ML19350C615

Inservice Insp Examination Rept, Conducted 800908-1231

ML19350C615
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	04/01/1981
From:	YANKEE ATOMIC ELECTRIC CO.
To:
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ML19350C614	List: ML19350C612 ML19350C615
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NUDOCS 8104060394
Download: ML19350C615 (75)

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1 9

- THIS DOCUMENT CONTAINS P00R QUALITY PAGES INSERVICE INSPECTION EXAMINATION REPORT VERMONT YANKEE NUCLEAR POWER CORPORA? ION SEPIEMBEP 8, 1980 THROUGH DECDBER 31, 1980 N

.E A

I

_ ', ~.

1 a

TABLE OF CONTENTS PACE NIS-1 Owner's Data Report 1

Su= mary Report 56 1.0 Introduction 58 1.1 Examination Methods 58

'l. 2 Evaluation of Data 59 1.3 Examination Results 59 2.0 Reactor Vessel Data 53 3.0 Piping Data 62 4.0 Pumps 65 5.0 Valves 66 6.0 Safety Class II 66 7.0 Category C-F 69 8.0 Category C-E-1 70 9.0 Category C-D 70 10.0 Safety Class III 71 System Pressure Test 72 Conclusions 72 O

m--____

FORM NIS-1 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) 05354 Vermont Yankee Nuclear Power Station, P.O. Box 157, Vernon, Vt.

2. Plant (Name and Address of Plant)

DPR-28 1

4. Owner Certificate of Authorization (if required)

3. Plant Unit 11/30/72 6. National Board Number for Unit None

5. Commercial Service Date

7. Components inspected Manufacturer Manufacturer or installer State or National Component or or Installer Serial No.

Frovince No.

Board No.

Appurtenance Safety Class ]

Merid. Welds Chicago Bridge & Iron B 4698 N/A N/A 2 Closure Heac 1 Closure Heac Circ. Weld Chicago Bridge & Iron B 4698 N/A N/A 1 Head to Flange Circ. Weld Chicaco Bridce & Iron B 4698 N/A N /A 3 Nozzle to Vessel Welds Chigaco Bridge & Iron B 4698 N/A~

N/A 6 wu tene-tration Welds Chicago Bridge & Iron B 4698 N/A N/A J hoZZie to Safe-end welds Chicago Bridge & Iron B 4698 N/A N/A 1 Nozzle to Safe-end Weld Mercury Co.

N/A N/A N/A 6 Vessel Closure Studs Chicago Bridge & Iron B 4698 N/A N/A 4 Vessel Closure Nuts Chicago Bridge & Iron B 4696 N/A N/A 6 Vessel Flan ;e IMgaments Chicnco Bridce & Tron R 4644 v/A v/s 6 Vessel Chicano Bridce & Iron B 4698 N/A N/A iro U'chave Clos 6 Vessel Clos 2re Bushines Chicago Bridge & Iron B 4698 N/A N/A 12 Vessel Chicago Bridge & Iron B 4698 N/A N/A Head Finnee Enits 2 Closure Head Clad Patches Chicago Bridce & Iron B 469R N/A N/A Beam Assys.p General Electric N/A N/A N /A 20 J t Pum Notes Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size (2) information in items I through 6 on this data report is included on each sheet, and (3) each sh and the number of sheetsis recorded at the top of this form.

10017 This form (E00029) rnay be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y Page 1 Of 72

FORM NIS-1 (back) 12/31/80 9. Inspection Interval from 11/30/72 o 11/30/82

8. Examination Dates 9/29/80 to t

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

See attached page.

11. Abstract of Conditions Noted See attached page.

12. Abstract of Corrective Measures Recommended and Taken See attached page.

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.

Vermont Yankee Nuclear Date SN 3

19 OI Signed Power Corporation By d2-MM Plan [ Supe'ritfen Owner DPR-28 December 11, 2007 Certificate of Authorization No. (if applicable)

Expiration Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issuedyb the National Board of Boiler and Pressure Vessel Inspectors and/er the State or Province of Ved M ag /

and employed by flS. A T d L /a of

~

6E have inspected the components Jewril,cd in this Owners' Data Report duIing the period

_f / 2 U2fo_ to /177//#'d 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 snd corrective rnessures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinju y or property damage or a loss of any kind arising from or connected with this inspection.

Date

%6 19 YI h

Commissions d-3/9 Inspector's Signature National Board, State Province and No.

Page 2 of 72

FORM NIS 1 OWNERS

• DATA REPORT FOR INSERVICE INSPECTIONF As required by the Provisions of the ASME Code Rules

1. Owner Vermont Yankee Nuclear Power Corp.,77 Grove St.. Rutland

.Vt.

05701 (Name and Address of Owner)

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

3. Plant Unit

4. Owner Certificate of Authorization (if required)

DPR-28

5. Commercial Service Date 11/30/72

6. National Board Number for Unit

'2 - a

7. Components inspected l

Manufacturer l

Component or Manufacturer or insta!!er State or National Appurtenance or installer Serial No.

Province No.

Board No.

Core Spray General Electric N/A N/A N/A Searcer Assv.

2 Piping Per attached isometrics Safe-end Welds rRAsco M/A V/A

'? / 3 Fer attached isometrics 26 Pipe Welds EBASCO yf3 ur.

er attacne isometdes 17 Pipe Welds N/A N/A N/A Mercur3 cn.

3> 6" Branch Per attached isometrics Connect. Welds EBASCO N/A N/A N/A l'

6" Branch Per attached isometrics Connect. Welds Mercury Co.

N/A N/A N/A 25 Supports /

Per attached isometrics Hangers EBASCO N/A N/A N/A 7 > 2" Bolts Byron Jackson 671-S-1108 N/A N/A Per attached isometrica 104<2" Bolts EBASCO N/A N/A N /A Safety Class 2 1 Vessel Weld Sweco Co.

N/A N/A N/A 108>1" Bolts Per attached isometrics vnAgen N/A N/A

'! / A 23 Pipe Welds Per attached isometrics EBASCO N/A N/A N/A 48 Supports /

Pcr attached isometrics Hangers EBASCO N/A N/A N/A Safety Class 3 22 Supports /

Per attached isometrics l

H m ers FRAcro v /a

'? ' A Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size as 8b 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 th". Order Dept., ASVE,345 E. 47th St., New York, N.Y. 10017 Page 3 of 72

l.

Ownar Vermont Yanken Nuclear Pownr Corp.,77 Grova St.,Rutland,Vt.

05701 (Nams and Address of Owner) 2.

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

A.

Nondestructive Examinations Category No. of Components Examined Examination Safety Class 1 Reactor B-B 2

Closure Head Meridional Welds UT 1

Closure Head Circumferential Weld UT B-C 1

Head to Flange Circumferential Weld UT B-D 3

Nozzle to Vessel Welds UT B-E 8

CRD Penetration Welds VT B-F 3

Nozzle to Safe-end Welds UT,PT,VT 1

Nozzle to Safe-end Weld UT (1)

B-G-1 6

Vessel Closure Studs UT,PT 4

Vessel Closure Nuts UT,PT 6

V.;ssel Flange Ligaments UT 6

Vessel Closure Washers VT 6

Vessel Closure Bushings VT B-G-2 12 Vessel Head Flange Bolts and Corresponding Nuts VT (in place)

B-I 2

Closure Head Cladding Patches PT,VT B-N 20 aet Pump Beam Assemblies UT,VT (2) 1 Core Spray Sparger Assembly VT (2)

Piping B-F

-2 Piping Safe-end Welds PT,VT (3)

B-G-2 24 Flange Bolts and Corresponding Nuts VT (in place)

B-J

'19 Pipe Welds UT,VT-(4) 3

> 6" Branch Connection Welds UT (4) 7 Pipe Welds RT 17 Pipe Welds UT,VT (5) 1

< 6" Branch Connection Weld UT,VT (5)

B-K-1 1_

Integrally-welded support PT,VT 1

Integrally-welded support MPT 1

Integrally-welded support PT,VT (5)

B-K-2 18 Non-Welded Supports VT 2

Non-Welded Supports VT (5)

Pumps B-G 7 Cover-to-Casing Bolts UT,VT B-K-2 2

Non-Welded Supports VT Valves B-G-2' 80 Bolts and Corresponding Nuts VT' (in plaae)

Safety Class.2 Vessels C-A 1

Circumferential Shell Weld UT C-D 68 Flange Bolts and Corresponding Nuts VT (in place)

Piping C-D 16 Flange Bolts and Corresponding Nuts C-E-1 8

Integrally-Welded Supports

.MPT,VT C-E-2 36 Non-Welded Supports VT

~

Page 4 of 72

l I

1.

Ownzr Varront Yankts Nuclear Power Corp.,77 Grove Street,Rutland.Vt.

05701 (Name and Address of Owner) 2.

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

05354 (Name and Address of Plant) 3.

Plant Unit 1

4.

Owner Certificate of Authorization (if required) DPR-28 5.

Commercial Service Date 11/30/72 6.

National Board Number for Unit None 10.

Abstract of Examinations (continued)

A.

Nondestructive Examinations (cont'd)

Category No. of Compone.ts Examined Examination Safety Class 2 C-F 3 Pipe Welds UT C-G 4 Pipe Welds UT 16 Pipe Welos UT (6)

Pumps C-E-1 4 Integrally-Welded Supports MPT Valves C-D 24 Bolts and Corresponding Nuts VT (removed) 3 Bolts from above lot MPT (removed)

Safety Class 3 Hangers IWD-17 Pipe Hangers / Supports VT while

> 4" 2410 (c) operating IWD-2410 (b) 5 Pipe Hangers / Supports VT under hydrostatic test pressure B.

Hydrostatic Tests:

1.

The Standby Liquid Control System discharge piping was hydrostatically tested, in accordance with IWA-4210, following repair by welding of an arc strike.

.This-piping is Safety Class 2, with a design pressure of 1500 psi. The required hydrostatic test pressure of 1875 psig was maintained for a duratioa of ten minutes on this uninsulated piping, and a visual inspection of the repaired area was performed, along with a walkdown of the entire piping run, to look for leakage. No leakage was discovered. This lh" piping meets the exer;ption criteria of IWC-1220, so no other examinations were performed.

This test also satisfies the inspection requirements of IWC-2510.

2.- The Fuel Pool Cooling and Clean-up System Suction and discharge piping was hydrostatically tested in accordance with the requirements of IWD-2410 (b).

This piping is Safety Class 3, with a design pressure of 150 psi. The required hydrostatic test pressure of 165 psig was maintained for a duration of ten minutes on this uninsulated pipir.g,.and a walkdown of the system was performed

'to look for-leakage and to inspect hangers and supports within the pressure boundary. No leakage or evidence of support degradation were detected.

3.

The CRD Scram Discharge Volume vs. hydrostatically tested, in accordance with IWA-4210, following installation offdecontamination connections. This piping is Safety Class 2, with a design pressure of 1250 psi. The required hydrostatic test pressure of 1563 psig was maintained for a~ duration of ten minutes on this uninsulated piping, and a visual inspection of all new wolds was performed, along with a walkdown of all piping within the test boundary, to look for leakage.. No leakage was discovered. This test also satisfies the. inspection requirements of IWC-2510.

.r Page 5 of 72

1.

Owner Vermont Yankee Nuclear Power Co p.,

77 Grove Street, Rutland, VT 05701 (Name and Address )f Owner)

J 2.

Plant Vermont Yankee Nuclear Power Station, P.O. Box 157 Vernon, VT 05354 (Name and Address of Plant) t 4

3.

Plant Unit 1

4.

Owner Certificate of Authorization (if required)DPR-28 5.

Commercial Service Datell/30/72 6.

Nationa'. Board Number for Unit None l

10.

Abstract of Examinations (continued)

B.

Hydrostatic Tests:

(cont'd) 4.

New piping installed in the Reactor Water rieanup System was hydrostatically tested as follows:

a.

Safety Class 3 suction piping downstream of the outboard isolation valve was tested, la accordance with IWA-4210, at a hydrostatic test pressure of 1375 psig for a duration of ten minutes. All new welds were inspected for leakage, with none detected.

a b.

Safety Class 3 discharge piping between the regenerative and non-1 regenerative heat exchangers was tested, in accordance with IWA-4210, at a hydrostatic tesc pressure of 1430 psig for a duration of ten minutes. All new welds were inspected for leakage, with none detected.

c.

Safety Class 1 piping between the inboard and outboard MOV's was tested, in accordance with ANSI B31.1, at a hydrostatic test pressure of 1875 psig for a duration of ten minutes. All new welds were I_

inspected for leakage, with none detected.

L d.

Replaced Safety Class 1 portions of the. system from the branch I

connection at the RHR suction line to the inboard MOV were tested in accordance with IWA-4210..during performance of the reactor coolant system hydrostatic pressure test at a pressure of 1020 psig and a temperature of 5300F for a duration of four hours. Examination was conducted in accordance with IWA-5240 and no evidence of= leakage was detected.

C.

No'tes:

f 1.

The CRD nozzle-to-cap weld installed in 1979 did not receive a baseline UT examination from the carbon steel side of the weld due to lack of a

. suitable calibration standard. The calibration standard was subsequently obtcined and the baseline UT was completed during the 1980 inservice finspection.

2.

These inspections were completed for Vermont Yankee by Gener 1 Electric in accordance with NRC Bulletins 80-07 and 80-13.

3.

Due to unexpected thickness variations in the configuration of these weld joints, lui altrasonic calibration standard was not available to complete thelrequired UT examination'. This examination will be completed

later in this inspection period.

~

4.

10 of 22 Category J Welds were examined in accordance with'the intent of NUREG-0313 for augumented inspection of service-sensitive lines.

5..

These inspections were baseline examinations, as required by IWA-4220 to establish a new preservice record, and were necessitated by replacement-ofsthe Safety Class 1 portion of the Reactor Water Cleanup suction piping due to discovery of rejectable indications during mandatory inspections.

z g L

.+.

e P

Page,6 of 72 1

1.

Ownsr Varront Yankee Nuclear Power Corp.,77 Grove Street,Rutland,Vt.

05701 (Name and Address of Owner) 2.

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

05354 (Name and Address of Plant) 3.

Plant Unit 1

4.

Owner Certificate of Authorization (if required) DPR-28 5.

Commercial Service Date 11/30/72 6.

National Board Number for Unit None 10.

Abstract of Examinations (continued)

C.

Notes:

(cont'd) 6.

These inspections were baseline examinations, as required by IWA-4220 to establish a new preservice record, and were necessitated by installation of decontamination connections in the Scram Discharge Volume.

7.

All examination procedures used were Yankee Atomic Procedures except where otherwise noted.

8.

The inspections completed during the 1980 refueling outage constitute approximately 1/3 of the total number of inspections required to be completed during Period 3 of the first Inservice Inspection Interval.

Prior to the 1980 inservice inspection, approximately 2/3 of all inspections required for this Inspection Interval had been completed.

D.

Ultrasonic Examination Procedures 1.'

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

YA-UT-2, Ultrasonic Examination of Vessels - Circumferential Longitudinsl, Meridional and Flange Welds.

3.

YA-UT-4, U crasonic Examination of Vessels -Nozzle to Vessel Welds 4.

YA-UT-6, Ultrasonic Examination of Flange Ligaments 5.

YA-UT-7, Ultrasonic Examination of Bolting 6.

YA-UT-8, Ultrasonic Examination of Reactor Closure Nuts 7.

YA-UT-9, Ultrasonic Examination of Piping - Ferritic Welds 8.

YA-UT-10, Ultrasonic Examination of Piping - Austenitic Welds (including Appendix A) 9.. YA-UT-11, Ultrasonic Examination of Piping -Dissimilar Metal Welds 10.

YA-UT-13, Ultrasonic Examination of Vessels-Nozzle Inner Radius 11.

YA-UT-14,. Ultrasonic Examination of Piping-Base Material and Weld H' eat-Affected Zone 12.

YA-UT-15, Ultrasonic Examination of Piping-Straight Beam Method when used for Weld and Heat-Affected Zone Examination 13.

YA-UT-16, Ultrasonic Examination of Full Penetration Welds Per Section V, Article V.

E.

Liquid Penetrant Examination Procedures 1.

YA-PE-2, Liquid-Penetrant Examination

2. -QCP-3104, Mercury Co., Liquid Penetrant Examination F.. Magnetic Particle Examination Procedur,es

1. 'YA-MP-1, Magnetic Particle Examination s;

Page 7 of'72

1.

Ownar Vermont Yankee Nuclear _ Power Corp. 77 Crove Street.Rutland,Vt.

05701 (Nar.e 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 (continued)

G.

Visual Examination Procedures 1.

YA-VT-1, Visual Examination Procedure 2.

QCP 3110, Mercury Co., Visual Inspection 3.

CP 4101, Rev. 8, Vermont Ysnkee RPV Operational Hydro Test 4

OP 4126.1, Rev. O, Hydrostatic Pressure Test of Fuel Pool Cooling System H.

Radicgraphic Examination Procedures 1.

20.A.' 3, Peabody Testing, Radiographic Examination of Welds lL.

Abetract o'f Co..ditions Noted:

A.

Category B-N:

1.' During ultrasonic inspection of Jet Pump Beam assemblies in accordance with NRC Bulletin 80-7, a rejectable indication was discovered in Jet Pump Beam No. 8.

2.

During visual inspection of Core Spray Sparger piping in accordance with NRC Bulletin 80-13, a rejectable indication characterized as a semi-circular crack was discovered on the "C" sparger junction box cover plate.

B.

Category B-J:

1.

During ultrasonic inspection of circumferential welds in the Reactor Water Cleanup _ System, Weld F3B was found to have a rejectable indication. Verification by radiography confirmed this finding to be a crack. As required by IWB-2430, three additional welds were examined by radiography and one of these, Weld F-4, exhibited evidence of cracking. Continue.d additional radiographic inspection was performed to complete the total number of walds in this line required for the inspection interval, amounting to three more welds for a total of_-eight volumetric examinations. Of these, Welds F6A and F6C were rej ected. Up to this point, all inspections had been performed on the isolable 4" Schedule 80 portions.of line CUW-18.

Because of the magnitude'of the problem in this piping, it was decided to expand the inspection program to include all non-isolable 4" Schedule 120 welds upstream of the welds originally rejected. During visual inspection

.c

.of this. piping, leakage was discovered coming from two through-wall cracks: one crack was located adjacent tu weld FlA and the other was found~on the throat of the sweepolet (away from the weld HAZ) that connects CUW-18 to the RHR suction line. Volumetric examinations Lof all welds in this portion of the system revealed no further indications.

Page 8 of 72

l..

Own%r Verront Yenkse Nuclear Power Corp.,77 Grove Street,Rutland,Vt.

05701 (Name and Address of Ovner) 2.

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

053,54 (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

'll.-

Abstract of Conditions Noted (continued):

C.

Category B-K-1:

'l.

During performance of liquid penetrant inspection of welded stanchion RR-70 on the Reactor Recirculation Loop B discharge line, rejectable indice* ions were found in the attachment veld metal. To satisfy the requirements of IWB-2430, an additional welded support was examined, and no further rejectable conditions were discovered.

D.

Category B-K-2:

.l. -During performance of visual inspection of spring hangers on Reactor Recirculation Loop B discharge piping, hanger RR-66 was found to have a load setting which was out-cf opecification. An additional examination of spring hanger RR-65 revealed that this hanger also had an unacceptable load setting. At this point, the inspection program was expanded to include spring hangers of similar type, size and function on Reactor Recirculation Loop A discharge piping. Hangers RR-29 and RR-30 were found to have unacceptable load settings. These four hangers constitute all components of similar type, size, and function on this piping.

2.

During performance of visual inspection of spring hangers on the HPCI Steam Supply Line MS-4A, hanger HPCI-3 was found to have an unacceptable load setting. Since.the only other spring hanger on this line was inspected and' accepted during a previous inservice inspection, and since there are no similar lines, no additonal examinations were deemed to be necessary.

3.

During performance of visualinspection of Safety Class 1 snubbers, one of those inspected, snubber CU-2 on Reactor Water Cleanup line CUW-18, was found to have a loose pipe clamp nut.

As required by IWB-2430, additional examinations were performed on an equivalent number of similar components, and no further rejectable conditions were discovered.

IC Category C-D:

1.

During. visual inspection of (23) of (68) bolts in the upper flange of RHR Heat Exchanger A, 2 bolts were found to have insufficient thread engagement. As required by IWC-2430, additional examinations of the remaining bolts were conducted and no.further rejectable conditions were discovered.

-F.

Category C-E-2:

1.

During visual examinations of hangers on the RHR System, spring hangers RHR-HD-194C, HD-16F,.HD-189A, and HD-87C were found to have unacceptable load settings..As required by IWC-2430, additional examinations were conducted on an-equivalent; number of similar components, and no further rejectable conditions were discovered.

?-

Page 9 of 72

-1.

Ownsr Varmont Yankte Nuclear Power Corp. 77 Grove Street,Rutland,Vt.

05701 (Name and Address of Owner) 2.

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

0$354 (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.(continued):

2.

During visual exaninations of hangers on the Core Spray System, spring hanger CS-RD-84 on Core Spray Line CS-2B was found to have an unacceptable load setting. An additional examination was conducted in accordance with IWC-2430 on a similar component in this system and no further rejectable conditions were discovered.

3.

During performance of visual inspection on hangers in the HPCI

. System, rigid hanger H-31 on HPCI Steam Supply Line MS-4B was fcond to have a loose turnbuckle. A similar component in this system was visually inspected and no further rejectable conditions were discovered.

G.

Code Subarticle IWD-2410 (c):

1. _ During-performance of' visual hanger inspections with the Service Water System operating, rigid hanger H-133 on RHR Service Water Line SW-6A'was found to have'a 1 pose nut and excessive movement. Although

-no additional examinations are required by ASME Section XI for Class 3 systems an additional examination was conducted on a similar component

.in this system and no further rejectable conditions were noted.

H.

[Other Findings:

During performance of a walk-down. inspection of Safety Class 3 portions

- of the Reactor Water Cleanup System at plant startup, additional leakage was. discovered at line CUW-3 between the regenerative and non-regenerative heat exchangers. The entire line was examined and no other leakage was

~

detected.

12. Abstract of Corrective Measures Recommended and Taken:

A.

' Category _B-N:

's t,

1.~ Jet Pump Beam No.~ 8 was' replaced'by-Ceneral Electric technicians prior to plant stattup.

~

4

':2. A clamping device was installed over the Core Spray Sparger "C" junction boxJto minimize the effect-of leakage'through the cracked area and to mitigate the consequences of possible' drop-out of the cracked portion

'of the cover-plate, u

- B.-

Ca~egory B-J:

l'.' The entire CUW-18 suction-line'from the branch connection at RHR-32 to 3

the cutboard' isolation. valve V12-18 way replaced with materials that

=' '

<satisfyL the intentLof NUREG-0313, Rev..l.

- All nondestructive examinations

~and proof. tests' required by the applicable construction code ~and ASME~

Section XI were~ performed on the installed piping. A portion of piping

containing cracks has been sent to a laboratory for determination of the e ; failure. mod,e.'

Page.10 of 72'

1.

Ownnr Vermont Yankte Nuclear Power Corp.,77 Grove Street,Rutland,Vt.

05701 (Name and Address of Owner) 2.

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

05354 (Name and Address of Plant) 3.

Plant Unit 1

4.

Owner Certificate of Authorizatior.(lf required) DPR-28 5.

Commercial Service Date 11/30/72 6.

National Board Number for Unit Nonc 12.

Abstract of Corrective Measures Recommended and Taken (continued ):

C.

Category B-K-1:

1.

-The rejectable indicati6ns on the RR-70 attachment weld were ground out, examined by liquid penetrant and visual inspection methods, and accepted.

An evaluation of actual grinding depth was performed to verify that minimum wall thickness requirements had not been violated. The results of this evaluation were acceptable.

D.

Category B-K-2:

1.

All Recirculation Loop A & B spring hanger load settings were adj usted to within specification requirements, visually reinspected, and accepted prior-to plant startup.

2.

Spring hanger HPCI-3 load setting was adjusted to within specification requirements, visually reinspected, and accepted prior to plant startup.

3.

The loose pipe clamp on snubber CU-2 was corrected, visually reinspected and accepted prior to plant startup.

E.

Category C-D:

1.

RHR A Heat Exchanger flange bolting was adjusted to within specification requirements, reinspected and accepted prior to plant startup.

F.

_ Category C-E-2:

1.

All RHR system spring-hanger load settings were adjusted to within specification requirements, visually reinspected and accepted prior to plant startup.

12.

Core Spray spring hanger CS-HD-84 load setting was adjusted to within specification requirements, visually reinspected, and accepted prior to plant startup.

3.

The loose turnbuckle en rigid hanger,H-31 was corrected, visually reinspected and accepted prior to plant startup.

G. -Code Subarticle IWD-2410 (c)

~

'l.~-The loose nut and excessive movement on Service Water hanger H-133 were corrected, visually reinspected and accepted prior to plant startup.

'H.

Other Findings:

l. 'The cracked section of RWCU line CUW-3 was replaced with material that has improved-corrosion resistance. All nondestructive examinations and

-proof tests required by the construction code and ASME Section XI were performed on the_ installed piping. A portion of piping containing cracks has'been sent'out~to a-laboratory for determination of the failure mode.

?

Page 11 of 72

1.

Owner Vsrmont Yankee Nuclear Powar Corp.,77 Grove Street,Rutland,Vt.

05702 -~

(Name and Address of Owner) 2.

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

05324 (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 Note: Unless otherwise indicated above, no further corrective action was deemed-necessary for the conditions noted.

IS0 METRICS (Attached)

Note:

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$*R NG MANGAR OR SUPPORT 3

(Neme and Address of Ownett 157. Vernon vt.

05354

& INTEGRALLY wCLD'E0 SPRahG MANG AR OR SUPPORT

2. Plan, Vermont Yankee Nuclear Power Station, P.O. Box (Nanne and Address ud Pland RIGr0 HANGAR,$UPPORT OR RESTR AINT a

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4. Owaer Cettdorate of Awthoruaten 4d fequwedl.. DPR-28

3. Plane Ung e

INTEGRALLY WELDE0 RPGIO NANGAR, SUPPORT OR RESTRalNT NQAe

$. Commercial service Deve,111.3Q/116. Nstens' Board Numhet fas Umt INTEGR ALLY WELDED $wAY $R ACE

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,z" h f Tar.' ee helear Power Cera. ?? Crove Street.htlanL Vt-05701

3. o. nee Versent v

theme and Aderen of oweeve u -s a Q-F Box 157. Verv e. Vt. 0535. Yankee helear Pcwer St ation., m.O. g g 2 Nee V e rnor.t ma, a.d wre.a. g m-n 1 .o.-cm.<-.. 4 .ue, d, i m., v e. o .e g g e Mre g S C_ ..al Seewwe Date '" f ?1 e Naisonal Board hombee W Unse o -= o e z, l 3 g 7 Cospponeauimeened g g g gw O gas .= .b. o e = u 3 Z W 4 4 D g E x e et 0

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/ / l- 'S 'O g 7 / / t.ECEND l 10 / l' l j! 8,$PRING HANGAR OR SUPPORT i, - a p 4 INTEORALLY WELDEO SPRING HANSAR OR SUPPCAT / e Rio)O HANDAR SUPPORT CR RESTRAINT / h/p/ g a INTEORALLY WELDED R108D HANGAR, SUPPCRT OR RESTR4 TNT SWAY ORACE

• =

~ tidTEORALLY WELDED SWAY ORACE H Do 4* i an SHOCK SUPPRESSOR l 4 es en if4TE0n ALLY WELDED SHOCK SUPPRESSOR q ! INTECR ALLY WELCED $ HEAR DLOCNS - I RHR PIPING LINE..c.. DRWG* H-6 REE EDASCO D'NG.5920-FS-1430

~ .m p. + B. Owner Jragn(,Ignhte_,)[uiliaI,ftyet C9IPu 2.l 9[9Y1.Jtreet.RgQ,nd. Vt. 05701 (Nanw and Address of Owneep

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

05354 t (Name end Addresssof Pland J. Plane Umet I

4. Ownee Certifwase of Aetheriserion (of repwedt DIR*28

5. Coenmercial Service Date MQl.22. 6. Nevsonal Board Numbes for Un e None F2A-SA

7. Componeans lespected F2A

• 2 A-5 8 F

e 'gw_ N4B N40 N4A SW[ F6A FF t F64-SA {N4A F64 % .\\ r3-29 I b FW-78 8 1 bFW-182 ,.F2 t2 )

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[$ V2 29A Lggggg F-lO F84 = FW-ll A F 9\\v 2-t e A 6 senso nAucaR OR SUPPORT l 4 INT (GR ALLY WELDED $PRIP.G M ANGAR OR SUPPORT l 4 RIGIO HANGAR,$UPPORT OR RESTR AINT INTEGR ALLY WELDED RIGID NANG AR,5UPPORT OR RESTR Ashf a j S*AY SRACE

== t INTEGR ARY WELDE0 $way ORACE

• ==

p.4' l =o SHOCK SUPPftC550R -o ,~1cGRau,.cLoro s 0CK sU-Ess0R yi 8 IN T EGR ALLY wtLDEO $HE AR 8 LOCKS i ~ l FEEDWATER PIPING 1.lNE "A" l RcF c Asco owa.s,20-Fs 12. DRWG. H-7 L

N. [s O O.

• mm I, poner _YttmontJank e.llude.4dgwer_Corpu,,JUrfvgJttett,Itydep4 y.LdF01 t

(Nonw and AdJeein of O nne 2 Plan, Vermont Tankee leuclear Power St at ion P,.O Box 157, Vernan. Vt. 0},Q4 u (Name end AJJesu e,( Pland a N4C5W 3, Pl. N _ 1 e o.,,n tenir.. ng a,,,h in sig,eq.,,eo DPR-28 e u4c "A'$osa "-~ ~ " - ~ - ' -'~ ~ / 'f54*lt 7, t impa enu an.peewd / N40- "~ 7" J*E4 $w Fe -F 3 A F34-$A .FSA-SS F Dw.10 .a I b FW-10 a l9 Q ' - F0W-20 b 00 W F S' ~ e 1 h FW-12 0 03 M p FS-SA b 8 20 7 ~ FtCs FM ],p e t -., ' 3 FW 214 F3 3A ~~ F DW-lO I4 mm N a y, pg p'3 3,. (Ow-IF F2 I pgg,g.gg FW-17 res 6 Vt 2Sg Liefh0 , ;.,S A F F FF ,',2 A gg 0 SP"'N8M'N8'" 088VP'0"I f'W-t4 6 ( -Ma F W -lG W-22 1- -F0W-20 & INit0R ALLY wtLDE O SPRING M AN644 OR SUPPORT . Recio HANGAR 3UPPORT OR RESTRalNT l e INTECR ALLY wtLDEO fit 010 H ANGAR, SUPPORT OR RtlTR AINT l SWAY BR ACE I INTf 0 RALLY wttetD $way SRACE P4 l .an SM0 Cit SUPPRESSOR l ses luf COR ALLY wt(Cf D SHOCR SurvRt 550m l 1 INit0RatLv sitet0 5HE AR DLOCuS .o w i FEE 0 WATER PIPING LINE "0" DRWG. H-8 8 a v.toAccOOwa.5,10-rs 1,.

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8. Ownev,,ltnnent.lgnkee NuSJepd.oweLQorpulqroyejtgeeMutlanddt. 05701 (Name and Address of Owner) g,pi Vermont Yankee Nuclear Power Station F.0, Box 157. Vernon, vt.

05154 t ' (Name and Addetes of Plant)

3. Ptees Uns I'

4. Ownee Cered = see of Authareration (si requaed) DPR-28 S. Commercial 5erwece Daae.1111QU2.6 Nasonal Bom 9 Near for Uns None

7. Components inspected I

l I. GRD RETURN PIPING m w 0: I oo-l 9 REMOVED AND REROUTED e N H f aL RPV i -w i WELD CAP-N9 ) Cerlss s&f N9S I coue ur i Lto!NO & SPRING HANGAR OR SUPPORT 4, e INTEGRALLY WELDED SPRING HANGAR OR SUPPORT l a RIGIO HANGAR SUPPORT OR RESTRAINT INTEGRALLY WELCED RIG 10 HANGAR, SUPPORT OR RESTRAINT SWAY BRACE

==

• INTEGRALLY WELCED SWAY BRACE

.so SHCCK SUPPRESSOR h

• eo INTEGR ALLY WELDED SHOCK SUPPRES$0R 1 INTEGRALLY WELDED $ HEAR BLOCKS

>a WO CRD RETURN DRWG. H-9 N0ZZl_E i. a

r O Lf0ENO I. Owner 1gTP?.DI_lankee Nuc_] ear _fewetCorp2 77 Crove,_gMJttg2Rutland d W 3701 & $PAING M ANGAA OA SUPPORT (Nanne and Addr*gs e Owner)

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

053}4 & 88sfE0AALLY WELDED $PAING HAN04 A OA SUPP0Af ^ e AiGt0 HANGAR,5UPPCAT On Atsf Matter

3. Ptene Unet I

4. Owner Ceredersee of Authoresasson (of requered) DEI"28 INitGAALLY w(LDED Ases0 HANGAA,suPP0AT 04 AtSTAAssef e

S. r .;al smise Dae* 11/J0112.e. Neeienal soard Nemtwr for Unst Nune e-SwAv s4ACC sNTEGRALLY wtLCIO SwAV SA ACE .ao $HOCR SUPPatSSOA e INif GA ALLY w(LOf D $ HOCK SUPPRE5'304 F,7A F,7 F6A pg g INTEGA ALLY wtLDED $HE AR 96MKS F04 s. F8 8 F5 F4A PSA F4 RPV HEAD f ~ m b oo to t awu as M S O F3g - AH A-ag.2 "i l-+-- FL AN G E "A" r30 I F99 y fu N I F 3C -- O - -F3G F4 E F 3F vio.29 vio-32 F3A,,p3 F3 pg g, ps i f F2A N-IT Ft. ANGE **B"NI?rts,- Ts' RHR-IlA RPV CONTAINMENT r2 /]RHR-i s 2 PH A-19 = FIA a g g.,,,, I 81HR-12 RHR-13 i l F28< I I l-s e-4 8 i HEAD SPRAY PIPING DRWG* H-lO REF. E8ASC0 0w0.SS20 FS 3438 e i e

m O A ,m ' f~ r

t. ow ee _Ytr=ondgnkee Nusleadwer_CorPu 77 GColf Ltre&R L]nddt. 05701 J

(Nanne and A&w of DeneH Plass Vermont Yankee Nuclear Power Stating P.O. Box 157. Vernon. Vt. 05354 2 (Name sad Addeets of Plant) DII"20 I 4 Ownee Certifacete of Astlwneseson hf reepswed) 3 Pisas Und N g*

5. Carnmernal Servese Date MQl11.6. Nanonst Board Nisenber for Unet Q

7. Carnponents in.pected

~ NSA NSASC g F6A eF6 8 FSO FSC FSS 'm ,'FSA tf j cs,4e I e U 8 FS FIA k Vl4 -14 9 I4 FI N e f30' l h F3 CSI PE N.Y-IS A r3A- \\ 8 vt4-138 .F 3 4 y s i I F3 vl4 -12 8 4 8 CS-38 ~ 8' LFGfNO I & SERING HANGAR OR SUPPORT l a iNiecRAtty wrt0c0 seniNG uANcAR OR suPP0av RIGIO H ANGAR,$uPPORT OR RESTR AINT l INICGR ALLY WELOCO RiGIO HAN04R,$UPPORT OR RE5fRAIIIT SeAY BRACC I INYt0R ALLY wet 0(D $WAY OR ACE = .us SHOCK SUP#RESSOR l .eu) INIEGR ALLY wEL0E0 SHOCW SUPPRESSOR t 4 i .Nic.RA u Y. u 0 0 neAR toc s t; j ~ I CORE SPRAY "A" SIDE DRWG* H-11 i Rtr ES ASCO OwG $920-FS-149 e

[%. s b-f a! r- ^ %=.

8. Owner ArinoCenk e NuijesLIwtE_C9fPu_22_.9L9Ye I(EffLEWLland.JWJ701 f

IPeame an.$ Addren of Owners

2. Plane. Vermont Vankve Nuclear Power Stat ion n

0. Box 157. Vernon. Vt.

05354 P (Name and Addrene of Pleno 3 Plant Unie __I 4 Owne,Cerederate of Authoessation fif reqwwed, DPR-28

5. C

..at Service Dave lif30f]2. e. Neueenal Rosed Number Int Unst ligge

7. Components Inspected B

9' FSS FSC "FSA FSO N SS5C

• c FSA NSB CS-3A F

0 g N g" Vi4 -14 A ,2 B&lb, vlA-iz O l'n f'leM-3 FS' F 3 A.. ' PEN M-160 7, V44-83A CS-2 FIA l Fl 8 t I C3 4A i g* l t ECEiso I' & $PRING HANGAR OR SUPPORT & INTEGR ALLV WELDEO SPRih0 H AhG AR OR $UPPORT RIGID M ANG AR. SUPPORT OR flESTR AINT e a BNIEGnat1V WELDED RIGIO HANGAR,5UPPORT OR RE$1RAINT f 5*Av BRACC

• = INIEGRALLV WTLDED $wAv SRACE g

.m> 5HOCh $UPPRE550R 1 .so INTEGR ALLY wtLDED $ HOCK SUPPRESSOR $f I GNTEGA ALLV WELDED SHE AR sLOCK5 w I core SPRAY "0" SIDE DRWG. H - 12 I REF COASC0 0wG. 5920 FS 143

e O- / \\

t. oom JermonMankee NuiltatfewerJMr.,,,,Z,l_Stovg.1tretLhtlanddt pj701 (Namor and AJJeest of peacet

' 2. Piene Vermo. Yankee Nuclear Power Stat ion P.O. Box 157, Ve rnor*. Yt, OD}4 t therne end Addeegn of Ptent) s 9 Plant Ua s I e Owner Ceetsf areer ed Aetherinseene tsf requaed, DPR-28 S. Carnemsal %ervue Dese MJQ/]16. Mateenal Scard Nomties fot Unse Ngge

7. (

s pa.e4 CU-5 6 bCU-4 I rsa - F6Al F69 Fct aCU-6 y cow-se F6G.aCU-7 00 ACU-3 O 8 aCU-8 y l CUw-I-F6C t/t FF k ete< x-se h-j ACU-9 Cb-2 vit te .r u W3 l V12 1 S ' F2 l' 0 8 V12 45 1 ' FIS l I t f GtwQ ,e .l mm-sa 6 $PaiNG waNGam on SUPPomf I & tNitGnalty witO(D $PRING MAN 344 On SUPPont piGiO waNGAR,$UPPom7 04 Misf R AINT p, l e l e iNTEGWattY witOCO RIGt0 MANGAR,$UPPORT OR RE5inalNT Ja obeks s/ tut /3A $as, e.nCE sNT(Gnalty wttCEO $wAY SW ACE y ggg[g/ .. SnoCm suPratison >.e -u G.1si<<ra,t was r ~ isa -ess TNT (Goatty wtLCEO SHOCR $UPPRESSOR I INf f Gnat tv mfLCEO 5H(84 OLOCMS f N M OM Of /tdu ps// o" l REACTOR CLEANUP DEMINERALIZER PIPING DRWG. H-13 Rtf E8ASCO DwG.5920 FS 14S

I~- a.,,k -Vl2-18 c S25 g[7 7 / ] I h '< 73 NgNp ly i, E,' i i-8 a CU A 1 z ? E \\ /U-7 e - 3 S17 U A-CU-6 ii[ [ 13 IC Cu p.,8 g g g, i; -C U-5

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ISI SLHMARY REPORT t e Page 56 of 72

PREFACE This report covers the Inservice Inspection of Vermont Yankee Nuclear Power Station during the period 8 September 1980 through 31 December 1980. Included in this report is the Form NIS-I as required by the provisions of ASME Section XI and a summary report of the examinations performed, conditions observed, and corrective measures taken. 4 i i l e j: ' Page57 of 72 1

1.0 INTRODUCTION

This report describes the Inservice Inspections performed during 1980 at the Vermont Yankee Nuclear Power Station, Vernon, Vermont. The examinations performed are those of the first 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 plant Technical Specifications. Pressure boundary welds, integrally welded supports, and adjacent base material were examined as required by Section XI to the extent that the system design and non-dastructive testing technology permitted. All limited scans are described in the data. This report summarizes the areas examined, the type of examinations, the results of the test data, evaluations and repairs. Ultrasonic, radiographic, liquid penetrant, magnetic particle and visual examination techniquer were employed to perform the required examinations. 1.1 Examination Methois, Non-destructive examinations were performed in accordance with the procedures contained in the Yankee Atomic Electric Compa.sy, Engineering Guidelines, Book III, " Inservice Inspection NDE Procedure", or Vendor Procedures reviewed and approved by Yankee Atomic Electric Company per the Engineering Department Quality Assurance Manual. The examination procedures were reviewed and approved by personnel qualified to SNT-TC-1A Level -III. These procedures conform to the requirements of ASME Section XI (S'75) and the referenced Page58 of 72

parts of AMSE Section V (S'75) except where these editions are in conflict with the Technical Specification requirements, i.e., for Category B-F and B-J, Section XI S'76 Addenda Appendix III and appropriate acceptance criteria. The inservice examinations were performed and evaluated by personnel qualified to the 1975 edition of SNT-TC-1A. The procedures used for these examinations are listed in Fection 10 of the NIS-I Form. 1.2 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 as defined in the Vermont Yankee Nuclear Tower Station Technical Specifications. 1.3 Examination Results Summaries of all the examinations that were performed are contained in Sections 2 through 10 of this report. The detailed examination data along with the' calibration records, procedures, equipment certifications and personal certifications are maintained at the plant site. 2.0 REACTOR VESSEL DATA LThis section summarizes the inservice examination data for the reactor vessel circumferential and longitudinal welds, nozzle-to-safe end welds, studs, nuts, washers,l bushings and ligaments. Also included are.the summaries for-the closure head circumferential and meridional' welds and interior cladding. For clarity, the results are summarized in' groups of similar ~ Page59 of 72

items. No reportable indications were found. Reactor Vessel Nozzle-To-Safe End Welds Four reactor vessel nozzle-to-safe end welds (N2A-SE, N2E-SE, N2J-SE and N9-SE) were examined using ultrasonic, liquid penetrant and visual techniques. No recordable indications were found. The recirculation inlet safe-end threaded sections were ultrasonically examined. No recordable indications were found. Reactor Vessel Studs, Nuts, Washers, Bushings and Ligaments Six reactor vessel s';uds, and ligaments (6 through 11) and four reactor vessel nuts (6, 8, 61, 62) were examined using color contrast, wa ter-washable penetrant and ultrasonic examination techniques. No recordable indications were found. Six reactor vessel washers (6,8,9,10,61,62) and bushings (6 through 11) were examined visually. No recordable indications were found. Closure Head Circumferential and Meridional Welds Two closure head meridional welds (5" of B1 and 5" of B2), one circumferential head weld (9" of AB), and one flange-to-dome circumferential weld (14 f t. of BC) were examined with ultrasonics. No recordable indications were found. Closure Head Interior Cladding Tr:;6" x 6" closure head clad areas were examined using liquid penetrant .and visual techniques. No recordable indications were found. Page 60 of 72 E

Nozzle-To-Vessel Welds Ultrasonic examinations were performed on reactor nozzle-to-vessel welds including the inner radii. The nozzle-to-vessel welds and inner radii examined were: Recirculation Inlet - N2E, N2J Main Steam - N3C No recordable indications were found during the performance of the inner radii or nozzle-to-vessel examinations. 'CRD Penetration Welds Prior to start-up, eight.(8), (14-11, 14-31, 18-03, 22-23, 26-39, 30-23, 34-19, 42-27),1 control rod drive penetration welds were visually inspected by the Plant Operations Department during the primary coolant leak test. No evidence of leakage was found. Reactor Vessel Internal Components - Jet Pump Beam Assemblies . Twenty ('20) jet pump. beam assemblies were. visually and' ultrasonically examined by General Electric. During the ultrasonic inspection, a rejectable . indication was discovered in jet pump beam #8. - Prior to plant start-up, General Electric.replacedejetipump beam f8. No other' recordable indications ~ were found.. Core Spray Sparger Assembly. One (1)} core spray sparger. assembly was examined visually by General L*- l Page61Lof 72 s

Electric. During the inspection, a rejectable indication characterized as a semi-circular crack was discovered on the "C" sparger junction box cover plate. Prior to start-up, a clamping device was installed as detailed in the abstract of corrective measures taken. No further rejectable conditions were noted. Vessel Head a. N6B (Blank Flange) - 12 bolts and nuts in place No recordable indications were found. - 3.0 PIPING DATA This section summarizes the inservice examination data for the piping welds, pressure retaining bolting and support components. For clarity, the results are summarized in groups of similar velds or items. Category F - Pipe to Safe-End Welds Liquid penetrant and. visual examinations were performed on two (2) pipe to saie-end welds. The examination was performed on core spray "a", weld

1. F3A, and core spray "b", weld #F3A. No recordable indications were found.

Category G Pressure Retaining Bolting Less than 2" Diameter ' Flange bolting was examined visually on the following main steam line components. 1. Main Steam-C" ~ i - Pressure Relief Valve Flange RV-C - 12 bolts and nuts in place ~ a. Page 62 of 72

b. Blank Flange C 12 bolts and nuts in place Category J - Piping Welds Forty-seven (47) piping welds were examined on the following systems using visual, radiography and ultrasonic examination techniques. a. N2D, N2C Risers 2 welds b. CUW-18 (Original Line) 9 velds c. RHR-32 to CUW-18 (Baseline) I weld d. CUW-18 (New Line) (Baseline) 17 welds e. RHR-C Line 30 5 welds f. Recirculation Riser N2A 5 velds g. RHR-A Line 32 I weld h. FDW-A Line 20 1 weld 1. Main Steam-A Line MS-7A 1 veld J. Main Steam-B Line MS-7B 1 veld k.- Main Steam Attachment (RCIC) l' weld

1. - Recirculation Risers - N2J, N2E 2 welds m.-

RHR-18-1 1 weld TOTAL 47 welds l Note: Ten (10) ou.t. of forty-seven (47). welds were examined in accordance with Proposed, Change 70 to Technical Specifications 'for augmented inspection of service-sensitive lines. "The examinations above included twelve (12) inches of intersecting ~~ Liongitudina) < seams where applicable. Of the forty-seven welds, five had recordable' indications. The five (5) welds were part of _ the original CUW- . Page 63 of 72

18 line which was replaced during this outage. Category B-K Integrally Welded Supports Three (3) integrally welded supports were examined using liquid penetrant, visual and magnetic particle techniques. The supports were: Recirculation Loop "B" - Support RR-70 Feedwater "B" - Support FW-22 Reactor Water Cleanup System - Support CU-3 During liquid penetrant inspecticn of support RR-70, a rejectable indication was found in the attachment weld metal, as noted in abctract of conditions. Corrective measures were taken as noted in Section 12 of the NIS-I report. Results were acceptable with no further indications reported. All other supports in this category had no recordable indications. Category B-K Non-Integrally Supports Twenty-(20) non-welded hangers and supports were visually examined in the following systems: ~1 a. Recirculation Riser N2A - RR-51 2 b. Recirculation Ring Header - _RR-57, RR-38 5 c. Recirculation Loop "B" - RR-65, RR-66, RR-71, RR-75,RR-88 1 d. Main Steam "B" - MS-16 l' e. Main Steam "C" - MS. 2 .f. 'Feedwater "B" - FW-20, FW-15 l' ~ g.- HPCI Steam Supply Line MS-4A - HPCI-3 - Page54 of 72 y ,p9 -e m

s 2 h. RCUW - CU-1, CU-2 (NOTE: CU-1 & CU-2 were examined on the original CUW-18 line. They were examined again for baseline on the new CUW-18 line.) 3 1. Recirculation Loop "A" - RR-29, RR-30 _1;

j. Feedwater "A" - FW-3 20 TOTAL EXAMINATIONS During visual inspection of spring hangers RR-66, RR-65 (Recirculation Loop "B") and HPCI-3 (HPCI Steam Supply Line MS-4A), the load settings were found to be out of specification. At this point, the program was expanded to include spring hangers RR-29, RR-30 (Recirculation Loop "A").

These were also found to have unacceptable load settings. All recirculation loop "A" and "B" and HPCI-3 spring hanger load settings were adjusted to within specification requirements, re-examined and accepted. Visual inspection of hydraulic snubber CU-2 (CUW-18 Line) revealed a loose pipe clamp nut. This was corrected, reinspected and accepted. 4.0 CATEGORY B-G PUMPS Cover-To-Casing Boltu (Pressure Retaining Bolting 72") Seven (7) cover-to-casing bolts (2, 4, - 6, 8, 10, 12,14) on recirculation loop "B"'(P-18-1B) were examined visually and ultrasonicsily. No recordable indications were found. B-K Non-Welded Supports Two (2) non-weldei.; supports (RR-20, RR-76) on recirculation pump A and B L. A were visoally. examined. 'No recordable indications were found. Page 65 of 72

5,0 VALVES Category G Pressure Retaining Bolting Less Than 2" Diameter Visual examination was performed in place on the bolting of 6 valves indicated below. The total bolts numbered 80. System Valve Bolts / Studs and Nuts RHR "A" V10-18 24 RHR "B" V10-27B 16 RHR "C" V10-27A 16 Main Steam "C" RV2-71C 12 Core Spray "B" V14-12A 2 Recirculation Loop "B" V2-54B 10, TOTAL 80 No recordable indications were found. 6.0 S_AFETY CLASS II This section summarizes the inservice examination data for Safety Class II components.- They are as follows: circumferential shell welds (RHR "A" Heat Exchanger), flange bolts and nuts, integrally welded supports, non-welded supports, pipe welds, pumps and valves. For clarity, the results are summarized in groups of similar items. . Category C-A - Circumferential Weld (RHR "A" Heat Exchanger) One-(l) pressure retaining veld ( A-HTEX-10-1) was examined ultrasonically. No recordable indications were found. Category C-D - Pressure Retaining Bolting >1" q . Sixty-eight (68) bolts and nuts on the upper flange of RHR "A" heat exchanger. Page 66 of 72 t- -

were visually exa=ined in place. Two (2) bolts were found to have insufficient thread engagement. These were adjusted within specification requirements, reirspected and accepted. No further indications were found. Category C-D - Pressure Retaining Bolting >1" Sixteen (16) flange bolts and corresponding nuts on the HPCI main pump were visually examined in place. No recordable indications were found. Category C-E Suppott Components for Piping, Valves and Pumps Eight (8) integrally welded supports were examined using visual and magentic particle techniques in the following systems: a. HPCI-2 Line - Support HD-26A b. HPCI-3 Line HD-108A

c. -HPCI-ISB Line HD-22B d.

RHR-2A Line HD-183A -e. RHR-3A Line' HD-130A f. Core Spray - 2A Line - HD-89 g. Core Spray - 2B Line - HD-85C HD-156A. h. RHR-6 'No recordable indications were found. Category C-E Support Components for Piping, Valves and Pumps (Thirty-seven (37) non-welded. supports were visually examined on the following ~ systems: a.. MS-4B - Support H-13, H-6, HD-103B Page 67 of 72 - 'O ?.

b. HPCI-3 - Support H-107 c. HPCI-15B - Support H-31 d. HPCI Booster to Hain Pump Piping - Support H-201 e. CS-2A - Support HD-52A, H-49 f. CS-2A - Support HD-90A g. CS-2B - Support HD-84, H-85 h. RHR-1B - Support HD-181 1. RHR-2A - Support H-183, H-185

j. RHR-3A

- Support HD-130C - k ~. RHR-3C - Support HD-197B 1. RHR-3D - Support HD-129B m. 'RHR-6 - Support HD-200D, HD-187A, HD-189A n. RHR-7 - Support HD-16F, HD-16B o.- RHR-8 - Support HD-200G p. RHR - Support HD-194C, HD-194B q. RHR-10 - Support CS-HD-54E r.' RHR-14 - Support HD-87B, HD-87C s. RHR-15 - Support HD-134B, CS-H-86B t. RHR-40 - Support HD-23, HD-28, HD-34 u. CRD-6A - Support H-14

v.

CRD-6 - Support H-13 w. CRD-8 Support H-5 TOTAL 36 'During the performance of the visual inspection,' spring hangers RHR-HD-194C, HD-16F, HD-189A, HD-87C, and CS-HD-84 were found to have unacceptable load - settings. Also, rigid hanger H-31 was found to have a loose turnbuckle. Page 68 of '72

.i All spring and rigid hangers were adjusted to within specification requirements, visually reinspected and accepted prior to plant startup. 7.0 CATEGORY C-F - PRESSURE RETAINING WELDS IN PIPING, PLMPS AND VALVES IN SYSTEMS WHICH CIRCULATE REACTOR COOLANT LThree (3) piping welds were exasined ultrasonically on the following syste=s: a. RHR-1A - Weld S-2 b. RHR-IC - Weld F-2 c. RHR-2C - Weld S-2, No recordable indications were found. Category C-C - Pressure Retaining Welds in Piping, Pumps and Valves in Systems Which Circulate Other Than Reactor' Coolant Four (4) pressure retaining welds were examined ultrasonically in the. following systems: a. HPSI-15B - Weld F-4

b. ; Core Spray "B"

- Weld S-19 c. CRD Return Line - Weld 6A-4 'd. MS-4B- - Weld S-4A No recordable indications were'found. Base. line on ' sixteen (16) piping' velds.was -performed on the.CRD return line -using ultrasonic examination techniques.. The lines involved are listed below: 1

a.

CRD-6a - Weld 6A-1A Page 69 of 72

6A-1B O 6A-lC 6A-ID 6A-lE 6A-lF J

b. 'CRD Weld 6-4A c.

CRD Weld 8-3A d. CRD-5A - Weld SA-1A SA-1B 5A-lC 5A-1D 5A-lE SA-lF e.. CRD Weld 5-4A f. .CRD-7 - Weld 7-3A No recordable indications were found. , SECTION 8.0 i - - Category C-E Support Components for Piping, Valves and Pumps . Four (4) integrally welded supports were examined on RHR pump P-10-1A using

magnetic particle techniques. No recordable indications were found.

- SECTION 9.0 LCategory C-D - Pressure Retaining Bolting >l" Twenty-four (24) bolts and corresponding nuts on RHR valve V10-48A were Page 70 off72 bb

visual examined with three (3) of the twenty-four (24) examined with magnetic particle techniques. No recordable indications were found. 10.0 SAFETY CLASS III This section summarizes the Inservice Inspection (performed in accordance with Section XI, IWD2410 (b) and (c)) data for Safety Class III pipe hangers and supports. IWD 2410(b) - Fuel Pooling Cooling System Five (5) pipe hangers and supports were visually examined under hydrostatic test pressure. They are the following: Support H-3, H-4, H-5, H-6 a. FPC-1B Support H-8

b..FPC-19 No recordable indications were found.

IWD 2410(c) - Service' Water Piping Seventeen (17) pipe hangers and supports were visually examined while ~ operating. They are the following: Line SW-18A - Support H-56, H-57, H-58, H-197, H-197B, HD-200A, a. H-76, H-216, HD-218A 'b. Line SW-18B - HD-230A .ine SW-8 'HD-215A H-133 o.- Line'SW-6A' H-126 e.- Line SW-6B

f. >Line SW-3 H-244B

_g. Line SW-2A - HD-244A Page 71 of 72 E

h. Line SW-1A - RD-88D, HD-246E O During the performance of visual hanger inspections, H-133 on line SW-6A o was found to have a loose nut and excessive movement. This problem was corrected, visually reinspected and accepted prior to plant startup. No further indications were found. System Pressure Test The Reactor Coolant System was given a system pressure test at operating pressure per IWB-5221 and Vermont Yankee OP4101. The reactor vessel, recirculation risers and non-isolable portions of the reactor coolant boundry received a systen hydrostatic leak test per the requirements of IWB-5222. The system hydrostatic leak test was performed as required by IWA-4210, which requires a pressure test af ter welded repairs. The subject repairs were replacement of the reactor clean-up water suction line (CUW-18). No leakage -(other than normal controlled leakage) was detected in either test. Conclusions The examinations performed during this outage constitute approximately 1/3 of thor. required'for the-third period of the first interval. There are no unacceptable conditions and no continuing or follow-up items. 6 Page 72' of "7:2 t}}