ML20244B380
| ML20244B380 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 01/12/1989 |
| From: | Hebert J, Mehlhorn P, Speed L Maine Yankee |
| To: | |
| Shared Package | |
| ML20244B369 | List: |
| References | |
| NUDOCS 8904190166 | |
| Download: ML20244B380 (27) | |
Text
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INSERVICE-INSPECTION
SUMMARY
REPORT FOR-l MAINE YANKEE ATOMIC POWER COMPANY
'. AUGUSTA, MAINE D
GENERATING PLANT: ' Maine Yankee Atomic Power Plant Hiscasset, Maine UNIT DESIGNATION NUMBER: Reactor Vessel 20865 COMMERCIAL OPERATING DATE: 12/29/72 EXAMINATION DATES FROM 09/18/87 to 01/12/89 IN THE SECOND TEN YEAR INTERVAL.
COMPLETION DATE: 01/12/89 7kt kf r Peter Me"h1 horn ISI Coordinator
// .] /
aLinco
,Spefd '
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Performance Engineering Supervisor-f-
M '
Japes Hebert Manager, Plant Engineering k0 G
DO K [
l' CONTENTS Page Number
. Preface .................................................................. 1
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NIS-1 Data Report ......................................................... 2 Abstract of Examinations .................................................. 4 Abstract of-Conditions Noted .............................................. 9 Abstract of Corrective Measures Recommended and Taken ..................... 9 NIS-2 Data Report ........................................................ 12 Abstract of Repairs or Replacements ....................................... 13 l
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.. PREFACE This report summarizes the preservice and inservice inspections and pressure tests that_were performed at Maine Yankee Atomic Power Plant between September 18,.1967 and' January 12, 1989 that fall within the 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.
t All exams required by Maine Yankee's Inservice Inspection Program have been completed for this second period except some miscellaneous system functional tests and system inservice tests, which should.be completed by the end of the period. The Authorized Nuclear' Inservice Inspector on-site to witness the inspections was Mr. Allan P.
. Schiaffino of Hartford Steam Boiler Inspection and Insurance Company.
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1 1267L-RCC Page 1 of 25
._-_______ .a
'.' FORM NIS 1. OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS I'y As required by the Provisions of the ASME Code Rules
- 3. Plant Unit 1 4. Owner Certificate of Authorization (if required) DPP-16
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- 5. Commercial Service Date12 / 29 / 72. 6. National Board Number for Unit Reactor Vessel 20865
- 7. Components inspected Manufacturer Component or Manufacturer or Installer State or National -
Appurtenance or Installer Serial No. Province No. ' Board No.
Reactor Head C.E. 67206 NA 20965 .
St. Gen.#1 C.E. 67501 NA 20919 St. Gen.#3 C.E. 67503 NA 20921 RCP #1 Byron-Jackson 681-N-0421- NA NA
,RCP #3 Byron-Jackson 681-N-423 NA NA Piping Stone & Webster NA NA NA
(
Note: Supplemental sheets in form of lists, sketches, or draw'.ngs rnay be used provided (1) size is 8% in. x 11 in..
(2) information in items 1 through 6 on this c'ata 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' forrn (E00029) rnay be obtained frorn the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017 Page 2 of 25
. ," . FORM NIS-1 (back)
- 8. Examination Dates 09 /18 /8 7 to 01/12/89 9. Inspection Interval fromL 2 / 2 9 / 8 2 to 12 / 29 / 9 2
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. See pages 4 thru 8 and Preface.
- 11. Abstract of Conditions Noted See pages 9 thru 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 examinations and corrective mea-sures taken conform to the rules of the ASME Code,Section XI.
Date A -) / 7 19 89 Signed Maine Yankee By JV # AM Owner /
Certificate of Authorization No. (if applicable) N/A Expiration Date N / 7\
CERTIFICATE OF INSERVICE INSPECTION .
I, the undersigned, holding a valid enmmission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of New York 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 09/18/87 to 01/12/89 . and state that to the best of my L owledge 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 warranry, expressed or implied, concerning the i; 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 April 7 198 9 Commissions NB 10011 I,N Inspector's Signature National Board, State, Province and No.
Page 3 of 25
1987-1988 INSERVICE INSPECTIONS' F e ,. ,-
I' 1..~0HNER[ Maine Yankee Atomic ~ Power Como'any. Augusta Maine 2... PLANT: Maine Yankee Atomic Power Comoany.'Avausta Maine 3.- PLANT UNIT: 1 4. OWNER CERTIFICATE OF AUTHORIZATION:~ DPR-36 5 .' COMMERICAL SERVICE DATE: 12/29/72 c
.6. ' NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865 10.,1eBSTRACT OF EXAMINATIONS:
' CATEGORY IT W NUMBER EXAMINED METHOD-B-B' B2.60 2- Tubesheet-to-Head welds, Regen Heat Exch. UT
.B-F: 1 1/2", Dissimilar Metal-Pipe Held B5.50 UT*
1 1/2", Dissimilar Metal Pipe Held , UT*, PT.
85.51 3'- 3",' Dissimilar Metal Pipe Held PT l'- 2-1/2", Dissimilar Metal Pipe Held' PT
~
1 - 2", Dissimilar Metal Pipe Held PT
- NOTE: 'UT from Carbon Steel Side Only B-G-1 B6.10 51 --Reactor Vessel Closure' Head Nuts (removed) MT, VT-1 B6.30 .11 - Reactor Vessel' Closure Head Studs (removed) UT, MT B6.50 51 - Reactor. Vessel Closure Head Washers (removed) VT B6.180 32 - Studs,. Reactor Coolant Pumps #1 & #3 (16 studs each)-(removed) UT, MT, VT-1 B6.190 2 - Flange Surfaces, Reactor Coolant Pumps #1 & #3 VT-1 B6.200 32 - Nuts Reactor Coolant Pumps #1 & #3 (16 nuts each) (removed) VT-1 B-G.2 B7.30 40 - Primary Hartway Bolting Steam Generator. #1,
, (2 manways, 20 each) (removed) MT, VT-1 67.50 1 - Piping Flange Bolting (in place) VT- l -
B7,70 9 - Body te Bonnet Bolting (iri place)- VT-1 B7.70 1 - Body to Bonnet Bolting (removed) MT, VT-1 1267L-RCC Page 4 of 25
- , ~1987-1988 INSERVICE INSPECTIONS.
11 LOHNER: Maine Yankee Atomic' Power Comoanv. Auausta Maine
'D J '2. PLANT: Maine Yankee Atomic Power Company. Augusta Maine
-3. PLANT UNIT:- 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: non C
- 5. : COMMERICAL SERVICE DATE:
12/29/72
- 6. .NATIONALcBOARD NUMBER FOR UNIT: Reactor Vessel 20865
.10. ABSTRACT OF EXAMINATIONS (Cont'd):
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, CATEGORY llEll E NUMBER EXAMINED' METHOD ~
.B-J 89.'11 ~1 1/2",:Circumferential Pipe Helds PT l
2 - 14", Circumferential Pipe Helds. .UT,-PT.
1;- 12", Circumferential Pipe Helds PT.
1 - 12", Circumferential Pipe Helds UT, PT 2 - 10", Circumferential Pipe Helds UT, PT 4 - 8",- Circumferential Pipe Helds . RT, PT 5 - 4". Circumferential Pipe Helds ' UT, PT .
89.21 13 - 3", Circumferential Pipe Helds PT
.1 5 1/2", Circumferential Pipe Helds PT B9.31 1 - 12", Branch Pipe Connection Held UT, PT 89.40 10 - 2", Socket Helds PT-B-L-1 'B12.10 120" of Casing Held, Reactor Coolant Pump #3 PT B-P B15.00 Reactor Coolant System Leak Test VT-2 B15.51~ Primary Inventory Trend System Hydro VT-2 B-Q B16.00 . Steam Generator #1 Tubing as required by ECT Maine Yankee Tech Spec. 4.10.
- 514 Tubos, First Sample 9
- 1028. Tubes, Second Sample
- 2056 lubes, Third Sample 11 Tubes additional to assure sample sizes were i accomplished.
1267L-RCC Page 5 of 25 b
1987-1988 L-INSERVICE INSPECTIONS l'. OHNER: Maine Yankee Atomic Power Co_moany. Augusta Maine
- 2. PLANT: Maine Yankee Atomic Power CompAOL_,_ngusta A Maine l 3. PLANT UNIT: 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: DPR-36
- 5. COMMERICAL SERVICE DATE: 12/29/72
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS (Cont'd):
1 CATEGORY IIEE NUMBER EXAMINED METHOD F-A,B&C F-1,2, 3&4 Safety Class 1 Supports 29 Supports VT-3 7 Supports VT3 & 4 4 additional exams as required by VT-3 IWF-2430. See Page 11 for details.
1 1267L-RCC Page 6 of 25
1987-1988' INSERVICE INSPECTIONS
- 1. 0WNER: Maine Yankee Atomic Power Comoany. Augusta Maine 2; PLANT: Maine Yankee Atomic Power Comoany. Auausta Maine
- 3. PLANT UNIT: 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: DPR-36
- 5. ~COMMERICAL 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 C-A C1.10 1 - Shell-to-Flange Held, Letdown Ht. Exch. UT C1.20 1 - Head-to-Shell Held, Residual Heat Removal Ht Exch. UT 1 - Shell-to-Head Held, Seal Hater Supply Filter UT C1.30 1 - Tubesheet-to-Shell Held, Seal Water Heater UT 1 - Shell-to-Tubesheet Held, Residual Heat Removal Ht. Exch. UT 2 - Tubesheet-to-Shell Helds, Regen Ht. Exch. UT C-B C2.21 1 - Nozzle-to-Shell Held, Residual Heat Removal Ht. Exch. UT, PT )
C-F C5.11 2 - 16", Circumferential Pipe Helds PT 3 - 14", Circumferential Pipe Helds PT i
4 - 12", Circumferential Pipe Helds PT 16 - 10", Circumferential Pipe Helds PT 1 - 8", Circumferential Pipe Helds PT l 4 - 6", Circumferential Pipe Welds PT l
1 - 6", Circumferential Pipe Helds MT l
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1267L-RCC Page 7 of 25
-1987-1988
- INSERVICE INSPECTIONS
- 1. CHNER: Maine Yankee Atomic Power Comoanv. Auausta Haine
'2 . PLANT: Maine Yankee Atomic Power ComDany. Auausta Maine
- 3. PLANT UNIT: 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: DPR-36 l
- 5. COMMERICAL SERVICE DATE: 12/29/72
- 6. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vessel 20865
- 10. ABSTRACT OF EXAMINATIONS (Cont'd):
CATEGORY ITFM NUMBER EXAMINER liET11QQ C5.21 1 - 30", Circumferential Pipe Helds UT, MT 1 - 6", Circumferential Pipe Helds UT, PT l C-G C6.10 Residual Heat Removal & Low Pressure Safety Injection Pump Casing Held (3 Circ Helds) PT C-H C7.00 Hydrostatic Pressure Tests VT-2
- a. Refueling Hater Storage Tank (RHST)
- b. RHST Siphon Heater (E-40)
- c. Secondary High Pressure Drain
- d. Containment Spray and Residual Heat Removal Recirculation Piping.
- e. Containment Spray, (3) Hydros
- f. High Pressure Safety Injection C-H C7.00 System Functional Tests VT-2
- a. Charging System
- b. Auxiliary Feedwater System
- c. Feedwater System
- d. Main Steam System
- e. Secondary High Pressure Drain System
- f. Auxiliary Steam System F-A,B,&C F-1,2,3&4 Safety Class 2 Supports 15 Supports VT-3 20 Supports VT-3 & 4 13 additional exams as required by VT-3 IHF-2430.
22 additional exams as required by IHF-2430. VT-3 & 4 l See Page 11 for details.
4 additional exams on supports not VT-3 )
required by Section XI.
1267L-RCC Page 8 of 25
'1987-1988 INSERVICE INSPECTIONS
~
2 . .- PLANT- Maine Yankee Atomic Power Comoany. Augusta Maine j
, '3. PLANT UNIT: 1- 4. 0HNER' CERTIFICATE OF AUTHORIZATION: DPR-36
- 5. COMMERICAL SERVICE DATE: 12/29/72'
.6' , NATIONAL's0ARDNUMBERFORUNIT: Reactor Vessel 20865
.11. ABSTRACT 0F CONDITIONS NOTED:
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN:
CORRECTIVE' CATEGORY CONDITION MEASURE
,B-Q Steam Generator #1 Tubing Row Lial 111LQ Location Defective' 22 105 48 9.3" Above. Cold Tube Sheet Plugged Tube Tubes: 23 34 48 7.6" Above Cold Tube Sheet- Plugged Tube 26~ 107 45 10.0" Above Cold Tube Sheet . Plugged Tube 65 9.7" Above Cold Tube Sheet.
48 55 48 9.6" Above Cold Tube Sheet . Plugged Tube 81 74 41 1.0" Below third Vertical Plugged Tube Support Additional exams were inspected per Maine Yankee Tech Spec.
4.10 Degraded 26 37 37 9.9" Above Cold Tube Sheet Plugged Tube.
Tubes 2 109 24 0.8" Above Hot Tube Sheet Additional 26 99 29 11.8" Above Cold Tube Sheet exams not 27 116 22 5.9" Above Hot Tube Sheet required for 31 138 33 18.7" Above Cold Leg #6 Horizontal less than 40*/.
Support through wa.ii 45 86 23 5.0" Above Hot Tube Sheet degradation 46 55 31 9.0" Above Cold Tube Sheet (THD).
.50 57 24 7.3" Above Cold Tube Sheet 52 57 21 8.5" Above Cold Tube Sheet 79 86 32 1.7" Above Hot Tube Sheet 85 92 21 1.1" Above Hot Tube Sheet 90 115 28 1.9" Above Cold Log #6 Horizontal Support.
I 1267L-RCC Page 9 of 25
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1987-1988
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' INSERVICE INSPECTIONS
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! .- 2.,l PLANT:' ' Maine' Yankee Atomic Power Comoany. Auausta Maine i #o E 3.:.. PLANT UNIT: 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: DPR-36 3 1 -.5; 'COMMERICAL SERVICE DATE: 12/29/72
~6.. NATIONAL BOARD NUMBER FOR UNIT: Reactor Vesse1~20865
- 11. ABSTRACT OF CONDITIONS NOTED: q
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN:
l CORRECTIVE CATEGORY ' CONDITION MEASURE-B-Q' Steam' Generator #1 Tubing Row Ling '%THD: Location Imperfect 29' 108- 13. 14.0" Above Hot Tube Sheet. None Tubes 35 98 15 14.1"'Above Cold Tube Sheet
.48 57 10 9.1" Above Cold Tube Sheet 59 58 19' 9.0" Above Cold Tube Sheet 61 58 11 0.1" Above Cold Tube Sheet 63 78. 12 13.1" Above Cold Tube Sheet 85 98. 15 5.6" Above Hot Tube Sheet 90 71 14 2.0" Above Hot Tube Sheet
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Seven additional tubes were conservatively plugged as follows:
31 138 Possible debris induced imperfection Plugged Tube 90 115 Possible' debris induced imperfection Plugged Tube 2 141 Uncharacterized Denting Plugged Tube 64 55 Uncharacterized Denting Plugged Tube 48 103 Uncharacterized Denting Plugged Tube 94 111 Uncharacterized Denting Plugged Tube r
4 106 97 Uncharacterized Denting Plugged Tube 11267L-RCC Page 10 of 25
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B ~1987-1988
+~
- INSERVICE' INSPECTIONS
- 1. OHNER: Maine Yankee Atomic Power Comoanv. Augusta Maine 2.' PLANT:- Haine Yankee Atomic Power Comoanv. Auausta Maine
'3. PLANT UNIT: 1 4. 0WNER CERTIFICATE OF AUTHORIZATION: DPR-36
- 5. COMMERICAL 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: 1 CORRECTIVE GATEGORY. CONDITION MEASURE Safety Class 1 SuoAqr_t1 F-A,B,&C One linear support for a 2" Loop The support was repaired. ;
drain header was found loose. and reinspected. Four l (4) additional supports l were examined in accordance with.IHF 2430. j Safety Class 2 Sucoorts F-A,B,&C One spring hanger on a 14" The support was repaired Residual-Heat Removal (RHR) and reinspected. Three (3) line was found with a loose additional supports were bolt on the pipe clamp. examined in accordance wito IHF 2430.
Two spring hangers on a 10" The supports were repairedL RHR line were found with and reinspected. Seven (7).
loose bolts on the pipe clamps. additional supports were examined in accordance with IWF 2430.
Of the above ten (10) additional These supports were supports examined two were repaired and reinspected.
found with loose locknuts on The remaining twenty-five the rod coupling. (25) RHR supports outside of containment and four (4) Non-Section XI component cooling supports, which support the supply and return piping to the RHR heat exchangers, were inspected. No rejectable indications were found.
1267L-RCC Page 11 of 25
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FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI
Sheet of
- 2. Plant Maine Yankee A @dTc Power un;, Reactor Vessel 20865 I
Plant, WisdUset, Maine woo,ese, l' 3. Work Performed by Se e oaces 13 thru 25.
therne)
See naces 13 thru 25.
Repeer organizahon P.O No JoD No , etc.
IAosess:
4 Identification of Systern See Dages 13 thru 2 5.
- 5. (e) Applicable Construction Code . B31.1 19 77 Edition; Addenda, Code Cases (b) Appilcable Edition of Section XI Utilized for Repairs'or Replacements - IR.R . W8 0 Addenda, Code Cases
- 6. Identification of Components Repaired or Replaced. and Replacement Components
[ Name of Name of Mfrs.Ser. Nat'l. CRN Other Year Repaired. ASME Code -
l Component Mir. No. Bd. No. Identi. Built Replaced, Stamped No. fication or
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(Yes or No)
Replacement See pages 13 thra 25'.
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- 7. description of Work _ See pages 13 thru 25.
- 8. Tests Conducted: Hydrostatic 0 Pneumatic O Nominal oper. ting Pressure O other O Pressure ps! Test Temp. 'F
- 9. Remarks popocaom uenutectv<er s outa nepons io tm anacnem CERTIFICATE OF COMPLIANCE We certify that t:ie statements mee in this reoort are correct and th;, re pa ir & replacem9980rms to section xi M the ASME Code. I'**" 0"'D'*"*"H Signed - /b M dA- #^# SW"/NV/ rm April 7 ,3g89 to.ner or oys en gan, rm. < case, 7
CERTIFICATE OF INSPECTION 1, the undersigned. holding a valid commission issued by the National Board of Boiler end Prmure Vessel Inspectors and the State or Province of New York , ,m pioy ,d by H.S.B.I&I Co. '
ot Hartford, Ct have inspected enerepair/rolc desc,ibed in this Report onApril 7 , igy ineca.<tsi o, nepiscamenimt and state that to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Sectinn XI of the ASME Code. By signing this certificate, neither the insotactor nor his employer rnakes any warranty, empressed or implied. concern.
ing the repair or replacement described in this Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damaiejr get ny kind arising from or connected with this inspection.
o ,te A p r i l 7 . 1 9 8 9 /v fp V Commission, NB 10011_I,N rnwecion _
tswo o, en-e+ei one sum Note; Supplemental sheets in form of lists, skerenes. or drawings may be used provided (1) size is 84 in. X 11 In.,
(2) Information in items 1 through 4 on this cata report is included on each sheet, and (3) each sheet is numbered and the number of sheeta le recorded et the top of this form. '
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4 1987-1988 INSERVICE' INSPECTIONS 1 . ibHNER: Maine' Yankee Atomic Power ComDany. DATE: 1988 Refuelina-Augusta Maine SHEET: 2 of 14-
- 2. PLANT: NJine Yankee Atomic Power Comoanv. UNIT: Reactor Vessel 20865 Hiscasset. Maine Job No. and
Title:
EDCR 88-36; CONTROL' ROOM HABITABILITY UPGRADE / CONTROL AND COMPUTER ROOM AIR CONDITIONER COOLING WATER TRAIN SEPARATION.
-System: Primary Component ' Cooling (PCC) and Secondary Component Cooling (SCC).
Safety Clain 3 Work Performed bv: Cianbro Corporation, Pittsfield, Maine
Description:
The PCC and SCC piping to the air-conditioners were swapped to provide independent redundant air conditioning to the Control Room. The piping was also rerouted close to the ceiling to provide more headroom in that area.
Section XI Preservice NDE: Narie required. New welds were inspected per the construction code and Yankee General Specifications.
Pressure Test: This modification was hydrostatically tested to at least 1.10 times the design pressure of 150 psi at a temperature greater than 40*F.
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1987-1988S
, ', : INSERVICE INSPECTIONS
/
. 0WNER: Maine-Yankee Atomic Power Comoanv. DATE: 1988 Refuelina Augusta Maine SHEET: ,3 of 14
=2..' PLANT:.Haine Yankee Atomic Power Comoanv. UNIT: Reactor Vessel 20865 Hiscasset. Maine
' Job No. and Titlei 'DR/R0 6758-88; SCC Underground. Piping at Spray-Building Penetrations.
System: . Secondary. Component Cooling (SCC).
Safety Class: 3 Rork Performed by: Cianbro Corporation, Pittsfield, Maine
Description:
Held repairs.'were made to degraded SCC piping underground. The leaks resultad.from external pitting at gaps in the protective covering on .
.the piping.
Sectio'n XI'Preservice NDE:
~
None--required. New welds were inspected per the construction code ~and Yankee General Specifications.
P_rfssure Test: The repaired piping was hydrostatically tested to at least 1.10 times the design pressure of 150 psi at a temperature greater than 40*F.
~1267L-RCC Page 14 of 25
[ -F 1987-1988-
>7 INSERVICE INSPECTIONS m' '
L. > 'fl'.; OWNER:l Maine Yankee Atomic Power comoany.
DATE: 1988 Refueling Auausta Maine SHEET: 4 of 14
, 2. PLANT: Maine Yankee Atomic Power Comoany. UNIT: Reactor Vessel 20865 Hiscasset. Maine
-Job'No. and
Title:
.DR/R0 2345-87 and 6890-88; Replacement of valve CH-155 and repair-
.of safety valve CH-S-62 respectively.
System: Charging (CH).
Safety Class: -3/2 Work Performed by: Anchor Darling Valve Co., Hilliamsport,'PA
.Dpscriotion:- Al2", safety valve (CH-S-62) was reinstalled following preventive maintenance' repairs.
A 1-1/2" valve (CH-155) was' replaced'due to' excessive seat leakage.
Section XI Preservice NDE: None required. New welds were inspected per.the-construction code and Yankee General Specifications.
Pressure Test: CH-155 and the high pressure side of CH-S-62 were hydrostatically tested to at least 1.25 times the safety valve set pressure of 2735 psi-M a temperature greater than 40*F. ,
The relief side of.CH-S-62 was hydrostatically tested to at least 1.10 times the design pressure of 150 psi- at a temperature greater than 40'F.
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L 1987-1988 kz, , . INSERVICE INSPECTIONS L
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- 1. 0WNER: Maine Yankee Atomic Power comoanv. DATE:. 1988 Refuelina Auausta Maine SHEET: 5 of - 14 2 .~ PLANT:' Maine Yankee Atomic Power Comoany. UNIT: Reactor Vessel ~20865 Hiscasset. Maine _
- Job th). and'
Title:
'DR/R0 0824-88; Replacement of-pipingLfrom refueling' water storage tank to-its heater.
System: Fuel Handling-u.
Safety' Class: 2 Hork Performed by: Maine Yankee-
Description:
The_ piping cracked due to repetitive water hammers. The piping was replaced with a higher schedule pipe.
Section XI Preservice NDE:- None required. New welds were inspected per the construction code and Yankee General Specifications.
Pressure Test: 'This repair was hydrostatically tested as' described by IHC-5222 (b).
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1267L-RCC Page 16 of 25
1987-1988-
,- ';' - INSERVICE INSPECTIONS-
- 1. OWNER: Maine Yankee Atomic Power Comoany. DATE: 1988 Refuelina Auausta Maine SHEET: 6 of. 14
- 2. . PLANT: Maine Yankee Atomic Power Comoany. UNIT: Reactor Vessel-20865 Hiscasset. Maine Job No,'and
Title:
DR/R0 6492-87; Repair of Storage Tank Heater E-40 System: Fuel. Handling-Safety Class: 2 ,
i Hork Performed bv: Maine Yankee ,
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Description:
Held repair at connection of 2'.' inlet pipe to the tube side of vessel.
The weld cracked due to high stresses caused by the pipe being
. restrained rather than allowed to expand freely.
Spction XI Preservice NDE: None required. New welds-were inspected per the construction code and Yankee General Specifications.
Pressure Test: This repair was hydrostatically tested to at l' east 1.10 times the design pressure of 150 p:;i at a temperature greater than 40*F.
1267L-RCC Page 17 of 25 l L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ . _
'1987-1988-J'
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INSERVICE' INSPECTIONS l'. OWNER: Maine Yankee Atomic Power Comoany. DATE: '1988 Refueling Augusta Maine SHEET: '7- of '14 -
ilob No. and
Title:
EDCR 87-03; RELOCATE HS-S-170 (Inlet Safety Valve to AFH Pump.
Turbine).
System: Main Steam (MS)-
, Safety Class: 3 Bork Performed by: Maine Yankee
Description:
MS-S-170~ was relocated to prevent. inadvertent lifting of the safety.
valve. 1 Section XI'Preservice NDE: LNone required. New weld's were inspected.per the.
construction code and. Yankee General Specifications.
Pressure Test: 'The new pip'ing was hydrostatically tested to at least 1.5 times the design pressure of 670 psi at a temperature greater than 40'F.
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1987-1988 INSERVICE INSPECTIONS
.,. 4 l '. 0WNER: Maine Yankee Atomic Power Comoanv. DATE: 1988_ _Ref u_eling e Augusta Maine SHEET:. 8 of 14 2.; PLANT: Maine Yankee Atomic Power Comoany. UNIT: Reactor Vessel 20865 Hiscasset. Maine
-Job No. and
Title:
DR/R0 1810-88; Removal of FI-3502.
t System: Post Accident Purge (PAP)
' Safety Class: 3-LHork Performed by: Maine Yankee Dpscriotion: A new flowmeter was installed in this system per EDCR-80-44, therefore,-
' the old flowmeter-(FI-3502) was removed.
':Section XI Preservice NDE: None required. New welds were inspected per the construction code and Yankee General-_ Specifications.
Pressure Test: The new piping was pneumatically tested to at least'l.25 times'the design pressure of 55 psi at a temperature greater than 40*F.
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-1987-1988 Je/. . INSERVICE INSPECTIONS
- 1. O NER: Maine Yankee' Atomic Power Comoany. DATE: 1988 Refueling.
Auausta Maine SHEET: 9 of 14
- 2. PLANT: Maine Yankee Atomic-Power comoanv. UNIT: Reactor Vessel 20865 Hiscasset. Maine Job No. and~ Title': DR/RO 2947-88; MS-49 Replacment ESyitem: Main Steam (MS) and Secondary High Pressure Drain (SHPD)
Safety Class: 2 Hork Performed by: Cianbro Corporation, Pittsfield, Maine
Description:
One 2 inch valve was replaced due to excessive seat leakage.
Section XI Preservice NDE: None required. . New welds were inspected per the construction code and Yankee General Specifications.
Pressure Test: The down stream side of the valve was hydrostatically tested to:1.25-times the design pressure of 950 psi at a temperature greater than.40*F.
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The upstream side of the valve received an inservice leak test in lieu of a hydrostatic test because the subject weld could not be isolated from the steam generator. See IWA 5214 (d), INA 2240 and Code Case N 416.
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c INSERVICE INSPECTIONS I
- 2. PLANT: Maine Yankee Atomic Power Comoanv. UNIT: Reactor Vessel 20865 }
Wiscasset. Maine Jpb No. and
Title:
DR/R0's 7000-87, 7001-87, & 1484-88; Replacement of Valves MS-230, MS-228, and MS-232 respectively. I System: Main Steam (MS) l Safety Class: 2 Work Performed by: Anchor Darling Valve Company, Hilliamsport, PA
Description:
Three 2 inch Main Steam valves were replaced due to excessive seat leakage.
Section XI Preservice NDE: None required. New welds were inspected per the construction code and Yankee General Specifications.
Pressure Test: These replacements received an inservice leak test in lieu of a hydrostatic test because the subject welds could not be isolated from the steam generators. See IWA 5214 (d), IHA 2240, and Code Case N416.
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1987-1988 j INSERVICE INSPF.CTIONS !
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Job No. and
Title:
EDCR 88-26; Primary Inventory Systems Upgrades .,
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4 System: Primary Inventory Trend System (PITS) l l
Safety Class: 1 I Work Performed bv: Cianbro Corporation, Pittsfield, Maine Opscriotion: The upgrade of the system included rerouting of tubing and installing new instrumentation.
i Section XI Preservice NDE: None required. New welds were inspected per the construction code and Yankee General Specifications.
Pressure Test: A section.of 2" pipe (seal pot) was hydrostatically inspected to at least 1.5 times the design pressure of 2500 psi at a temperature greater than 40*F.
The isolatable portion of the system was hydrostatically tested to the design pressure of 2500 psi for information only.
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-1987-1988- 4 1, f.
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l '. J OWNER: tigine Yankee Atomic Power Comoanv. DATE: .1988 Refuelinc Auausta Maine SHEET: 12 of 14 2'. - PLANT: Maine Yankee' Atomic Power Comoany. 'l UNIT: Reactor Vessel 20865 Hiscasset. Maine L
. Job- No. ' and
Title:
EDCR-88-54; Regulatory Guide 1.97, " CONTAINMENT SPRAY FLOH -!
INDICATION".
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K, Svstem:- Containment Spray (CS) ) '
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' Safety Class:
3 i l
Hork Performed by: .Cianbro Corporation, Pittsfield? Maine
Description:
Flow. instruments were. installed into the piping to the containment.
spray = rings..
.Section XI Preservice NDE: None required. New welds were inspected'per the construction code and Yankee General Specifications.
i This modification was hydrostatically tested to at least 1.25 times' the
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-Er_ essure Test: .i design pressure of 235 psi..at a temperature of greater than 40*F.
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1987-1988 INSERVICE INSPECTIONS
'1. 0HN R: B ine Yankee Atomic Power ComDany. DATE: 1988 Refueling Augusta Maine SHEET: 13 of 14 1
- 2. PLANT: Dine Yankee Atomic Power ComDany. UNIT: Reactor Vessel 20865 )
Hiscasset. Maine Job No. and
Title:
DR/R0 0261-88; Replacement of check valve EFH-314.
i System: Emergency Feedwater (EFH)
)
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Safety Class: 3 l Hork Performed by: Maine Yankee
Description:
EFH-314 (EFH Pump discharge check) was replaced due to a through body pin hole leak.
Section XI Preservice NDE: None required. New welds were inspected per the construction code and Yankee General Specifications.
Pressure Test: The new welds received an inservice leak test while the pump was run on recirc. This check valve can not be isolated from the suction side of the pump, therefore, would experience greater pressure in recirc than a hydro at 1.10 times the suction pressure.
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1987-1988 !
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INSERVICE INSPECTIONS
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- 1. 0WNER: Maine Yankee Atomic Power Comoany. DATE: _1988 Refueling .
Augusta Maine SHEET: 14 of 14
- 2. PLANT: Maine Yankee Atomic Power Comoanv. UNIT: Reactor Vessel _20345 Hiscasset. Maine Job No. and
Title:
EDCR 88-44; MODIFICATION OF NO. 3 FEEDHATER LINE SUPPORTS.
System: Feedwater (FH)
Safety Class: 2 Hork Performed by: Cianbro Corporation, Pittsfield, Maine.
Description:
.An anchor on the #3 feed line was changed to a sliding support. Other supports were adjusted.
Section XI Preservice NDE: A VT-3 inspection was performed on the modified support.
Pressure Testi None required.
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