ML20011A924

Inservice Insp Exam Rept for 810502-0625.Describes Inservice Insp Performed During 1981 Refueling Outage

ML20011A924
Person / Time
Site:	Yankee Rowe
Issue date:	10/14/1981
From:	Lane R YANKEE ATOMIC ELECTRIC CO.
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ML20011A921	List: ML20011A920 ML20011A924
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NUDOCS 8111030360
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INSERVICE INSPECTION EXAMINATION REPORT YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION MAY 2,1981 TilROUGH JUNE 25, 1981 8111030360 011030 PDR ADOCK 05000029 G

PDR

PREFACE This summary report covers the inservice inspection of Yankee Nuclear Power Station during the period of May 2,1981 through June 25, 1981, also included within the scope of this report is the inservice inspection, that was performed during the period June 9,1980 through July 12, 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.

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Table of' Contents i

Page s

Preface...................................................

1-Ta bl e o f Co n t e n t s.........................................

11 NIS-1 Owner's Data Report ISI Summary Report

1.0 INTRODUCTION

1.1 Examination Methods.............................

1.2 Examina t i o n o f Da t a.............................

1.3 Examination Results.............................

2.0 REACTOR VESSEL DATA..................................

1 3.0 ST EAM G ENERATO R D ATA.................................

4.0 FEED & BLEED HX......................................

5.0 PIPING DATA..........................................

6.0 PUMP DATA...........................................

1 7.0 VALVE DATA...........................................

8.0 SYSTEM PRES SU RE L EAK TE ST............................

9.0 SAFETY VALVE TESTS...................................

i 10.0 REPAIRS & MODIFICATIONS..............................

5 11.0 CONCLUS10NS..........................................

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FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules Yankee Atomic Electric Co., 1671 Worcester Road, Framingham, Ma. 01701

1. Owner (Name and Address of Owner)

2. Plant Ynnkoo Mncionr Pnuor Senrinn, nnwg Macenchnentre 01367 (Name and Address of Plant)

DPR-3 Yankee Rowe

4. Owner Certificate of Authorization (if required)

3. Plant Unit

5. Commercial Service Date 7/1/61

6. National Board Number for Unit R..ncent #NR M96tf

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

Province No.

Board No.

Reactor B&W 610 0011 N/A 2396U Steam W

N/A N/A 404E(Z)1 Generator Piping S&W N/A N/A N/A i

n 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

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i FORM NIS 1 (back) 5/2/81 7/25/81,,,,,,,,,;,,,n,,,y,ig,o, 12/1/74

,o 12/1/84

8. Examination Dates

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

11. Abstract of Conditions Noted See Attached Page l

12. Abstract of Corrective Measures Recommended and Taken See Attached Page a

b We certify that the statements made in this report are correct and the examinations and corrective mes-4 sures taken conform to the rules of the ASME Code,Section XI.

39 Signed gyg g [3M Sept. 29 81 Y.A.E.C.

Date Owner fCertificate of Authorisation No. (if applicable)

DPR-3 Expiration Date 11-4-97 (U.S. NRC Facility Li cetise No. )

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Massachusetts and employed by li.S.B.I. & I. Co.

or

, Inspectors an<f/,or the State or Province of

_ have ins ected the components described in this owners' Data Report during the period 5/2/81 to 7/ 5/81

. and state that to the best of my ktowledge and belief, the Owner has performed examinstions and taken corrective measures described in this Owrers' Data Repon 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 Report. Furthermore, j

neither the 8nspector nor his employer shall be liable in any manner for any personal injury or property damage i

or ploss of any kind arising from or connected with this inspection, f

October 14, 81 Date

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Commissions Mass. 1182 1-Insp'ector's Signature National Board, State. Province and No.

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1.

Owner Yenkee Atomic Elcetric Co peny 1671 Worcester Road, Frsminghem, MA 01701 2.

Plant Ycnkao Nucle r P:ver Station, Rowe, M3:cachurettn, 01367 3.

Plant Unic ranxee nowe 4.

Uwner certiticate 01 Authorization DPR-3 5.

Commercial Service Date July 1, 1961 6.

National Board Number for Unit Reactor #NB 2396U 10.

AL$ TRACT OF EXAMINATIONS A.

Non-Destructive Examinations Category No. of Components Examined Examination Safety Class I Reactor B-I-l Closure Head Cladding

'vT Press ure B-N-1 Vessel Interior VT Vessel Pumps Main B-C-1 24 Pressure Retaining Bolting UT,VY,MPT Coolant 16 Stator Cap Bolts B-K-1 2 Main Coolant Pump Hangers PT,VT on pump #4 B-L-1

1. 2 Main Coolant Pump Casing VT Valve s B-M-2 1 thin Coolant Check Valve VT Piping B-J 14 thin Coolant Pipe Welds RT B-F 3 Piping Safe-End Welds UT, VT, PT B-J 23 Piping Welds PT,UT,VT Feed & Bleed HX B-B 1 Lower Circumferential weld on VT,PT Heat Exchangers

1. 4 and #1 Safety Class II Steam C-A 1 Circumferential Shell Weld UT,MPT Cencrator #3 C-D 80 Secondary Side }bnway Bolts VT,MPT

1. -1,2,3,4 Charging Pumps C-E-1 1 Integrally Welded Support on #3 Vi s.

Charging Pump Pipi ng C-G 10 Pipe Welds VT,UT,MPT 759 Pipe Welds (Baseline)

PT(2)

C-E-2 18 Non-Welded Supports VT C-E-1 8 Integrally Welded Supports VT,MPT C-C 1 Support Lug on #3 Steam Generator PT Valve s C-E-1 1 Integrally Welded Support VT,MPT NUIES:

1.

Yankee Atomic Examination Procedures were used except where otherwise me ntioned.

2.

These inspections were baseline examinations, as required by IWA-4220 to establish a pre-service record.

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1.

Own:r Ycnkan Ato2ic Electric Company.1671 Worcactor Rord, Fr ringhan, MA 01701

'2.

Plant Ycnken Nuclear Power Station, Rowe, Massachu=etto, 01367 3.

Plant Unit Yankee Rowe 4.

Owner Certificate of Authorization DPR-3 5.

Commercial Service Date July 1, 1961 6.

Fational Board Number for Unit Reactor #NB 2396U

11. ABSTRACT OF CONDITIONS NOTED Ca tego ry C-C 1)

Liquid penetrant examination on the east lug of #4 steam generator revealed 3 linear indications.

C-A 2)

Magnetic particle examination on #3 S.C. head to shell weld revealed a linear indication at area "A" SG-3-1.

C-G 3)

Magnetic particle examination on main steamline weld #M.S.1-5 revealed two(2) linear indications.

B-F 4)

L. quid penetrant examination on S.G. #3 safe end weld #MC-3-6 revealed rounded and linear indications.

B-J 5)

Liquid penetrant examination on loop #4 charging line revealed linear indications on weld #CH-29.

B-J 6)

Liquid penetrant examination on loop #3 main coolant piping revealed rounded indications on weld #MC-3-20.

B-J 7)

Liquid penetrant examination on loop #3 main coolant by pa ss line revealed linear and rounded indications on branch connection MCB-3BRr2.

C-E-1 8)

Magnetic particle examination on feedwater hanger WCBD-RH-118 and WCBD-RH-121 revealed linear indications.

C-G 9)

Ultrasonic and radiographic examination on main steam line welds MS-3-8, and MS-3-10 revealed recordable indications.

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Evaluation by Yankee personnel was made and determined not to he service induced (refer to Yankee memo MEG 370/81).

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12.

ABSTRACTS OF CORRECTIVE MEASURES RECO}NENDED AND TAKEN Category C-C 1)

The indications on the east lug of #4 steam generator were j

evaluated and determined to be depressions which were part of the original as welded surface. The results of this evaluation were acceptable.

C-A 2)

The indication found on #3 eteam generator head to shell weld was buffed out, reinspected by magnetic particle inspection methods, and accepted.

C-G 3)

The indications on the main steam line weld #MS.1-5 were ground out, reinspected bc magnetic particle method, and l

accepted. An evaluation of actual grinding depth was performed to verify that design minimum wall thickness l

requirements has not been violated. The results of this evaluation were acceptable.

Page 4 of 12

1.

Ownnr Yanken Atomic Electric Corpany, 1671 Worcester Rord, Framingham, MA 01701 2.

Plant Yankee Nuclear Power Station, Rowe, Massachusetts, 01367 3.

Plant Unit Yankee Rowe 4.

Owner Certificate of Authorization DPR-3 5.

Commercial Service Date July 1, 1961 6.

National Board Number for Unit Reactor #NB 2396U B-F 4)

The indications found on #3 steam generator safe-end weld MC-3-6 were removed by buf fing. The crea was reinspected using liquid penetrant methods and found acceptable.

B-J 5)

Indications found on loop #4 charging line weld CH-29 were removed by buf fing, and accepted using liquid penetrant methods.

B-J 6)

Indications found on loop #3 main coolant line seld #MC-3-20 were removed by buf fing, reinspected with liqu d penetrant, and accepted.

B-J 7)

Indications found on loop #3 main coolant bypass line veld

1. MCB-3BR-2 were removed by buf fing, reinspected with liquid pe ne tra nt, and accepted.

8)

Indications found on feedwater integrally welded supports WCBD-RH-118 and WCB-RH-121 were removed by buf fing, reinspected with magnetic particle techniques, and accepted.

NOTE:

Unless otharwise indicated above, no further correcting actions was deemed necessary for the conditions noted. The conditions were associated with original construction. They were found to be fabrication (welding) related on the Class II items, all of which were examined for the first time.

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1.0 INTRODUCTION

This report describes the inservice inspection performed during the 1981 refueling outage at the Yankee Nuclear Power Station, Rowe, Massachusetts. 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 System", 74 edition, S75 Addenda except that B-F & B-J category welds were examined per the S76 Addenda Appendix III as referenced by the plant technical specifications. Pressure boundary welds and adjacent base metal were inspected to the extent that the system design and non-destructive testing technology permitted. This report summarizes the areas examined, the type of examinations, the results of the test data, evaluations and repairs. Manual ultrasonic testing techniques were employed in conjunction with visual, liquid pene t ra nt, radiographic and magnetic particle examinations.

1.1 Examination Methods All non-destructive examinations were performed in accordance with the procedures contained in the Yankee Atomic Electric Company Engineering Guidelines, Book III, " Inservice Inspection NDE Proced ure s ". The examination procedures were reviewed and approved by personnel qualified to SNT-TC-1A Level III. The inservice examinations were performed and evaluated by technicians qualified to the 1975 edition of SNT-TC-1A.

12 Evaluation of Data The examination results were reviewed at the site by personnel qualified to SNT-TC-1A Levels II and III.

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

1.3 Examination Results Summaries of the examinations performed are contained in Sections 2 through 10 of this report. The detailed examination data along with the calibration record, procedures, equipment certifications and personnel qualifications are maintained at the plant site.

The procedures used for these examinations are as follows:

Procedure Number Rev.

Title YA-ISI-1 6

Inservice Inspection Program Requirements YA-VT-1 4

Visual Examination Procedure YA-PE-2 2

Liquid Penetrant Examination YA-MP-1 1

Magnetic Particle Examination Y A-UT-1 1

Ultrasonic Examination - General Requirements Page 6 of 12

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l YA-UT-5 1

UT of Veccele - Integral Support Attachment YA-UT-7 1

UT Examination of Bolting YA-UT-9 1

UT Examination of Piping - FerJ' tic Welds YA-UT-10 2

UT Examination of Piping - Austenitic Welds YA-UT-11 1

UT Examination of Piping - Dissimilar Metal Welds YA-UT-14 1

Ultrasonic Examination of Piping Base

}bterial & Weld Heat Af fected Zones OP-4200 8

Main Coolant System Leak Inspection or Pressure Test 2.0 REACTOR VESSEL DATA Category B-I Closure Head C1. adding Plant personnel qualified to perform visual examination examined the closure head cladding over the entire inside surf ace of the teactor vessel head. Particular attention was paid to the known clad defect (see 78 ISI report) near stud hole #13. The defect was measured and photographed. It was determined no change had occurred.

Category B-N Reactor Vessel Interior Plant personnel qualified to perform visual inspections, examined the reactor vessel interior.

The examination included accessible portions of the space above and below the reactor core. No recordable indications were found.

NOTE: This examination was recorded on video tape and stored on site.

3.0 STEAM GENERATORS Category B-G Pre ssure Retaining Bolting Less Than ' Inches Diameter All (80) secondary side manway bolts and washers on steam generators number 1, 2, 3, 4 were visually examined. No recordable indications were found. Magnetic particle examination was performed on 10% of all bolting. No recordable indications were found.

Category C-A - Circumferential Weld One (1) upper head to shell weld (SG-3-1) on #3 steam generator was examined using ultrasonic and magnetic particle techniques. During magnetic particle of weld SC-3-1, an indication was found, as noted in "abstrac t of conditions." Corrective measures were taken as noted in section 12 of the NIS-I report. Results were acceptable with no further indications reported.

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Category C-C - Integenlly Weldad Support Lug The east support lug on #3 steam generator was inspected using liquid penetrant techniques. Ultrasonic examination was not possible due to support configuration.

Liquid penetrant was possible only in the lower 60% of the vertical sides and 100% on the lower side. Indications were found in the attachment weld metal, as noted in abstract of conditions.

Evaluation by Yankee personnel was made and determined to be depressions which were part of the original as-welded surface. These areas appeared not to have been ground out during weld preparation. See Report #PE-21 and NRC Inspection Report 50-29/78-18.

Category C-D - Pressure Retaining Bolting 1"

All the secondary side manway bolting (80) on steam generators number 1, 2, 3, 4 were visually examined. No recordable indications were found.

4.0 CATEGORY B-B - CIRCUMFERENTIAL SHELL WELD-FEED & BLEED HX The lower ciremnferential weld on #1 and 4 feed and bleed heat exchangers were examined using liquid penetrant and visual techniques. No recordable indications were found.

5.0 PIPING DATA This section summarizes the inservice examination data for the piping welds, pressure retaining bolting and support components. For clarity,

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the results are summarized in groups of similar welds or items.

Category B-F-Pipe to Safe-End Welds.

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Ultrasonic, liquid penetrant and visual examinations were performed on three (3) pipe to safe-end welds. The examination was performed on weld MC-3-6 (inlet) and weld MC-3-9 (outlet) in loop #3. Recordable indications were found with liquid penetrant. Corrective measures were taken as noted in Section 12 of the NIS-1 Report. Results were acceptable with no further indications reported. As a result of the-indications on MC-3-6 and MC-3-8, an additional pipe to safe-end weld MC-4-6 (outlet) in loop #4 was examined using liquid penetrant techniques. No recordable indications were found.

Category B-J-Piping Welds Fif ty (50) pipe welds were examined using visual, liquid penetrant, radiography and ultrasonic examination techniques. The following systems were examined:

Exam a.

Shutdown Cooling Branch Connection 1 weld UP,PT b.

Safety Injection Branch Connection 1 weld PT c.

Fbin Coolant Bypass Branch Connection 2 welds PT d.

Main Coolant Piping (358-CF8M fittings) 14 welds RT Ej-e.

Charging (feed) system 4 welds PT f.

Main Coolant Piping 3 welds UT,VT e f.

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Shutdevn Cooling - Loop f 4 5 welda UT h.

Charging Line - Loop #4 4 welds UT i.

Hain Coolant Bypass - Loop #3 4 velds UT j.

Pressurizer Spray Line - Loop #2 (Baseline) 12 welds PT TOTAL 50 welds of the fif ty (50) welds examined.two had recordable LP indications, CH-29 on the charging feed line and HCB-3BR.-2, main coolant branch connection.

Evaluation by Yankee personnel determined these to be of original construction and not service related.

(Refer to Report #PE-12.)

Category C-E Integrally Welded Supports Eight (8) integrally welded supports were examined using visual and magnetic particle techniques in the following system:

a.

Feedwater Line 601 WCBD-H114A b.

Feedwater Line 601 WCBD-H113A c.

Feedwater Line 601 WCBD-H114B d.

Feedwater Line 601 WCBD-H113B e.

Feedwater Line 601-7 & 601 WCBD-RH118 f.

Feedwater Line 601-7 & 601 WCBD-RH119 g.

Feedwater Line 601-7 & 601 #CBD-RH121 h.

Feedwater Line 601-7 & 601 WCBD-RH122 During magnetic particle inspection of supports WCBD-RH118 and RH-121, indications were found in the attachment weld metal, as noted in abstract of conditions. Corrective measures were taken as noted in Section 12 of the NIS-1 report. Results were acceptable with no further indications reported. All other supports in this category had no recordable indications.

Category C-E Non-Integrally Welded Supports

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Eighteen (18) non-welded hangers and supports were visually examined in the following systems:

a.

Low Pressure Surge Tank Cooling System PRCL-H-51 PRCL-H-55 PRCL-H-61 CRT-H-62 b.

Feedwater System (outside containment)

WCBD-RH115A WCBD-115B WCBD-RH116 WCBD-117 WCBD-118A WCBD-119A WCBD-119B 7

. b ' iI.

Feedwater System (inside V.C.)

WCBD-H2 WCBD-H3 WCB D-H5 WCBD-H8 WCBD-H9

-t WCBD-H11 F

WCBD-H12 k

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During visual inapsetien of supports CRT-H-62, PRCL-H-51 and PRCL-H-61, tha

- alignment.and condition of the support rods were ' unacceptable. Both rods and the alignment on support CRT-H-62 were corrected, reinspected and accepted. The alignment on supports PRCL-H-51 and 61 were :orrected, reinspected and accepted.

CATEGORY C-G - PRESSURE RETAINING WELDS IN PIPING, PUMPS AND VALVES IN SYSTEMS WHICH CIRCULATE OTHER THAN REACTOR COOLANT.

Ten (10). pressure retaining. welds were examined 'sith ultrasonic, magnetic particle and visual examination techniques.' The eystems examined were:

a.

Main Steam 3

- Welds MS-3-8, MS-3-9, MS-3-10 b.

Main Steam-1

- Welds MS-1-3, MS-1-4, MS-1-5 c.-

Vapor Container Heating System

- Welds 6-1, 6-2, 6-4, 6-5' During magnetic particle examination of weld MS-1-5, an indication was -

< found, as noted in abstract of conditions. Corrective measures were taken as noted in Section 12 of the NIS-1 report. Results were acceptable wis$ no further indications reported.

Baseline examinations were performed on seven hundred and fif ty-nine (759) pressure retaining welds using liquid penetrant techniques in the following.

systems:

a.

Chemical Shutdown System

- 70 welds b.

Feedwater Cross-connect

- 87 welds c.

Auxiliary Steam System

- 252 welds

,f d.

Auxiliary Feedwater System

- 350 welds Ei TOTAL 759 welds No recordable indications were found.

b 60 PUMP DATA p

Category B-G Pressure Retaining Bolts & Studs P

Twenty-four (24) main flange bolts and sixteen (16) stator cap bolts on #2

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main coolant pump were examined using visual, magnetic particle and

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ultrasonic techniques. The pump was disassembled for maintenance. No recordable indications weJe found.

Category B-L Pump Casing d 'ual examination was performed on Number 2 main coolant pump casing.

a The pump was disassembled for maintenance. - No recordable indications were found.

Category B-K Support Components for Pumps Two supports H-26 and H-17 on #4 main coolant pump were inspected using liquid penetrant and vir.i techniques. No recordable indications were found.

Page 10 of 12 W

C:tegory C-E Integrally Walded Support One (1) integrally welded support on #3 charging pump was visually examined. No recordable indications were found.

7.0 VALVES Category B-M Valve Bodies Visual examination was performed on the internal surf aces of main coolant check valve MC-V-239.

No recordable indications were found.

Cacegory C-E Integrally Welded Support Visual and magnetic particle examinations were performed on main steam throttle valve support (right side). No recordable indications were found.

NOTE: As of the end of the 1981 outage, the main steam throttle valve is now classified non-nuclear safety (refer to EDCR 79-17).

8.0 SYSTEM PRESSURE LEAK TESTS Eight (8) hydrostatic tests were performed af ter modification or repair to Safety Class Systems. The tests were conducted in accordance with Section X1 1WC-5000 for Saf ety Class 2 components and IWD-5000 for Safety Class 3 components. A summary of the tests completed are listed below:

System Safety Class Design Press Test Press Test Dut?*ien

1. Main Coolant 2

2300 2875 20 Mins.

Drain Header

2. Charging Sys.

2 2300 2875 10 Mins.

3. Loop Fill Up-2 2300 2875 11 Mins.

stream of CH-V-617

4. Low Pre ssure 2

680 860 17 Mins.

Safety Inj.

5. Safety Injection 2

1550 1940 4 Hrs.

Recire. Pump High Pressure Low Pre ss.

2 680 850 4 Hrs.

6. Aux. Feed to Steam 2

1035 1340 10 Mins.

Generator

7. Aux. Feed Pump 3

1100 1210 4 Hrs.

Discharge Page 11 of l2

8. Main Steam 2

1035 1250 10 Mins.

9. Reactor Head Vent 1/2 2500 2750 10 mins.

The Main Coolant System was subjected to the Required System Leakage Test prior to startup. All test results were acceptable.

9.0 SAFETY VALVE TESTS The following safety valves were subjected to tests in accordance with ASME PTC 25.2 - 1966 per Section XI Subsection IWV 3510.

Valve System PRSV-181 Pressurizer Code Safety PRSV-182 Pressurizer Code Saf ety SV-409A Main Steam Safety Valve SV-409B Main Steam Safety Valve SV-409C Main Steam Safety Valve SV-409D Main Steam Safety Valve SV-409E Main Steam Safety Valve SV-409F Main Steam Safety Valve SV-409G Main Steam Safety Valve

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SV-409H Main Steam Safety Valve SV-409I Main Steam Safety Valve SV-409J Main Steam Safety Valve SV-409K Main Steam Safety Valve SV-409L Main Steam Safety Valve SV-215E Low Pressuie Surge Tank Safety SV-215F Low Pressure Surge Tank Safety SI-SV-1 Accumulator Relief Valve i

SI-SV-2 Accumulator Relief Valve SI-SV-609 Accumulator Relief Valve SV-204 Shutdown Cooling Relief Valve SV-205 Shutdown Cooling Relief Valve 10.0 REFAIRS AND MODIFICATION The following modifications were performed during the 1981 Outage:

l PDCR 16 Charging pump suction header i

EDCR 8A Feedwater cross connect EDCR 16 Aux. Feed System EDCR 17 Automated Non-return valve l

The design packages and installation programs are on site at the plant site.

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11.0 CONCLUSION

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The examinations performed during this outage complete the Inservice Inspection requirements of the Yankee Nuclear Station Technical l

Specifications for the second period of the second interval.

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