ML20141N765
| ML20141N765 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/06/1986 |
| From: | Fetherson N YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20141N763 | List: |
| References | |
| NUDOCS 8603180081 | |
| Download: ML20141N765 (27) | |
Text
V 1,
INSERVICE INSPECTION EXAMINATION REPORT YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION OCTOBER. 19, 1985 THROUGH DECEMBER 11, 1985 i
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86031800s1 860307
$DR ADOCK 05000029 PDR M47 f
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TABLF OF CONTENTS Pagg 1.
PREFACE'...............................................
11 2.
NIS-1 OWNERS DATA REPORT..............................
1 3.
INTRODUCTION..........................................
10 4.
NONDESTRUCTIVE EXAMINATION PROCEDURES.................
11 5.
EVALUATION OF DATA....................................
12 6.
SUMMARY
REPORT........................................
13 7.
REPAIRS AND MODIFICATIONS.............................
23 8.
CONCLUSIONS...........................................
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7-1 1.0 PREFACE b
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.This sunnary report covers the inservice inspection of Yankee Nuclear Power l
' Station during the period of October 19,.1985 through December 11, 1985.
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Included in this report is the NIS-1 form as required by.the provision of ASME Section XI.
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FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECllONS As required by the Provisions of the ASME Code Rules
- 1. Owne, Yankee Atomic Electric Co.,1671 Worcester Rd., Fram_ingham,lta. 01701 (Name and Address of owner)
Yankee Nuclear Power Station, Rowe, Massachusetts 01367
- 2. Plant (Name and Address of Plant)
Yankee Rowe
- 4. owner Certiricate of Authorisation (if required)
Dl3-)
- 3. Plant Unit
- 5. Commercial Service Date _7[1/61
- 6. National Board Number for Unit Reactor #NB-2R64____
- 7. Cor.iponents inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Insta:!ct serial No.
Province No.
Board No.
Reactor vossn1 R,henet-wilcny 610-001 N/A 23 % 1 Steam Generator Westinghouse N/A N/A 404E(2) 1 Piping Stone 6 Webster N/A N/A N/A Pressurizer Babcock Wilcox 610-0011 N/A 23974E22 Note: Supplemental sheets in form of lists. sl caches, or drawings may be used provided (15 sisc is 8% in. x 11 in.,
(2) information in items I through 6 on this data report is included on cach sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
This form (E00029) rmy be obtained from the order Dept., ASME, 345 E. 4 7th St., New York, N.Y.
10017 Page 1 of 24 L.
I FORM NIS 1 (back)
- 8. Examination Dates 10/11/85 12/11/85,, ir.spsnion intersal from._10f__1/84 to _10/_1/14
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- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.
Page 3 of 24
- 11. Abstract of Conditions Noted Page 7 Of 24
- 12. Abstract of Corrective Measures Recommended and Taken Page 8 of 24 We certify that the statements made in this report are correct and the examinatic.ha and corrective mes-sures taken conform to the rules of the ASME Code,Section XI.
Date 2/7 19 86 SignedA///f N4 By lillikee Atomic Elec Owner DPR-3 Ex 11/4/97 Certificate of Authorisation No. (if applicable)US NRC Facility License No. piration Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of.hL PA, OH and employed by H9BT F. T Co_
of ConnecticuL have inspected the components described in this Owners' Data Report during the period 12 /11/AR and state that to the best of my knowledge and belief, the Owner 10/19/R5 to has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners
- Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
!/8 19 8de_
Date 4
k Commissions WAf[LO, AWMs PA *Ht" S/3/y $CMu 0
[nspector's Signature National Board, State. Province and No.
Page 2 of 24
YANKEE ATOMIC ELECTRIC COMPANY NIS-1 NNER DATA REPORT
- 10. Abstract of Examinations (Safety Class 1)
ASME Code Category No.
Components Examined Method B-B (1) Feed / Bleed Heat Exchanger Weld LP (1) Pressurizer Circumferential Weld UT B-D (2) Pressurizer Nozzle Welds UT B-E (1) Feed / Bleed Heat Exchanger Nozzle VT B-F (3) F,essurizer Safe End Welds RT,LP (2) Steam Generator Safe End Welds UT,LP B-G-1 (2) Reactor Vessel Flange Bushings VT B-G-2 (40) Steam Generator Primary Manway Studs VT
- 12) Pressurizer Heater Bolts VT Safety Valve 181 Studs VT Stator Cap Bolts VT Main Coolant Stop Valve Studs VT
- 20) Main Coolant Check Valve Studs VT
- 24) Main Coolant Bypass Valve Studs VT
- 16) Shutdown Cooling Valve Studs VT
- 8) Pressurizer Solenoid Valve Studs VT B-H (1) Pressurizer Integrally Welded Support MT B-J (4
Main Coolant System Welds UT,RT,LP (1
Main Coolant Bypass Weld UT,LP (1
Main Coolant Branch Connection Weld UT,LP (3
Pressurizer Piping Welds LP (2
Charging System Welds LP (1) Shutdown Cooling System Weld UT,LP Bleed System Welds LP Safety Injection System Welds UT,LP Main Coolant Urain System Welds LP B-K-1 (2) Main Coolant Pump Integrally Welded Supports LP B-K-2 (5) Main Coolant Pump Supports VT (3) Pressure Control and Relief Pipe Supports VT
- 2) Charging and Volume Control System Supports VT
- 1) Bleed System Support VT
- 2) Shutdown Cooling System Supports VT
YANKEE ATOMIC ELECTRIC COMPANY NIS-1 OWNER DATA REPORT
- 10. Abstract of Examinations (Safety Class 1) (continued)
ASME.
Code Category No.
Components Examined Method B-M-2 (1) Main Coolant Check Valve (Internals)
VT B-P (1) Main Coolant System Leakage Test VT l.
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7 YANKEE ATOMIC ELECTRIC COMPANY NIS-1 OWNER DATA REPORT
- 10. Abstract of Examinations (Safety Class 2)
ASME Code Category No.
Components Examined Method C-A (1) Steam Generator Transition Wcid UT C-B (1) Steam Generator Feedwater Nozzle UT,MT CC-CE (1) Steam Generator Integrally Welded Support LP (4) Steam Generator Supports VT (4) Feedwater System Supports VT (1) Main Steam System Suppcrt VT (12) Shutdown Cooling / Low Pressure Surge Tank Cooling Supports VT C-F (1) Pressure / Control Relief System Weld LP (6) Feedwater System Welds VT,MT,RT (1) Vapor Container Heating System Weld MT (5) Main Steam System Welds MT,UT,VT (10) Safety Injection System Welds LP (9) Shutdown Cooling System Welds LP C-H (8) Safety Class 2 System Hydrostatic Tests VT Page 5 of 24 L _
i YANKEE ATOMIC ELECTRIC COMPANY NIS-1 OWNER DATA REPORT
- 10. Abstract of Examinations (Safety Class 3)
ASME Code Category No.
Components Examined Method D-A (32) Service Water System Supports VT (55) Component Cooling System Supports-VT D-B (6) Safety Class 3 System Hydrostatic Tests VT-Page 6 of 24
YANKEE ATOMIC ELECTRIC COMPANY NIS-1 OWNER DATA REPORT
- 11. Abstract of Conditions Noted l
B-H Magnetic particle examination of (1) pressurizer integrally l
welded support revealed an unacceptable rounded indication.
B-J Liquid penetrant examination of main coolant weld MC-1-4 revealed several unacceptable linear indications.
Ultrasonic examination of main coolant bypass weld MCB-1-2 resulted in a recordable indication.
Liquid penetrant examination of safety injection weld SI-1-2 revealed (1) unacceptable linear indication.
Liquid penetrant examination of main coolant drain line weld DRC-2-1A revealed (1) unacceptable linear indication.
B-K-2 Visual examination of pressurizer piping supports H-1 and H-3 revealed an unacceptable condition (loose hanger assembly)
Visual examination of main coolant drain line support DRH-1 revealed an unacceptable condition (loose hanger components).
CC-CE Visual examination of shutdown cooling supports BRL-H-51 and PRCL-H-3 revealed an unacceptable condition (loose and missing hanger components).
0-A Visual examination of (32) service water supports identified an unacceptable condition on two supports WSL-H-12 and WS-H-10.
Visual examination of (55) component cooling supporti identified an unacceptable condition on (13) supportt.
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YANKEE ATDMIC ELECTRIC COMPANY NIS-1 OWNER DATA REPORT
- 12. Abstract of Corrective Measures Recommended and Taken B-H The magnetic particle indication identified on pressurizer support PRS-H-3A was subsequently removed and repair welded in accordance with plant procedures. Re-examination of this area following repair resulted in no unacceptable conditions.
B-J The liquid penetrant indications on main coolant weld MC-1-4 were subsequently removed by light buffing and re-examined satisfactory.
The ultrasonic indication recorded on MCB-1-2 was subsequently evaluated in accordance with IWB 3514.5 and determined to be a geometric reflector.
The ultrasonic indication recorded on SI-1-19 was subsequently evaluated in accordance with IWB-3514.5 and determined to be a geometric reflector.
The linear indication on safety injection weld SI-1-2 was reconditioned, re-examined, and determined to be a nonrelevant indication.
The liquid penetrant indication on main coolant drain line weld DRC-2-1A was subsequently removed by light buffing and re-examined satisfactory.
B-K-2 The two pressurizer piping supports M-1 and H-3 that were identified as being unacceptable were subsequently corrected and re-examined _ satisfactory.
The unacceptable condition on main coolant drain line support DRH-1 was subsequently corrected and re-examined satisfactory.
C-A The ultrasonic indications recorded on steam generator transition weld SG-4-4 were subsequently evaluated in accordance with IWB-3514.5 and determined to be geometric reflectors due to metallurgical conditions present at weld fabrication.
CC-CE The unacceptable conditions identified on shutdown cooling / low pressure surge tank system supports BRL-H-51 and PRCL-H-3 were subsequently corrected and re-examined satisfactory.
D-A The unacceptable conditions identified on service water supports WSL-H-12 and WS-H-10 were subsequently corrected and re-examined satisfactory.
Page 8 of 24
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-YANKEE ATOMIC ELECTRIC COMPANY p
NI5-1 OWNER DATA REPORT
- 12. Abstract of Corrective Measures Recommended and Taken (continued) 0-A The (13) unacceptable conditions identified on the component cooling system supports were subsequently corrected and re-examined satisfactory.
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3.0 INTRODUCTION
This report covers the inservice inspections of Yankee Nuclear power Station from October 19, 1985 to December 11, 1985. The examinations performed are those of the first period of the tnird interval.
On October 1st, 1984, Yankee' initiated the beginning of the first period of the third ten year inspection interval. As can be seen from the attached report,' Yankee has once again demonstrated the responsible philosophy under which it was originally constructed. With the exception of several minor discontinuities which were subsequently corrected, the various plant systems and components continue to meet the standards of Section XI after over 25 years of operation.
Page 10 of 24
4.0 NONDESTRUCTIVE EXAMINATION PROCEDURES Nondestructive examinations were performed in accordance with the procedure contained in the Yankee Atomic Electric Company Engineering Guidelines Book III, " Inservice Inspection NDE Procedures."
The examination procedures were reviewed and approved by personnel certified to Level III per SNT-TC-1A 1975 Edition, and the Authorized Nuclear Inservice Inspector.
These procedures conform to.the requirements of the ASME Code,Section XI,
" Rules for Inservice Inspection of Nuclear Power Plant Components," 1977 Edition, Summary 1978 Addenda.
The following procedures were used during the 1985 inservice inspections:
l 1.
YA-PE-2 Rev. 5
" Liquid Penetrant Examination" l
2.
YA-MP-111 Rev. O
" Procedure for Magneu e Particle Examination" 3.
YA-RT-111 Rev. 1
" Radiographic Examination" 4.
YA-VT-11 Rev. 1
" Visual Examination Procedure" 5.
YA-UT-1 Rev. 3
" Ultrasonic Examination - General Requirements" l
6.
YA-UT-9 Rev. 2
" Ultrasonic Examination of Piping-Ferritic Welds" 7.
YA-UT-10 Rev. 5
" Ultrasonic Examination of Piping-Austenttic Welds" 8.
YA-UT-11 Rev. 2
" Ultrasonic Examination of Piping-Dissimilar l
Metal Welds" 9.
YA-UT-13 Rev. 1
" Ultrasonic Examination of Vesse: s Nozzle Inner Radius" l
- 10. YA-UT-22 Rev. O
" Ultrasonic Examination of Vessels Circumferential, Longitudinal, Merridional &
- 11. YA-UT-44 Rev. O
" Ultrasonic Examination of Vessel Nozzle to Nozzle Welds" 1
- 12. OP-4200 Rev. 11
" Main Coolant System Leak Inspection"
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- 13. OP-2120 Rev. 6
" System Component, Isolation and Pressure Leak Test" l
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i 5.0 EVALUATION OF DATA All inservice examinations were performed, evaluated, and reviewed by personnel certified to Level II in accordance with SNT-TC-1A, 1975/1980 Edition and ASME Section XI, 1977 Edition, Summer 1978 Addenda.
The examination methods, volumes, and evaluation of indications were in accordance with ASME Boiler and Pressure Vessel Code,Section XI, 1977 Edition, Summer 1978 Addenda, except for Class 1 piping ultrasonic calibration. This was conducted in accordance with Article III-2000 of Appendix III, ASME Section XI, Summer 1976 Addenda, as required per Plant Technical Specifications.
Summaries of the examinations that were performed are contained in Section 4.0 of this report. The detailed examination data along with the calibration records, procedures, personnel, and equipment certifications are maintained at the plant site.
Attached is a summary of the examination methods, volumes, and the results and evaluation of test data thereof, including any corrective measures taken.
Page 12 of 24
6.0
SUMMARY
REPORT The following is a summary of all the examinations performed, the conditions noted, and corrective measures taken during the 1985 inservice inspections.
CODE CATEGORY B-P PRESSURE RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS Ultrasonic examination was performed on pressurizer circumferential weld no. PRMH-C with no recordable indications observed.
Feed / bleed heat exchanger body to top head weld no. FBB-1-3 was subjected to a liquid penetrant examination.
No recordable indication were observed.
CODE CATEGORY B-D FULL PENETRATION WELDS OF N0ZZLES IN VESSELS Ultrasonic examination was performed on (2) pressurizer nozzle welds, PRZN-1 and PRZN-4. These nozzles were also subjected to a nozzle inner radius examination. No recordable indication were observed.
CODE CATEGORY B-E PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS No.1 Feed / bleed heat exchanger nozzle FBN-1-1 was visually examined during the main coolant system leakage inspection (plant procedure OP-4200) with no leakage observed.
CODE CATEGORY B-F PRESSURE RETAINING DISSIMILAR METAL WELOS Pressurizer safe end welds PR-SE-1 and PR-SE-2 were subjected to a liquid penetrant examination. No unacceptable indication was observed.
Pressurizer safe end weld PR-SE-9 was subjected to a liquid penetrant and radiographic examination. No unacceptable indications were observed.
Main coolant pipe to steam generator safe end welds MC-1-9 and MC-1-6 were subjected to a liquid penetrant examination with no unacceptable indication observed.
In addition, ultrasonic examination was performed from the steam generator side with no recordable indications observed.
CODE CATEGORY B-G-1 PRESSURE RETAINING BOLTING LARGER THAN 2" IN DIAMETER (2) reactor vessel flange bushings (stud hole #36 and 49) were visually inspected in place, with no unacceptable indications observed.
Page 13 of 24
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CODE CATEGORY B-G-2 PRESSURE RETAINING BOLTING 2" AND SMALLER The following Class 1 bolt / studs were visually examined and determined to be satisfactory:
No Component (40)
Steam Generator #1 Primary Manway Studs Removed (12)
Pressurizer Heater Bolts (PR-HP-1)
In Place (16)
Pressurizer Safety Valve 181 Studs Removed (16)
- 1 Main Coolant Pump Stator Cap Bolts In Place (20)
Main Coolant Gate Valve MC-MOV-325 Studs In Place (20)
Main Coolant Gate Valve MC-MOV-326 Studs In Place (20)
Main Coolant Gate Valve MC-MOV-319 Studs In Place (20)
- 1 Main Coolant Check Valve MC-V-239 Studs In Place (12)
Main Coolant Bypass Valve MC-MOV-501 Studs In Place (12)
Main Coolant Bypass Valve MC-MOV-504 Studs In Place (16)
Shutdown Cooling Valve SC-M0V-551 Studs In Place (8)
Pressurizer Solenoid Valve PR-SOV-90 Studs Removed CODE CATEGORY B-H VESSEL SUPPORTS Pressurizer integrally welded support PRS-H-3A was subjected to a magnetic particle examination which resulted in (1) unacceptable nonservice induced indication. This indication was subsequently repaired and re-examined satisfactory.
CODE CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING Weld No.
MC-1-4 Main coolant pipe weld subjected to a liquid penetrant and ultrasonic examination. The liquid penetrant examination resulted in several unacceptable linear indications which were subsequently removed by light buffing. The liquid penetrant re-examination resulted in no unacceptable indications.
In accordance with IWB-2430 an additional weld was examined (MC-4-10) which identified no unacceptable indications.
MC-1-7 Main coolant pipe weld subjected to a liquid penetrant and ultrasonic examination. No unacceptable indications observed.
MC-1-5 Main coolant pipe weld subjected to a liquid penetrant, ultrasonic and radiographic examination. No unacceptable indications observed.
MC-1-14 Main coolant pipe weld subjected to a liquid penetrant, ultrasonic and radiographic examination. No unacceptable indications observed.
MCB-1-2 Main coolant bypass pipe weld subjected to a liquid penetrant and l
l ultrasonic examination. The ultrasonic examination resulted in a l
l recordable indication, which was subsequently evaluated as a geometric reflector in accordance with IWB-3514.5.
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CODE CATEGORY B-J (continued)
Weld No.
MCB-1BR-1 Main coolant branch connection pipe weld subjected to a liquid penetrant and ultrasonic examination. No unacceptable indications observed.
PRS-206-3 Pressurizer piping welds subjected to liquid penetrant PRS-206-6 examination. No unacceptable indications observed.
PRS-206-9 CH-8 Charging pipe welds subjected to a liquid penetrant examination.
CH-7 No unacceptable indication observed.
SDC-BR-1 -Shutdown cooling branch connection weld. Subjected to a liquid penetrant and ultrasonic examination. The liquid penetrant examination resulted in an indication which was subsequently determined acceptable by ultrasonic inspection.
BL-1-02 Bleed system welds subjected to liquid penetrant examination with BL-1-1 no unacceptable indications observed.
BL-1-2 BL-1-01 BL-1-3 SI-1-12 Safety injection system pipe welds subjected to liquid penetrant SI-1-21 and ultrasonic examination.
No unacceptable indications observed.
SI-1-19 Safety injection system pipe weld subjected to liquid penetrant and ultrasonic examinations.
The ultrasonic examination resulted in a recordable indication which was subsequently evaluated as a geometric reflector in accordance with IWB-3514.5.
SI-1-2 Safety injection system pipe weld subjected to a liquid penetrant examination. This examination revealed (1) nonservice induced indication which was subsequently removed by light buffing.
Liquid penetrant re-examination identified no unacceptable indications.
DRC-2-1A Main coolant drain line pipe weld subjected to a liquid penetrant examination. This examination revealed (1) unacceptable linear indication which was subsequently removed by light buffing and re-examined satisfactory.
In accordance with IWB-2430 an additional weld was examined (DRC-4-1A) which identified no unacceptable indications.
DRC-3-2 Main coolant drain line pipe welds subjected to a liquid DRC-3-3 penetrant examination. No unacceptable inriications were observed.
Page 15 of 24
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CODE CATEGORY B-K-1 SUPPORT MEMBERS PIPING, PUMPS, VALVES Main coolant pump integrally welded supports CRM-H-6 and CRM-H-7 were subjected to a liquid penetrant examination.
No unacceptable conditior;s were observed.
CODE CATEGORY B-K-2 COMPONENT SUPPORTS FOR PIPING, PUMPS AND VALVES Support No.
System Examinations / Conditions / Corrective Action CRM-H-5 Main Coolant Subjected to a VT-3/VT-4 visual examination.
CRM-H-6 Pump Supports No unacceptable conditions observed.
CRM-H-7 CRM-H-19 CRM-H-20 CRG-H-30 Pressurizer Subjected to a VT-3/VT-4 visual examination.
Piping No unacceptable conditions observed.
H-1 Pressurizer Subjected to VT-3 visual examinations. Both H-3 Piping examinations revealed nonservice induced discontinuities (loose hanger assembly) which were subsequently repaired and re-examined satisfactorily.
CRCH-H-2 Charging Subjected to a VT-3 visual baseline CRCH-S-1 System examination following modification. No unacceptable conditions observed.
CRBH-R-1 Bleed System Subjected to a VT-3 visual baseline CRBH-R-4 examination. No unacceptable conditions CRBH-RH-6 observed.
DRH-H-5 Main Coolant Subjected to a VT-3 visual baseline DRH-H-7 Drain System examination. No unacceptable conditions noted.
DRH-4 Main Coolant Subjected to a VT-3 visual examination. No DRH-7 Drain unacceptable conditions observed.
DRH-1 Main Coolant Subjected to a VT-3 visual examination which Drain revealed a nonservice induced discontinuity.
Condition was subsequently repaired and re-examined satisfactory.
i CH-P-1 Chargir.g Subjected to a VT-3 visual examination. No System unacceptable conditions observed.
BL-H-1 Bleed System Subjected to a VT-3 visual examination. No I
unacceptable condition observed.
j PRCH-RH-2 Shutdown Subjected to a VT-3 visual examination. No Cooling unacceptable conditions observed.
Page 16 of 24 1
y-COCE CATEGORY B-K-2 COMPONENT SUPPORTS FOR PIPING, PUMPS AND VALVES (continued)
Support No.
System Examinations / Conditions / Corrective Action PRCH-SNB-1B Shutdown Subjected to a VT-3/VT-4 functional test. Ifo Cooling unacceptable conditions observed.
Snubber PRSH-SNB-3 Safety Subjected to a VT-3/VT-4 functional test. No PRSH-SNB-9 Injection unacceptable condition observed.
Snubbers PRSH-RH-19 Safety Subjected to a VT-3 visual examination. No PRSH-RH-24 Injection unacceptable condition observed.
PRSH-RH-25 CODE CATEGORY B-M-2 PUMP CASINGS AND VALVE BODIES A VT-3 visual examination was conducted on the internals of main coolant check valve MC-V-239. No unacceptable conditions were observed.
CODE CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS The main coolant system was subjected to a system leakage test prior to start-up. No serious leakage or degradation was observed during the VT-2 visual examination.
SUMMARY
REPORT - SAFETY CLASS 2 COMPONENTS CODE CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS Ultrasonic examination was conducted on 50% of #4 steam generator transition weld (SG-4-4). This examination resulted in several recordable indications which were subsequently evaluated as geometric reflectors in accordance with IWB-3514.5.
CODE CATEGORY C-B PRESSURE RETAINING N0ZZLE WELDS IN VESSELS
- 3 steam generator feedwater nozzle weld (SG-3-FN) was subjected to a magnetic particle and ultrasonic examination.
No recordable indications were observed.
CODE CATEGORY CC-CE COMPONENT SUPPORTS Support No.
System
. Examinations / Conditions / Corrective Action SG-3-N
- 3 Steam Integrally welded support subjected to a Generator liquid penetrant examination. No unacceptable conditions observed.
Page 17 of 24 t
CODE CATEGORY CC-CE COMPONENTSUPPORTS(continued)
Support No.
System Examinations / Conditions / Corrective Action SG-4-SN-447
- 4 Steam
- 4 steam generator snubber, removed and Generator subjected to a VT-3/VT-4 functional visual examination.
No unacceptable conditions observed.
SG-1-SN
- 1 Steam Subjected to a VT-3 visual examination. No SG-1-SE Generator unacceptable conditions observed.
SG-1-SW WCBD-RH-115 Feedwater Subjected to a VT-3 visual examination. No WCBD-RH-118-2 unacceptable condition observed.
WCBD-RH-119-3 WCBD-RH-120-4 SHP-H-82 Main Steam Subjected to a VT-3/VT-4 visual examination.
No unacceptable condition observed.
BRL-H-51 Low Pressure Subjected to a VT-3 visual examination. This Surge Tank examination revealed a nonservice induced Cooling discontinuity, which was subsequently repaired and re-examined satisfactory.
PRSL-H-42 Shutdown Subjected to VT-3/VT-4 visual examination.
PRCL-H-42 Cooling No unacceptable condition observed.
PRCL-H-41 PRCL-H-44 PRCL-H-52 PRCL-H-53 PRCL-H-57 PRC L-H-61 CRT-H-59 CRT-H-65 PRCL-H-3 Shutdown Subjected to a VT-3/VT-4 visual examination.
Cooling TFe VT-3 examination revealed a nonservice induced discontinuity which was subsequently repaired and re-examined satisfactory.
CODE CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING Weld No.
System Examinations / Conditions / Corrective Action PRS-2-10 Pressurizer Subjected to a liquid penetrant examination.
Piping No unacceptable conditions observed.94-12C Feedwater Subjected to a magnetic particle examination.
FW-1-27 No unacceptable conditions observed.
Page 18 of 24
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t CODE CATEGORY C-F PRESSURE RETAINING WELOS IN PIPING (continued) i Weld No.
System Examinations / Conditions / Corrective Action 94-1A Feedwater Subjected to visual, magnetic particle, and 94-1B radiographic examinations. No unacceptable 94-1C conditions observed.
94-10 j
VCH-1 Vapor Subjected to a magnetic particle examination.
Container No unacceptable conditions observed.
t Heating i
MS-1-25 Main Steam Subjected to a magnetic particle and ultrasonic examination. No unacceptable conditions observed.
MS-2-6 Main Steam Subjected to a visual magnetic particle and MS-2-7 ultrasonic examination. One indication was MS-2-11 recorded on MS-2-7 which was subsequently MS-2-12 evaluated as a geometric reflector in accordance with IWB-3514.5.
NRV-405a Main Steam /
Subjected to a visual, magnetic particle and NRV-405b Non-Nuclear ultrasonic examination. Only one indication NRV-405c Safety was observed on NRV-405b. This indication NRV-405d has been previously identified and evaluated as a nonservice induced discontinuity (LAP) and accepted as is. No change was observed i
since the last examination.
SI-4 Safety Subjected to liquid penetrant examinstion.
SI-7 Injection No unacceptable conditions observed.
SI-10 SI-13 SI-16 SI-22 SI-7A SI-28 SI-9A SI-147 Safety Subjected to a liquid penetrant and Injection ultrasonic examination. No unacceptable condition observed.
SOC-1-19 Shutdown Subjected to liquid penetrant examinations.
SOC-1-20 Cooling Several indications were observed on 50C-1-24 SDC-1-29 which were subsequently buffed 50C-1-26 down, and re-examined satisfactory. An
$0C-1-28 additional examination was performed in SDC-1-29 accordance with IWC-2430 (SDC-4-5) which SDC-1-30 identified no unacceptable conditions.
SDC-4-4 i
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i CODE CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS Portions of the following systams were subjected to system hydrostatic tests:
1.
Purification syster 2.
Service water system 4..
Safety injection system 3.
Vapor container heating steam system 5.
Main steam system 6.
Low pressure surge tank cooling system 7.
Component cooling system 8.
Charging system No system degradation or unacceptable leakage was observed.
SUMMARY
REPORT - SAFETY CLASS 3 COMPONENTS CODE CATEGORY 0-A The Class 3 supports on the service water and component cooling systems were inspected with results as follows:
Support No.
System Examinations / Conditions / Corrective Action WS-A-1 Service Water Subjected to a VT-3 visual examination. No WS-A-2 unacceptable conditions observed.
WS-A-3 WSL-H-15 WSL-H-1 WS-H-24 WSL-H-2 WS-II-58 WSL-H-3 WS-H-59 WS L-H-4 WS-H-67 V"L-H-5 WS-H-68 WSL-H-6 WS-H-70 WSL-H-7 WS-H-71 WSL-H-8 WS-H-72 WS L-H-9 WS-H-73 WSL-H-10 WSL-S-2 WSL-H-11 WSL-S-31 WSL-H-13 WSL-16A WSL-H-14 WSL-16B WSL-H-12 Service Water Suojected to a VT-3 visual examination.
WS-10 This examination revealed an unacceptable condition (loose nuts) which was subsequently corrected and re-examined satisfactory.
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CODE CATEGORY 0-A~(continued)
Support No.
System Examinations / Conditions / Corrective Action K-S-73 Component Subjected to a VT-3 visual examination.
No K-S-74 Cooling unacceptable conditions observed.
K-H-79 K-H-80 K-S-53 K-S-69 K-S-54 K-S-70 K-S-55 K-H-70 K-S-50 K-H-72 K-H-51 K-S-64 K-H-53 K-H-76 K-H-66 K-H-74 K-S-61 K-S-66 K-H-57 K-S-60 K-R-1 K-S-59 K-H-58 K-H-65 K-H-59 K-S-52 K-H-60 K-S-58 K-H-62 K-H-87 K-H-68 K-H-85 K-H-77 K-S-57 K-S-12 K-S-65 K-S-13 K-H-55' K-H-54 K-H-81 Component A VT-3 visual examination identified a K-H-73 Cooling a combination of loose nuts bolts and hanger K-H-86 assembly. These conditions were subsequently K-H-61 corrected and reinspected satisfactory.
X-H-63 K-H-64 K-H-84 K-S-51 K-H-56 K-H-50 K-H-52 K-H-78 K-S-56 Component VT-3 visual examination identified cracked Cooling grout on the baseplate. This condition was subsequently corrected and re-examined sati sf actory.
K-H-82 Component VT-3 visual examination revealed that the Cooling support did not conform to the engineering drawing. The support was subsequently modified and re-examined satisfactory.
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CODE CATEGORY D-A/D-B/O-C PRESSURE RETAINING COMPONENTS Portions of the following systems were subjected to system hydrostatic testing:
1.
Primary water storage tank 2.
Demineralized water storage tank 3.
Service water system 4.
Primary pump seal water system 5.
Chemical shutdown system 6.
Component cooling system No system degradation or unacceptable leakage was identified, f
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7.0 REPAIR AND MODIFICATIONS The following Section XI repair / replacement modifications were performed during the 1985 refueling outage:
PDCR 84-008
" Totalizer Meter Replacement" PDCR 85-009
" Type "C" Testing Modifications" PDCR 85-002
" Containment Isolation Valve Modification:
EDCR 83-31
" Reactor Head Thermocouple Modification" EDCR 84-319 "Small Bore Piping Supports" Maintenance Request 85-234 Replacement of AS-V-760 Maintenance Request 85-234 Replacement of AS-V-719 i
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h, 8.0 ' CONCLUSIONS.
The examinations completed and identified within this report constitute approximately one half of those examinations required by the Yankee Nuclear
. Power Station Technical Specifications for the first period of the third interval.
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