ML20235C634
| ML20235C634 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/18/1987 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20235C542 | List: |
| References | |
| NUDOCS 8709240514 | |
| Download: ML20235C634 (27) | |
Text
j
,j V .
)
l l
I l
l l
INSERVICE INSPECTION l EXAMINATION REPORT YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION l 1
DECEMBER 11, 1985 THROUGH JUL.Y 3, 1987 I l
8709240514 870918 PDR ADOCK 05000029 k PDR
TABLE OF CONTENTS pace
- 1. Introduction 1
- 2. Evaluation'of Data 2
- 3. NIS-1 Owners Data Reports 3 4., Repairs and Modifications 21
- 5. Conclusions 22
-i-l l
1 i
L__ --_ - - _ \
1.0 INTRODUCTION
This report covers the Inservice Inspections of Yankee -
Nuclear Power Station from December 11, 1985 to July 3, 1987.
The inspections performed during this time frame constitute completion of the examinations required by ASME Section XI and the Yankee Inservice Inspection Program for the first period of the third interval.
The examination methods employed were Ultrasonics (UT),
Radiography (RT), Liquid Penetrant (LP), Eddy Current (ET),
Visual Inspection (VT), and Magnetic Particle (MP).
l e
i
-1
- c. '
j j
2.0^ EVALUATION OF DATA )4 i
All inservice examinations were performed, evaluated, and j reviewed by personnel certified to Level II in accordance !
with SNT-TC-1A, 1975/1980 Edition and ASME Section XI, 1977 l Edition, Summer 1978 Addenda. I l,
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, execpt for Class 1 piping ultrasonic calibration. Class 1 piping calibration was conducted in accordance with Article 111-2000 of Appendix III, ASME Section XI, Summer 1976 Addenda, as required per Plant Technical Specifications.
1 The detailed examination data along'with the calibration records, procedures, personnel, and equipment certifications are maintained at the plant site.
1 l
l' w _________ ________________
FOllM NIS-1 OWNEllS' DATA ItEPOltT FOlt INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules Yankee Atomic Electric Co., 1671 Worcester Road, Framinghaa, MA 01701
- 1. Owner (Name and Address of Owner)
Yankee Nuclear Pe>wer Station, Rowe, MA 01367
- 2. Ph _
(Name and Address of Plant)
- 3. Plant Unit Yankee _Rowe _,,_4. Owner Certificate of Authorization (if required)_ __DRE-3_
7/1/61 6. National Board Number for Unit Reactor #NB-23964
- 5. Commercial Service Date .
- 7. Components inspected l
Manufacturer i Connponent or Manufacturer or installer State or National Appurtenance or Installer Serial No. Province No. Board No.
I Reactor Vessel Babcock Wilcox ft10-001 N/A 7146A l ~
Steam Generator Westinghouse N/A N/A AnAr(?T 1 Piping Stone & Webster N/A N/A N/A Pressurizer Babcock _Wilcox 610-0011 N/A ?9324E2?
a Note: Supplernental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8% in. x 11 in.,
(2) information in items 1 through 6 on this data report is iricluded on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
This fot m (t00029) rray be obtained from the Order Dept., AS.ME, 345 E. 4 7th St., New Yor k, N.Y. 10017
FORM NIS-1 (back)
- 8. Examination Dates 12/11/85 to 7/3/87 9. Inspection Interval from 10/1/84 to 10/1/94
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. See pages 5-12
- 11. Abstract of Conditions Noted See Pages 13-16
- 12. Abstract of Corrective Measures Recommended and Taken See pages 17-22 ,
We certify that the staten,ents made in this report are correct and the examinations and corrective mea-sures taken conform to the rules of the ASME Code, Se ion XI.
Date f"' [ 19 N_ Signed , h WM ayy Yankee Atomic Elec.
Owner Certificate of Authorization No. (if applicable) DPR-3 Expiration Date 11b4[97 US NRC Facility License No.
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid cnmmission issued by the National Board of Boiler and Pressure Vessel NY, PA, Oli and employed by liSBI & I Co. or Inspectors and/or the State or Province of Connecticut have inspected the components described in this Owners' Data Report during the period
_ lob LL 85 to_~7 3 %7 . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described 'm 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.
Date 9* lfo 19 ?>7
_A ,
__. 7/%$4 M Inspector's Signature
_ Commissions PJ)4.3O&fA W G 3131pah National Board, State, Province and No.
1 l
4 0
-~_
Owners YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701 Plants YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of Plant Unit YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date 7/1/61 Number for Unit REACTOR #NB-23964
- 10. ABSTRACT OF EXAMINATIONS l
ASME CODE CODE EXAM J CATEGORY ITEM NO. COMPONENTS EXAMINED METHOD I l
B-B B2.11 SO% of the Pressurizer Bottom UT )
Head to Shell Circumferential i Weld
- (PRBH-C)
B-B B2.12 12" of the Pressurizer UT Intersecting Longitudinal Weld to Bottom Head
- (PRBH-L-A)
B-B B2.60 100% of the Feed / Bleed Heat LP Exchanger Tubesheet to Bottom Head Weld
- (FBB-1-1)
B-D B3.110 (2) Pressurizer Nozzle to Vessel UT Welds
- (PRZN-7/PRZN-11)
B-D B3.120 (2) Pressurizer Nozzle Inner UT Radius Examinations
- (PR-IR-7/PR-IR-11)
B-F B5.30 (2) Steam Generator Dissimilar UT Metal Welds
- (MC-1-6/MC-1-9)
I
)
I l
l L-___-____-__
t Owner: YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701 Plants YANKEE NUCLEAR POWER STATION, ROWE,. MASSACHUSETTS 01367 Owner Certificate of Plant Units YANKEE ROWE Authorization.(if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Un5ts REACTOR hNB-23964 i
- 10. ABSTRACT OF EXAMINATI_ONS ASME CODE CODE EXAM CATEGORY ITEM NO. COMPONENTS EXAMINED METHOD
\
B-G-1 86.30 (104) Reactor Vessel Studs UT/MT/VT
- (L-43/B-1! Sets)
B-G-2 B7.30 (40) Studs / Nuts #2 Steam MP/VT Generator Primary Manway B-G-2 B7.30 (40) Studs / Nuts #3 Steam VT Generator Primary Manway i
B-G-2 B7.30 (40) Studs / Nuts #4 Steam VT Generator Primary Manway B-G-2 B7.60 #3 Main Coolant Stator Cap Bolts VT/MT B-G-2 B7.70 Bolting (15) Valves VT
- (MC-MOV-325 MC-MOV-302, MC-V-308, MC-MOV-316, SC-MOV-552, SC-MOV-553, SC-MOV-554, CH-V-614, CH-MOV-525, CH-MOV-524, CS-MOV-536, PR-SV-181, PR-SV-182, PR-SOV-90, PR-MOV-512)
B-J 89.11 (3) Circumferential Pipe Welds >4" UT/LP
- (MCB-1-6, 51-1-10, S1-1-22)
B-J 89.21 (1) Circumferential Pipe Welds (4" LP
- ( SI -l-3 )
I ; ,
oOwner: . YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD,.
l -, FRAMINGHAM~ MA , 01701 E ' . Plant: YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 l N Owner Certificate of Plant Unit: YANKEE ROWE Authorization (if rOguired): DPR-3
' Commercial National Board '
Service Date: 7/1/61 Number for Unit: PEAR, TOR #NB-23964 4
- 10. ABSTRACT OF EXAMINATIONS ASME CODE CODE EXAM C AT EGOR_Y_ ITEM NO. C O M_P_ O N E N T S E X A M I N_E D_ METHOD B-J 89.31 .( 2) Branch Pipe Connection Welds UT/LP
, - (PRS-1ER-1, PRS-1BR-1A)
B-J 89.40 (9) Socket Welds LP !
'- (PRS-206-11,- CH-56, CH-14-1, CH-2, BL-1-1,4, DRC-3-5, c !
DRH-1-1, DRis-3-1, DRH-4-1) l B-K-1 810.20 (2) Integrally Welded Pump LP Supports !
- (CRM-H-19, CRM-H-20)
B-K-2 B11.10 (20) Piping Supports VT-3/4 y., - (CRB-H-30, CRB-R-1, CRCH-H-2, i t'y' CRCH-R-11, DR-H-10, DR-H-7, l DRH-H-1, H-2, H-3, PRCH-SNB-OO4B, l PRSH-RH-20, PRSH-RH-21, PRSH-RH-7, !
PRSH-SNB-OO4, PRSH-SNB-OO2, j PRSH-CNB-010, CRM-H-25, CRM-H-24, ;
MCB1-H-1, MCB1-H-2)
)
' B-M-2 B12.40 (4) Valve Body Internal Surfaces VT-1
- (MC-MOV-325, MC-MOV-302, MC-V-308, CH-MOV-524) 8
(- B-N-1 B13.10 Vessel Interior / Shroud Tube VT-3 8-P Main Coolant System Leakage Test VT-2 o 1 A
N k.___.,.__._.._____.____ _ _ . . . . _ .
n.
. Owners YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701 Plant: YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 Jb Owner. Certificate of
' Plant Unit YANKEE ROWE Authorization (if required)t DPR-3 Commercial National Board Service Date 7/1/61 Number for Unit: 'REACTO8,#ND-23964
- 10. ABSTRACT OF EXAMINATIONS i- I ASME CODE CODE EXAM CATEGORY ITEM NO.: COMPONENTS _ EXAMINED METHOD B-P ' Main Coolant Drain Sy' stem VT-2 Hydrostatic Test B-O B16.20 (1504) Tubes, #2 Steam Generator ET I
l
(
(-
_g_
l
\
Owners YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701 Plant YANKEE NUCLEAR POWER S~lATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of Plant Units YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for. Unit: REACTOR #NB-23964
- 10. ABSTRACT OF EXAMINATIONS I
ASME CODE CODE EXAM I CATEGORY ITEM NO. COMPONENTS EXAMINED METHOD ]
)
C-A C1.10 50% #4 Steam Generator Transition UT j Weld l
- (SG-4-4)
C-A C1.20 50% Safety Injection Accumulator UT/MT l Shell to Bottom Head Weld
- (SI-ACC-1)
C-A C1.20 33-1/3% #3 Steam Generator Shell UT to Head Weld '
- (SG-3-6)
C-A C1.30 33-1/3% #3 Steam Generator Tube UT Sheet to Shell Weld
- (SG-3-2)
C-B C2.20 (2) Nozzles, #4 Steam Generator UT/MT/VT
- (SG-4-SO, 94-1D)
CC-CE C3.20 (2) Steam Generator Supports VT-3
- (SG-1-SS, SG-4-SN)
CC-CE C3.30 (1) Steam Generator Mechanical VT-3/4 Support
- (SG-3-SN-446) l
_9_
l
[
l Owner: . YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701-Plant: YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 I
Owner Certificate of l Plan t Unit: YANKEE ROWE Authorization (if required): DPR-3 I o
Commercial National Board Service Date: 7/1/61 Number for Unit: REACTOR #NB-23964 l
l
- 10. 'ADSTRACT OF EXAMINATIONS ASME CODE CODE EXAM l CA1EGORY ITEM IJO, COMPONENTS EXAMINED METHOD CC-CE C3.50 (22) Piping Component Supports VT-3/4 (A-1, BRL-H-40, BRL-H-51, !
CRT-H-68 H-27 H-28, H-9, PRCL-RH-1, PRCL-S-56, PRSL-H-3, PRSL-H-42, SHP-R-3, WCBD-RH-116, WCBD-H-123-3, WCBD-RH-OO1, WCBD-RH-OO3, WCBD-RH-OO8, WCBD-RH-OO9, WCBD-RH-010. WCBD-RH-121-2, ,
H-33, WCBD-H-7) l C-F C5.11 (4) Circumferential Piping MT Welds - Feedwater
- (94-6D, FW-2-15, FW-3-21, FW-4-11)
.C-F C5.11 (22) Circumferential Piping LP ;
Welds - Shutdown Cooling '
- (PRS-2-11 PRS-2-13 SDC-1-6 SDC-1-8, SDC-1-10, SDC-4-19 SDC-1-15, SDC-1-16, SDC-1-17, SDC-1-25, SDC-1-27 SDC-1-31, SDC-1-32, SDC-1-33, SDC-4-3 SDC-L-18, SDC-L-19, SDC-4-20.
SDC-4-21)
Owner: YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701 Plant: YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of Plant Unit: YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit: REACTOR #NB-23964
- 10. ABSTRACT OF EXAMINATIONS ASME CODE CODE EXAM CATEGORY ITEM NO. COMPONENTS EXAMINED METHOD C-F C5.11 (13) Circumferential Piping LP Welds - Safety Injection
- (SI-12A, SI-14A,51-005, 51-037, SI-043, SI-049, SI-052,51-055, SI-082, SI-084A, SI-085,51-09B, SI-10A)
C-F C5.21 (13) Circumferential Piping UT/MT/VT Welds - Main Steam
- (MS-1-1, MS-1-2, MS-2-1, MS-2-2, MS-3-1, MS-3-2, MS-4-1, MS-4-2, MS-3-21, MS-2-6, MS-2-7, MS-2-11, MS-2-12)
C-H (10) Class 2 System Hydrostatic VT-2 Tests
- VC Heating Steam
- Charging Pump Discharge
- Charging Pump Suction
- Pressurizer Heise Gauge Line
- High Pressure Safety Injection Discharge
- Low Pressure Safety Injection Discharge
- Low Pressure Safety Injection Suction
- Main Coolant Drain
- iiain Coolant Vent
- Purification Pump Suction l
l 1
r . - - - _ . - - - - _ _ _ _ _ - . _ - . _ _ _ _
Uwner YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701 I Plant YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of Plant Units YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board
) Service Date 7/1/61 Number for Units REACTOR #NB-23964
- 10. AUSTRACT OF EXAMINATIONS ASME CODE CODE EXAM CATEGORY ITEM NO. COMPONENTS EXAMINED METHOD C-H (3) Class 2 System Functional VT-2 Tests
- Chemical Shutdown
- Hot Leg Injection
- High Pressure Safety Injection Discharge D-A (5) Class 3 System Hydrostatic VT-2 Tests
- Component Cooling Pump Discharge
- Component Cooling Surge Tank
- Primary Pump Seal Water to Purification Pumps
- Primary Pump Seal Water to Shutdown Cooling / Low Pressure Surge Tank Pumps D-A (5) Class 3 System Leakage Tests VT-2
- Motor Driven Emergency Boiler Feed Pump Suction / Discharge Piping
- Primary Pump Seal Water
- Steam Driven Emergency Feedwater
- Feedwater Crossconnect Piping
- Steam Piping to Emergency Feedwater Pump D-C (1) System Leakage Test VT-2
- Spent Fuel Pit Cooling .
I l
l l
____ _ _ _- --_ i
Owner: YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701 Plants YANKEE NUCLEAR POWER ETATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of Plant Unit: YANKEE ROWE Authorization (if required): DPR-3 I
l Commercial National Board l Service Date: 7/1/61 Number for Unit: REACTOR #NB-23964 1
{
l 11. ABSTRACT OF CONDITIONS NOTED I
l ASME CODE CODE CATEGORY ITEM NO. COMPONENTS EXAMINED l
l l B-G-1 B6.30 Visual examination of (104) Reactor Vessel Closure studs (stud sets L-43/B-
- 16) revealed two studs from set L-43 with I minor thread damage. (50T & 4T)
{
l B-G-2 B7.30 Visual examination of (120) Steam l
l Generator Primary Manway studs / nuts revealed (4) studs on #3 Steam Generator with minor thread damage.
l B-G-2 B7.70 Visual examination of Pressurizer Code Safety Valve PR-SV-181/182 stud / nuts
(
revealed (1) stud with minor thread l damage and (34) nuts with linear indications.
I 1
l B-G-2 B7.60 Visual examination of the #3 Main Coolant Pump Stator Cap bolts revealed minor plating damage on (16) bolts.
l l
i Il-J B9.11 Liquid penetrant examination of Safety Injection System pipe weld SI-1-22 I
revealed a linear indication in the base metal.
l B-K-2 B11.10 Visual examination of Main Coolant Drain Line hanger DR-H-10 revealed several loose nuts.
l l
l l
l l
Owners YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, j FRAMINGHAM, MA 01701 )
Plant YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of Plant Unit: YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit REACTOR #NB-23964
- 11. ABSTRACT OF CONDITIONS NOTED ASME CODE CODE CATEDORY ITEM NO. COMPONENTS EXAMINED B-K-2 B11.10 Visual examination of Safety Inj ec tion Snubber PRSH-SNB-OO4 revealed a minor gouge on the snubber sleeve.
B-Q B16.20 Eddy current examination of the #2 Steam Generator Tubes revealed (26) tubes with wall losses of 35-40%.
l l
I L-- _ -
1 1
I Uwner: YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM. MA- 01701 l 1
j Plant: YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 j i
Owner Certificate of ;
Plant Unit: YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit: REACTOR HNB-23964
- 11. ABSTRACT OF CONDITIONS NOTED ASME CODE CODE CATEGORY ITEM-NO. COMPONENTS EXAMINED C-A C1.10 Ultrasonic examination of it4 Steam Generator Shell Weld (SG-4-4) revealed several recordable indications.
C-A C1.20 Ultrasonic examination of Safety Injection Accumulator Bottom Head Weld (SI-ACC-1) revealed several recordable indications.
C-B C2.20 Ultrasonic examination of the #4 Steam Generator Steam Outlet Nozzle SG-4-SO revealed several recordable indications.
CC-CE C3.50 Visual examination of Safety Injection Pipe Hanger PRSL-H-3 revealed several loose nuts and misalignment of the hanger.
CC-CE C3.50 Visual examination of Feedwater Pipe Hanger WCDD-RH-10 revealed a loose lock nut.
C-F C5.11 Liquid penetrant examination of Shutdown Cooling Pipe Weld SDC-4-20 revealed a linear indication in the base metal.
Y_-__________________-________
1 l
l I
l YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, Owner:
FRAMINGHAM, MA 01701 l Plants YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 I
l Owner Certificate of j l'Iant Unit YANKEE ROWE Authorization (if required): DPR-3 1
Commercial National Eoard Service Date 7/1/61 Number for Unit: REACTOR HNB-23964 l
l l 11. ABSTRACT OF CONDITIONS NOTED 1
l ASME CODE CODE j CATEGORY ITEM NO._ COMPONENTS EXAMINED l
C-F C5.21 Ultrasonic examination of Main Steam Line Welds MS-1-2, MS-2-2, MS-2-7, and MS l 12 revealed neveral recordable indications.
C-F C5.21 Magnetic particle examination of Main Steam Line weld MS-3-2 revealed an unacceptable linear indication.
l l C-H During the hydrostatic test of the Main Coolant Vent System a valve body to bonnet flange leak was identified.
C-H During the hydrostatic test of the Main Coolant Drain Header a valve body to l
bonnet flange leak was id?ntified.
l l
l 1
l l
l l
l l
l l
l Owner: YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701 Plant: YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of Plant Unit: YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit: REACTOR #NB-23964 l 12. AUSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN l
l ASME CODE CODE l CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN B-G-1 B6.30 The minor thread damage noted on Reactor l Vessel Closure Studs 4T and 50T of stud i
set L-43 was subsequently evaluated and l determined to be acceptable as is. The I studs were returned to service.
l l B-G-2 B7.30 The minor thread damage (galling) on (3)
Steam Generator Primary Manway studs was l
repaired by light filing. The studs were re-inspected satisfactory and returned to service. The Primary Manway studs / nuts I on Steam Generator #2 and #4 were l inspected with no unacceptable conditions l noted.
l l B-G-2 B7.70 (14) nuts on Pressurizer Code Safety l Valve PR-SV-181 with linear indications l
were subsequently replaced in kind.
l l As required by lWB-2430, an additional I examination was selected. The inlet and l
outlet studs / nuts of Pressurizer Safety l Valve PR-SV-182 were su bj ec ted to a visual examination. This examination resulted in an additional (20) nuts and (1) stud with unacceptable conditions.
( The minor thread galling noted on the I stud was subsequently repaired by light filing. The (20) nuts were replaced in l kind.
l I
1 As required by IWB-2430, the remaining l
i similar components were examined (PR-MOV-l 512/PR-SOV-90). No unacceptable conditions were noted.
e Owners' YANKEE' ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD,.
FRAMINGHAM, MA 01701
, Plants YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of
! Plant Unit YANKEE ROWE Authorization (if required): DPR-3 L Commercial National Board Service Date: 7/1/61 Number for Unit REACTOR #NB-23964
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN ASME CODE CODE CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN B-G-2 B7.60 (5) of the (16) stator cap bolts on #3.
Main Coolant Pump with plating damage were replaced in kind. The remaining (11) stator cap boltc were determined to be acceptable for further service.
The stator cap bolting on the other,three Main Coolant Pumps were-inspected with no degradation noted.
B-J 89.11- The indication on Safety Injection System pipe weld 51-1-22 was subsequently determined to be a nonrelevant indication. Surface conditioning was performed on the area in question and the weld was re-examined with no unacceptable condition noted.
B-K-2 B11.10 The loose nuts identified on Main Coolant Drain Line hanger DR-H-10 were subsequently tightened. In accordance with IWB-2430 an additional hanger was selected for examination (DR-H-7). The examination identified no unacceptable conditions.
B-K-2 B11.10 The minor gouge on Safety Injection Snubber PRSH-SNB-OO4 was determined to be nonservice induced (mishandling). A functional test of the snubber was performed which proved the gouge was not detrimental to the operation of the snubber.
1 Visual examinations were conducted on all !
the remaining safety class snubbers. No l unacceptable condition was noted.
l l
. \
l Owners YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701 1 Plant: YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of Plant Units YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board Service Date: 7/1/61 Number for Unit REACTOR #NB-23964
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN ASME CODE CODE CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN B-O B16.20 The (26) tubes in Steam Generator #2 exhibiting 35-40% wall loss were plugged by mechanical means. In addition, a review of past eddy. current data resulted in plugging 18 tubes in #3 Steam Generator and 16 tubes in #4 Steam Generator. A complete report of the 1987 i eddy current examination activitien will be filed in accordance with Plant Technical Specifications.
i l
j I
l 1
)
i s '. -
l.
l l Owners YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, l
l-FRAMINGHAM, MA 01701 l
l Plant: YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 l
l l Owner Certificate of l Plant Unit: YANKEE ROWE Authorization (if required): DPR-3 l
l Commercial National Board l Service Date: 7/1/61 Number for Unit REACTOR #NB-23964 1
l 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN
! ASME CODE CODE l CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN i
C-A C1.10 The ultrasonic indications recorded on #4 l Steam Generator Shell Weld (SG-4-4) were l subsequently evaluated in accordance with J IWB-3514.5 and determined to be geometric reflectors. The results of this examination were compared to the 1985 inspection which revealed no change had occurred.
C-A C1.20 The ultrasonic indications recorded on Safety Injection Accumulator Weld (SI-ACC-1) were subsequently evaluated in accordance with IWB-3514.5 and determined to be geometric reflectors due to metallurgical conditions.
C-B C2.20 The ultrasonic reflector noted on #4 Steam Generator Outlet Nozzle (SG 4-60) were subsequently evaluated as fabrication related and acceptable for continued service. The nozzle will be re-examined during the next refueling outage to verify no change has occurred.
CC-CE C3.50 The Safety Injection Pipe Hanger (PRSL-H-
- 3) identified as misaligned with loose parts was subsequently corrected. In accordance with IWC-2430 an additional hanger was selected for examination (H-33). The examination did not reveal any unacceptable conditions.
Owners YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA 01701 Plant: YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of Plant. Unit: YANKEE ROWE Authorization (if required): DPR-3 )
l Comtaercial National Board I Service Date: 7/1/61 Number for Unit: REACTOR #NB-23964
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN ASME CODE CODE CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN l
CC-CE C3.50 The Main Feed Line Wanger (WCBD-RH-10) identified as having loose lock nuts was subsequently corrected. In accordance with IWC-2430 an additional hanger was j selected for examination (WCBD-RH-7). i This examination did not identify any unacceptable conditions.
.C-F C5.11 The linear indications identified in the base metal of Shutdown Cooling System Pipe Weld SDC-4-20 was subsequently removed by buffing. As required by IWC-2430 an additional area was examined.
The examination resulted in no unacceptable conditions.
C-F C5.21 The ultrasonic reflectors identified in Main Steam Line Welds MS-1-2, MS-2-7 and
) MS-2-12 were recorded for future reference. Since all reflectors were less than 100% of reference level, no further action was required.
In accordance with IWB 3514.5 the ultrasonic reflector in Main Steam Line Weld MS-2-2 was subsequently determined to be a geometric reflector.
r' O Owner YANKEE ATOMIC ELECTRIC COMPANY, 1671 WORCESTER ROAD, FRAMINGHAM, MA' 01701 Plants YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS 01367 Owner Certificate of Plant Unit YANKEE ROWE Authorization (if required): DPR-3 Commercial National Board i Service Date: 7/1/61 Number for Unit REACTOR #NB-23964
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN
'ASME CODE CODE CATEGORY ITEM NO. CORRECTIVE MEASURES TAKEN C-F C5.21 The linear indication identified on Main Steam Line Weld MS-3-2 was subsequently removed by light buffing. As required by.
IWC-2430 an additional weld was subjected
.to examination (MS-4-2). This examination did not idertify any unacceptable conditions.
C-H The valve body to bonnet flange leak on the Main Coolant Vent System was subsequently corrected by torquing the flange bolts. The re-examination did not reveal any further leakage.
C-H The valve body to bonnet flange leak on the Main Coolant Drain Header was I subsequently corrected by torquing the '
flange bolts. The re-examination did not i reveal any further leakage.
i l
{ l f
I l
r 4
REPAIRS AND REPLACEMENTS The following Section XI Repairs / Replacements were performed during the time frame of December 11, 1985 to July 3, 1987:
Maintenance Request 87-37 " Repair of #1 Charging Pump Block" Maintenance Request 87-431 " Replacement of Pressurizer Safety Valve PR-SV-182 Flange Nuts" Maintenance Request 87-801 " Replacement of Main Steam Trap Line" Maintenance Request 87-880 " Replacement of Pressurizer Safety Valve PR-SV-181 Flange Nuts" Maintenance Request 86-516 "#3 Main Coolant Pump Stator Cap Bolt Replacement" Maintenance Request 86-564 "#3 Charging Pump Block Repair" Maintenance Request 86-897 " Repair of #3 Steam Generator Blowdown Line Pinhole Leak" Maintenance Request 86-1648 " Replacement of Main Steam Line Traps" Maintenance Request 86-1675 " Replacement of #2 Steam Generator Blowdown Line Manual Isolation Valve" Engineering Design Change 86-307 " Replacement of Safety Injection Relief Valves" Engineering Design Change 86-315 " Post Accident Sample Line From High Pressure Safety Injection Discharge" l
1
)
i
- ._ _ ___.__.____._____________J
4 e P
8.0 CONCLUSION
S The examinations completed and identified within this report ~
constitute completion of those examinations required by the Yankee Nuclear Power Station Technical Specifications for the first period of the third interval.
l i
% .i~
)
b.:,
I
e ,
l l
l l
1
)
i
)
I i
1 1
l O l j
i l
ot <t a
c~
M.E.
07 Q-D E {
4 i
I
. _