-2 Support H-265 VT D-2 Support RSW-236 VT D-4 Support RSW-237 VT D-4 Support RSW-HD141C VT D-5 Line SW-1B Support HD-246D VT D-6 i

Page 19 of 27 l

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1. Owner Vermont Yankee Nuclear Power cnrn_ _ 77 crmm Strone Quelnnd V*

05701 (Name and Address of Owner) f Vermont Yankee Nuclear Power Station, P.O. Box 157. Vernon. Vt 05354

2. Plant (Name and Address of Plant) l 1
4. Owner Certificate of Authorization (if required)

DPR-28 l

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 10.

Abstract of Examinatig (Continued)

A.

Nondestructive Examinations (C:ntinued)

Component Component Category Description Identification Examination Isometric (1)

Safety Class 3 IWD-2410(c)

Hangers and Line SW-6A l

Supports >4" Support RSW-HD220 VT D-3 NPS Line SW-6B Support RSW-H232 VT D-5 Line FPC-1B Support H-31 VT D-7 Support H-32 VT D-7 Support H-33 VT D-7 Support H-34 VT D-7

{

Support H-35 VT D-7 Support H-36 VT D-7 Support H-37 VT D-7 Line FPC-2 Support H-2 VT D-7 NOTES:

1.

Referenced isometric drawings are contained in the Vermont Yankee Inservice Inspection Prograu.

2.

UT carried over from 1980. PT and VT previously completed.

3.

Inspection included 12" of longitudinal seam welds.

4.

Augmented examinations in accordance with Proposed Change 70 to Technical Specifications.

Page 20 of 27 O

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77 nrmo S t r o n,- u l,na

"* n5701

1. Owner Vermont Yankee Nuclear Pouer enrn_ _

(Name and Address of Owner)

Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon. Vt 05354

2. Plan (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 10.

Abstract of Examinations (Continued)

A.

Non-destructive Examinations.(Continued)

NOTES:

5.

Baseline examinations in accordance with IWA-4220.

6.

VT carried over from 1980. UT completed previously.

7.

Double support of welded /non-welded construction. Also listed under Category C-E-2.

B.

Hydrostatic Tests The following system pressure tests were performed in accordance with IWA-4210 and/or Subarticles IWB-5000, IWC-5000, or IWD-5000 as appropriate.

1.

New Safety Class 3 welds in the Service Water System were hydrostatically tested and accepted following j

replacement of piping and components.

2.

New Safety Class 1 and 2 welds in the Feedwater System were hydrostatically tested and accepted following re-placement of two outboard feedwater-check valves.

Although the Safety Class 1 piping affected by this installation required a lower test pressure and a higher test temperature than the Safety Class 2 portion, it could not be excluded from the Safety Class 2 test boundary. Following an engineering evaluation, it was determined that subjection of the Safety Class 1 feed-water piping to the Safety Class 2 test would not be detrimental to the primary coolant system since this Safety Class 1 piping is of the same design pressure as the Safety Class 2 portion and can be isolated from the reactor vessel for performance of the test.

Therefore, the Safety Class 2 hydrostatic test parameters were applied to all piping.

Page 21 of 27

1 I

li j

1. Owner Vermonit Yankee Nuclear Pover enrn_

77 crmrn Strone nuelnna tre n5701 (Name and Address of' Owner) l Vermont Yankee Nuclear Power Station. P.O. Box 157. Vernon. Vt 05354

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 10.

Abstract of Examinations (Continued)

B.

Hydrostatic Tests (Continued) 3.

New Safety Class 3 welds in the Reactor Water Cleanup System were hydrostatically tested and accepted following extensive replacement of piping and components.

4.

New Safety Class 2 welds in the Alternate Fuel Pool Cooling return line were hydrostatically tested and accepted following a minor piping modification.

5.

New Safety Class 2 welds in the HPCI System were hydrostatically tested and accepted following a minor piping modification.

6.

A primary coolant system leakage test was performed in accordance with IWB-5221 and accepted prior to plant startup.

C.

Ultrasonic Examination Procedures 1.

YA-UT-1, Ultrasonic Examination - General Requirements 2.

YA-UT-6, Ultrasonic Examination of Flange Ligaments 3.

YA-UT-7, Ultrasonic Examination of Bolting 4.

YA-UT-8, Ultrasonic Examination of Reactor Closure Nuts 5.

YA-UT-9, Ultrasonic Examination of Piping - Ferritic Welds 6.

YA-UT-10, Ultrasonic Examination of Piping - Austenitic Welds (including Appendix A) j 7.

YA-UT-ll, Ultrasonic Examination of Piping - Dissimilar Metal Welds 8.

YA-UT-12, Thickness Measurement by Ultrasonics 9.

YA-UT-14, Ultrasonic Examination of Piping - Base Material and Weld Heat-Affected Zone Page 22 of 27 i

m

I

1. Owner Vermont Yankee Nuclear P mer enrn, 77 crnen St rnoe _ nue t,w, tr e n5701 (Name and Address of Owner)

Vermont Yankee Nuclear Power Station, P.O. Box 157. Vernon. Vt 05354

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 10.

Abstract of Examinations (Continued)

D.

Liquid Penetrant Examination Procedures 1.

YA-PE-2, Liquid Penetrant Examination E.

Magnetic Particle Examination Procedures 1.

YA-MP-1, Magnetic Partical Examination F.

Visual Examination Procedures 1.

YA-VT-1, Visual Examination 2.

QCP-3110, Mercury Company, Visual Examination 4.

OP 4101, Rev. 8, Vermont Yankee RPV Operational Hydro Test G.

Radiographic Examination Procedures 1.

20.A.1-3, Peabody Testing, Radiographic Examination of Welds 11.

Abstract of Conditions Noted A.

Category B-H 1.

During visual inspection of two of four vessel stabilizer brackets, nuts which secure the brac.kets to the top of the biological shield wall were found to be loose and to have inadequate clearance between the nut and the bracket to permit thermal expansion. As required by IWB-2430, the other two brackets were visually examined for this condition, and the same deficiency was discovered.

B.

Category B-K-2 1.

During visual examination of hangers on the Feedwater System, one of two spring hangers inspected, FW-12, was found to have a loose clamp bolt. As required by IWB-2430, additional examinations were conducted on an equivalent tumber of similar components in this system, and no further rejectable conditions were discovered.

Page 23 of 27

1

~

~

1. Owner Vermont Yankee Nuclear Power cnrn..

77 crnun Strone nuel,nd "e

05701 (Name and Address of Owner)

Vermont Yankce Nuclear Power Station, P.O. Box 157. Vernon. Vt 05354

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 11.

Abstract of Conditions Noted (Continued) is.

Category B-K-2 (Continued) 2.

During visual examinations of hangers on the Main Steam System, the following conditions were noted:

On Main Steam "A", one spring hanger inspected, MS-2, a.

was found to have a loose clamp bolt.

I b.

On Main Steam "B", one spring hanger inspected, MS-13, was found to have a loose clamp bolt.

On Main Steam "D", one spring hanger inspected, MS-30, c.

was found to have a loose clamp bolt.

I In each case an additional examination was conducted on a similar component in the system and no further rejectable conditions were discovered.

C.

Category B-G-2 1.

During visual examination of bonnet bolting removed from RHR Shutdown Cooling Check Valve V10-46A as part of normal maintenance activities, galling was discovered on the threaded portion of one of four bolts inspected. Since inspections of bolt threads are performed only when components are disassembled for other reasons, and no other components were disassembled during this outage, no additional thread examinations were conducted.

D.

Category C-E-2 1.

During visual examination of hangers on the RHR Containment Spray Subsystem, the following conditions were noted:

One spring hanger, CS-HD-54B, was inspected on one of a.

two torus spray lines and was found to have an unacceptable load setting. This hanger was also found to be mounted incorrectly on its supporting channels such that the rod bearing the pipe was binding on one of the channels, thereby potentially restricting its ability to perforr. as designed.

As required by IWC-2430, a similar component on the redundant torus spray line was examined, and no further rejectable conditions were discovered.

s Page 24 of 27

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1. Owner Vermont Yankee Nuclear Power Corn-77 crnun Strnor - nuel,na eft n5701 (Name and Address of Owner)
2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon. Vt 05354 (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None j

11.

Abstract of Conditions Noted (Continued)

D.

Category C-E-2 b.

One spring hanger, H-191, was inspected on one of two drywell spray lines and was found to have an unacceptable load setting. As required by IWC-2430, another spring hanger on this line, HD-87, was examined and was also found to have an unacceptable load setting. At this point, the scope of the inspection was expanded to in-clude all components of similar size, type, and function on this line and on the redundant drywell spray line.

This inspection resulted in the discovery of one additional spring hanger, HD-87D, with an unacceptable load setting.

2.

During visual examination of hangers on the north and south Control Rod Drive Scram Discharge Volumes, one of two rod f

hangers inspected, H-17, was found to have a loose clevis bolt and a misaligned clevis. As required by IWC-2430, two additional similar components were examined and one, H-15, was found to have a loose clevis bolt and no load on the rod.

These four rod hangers constitute all components of similar size, type, and function on this piping.

3.

During visual examination of one spring hanger, HD-188D, on one of two RHR Shutdown Cooling Heat Exchanger outlet lines, inadequate thread protrusion was discovered on the clevis bolt.

As required by IWC-2430, a similar component on the redundant RHR Shutdown Cooling loop was examined, and no further reject-able conditions were found.

E.

Code Subarticle IWD-2410 (c) 1.

During visual examination of hangers on the Service Water System, one rigid hanger, H-59, on one of two Emergency Diesel Generator Cooling supply lines was found to have loose nuts on one rod.

No additional examinations ere required by ASME Section XI, 1974 Edition, Summer 1975 Addenda, for Class 3 systems.

Page 25 of 27 i

i

1

1. Owner Vermont Yankee Nuclear Pever enrn. _ 77 centm strone nuet,na ve n5701 (Name and Address of Owner)

Vermont Yankee Nuclear Power Station, P.O. Box 157. Vernon. Vt 05354

2. Plant (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DpR-28 l

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 12.

Abstract of Corrective Measures Recommended and Taken A.

Category B-H J

1.

All nuts on the four vessel stabilizer brackets were adjusted to obtain the required clearance, and the set screws which hold them in place on the studs were tightened.

In addition, a second set screw was installed on each nut to prevent backing off of the first screw due to vibration. This action was completed, visually reinspected, and accepted prior to plant i

startup.

B.

Category B-K-2 1.

The loose bolt on Feedwater spring hanger FW-12 was tightened, visually reinspected, and accepted prior to plant startup.

2.

The loose bolts on the Main Steam spring hangers were tightened, visually reinspected, and accepted prior to plant startup.

C.

Category B-G-2 l

1.

The galled thread on one bolt. removed from the RHR Shutdown i

Cooling check valve was repaired as part of the maintenance effort for which the valve was disassembled. This action was completed, visually reinspected, and accepted prior to reassembly of the valve.

In addition, the valve was visually inspected for leakage during the primary coolant system leakage test.

D.

Category C-E-2 1.

a.

The tack welds holding spring hanger CS-HD-54B in place on the supporting channels were removed, the spring can was centered between the channels to provide proper clearance for the rod and rewelded, and the load setting was adjusted to within specification requirements. These actions were completed, visually reinspected, and accepted prior to plant startup.

b.

All drywell spray line egring hanger load settings were adjusted to within specification requirements, visually reinspected, and accepted prior to plant startup.

Page 26 of 27

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1. Owner Vermout Yankee Nuclear Pouer Cnrp.. 77 cvmm Stroor Riv e i rm A, Ue A5701 (Name and Address of Owner)
2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon. Vt 05354 (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit
5. Commercial Service Date 11/30/72 6. National Board Number for Unit None 12.

Abstracts of Corrective Measures Recommended and Taken (Continued)

D.

Category C-E-2 (Continued) 2.

All discrepancies on CRD Scram Discharge Volume rod hangers were corrected, visually reinspected, and accepted prior to l

plant startup.

3.

Inadequate thread protrusion on spring hanger HD-188D was corrected by replacing the existing bolt with a longer one of comparable quality. This action was completed, visually reinspected, and accepted prior to plant startup.

E.

Code Subarticle IWD-2410 (c) i The existing welded nuts on Service Water hanger H-59 were replaced with a load nut and lock nut configuration, following an l

engineering evaluation and recommendation. This action was j

completed, visually reinspected, and accepted prior to plant startup.

l l

f 1

Page 27 of 27 i

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1. Owner Vermotat Yankee Nucicar Pnver Cnrn..

77 crma S t ra a t-Devel,na tre n5701 l

(Name and Address of owner)

2. Plant Vermont Yankee Nuclear Power Station. P.O. Box 157, Vernon. Vt 05354 (Name and Address of Plant) 1
4. Owner Certificate of Authorization (if required)

DPR-28

3. Plant Unit

~

5. Commercial Service Date 11/30/72 6. National Board Number for Unic None Authorized Nuclear Inservice Inspector Exceptions:

A. Abstract of Examinations Page 7 t

Category B-0 l

CRD Housing to Flange Welds f

Originally, o,ne weld was due to be examined. Due to obstructions, only one-third of the weld was examined. To satisfy requirements, one-third of Weld No's 22-03 and 26-03 were examined.

B. Page 11 Category B-G-1 Pump P-18-1A Cover to Casing Bolts and Nuts t

Four bolts required examination. As the bolts were not marked for identification, all bolts were examined. Credit for bolt no's

1. 5, 9 and 13 is taken. Bolt no's 1, 5, 9 and 13 cannot be ident-ified as the bolts examined.

I

'sc/lG'Le/u

.i W v

Richard L. Lane I

Authorized Nuclear Inservice Inspector l

l Page 27a of 27 1

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