ML20080J425

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Inservice Insp Rept for 830305-0616.Rept Describes Exams Performed of Final Outage of Third Period of First 10-yr Interval
ML20080J425
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 08/30/1983
From:
VERMONT YANKEE NUCLEAR POWER CORP.
To:
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ML20080J418 List:
References
NUDOCS 8309260353
Download: ML20080J425 (48)
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Text

._.

VERMONT YANKEE NUCLEAR POWER CORPORATION 1983 INSERVICE INSPECTION

SUMMARY

REPORT M ARCI! 5,1983 TIIROUGli JUNE 16,1983 PREPARED BY

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' PLpT INSERVICE SPE TION COORDINATOR APPROVED BY p

p, ENGINEERING SUFPOp SUPERVISOR 8309260353 830914 0500027 gDRADOCK

_-. = _. - _ - -.._ _

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 i

for Inservice Inspections I

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VERMONT YANKEE NUCLEAR POWER CORPORATION 1983 INSERVICE INSPECTION

SUMMARY

REPORT MARCil 5,1983 TIIROUGli JUNE 16,1983 1.

INTRODUCTION The attached Form NIS-1, " Owners' Data Report for Inservice Inspection" describes the inservice inspections performed during 1983 at the Vermont Yankee Nuclear Power Station, Vernon, Vermont. The examinations performed were those of the final 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 Boller 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 examina-tion and the methods used were in accordance with the Vermont Yankee In-service Inspection Program and the plant Technical Specifications. This report summarizes the components examined, the types of examination, the non-con-forming conditions noted, and the corrective actions taken. Ultrasonic, liquid penetrant, magnetic particle and visual examination techniques were employed to perform the required examinations.

2.

EXAMINATION METIIODS 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-1 A 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 Specification requirements. The inservice examinations were performed and evaluated by personnel qualified to the 1975 edition of SNT-TC-1 A. The procedures used for these examinations are listed in Section 10 of the NIS-I Form.

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3.

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

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

4.

EXAMINATION RESULTS A list of the examinations that were performed is contained in Section 10 of the NIS-I Form. The detailed examination data along with the calibration records, procedures, equipment cerifications and personnel certifications are maintained at the plant site.

Except for the conditions,Jreviously described in our response to NRC IE Bulletin 83-2, no rejectable conditions other than those described in Section II of the NIS-I Form were noted during these examinations. Upon completion of the corrective actions detailed in Section 12 of the NIS-1 and upon NRC acceptance of our response to Bulletin 83-02, there were no remaining unacceptable conditions.

No continuing or followup items resulted from mandatory examin-ations performed under ASME Section XI.

CONCLUSIONS The scheduled inspections accomplished during the 1983 Inservice In-spection constituted 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 1983 Inservice Inspection,100% of all inspections required for this inspection interval had been performed.

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., RD 5 Box 169, Ferry Rd., Brattleboro, Vt.

(Name and Address of Owner) 05301 Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, Vt.

05354

2. Plant (Name and Address of Plant)

DPR-28

3. Plant Unit
4. Owner Certificate of Authorization (if required)
5. Commercial Service Date 11/30/7?
6. National Board Number for Unit None
7. Components inspected

}

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

Province No.

Board No, SAFETf CL\\SS 1 REACTOR VESSEL 4 closure head welds Chicago Bridge & Iron B 4698 N/A N/A 11 bottom head welds Chicano Bridae & Iron B 4698 N/A N/A 2 shell long-itudinal welds Chicago Bridge & Iron B 4698 N/A N/A 1 shell to flange weld Chicago Bridge & Iron B 4698 N/A N/A 10 nozzle to vessel welds Chicago Bridge & Iron B 4698 N/A N/A 1 CRD housing weld Chicago Bridge & Iron B 4698 N/A N/A 3 nozzle to safe end welds Chicaco Bridae & Iron B 4698 N/A N/A 8 vessel clo-sure studs Chicano Bridee & Iron B 4698 N/A N/A 8 vessel closurn nuts chicnco Bridee & Tron R 469R N/A N/A 8 vessel clo-e.,vo u,ekarc Chicaco Bridae & Iron B 4698 N/A N/A l

8 vessel flange l

ligaments Chicago Bridge & Iron B 4698 N/A N/A Various vessel internals Chicago Bridge & Iron B 4698 N/A N/A Various inter-nni attachment.; Chicano Bridge & Iron B 4698 N/A N/A 28 CRD r

Penetrations Chicago Bridge & Iron B 4698 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 1 of 44

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FORM NIS 1 (back)

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s. Examination Dates 3/5/83 6/16/83
9. Inspection Interval from 11/30/72 o 6/16/83 to t
10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

See attached pages.

11. Abstract of Conditions Noted See attached pages.
12. Abstract of Corrective Measures Recommended and Taken I

See attached pages.

4 l

We certify that the statements made in this report are correct and the examinations and corrective mea-I.

sures taken conform to the rules of the ASME Code,Section XI.

Vermont Yankee Nuclear Y /(.

19 83. Signedpowe enepneerinn By #

i

_M Date O*""

Plant Manager Certificate of Authorization No. (if applicable)

DPR - 28 Expiration DateDecember-11, 2007 CERTIFICATE OF INSERVICE INSPECTION 9

f 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 Stonm Biolemf Ilartford. Conn. have inspected the components described in this Owners' Data Report during the period March 5, 1983 to June 16. 1983. 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 measures described in this Owners' Data Repor*. rorthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

Date September 13, 19 83

_d M._. Commissions Vermont 318 Inspector's Signature National Board, State. Province and No.

1 1

t 2 of 44 l

j

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., RD 5 Box 169, Ferry Rd., Brattleboro, Vt.

(Name and Address of Owners 05301

2. Plant Vermont Yankee Nulcear Power Station, P.O. Box 157, Vernon, Vt. 05354 (Name and Address of Plant)

DPR-28

3. Plant Unit
4. Owner Certificate of Authorization (if required)
5. Commercial Service Date 11/30/72
6. National Board Number for Unic None
7. Components inspected l

Manufacturer l

Component or Manufacturer or installer State or Na tional Appurtenance or Installer Serial No.

Provmce No.

Board No.

1 Vessel l Chicago Bridge & Iron N/A l

N/A i

N/A l

l Support i

SAFETY CLASS 1 PIPING 59 Per referenced isometrics.

Piee welds EBASCO N/A N/A N/A 2 >6" branch Per referenced isometrics connect. weld!

EBASCO N/A N/A N/A 53 supports /

Per referenced isometrics hangers EBASCO N/A N/A N/A 12 <2" bolts Per referenced isometrics EBASCO N/A N/A N/A PUMPS Per referenced isometrics 1 Support enasco v/3 of1 v/s VALVES Per referenced isometrics 68 4,,,, bolts EBASCO N/A N/A N/A l

SAFETY CLASS 2 VESSELS 23 >1" bolts Per referenced isometrico EBASCO N/A N/A N/A PIPING l

Per referenced isometrico 20 >1" bolts

'* / A N/A EBASCO v/A 78 supports /

Perreferencedisometricj l

l h an ce r s rRAcen N/A N/A N/s 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 1 through o on this data report is inciuded on eacn sheet. and ( 3) each sheet is numbered and the numoer of sheers is recorded at the top of this form.

This forrn tE000291 eav ce cetained frern tne Creer Cect., ASVE, 345 E. 47th St., New York, N.Y.

10017 3 of 44

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. RD 5, Box 169, Ferry Rd., Brattleboro, Vt.

(Name and Address of Owner) 05301

2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, Vt. 05354 (Name and Address of Plant)
3. Plant Unit 1

DPR-28

4. Owner Certificate of Authorization (if required)
5. Commercial Service Date 11/30/72
6. National Board Number for Unit None
7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or installer Serial No.

Province No.

Board No.

58 Supports /

Per referenced isometrics hangers Mercury Co.

N/A N/A N/A Per referenced isometrics 8 pipe welds EBASCO N/A N/A N/A Per referenced isometrics 32 pipe welds Mercury Co.

N/A N/A N/A VALVES Per referenced isometrics 32 >1" bolts EBASCO N/A N/A N/A SAFETY CLASS 3 PIPING 102 supportsf-Per referenced isometrics hnngers ERASCO N/A N/A N/A 6 supports /

Per referenced isometrics hnngnrn Morenry Cn.

N/A N/A M/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 1 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 4 of 44

l. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Cert)ficate Authoriztion (if required)

DPR-28

5. Commercial Service Date 11/30/72
6. National Board Number for Unit None L
10. Abstract of Examination

[

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

SAFETY CLASS 1 REACTOR B-B Closure Head Meridional Welds B-3 UT

.H-22 B-4 UT H-22

.B-5 UT H-22 B-6 UT H-22 Bottom Head Meridional Welds H-1 UT H-22 H-2 UT H-22 H-3 UT H-22 H-4 UT H-22 H-5 UT H-22 H-6 UT H-22 11-7 UT H-22 H-8 UT H-22 Dollar Plate Circumferential Weld H-J UT H-22 Dollar Plate Longitudinal Welds J-1 UT H-22 J-2 UT H-22 Vessel Shell Longitudinal Welds D-1 UT H-22 D-2 UT H-22 i.

B-C Vessel Shell to Flange Weld

'C-D UT H-22 5 of 44 L

)

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

D PR-28

5. Commercial Service Date 11/30/72
6. National Board Number for Unit None
10. Abstract of Examination I

A. Nondestructive Examinations Component Component Category Description Identification Examination Isometric (1) 1 B-D Nozzle to Vessel Welds N2F UT H-22 N2H UT H-22 N2K UT H-22 N3D UT H-22 N6A UT-H-22 N6B UT H-22 N7 UT H-22 N8A UT H-22 N8B UT H-22 N10 UT H-22 B-E CRD Stub Tube to Housing Weld 18-03 UT(2)

H-25 B-F Nozzle to Safe-End Welds N2F-SE UT,PT,VT H-1 N2H-SE UT,PT,VT H-1 N2K-SE UT,PT,VT H-1 B-G-1 Vcssel Closure 43 through 46 UT,PT H-21 Studs and Nuts 61 through 64 UT,PT H-21 Vessel Closure 43 through 46 VT H-21 Washers and 61 through 64 VT 11-2 1 Bushings (3)

Vessel Flange 43 through 46 UT H-21 Ligaments 61 through 64 UT H-21 l

B-II Support Skirt None M PT,PT,UT None I

to Vessel Weld l

6 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

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)

B-N-1 Vessel Interior Jet Pump VT None Assemblies Shroud Annulus VT None Feedwater VT None Sparger and Brackets Core Spray VT None Sparger and Brackets Accessible Portions of:

Standby VT None Liquid Control Line Differential VT None Pressure Line Shroud Weld VT None CRD liousings VT None CRD Housing to VT None i

Stub Tube Welds I

Stub Tube to VT None RPV Welds Incore Housing to VT None Incore Guide Tube Welds Incore Guide Tube VT None Stabilizers 7 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169. Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

D PR-28

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)

B-N-1 Vessel Interior (Cont'd)

Bottom Head, VT None General Area B-N-2 Interior Attachments Steam Dryer VT None and Core Support Support Brackets Structures and Welds Guide Rod Brackets VT None and Welds Dryer Hold-down VT None Brackets and Welds Surveillance VT None Specimen Support Brackets and Welds B-O CRD Housing Penetrations 02-27 VT(4)

H-25 02-23 VT(4)

H-25 02-19 VT(4)

H-25 06-15 VT(4)

H-25 06-11 VT(4)

H-25 10-07 VT(4) 11-2 5 14-07 VT(4)

H-25 18-03 VT(4)

H-25 22-03 VT(4)

H-25 26-03 VT(4)

H-25 30-07 VT(4)

H-25 34-07 VT(4)

II-25 38-11 VT(4)

H-25 42-19 VT(4)

H-25 42-23 VT(4)

H-25 42-27 VT(4)

H-25 38-31 VT(4)

H-25 8 of 44 l

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 189, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

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)

B-O CRD Ilousing 38-35 VT(4) 11-2 5 Penetrations (Cont'd) 34-39 VT(4) 11-2 5 30-39 VT(4) 11-25 26-43 VT(4) 11-25 22-43 VT(4) 11-2 5 18-43 VT(4) 11-2 5 14-39 VT(4) 11-2 5 10-39 VT(4) 11-2 5 06-35 VT(4)

H-25 06-31 VT(4) 11-2 5 38-15 VT(4)

H-25 SAFETY CLASS 1 PIPING B-J Circumferential and Recire Riser N2A Longitudinal Welds Weld 45 UT(5) 11-1 Weld 44 UT(5)

H-1 Weld 43A UT(5) 11-1 Weld 43 UT(5)

H-1 Recire Riser N2B Weld 42 UT(5) 11-1 Weld 41 UT(5) 11-1 Weld 40A UT(5) 11-1 Weld 40 UT(5) 11-1 Recire Riser N2C Weld 36 UT(5) 11-1 Weld 35 UT(5) 11-1 Weld 34A UT(5) 11-1 Weld 34 UT(5) 11-1 Recirc Riser N2D Weld 33 UT(5) 11-1 Weld 32 UT(5)

H-1 Weld 31A UT(5) 11-1 Weld 31 UT(5) 11-1 Recire Riser N2E Weld 30 UT(5) 11-1 Weld 29 UT(5) 11-1 Weld 28A UT(5)

H-1 Weld 28 UT,VT(5)(6) 11-1 m eR ea

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

5. Commercial Service Date 11/30/72
6. National Board Number for Unit ITone
10. Abstract of Examination A. Nondestructive Examinatit,...

Component Component Category Description Identification Examination Isome+ric (1)

B-J Circumferential and Longitudinal Welds Recire Riser N2P Weld 23 UT(5) 11-1 Weld 24 UT(5) 11-1 Weld 24A UT(5)(7) 11-1 Weld 25 UT,VT(5)(6) 11-1 Recire Riser N2G Weld 20 UT(5) 11-1 Weld 21 UT(5) 11-1 Weld 21 A UT(5) 11-1 Weld 22 UT(5) 11-1 Recire Riser N211 Weld 16 UT(5) 11-1 Weld 18 UT(5) 11-1 Weld 18A UT(5) 11-1 Weld 19 UT(5) 11-1 Recire Riser N2J Weld 53 UT(5) 11-1 Weld 54 UT(5)

II-1 Weld 54A UT(5) 11-1 Weld 55 UT(5) 11-1 Recire Riser N2K Weld 50 UT(5) 11-1 Weld 51 UT(5) 11-1 Weld 51 A UT(5) 11-1 Weld 52 UT,VT(5)(6) 11-1 l

10 of 44 L

1. Owner _ Vermont Yenkte Nucleer Powrr Corp., RD 5, Box 169, Ferry Ro d, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

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)

B-J Circumferential and Longtudinal Welds Recire Ring Header Weld 16B UT(5)

H-1 Weld 23A UT(5)

H-1 Weld 30A UT(5)

H-1 Weld 30B UT(5)

H-1 Weld 36B UT(5)

H-1 Weld 46 UT(5)

H-1 Recirc Loop A Weld 1 A UT(5)

H-2 Weld 2 UT(5)

H-2 Weld 9A UT(5)

H-2 Weld 9B UT(5)

H-2 Weld 15A UT(5)

H-2 Recire Loop B Weld 17 UT(5)

H-3 Weld 38 UT(5)

H-3 Weld 58 UT(5)

H-3 Weld 59 UT(5)

H-3 Weld 64 UT(5)

H-3 Weld 65A UT(5)

H-3 Weld 66 '

UT(5)

H-3 RHR A Weld 4 UT(5)

H-4 RHR B Weld 1 UT(5)

H-5 MS-7A Weld 11 UT,VT H-14 11 of 44

1. Ownte Vermont Ycnkee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

D PR-28

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)

B-K-1 Integrally Welded Recirc Ring Header Supports RR-37 VT(8)

H-1 RR-44 VT(8)

H-1 R R-49 VT(8)

H-1 RR-52 VT(8)

H-1 R R-59 VT(8)

H-1 Recire Loop A RR-10 VT(8)

H-2 RR-11 VT(8)

H-2 RR-15 VT(8)

H-2 R R-16 VT(8)

H-2 R R-17 VT(8)

H-2 Recire Loop B R R-86 VT(8)

H-3 RR-87 VT(8)

H-3 RR-83 VT(8)

H-3 RR-84 VT(8)

H-3 RR-85 VT(8)

H-3 B-K-2 Non-Welded Recire Ring Header Supports RR-45 VT H-1 RR-47 VT H-1 RR-54 VT H-1 RR-36 VT(12)

H-1 RR-41 VT(1?)

H-1 RR-43 VT(12)

H-1 R R-46 VT(12)

H-1 RR-56 VT(12)

H-1 i

RR-58 VT(12)

H-1 RR-61 VT(12)

H-1 1

Recire Loop A RR-7 VT(8)

H-2 R R-8 VT(8)

H-2 R R-22 VT(8)

H-2 RR-23 VT(8)

H-2 12 of 44

r-

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

' 5. Commercial Service Date 11/30/72

6. National Board Number for Unit None
10. Abstract of Examination A. Nondestructive Examinations i

Component Component i

Category Description Identification Examination Isometric (1)

B-K-2 Non-Welded Supports Recirc Loop A R R-25 VT(8)

H-2 RR-26 VT H-2 RR-29 VT(8)

H-2 R R-30 VT(8)

H-2 RR-31 VT H-2 RR-33 VT H-2 l

Recirc Loop B RR-89 VT(8)

H-3 R R-90 VT(8)

H-3 R R-75 VT(8)

H-3 RR-74 VT(8)

H-3 RR-72 VT(8) 11-3 RR-71 VT(8)

H-3 RR-66 VT(8)

H-3 RR-65 VT(8)

H-3 Line MS-7A MS-4 VT 11-14 MS-7 VT H-14 Line MS-7B MS-15 VT H-15 Line FDW-21 FW-8 VT 11-7 Line FDW-20 F W-13 VT(9)

~i-8 13 of 44

r-

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres of Owner)
2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, VT 05354 (Name and Address of Plant)
3. Plant Unit i
4. Owner Certificate Authoriztion (if required)

DPR-28

5. Commercial Service Date 11/30/72
6. National Board Number for Unit None
10. Abstract of Examination A. Nondestructive Examinations Component Component Catrgory Description Identification Examination Isometric (1)

B-K-2 Non-Welded Supports Line CUW-18 CU-7 VT 11 - 1 3 CU-6 VT(9) 11-1 3 CU-8 VT(9) 11-13 C U-9 VT(9) 11-1 3 Line MS-5A 11-6 0 VT H-19 B-G-2 Bolting <2" Diameter and Corresponding Nuts Line MS-7A SV-A VT H-14 Inlet Flange (12 bolts in place)

SAFETY CLASS 1 PUMPS lt B-K-2 Non-Welded Supports Pump P-18-1 A Support RR-21 VT 11-2 SAFETY CLASS 1 VALVES B-G-2 Bolting <2" Diameter and Corresponding Nuts Recirc A Bypass Valve V2-54 A VT 11-2 (10 bolts in place) 14 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

D PR-28

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)

B-G-2 Bolting <2" Diameter and Corresponding Nuts Line FDW-19 Valve V2-29A VT H-7 (6 bolts in place)

Line CUW-18 Valve V12-18 VT H-13 (4 bolts in place)

Line MS-7C Valve V2-86C VT H-16 (18 bolts in place)

Line MS-7D I

Valve V2-86D VT H-17 (18 bolts in place)

Line MS-7A Valve SV2-70A VT H-14 (12 bolts, removed)

SAFETY CLAS? 2 VESSELS C-D Bolting >1" Diameter i

and Corresponding Nuts RHR "B" R H R-H X-B VT l-20 (23 bolts in place) 15 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

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 2 PIPING C-D Bolting >1" Diameter and Corresponding Nuts Line RHR-3A Flange, RO-10-105A VT I-10 A (20 bolts in place)

C-E-1 Integrally Welded Supports Line HPCI-2 Support H-26 PT I-5 Support 11-24 VT(10)(11)

I-5 Support IID-24 VT(10)(11)

I-5 Support HD-26A VT(10(11)

I-5 Support IID-26B VT(10)(11)

I-5 Support H-28 VT(10)(11)

I-5 Support HD-28 VT(10)(11)

I-5 Line HPCI-15B Support HD-22D VT(10)

I-4 Support H-22 VT(10(11)

I-5 Support HD-22A VT(10)(11)

I-5 l

Support HD-22B VT(10)(11)

I-4 Support HD-22E VT(10)(11)

I-4 Support H-35 VT(10)(11)

I-4 Support HD-35A VT(10)(11)

I-4 Support HD-35B VT(10)(11)

I-4 Support HD-35C VT(10)(11)

I-4 l

Support HD-35D VT(10)(11)

I-4 l

l l

l l

16 of 44

1.' Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28 1

5. Commercial Service Date 11/30/72

'6. National Board Number for Unit None j

' 10. Abstract of Examination A. Nondestructive Examinations Component Component Category Description Identification Examination Isometric (1)

C-E-1 Integrally Welded Supports Line MS-4B Support HD-13B

.VT(10)

I-2 Line RHR-1B Support H-22 PT,VT(12)

Under Development Support HD-127A VT(10)

I-7 B Support HD-127B VT(11)

I-7B Line RHR-2B Support HD-127D PT I-9 Line RHR-3D Support HD-188C PT I-10B Line RHR-8 Support H-16 PT,VT(12)

Under Development h

Line RHR-10 i

l Support H-83 PT,VT(12)

I-15 Line RHR-15 i

Support H-98 PT,VT(12)

Under Development Support CS-H-86B PT,VT(12) i 17 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

5. Commercial Service Date 11/30/72
6. National Board Number for Unit None
10. Abstract of Examination A. Nondestructive Examinations 2 -

Component Component Category Description Identification Examination Isometric (1)

C-E-1 Integrally Welded Supports Line RHR-23 Support CS-HD-54H PT,VT(12)

Under Development Line RHR-40 Support HD-37 VT(10)

I-17 Support HD-3 VT(10)

I-17 Fupport HD-5 VT(10)

I-17 Line CS-2A Support HD-61B VT(10)

I-6A Support CS-H-52 PT,VT(12)

Under Devt Oment Support CS-H-61 PT,VT(12)

Under Development 4

Support CS-H-89 PT,VT(12)

Under Development Support CS-H-90 PT,VT(12)

Under Development Line CS-2B Support CS-II-45 PT,VT(12)

Under Development Support CS-H-46 PT,VT(12)

Under Development Support CS-H-55 PT,VT(12)

Under Development Support CS-H-84 PT,VT(12)

Under Development j

Support CS-H-85C PT,VT(12)

Under Development CRD Scram Discharge Instrument Volume (North)

Support SDV-N-R11 PT(12)

Under Development Support SDV-N-A01 PT(12)

Under Development CRD Scram Discharge i

Instrument Volume (South)

Support SDV-S-ROI PT(12)

Under Development Support SDV-S-A01 PT(12)

Under Development 18 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

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)

C-E-2 Non-Welded Supports CRD Scram Discharge Header (North)

Support SDV-N-H01 VT(12)

Under Development Support SDV-N-R10 VT(12)

Under Development Support H-1 VT(12)

Under Development Support 11-2 VT(12)

Under Development Support H-3 VT(12)

Under Development Support H-4 VT(12)

Under Development Support H-5 VT(12)

Under Development Support H-6 VT(12)

Under Development Supoort H-7 VT(12)

Under Development Support H-8 VT(12)

Under Development Support H-9 VT(12)

Under Development Support H-10 VT(12)

Under Development Support H-11 VT(12)

Under Development Support 11-12 VT(12)

Under Development Support H-13 VT(12)

Under Development Support H-14 VT(12)

Under Development Support H-17 VT(12)

Under Development Non-Welded Supports CRD Scram Discharge Header (South)

Support SDV-S-H01 VT(12)

Under Development Support H-18 VT(12)

Under Development Support H-20 VT(12)

Under Development Support H-21 VT(12)

Under Development Support H-22 VT(12) under Development Support H-23 VT(12)

Under Development Support H-24 V'I(12)

Under Development Support H-25 VT(12)

Under Development Support H-26 VT(12)

Under Development 19 of 44 L

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres of Owner)
2. Plant - Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, VT 05354 (Name and Address of Flant)
3. Plant Unit 1
4. Owner Certificate Authoriztion (if required)

DPR-28

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)

C-E-2~

Non-Welded Supports CRD Scram Discharge Header (South)

Support H-28 VT(12)

Under Development Support H-29 VT(12)

Under Development Support H-30 VT(12)

Under Development Support H-31 VT(12)

Under Development Support H-32 VT(12)

Under Development Support H-33 VT(12)

Under Development Support H-34 VT(12)

Under Development Support H-35 VT(12)

Under Development Support H-36 VT(12)

Under Development Line HPCI-15B Support HD-22C VT I-4 Support H-32 VT(12)

I-4 Line HPCI-3 Support H-39 VT(12)

I-3 Support H-107 VT(12)

I-3 Support H-108 VT(12)

I-3 Line MS-4B Support HD-102B VT I-2 Support H-103A VT I-2 Support H-3 VT(11)(12)

I-2 Support HD-3 VT(11)

I-2 Support H-5 VT(11)

I-2 Support H-6 VT(11)

I-2 Support HD-6 VT(11)

I-2 Support HD-8C VT(11)

I-2 20 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RI' 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

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)

C-E-2 Non-Welded Supports Line MS-4B Support HD-13A VT(11)

I-2 Support HD-102A VT(11)

I-2 Support H-103B VT(11)

I-2 Support IID-103C VT(11)

I-2 Support HD-102D VT(11)

I-2 Line RHR-1 A Support H-181 VT(12)

I-7A Support H-185F VT(12)

Under Development Support H-183 VT(12)

I-8 Line RHR-1B l

Support H-127 VT(12)

I-7 Support HD-127K VT(12)

I-7B Support HD-127M VT(12)

Under Development Line RHR-2A Support 11-184 VT(12)

I-8 Support HD-184A VT(12)

Under Development Support HD-184B VT(12)

Under Development Line RHR-2B Support HD-127J VT(12)

I-9 Support HD-127L VT(12)

Under Development Support HD-127C VT(12)

I-9 Support HD-127D VT(12)

I-9 Line RHR-2D Support HD-127F VT(12)

I-9 Support HD-127G VT(12)

I-9 21 of 44

  • mi+

-e

~,

._9g

,.,-&-rT7y

'---""4 wr

-v-7w

, w yra

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28 I

5. Commercial Service Date 11/30/72
6. National Board Number for Unit None I
10. Abstract of Examination A. Nondestructive Examinations Component Component Category Description Identification Examination Isometric (1)

C-E-2 Non-Welded i

Supports Line RIIR-3B Support HD-129C VT I-10B Line RHR-3A Support HD-130B VT(12)

I-10 A Line RilR-3D Support HD-188B VT I-10B Line RIIR-7 Support HD-16B VT I-13 Line RHR-8 Support IID-200J VT I-14 Line RHR-10 Support H-192 VT I-15 Support CS-HD-54E VT(12)

I-15 Line RHR-12 Support CS-HD-86A VT(12)

I-16 Line RHR-15 Support ilD-134 VT(12)

I-16 i

Support CS-H-86A VT(12)

I-16 Line RHR-17 Support CS-HD-54A VT(12) 1-15

+

)

22 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres of Owner)
2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, VT 05354 (Name and Address of Plant) j
3. Plant Unit 1
4.. Owner Certificate Authoriztion (if requireci)

DPR-28 i-i

5. Commercial Service Date 11/30/72
6. National Board Number for Unit None 9
10. Abstract of Examination j

A. Nondestructive Examinations I

Component Component Category Description Identification Examination Isometric (1)

C-E-2 Non-Welded Supports Line RIIR-20 i

Support CS-IID-86C VT(12)

I-16 l

Line RIIR-23

(

Support CS-IID-54C VT(12)

I-15 Line CS-2A Support 11-54 VT(12)

I-6A

[

Support IID-90B VT(12)

I-6A Support ilD-90C VT(12)

Under Developmen0 f

Line CS-2B Support CS-H-42 VT(12)

I-6 B Support CS-II-43 VT(12)

I-6 B l

Support CS-II-46 VT(12)

I-6B l

Support CS-IID-55B VT(12)

I-6B l

Support CS-IID-85D VT I-6B Line CS-3B Support CS-IID-42 VT(12)

I-6B Line CS-6 A Support CS-11D-54G VT(12)

I-6A C-F Pressure Retaining Welds In Piping Which Circulates Reactor Coolant Line RIIR-1B Weld S-9 UT I-7 B 23 of 44 ~

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres of Owner)
2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, VT 05334 (Name and Address of Plant)
3. Plant Unit 1
4. Owner Certificate Authoriztion (if required)

D PR-28

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)

C-F Pressure Retaining Welds In Piping Which Circulates Reactor Coolant Line RHR-2B Weld S-7 UT I-9 Line RHR-3A Weld S-4 UT I-10 A Line RIIR-5A Weld S-1 UT I-11 C-G Pressure Retaining Welds In Non-Reactor Coolant Piping Line HPCI-3 Weld F-2 UT I-3 Line CS-3B Weld S-3 UT I-6B Line RHR-17 Weld S-7 UT I-15 Line RIIR-40 Weld S-13 UT I-17 24 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro. VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

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)

C-G Pressure Retaining Welds In Non-Reactor Coolant Piping CRD Scram Discharge Instrument Volume (North)

Weld 4 UT(12)

Under Development Weld 5 UT(12)

Undcr Development Weld 6 UT(12)

Under Development Weld 20 UT(12)

Under Development CRD Scram Discharge lleader (North)

Weld 6A-1 A UT(12)

Under Development Weld 6A-2A UT(12)

Under Development Weld 6A-3A UT(12)

Under Development Weld 6 A-5 A UT(12)

Under Development Weld 6A-6 A UT(12)

Under Development Weld 6 A-7 A UT(12)

Under Development i

Weld 6A-8 A UT(12)

Under Development Weld 6 A-9 A UT(12)

Under Development Weld 6A-10A UT(12)

Under Development Weld 6A-11 A UT(12)

Under Development i

Weld 6A-12A UT(12)

Under Development l

Weld 6A-13A UT(12)

Under Development Weld 6 A-14 A UT(12)

Under Development CRD Scram Discharge Instrument Volume (South)

Weld 4 UT(12)

Under Development Weld 5 UT(12)

Under Development Weld 6 UT(12)

Under Development Weld 7 UT(12)

Under Development i

Weld 20 UT(12)

Under Development L -.

25 of 44

1. Owner' Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

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)

C-G Pressure Retaining Welds in Non-Reactor Coolant Piping (Cont'd)

CRD Scram Discharge lleader (South)

Weld SA-1 A UT(12)

Under Development Weld SA-2A UT(12)

Under Development Weld SA-3A UT(12)

Under Development Weld SA-5A UT(12)

Under Development Weld 5A-6A UT(12)

Under Development Weld SA-7A UT(12)

Under Development l

Weld SA-8A UT(12)

Under Development l

Weld 5A-9A UT(12)

Under Development Weld SA-10A UT(12)

Under Development Weld SA-11 A UT(12)

Under Development SAFETY CLASS 2 i

VALVES Bolting >1" Diameter and Corresponding Nuts Line RHR-6 Valve V10-65A VT I-12 (32 bolts in place) 26 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres of Owner) j i
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 Authoriztion (if required)

DPR-28

5. Commercial Service Date 11/30/72
6. National Board Number for Unit None
10. A_bstract of Examination A. Nondestructive Examinations Component Component Category Description Identification Examination Isometric (1)

SAFETY CLASS 3 SUPPORTS IWD-2410(C)

IIangers and Supports

>4" NPS Line SW-1 A Support 11-244 VT D-6 Support IID-244C VT D-6 Support RSW-IID-88E VT D-3 Support RSW-IID-88C VT D-3 Line SW-1B Support 11-246 VT D-6 Support IID-246C VT D-6 Support RSW-IID-230B VT D-5 Support RSW-IID-230C VT D-5 Line SW-1C Support IID-244D VT D-6 Line SW-1D Support IID-244E VT D-6 Line SW-2B Support IID-246A VT D-6 Line SW-3 Support IID-246B VT D3 27 of 44

(

l. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro. VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

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)

IWD-2410(C)

IIangers and Supports l

>4" NPS Line SW-6A i

Support RSW-HD133 VT D-3 Support RSW-HD221 VT D-3 Support RSW-HD220B VT D-3 Support RSW-H-221 VT D-3 i

Support RSW-H-220 VT D-3 Line SW-6B Support RSW-HD126 VT D-5 Support RSW-HD233C VT D-5 Support RSW-HD233B VT D-5 Support RSW-IID233A VT D-5 i

Support RSW-H233 VT D-5 i

Line SW-6C Support RSW-HD220C VT D-3 Line SW-6D Support RSW-HD-232A VT D-5 Line SW-8 Support RSW-HD-230D VT D-5 Line SW-18 A&B l

Support H-7 VT D-2 l

Support H-187 VT D-1 Support HD-197A VT D-1 Support HD-200B VT D-1 Support H-55 VT D-1 Support H-195 VT D-1 28 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro. VT 05301 (Name and Addres 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 Authoriztion (if required)

DPR-28

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)

IWD-2410(C)

IIangers and Supports

>4" NPS Line SW-18A Support IID-23 VT D-2 Support HD-76B VT D-2 Support HD-76A VT D-2 Support 11-74 VT D-2 Support 11-81 VT D-2 Support H-82 VT D-2 Support H-188 VT D-2 Support 11-189 VT D-1 Support H-193 VT D-1 Support 11-194 VT D-1 Support H-198 VT D-1 Support H-201 VT D-1 Support H-204 VT(12)

D-1 Support 11-205 VT D-1 Support RSW-II219 VT D-4 Support RSW-HD218D VT D-4 Support RSW-H218 VT D-4 Support RSW-IID218B VT D-4 Support RSW-IID217D VT D-4 Support RSW-HD217 VT D-4 Support RSW-HD217C VT D-4 Support RSW-HD217B VT D-3 Support RSW-HD217A VT D-3 Support RSW-HD216A VT D-3 Support RSW-HD216B VT D-3 Line SW-18D Support HD-7A VT D-2 Support H-80 VT D-2 Support H-80D VT D-2 Support H-80C VT D-2 Support H-13 VT D-2 Support H-79 VT D-2 29 of 44

~

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (Name and Addres of Owner)
2. Plant Vermont Yankee Nuclear Power Statinn, P.O. Box 157, Vernon, VT 05354 (Name and Address of Plant)
3. Plant Unit 1
4. Owner Certificate Authoriztion (if required)

DPR-28

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)

IWD-2410(C) llangers and Supports

>4" NPS Line SW-18B (Cont'd)

Support H-11 VT D-2 Support HD-75 VT D-2 Support H-75 VT D-2 Support H-73 VT D-2 Support IID-192 VT D-1 Support H-192 VT D-1 Support H-196 VT D-1 Support H-199 VT D-1 i

Support H-203 VT(12)

D-1 Support RSW-HD236C VT D-4 l

Support RSW-H103 VT D-4 Support RSW-HD236B VT D-4 i

Support RSW-HD236A VT D-4 Support RSW-H100 VT D-4 Support RSW-H105 VT D-4 Support RSW-HD235E VT D-4 Support RSW-HD235D VT D-4 Support RSW-H235 VT D-4 Support RSW-HD235C VT D-5 Support RSW-HD231 A VT D-5 Support RSW-HD235B VT D-5 Support RSW-HD235A VT D-5 Line SW-18C Support RSW-HD216C VT D-3 Line SW-18D Support RSW-HD233D VT D-5 30 of 44 t

l l

. ~.

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Erattleboro, VT 05301 (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 Examination A. Nondestructive Examinations Component Component Category Description Identification Examination Isometric (1)

IWD-2410(C) llangers and Supports

>4" NPS Line RCW-1 A Support RCW-IID142A VT D-12 Support RCW-II142 VT D-12 Support RCW-Il93 VT D-12 Support RCW-ilD93 VT D-12 Support RCW-IID91 A VT D-12 support RCW-Il91 VT D-12 Support RCW-IID91B VT D-12 Line RCW-2A Support RCW-IID162A VT D-12 Support RCW-IID162B VT D-12 Support RCW-H162 VT D-12 Support RCW-il161 VT D-12 Support RCW-II161 A VT D-12 Support RCW-IID161C VT D-12 Line RCW-2B Support RCW-IID162C VT D-12 Support RCW-IID161B VT D-12 Support RCW-IID161D VT D-12 Line RCW-3 A Support RCW-IID156A VT D-12 Support RCW-il156 VT D-12 Line RCW-4 A Support RCW-II94 VT(12)

D-12 Support RCW-II-160 VT(12)

Under Developmen0 31 of 44 l

4

\\

4 I-

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road. Brattlebore. VT 05301 (Name and Address of Owner) 4 i
2. Plant Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, VT 05354 (Name and Address of Plant)

')

3. Plant Unit

'l

4. Owner Certificate of Authorization (if required)

DPR-28'

5. Commercial Service Date 11/30/72
6. National Board Number for Unit ~

None 4

10. Abstract of Examination A. Nondestructive Examinations Component Component Category Description Identification Examination Isometric (1),

IWD-2410(C)

Ifangers and Supports

)_

>4" NPS Line RCW-5A f

Support RCW-H148 VT(12)

D-13 1

)

Line FPC-3B i

Support CUN-IID-49A VT(12)

Under Development NOTES:

1.

Referenced isometric drawings are contained in the Vermont Yankee Inservice Inspection Program or, if under' development, will be included in the next revision.

2.

This examination was carried over from 1981.

i 3.

Vessel Closure Bushings were uninspectable because the flange joint was not completely disassembled at time of inspection (closure studs in place).

4.

The peripheral CRD housing penetrations through the bottom head dollar plate were visually examined for evidence of leakage.. This examination supplements one performed during the vessel pressure test in 1980, and also responds to INPO SER 3-83.

5.

These circumferential butt welds in the Reactor Recirculation System were examined in accordance l-with NRC IE Bulletin 83-02.

i 6.

These Recirculation System welds were also inspected in accordance with the VY ISI Program and Plant Technical Specifications; the inspection included 12" of the longitudional seam weld adjacent

-to the circumferential butt weld.

7.

This Recirculation System weld was also examined to re-evaluate indications identified during the I

1981 Inservice Inspection. Techniques developed for performance of Bulletin 83-02 examinations have shown these indications to be geometric in origin.

i

8. - Subsequent to overlay repair of Reactor Recirculation System welds, the load settings of these constant supports were inspected and adjusted as necessary to meet the requirements'of the VY ISI Program.

32 of 44

i

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (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. Plent 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 s
10. Abstract of Examination s

A. Nondestructive Examinations v

Component Component Category Description Identification,

Examination Isometric (1) f NOTES: (Cont'd)

\\

9.

Additional examinations performed in accordance 'with IWB-2430.

10. These saddle-type welded supports were visually examined in accordance with Relief Request Basis C-2 of the VY ISI Program.
11. Additional examinations performed in accordance with IWC-2430.
12. Baseline examinations of components installed or modified during the 1983 Refueling Outage performed in accordance with IWA-4220.

s s

t t

.i N.

w 33 of 44 i

1. Owner Vermont Yankee Nuclear Power Corp., RD 5. Box 169, Ferry Road Brattleboro, VT 05301 (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 B.

liydrostatic Terts The.following system pressure tests were performed in accordance with IWA-4210 and Subai icles t

IWA-5000, IWB-5000, IWC-5000, and/or IWD-5000, as appropriate:

1.

New Safety Class I welds in Reactor Water Cleanun line CUW-19 were inspected for leakage and accepted during the primary coolant system hydrostatic pressure test, following extensive piping replacement.

2.

Weld overlay repairs on Safety Class 1 Reactor Recirculation ricer piping welds were inspected for leakage and accepted durag the primary coolant system leakage test and again, remotely, during the primary coolant system hydrostatic pressure test. In both cases, the test pressure was held for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This approach was necessary because the repaired areas were inaccessible during the pressure test due to elevated upper drywell temperatures.

3.

New Safety Class 2 welds in the North and South Control Rod Drive Scram Discharge Volumes, Instrument Volumes, and associated piping were hydrostatically tested and and accepted following extensive piping and component replacement.

4.

Safety Class 2 welds in the Reactor Recirculation Pump Seal Purge System were hydrostatically tested and accepted following installation of this new system.

5.

New Safety Class 2 welds in the Primary Containment Atmospheric Control System were pneumatically tested and accepted follo'ving a minor piping modification. This test was performed in accordance with Relief Request Basis 11-2 of the Vermont Yankee Inservice Inspection Program.

6.

New Safety Class 2 welds in the Residual IIcat Removal System were hydrostatically tested and accepted following relocation of a relief valve.

7.

New Safety Class 3 welds in two Residual lleat Removal Service Water Pump motor cooler lines were hydrostatically tested and accepted following replacement of piping and components. (See attached ANI Ex eptions page for a description of this test).

8.

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

34 of 44

l. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro VT 05301 (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 B. IIydrostatic Tests 9.

New Safety Class 2 welds in the Containment Sampling System and the Nitrogen Inerting System (PCAC portion) were pneumaticall. tested and accepted following replacement of valves. This test was performed in accordance with Relief Request Bases 11-7 and 11-2 of the Vermont Yankee Inservice Inspection Program.

10. A primary coolant system leakage test in accordance with IWB-5221 and a primary coolant system hydrostatic pressure test in accordance with IWA-4210 and IWB-5222 were performed and accepted prior to plant startup.

C. Ultrasonic Examination Procedures 1.

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

2.

YA-UT-2, Rev.1, Ultrasonic Examination of Vessels, Circumferential, Longitudional, Meridional and Flange Welds.

3.

YA-UT-4, Rev.1, Ultrasonic Examination of Vessels, Nozzle to Vessel Welds.

4.

YA-UT-5, Rev.1, Ultrasonic Examination of Vessels, Integral Support Attachment Welds.

5.

YA-UT-6, Rev.1, Ultrasonic Examination of Flange Ligaments

'. YA-UT-7, Rev. 2, Ultrasonic Examination of Bolting 7.

YA-UT-8, Rev.1, Ultrasonic Examination of Vessel Closure Nuts.

l 8.

YA-UT-9, Rev. 2, Ultrasonic Examination of Piping Ferritic Welds.

9.

YA-UT-10, Rev. 3, Ultrasonic Examination of Piping Austenitic Welds Including Appendix A for Detection of IGSCC.

10. YA-UT-11, Rev. 2, Ultrasonic Examination of Piping Dissimilar Metal Welds.
11. YA-UT-13, Rev.1, Ultrasonic Examination of Vessels, Nozzle Inner Radius.
12. YA-UT-14, Rev. 2, Ultrasonic Examination of Pi ing Base Material & Weld IIcat Affected Zones.

I 35 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (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 C.

Ultrasonic Examination Procedures

13. YA-UT-15, Rev. 2, Ultrasonic Examination of Piping, Straight Beam Method when used for Weld & IIcat Affected Zone Exatnination.
14. YA-UT-16, Rev. O, Ultrasonic Examination of Full Penetration Welds Per Section V, Article V.
15. YA-UT-83-13-1, Rev. O, Ultrasonic Examination, Straight Beam Method when Used for Examination of Weld Overlay Clad Bond.
16. YA-UT-83-13-2, Rev. O, Ultrasonic Examination, Angle Beam Method When Used for Examination of Weld Overlay Clad Bond and Clad Flaw Indication?.
17. Magnaflux Procedure 2.2.A.35, Rev. 2, including Engineering Notice 83.2 and 83.5, Ultrasonic Examination of Austenitic Piping and Branch Connectior. Welds for IGSCC.

D. Liquid Penetrant Examination Procedures 1.

YA-PE-2, Rev. 3, Liquid Penetrant Examination.

2.

Mercury Company Procedure QCP-3104, Rev.1, Liquid Penetrant Examination.

E, Magnetic Particle Examination Procedures 1.

YA-MP-1, Rev.1, Magnetic Particle Examination F. Visual Examination Procedures 1.

YA-VT-1, Rev. 4, Visual Examination.

2.

Mercury Company Procedure QCP-3110.2, Rev. 2, including Appendix A, Rev. O Steel Structure Inspection, Support Components (Section XI) 3.

OP 4101, Rev. 9, Vermont Yankee RPV Operational llydro Test 4.

OP 1412, Rev. 4, Jet Pump and Shroud Annulus Inspection 5.

OP 1413, Rev. O, Visual Examination of Miscellaneous Internal Reactor Vessel Brackets 6.

OP 1414, Rev.1, Core Spray Sparger Inspection 7.

OP 1418, Rev. O, Feedwater Sparger Inspection 8.

OP 1419, Rev. O, Visual Examination of Reactor Components below the Core Plate 36 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road. Brattleboro, VT 05301 (Name and Address of Owner)
2. Pl nt 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)

D PR-78

5. Commercial Service Date 11/30/72
6. National Board Number for Unit None
11. Abstract of Conditions Noted A.

Category B-J 1.

During performance of scheduled ultrasonic examinations of Reactor Recirculation Systern riser piping welds 25 and 52, rejectable indications were discovered in the heat-affected zone (llAZ) on the pipe side of these pipe-to-safe end welds. Weld 25 exhibited indications approximately 15% through-wall-dimension (TWD) and 2"long, while the indications adjacent to Weld 52 were approximately 10% TWD,360" intermittent in linear extent.

These examinations, which were mandatory to complete the requirements of ASME Section XI and Plant Technical Specifications for the first 10 year inspection interval, comprised part of an extensive primary coolant piping augmented inspection effort involving 60 welds, which was undertaken in accordance with NRC IE Bulletin 83-02. This larger scope of work. including number and approximate size of all indications noted, has been addressed in our response to Bulletin 83-02, dated June 3,1983. The augmented inspection program encompassed examination of all 40 circumferential welds in the Recirculation riser piping thus complying with IWB-2430.

B.

Category B-K-2 1.

During visual examination of non-welded Safety Class 1 supports, support FW-8 (one of one inspected) on the Feedwater System was found to have an incorrect load setting.

As required by IWB-2430, an additional examination was conducted on a similar component in the system and no further rejectable conditions were discovered.

2.

Visual examination of support CU-7 (one of one inspected) on Reactor Water Cleanup line CUW-18 revealed loose bolting on the pipe clamp attachment. As required by IWB-2430, an additional component on this line, support CU-8, was examined and further loose clamp bolting was found. At this point, all similar support components on this piping were examined and one additional support, CU-9, was found to have loose clamp bolting.

C.

Category C-E-1 1.

During visual examination of saddle-type support components on the liigh Pressure Coolant injection pump discharge line HPCI-2/IIPCI-15B, it was discovered that the saddle on support IID-22D (one of two inspected) showed evidence of radial deformation.

Since this condition appeared to indicate a potentially significant structural deficiency, all saddle-type supports in this system were examined and the following supports were found to have varying degrees of similar deformation: IID-22B, llD-24,11-28, IID-35A, IID-35B, IID-35C, and IID-35D.

37 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (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
11. Abstract of Conditions Noted C.

Category C-E-1 (Cont'd)

During performance of these additional examinations, which addressed all inspection parameters for each component, it was also discovered that supports llD-35C and IID-22A had incorrect load settings, IID-22C had loose structural member bolting and misaligned spring can pedestal, IID-22E had spalled concrete at wall anchor locations, IID-35B and ilD-22B had a non-perpendi-cular relationship between the spring can pedestal and the support saddle, IID-24 had a cracked saddle-to-pipe fillet weld, and IID-35A had a saddle which was off-center to the supporting structural member. This examination constituted a 100% inspection of all similar support components in this subsystem.

2. During visual examination of saddle-type support IID-127A (one of one inspected) on the Residual llent Removal Shutdown Cooling supply header RIIR-1B, loose base plate anchor bolts were discovered. As required by IWC-2430, an additional examination was conducted on a similar component in this subsystem and no further rejectable conditions were found.

D.

Category C-E-2 1.

During baseline visual examination of all Control Rod Drive Scram Discharge Volume support components installed or modified as a result of system upgrades in accordance with NRC IE Bulletin 80-17, two supports, II-6 and 11-32, were found to have loose or missing nuts on the U-bolt attachment to the pipe.

2.

During visual examination of support components on the fligh Pressure Coolant Injection turbine steam supply line MS-48, support IID-102B (one of two inspected) was found to have loose bolting on the pipe clamp attachment. As required by IWC-2430, additional examinations were performed on an equivalent number of similar components on this sub-system and support IID-102A was found to have loose pipe clamp bolting. At this point, all similar supports on this piping were visually examined and three additional supports, IID-103C, IID-3, and 11-5 were found to have loose clamp bolting. During performance of these examinations, it was also noted that supports II-5 and IID-3 had incorrect load settings. It was decided to examine all spring hangers and supports within the group of similar components for adequacy of load settings. This additional examination revealed incorrect load settings on supports llD-13A, IID-103C and IID-103 A.

38 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (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
11. Abstract of Conditions Noted D.

Category C-E-2 (Cont'd) 3.

During baseline visual examination of support IID-130B on the Residual IIcat Removal pump discharge line RIIR-3A, following removal of this support for access to an adjacent pipe weld and subsequent replacement, loose bolting was discovered on the pipe clamp attachment. Because this was a special case related to a planned maintenance activity, no additional examinations were conducted.

4.

During visual examination of support IID-200J (one of one inspected) on the Residual IIcat Removal Low Pressure Coolant Injection header, the spring can load setting was found to be incorrect. As required by IWC-2430, an additional examination was conducted on a similar component in this subsystem and no further rejectable conditions were discovered.

E.

Code Subarticle IWD-2410(C) 1.

Visual examinations were performed on 86 piping supports in the Service Water System and 21 piping supports in the Reactor Building Closed Cooling Water System while these Safety Class 3 systems were operating. The following rejectable conditions were noted. No additional examinations were performed, since none are required by ASME Section XI 1974 Edition, Summer 1975 Addenda for Class 3 systems.

a.

Service Water System 1.

Grout cracked under base plate:

Support RSW-IID-88C Support RSW-IID-88D 2.

Inadequate thread engagement on clevis bolting:

Support ilD-192 Support 11-193 Support 11-203 Support RSW-II-221 Support RSW-II-233 39 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5. Box 169, Ferry Road, Brattleboro, VT 05301 (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
11. Abstract of Conditions Noted E.

Code Subarticle IWD-2410 (c) (Cont'd) 3.

Missing nut on pipe clamp attachment:

Support RSW-IID-233C 4.

Missing washer on base plate:

Support RSW-IID-235B b.

Reactor Building Closed Cooling Water System 1.

Loose bolting on pipe clamp attachment:

Support RCW-II-161 2.

Grout cracked under base plate:

Support RCW-IID-161D EJpport RCW-IID-162A 3.

Base plate not centered on grout pad:

Support RCW-IID-161C 4.

Rod hanger not plumb:

Support RCW-IID-162B 5.

Shim plate under base plate moved out-of-position:

Support RCW-IID-162C

12. Abstract of Corrective Measures Recommended and Taken A.

Category B-J 1.

Welds 25 and 52 in the Recirculation riser piping were repaired using a weld overlay technique, along with 20 other welds of the same pipe size which were identified as defective under the augmented inspection program required by Bulletin 83-02.

40 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (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
12. Abstract of Corrective Measures Recommended and Taken A.

Category B-J (Cont'd)

This technique and the scope of the repair effort have been described in detail in our response to the Bulletin. Post-weld ultrasonic examinations were performed to confirm adequate bonding of the weld metal to the base material, and to verify the integrity of the overlay layers. No rejectable indications were discovered as a result of these examinations. All reinspections were completed and accepted prior to plant startup, as dictated by Bulletin 83-02.

B.

Category B-K-2 1.

The incorrect load setting on Feedwater System Support FW-8 was adjusted to within specification requirements, visually reinspected, and accepted prior to plant startup.

2.

The loose bolts on Reactor Water Cleanup System supports CU-7, CU-8 and CU-9 were tightened, visually reinspected and accepted prior to plant startup.

C.

Category C-E-1 1.

An engineering evaluation of support saddle deformation on the IIPCI pump discharge line could not conclusively determine whether the degradation of these components was due to poor construction practices or 1o water hammer events experienced during early operating cycles. Engineering personnel performed an investigation of the piping to ascertain whether any stress damage had occurred as a result of support component degradation. Although no evidence of pressure boundary damage was found, a conservative position was taken that the design of these supports should be modified to prevent a recurrence of this problem. A design change was undertaken to replace the damaged support saddles with steel plate stock welded to the supporting members but not to the pressure boundary. Removal of the saddles was accomplished without penetrating the pipe surface, with the exception of supports IID-35A, IID-35C, IID-35D, and IID-22B which required minor grinding. Category C-E-2 non-welded supports were installed in place of existing saddles on supports IID-22D, IID-22B, IID-24,11-28, IID-35A, IID-35B, IID-35C, and IID-35D. A baseline visual examination was performed on all of these supports prior to plant startup and the pipe surface at supports IID-22B, IID-35A, IID-350 and IID-35D also received a liquid penetrant examination of ground areas. All results were satisfactory.

The additional deficiencies discovered in this subsystem were attributable to either normal service (loose bolting, load setting deviations) original plant construction (misaligned and non-perpendicular components) or water hammer events (spalled concrete, cracked fillet welds).

41 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 (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 S. Commercial Service Date 11/30/72

6. National Board Number for Unit None
12. Abstract of Corrective Measures Recommended and Taken C.

Category C-E-1 (Cont'd)

Normal corrective maintenance measures were used to tighten bolting, adjust load settings, and repair spalled concrete, while construction anomalies and cracked welds were corrected as part of the design change implementation. Furthermore, the water hammer problem which apparently caused some of these discrepancies was eliminated in 1977. The results of all corrective actions were visually reinspected and accepted prior to plant startup.

2.

The loose base plate anchor bolts on Residual IIcat Removal System support IID-127A were tightened, visually reinspected, and accepted prior to plant startup.

D.

Category C-E-2 1,

The loose and missing nuts on Control Rod Drive Scram Discharge Volume supports II-6 and 11-32 were tightened or replaced with suitable spares, visually reinspected and accepted prior to plant startup.

2.

The loose pipe clamp bolting on High Pressure Coolant Injection turbine steam supply line supports HD-102A, IID-102B, IID-103C, IID-3 and IID-5, and the incorrect ioad settings on supports IID-5, IID-3, IID-13A, IID-103C and IID-103A were corrected, visually reinspected and accepted prior to plant startup. The large number of similar discrepancies is attributable to the thermal and dynamic loading to which these supports are subjected during periodic surveillance testing.

3. The loose pipe clamp bolting on Residual IIeat Removal System support IID-130B was tightened, visually reinspected, and accepted prior to plant startup.

4.

The incorrect load setting on Residual IIcat Removal System support IID-200J was adjusted to within specification requirements, visually reinspected, and accepted prior to plant startup.

E.

Code Subarticle IWD-2410(c) 1.

All support component discrepancies in the Service Water and Reactor Building Closed Cooling Water Systems were corrected as shown below, visually reinspected, and accepted prior to plant startup. Since these systems remain in service essentially 100% of the time, vibration-induced degradation of the type and extent experienced is not considered abnormal.

42 of 44

1. Owner Vermont Yankee Nuclear Power Corp., RD 5, Box 169, Ferry Roac, Brattleboro. VT 05301 (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
12. Abstract of Corective Measure Recommended and Taken E.

Code Subarticle IWD-2410 (c) (Cont'd) a.

Service Water System 1.

Based on an engineering recommendation, the cracked grout pads beneath the base plates of supports RSW-IID-88C and RSW-IID-88D were replaced with grout pads which exceed the outside dimensions of the base plates by 2" on all sides.

2.

The inadequate clevis bolt thread engagement on supports11-192,11-221 and 1I-233 was corrected by tightening. On supports11-193 and 1I-203, this condition was corrected by replacement with a longer bolt of suitable material.

3&4. The missing pipe clamp nut on support RSW-IID-233C and the missing base plate washer on support RSW-IID-235B were replaced with spare parts of suitable material.

b.

Reactor Building Closed Cooling Water System 1.

The loose pipe clamp bolting on suoport RCW-II-161 was tightened.

2&3. The cracked grout pads beneath the base plates of supports RCW-IID-161D and RCW-IID-162A, and the off-center base plate-to-pad condition at support IID-161C were corrected by replacement of the grout pads with new pads which exceed the outside dimensions of the base plates by 2" on all sides.

4.

The out-of-plumb rod hanger on support RCW-IID-162B was adjusted in the axial direction to achieve a vertical orientation. Adjustment in the circumferential direction was not possible without moving the ceiling-mounted base plate, but an engineering evaluation showed the out-of-plumb condition in that direction to be within acceptable tolerances.

5.

The misaligned shim plate beneath support RCW-IID-162C was replaced with a larger steel plate which exceeds the outside dimension of the support base plate by 1/2" on all sides.

43 of 44

l

1. Owner Vermont Yankee Nuclear Power Corp., RD 5. Box 169, Ferry Road, Brattleboro, VT 05301 (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 Authorized Nuclear Inservice Inspector Excep* ions
10. Abstract of Examinations Pages 3 and 4 B.

Ilydrostatic Tests 1.

Following replacement of piping and components in the cooling water lines to the "B" and "D" RIIR Service Water pump motors, a hydrostatic pressure test was required at 1.1 times the system design pressure of 350 psig. However, it was discovered that these lines are not isolable from the suction side of the pumps, and pressurization of the motor cooler lines to the required 385 psig would have overpressurized the 125 psig suction piping. Ultimately, inservice leak testing of the system at normal operating pressure resulted in a satisfactory test of the "B" and "D" motor cooler lines at pressures of 320 and 280 psig, respectively.

2, Safety Class 2 and 3 piping systems involved in the Mark I Containment upgrade were not hydrostatically tested following attachment of new and modified support components to the pressure boundary by fillet welding. This is consistent with the position established in later editions of ASME Section XI, which exempt such partial-penetration welding from pressure test requirements. These welds were subjected to the surface and/or visual examinations required by ASME Section XI for Class 2 and 3 support components.

man-t f

tw WUh5 Richard L. Lane Authorized Nuclear Inservice inspector 44 of 44

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