ML20153B229

Inservice Insp Rept from 780129-780828,covering 1978 Refueling Outage Insp W/Abstract of Examinations Performed by Nuclear Engineering Svcs & NDT Engineering Personnel

ML20153B229
Person / Time
Site:	Maine Yankee
Issue date:	11/27/1978
From:	Maine Yankee
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ML20153B227	List: ML20153B223 ML20153B229
References
PROC-781127, NUDOCS 7812010216
Download: ML20153B229 (20)

Text

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INSERVICE INSPECTION EXAMINATION REPORT MAINE YANKEE ATOMIC P0h'ER COMI ANY January 29, 1978 through August 28, 1978 781201opl6 i

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ir I-f, PREFACE 1

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This summary report covers the inservice inspection during the 1

j 1978 refueling outage of Maine Yankee Atomic Power Plant located at Wiscusset, Maine. Included is an abstract of examinations perfornied with the conditions observed and corrective measures taken. These examination's were performed primarily by Nuclear Energy Services Corporation of Danbury, Connecticut, with a limited number .of inspec- i j tions performed by NDT Engineering Personnel and Yankee Personnel.

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TABLE OF CONTENTS PAGE NlS-1 OWNER'S DATA REPORT 1

SUMMARY

REPORT f

1.0 INTRODUCTION

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~1.1 Examination Methods 9 1.2 Evaluation of Data 11 1.3 Examination Results 11 2.0

SUMMARY

OF EXAMINATIONS 12 2.1 Reactor Vessel 12 l 2.2 ' Pressurizer 14 2.3 Regenerative Heat Exchanger 1/

2.4 Piping 15 2.5 Pump Pressure Boundary 17 2.6 Valve Pressure Boundary 17  !

2.7 Safety Class 2 Piping (Valve House) 17 l

3.0 REACTOR COOLANT SYSTEM LEAK TEST 19

4.0 CONCLUSION

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FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS ,

As required byIshe Provisions of the ASME Code Rules i

1. Owner Maine Yankee Atpmic Power Comnany, Wisensmer. Mnina (Name and Address of Owngr) ,

2. Plant Maine Yankee Atomic Power Plant, Wiscasset, Maine (Name and Address of Plant) 1 4. Owner Certificate of Authorization (if required) DPR-36

3. Plant Unit

5. Commercial Service Date 12/29 /72 ,,6. National Board Number for Unit Reactor Vessel 20865

7. Components Inspected Manufacturer

• Component of Manuf turer or installer State or National Appartenance or bStaller Serial No. Province No. Board No.

R.P. Vessel Combustion 2ngineering 67106 NA 20865 R.P. Head Combustion Engineering 67206 NA 20865 Regen. HX Whitlock 75274 NA NA Pressurizer Combustion Engineering 67601 NA 20858-Piping Stone & Webster NA NA NA i

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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.

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This form (E00029) rnay be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017 l Page 1 of 20 ,

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w U. 2 FORM NIS 1 (back)

8. Examination Dates 1/29/78 to 8/28/78 9. Inspection Interval from12 /29/72 to _12 /29/82

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

Page 3 through 20 1

11, Abstract of Conditions Noted Page 7 of 20

12. Abstract of Corrective Measures Recommended and Taken i l

Page 8 of 20 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. ,

7 I Date h /)"? 19 77 Signed Maine Yankee By .[e M('

Owner l l

Certificate of Authorization No. (if applicable) DPR-36 Expiration Date October 21, 2008 CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by'The National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of MA /A/E and employed by MfA I YZ M of

//ARTfCRD (.0 MN have inspected the components described in this Owners' Data Report during the period

/ - 2 7 '7 % to 9 29-7I . 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 snakes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data Report. Furthermore, 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. J Date / /. ~ 219 7

.r7 Commissions M M/NE cohs3H National B'oard, State, Province and No.

' inpctor's Signature 1

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1. ~ Owner Maine Yankee Atomic Power Company, Wiscasset, Maine

2. Plant Maine Yankee Atomic Power Plant,'Wiscasset, Maine l

l 3. Plant Unit #1 4. Owner Certificate of Authorization DPR-36 4 5. Commercial Service Date 12-29-72

6. National Board Number for Unit Reactor Vessel 20865 l

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10. Abstract of Examinations k

COMPONENT CATEGORY NUMBER OF COMPONENTS EXAMINED EXAMINATION i

! Reactor Vessel B-C 50% of reactor vessel flange UT to reactor vessel weld B-C 50% of reactor vessel head UT flange to head weld

B-D 100% of 3 nozzle to vessel welds UT 1 including inner radil B-E Vessel penetrations VT B-G-1 18 closure studs, 18 nuts PT,MT,VT,UT B-G-1 18 reactor flange ligsments UT between threaded stud holes B-G-1 18 wash 2rs VT B-1-1 100% of closure head cladding VT 4

Pressurizer' B-E Vessel penetrations VT 4

Regenerative B-B 10% of each of 2 longitudinal UT Heat Exchanger welds' B-B 10% of each of 3 circumferential UI welds Page 3 of 20 t- _ _.

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1. Owner Maine Yankee Atomic Power Company, Wiscasset, Maine

2. Plant Maine Yankee Atomic Power Plant, Wiscasset, Maine j

3. Plant Unit #1 4. Owner Certificate of Authorization DPR-36 l l

5. Commercial Service Date 12-29-72

6. National Board Number for Unit Reactor Vessel 20865

- 10. Abstract of Examinations COMPONENT CATEGORY NUMBER OF COMPONENTS EXAMINED EXAMINATION Piping B-J 5 circumferential welds with 12" PT, UT each of intersecting longitudinal welds.30 circumferential butt welds.

B-J 1 branch connection weld PT,UT,RT greater than 6" B-J 1 branch connection weld PT, UT 6" or staller B-J 51 socket welds PT

.B-K-1 Welds of 6 integrally UT welded pipe supports B-K-2 92 piping support VT components B-K-2 72 hydraulic shock suppressors VT B-G-2 Bolting of 2 pipe joints VT Pump Pressure B-G-1 16 studs, 16 nuts in place UT Boundary B-K-2 1 reactor coolant pump support VT

- Valve. Pressure B-G-2 Bolting of 30 valves in place VT Boundary Page 4 of 20

1. Owner Maine Yankee Atomic Power Company, Wiscasset, Maine

2. Plant Maine Yankee Atomic Power Plant, Wiscasset, Maine

3. Plant Unit #1 4. Owner Certificate of Authorization DPR 5. Commercial Service Date 12-29-72

6. National Board Number for Unit Reactor Vessel 20865

10. Abstract of Examinations The following are Safety Class 2 components required to be inspected by Technical Specifications.

COMPONENT CATEGORY NUMBER OF COMPONENTS EXAMINED EXAMINATION Piping C-G 100% of 26 circumferential welds UT C-G 100% of 5 longitudinal welds UT C-C 100% of 12 welded supports NT 1

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1. Owner Maine Yankee Atomic Power Company, Wiscasset, Maine '

e l 2. Plant Maine Yankee Atomic Power Plant, Wisessset, Maine i

t I j 3. Plant Unit #1 4. Owner certificate of Authorization DPR-36

5. Commercial Service Date 12-29-72 l 1

4 j 6. National Board Number for Unit Reactor Vessel 20865 t

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i 10. Abstract of Examinations j Status of Work Required for Current Interval l

] The examinations performed during this outage completes all the inservice '

inspection requirements of the Maine Yankee Technical Specifications i for the second inspection period of the first interval with the exception j of the following items

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} EXAM CATEGORY ITEM i

B-I-1 2 vessel interior clad patches of the reactor vessel. These will be inspected at the end of the interval.

B-D 100% of 1 nozzle weld of the regen-j erative heat exchanger. This will be inspected during the 1979 outage.

1 B-H 100% of 5 support welds of the regenerative heat exchanger. These

{; will be inspected during the 1979 outage.

The remaining 17 to 33 percent of the components in the examination f

i categories inspected during the 1977 outa a e will be included as part of tne 1979 inspection program. This will bring these categories up j to the required 50 percent minimum, 66 percent maximum for the end

of the second period.

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I For Maine Yankee, the current schedule is to complete its second inservice inspection period by the end of 1979; and to complete its first inspection interval by the end of 1982, i

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1. Owner ' Maine Yankee Atomic Power Company, Wiscasset, Maine l 2. Plant ' Maine Yankee Atomic Power Plant, Wiscasset, Maine ,

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!. 3. ' Plant Unit #1 4. Owner Certificate of Authorization DPR-36 j 5. Commercial Service Date 12-29-72

6. National Board Number for Unit Reactor Vessel 20865 j 11. Abstract of Conditions Noted I

i l l WELD / COMPONENT EXAMINATION METHOD INDICATIONS l 1

l 3" RC-17 weld #41 Ultrasonic 360' root indication

50% dac. Reconfirmed 1975

! data.

j 6" decay heat line Ultrasonic Geometric indication up l (SC-2) weld #3A to 50% dac.

f 12" RC 29 weld #29 Penetrant Non-relevant indication d,

l 2" CH 126 elbow between Penetrant Linear indication l l

welds 1548 and 1549 l RV washers Visual Light rust, pitting on OD l

3 and ID of washers j I

RCP base Visual Light rust in 3 locations I Valve bolting Visual Discoloration due to boron buildup Piping supports Visual Missing nuts, insufficient thread engagement i

j 1" CH-48 valve Visual Failed gland flange during RCS leak test f

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1. Owner Maine Yankee Atomic Power Company, Wiscasset, Maine l

2. Plant Maine Yankee Atomic Power Plant, Wiscasset, Maine

3. Plant Unit #1 4. Owner Certificate of Authorization DPR-36 i

5. Commercial Service Date 12-29-72  ;

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6. National Board Number for Unit Reactor Vessel 20865

12. Abstract of Corrective Measures Recommended and Taken WELD / COMPONENT Corrective Measure ]

2" CH 126 elbow Removed linear indication with light grinding and rechecked with penetrant. l Piping supports Replaced missing nuts and tightened nuts ,

l with insufficient thread engagement.

1" CH-48 valve Replaced failed gland flange, l

No action was deemed necessary In the case of the remaining indications.

Those items will be recorded for evaluaticn during' future inspections.

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1.0 INTRODUCTION

This report describes the inservice inspection performed during the 1978 refueling outage at the Maine Yankee Atomic Power Station, Wiscasset, Maine. The non-destructive examination procedures used for inservice inspection were in accordance with the 1974 edition of the ASME Boiler and Pressure Vessel Code,Section XI, " Rules for Inservice f

Inspection of Nuclear Power Plant Components", up to and including the Summer 1975 Addenda; except that piping examinations and acceptance criteria for piping examinations were in accordance with the Summer 1976 Addenda. Additional examinations were as delineated by Plant Technical Specifications. Inspections were conducted to the extent allowed by system design and the non-destructive testing technology employed. This '

report summarizes the areas examined, the type of examinations, test data results, evaluations, and repairs. Manual ultrasonic testing techniques were employed in conjunction with visual, magnetic particle, liquid penetrant, and radiographic examinations.

1.1 Examination Methods ,

All non-destructive examinations were performed in accordance with Yankee Atomic Electric Company procedures found in Engineering Guidelines Book III, " Inservice Inspection NDE Procedures". The examination proce-dures were reviewed and approved by personnel qualified to SNT-TC-1A, Level III; and conform to the requirements of ASME Section XI (S' 75 &

S' 76) and applicabla pes tions of ASME Section V (S' 75). The inservice inspection examinations were performed and evaluated by personnel qualified to the 1975 edition of SNT-TC-1A.

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l The following procedures were utilized for the examinations: '

PROCEDURE NUMBER REVISION TITLE YA-ISI-1 2 ' Inservice Inspection Program Requirements I

YA-VT-1 1 Visual Examination Procedure YA-PE-2 1 Liquid Penetrant Examination I

YA-MP-1 1 Magnetic Particle Examination ,

l YA-RT-1 1 Radiographic Examination I l

YA-UT-1 1 Ultrasonic Examination - General l Requirements l YA-UT-2 1 UT of Vessels - Circumferential, Longitudinal, Meridional, and Flange Welds YA-UT-3 1 UT of Vessels - Flange to Shell Weld from Flange Face j YA-UT-4 1 UT of Vessels - Nozzle to Vessel Welds YA-UT-6 0 UT of Flange Ligaments YA-UT-7 1 UT of Bolting YA-UT-8 0 UT of Reactor Closure Nuts YA-UT-9 0 UT of Piping - Ferritic Welds YA-UT-10 0 UT of Piping - Austenitic Welds YA-UT-13 0 UT of Vessel - Nozzle Inner Radius YA-UT-14 0 UT of Piping - Base Material and Weld Heat Affected Zones YA-UT-15 0 UT of Piping - Straight Beam Method When Used for Weld and Heat Affected Zone Examination The technique sheets used for these examinations are as follows:

I TECHNIQUE SHEET NO. REVISION SUBJECT UT-3, TS-1 0 Maine Yankee Flange Weld Technique MP-1, TS-1 0 Use of Parker Probe on Steam Header Saddle Welds Page 10 of 20

i 1.2 Evaluation of Data

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! The examination results were reviewed by personnel qualified to 1

SNT-TC-1A L als II and III. Indications were evaluated to the I

acceptance standards in the 1974 edition of the ASME Boiler and Pressure Vessel Code Section XI, up to and including the Summer 1975 Addenda, 1

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accordance with the Summer 1976 Addenda.

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i 1.3 Examination Results j Summaries of all examinations that were performed are contained in J

} Section 2.0 of this report. All detailed examination data, calibration i

j records, material and equipment certifications, personnel qualifications, ,

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l l and procedures are maintained at the Plant site as part of the permanent

! Plant records. )

l i Details of reportable indications and corrective measures enn be found in the applicable parts of Section 2.0.

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f 2.0

SUMMARY

OF EXAMINATIONS This section summarizes the inservice inspection examination data for the 1978 refueling outage at the Maine Yankee Atomic Power Station, Wiscasset, Maine. The results are summarized by ASME code categories of Section XI.

2.1 Reactor Vessel B-C Reactor Vessel Flange to Vessel Weld 50 per cent of the flange to vessel weld from Number 1 stud hole to Number 27 stud hole (0* to 180*) was examined ultrasonically. No j recordable indications were found. The examination was accomplished from the flange face.

B-C Reactor Vessel Head Flange to Head Weld 50 per cent of the flange to head weld from Number 1 stud hole to Number 27 stud hole (0* to 180*) was examined ultrasonically. No recordable indications were found. One side scan was possible only due to head configuration.

B-D Reactor Vessel Nozzle to Vessel Welds Including Inner Radii 100 per cent of 3 nozzles were examined ultrasonically. The nozzles include the B inlet (120 ), B outlet (180 ), and C inlet (240 ). No-recordable indications were found.

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l B-E Vessel Penetrations l Vessel penetrations including the CEDM housings, vents, and instrument i

j nozzles were examined visually during the Reactor Coolant System Leak

, Test. There was minor leakage'from 3 CEDM vents. These were tightened i

and the leakage stopped.

J B-G-1 Closure Studs, Closure Nuts 18 closure studs numbers 3, 5, 7, 9, 11,~13, 17, 19, 21, 23, 27, 29,  ;

, i 31, 33, 39, 49, 51, and 53 were examined visually, ultrasonically, and by liquid penetrant. Several studs had minor pitting and generalized  !

corrosien evaluated as insignificant. 18 closure nuts numbers 3, 5, 7, 9, 11, 13, 17, 19, 21, 23, 27, 29, 31, 33, 39, 49, 51, and 53 were examined visually, ultrasonically, and by magnetic particle examination. There P

was minor pitting on two nuts evaluated as insignificant.

B-G-1 -Reactor Vessel Flange Ligaments q l

20 reactor vessel flange ligaments between stud holes numbers 18 through 38 were' examined ultrasonically. No' recordable indications were found.

. B-G-1 Closure Stud Washers 18 closure stud washers numbers 3, 5, 7, 9, 11, 13, 17, 19, 21, 23, 27, 29, 31, 33, 39, 49, 51, and 53 were examined visually. All washers exhibited slight pitting and generalized corrosion evaluated as i l

insignificant.

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B-I-l' Closure Head Cladding f 100 per cent of tt.e closure head cladding was examined visually.

f- Visual inspection was done in lieu of surface examination due to the i high radiation levels encountered. Extensive surface preparation would have been necessary to accomplish the surface examination'resulting in

high exposure to personnel. Boron deposits would highlight any discon- l tinuities (cracks, linear indications, etc.) present in the cladding.

No recordable indications were found.

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2.2 Pressuricer 4

i B-E Vessel Penetrations i

I All vessel penetrations including nozzles, instrument penetrations, 4

and heater penetrations were examined visually during the Reactor Coolant System Leak Test. No leakage was evident.

2.3 Regenerative Heat Exchanger 1

.B-B Longitudinal Vessel Welds 1

1 10 per cent of each of 2 longitudinal vessel welds was examined ultra-l sonically. No recordable indications were found.

4 B-B Circumferential Vessel Welds 10 per cent of each of 3 circumferential vessel welds was examined ultrasonically. No recordable indications were found.

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4 1 2.4 Piping B-J Circumferential Pipe Welds i

5 circumferential pipe welds with 12 inches of each intersecting ,

longitudinal weld were examined ultrasonically and by liquid penetrant. ,

No recordable indications were found. 30 circumferential butt welds were examined ultrasonically or radiographically. Weld number 41 of the-3 inch RC-17 had a 360* rc>t indication recorded at a maximum of 50' percent of DAC. This was reconfirmed data from the 1975 ISI. No other indications were found B-J Branch Connection Welds Greater than 6 Inches 1 branch connection weld greater than 6 inches was examined ultra- l l

sonically and by liquid penetrant. An indication was found on weld I number 29 of the 12 inch RC-29 line by liquid penetrant. This indication was determined to be non-relevant. No other indications i

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were found.

B-J Branch Connection Welds 6 Inches"or Less 1 branch connection weld 6 inches or less in size was examined by liquid penetrant. No indications were found.

B-J Socket Welds 51 socket welds were examined by liquid penetrant. The elbow between welds 1548 and 1549 had a 1/2 inch linear indication on the inner radius. This indication was removed by light grinding and rechecked by liquid penetrant. The second inspection was found satisfactory. The wall thickness of the elbow was checked ultrasonically and found to be Page 15 of 20

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! B-K-1 Integrally Welded Supports l

i 6 integrally welded pipe supports were examined ultrasonically. No I recordable indications were found.

a i B-K-2 Piping Support Components i

l 92 piping supports were examined visually. These included 27 pipe 1

j spring hangers. A total of 16 discrepancies were noted; however, only

2 of these were evaluated as being significant. Support numbers CH-73-1, SIH-135, SIH-RH-500, and SIH-A-119 had missing bolts. Support numbers

! CH-73-1, STH-135, SIH-RH-501, and SDHV-4 had nuts with less than full t

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! thread engagement er loose nuts. These were evaluated as resalting from i

construction errors and were corrected. A memo to J. Lance from NDT i

g- engineering personnel dated 8-11-78 gives further details. A memo to J. T.ance from P. R. Willoughby dated 9-5-78 gives details of evaluations, i

[ B-K-2 Hydraulic Shock Suppressors i

j 72 hydraulic shock suppressors were examined visually as part of plant

{ surveillance requirements. This includes all safety class shock i

{ suppressors. No discrepancies other than minor weepage were noted. All l

j shock suppressors were operable. Additionally, 8 shock suppressors were

functionally tested and found to be satisfactory.

! B-G-2 Pipe Bolting 2 bolted pipe connections were examined visually. No recordable

indications were found.

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1 2.5 Pump Pressure Boundary i

B-G-1 Pump Studs and Nuts, In Place 16-reactor coolant pump studs and nuts were examined in place ultrasonically.

No recordable indications were found. The studs and nuts were on the number 2 reactor coolant pump.

B-K-2 Pump Support The number 2 reactor coolant pump support was examined visually. Minor rust was found in 3 locations. This was determined to be insignificant.

2.6 Valve Pressure Boundary B-G-2 Valve Bolting Bolting of 30 valves was examined visually. On several valves the bolting was discolored or corroded slightly by boron deposits and was ev,..luated as being insignificant.

2.7 Safety Class 2 Piping (Valve House)

The following items were inspected as part of Technical Specifi-cation requirements. These will be incorporated in the expanded program in subsequent inservice inspections.

C-G Piping Circumferential Welds 100 per cent of 26 circumferential welds were examined ultrasonically.

Wald number 3A of the 6 inch decay heat line was found to have a geometric indication recorded at a maximum of 50 percent of DAC. No other indications were found.

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). C-G Piping Longitudinal Welds i- 1 j 100 per cent of 5 longitudinal welds were examined ultrasonically. No  ;

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i recordable indications were found.

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! l 100 per cent of 12 welded supports were examined using magnetic particle l 1

examination. No recordable indications were found.

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3.0 REACTOR COOLANT SYSTEM LEAK TEST l

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i A leak test of the reactor coolant system was given at nominal system

operating pressure as per Plant Technical Specifications. Numerous a

leakages were detected at packing glands of valves. The gland flange a

of CH-48, a 1-inch isolation valve, failed and had to be replaced. All l A

l 1eakages were corrected prior to the final system leak test. No leakages 1 1

1 (other than normal controlled leakages) were detected during the final )

l l system leak test. I 1

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4.0 CONCLUSION

S The examinations performed during thir inspection outage completes the inservice inspection requirements for the second-inspection period of the first. interval except as noted in the Abstract of Examination above.

Final closeout of che second inspection period'will be accomplished by the end of 1979.

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