ML20237B050
| ML20237B050 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 09/18/1987 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML20237B047 | List: |
| References | |
| NUDOCS 8712150436 | |
| Download: ML20237B050 (22) | |
Text
.
I INSERVICE INSPECTION
SUMMARY
REPORT FOR i
MAINE YANKEE ATOMIC POWER COMPANY AUGUSTA, MAINE 1
GENERATING PLANT: Maine Yankee Atomic Power Plant Wiscasset, Maine UNIT DESIGNATION NUMBER: Reactor Vessel 20865 COMMERCIAL OFERATING DATE: 12/29/72 EXAMINATION DATES FROM 11/17/85 to 9/18/87 IN THE Second TEN YEAR INTERVAL.
I COMPLETION DATE: 9/18/87 f
8712150436 871201 9 DR ADOCK 0500
l CONTENTS Preface 1 NIS-1 Data Report 2 NIS-2 Data Report 13 i
?
e PREFACE This report summarizes the preservice and inservice inspections and pressure tests that were performed at Maine Yankee Atomic Power Plant l between November 17, 1985 and Septc.nber 18, 1987 that fail within the i scope of Section XI of the ASME Boiler and Pressure Vessel Code and the .
Maine Yankee Inservice Inspection Program. The end of the second inspection period of the second ten year inspection interval is August 29, 1989. The Authorized Nuclear Inservice Inspector on-site to witness the inspections was Mr. Allan P. Schiaffino of Hartford Steam Goiler Inspection and Insurance Company.
l Page 1 of 20 2124P
As required by the Provisions of the ASME Code Rules rane 2 of 20
- 1. Owner ? hine Yankee Atomic Iher Comrnny, Aunusta. finine (Name and Address of Owner)
- 2. Plant Ih ne Yankee Atorric IDCr Plant, Wiscasset, l'aine ;
(Name and Address of Plant)
- 3. Plant Unit 1 4. Owner Certificar. of Authorization (if required) DPR-36
~
- 5. Commercial Service Date 12/29/72 6. National Board Number for Unit Ecactor Vessel 20R65
- 7. Components Inspected Manufacturer I Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No. ,
Peactor Vessel C.E. 67106 tm 20965 -
I Peactor llead C.E. 67206 tm 20065 l
l Pressurizer C.E. 67601 NA 20858 )
l l
, St. Gen. #1 C.E. 67501 NA 20919 l
- 1 St. Gen. =2 c.E. 67509 un 9nr19n St. Gen. #3 C.E. 67503 NA ? O') ? 1 1
1 BCP #2 Bryon-Jackson 681-N-0422 KA MA 3 RCP #3 Bryon ,7ackson 681-N-0423 NA FA Picinn Stone & Webster KA MA NA 1
l 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 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
This form (E00029) rnay be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
- 43. .
FORM NIS-1 (back) -
- 8. Examination Dates 11/17/85 to 9/18/87 9. Inspection Interval from 12 /29 /R 2 to 1?/?4/49
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required I for current interval. See Pages 3 thru 8
- 11. Abstract of Conditions Noted See Pages 9 diru 11
- 12. Abstract of Corrective Measures Recommended and Taken See Pages 9 thru 11 We certify that the statements made in this report are correct and the examin ions and corrective men-sures taken conform to he rules of the ASME Code,Section XI.
Date /h 19 4 7 Signed h e Yadeo "y B ; b .w[ /F
/
Owner //[
Certificate of Authorization No. (if applicable) N/A Expiration Date N/A CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid enmmission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of Now Vnrk and employed by H . S . B . I &I Co , of Hartford.Ct have inspected the components described in this Owners' Data Report during the period 11/17/95 to 9/19/87 . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective rncasures 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.
Date November 19 19 87 M Commissions NB 10011 IN Inspector's Signature National Board, State, Province and No.
1
_ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . N%
1986-1987 INSERVICE INSPECTIONS
- 3. PLANT UNIT: 1 4. OWNER CERTIFICATE OF AUTHORIZATION: DPR-36
- 5. COMMERCIAL SERVICE DATE: 12/29/72
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS:
CATEGORY ITEM NUMBER EXAMINED METHOD B-B B2.10 Pressurizer, Longitudinal shell UT (B2.12) Weld - 2 welds, 9" each B2.30 (B2.32) Steam Generator #3, Meridional UT Head Weld B2.40 Steam Generatcc #1, Tubesheet to UT Head Weld B-D B3.110 Pressurizer, Nozzle to Vessel UT Weld 3 Nozzles B3.120 Pressurizer, Nozzle Inside UT Radius Section - 3 Nozzles B3.130 Steam Generator #1, Nozzle to UT Vessel Welds - 2 Welds B3.140 Steam Generator #1, Nozzle UT Inside Radius Section -
2 Nozzles B-E B4.12 Reactor Vessel Control Rod VT-2 Drive Nozzles - All Accessible Nozzles i
B4.13 Reactor Vessel Instrumentation VT-2 l Nozzles - All Accessible Nozzles i B-F B5.20 One Pressurizer Nozzle to Safe PT End Dissimilar Metal Weld j B5.50 One 33 1/2" Dissimilar Metal Pipe Weld UT*
B5.50 Four 33 1/2" Dissimilar Metal Pipe Welds UT*,PT
- From Carbon Steel Only Page 3 of 20 2124P
1986-1987 i INSERVICE INSPECTIONS
- 3. PLANT UNIT: 1 4. OWNER CERTIFICATE OF AUTHORIZATION: DPR-36
- 5. COMMERCIAL SERVICE DATE: 12/29/72 l
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS (Cont'd):
CATEGORY ITEM NUMBER EXAMINED METHOD l B-G-1 86.30 Reactor Vessel Closure Head Studs UT,MT 27 Studs B6.180 Reactor Coolant Pump #2 Closure UT.MT, Case Studs - 16 Studs VT I
B6.190 Reactor Coolant Pump #2 Flange VT-1 Surface B6.200 Reactor Coolant Pump #2 Nuts - VT-1 I i
16 Nuts B-G-2 B7.10 Reactor Vessel Instrumentation VT-1 Nozzle Flange Bolting -
2 Nozzles in place B7.20 Pressurizer Manway Bolting in VT-1 Place i B7.30 Steam Generator #2 Primary Manway MT,VT Bolting While Removed - 2 Manways Steam Generator #1 Primary Manway VT-1 Bolting While in Place - 2 Manways B7.50 One Piping Flange Bolting VT-1 B7.70 Body to Bonnet Bolting, 10 Valves in place VT-1 B-H B3.20 Pressurizer Support Skirt Held MT 88.30 Steam Generator #3 Support Skirt MT Held Page 4 of 20 2124P j
1986-1987 INSERVICE INSPECTIONS
- 3. PLANT UNIT: 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: DPR-36 l
- 5. COMMERCIAL SERVICE DATE: 12/29/72
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS (Cont'd):
CATEGORY ITEM NUMBER EXAMINED METHOD B-J 89.10 Two 33 1/2" Circumferential PT Pipe Helds !
One 33 1/2" Circumferential UT Pipe Helds i
Four 33 1/2" Circumferential UT,HT Pipe Helds Two 14" Circumferential UT,PT Pipe Helds ,
1 l
Three 10" Circumferential UT,PT ;
Pipe Helds i One 8" Circumferential RT,PT '
Pipe Held One 8" Circumferential RT Pipe Held 1 l
One 4" Circumferential UT,PT i Pipe Held l 89.20 Six 3" Circumferential PT j Pipe Helds B9.40 Twelve 2" Socket Helds PT B-K-1 B10.0 Two Pipe Integral Attachment Helds PT B-M-1 B12.10 Reactor Coolant Pump #3 Casing Held- PT 36" of Held B12.20 Reactor Coolant Pump #2 Casing Internal Accessible Areas VT-3 Page 5 of 20 1
1986-1987 INSERVICE INSPECTIONS <
- 3. PLANT UNIT: 1 4. OWNER CERT 1FICATE OF AUTHORIZATION: DPR-36
- 5. COMMERCIAL SERVICE DATE: 12/29/72
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865_
- 10. ABSTRACT OF EXAMINATIONS (Cont'd):
CATEGORY ITEM NUMBER EXAMINED METHOD B-N-1 813.10 Interior of Reactor Vessel VT-3 Accessible Areas B-P B15.00 Reactor Coolant System Leak Test VT-2 B-Q B16.20 Steam Generator Tubing ET
-515 Tubes in Generator #2 as required by Maine Yankee Tech. Spec. 4.10 l
-502 Tubes in Generator #2 For information only. '
F-A,B,&C F-1,2,3,&4 Safety Class 1 Supports
-25 Supports VT-3
-13 Supports VT-3&4 i
-10 Additional Exams as required by !
IWF-2430. See page 10 for details. VT-3 & 4 l i
I l
l Page 6 of 20 ,
2124P j l
l l
l 1986-1987 INSERVICE INSPECTIONS
- 3. PLANT UNIT: 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: DPR-36 1
- 5. COMMERCIAL SERVICE DATE: 12/29/72
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865 1
- 10. ABSTRACT OF EXAMINATIONS (Cont'd): 1 l
CATEGORY ITEM NUMBER EXAMINED METHOD l l
C-A C1.10 Two Steam Generator #3 UT,MT j Circumferential Vessel Welds l 1
C-B C2.21 Steam Generator #3 Main Steam UT,MT Nozzle to Vessel Weld l
C2.22 Steam Generator #3 Main Steam UT,MT Nozzle Inside Radius Section C-C C3.10 Two Steam Generator #3 Integral MT Attachment Welds (Partial)
C-F** C2.0** One 30" Circumferential Pipe Weld MT Four 14" Circumferential Pipe Welds PT j Eleven 10" Circumferential Pipe Helds PT Two 10" Circumferential Pipe Welds PT,UT Three 12" Circumferential Pipe Welds PT Two 6" Circumferential Pipe Welds PT ,
C-G** C2.0** One 18" Circumferential Pipe Helds PT Two 16" Circumferential Pipe Helds PT Three 14" Circumferential Pipe Helds UT,MT One 14" Circumferential Pipe Held PT i
One 14" Circumferential Pipe Weld PT,RT Page 7 of 20 2124P
1 1986-1987 INSERVICE INSPECTIONS
- 3. PLANT UNIT: __ 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: DPR-36
- 5. COMMERCIAL SERVICE DATE: 12/29/72
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS (Cont'd):
CATEGORY ITEM NUMBER EXAMINED METHOD l C-G** C-2.0** Two 10" Circumferential Pipe Helds PT Two 8" Circumferential Pipe Helds PT Two 6" Circumferential Pipe Helds PT
- Category and Item Conform to 74/S '75 Code
)
C-H C-7.00 Hydrostatic Pressure Tests VT-2
- a. Volume Control Tank
- b. Charging Pumps Discharge Lines
- c. Blowdown
- d. Seal Water (2) Hydros
- e. Refueling Water Storage Tank
- f. Letdown
- g. Secondary High Pressure Drain
- h. Primary Component Cooling (2) Hydros
- 1. Secondary Component Cooling (2) Hydros
- j. Emergency Feedwater
- k. Main Steam
- 1. Containment Spray F-A,B,&C F-1,2,3,&4 Safety Class 2 Supports
-21 Supports VT-3
-13 Supports VT-3,4
-35 Additional Exams as required by IHF 2430 '/T-3,4
-21 Additional Exams MT See page 11 for details.
Page 8 of 20 2124P
- - _ _ - _ _ _ _ _ - . - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ i
1986-1987 INSERVICE INSPECTIONS
- 3. PLANT UNIT: 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: DPR-36
- 5. COMMERCIAL SERVICE DATE: 12/29/72
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865
- 11. ABSTRACT OF CONDITIONS NOTED:
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN CORRECTIVE CATEGORY CONDITION MEASURE B-Q Steam Generator #2 Tubing ROH LINE %THD LOCATION 40 51 Severe @ 7th Horizontal Support Plugged Tube .
Dent l Degraded 13 96 34 1.3" Above Cold Tube Sheet Additional Tubes 17 96 20 1.6" Above Cold Tube Sheet exams not 24 139 29 1.0" Above 3rd Cold Hor. required for Support less than 40%
36 97 32 1.5" Above Hot Tube Sheet Through Hall 46 55 23 8.1" Above Cold Tube Sheet Degradation (THD) 48 55 29 7.4" Above Cold Tube Sheet 52 95 32 7.6" Above Cold Tube Sheet 54 51 29 8.3" Above Cold Tube Sheet 59 56 31 7.8" Above Cold Tube Sheet 100 77 28 14.8" Above 1st Hot Side Verticle Support Imperfect 5 136 10 @ Verticle Center Support Tubes 6 103 12 @ Verticle Center Support 15 96 18 1.5" Above Cold Tube Sheet 35 132 11 18.7" Above Hot Tube Sheet 36 97 6 1.0" Above Hot Tube Sheet 44 95 8 8.0" Above Cold Tube Sheet 51 94 15 8.0" Above Cold Tube Sheet 55 80 16 6.5" Above Cold Tube Sheet 57 52 18 1.3" Above Hot Tube Sheet 80 117 13 5.0" Above Hot Tube Sheet Information Inspections Steam Generator #2 ROH LINE %THD LOCATION 58 55 67 8.1" Above Cold fube Sheet Plugged tube 47 54 23 8.1" Above Cold Tube Sheet 53 52 30 10.8" Above Cold Tube Sheet 62 57 20 9.8" Above 3rd Hot Horiz. Spt 51 54 19 5.1" Above Cold Tube Sheet 54 55 15 7.9" Above Cold Tube Sheet Page 9 of 20
_ ______JJU2 @ - - - - .
1986-1987 INSERVICE INSPECTIONS
- 3. PLANT UNIT: 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: DPR-36
- 5. COMMERCIAL SERVICE DATE: 12/29/72
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865
- 11. ABSTRACT OF CONDITIONS NOTED: J
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN CATEGORY CONDITION CORRECTIVE MEASURE Safety Class 1 Supports F-A,B,&C Two anchor bolts of a pipe The anchor bolts were support for a 2" charging retorqued and line were found to be loose, reinspected. l Three (3) Additional j supports were examined in accordance with IHF 2430.
One snubber on a 3" charging The tubing fitting was .
line had a leaking tubing tightened and inspected.
fitting and low fluid level The snubber Tas repaired in reservoir. as required by Tech.
Spec. 3.20 and l reinspected.
i Additional inspections
! are to be pecformed to .
snubbers listed in T.S. I 3.20 in 12 + 3 months as required by T.S. 4.9.
One spring hanger on a 10" The travel stops were Safety Injection line was found removed and the support with travel stops in the spring was reinspected.
can restricting movement. Five (5) additional supports were examined in accordance with INF-2430.
l Page 10 of 20 2124P
l 1986-1987 INSER'/ ICE INSPECTIONS
- 3. PLANT UNIT: 1 4. OWNER CERTIFICATE OF AUTHORIZATION: DPR-36 ,
1
- 5. COMMERCIAL SERVICE DATE: 12/29/72
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865 !
I'
- 11. ABSTRACT OF CONDITIONS NOTED:
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN CATEGORY CONDITION CORRECTIVE MEASURE Safety Class 2 Supports F-A, B & C One rod hanger on a 10" Charging The rod was adjusted to Line was found to be loose and properly support the not fully supporting pipe. pipe and reinspected.
Three (3) additional supports were examined i in accordance with IWF-2430.
One spring hanger on an 18" The spring hanger was Containment Spray line was thoroughly cleaned, found heavily corroded due to painted and its location in a very moist reinspected.
environment. Three (3) additional suppcrts were examined in accordance with IHF-2430.
Two supports on a 14" Residual The two supports were Heat Removal line were found repaired and with loose parts, reinspected. Five (5) additional supports were examined in accordance with IHF-2430.
Five supports on a 14" Feedwater All supports were line were found rejectable. repaired and Four of the supports had loose reinspected.
bolting and one was deformed Twenty-Six (26)
A water hammer on 4/17/86 additional supports is assumed to be the were examined in cause of these rejects, accordance with IHF-2430. In addition, all integral attachments to this line and anchor at each end were MT inspected.
Page 11 of 20 2124P
f i l
FORM NIS 2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI
- 1. owner M, inn vankee Atomic Powr Oxnpany oete 1987 Fefueling
<N.me, Ancusta. Mu,ne 1 9 33,,, ,,
aoenN
- 2. Plant M nn Y-mt no At nrnin TbWer Plant Unit Peactor Vessel 20865 Wiscasset, M d NE poesni
- 3. Work Performed by Sen Panon 11 thni 20 See Pages 13 thru 20 (MI Recaer Organizaison P.O No. Joe No. etc.
moonsa,
- 4. Identification of System cnn Pages 13 thn120
- 5. la) Applicable Construction Code nn1 1 19 77 Edition Addenda, Code Cases -
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements - 198.0., ERO Addenda, Code Cases
- 6. Identification of Components Rupaired or Replaced, and Replacement Components Name of Name of Mf ts, Ser. Nat'l. CRN other Year Repaired. ASME Code Component Mfr. No. Bd. No. Identi- Built Replaced, S tamped No. fication or (Yes or No)
Replacement con n- gne l 't am 20 1
1
- 7. Description of Work See Panes 13 thn1 20
- 8. Tests Conducted: Hydrostatic D Pneumatic 0 Nominal Operating Pressure O otner 0 -
Pressure psi Test Temp. 'F 9 Remarks Appucaue Manufacturer s Dala Aeports to be attacnem
~
r- l
)
CERTIFICATE OF PLI CE we ME Co rN st the statements made in this
^
ort are correct and this 4 kfA 4 MW conforms to Section xi of tne s /
ND**"" w a nu igned
' to A ~ '
NMlf WO' ,19 S7 signeti rme ica.e, f
U CERTIFICATE OF INSPECTION t, the undersigned, holding a valid commission issued by the National Board of Boller and Pressure Vessel inspectors and or Province o, New York , empioved by H.S.B.I&I Co.
Hartford, Ct or hove inspected the re oa ir /rpi c case,ie,ein inis p ,po, ton November 19 , ig 81 inepairts, or Replacemenusit and state that to the best of my knowledge and belief, this repair or replacement has been constructed in accordance i with Sect o the ASME Code. By signing this certificate, neither the Inspector nor his employer rnekes any warranty, empressed or implied co ,
ing the repair or replacement described in this Report. Furthermore, neither the Inspector not his employer shall be liable in for any personal injury or property dam *Je off p osteNovember 19.1987 ( o 7/y kindo arisirigCommissions from or Connected NB 10011 with I,Nthis Inspection.
mwwc <sia,e o, % ce new soorm {
i Note: supplemental sheets in town of itses, sketcha, or drawings may be used provided (Il size Is 8% in. X 11 in.,
(2) Information in stems 1 through a on this data reoort is included on each sneet, and (3) each sheet is numbered and tn. numo.r of sh.ees is record.d et the too of snis form.
Page 12 of 20
)
1986-1987 INSERVICE INSPECTIONS
- 2. PLANT: Maine Yankee Atomic Power Company UNIT: Reactor Vessel 20865 Hiscasset, Maine REPAIRS, REPLACEMENTS AND ALTERATIONS LISTED BELOH:
A. Job No. and
Title:
EDCR 85-13-1; Appendix J Refueling Cavity Purification System Modification System: Refueling Cavity Purification (CPU)
Safety Class: 2 and NNS (See IWA 1300 [f])
( Hork Performed By: Cianbro Corporation, Pittsfleid, Maine
Description:
A test boundary valve and test / drain connection were added to the CPU System to permit leak testing of the Containment Isolation valves in accordance with 10CFR50, )
Appendix J.
Section XI Preservice NDE: None required as indicated by Section XI, )
IHA-1300 (f). NDE was performed to satisfy !
construction requirements as follows.
Component Method Four 6" Butt Helds Liquid Penetrant & Radiography Pressure Test: This modification was hydrostatically tested to at least 1.1 times the design pressure of 150 psig at a )
temperature greater than 40*F.
Page 13 of 20 l 2124P
/
1986-1987 INSERVICE INSPECTIONS
- 2. PLANT: Maine Yankee Atomic Power Company UNIT: Reactor Vessel 20865 Hiscasset, Maine REPAIRS, REPLACEMENTS AND ALTERATIONS LISTED BELOW:
B. Job No and
Title:
EDCR 85-37; Appendix J RCS Letdown System Modification System: Letdown (LD)
Safety Class: 2 Hork Performed By: Cianbro Corporation, Pittsfield, Maine i
Description:
A trip valve and test / drain connections were added to the Letdown System to permit leak testing of the Containment Isolation valves in accordance with 10CFR50 Appendix J.
Section XI Preservice NDE: None required as indicated by Section XI, f IHC-2200 and IHC-1220. NDE was performed i to. satisfy construction requirements as !
follows.
Component Method Two 2 1/2" Butt Helds, SC-2 Visual, Liquid Penetrant, Radiography Three 2" Butt Helds, SC-2 Visual, Lquid Penetrant, Radiography !
One 3/4" Butt Held, SC-2 Visual, Liquid Penetrant, Radiography Pressure Test: This modification was hydrostatically tested to at- ]
least 1.25 times the design pressure of.2485 psig at a l temperature greater than 70*F, j l
1 Page 14 of 20 2124P l
1 l
1986-1987 INSERVICE INSPECTIONS
- 2. PLANT: Maine Yankee Atomic Power Company UNIT: Reactor Vessel 20865 l Wiscasset, Maine REPAIRS, REPLACEMENTS AND ALTERATIONS LISTED BELOW:
C. Job No. and
Title:
DR/R0 3058-86; Replacement of Valve 80-T-32 System: Steam Generator Blowdown (BD)
Safety Class: 2 Work Performed By: Maine Yankee
Description:
A 2" valve (BD-T-32) was replaced due to excessive leakage.
Section XI Preservice NDE: None required. New welds were inspected per construction codes.
Pressure Test: This replacement was hydrostatically tested to at least 1.25 times the design pressure of 950 psi at a temperature greater than 70*F.
D. Job No. and
Title:
DR/R0 362-87; Replacement of check valve SL-36 l System: Reactor Coolant Pump Seal Water (SL)
Safety Class: 2 l Work Performed By: Maine Yankee
Description:
A 1 1/2" check valve (SL-36) was replaced due to damage during maintenance.
i Section XI Preservice NDE: None required. New welds were inspected per construction codes. l Pressure Test: This replacement was hydrostatically tested to at least 1.25 times the design pressure of 2500 psi at a temperature greater than 40*F.
l l
i l l
Page 15 of 20 2124P
1986-1987 INSERVICE INSPECTIONS
- 2. PLANT: Maine Yankee Atomic Power Company UNIT: Reactor Vessel 20865 Hiscasset, Maine REPAIRS, REPLACEMENTS AND ALTERATIONS LISTED BELOH:
E. Job No. and
Title:
DR/R0 4765-86; Repair of Safety Valve SL-S-67 System: Reactor Coolant Pump Seal Water (SL)
Safety Class: 2 Work Performed By: Maine Yankee
Description:
A 3" safety valve (SL-S-67) was reinstalled following preventive maintenance repairs.
Section XI Preservice NDE: None required. New welds were inspected per construction codes.
Pressure Test: This reinstallation was hydrostatically tested to at least 1.25 times the safety valve setting pressure of 200 psig at a temperature greater than 40*F.
F. Job No and
Title:
DR/R0 2975-86 and DR/R0 2979-86.
Replacement of valves HPD-13 and 3, respectively.
System: High Pressure Drain (HPD)
Safety Class: 2 Hork Performed By: Maine Yankee
Description:
Two 1 1/2" valves (HPD-3 and HPD-13) were replaced.
Section XI Preservice NDE: None required. New welds were inspected per construction codes.
l Pressure Test: This replacement was hycrostatically tested to at least j 1.25 times the design pressure of 950 psi at a temperature greater than 70*F.
i l
i Page 16 of 20 2124P l
1986-1987 l INSERVICE INSPECTIONS
- 2. PLANT: Maine Yankee Atomic Power Company UNIT: Reactor Vessel 20865 '
Wiscasset. Maine REPAIRS, REPLACEMENTS AND ALTERATIONS LISTED BELOH:
G. Job No, and
Title:
DR/R0 4767-86; Repair of Safety Valve EFW-S-38 System: Emergency Feedwater (EFW) , !
Safety Class: 2 I Work Performed By: Maine Yankee
Description:
A i 1/2" safety valve (EFW-S-38) was reinstalled following preventive maintenance repairs.
Section XI Preservice NDE: None required. New welds were inspected per construction codes. ,
1 Pressure Test: This reinstallation was hydrostatically tested to at )
least 1.10 times the safety valve setting pressure of 75 psig at a temperature greater than 40*F.
H. Job No. and
Title:
DR/R0 1591-87; Repair of valve MS-P-168 System: Main Steam (MS)
Safety Class: 3 l
Work Performed By: Maine Yankee
Description:
A 1 1/2" pressure regulating valve (MS-P-168) was reinstalled following repairsSection XI Preservice NDE: None required. New welds were inspected per construction codes.
Pressure Test: This reinstallation was hydrostatically tested to at least 1.25 times the design pressure of 985 psi at a temperature greater than 40*F.
Page 17 of 20 2124P l
i l
l
1986-1987 INSERVICE INSPECTIONS
- 2. PLANT: Maine Yankee Atomic Power Company UNIT: Reactor Vessel 20865 Wiscasset, Maine REPAIRS, REPLACEMENTS AND ALTERATIONS LISTED BELOW: j I. Job No. and
Title:
DR/R0 4973-86; Repair of Storage Tank Heater E-40 ,
System: Fuel Handling Safety Class: 2 l
l Work Performed By: Maine Yankee
Description:
Weld repair at connection of 2" inlet pipe to tube side of vessel.
Section XI Preservice NDE: None required. New welds were inspected per construction codes.
Pressure Test: This repair was hydrostatically tested to at ^
least 1.25 times the design pressure of 75 psig at a ,,,qN temperature greater than 60*F.
J. Job No. and
Title:
DR/R0 1505-87; PCC and SCC Temporary Bypass System: Primary Component Cooling (PCC) and Secondary Component Cooling (SCC) l Safety Class: 3 Work Performed By: Cianbro Corporation, Pittsifeld, Maine
Description:
Two 2 1/2" lines were temporarily removed to accomodate space requirements for the installation of EDCR 86-10.
Section XI Preservice NDE: None required. New welds were inspected per construction codes, nenure Test: This reinnailations were hydrostatically tested to at least 1.10 times the design pressure of 150 psi at a temperature greater than 40*F-.
1 1
1 l
Page 18 of 20 2124P l
1 1986-1987 INSERVICE INSPECTIONS
- 1. OWNER: Maine Yankee Atomic Power Company DATE: 1987 Refueling !
_ ugusta, Maine A SHEET: 8 of 9
- 2. PLANT: Maine Yankee Atomic Power Company UNIT: Reactor Vessel 20865 Wiscasset, Maine REPAIRS, REPLACEMENTS AND ALTERATIONS LISTED BELOH:
K. Job No. and
Title:
EDCR 86-04; Primary and Secondary Component Cooling Heat Exchangers (E-4A and E-58) Replacement System: Primary Component Cooling (PCC) and Secondary Component Cooling (SCC)
Safety Class: 3 Work Performed By: Cianbro Corporation, Pittsfield, Maine
Description:
Installation of two new component cooling heat exchangers.
Section XI Preservice NDE: None required. New weids were inspected per construction codes.
Pressure Test: These installations were hydrostatically tested to 1.10 times the safety valve setting pressures of 150 psig at a temperature greater than 40*F.
L. Job No. and
Title:
DR/R0 2628-87; Repair of Refueling Water Storage Tank TK-4 System: Fuel Handling l Safety Class: 2 Work Performed By: Maine Yankee i'
DescrQtion: Held repair to TK-4 vessel wall.
Section x.' Preservice NDE: None required. New welds were inspected per construction codes. l
{
Pressure Test: T.9 s repair was hydrostatically tested as described by IWC-5222 (b).
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1 i
1986-1987 INSERVICE INSPECTIO"S
- 2. PLANT: Maine Yankee Atomic Power Company UNIT. Reactor Vessel 20865 Wiscasset, Maine REPAIRS, REPLACEMENTS AND ALTERATIONS LISTED BELOH: I l
M. Job No. and
Title:
DR/R0 3958-87, Replacement of -/alve MS-90 System: Main Steam (MS)
Safety Class: 2 Work Performed By: Maine Yankee l
Description:
One 2 inch valve was replaced.
Section XI Preservice NDE: None Required. New welds were inspected per-construction codes.
Pressure Test: An inservice leak test was performed in lieu of a hydrostatic test because the subject welds could not be isolhted from the Steam Generator. See IHA 5214(d).
Page 20 of 20 2124P