ML20080F678
| ML20080F678 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 01/17/1995 |
| From: | Jones T, Ricker J, Vik M NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20080F673 | List: |
| References | |
| NUDOCS 9501300143 | |
| Download: ML20080F678 (105) | |
Text
_
I '-
j NORTHERN STATES POWER COMPANY l
414 NICOLLET MALL MINNEAPOLIS, MN 55401 i
MONTICELLO NUCLEAR GENERATING PLANT OLD HIGHWAY 152 MONTICELLO, MN 55362 REFUELING OUTAGE NUMBER 17 OUTAGE DATES 9-15-94 TO 10-23-94 COMMERCIAL SERVICE DATE JUNE 30,1971 INSERVICE !NSPECTION INTERVAL 3, PERIOD 1
(
CONTENTS i
1.
Summary I
II.
Form NIS-1 Information Ill.
Form NIS-2 Information APPENDICES A.
List of Interval 3, Period 1 inspections by ISO B.
List of Interval 3, Period 1 inspections by ASME C.
List of Interval 3, Period 1 Inspections by inspection Report j
D.
Section XI VT-2 Examinations I
E.
Reactor Vessel Inspections F.
Snubber Inservice Testing i
'?!W Report Date:
Prepared By:
LotOc C
Monica Vik Reviewed By: IMA do4/
Tom Jone f
Approved By: _
Jeff Ricker DO 000 63 i
P PDR
NORTHERN STATES POWER MONTICELLO INSERVICE INSTPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 1.
Summary Page 1 of 2 t
1.0 Introduction r
The seventeenth Monticello refueling outage began September 15,1994 and i
ended October 23,1994.
r in reference to the NRC letter received August 28,1991 from Thomas Ippolito on " implementation of Unresolved Safety issue A-10, BWR Nozzle Cracking" and NSP's submittal of April 22,1985 giving supplemental information related to the inservice inspection examination summary for refueling outage No.10, the following information relating to the feedwater sparger inspection performed during the 1994 Refuel and Maintenance Outage is provided for use by the NRC Staff.
The total number of startup cycles since the last feedwater nozzle surface inspection done during the 1993 refuel outage is six. The total number of shutdown cycles since the 1993 outage is also six.
An on line feedwater nozzle thermal sleeve leak detection system has been used to monitor feedwater nozzle thermal sleeve bypass flow. This system indicates that there is no significant bypass flow and there is no increasing trend on any of the nozzles.
2.0 Personnel Visual and nondestructive examinations were performed by NSP, Lambert MacGill and Thomas and General Electric. Hartford Steam Boiler Inspection and insurance Company provided the Authorized Inspection. Copies of examination procedures, personnel certifications and equipment records are available at NSP.
3.0 Inspection Summary Results of the examinations indicate that the integrity of the plant systems has been maintained.
4.0 Examination Reports, Equipment and Materials Examination reports contain references to procedures, equipment and materials used to completed specific examinations. Copies of the examination reports, examination records are available at Northern States Power Company.
Page 2 of 6
7 NORTHERN STATES POWER MONTICELLO INSERVICE INSPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 1.
Summary (continued)
Page 2 of 2 This Summary report contains several abbreviations which are identified below-BL = Baseline examination GEO = Geometry, evaluation of an indication IND = Indication, requires further evaluation NAD = No Apparent Defects R1, R2 etc. = consecutive examinations following repair, rework or evaluation of an initial exam i
i 1
1 Page 3 of 6
NORTHERN STATES POWER MONTICELLO INSERVICE INSPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 ll.
Form NIS-1 Information Page 1 of 2 Form NIS 1 Owner's Data Report for Inservice inspections (As required by the Provision of the ASME Code Rules) 1.
Owner: Northern States Power Company Address: 414 Nicollet Mall; Minneapolis, MN 55401 2.
Plant: Monticello Nuclear Generating Plant Address: Monticello, MN 55362 3.
Plant Unit: 1 4.
Owner (Certificate of Authorization): -
5.
Commercial Service Date: 6/30/71 6.
National Board No. for Unit: NA 7.
Components inspected:
Manufacturer Commponent or Manufacturer or Installer State or National Appurtenance or Installer Serial No.
Province No. Board No, Reactor Pressure Chicago Bridge B-4697 Vessel
& Iron ASME (See appendices for components inspected this outage )
8.
Examination Dates: 3/26/93 to 10/23/94 9.
Inspection Interval from 6/1/92 to 5/31/02 i
10.
Applicable Edition of Section XI 1986 Addenda -
11.
Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.
See appendices A through F (Attached) 12.
Abstract of Conditions Noted.
See appendices A through F (Attached) 13.
Abstract of Corrective Measures Recommended and Taken.
See appendices A through F (Attached)
Page 4 of 6 l
NORTHERN STATES POWER MONTICELLO INSERVICE INSPECTION
SUMMARY
PrPORT THIRD INTERVAL 1994 ll.
Form NIS-1 Information Page 2 nf 2 We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.
Certification of Authorization No. (if applicable) M Expiration Date M
- 7#64rv57 eros By Itou'4 Mb Date 19 6 Signed Owner P0w6{
CERTIFICATE OF INSERVICE INSPECTION f
and Pressure Vessel ir spectors and tpe State or Proyipce nf P1 uin e s o/rd of 1, the undersigned, holding a valid commission issued by the National Boa hand employed by krtford &n 8delecIrIof bth Go M.
have inspected the components described in this Owners Report during the period Nk'/3 to /0-23-W
. and state that to the best of my knowledge and belief, the l
Owner has performed examinations and taken corrective measures described in this Owners 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 Report. Furthermore, neither the Inspector nor his I
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.
dmM N
Commissions /VA /027V, /W 95-/79 I
' Inspectors Signature National Board, State, Province, i
Endorsements i
l l
l l
l l
Page 5 or6 i
-NORTHERN STATES POWER MONTICELLO INSERVICE INSPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 lli.
NIS-2 Information Page 1 of 1 i
NIS-2 forms are iricluded for the following repairs and replacements:
WRA 94-4825, 94-5070 Removed Surface Indication WRA 94-5502, 5310, 5291 Replaced Bolting i
WRA 93-1806 Replaced Valve MOD 94Q110 CRD Hangers MOD 930305 HPCI & RC!C MOD 930305 MS Valves MOD 93Z026 MS SRVs WRA 94-5281 Replaced Bolting WRA 94-5158 Removed Surface Indication i
i e
I a
Page 6 of 6
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAlRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 1 of 2 As required by the provisions of the ASME Code Section XI, this form SHALL be completed for repairs and replacements at MNGP1 1.
Owner Northem States Power Co.
Date Il-Z8 'Ih Name 2..
Plant Monticello Nuclear Generatina Plant Sheet I
I og Name 2807 W Hwy 75, Monticello, MN lJ 'LA 9 4 - 4 824, 94-6o70 Address 3epair Organization P.O. Na, Job No., etc.
3.
Work Performed By A,>xfa Type Code Symbol Stamp W
Company Name Authorization No.
/
w,. ben Expiration Date h
Address 4.
Identification of System 4 /cu du b hoverf [ d [ek br>r%
l I
I 5.
(a) Applicable Construction Code 831 - l 19.21 Edition, U 7F Addenda, ~ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 19 b 6.
Identification of Components Repaired or Replaced and Replacement Components ASME Code
- Repaired, Stamped Name of Name of Manufacturer National Other Year Replaced, or (Yes or Component Manufacturer Serial No.
Board No.
Identification Built Replacement No) rv W e
RJM-14%E W
tJA WA NA NA fwad Alo Tdl-lU-BE h
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N Description of Work bmrtL) $Yku buba bm1 b W.UM 7.
t 8.
Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure (WM)
Other Pressure PSI Test Temp
- F NOTE 1:
This form may not address all items needed for documentation of a repair / replacement program, see 4 ACD-05.02 for further guidance.
NOTE 2:
Supplemental sheets in form of IIsts, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 11 in, (2) Information in iterns 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
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smygg Resp Supv-SSSE LW I Assoc Rot: SSSE ISR: N Frea: 0 vrs
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Fae' ONLY35 Y ARMS: 3613 IDoc Type:
l Admin initials: CM4, Date: y- //j-9V l/lal
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MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 2 of 2 i
9.
Remarks W e-f Appleable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE l
We certify that the statements made in the report are correct and this Wd l
conforms to the rules on the ASME Code,Section XI.
repair / replacement ub4v h. bW o
Date Ou_ - lb 9h Signed ohm
'19 l
Owner or Owner's Designee, TNie l
{
CERTIFICATE OF INSERVICE INSPECTION I
1, the undersigned, holding a valid commission issyhnne s o rned by the N tional Board of Boiler and Pressure 9
Vesspl Inspeptorspnd the State of,Proyince of /
and employed by Han F Ice-J Slen Bo il' er I(E of & &~ f Fer 1
%m ected the cr. ponents described in this Owner's Report during the have insp/24 /4 3*
3 to
/o/2.J/4 4
. and state that to the best of my knowledge period and belief,'the Owner has performed examinations and taken corrective measures described in this I
Owner's 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 impliod, concerning the examinations and corrective measure described in the Owner's Report.
Furthermore, neither the Inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
/?uxnvt Y/
m l?N YY'l?Y Commissions
/
Inspector's Signature National Board, State, Province, and Endorsements Date C
M1 19 i
l I
1/lal
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 i
REPLACEMENTS - FORM NIS-2 Page 1 of 2 As required by the provisions of the ASME Code Section XI, this form SHALL be completed for repairs and replacements at MNGP1 1.
Owner Northem States Power Co.
Date iI-2 9-9 k Name 2.
Plant Monticello Nuclear Generatino Plant Sheet I
og l
Name 2807 W Hwy 75. Monticello, MN WM q 4 -((o 2., S3 io, 5 2.') l Address Repair Organizatsn P.e-No., Job No., etc.
l 3.
Work Performed By hum Type Code Symbol Stamp dA Company Name Authorization No.
/
4tA ab Expiration Date D
~
Address 4.
Identification of System b krh NW (a) Applicable Construction Code U.L. k 19')3. Edition, W ~7 A ~ Addenda, ~~
Code Case 5.
(b) Applicable Edition of Section XI Utilized for Repairs or Replacement 19 No 6.
Identification of Components Hepaired or Replaced and Replacement Components ASME Code
- Repaired, Stamped Name of Name of Manufacturer National Other Year Replaced, or (Yes or Component Manufactt.Ter Serial No.
Board No.
Identification Built Replacement No)
D$
PA tJA tJ A IJ A-tJA u,Lud
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A Description of Work OnlanM beb, eta p# N 600 dN4 kutubwe, reuk 7.
(~tp' W t-t[Jp)Hb't0 LM., rvplate itR1 JW av 4* Wk 4
8.
Tesus Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure Other Pressure PSI Test Temp
- F q%p,
NOTE 1:
This form may not address all items needed for documentation of a repair / replacement program, see 4 ACD-05.02 for further guidance.
NOTE 2:
Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 11 in, (2) Information in items 1 through 6 on this 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.
Ai Resp Supv-SSSE UV l Assoc Ref: SSSE ISR: N Frea: 0 yrs arves N
"' e " M.. vysagg d 0ftf,yAmse ARMS: 3613 l Doc Type:
l Admin initials: (L(4 Date: 9-///- 9V I/lal
i MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 2 of 2 9.
Remarks ThDL Me (Mulw ukhoMA (meDmt8 uNeL A
$ppleable Manufacturer's Data Rep 6rts to be attachebINMh tub l HLh lt)$ lN (FY kc.
ra L h1%m L
Lu) k J SLe L LLL [> m A m.
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I CERTIFICATE OF COMPLIANCE MMm*k We certify that the statements made in the report are correct and this conforms to the rules on the ASME Code,Section XI.
rephir/ replacement
~
Signed O/m
% Eum oate k I4
' is 4 4-Owner or Owner's Designee, Title l
CERTIFICATE OF INSERVICE INSPECTION I
1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure P
M /th e s o fx.-
and employed t rs a d the State or$ vin e of Vesselinsp S' feo m Irr of H m. H o,. J, ((e n n by H c
e the components describpd in this Owner's Report during the have ins /pectecj 3 24/93 to /o/> 7/4#
.and state that to the best of my knowledge period and belief', the Owner has performed e'xaminations and taken corrective measures described in this Owner's 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, conceming the examinations and corrective measure described in the Owner's Report.
Furthermore, neither the inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a lots of any kind arising from or connected with this inspection.
b?/Y YY~I?Y nem Commissions
/
Inspector's Signature National Board, State. Province, and Endorsements Date N 22 19 1/lal
MONTICELLO NUCLEAR GENERATING PLANT 3613 i
TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 l
REPLACEMENTS - FORM NIS-2 Page 1 of 2 l
f As required by the provisions of the ASME Code Section XI, this form SHALL be completed for repairs and replacements at MNGP1 i
1.
Owner Northern States Power Co.
Date l l - 7A
- f h Name I
2.
Plant Monticello Nuclear Generatina Plant Sheet I
og Name l
2807 W Hwy 75. Monticello. MN w/RA C s - Ip,o (o 1
l Address Repair Organization P.O. Sb., Job No., etc.
3.
Work Performed By 6Ww Type Code Symbol Stamp M
Company Name Authorization No.
/
%aM Expiration Date k
4.
Identification of System Nmh krWDw b bt~ b
% 45*
5.
(a) Applicable Construction Code Ml 19 22 Edition, W 7 6 Addenda, - Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 19 I6 6.
Identification of Components Repaired or Replaced and Replacement Components ASME Code
- Repaired, Stamped Name of Name of Manufacturer National Other Year Replaced, or (Yes or Component Manufacturer Serial No.
Board No.
Identification Built Replacement No)
Mo-?o%
WA tJA N A-tJ A-
^>A rdJ Alo
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l X
/
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Description of Work bdurO MO-7ML; ldKl Torb Wo dam MainfahYA_lvc 7.
Pneumatic 0 NominalOperating Pressure @ (tJ-4 Il< f f DI) 8.
Tests Conducted: Hydrostatic Ofher Pressure PSI Test Temp
- F NOTE 1:
This form may not address all items needed for documentation of a repair / replacement program, see 4 ACD-05.02 for further guidance.
NOTE 2:
Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 11 in, (2) Information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the 7
number of sheets is recorded at the top of this form.
Ai irvre ADWNssusATIVE Resp Supv-SSSE LW l Assoc Ref: SSSE i SR: N Frea: 0 yrs c NUSE OfnYs' 24 ARMS: 3613 l Doc Type:
l Admin initiah: (14 Date: y //p-9t/
I/lai
MONTICELLO NUCLEAR GENERATING PLANT T'
3g33
\\
TITLE:
OWNER'S REPORT FOR REPAIRS OR
. L., vision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 2 of 2 9.
Remarks kM
~
Appkcable Manufacturer's Data Reports to be attached l
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this r<0Ltastd conforms to the rules on the ASME Code,Section XI.
repdir/ replacement r bkAwto Date bb N
Signed 1A M
'19 Owner or Owner's Designee,' Title l
CERTIFICATE OF INSERVICE INSPECTION I
I, the undersigned, holding a valid commission issued by the Nptional Board of Boiler and Pressure Vesse, ) insppgtors pnd the State oA royince of /b nrAora and employed P
by Har t f er d Steam Deiler of HerHerJ &u have inspected the components described in this Owner's Report during the f 27/f f
. and state that to the best of my knowledge
/
3 2/,/43 to d
period and belief,'the' Owner has performed examinations and taken corrective measures described in this Owner's 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, conceming the examinations and corrective measure described in the Owner's Report.
Furthermore, neither the Inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
hn, Commissions NM Y
'/7k' inspector's Signature National Board, State, Province, and Endorsements Date C
sd 19 1
1/lal
~~
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 i
REPLACEMENTS - FORM NIS-2 Page 1 of 2 As required by the provisions of the ASME Code Section XI. this form SHALL be completed for repairs and replacements at MNGP1 1.
Owner Northem States Power Co.
Date f "L-I
'I h Name l
I 2.
Plant Monticello Nuclear Generatina Plant Sheet 1
og Name 2807 W Hwy 75. Monticello. MN Mob 9/G iIO Address Repair Organization PO-No., Job No., etc.
3.
Work Performed By neu Type Code Symbol Stamp Company Name Authorization No.
504 abM Expiration Date Address Identificationof System bndrei M 0,e 9 r-D,9Lp Wu-4.
5.
(a) Applicable Construction Code MI, (
19 22 Edition, W 'l f0 Addenda, '
Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 19 O _-
6.
Identification of Components Repaired or Replaced and Replacement Components ASME Code
- Repaired, Stamped i
Name of Name of Manufacturer National Other Year Replaced, or (Yes or Component Manufacturer Serial No.
Board No.
Identification Built Replacement No) 01:%
N0 NA AI A FA trolwm d I
l bo
- dto1, b
f V
f b roha..,J slo
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Description of Work McMa< comb bMG M rdbh Uf { bud b NM 7.
144%W c% OS d$h W3 w 8.
Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure bk Other Pressure PSI Test Temp
- F NOTE 1:
This form may not address allitems needed for documentation of a repair / replacement program, see 4 ACD-05.02 for further guidance.
MQIE2:
Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 11 in,(2) Information in items 1 through 6 on this report is included on each shoot, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Ai true ADIEPesot=nisyii IResp Supv-SSSE UV I Assoc Ref: SSSE l SR: N Frea: 0 yrs
- sqg gyW TIARMS: 3613 l Doc Type:
1 Admin initials: UA4.-
Date: y- ///- yy 1/lal
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 2 of 2 9.
Remarks hM Appleable Manufacturer's Data Reports to be attached I
l l
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this habu*
l conforms to the rules on the ASME Code,Section XI.
repair / replacement N b4W Date b
No
,i9 9h Signed M
Ad Owner or Owner's Designee, Titid l
CERTIFICATE OF INSERVICE INSPECTION I
I, the undersigned, holding a valid commission issued by the fjational Board of Boiler and Pressure i
Vess.eJ insp9ctors and the State of Province of Mmn <3 o r 4 and employed by Marticed
.5 tea m EcHer E rf of Haw Hal.Ec u have inspected the components described in this Owner's Report during the period 37z4 h3 to /0/z3 A /
. and state that to the best of my knowledge and belief,' the 'O'wner has performed examinations and taken corrective measures described in this Owner's 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, conceming the examinations and corrective measure described in the Owner's Report.
I Furthermore, neither the inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
/ M/ N-/ 7 h
Commissions 7
Inspector's Signature National Board, State, Province, and Endorsements Date C
S Y
19 I
1/lal l
l 1l l
l R ____ _
j
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAlRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 1 of 2 As required by the provisions of the ASME Code Section XI, this form SHALL be completed for repairs and replacements at MNGP1
( l
'2. 0 - 9 h 1,
Owner Northem States Power Co.
Date I
Name 2.
Plant Monticello Nuclear Generatina Plant Sheet i
og
\\
Name 2807 W Hwy 75, Monticello, MN Me) 'T 3G 3o E oLAk H-G31, Gr3t.
Address Repair Organization f%-No., Job No., etc. ~
3.
Work Performed By Oum Type Code Symbol Stamp MA Company Name Authorization No.
I bu edtev-t-Expiration Date b
Address 4.
Identification of System @C l I kC(f SW~r&
I s
5.
(a) Applicable Construction Code MI I 19.23 Edition, W 7 6 '
- Addenda, Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 19 Y/o 6.
Identification of Components Repaired or Replaced and Replacement Components ASME Code Repaired.
Stamped Name of Name of Manufacturer National Other Year Replaced, or (Yes or Component Manufacturer Serial No.
Board No.
Identification Built Replacement No)
(%-l'\\ -<- Eo h)A h/ 4
&A hl A Sh ontwl) do K-IP-9"- Eb k/
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Description of Work OLW OfWIn[hN54WA tk &f @If aim lo aS#
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M klW S rg two o u t4W m,sys,
' I i
8.
Tests Conducted: Hydrostatic Pnedmatic NominalOperating Pressure S Other Pressure PSI Test Temp
'F NOTE 1:
This form may not address allitems needed for documentation of a repair / replacement program, see 4 ACD-05.02 for further guidance.
NOTE 2:
Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 11 in,(2) Information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of shoots is recorded at the top of this form.
Ai ervetE Iruus,ii Resp Supv: SSSE UV l Assoc Ref: SSSE ISR: N Frea: o yrs miggg ggggyser > -
ARMS. 3613 IDoc Type:
l Actmin initials: (MAlL.
Date: y- ///- 9y 1/lal
1 MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 2 of 2 9.
Remarks aa Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPUANCE We certify that the statements made in the report are correct and this Mm I
conforms to the rules on the ASME Code,Section XI.
repair / replacement
$.. b%&
Date b Ib N
Signed im Au
<o
'19 Owner or Owner's Designee, TRie l
CERTIFICATE OF INSERVICE INSPECTION I
1, the undersigned, holding a valid commission issued by the Ngtional Board of Boiler and Pressure Vessej inspeptors and the State 97 Province of P7#nn m ofn and employed by Har Her d Sfam Re.;/e<~ Irr of Ha e f f e r al lo nn descri ed in this Owner's Report during the have inspected the components /23/4f period 3/24 /43 to /o
.and state that to the best of my knowledge and belief, the ' Owner has performed examinations and taken corrective measures desenbod in this Owner's 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, conceming the examinations and corrective measure described in the Owner's Report.
Furthermore, neither the inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
nwnvf Md bM W-N Commissions Inspector's Signature National Board, State, Province, and Endorsements W
M Date
/
1^
19 t/lal
MONTICELLO NUCLEAR GEKdNATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 1 of 2 As required by the provisions of the ASME Code Section XI, this form SHALL be completed for repairs and replacements at MNGP1 I l-7A - 9 h 1.
Owner Northern States Power Co.
Date Name 2.
Plant Monticello Nuclear Generatina Plant Sheet l
og
/
Name 2807 W Hwy 75, Monticello, MN
% J t)3(D3oC Address Repair Organization PO-No., Job No., etc.
3.
Work Performed By /h&
Type Code Symbol Stamp MA Company Name Authorization No.
/
Cu n b c,4 Expiration Date U
Address 4.
Identification of System M., m Nw S.
(a) Applicable Construction Code P> 3 I + \\
19.22. Edition, M1 R
- Addenda, Code Case
~
(b) Applicable Edition of Section XI Utilized for Repairs or Replacement 19 %
6.
Identification of Components Repaired or Replaced and Replacement Components ASME Code
- Repaired, Stamped Name of Name of Manufacturer National Other Year Replaced, or (Yes or Component Manufacturer Serial No.
Board No.
Identification Built Replacement No) ho-2A%P $
IM
/J &
NA NA r4Lw++
Mo
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wz-% f, Ao R c As-t-St D W
W l/
V V
V V
7.
Description of Work olauOmNvwwd M4iW l
8.
Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure tu h e/
f Other Pressure PSI Test Temp
'F NOTE 1:
This form may not address allitems needed for documentation of a repair / replacement program, see 4 ACD-05.02 for further guidance.
NOTE 2:
Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 11 in,(2) Information in items 1 through 6 on this 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.
Ai t yveg ADBWessinATIVE Resp Supv-SSSE L.W I Assoc Ret: SSSE lSR: N Frea: 0 vrs 1
' %USE 0ffLY Je ARMS: 3613 IDoc Type:
l Admin initials: 844.-
Date: y - /(f - 9</
j 1/lal l
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 2 of 2 9.
Remarks tw-Apphcable Manufacturer's Data Reports to be attached
(
CERTIFICATE OF COMPLIANCE Me umad We certify that the statements made in the report are correct and this conforms to the rules on the ASME Code,Section XI.
rephir/ replacement Date 04- /b 9h Cr b tx e_ea Signed A zn1
'19 Owner or Owner's Designee, Tdle l
l-CERTIFICATE OF INSERVICE INSPECTION I
1, the undersigned, holding a valid commission issued by the N tional Board of Boiler and Pressure 9
Vess9 nspectorp and the Statp orJ'rovince of
/% nn r3 o f a and employed 1I by Hart Ic.-J Steen (S o,'ir e Trr of Ha r i fc 1 _ Evnr1 have ins ectpd the components describpd in this Owner's Report during the period f /,/43 to /Od1/4 F
.and state that to the best of my knowledge and belief, the' Dwner has performed examinations and taken corrective measures described in this Owner's 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 1
implied, concerning the examinations and oorrective measure described in the Owner's Report.
i Furthermore, neither the inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
J f
b N Y*llY Commissions n1 err Inspector's Signature National Board, State, Province, and Endcrsements 0PC ]S Date 19 i
l/lal
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 1 of 2 As required by the provisions of the ASME Code Section XI, this form SHALL be completed for repairs and replacements at MNGP1 l
1.
Owner Northem States Power Co.
Date 17 -l Cih Narne 2.
Plant Monticello Nuclear Generatina Plant Sheet I
og l
Name 2807 W Hwy 75. Monticello, MN 4 7't o L 6 I
3 Address Repair Organization P.O..h, Job No., etc.
l 3.
Work Performed By De bk bA Type Code Symbol Stamp M
Company Name I
Authorization No.
/
banM hk i bJ Y Expiration Date 6
~
Addr6ss 4.
Identification of System $
4b N b eom M
- o-l 5.
(a) Applicable Construction Code M \\.I 1913 Edition, kl7 A ~ Addenda, '~ Code Case f
(b) Applicable Edition of Section XI Utilized for Repairs or Replacement 19 6
i 6.
Identification of Components Repaired or Replaced and Replacement Components ASME i
Code
- Repaired, Stamped Name of Name of Manufacturer National Other Year Replaced, or (Yes or Component Manufacturer Serial No.
Board No.
Identification Built Replacement No) 4Rv' b ed-b b l'L2.
AlA A/4 M rerbewd Mo 5 AN' V-e &
lY blAr AJA
% adwad bio
\\
/
X
/
N Description of Work bb>O bb*d ( M ld $#M ia b bot &[4.G MMM lt-eA 7.
n iI s
8.
Tests Conducted: Hydrostatic O Pneumatic Nominal Operating Pressure Other Pressure PSI Test Temp
- F NOTE 1:
This form may not address allitems needed for documentation of a repair / replacement program, see 4 ACD-05.02 for furthcr guidance.
NOTE 2:
Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 11 in,(2) Information in items 1 through 6 on this 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.
Ai a rvet AUREPs sstsATIVE Resp Supv:
SSSE LW I Assoc Ret: SSSE l SR: N Frea: 0 yrs i
swggg g yy c
- ARMS: 3613 IDoc Type:
l Admin Initials: h Date: y-/&-9y I/lai i
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 2 of 2 Nob Nd H DN Ao d 14 4 W $11 L~
9.
Remarks Applicab e Man acturer's Data Reports to be attached a ~
ur dme vi A Am LIE '/J EJ W /d A_l, / vow,
4b rim 4 x 4 ffac 00 4o t s 63 I. l.
' I J
8 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R4 b
conforms to the rules on the ASME Code,Section XI.
rebair/ replacement
. EMMA b fb 9h Signed h
A/11 s
Date
- 19 Owner or Owner's Designee, istle l
CERTIFICATE OF INSERVICE INSPECTION I
1, the undersigned, holding a vald commission issued by the National Board of Boiler and Pressure Vossql inspectorp and the Statq or Province of Minn e s o f n and employed by Hun f hrE 5% m 16citee Irr of Hu e Hs A Conn have insp9cted the components des.critjed in this Owner's Report during the and belief,/zu93 period 3 to /o/c? /44
.and state that to the best of my knowledge the Owner has performed dxaminations and taken corrective measures described in this
~
Owner's 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, conceming the examinations and corrective measure described in the Owner's Report, i
Furthermore, neither the inspector nor his employer SHALL be liable in any manner for any personal I
injury of property damage or a loss of any kind arising from or connected with this inspection.
)
NM W~ / 7
[
Commissions r o vim inspector's Signature National Board, State, Province, and Endorsements Date fC A1 19 I/lai
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FL 9 REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 1 of 2 As required by the provisions of the ASME Code Section XI, this form SHALL be completed for repairs and replacements at MNGP1 1.
Owner Northem States Power Co.
Date
/ 'Z - /
- 1 h Name 2.
Plant Monticello Nuclear Generatino Plant Sheet I
og l
Name 2807 W Hwy 75, Monticello, MN WD.A4d-O8l Address Repair Organization PO-No., Job No., etc.
3.
Work Performed By Sha Type Code Symbol Stamp d
Company Name Authorization No.
/
'h u a ($-thef--
Expiration Date M
Address 4.
Identification of System k b tre v I b r
5.
(a) Applicable Construction Code b \\ 19 33. Edition, W'? 8 Addenda.
Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 19 b 6.
Identification of Components Repaired or Replaced and Replacement Components ASME Code
- Repaired, Stamped i
Name of Name of Manufacturer National Other Year Replaced, or (Yes or Component Manufacturer Serial No.
Board No.
Identification Built Replacement No)
J hA NA udw..&
l
% m k. J AJ A
&A (J A fo
\\'
/
V/\\
/
\\
Description of Work k4bu bo S m W Ar ( L4 [Su r%Ju )
7.
I I a
8.
Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure i
fd b Other Pressure PSI Test Temp
- F NOTE 1:
This form may not address allitems needed for documentation of a repair / replacement program, see 4 ACD-05.02 for further guidance.
NOTE 2:
Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 11 in, (2) Information in items 1 through 6 on this 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.
Ai
- Fvet AIMWessiswWE. Resp Supv-SSSE LW l Assoc Ref: SSSE lSR: N Freq: 0 yrs
/' L U$E CWLY@#@ ARMS: 3613 IDoc Type l Admin initials: C%4, Date: y ///-9y 1/lai
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 2 of 2 b DI& dAwdnIs ertav A u h b b (4NtiA l
9.
Remarks c et o L 4 c ]IL w & ruLta Replorts to tie attachedA n w /% A,I I
plicable Manufadturer's D I
e AtL. 7% ck wa dsasst,La k d% u rs' Tun d& ud0. 75 bolk (~n-shkD) ML L %
\\ & N $ Y 40 )22.
l.a.c s.0 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this W b mM conforms to the rules on the ASME Code,Section XI.
repdir/ replacement b Aler ce Date OI<- b 9
Signed A
J J
r
- 19 Owner or Owner's Designee, Titib l
CERTIFICATE OF INSERVICE INSPECTION I
I, the undersigned, holding a valid commission issued by the Nptional Board of Boiler and Pressure VesseJ Inspeptorspnd the State or Province of F7 m n r".s o T 4 and employed by Hav t {e r& Stnm 13 sihr I (I' of Hartfee d Eonn have insoectect the components descriged in this Owner's Report during the period i/24 /4 3 to /0/23 /4f
.and state that to the best of my knowledge and belief, the Owner has performed bxaminations and taken corrective measures described in this Owner's 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, conceming the examinations and corrective measure described in the Owner's Report.
Furthermore, neither the inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
/U Y /-/74/
l me Commissions i
Inspector's Signature National Board, State, Province, and Endorsements Date C
19 1/lai
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 1 of 2 As required by the provisions of the ASME Code Section XI, this fctm SHALL be completed for repairs and replacements at MNGP1 1.
Owner Northem States Power Co.
Date lI-1 % 9 h Name 2.
Plant Monticello Nuclear Generatina Plant Sheet
/
l og Name 2807 W Hwy 75, Monticello, MN y (2-A ci 4 - ( / 5 B Address Repair Organization PO-No., Job No., etc.
3.
Work Performed By O Ato Type Code Symbol Stamp A/ A Company Namo Authorization No.
/
W n be Expiration Date M
~
Address 4.
Identification of System
$b) b bt<m e d Abv i
0 5.
(a) Applicable Construction Code SM, I 19 ~1'7 Edition, h/ 1R ' Addenda, ' Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 19 Do 6.
Identification of Components Repaired or Replaced and Replacement Components ASME Code
- Repaired, Stamped Name of Name of Manufacturer National Other Year Replaced, or (Yes or Component Manufacturer Serial No.
Board No.
Identification Built Replacement No)
W AA N
blA rem o
C4 E-l'/t -DC
/dA M
I N
/
N/
/\\
/
\\
7.
Description of Work OA beb 6duab bwh I1] Y 8.
Tests Conducted: Hydrostatic Pneumatic NominalOperating Pressure %
Other Pressure PSI Test Temp
- F NQIE.1:
This form may not address all items needed for documentation of a repair / replacement program, see 4 ACD-05.02 for further guidance.
NQIEl:
Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 11 in, (2) Information in items 1 through 6 on this 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.
l Ai 4yvsq ADMpssggesnupf5: Resp Supv: SSSE L)4/
l Assoc Ref: SSSE lSR: N Frea: 0 yrs gr <3ggg M V;gsig ARMS: 3613 l Doc Type:
l Admin initials: M4-Date: 9-///- W 1/lal
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE:
OWNER'S REPORT FOR REPAIRS OR Revision 1 09/15/94 REPLACEMENTS - FORM NIS-2 Page 2 of 2 9.
Remarks M-Apphcable Manufacturer's Data Reports to be attached 1
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this IN M
confomis to the rules on the ASME Code,Section XI.
repair / replacement Fbm W be 9
Signed BM 4
A Date
'19 Owner or Owner's Designee, l'itle l
CERTIFICATE OF INSERVICE INSPECTION I
i I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inrnectors and the State or Province of Minnr<nf4 and employed by Ha % ) Stean (bnile c ZrE of Ha < l fo< d Pnmn describ d in this Owner's ' Report during the have inspecte I the components /13 /#+9
. and state that to the best of my knowledge period J/16 /4 3 to /0 and belief, the Owner has performed examiriations and taken corrective measures described in this Owner's 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, conceming the examinations and corrective measure described in the Owner's Report.
Furthermore, neither the inspector nor his employer SHALL be liable in any traner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
MM W - / 79' Commissions rum
(>~
Inspector's Signature National Board, State, Province, and Endorsements bC 21 Date 19 1/lal
NORTHERN STATES POWER MONTICELLO INSERVICE INSPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 Appendix A List of Interval 3, Period 1 Inspections Sorted by ISO (pages 1 through 23) t I
4 l
l l
[
l s
l I
'l Monticello Nuclear Generating Plant Inservice Inspection Report 1,og Northern States Power Company I
old Ewy 152 NW of Monticello Third Interval By Iso / Item die Nicollet Mall monticello, MN $5362 Cosearcial Service Dater June 30, 1971 Minneapolis, MN 55401 180 Item Report Number Method Results System Item Description Exam Date ASME Section XI Item ISI-13142-17-A H-2 94-0013 VT3 IND RER Suction A slide / Clamp 08/04/94 P-A,B,C Missing weep hole.
1$1-13142-17-A H. 2 94-0013R1 VT3 NAD~
RHR Suction A Slide / Flamp 10/07/94 P-A,B,C Reworked
'fS1 M i42'-17!A
'H-9 94-0011 VT3
~ (D~
2 1)
PHR Suction A Slide 08/04/94 F-A,B,C Thread engagement and missing I
weep hole.
l 1SI-13142-17-A H-9 94-0011R1 VT3 l 1ND RHR Suction A Slide 10/07/94 F-A,B,C Reworked weep hole, thread l engagement remains.
ISI-13142-17-A H-9 94-0011R2 VT3 NAL RHR Suction A slide
/ /
F-A,B,C Use-as-is w/ Technical Justification.
j '9476 N
'MT NAD ISI-13142-17-A W-5 RHR Suetion A Pipe-to-Weldolet 08/08/94 C 5. 81 ISI-13142-17-A l w 14 N 47 d31 MT NAD j
RRR Duction A l Elbow-to-Elbow 08/08/94 C b. 51 l
1sg!h j 4 F3 7'ZA-
~ --* w.24 94-0050 UT45 NAD RHR Suction A Elbow to-SIbow 08/10/94 C 5.
51 ISI-13142 17 C H.
4 94-0059 VT3 NAD RHR Suctio-! B Slide 08/17/94 F-A,B,C i
IS!-13142-17 C H-5 94-0060 VT3 NAD RHR Suction B Strut / Clamp 08/17/94 F-A,B,C j
ISI-13142-17-C
~
HI9 94TDON VT3
-~NA6--
RHR Suction b
- Db1 Strut / 8 Lugs 08/17/94 F-A,B,C C 3.20 NTD0D MT
'NAD i H '9' 2
ISI-13142-17-C RHR Suction B lDb1 Strut / 8 Lugs 08/19/94 F-A,B C C 3.20 M1 - 1314 2 A
- HG 94-0347 VT3 NND~
RHR Djecharge B l St rut / Clamp 10/04/94 P-A,B.C
_+
3 kHR Discharge B Db1 Spring / 4 Lugs 10/11/94 P-A,B,C C 3.20
[
ISI-13142-18-A Welded lugs not on dwg.
H-9 94-0220 MT NAD f
RHR Discharge B Db1 Spring / 4 Lugs 09/26/94 F-A.B,C C 3.20 Limited due to support acceau l
restriction.
I PHR Discharge B J Db) Spring / 4 Lugs
/ /
F-A,B,C C 3.20 i
l Use-as-is w/ Technical
{
Justificatic.1
'151 O~14f~iG A'~ ~
!H-10
~'
94-0078~
VT3 IND RHR Discharge B fSpring/ Clamp / Slide l09/01/94 P-A,B,C
} 94~0Cifk1~
VT3 NAD Extra hot and cold tags.
1 1rIT'3j42'-1B A- ~ ~
} H 10 I
~ T RHR Discharge B
} Spring / Clamp / Slide 10/11/94
-A,B,C P
.--..~. 4 Reworked 1
RHR Di.scharge B lSeismicRestraint 08/02/94 F-A.L.C l
RHR Discharge B ITee-to-F1pe l 08/12/ 94
' C 5. 51 i
-._.u._---
i 01/17/95 Page 1
s h
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company old Ewy 152 Nw of Monticello Third Interval By Iso / Item 414 Nicollet Mall l
Monticello, aos $53s2 Commeretal service note: June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results Rystem Item Description Exam Date ASME Section XI Item 3SI-13342-18-A W-14 94-0055 UT45 NAD RRR Discharge B Tee-to-Pipe 08/15/94 C 5. 51 ISI-13142-18 A W-22
- ~I94-0041 WT NAD RHR Discharge B Pipe-to-Elbow 08/12/94 C 5. 51 ISI-if142-18-A W-22 94-0056 UT45 NAD RHR Discharge B Pipe-to Elbow 08/15/94 C 5. 51
.-..---A I
RHR Discharge B Variable Clarp 08/25/94 F-A,B,C
.g RHR Discharge B Strut / Clamp 08/17/94 P-A,B,C JSI-13342-19-A H-1 94-0007
~~ VT3 NAD
~
~
I 08/02/94 F-A,B,C HPCI Steam Disch Snubber / Clamp 1SI-13142-19-A H-94-0066 VT3 '
NAD HPCI Steam Disch i-nubber / Clamp 08/22/94 F-A,B,C 7 668'
~~tTT4 5' NAD--
ISI-13142-.19-A W-7
~~-
94 0 ~
HPCI Steam Disch Pipe-to-Elbow 08/22/94 C 5. 51 f
ISI-13142-19-A W-7 94-0067 MT NAD l
HPCI Steam Disch Pipe-to Elbow 08/22/94 C 5. 51 ISI-13142-20-A H-3 94-0421BL VT3 IND r
Core Spray B Snubber 10/21/94 P-A,B,C ISI-13142-20-A H-3 NT042iBI.R1
~ ~ ~ - - - 'N b~ '
/ /
F-A,B,C USE AS IS W/ TECHNICAL L
JUSTIFICATIDN l
ISI-13142-20-B H-1 94-0003
' VT 3'
[NAD~-
Core Spray A Variable 08/01/94 P-A,B,C ISI-13142-20-B H-3 94-0335BL VT3 NAD l
Core Spray A Snubber / Clamp 10/03/94 F-A,B,C 2SI-13142-20-B
'W-1 94-0081 MT IND i
Core Spray A l Torus Penn-to-Bibow 09/16/94 C 5. 51 Two linears.
ISI-13142-20-B "W-1 94-0084
- UT45 NAD
^
Core Spray A Torus Penn-to-Elbow 09/16/94 C 5. 51
~"i W-1 94-0001R1 MT NAD ISI 13142-20-B i
Core Spray A iTorus Penn-to-Elbow 09/28/94 C 5. 51 l
i Reworked
_-g l
Core Spray A Pipe-to-Elbow 09/16/94 C 5. 51 151-13142-20-9 W-4 94-0083 ITT45 NAD Core Spray A Pipe-to-Elbow 09/16/94 C 5. 51 ISI 13142 26 B'~~
~ ~ M W-23 94-0069
' ' MT NAD 2
Core Spray A Elbow to-Pipe 08/23/91 C 5. 51 1
IS1 '3142'-20-B~
~~~1
~ ~
- 94-0076 IJT45
[NAD-~
11 W-23 Core Spray A Elbow-to-Pipe l08/'5/94 C 5. 51 l
i Limited due to configuration.
.._.d...~.___
- W-27
'94;bO70 l MT NAD
]
Core Spray A jElbow-to Pump 08/23/94 C 5.
51 t
i W 27~"
~~ ~
94-0075 ~ ~ ~ ~~ tTT4 5~~~~~~~~~'~~~~~~""GEO~
i
~
ISI-13142-26-B~
Core Spray A lElbowto-Pump 08/25/94 C 5. 51
(
l Limited due to configuration 01/17/05 Pt.Je 2
i e
ganticalls Lelaar C.anatatir.g Flar.t Isaazvica Isanctice Kapost Log Nos tsern stat % sover Company Old Bwy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, MN 55362 Commercial Service Dates June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results System Item Description Exam Data ASMR Section 11 Item 181 13142-26-A B-1 96-0193 VT1 IND Core Spray A Valve Bolts 05'25/94 B7 70 Examined in place.
Inadequate thread engagement.
'isf'~1h42-26 A B-1 94-0193R1 VT1 NAD Core Spray A Valve Bolts
/ /
B 7. 70 Use-as-is w/ Technical Justification.
IS1!I3i42226A' ~ ~ ~
B-2 94-0194 VT1
[ NAli~
core spray A valve Bolts 09/25/94 B7 70 mn n place.
._,_n, Core Spray A Valve Int surfaces 10/10/94 B12. 50 Isi!13142 26 A W-13 94-0157
'PT
~NAD Core Spray A Pipe-to-Valve 09/23/94 8 9. 11
-,-_._....q Core Spray A Pipe-to-Valve 09/23/94 8 9.
11 Limited due to configuration.
ISI-13142'-26 A W+14 94-0150
' ' PT
~~ ~ ~~~'~- ^
NAD Core Spray A Valve-to-Pipe 09/23/94 9 9. Il j
ISI-13142-26 A W-14 94+0148 ITT4 5 NAD Core Spray A Valve-to-Fipe 09/23/94 9 9.
11 Limited due to configuration.
ISI 13142-31-A
} B- 'l
~ '94'-0139 VT1
' NAD i
Core Spray B Valve Bolts 09/22/94 B 7. 70 Core Spray B Valve Int Surfaces 09/22/94 B12. 50 t
,. 7 l
- ~ _. - - _
-..-.4 Core Spisy B Bent Pipe / Safe End 09/25/94 B 9, 11 i
s.
.- ~ - -- ~--~
- - - - ~ - - -
. - - - ~ ~. - - - ~ ~,
-e-----~----
Core Spray B Bent Pipe / Safe End 09/26/94 9 9. 11 l
ISi-13142-31-A W-15 94-0148 MT
^ ~ ~ - ~
'NAD~
~
Core Spray B Safe End-to-Nossle 09/25/94 B 5. 10 ISt ~5i42-31-A
~~
W 15 94-0101 UT45' NAD 1
~
. Safe End-to-Nozzle 09/26/94 B 5. 10 l
Limited due to configuration.
IS1-13142-33 A B-1 94-0378BL VT1 IND i
Main Steam A Flange Bolts e W-12 10/OR/94 87, 50 Examined in places Thread engagement.
.. - ~... -- 4 Main Steam A Flange Bolts e N-12
/ /
B 7.
50 Use as is w/ Technical Justification.
g g t.1314 2 ' 3 3 - A' ~ - ' ~ ~ ~ ~
~ BT f " ~~~ ~ ~ ~ ~ '
94-0380BL VT1 NAD Main Steam A Flange Bolts e W-16 10/08/94
- 97. 50 i
Examined in place.
1st-13142-33-A B-S 94-0373BL VT1 NAD J
Main steam A Valve Bolts 10/06/94 87 70 Examined in place.
ISt-'ili42 33; f~~
TB-9
~94-03798L VTi ' ~ -~~ ~ ~ ~ ~~ ~ ~~~~NAD~
Main Steam A Valve Bolts 10/08/94 9 7. 70 l
Examined in place.
T )811L ~
] in T1~
~ ~ ~ ~ ~ ' - ~ ~ ~
'NAD~~
151 1314273)
A~~
~
~
B 10 ~
" 94 C
Main Steam A Valve Bolts 10/08/94
!B7 7D l Examined in place.
Isi;'i3142 13-A'
~ ~ " ~ ' HT~1 ~ ~ ~
~~ ~ ' '
~,
~~ ~
l'VT)"
~~ ~ ~ ~ ' ~ ~ '
~
IND
~
94-6221
! outle Spring /4 Lugs 09/25/94 lF-A,B,C D
B10.10 Main Steam A
_.-_1. _ ____ _. _. ] Thread engagement.
01/17/95 Page 3
1
e Monticello Nuclear Generating Plant inservice inspection Report Log Northern States Power Company Old Bwy 152 NW of Monticello Third Interval By 1so/ Item 414 Nicollet Mall Monticello, MN 55362 Comunercial Service Date June 30, 1971 Minneapolis, ICS 55401 ISO item Report Number Method Results system Item Description Eaam Date ASME Section X1 Item 1S1-13142 33-A H-1 94-C221R1 VT3 lNAD Main Steam A Double Spring /4 Lugs
/ /
F-A,B,C B10.10 l
Use-as-is w/ Technical Justification.
Main Steam A Snubber / Clamp 10/05/94 F-A,B,C
.. _... _ -.. ~..
Main Steam A Snubber / Clamp 09/21/94 P A,B,C
-Ig{J13142O 3 A~ " ' ' ~ ~ ~
H"- 4 " ~ ~~~
' ~ ~ ~ ~
'94-0126 VT3 IND Main Fteam A Varible / Spring 09/21/94 F A,B.C
~
H
~
Drawing compliance,
"!S! ijl42 33 A"-~~
'-~4' J ~~ ~~
~ ' ~ ~
~
94-6126R1 VT3
~
~^~
NAD~
Main Jteam A Varible / Spring
/ /
F-A,B,C Use-as is w/ Technical Justification.
IS1 13142-33 A H-7 94'-0353BL VT3
~~'~NAD~~
Main Steam A Snubber / Clamp 10/05/94 F A,B,C ISI-13142-33 A V-3 94-0414 VT3 NAD Main Steam A Valve Int Surfaces 10/06/94 B12. 50 ISI 13142-33 A V-4 94-0324BL VT3
'NAD
~
Main St eam A Valve Int surfaces 10/04/94 B12. 50 ISI-13142-33-A W-1 LS T1 94 0107 MT NAD Main Steam A Nossle-to-Safe End 09/20/94 B 9. 10 94 0226~~
~ ~ ~ " t7f 4 5 '- ~ ~~~~ - ^ --
'NAD^^
ISI-13142-33 A' Wi 1 1,6 D
~ ^ ~ ~
I k
Main Steam A Nortle-to-Safe End 09/26/94 B 9. 10
'
- W I ' LS U~
~ ~ ' ' ~ ~ -'
' 94-620f ~ ~ ~ "
NT"
'-~~ ~'~~~'
NAD -
Islil?14213s-A~~
2 Main Steam A Saf e End-to-Elbow 09/20/94 B 9.
10 ISI-13142-33-A W-2 LS U 94-0119 UT45 NAD Main Steam A Saf e End-to-Elbow 09/21/>4 B9 10 151'- 1314 2 - 3 3 - A
W-~5 ~
94-0106 MT NAD Main Steam A Elbow to-Pipe 09/20/94 B 9.
11 151-131G A W-5 94-0118 (TT4 5 NAD Main Steam A Elbow to-Pipe 09/21/94 B 9. 11 ggI;13142-33-A~ ~ ~ ~ ~ ~ ~
1Wi32^ ^ ~ ~ ' - - ' ' ~ ' - ' ~ ~
~
94 E s66BL~ ~ ' ' ' '
MT'
~ ~ ~ ~ -~
NAD~
O Main steam A Pipe-to-Valve 10/08/94 8 9. 11 T
~i IS!'-13142-33 A W-32~~
~ '-~' ' '
94-0404BL
' tfr4 5
~ ~ ~ ~ ~ ~ - - ~ ~ - '
GEO '
Main Steam A Pipe-to Valve 10/10/94 B 9. Il Limited due to configuration.
1sg.13142 33-A
~ ~
'^^ WJ32^
~~ '~
~ l 94 - 6 3 9 7B' - ~'-~
"tyto- ~ ~ - ~
~ ~ ~ ~ ' ~
NAD~ ~ ~
L 1
Main Steem A l Pipe-to Valve
^ 10/10/94 8 9. 11 Limited due t o configuration.
1S1413142-34'-A~
B-1 94-0376BL VT1 NAD Main Steam B Flange Bolts a W 13 10/08/94 B 7. 50 Examined in place.
ISIT 3142-34 A'~
B '3~
~
- ' 94:0377BL-~
"VTi~
' ' ~ ' - " - ~ ~ - - ^
NAD'~
1 T
Main Steam B Flange Bolts 9 W-16 10/08/94 B7 50 Examined in place.
ISI-13142-34"-A '
~
~,B-
$~
~
~l94-0372BL
~ ~ ~ ' 3 NAD
~
VT1' ~
fValveBolts
'10/06/94 B7 70 Main Steam H I
Examined in place.
IS1 11142 34-A'
~
Bi 6 94 0141~
[ VT1 ~~ ~ ~
' ~~
'NAD
~
J Main 9 team B Valve bolta j10/08/94
!B7 70 i
- Examined in pl_ac _e._. _ _
.A 01/17/05 Page 4
e Monticello Nuclear Generating Plant Inservice Inspection Report Log Ndrthern States Power Company Old Ewy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, NM $5342 Commeretal Service Date June 30, 1971 Minneapolis, MN $5401 ISO item Report Number Method Results System Item.)escription Exam Date ASME Section II Item 161-13142-J4-A B-6 94 - 0141BLR1 VT1 NAD Main Steam B Valve Bolts 10/10/94 B 7. 70 Reexamination after replacement.
151-13142 34-A B-7 94-0142
'VT1
~
~NAD' ~~~ '
Main Steam B Valve Bolts 10/08/94 B 7. 70 Examined in place.
ISI-13142-34-A H-3 94 0420BL VT3 NAD Main Steam B Enubber / Clamp 10/21/94 P-A,B,C Limited to verification of fluid level following addition.
IS14 3iti-34-A V-4 94-0325BL VT3 NAD Main Steam B Valve Int Surfaces 10/04/94 B12. 50 ISI-13141 34 A' W-33 94-0367BL MT
'NAD Main Steam B Pipe-to-Valve 10/07/94 B 9. 11 151-13142-34-A W-33 94-0405BL UT45 NAD Main Steam B Pipe-to-Valve 10/10/94 B 9. 11 Limited due to configuration.
IS1-13142-34-A W-33 94-0398BL UTO NAD Main Steam B Pipe -t o-Valve 10/10/94 B 9. 11 Limited due to configuration.
f ISI-13142-35 A ~
B-2
~ ~ ' ~ ~194-0371BL
~
VT1
'NAD-Main Steam C Valve Bolts
{10/06/94 B 1. 70
{fe4-0386BL Examined in place.
VT1 NAD 151-13142-35-A B-4 Main Steam C Flange Bolte e W-18 10/C8/94 B7 50
~
Examined in place.
i IS!-i3i42-35-A" - "
B' ~ 5- ' ~ ~ ~ ~ - ~ ~ ~ ~ ~
94!0384B I -~ ~
VT1 NAD Main Steam C Flange Bolts e W-14 10/08/94 B 7.
70 F1amined in place.
ISI-13142-35 A B-4 94-03878L VT1 NAD Main Steam C Valve Bolts 10/08/94 B7 5*
Examined in place.
ISI-13142-35-A D-7 94-0385BL VT1 NAD Main Steam C Valve Bolts 10/08/94 B 7. 50
~
~
Examined in place.
ISI-13142-35-A B-7' 94-0385BLR1 ~-* 'VT1 NAD Main Steam C Valve Bolts 10/21/94 B 7, 50 Examined in place after i
.etensioning.
181 13i42-35 h' "-~'
~Y-3 2
H 94-0354BL VT3 NAD Main Steam C Snubber / Clamp 10/05/94 F-A,B,C l
IS1-13142 35 A V-1 94-0225 VT3 NAD Main Steam C Valve Int Surfaces 09/26/94 B12. 50 IS1-13142 35-A V-4 94-0326BL VT3 NAD Mair. Steam C Valve Int Sarfaces 10/04/94 B12. 50 iS17 i142 il"-k'-'
~ ^" W' 10 94-0133 KT NAD 1
Main Steam C Pipe to-Elbow 09/22/94 B 9. 11 ISI-i3142!)5' A"
~]W-10 ~ ~ ~ ~ ~ ~ '~~' 54 012 f
~~
'~tTT4 5'
~NAD~~
Main Steam C iPipe-to-Elbow 09/22/94 B 9. 11 161.ili42-35'A~~
l W-i1 ~
~
'-'I94-013f'
~~ ~
MT~ ~ ~ ~ ~ ~ ~ ~ ~
NAD~
f09/22/94 B 9.
11 l
Main Steam C Elbow-to-Elbow i
I S I - 1314 2 - 3 b"- A
^
NW-11 94'-0128
'UT45
- ~ ~ "
~M NAD
~
I lbow-to-Elbow 09/22/94 i B 9.
11 Main Steam C E
i i
IS1-13i42-is-A ~~
~
' WZ12 ~ ^ '
' ~ - ~
~ ~ ~ j 960i3f ~
~ MT~ ~ ~
~ ~ - ~ ~ ~ ~ ~ ~
NAD-~
Main Steam C Elbow-to-Pipe
!09/22/94 l B 9.
11 i
_ _ ~.
..__.__...__....._L.._.
l l
I i
01/1?/95 Page 5
l Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company old Rwy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, MN 55362 Commercial service Date June 30, 1971 Minneapolis, MN $5401 230 Item Report Number Method Results system Item Description Eman Date ASME Section XI Item IS1-13142-3b-A W-12 94-0127 trr45 NAD Main Steam C Elbow-to-Pipe 09/22/94 B 9. 11 Limited due to support rortriction.
ISI-13142-35-A W-34 94-03689L MT NhD-~
Main Steam C Pipe-to-Valve 10/07/94 B9 11 ISI-13142-35-A W-34 94-0406BL
" UT4 5~
NAD~
Main Steam C Pipe-to-Valve 10/10/94 8 9. Il Limited due to configuration.
ISI-13142-35-A W-34 94-0399BL UTO NAD l
Main Steam C Pipe-to-Valve 10/10/94 B 9, 11 Limited due to configuration.
J
'iSi-13142-36-A B-1 94-0382BL VT1 N^f> ~
Main Steam D Flange Bolts a W-13 10/08/94 B 7. 50 Examined in place.
'iS Fi31'42 36 A B+ 3 94-0383PL YT1 NAD~
Main Steam D Flange Bolte e W-17 10/08/94 B 7. 50 Examined in place.
isi-1)142 3 FA'~' ~ ~ ~
]B-8 5FUi7CBL VTi NAD 2
Main Steam D Valve Bolts 10/06/94 B 7. 70 Examined in place.
l ISI-13142-36-A B-9 94+0125 VT1 NAD Main Steam D Valve Bolts 10/08/94 B 7. 70
[
Examined in place.
ISI-13142-36-A B-10 94-0123 VT1 NAD Main Steam D valve Bolts 10/08/94 B 7. 70 Examined in place.
i IS1-13142-36-A H-2 94-0120BL VT3 NAD Main Steam D Snubber / Clamp 09/21/94 F-A,B,C i
ist;jjiqi.3s.A~ - - ~ '
' H+ 5 94-0121 VT3 NAD Main Steam D Snubber / Clamp 09/21/94 F-A,B,C i
1$1-13142-36-A H-5 94-0121BLR1 VT3 NAD~
Main Steam D Snubber / Clamp 10/07/94 P-A,B,C Reexamined after gremoval/ reinstallation.
~1SI 131'42-36-A H-6 94-0122 VT3 IND i
Main Steam D Snubber / Clamp 09/21/94 P-A,B,C Loose bolt and fluid leakage.
ISI-13142-36 A H-6 94-0122R1 VT3 NAD i
Main Steam D Snubber / Clamp 10/07/94 F-A,B,C Reworked
~1S1 13142 36-4 H-7 94-0124 VT3 IND Main Steam
- Double Spring /4 Lugs 09/21/94 F-A,B,C B10.10 Drawing confor.mance.
Main Steam D Double Spring /4 Lugs
/ /
F-A,B,C B10.10 Use as-is w/ Technical I
Justification.
Isi-i314 F36-A V-2 94-0224 VT3 NAD Main Steam D Valve Int Surfaces 09/26/94 B12. 50 d
Main Steam D Valve Int Surfaces 09/24/94 912. 50 Main Steam D valve Int surfaces 10/04/94 i B12. 50 I
- ~ _d
. _ - ~ - _ _
I Main Steam D Elbow-to-Pipe 09/25/94 8 9.
11 I
.-a Main Steam D Eltow to-pipe 09/26/94 f B 9.
11
-I I
01/17/95 Page 6
e Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Did swy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, NW 55362 Comunercial service Date: June 30, 1971 Minneapolis, MN $5401 180 Item Report Number Method Results System 2 tem Description Exam Date ASME Section 11 Item ISi 13142-36-A W-12 94-0134 MT NAD Main Steam D Pipe to-Sweepolet 09/22/94 B 9. 31 ISI-13142-36-A W-12
'94-0130 UT45 NAD Main Steam D Pipe-to-Sweepolet 09/22/94 B 9.
31 Limited due to configuration.
~~ 76189 MT~
' ' 'NAD~
'Is1 H142 36-A W-25 T
94 Main Steam D Elbow-to-Pipe 09/25/94 B 9.
11
~ISI-13142-36-A W 25 94-0200 UT45 NAD Main Steam D Elbow-to-Pipe 09/26/94 B 9, 11 ISI-13142-36-A W-35 94-0369BL MT NAD Main Steam D Pipe-to-Valve 10/07/94 B 9. 11
~ iO2BL
~UTib' GEO~
' lS f-1314 2 - 3 6 - A W-35 94 0
Main Steam D Pipe-to-Valve 10/08/94 B 9. 11 Limited due to configuration.
iSI-13142-36-A W-35 94 - 04 00BL UTO NAD Main Steam D Pipe-to-Valve 10/08/94 8 9. 11 Limited due to configuration.
161-13142-37-A H-3 94-0344BL VT3 NAD RHR Discharge A Snubber 10/04/94 F-A,B,C ISI 13142-37 A H-3 347 544BLR1
VT3
'NAD 0
RHR Discharge A Snubber 10/21/94 P-A,B,C Reexamination after snubber bolt replacement.
IS1 13142-37-A H-4 94 0015 VT3
~ ~ ^1ND RHR Discharge A Db1 Spring / Clamp 08/05/94 F-A,B,C Drawing conformance.
ISI-13142-37-A H-4 94-0015R1 VT3 IND RHR Discharge A Db1 Spring / Clamp 10/05/94 F-A,B,C Partial rework.
ISI-13142-37-A H-4 94-0015R2 VT3 NAD RHR Discharge A Db1 Spring / Clamp
/ /
F-A,B,C Use-as-is w/ Technical Justification.
IS!-33142-37-A H-6 94-0346 VT3 NAD RI.R Discharge A Strut / Clamp 10/04/94 F-A,B,C ISGi3542;M! ~~~~
H-7 94-0052
~ MT NAD A
RHR Discharge A Db1 Spring / 4 Lugs 08/16/94 P-A,B,C C 3.20 Isi:151'42-37 A!-~~~
H-7 94-0051 VT3 IND RHR Discharge A Db1 Spring / 4 Lugs 08/16/94 F-A, B. C C 3.20 Loose nuts and drawing fconformance.
i ISI-13142 37-A
}H77
~
' i>5!005'iki VT3 IND I
RHR Discharge A Db1 Spring / 4 Lugs 09/14/94 P-A,B,C C 3.20 Reworked loose nuts but still.
l have drawing conformance
~MI gh 4y.'37:A~
HI7-~-
-~~W OO5iR2
~NAD~
RHR Discharge A Db1 Opring / 4 Lugs
/ /
F-A,B,C C 3.20 Use-as-is w/ Technical 1
Justification.
RHR Discharge A l Variable / Clamp 08/16/94 F-A,B C 2
1 94-0028 VT3
~ ~ ' ~ ~ - *IND"
~
2$14 I142 37 B'
~
~~]H-Conteinment Spray l Variable Spring 08/05/94 F-A,B,C
! i14f-37-B'
~
jH-~ '1"
~ '
~ 94-002BR1'
' ~ ~
Drawing compliance.~ ~ ' - ~ ' ~ ~ ~ ~ ~ ~ iD~
1
~
~
VT3^ " " ~ ~ ~ '
N IS!
Containment spray Variable Spring
/ /
F-A,B,C l
Use-as-la w/ Technical i
a
- -.. - -.. - - --.--...j._-.-.-.--.--_.
l
. -.tificat_ ion...
Jus
p--
i Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Ewy 152 NW of Monticello Third Interval By Iso / Item 414 micellet Mall Monticello, MN $5362 Comercial Service Date June 30, 1971 Minneapolis, MN 55401 1
ISO Item Report Number Method Results System Item Description Exam Date ASME Section XI Item ISI-13142-37-B H-2 94-0025 VT3 NAD Containment spray St rut / 8 Lugs 08/05/94 F-A,B,C
'isisili4}-37-B H-2
~~
5E6010 MT NAD Containment Spray Strut / 8 Lugs 08/08/94 F-A,B,C l
181-13142-37-B H-3 94-0029 MT NAD Containment Spray St rut / 8 Lugs 08/08/94 F-A,B,C C 3.20 I
isiT di4fT 1-B H-3 94 0024
~VT3 NAD 3
Coritainment Spray Strut / 8 Lugs 08/05/94 F-1.,B,C C 3.20
' 'I N' ~
181-13142-37-B H-4 94-0027 VT3 D
Containment Spray Variable Spring 08/05/94 F-A,B,C l
I Improper load settings J
- stamped, i
!SI-13142-37 8 H-4 N!0027' 1 "VT3
~~'
NAD~
R rontainment Spray variable Spring 09/14/94 F-A,B,C
'4TO 34 $BC ~~~
NAD-
~151213i4237'B"~ ~ ~
HI' 5' 9
Containmed
.r a y Snubber / Luge 10/04/94 F-A,B,C C 3.20 1S!ZU142')7-B~
H-7 94-0416 VT3 NAD 2
Containment spray Db1 Spring / 4 Lugs 10/13/94 F-A,B,C C 3.20
.-..--.y Containment Spray Db1 Spring / 4 Lugs 10/12/94 F-A,B,C C 3.20
'IS1:13142'-377C' ~ ~ ~~ " '"
H-1 94-0010
'VT3 IND 1
RHR Discharge A Spring / Clamp 08/04/94 F-A,B,C I
Drawing conformance, extra i
parts and missing welds.
ISI'ii14'72 37 C H-1 94-0010R1 VT3 NAJ 2
RHR Discharge A Spring / Clamp
/ /
F-A,B,C i
Use-as-is w/
Tech. Justification.
)
ISI-13142-37-C H-1 94-0010BLR2 VT3 NAD RHR Discharge A Spring / Clamp 10/21/9C F-A,B,C New inspection after modification.
'iSI-13i42-37 C'
~ ' ' ~
N ~4~--
94-0336BL
~VT3 NAD
~~ !
RHR Discharge A Db1 Strut-&-Snubber 10/03/94 F-A,B,C l
ISI-13142-37 C' H-4 94 - 0 3 3 6 8'LR'1 VT3 NAD~'~
RHR Discharge A Db1 St rut + Snubber 10/21/94 F-A, B, C Reexamination after snubber is1'-014f-40-A' ~ ~ ' ' ~ ~ ~ ~ ~j
] VT3 bolt replacement, H-14 94-0004 IND I
HPCI Water Side Dsch iSeismic Restraint 08/01/94 F-A,B,C l
Thread engagement
]H-li ~
'~l94-0004R1' VT3 NAD ISI 13142-40-A KPCI Water Side Doch Seismic kestraint
/ /
F-A,B,C Use-as-is w/ Technical i
l Justification HPCI Nater Side Dsch Valve-to-F1pe 08/02/94 C 5. 51
._...--4 HPCI Water Side Doch Valve-to-Fipe 06/03/94 C 5. 51 1$1-13142-42 A
~~
B-"2'~~--'~
~ ~ ~ ~ ~" 9420281~ - - - ~ " VT1~ - ' - - ~ ~ ~ ~ - - ' ~
'NAD'~
l Valve Bolts HPCI Steam 09/30/94 B7 70 l
3SI- 0142 42';A H-2"
'~'
~
~
94-0392 VT3 IND T
~
HPCI Steam Spring / Clamp jl0/10/94 F-A,B,C j
Loose bolt and load below j
allowable.
Monticello Nuclear Generating Plant Inservice inspection Report I,og Northern States Power Company Old Ewy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, MN 55362 Commercial service Dates June 30, 1971 Minneapolle, MN 55401 Iso Item Report Number Method Resulte t
system item Description Eman Date ASME Section XI Item 3SI-13142-42-A H-2 94-0392R1 VT3 NAD HPCI steam Spring / Clamp 10/13/94 F-A,B,C Reworked J'966~635 ISI-13142-42-A H-5 VT3 NAD HPCI Steam Spring / Clamp 08/09/94 F-A,B,C
~ISI-13i~4f~42 A~ ~ ~ - -
HT6~
~94'70016
~VT3 NAD~
~
HPCI Steam Spring / Clamp 08/09/94 P-A, B, C
'ISI-13142-42-A H-7
' 94-0037 VT3 IND~
~
HPCI Steam Spring / Clamp 08/09/94 F-A,B,C Setting outside of allowable.
ISI-13142-42-A H-7 94-0037R1 VT3 NAD HPCI Steam Spring / Clamp 10/17/94 F-A,B,C Reworked 1S1'13i42 42 A~
if-if 5470 3 5'0 BL VT3 NAD
! 2
~
HPCI Steam Snubber / Clamp 10/05/94 F-A,B,C ISI-13142-42-A V-2 94-0280 VT3 NAD HFCI Steam Valve Int Surfaces 09/30/94 B12. 50 ISI-13142-42 A V-3 94-0413BL VT3 NAD HPCI Valve Int surf 10/12/94 B22. 50 ISI-13142-42-A W-18
~
i94-0395BL MT NAD HPCI Steam Valve-to-Tee 10/10/94 C 5. 51 ISI-13142-42-A W-le 94-0403BL
~ DT4 5
~
'GE6 -
HPCI Sttsm Valve-to-Tee 10/11/94 C 5. 51 Limited due to configuration {
ISI-13142-42-A W-21A 94 0394BL MT NAD_
HPCI Steam Pipe-to-Pipe 10/10/94 C 5.51
^']iG'03MBU
'~UT45
- NAD
~
ISI-13142-42-A W 21A HPCI Steam Pipe-to-Pipe I30/10/94 C 5.51
_4 7
HPCI Steam Pipe-to-Pipe 10/10/94 C 5.51 ISI-13142-42-A W-219 94-0393BL MT NAD HPOI Steam Pipe-to Pipe 10/10/94 C 5.51 ISI-13142-42-A W-21B 94-0389BL UT45 NAD HPCI Steam Pipe-to Pipe 10/10/94 C 5.51 g96638886 1706~
~ ~ ~TNAI ISI-13142+42-A W-21B HPCI Steam Pipe-to Pipe l20/10/94 C 5.51 l
56 360BL
MT NAD 0
ISI-13142-42-A W-45 l10/06/94 C 5. 51 HFCI Steam Pipe-to-Valve TNAD '
}31~3jj42!4 2 A'
'~'
W-45
' 94 - 0416 BL '~
UT45
~
HPCI Steam Pipe-to-Valve
/ /
C 5. 51 ISI il142 4F A"
~~
~ ~ 6W-46'~ ~ ~~ ~ ~ ~ ~
- 94-03598L
~MT
'NAD 7
HPCI Steam Valve-to-Pipe 10/06/94 C 5. 51 IS1-i'3i42'4)-A
- W-46 94-0417BL UT45 NAD
~ ~ '
HPCI Steam Valve-t o-Pipe
/ /
C 5. 51
!$1 lil'47-~43-A'~
'"~~~i W-9 94-0150 l MT NAD RCIC Steam Pipe-to Elbow 09/23/94 l B 9. 21 i
i IS! 13142 43-A I W-10
' 94-0149 I MT~
NAD 7
RCIC Steam Elbow-to Pipe l09/23/94 B 9.
21 i
-__--...__.-_l_
-..__ _.. -.i_._. _ -. _ _. _
J _-
01/17/95 Page 9
a I
l Monticello Nuclear Generating Plant Inservice Inspection Report Log Nurthern States Power Company old Ewy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, NW 55362 Cosumercial Service Dates June 30, 1971 Minneapolia, NW 55401 ISO Item Report Number Method Results rystem Item Descriptio:
Exam Date ASME Section XI Item ISI-13142-49-A H-4 94-0046 VT3 IND RHR Suction A Snubber / Clamp 08/12/94 F-A,B,C Loose nuts and drawing conformance.
iSi-13142-49 A H-4 94-0048R1 VT3 IND RHR Suction A Snubber / Clamp 09/15/94 P-A,B,C Reworked loose nuts, still have drawing conformance issues.
ISI-13142-49-A H-4
~ 94-0048R2 VT3 NAD RHR Suction A Snubbar / Clamp
/ /
F-A,B,C Use-as-is w/ Technical Justification, S
7'
'9fl0044 VT3 NAD gg g y3j42'-4'9 A2~
I RHR Suction B Db1 Strut /Db1 Strut 08/11/94 F-A,B,C
'i$1-13142-49-A H-10
~W63'5FBL i/T3 IND RHA Suction B Snubber / Clamp 10/05/94 F-A,B,C Thread engagement and drawing conf o mance.
_j_94-0351BLR1 NAD VT3 ISI 13142-49-A
~
H-10 RHR Suction B Snubber / Clamp
/ /
F-A,B,C Use-as-is w/ Technical Justification.
ISI-13142-49-A W-15
~ ~ ~
]94-0043 MT NAD RER Suction A Elbow-to-Pipe 08/12/94 C 5. 51
___.4 RHR Suction A Elbow-to-Pip 6 08/18/94 C 5. 51 ISI-13142-51-A H-1 94-0012 VT3 NAO RHR Discharge A Snubber / Db1 Strut 08/04/94 F-A,B,C 1SI-13142-51-A H-1 94-0012R1 VT3 NAD RHR Discharge A Snubber / Db1 Strut 08/24/94 P-A,B C Reeham after clamp removed and reiastalled.
ISI-13142-51-A W-25
~ ' ~ ~ ~
9f ~~0 0i3
- MT IND
~
RHR Discharge A Reducer-to-Nozzle 08/24/94 C 5. 51 Linear ISI-13142-51-A W-25 94-0072 UT45 CEO RHR Discharge A Reducer-to Nozzle 08/24/94 C 5.
51 Limited due to configuration.
RHR Discharge A l Reducer-toNozzle 08/24/94 C 5. 51 rked.
]
Containment Spray lDb1 Spring / 4 Lugs 08/11/94 F-A;B,C C 3.20 l
' g SF.'1'3 3 4 2 : 51 -I
"~
HT I ~~
~ -
94!6646 irT3'
~ ~ ~ ~ - ~
'I N9"~
l08/11/94 Containment Spray Db1 Spring / 4 Lugs P-A,B,C C 3.20 Drawing conformance.
iSiJ 5i42'-5f-B'
'~
'~ ~ f H-2 1
~
94-0046R1 VT3 NAD Containment spray Db1 Spring / 4 Lugs
/ /
F-A,B,C C 3.20 Use-as-is w/ Technical j
Justification.
~ IVT)
IND l NTb ~)9 151-13142 51 B H-3 Containment Spray
!Db1 Spring / Clamp
- 09/07/94 P-A,B,C 1
.._._.._.J Drawing confomance.
IS1-13142-51-B H-3 94 0079R1
- VT3 NAD I
containment spray iDb1 Srring / Clamp 09/14/94 F-A,B,C l
Reworked 1$1-13142-51-B
'H-4
~ 1 94-0645 ~
~' 1 VT3 ~ ~ ~ ~ ~ ' ^ ~ - ' ~ ~ ~
IND lF-A,B,C Containment spray strut / Clamp 08/11/94
- ""E*
--__._..___J.
01/11/95 Page 10
e l
Konticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Po dr Company Cid swy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Wall Monticello, MN 55362 Commercial Service Date: June 30, 1971 Minneapolis, MN 554ct ISO Item Report Number Method Resul System Item Description Exam Date ASME Section XI Item 181-13142 51-B H-4 94-0045R1 VT3 NAD Containment Spray Strut / Clamp 08/23/94 F-A,B,C Reworked 1SI-13142 51-B H-5 94-0080 VT3 NAD Containment Spray Db1 Strut /Db1 Clamp 09/07/94 P-A,B,C
'iSf-13142-52 A H-2 94-0186 VT3 NAD reedwater Variable / Spring 09/22/94
!-A,B,C
'lS1-13142-52-A H-3
'94-0159 VT3 NAD Feedwater Double Spring /4 Lugs 09/22/94 F-A.3,C R10.10 IS!-13142-52-A H-4 94 0143 VT3 NAD Feedwater Snubber / Clamp 09/22/94 F-A,B,C ISI-13142-52-A W-21 94-0137 MT NAD Feedwater Pipe-to-Elbow 09/22/94 B 9. 11 Feedwater Pipe-to-Elbow 09/22/94 B 9.
11 Limited due to configuration.
ISI-13142-52-A' W-22 94-0136 MT
- N5 F ~
l Feedwater jElbow-to-Pipe 09/22/94 B 9. 11 ISI-13142-52-A W-22 94-0145 UT45 NAD Feedwater Elbow to-Pipe 09/22/94 B 9. 11 Limited due to configuration.
IS1-13142-52 A W-23 94-0173 MT NAD Feedwater Pipe-to-Safe End 09/25/94 B 9. 11 ISIU 1142'-51-'A--'
' ' - - ' ~ ~ ' ^W-2 F ~
~' ~~I94-016e UT45 NAD
~
Feedwater Pipe-to-Safe End 09/25/94 B 9. Il Limited due to configuration.
ISI-13142 52-A W-24 94 0169 MT NAD Feedwater New S.E.-to-Cld S.E.
09/25/94 B 9. Il ISI-13142-52-A W-24 94-0166 UT45 NAD Feedwater New S.E.-to-01d S.E.
09/25/94 B 9.
11 ggg;-g3g42-52;A~'-~'~~IW 25 94-0170
~MT
~
'NAD Feedwater Safe End to-Nozzle 09/25/94 B 9. 11 Feedwater Safe End-to-Nozzle 09/25/94 B 9. 11
__._.4 Limi_te_d due to_co._n_figur_a_ tion.
g Peedwater Snubber / Clamp 09/24/94 F-A,B C iS1-lii4' 53 A'-'-
~~
H76
~
~ ~ " - -'90 0178~ ' - ~ ' ~ - ' "VT5
' ~ ' ~ ~ ' ' ' ~
NdD~
2 Feedwater Spring / Clamp 09/24/94 P A,B,C f
1$1'-13142-53 A~
~
'~~'lH-7 179
-~
'VT3-
~~ NAU ~
7~~
' ~ ' ~
~~
'94 0
' Snubber / Clamp 09/24/94 F A,B,C l,
Feedwater Valve Int surfaces 10/08/94 B12. 50 4
ISI 13142-53-A i W-28 94 0257 Kf NAD Feedwater
! Pipe-to-Fipe 09/29/94 9 9.
11 l
IS1-13i42-53;A'-
- " W-20
~ ~~
94-026ii~ ~ ' ~ -
UT45' - ~' - ~~ ~ ~'~~'~ ' NAD~
~
! Pipe-to-Fipe 09/29/94 i B 9.
Il Limited due to surface.
181-13142-53A
'~
' W 32~
~ ~ ~
94-0206 MT
-
- NAD "
Feedwater b re-to-Elbow
!09/26/94 B 9.
11 1
i
..1._..______.___..____.--_.___._.__._____._._.._.__
01/11/05 Page 11
y n
- i..
[..
s Monticelle Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company i
Old Rwy 152 NW of Monticello Third Intervel By Iso / Item 414 Nicollet Wall 1
Monticello, MN 55342 Commercial service Detoe June 30, 1971 Minneapolis, MN 55401 1so Item Report Number Method Results system Item Description Eman Date AsME section XI Item 181-13142-53-A W 32 94-0268 UT45 NAD Feedwater Pipe-to-Elbow 09/29/94 9 9. 11
'~TW 33~
~
54-0205 MT NAD
'ggg'13i42'53-A
~
Feedwater Elbow to-Pipe 09/26/94 89, 11 IS!-l3i42-53-A" ~
W-33 94-0259 LTT45 NAC
~
Feedwater Elbow-to-Pipe 09/29/94 8 9. 11
. - - - -. -. ~ - - - - - -,
__. 4 Reactor wtr cleanup Double Spring /4 Lugs 09/25/94 F-A,B,C f
Thread engagement and tack welded nuts.
_.. ~.
. _ - _.. _ _.. -. ~.
_q Reactor Wtr Cleanup Double Spring /4 Luge
/ /
F A,B,C Use-es-is w/ Technical Justification.
ISI-73080-A W-7 94-0290 UT45 NAD Reactor Wtr Cleanup Elbow-to-Valve 09/27/94 D 9, 11 t
!St-73880-A W-21 94-0183 KT NAD Reactor Wtr Cleanup Pipe to-Eltow 09/24/94 99, il
-.. -.... - - - -.. - ~.. +
Reactor Wtr Cleanup Pipe-to-Elbow 09/24/94 B 9. 11 94 018 i' ~~ ~~ ~MT ' ~ ~ ~ ~ - ~ ~ ~~
~NAD~ ~ '
'T
'~
~ "~"~
W 22'"
2 2S!J75880-A~ ' ~ ~ ' - ' '
Reactor Wtr Cleanup Elbow-to-Valve 09/24/94 89, 11 Reactor Wtr Cleanup Elbow to-Valve 09/24/94 B 9, 11 Limited due to conf.igur.at. io.n.
Recirc A Drain Line Tee-to Pipe 09/27/94 B 9. 40 94 02s)~~~~
"PT~'~
~~~~ ' " - ~
NAD~-
gg3 94go9;i'.A~ ~ ~ ' - - ~
' wT g ~ ~
~ ' - ~
7 Recirc A Drain Line Pipe-to-Valva 09/27/94 9 9. 40 ISI-74215 A H-1 94 0228 VT3 NAD Standby Liquid Cntrl Box Restraint 09/27/94 F-A, B, C ISI-74215 A W-7 94-0135 PT
" ' " ~
'~"I ND ' ~
Standby Liquid Cntrl Pipe-to Head Fitting 09/22/94 8 9. 40 q;, _
. - ~... -.
. Mul.tiple i.ndications.
. ~.
Standby Liquid Cntrl Pipe-to. Head Pitting 09/28/94 B 9. 40 Reworked IS U74216 A~ ' '
~
W-15
~ 94-0282 PT NAD Standby Liquid Cntrl Pipe to-valve 09/30/94 9 9. 40 4
_-__..q
._ _ ~ ~ - -. -.. _ -... - _ __
Head Vent Hanger 10/04/94 F-A,B,C
,)
Head Vent Pipe to Coupling 10/03/94 8 9. 40
- ~ [ PT NAD 151-782 A W-23B 94-0301BL Head Vent coupling to Pipe 10/03/94 8 9. 40
'3s1 702 A'
~
W-26
~~
~
941 ^16 ' ~ ~ ~
PT " - '
~ ~ ~ ~ - ~ ~ ~
NAD~~
f ~
Head Vent Tee to-Pipe 09/23/94 9 9. 40 JSt 782 A
'W - 2 6 A '
94 6302BL ~~
~
PT'
~~
'NAD 2
i
~
Head Vent
- Pipe to-Coupling 10/03/94 B 9.
40
- [ _.
I 01/11/Q5 Page 12
l l
,~
1 I
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern states Power Company Old Ewy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, MN 55362 Commercial service Date June 30, 1971 Minneapolis, MN 55401 130 Item poport Number Mst. hod Results system item Description Eaam Date ASME section XI Item ISI-782-A W-26B 94-0299BL PT NAD Head Vent Coupling-to-Pipe 10/03/94 8 9. 40 ISI-782-A W 27 94-0162 PT NAD
[
Head Vent Pipe-to-Valve 09/23/94 B 9. 40
'iSI-782-A W-28 94-0160 PT NAD i
Head Vent Valve-to-Pipe 09/23/94 B 9. 40
!st.782A-A B-2 94-0289 i VT1 NAD Head Vent Flange Bolts 09/30/94 B7 50 161-786-A HT~
'9f'6265
'VT3' fiAb' 2
MS Condensate Lkoff Box Support 09/29/94 F-A,B,C MS Condensate Lkoff
' Linear Support 09/29/94 F-A,B,C ISI-786-A W-10 94-0156 KT NAD 3
MS Condensate Lkoff Elbow-to-Pipe 09/23/94 9 9. 21 ISI-786-A W-28 94-0161 KT NAD MS Condensate Lkoff Elbow-to-Pipe 09/23/94 B 9. 40
!si-786-A W 29 94-0152 MT NAD i
MS Condensate Lkoff Pipe to-Elbow 09/23/94 B 9. 40
~1SI-786-A W-30 94-0153 MT NAD MS Condensate Lkoff Elbow to-Pipe 09/23/94 B 9. 4 0 IS!-766-A W-31 94-0154 KT NAD MS Condensate Lkoff Pipe-to-Elbow 09/23/94 B 9. 40
'!SIM 5 s2 k' W-32 94-0155 MT NAD MS Condensate Lkoff Elbow to-Pipe 09/23/94 8 9. 40
~1Si-'7905-32-A N-2 94+0014 KT NAD RHR Heat Exchanger A Shell-Pad-Nos 08/04/94 C 2. 31 ISI-7905-32-A Support A 94-0016 VT3 IND RHR Heat Exchanger A Support A,E200A, De 08/05/94 F-A,B,C C 3 10 Drawing conformance.
lgt;7905'if A
' ^ ~ ~ ~
' Support A 94-0018 MT NAD t
RHR Heat Exchanger A Support A,E200A, Ce 08/04/94 F-A,B,C C 3.10 Limited by configuration.
ISI-7905-32-A Support A
~
~94-0016R1 TVT3
'NAD RRR Heat Exchanger A Support A,E200A, ce
/ /
F-A,B,C C 3.10 Use-as-is w/ Technical Justification.
181-7905-32-A Support B 94-0017 VT3 IND RHR Heat Exchanger A Support B,E200A 180s 08/05/94 F-A,B,C C 3.10
~lSI-79C5-32-A
- ~~~
- Support B 94 0019~
Drawing conformance.
MT NAD RHR Heat Exchanger A Support B.E200A 180s Ot/04/94 P-A, B. C C 3.10 Limited by configuration.
181-7905-12 A Support B 94-0017RI VT3 NAD RHR Heat Exchanger A Support B E200A 180e
/ /
F-A,B,C C 3.10 r
Use-as-is w/ Technical l
Justification.
ISI-7905-32-A W-1 94-0049 ITT4 5 NA6 l
ItHR Heat Exchanger A Top Flange to Shell 08/10/94 C 1. 10 3
]Limitedduetoconfiguration.
I e
Bottom Head Drain Box Restraint 110/04/94 F A,B,C i
_____.~_.__._.L.____
6 01/17/05 Page 13
I t
I e
]
i Monticello Nuclear Generating Plant Inservice Inspection Report 1,og Northern States Power Company Old Rwy 152 NW of Monticello Third Interval By Iso / Item 414 Micollet Mall Monticello, MN 55362 Commercial Service Dates June 30, 1971 Minneapolis, MN 55401 Iso Item Report Number Method Results System Item Description Exam Date ASNE Section XI Item 161-821-A W-23 94-0331 MT NAD Bottom Head Drain Pipe-to-Coupling 10/04/94 B 9. 40 ISI-821-A W-24 94-0330 MT NAD Bottom Head Drain Coupling-to-Pipe 10/04/94 B 9. 40 ISI 821-A W-25 94-0329 MT
~ND~-~
Bottom Head Drain Pipe-to-Elbow 10/04/94 B 9. 40 t
IS1-821-A W 26 94-0328 MT NAD Bottom Head Drain Elbow-to-Pipe 10/04/94 B 9. 40 ISI-8292-42-A DVS Supp A 94-0001 VT3 NAD HPCI Pumps DVS Pump Support 07/29/94 F-A,B, C
} j;(.yj g2 Q 2. A~
- ~ " DVS Supp B 94-0608 VT3 NAD HPCI Pumps DVS Pump Support 07/29/94 F-A,B,C IS'<93268-1-A B-1 94-0040 VT1 NAD CRD Scram Header A Flange Bolte e W-7 08/08/94 B7 50 IS1-93268-1-A H-1 94-0022 VT3 NAD CRD Scram Header A Box Restraint 08/08/94 F-A,B,C
.ISI-93268-1-A_...... _ _ _.... -. -... _
H--
____._.__J----...._--.-----
NAD 1
94-0022BLR1 VT3 CRD Scram Header A Box Restraint 10/08/94 F-A,B,C Reexamination after modifica61on.
ISI-93268-1-A H-4 94-0021 VT3 NAD CRD Scram Header A Box Restraint 08/08/94 F-A,B,C CRD Scram Header A Rod / Clamp 08/08/94 F-A,B,C 1SI-93268-1-A H-6 94-0023 VT3 NAD CRD Scram Header A Double Strut 08/08/94 F-A,B,C CRD Scram Header A Double Strut 10/C8/94 F-A,B,C Reexamination after modi f icat ic,n.
ISI-93268-1-A H-13 94-0422BL VT3 IND CRD Scram Header A Strut / Clamp 08/27/93 F-A,B.C Drawing Conformance
' AD"~~
}
ISI-93268-1 A H-13 94-0422BLR1 VT3 N
CRD Scram Header A Strut / Clamp 01/12/95 F-A,B,C Use as is w/ technical justification CRD Scram Header A Tank Support 09/30/94 F-A,B,C B10.10
-4 CRD Scram Header A Pipe-to-Tee 09/23/94 B 9. 11 l
'181 0i268-11A'
~ ~ ~'~
W "6~ ' - ~ ~
- - ~ ' 94-0176 UT45 NAD CRD Scram Header A Pipe-to-Tee 09/24/94 B 9. 11 CRD Scram Header A Flange-to-Tee 09/23/94 B 9.
Il l
2-A
~
W'- Y-
~
~ --
3 4!0 i 7 5' ~ ~ ~ -
UT45
'NAD 1
Is!'- b 32 6 8 CRD Scram Header A Flange-to-Tee l09/24/94 B 9. 11 151 9326811-A~"'
W!-9 i.S' U6D ~~
~
94'-0164 ~~ '
- ~~
~
NAD "'-~
~
~
~
CRD Scram Header A jReducer-to-Pipe
.09/23/94 8 9. 10
_ _ _ ~
01/17/95 Page 14
]
Monticello Nuclear Generating Plant Inservice Inspection Report 1,og Northern States Power Company old Swy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, MN $5362 Consarcial Service Date: June 30, 1971 Minneapolis, MN $5401 ISO Item Report Number Method Results System item Description Eran Date ASME Section II Itea
{
151-53268-1-A W-9 LS U&D 94-0177 UT45 GEO CAD Scram Header A Reducer-to-Pipe 09/23/94 B 9. 10 W Y07,S 'U6D' N6~096
'PT
"'NAD- - ~ '
T ISI-93268-2-A CRD Scram Header A Pipe-to Elbow (45e) 09/19/94 8 9.
10
.,.-. _ _ _... ~ _. -.. -
CRD Scram Header A Pipe-to-Elbow (45e) 09/20/94 B 9. 10 lSfi D68 1-B H3 94-0283 VT3 NAD 9
CRD Scram Hdr Disch Box Restraint 09/30/94 F-A,B,C ISI-93268-1-8 H-6 94-0284 VT3 NAD CRD Scram Hdr Disch Box Restraint 09/30/94 F-A,B,C ISI-93268-1-B W 16 94-0085 PT NAD CRD Scram Hdr Disch Elbow-to-Pipe 09/17/94 B 9. 40 ISI-93268-3-A P-1 94 0024 VT1 NAD CRD Scram Header A Flange Bolte s W-7 09/01/94 B 7.
50 ISI-9326'B-3-A B-l-~~~
94-0077 VT1 NAD 1
CRD Scram Header A Flange Bolts e W-1 08/09/94 B 7.
50 ISI-93268-3-A H-1 94-0038 VT3
~~
NND CRD Scram Header B Box Restraint 08/09/94 F-A,B C
.-._._~._.-._--.4 CRD Scram Header B Strut / Clamp 08/09/94 F-A,B,C 151-93268 3-A H-3 94-0033
~VT3 NAD CRD Scram Header B Restraint / 4 Lugs 08/09/94 F-A,B,C B10.10 ISI-93268-3-A H-4 94-0039 VT)
NAD CRD Scram Header B Strut / Clamp 08/09/94 F-A,B,C 4
"ISI-93268Zi: A' ~ ~ ~ - iH ~11 94 - 04 01BL VT3 NAD CRD Scram Header B Restraint / 4 Luge 10/08/94 F-A,B,C B10.10 ISI-93268-3-A W-6 94-0093 PT NAD CRD Scram Header B Pipe-to-Tee 09/19/94 B 9.
11 ISI-93268-3-A W-6 94-0104 UT4'S
~~NAD~
CRD Scram Header B Pipe-to-Tee 09/20/94 8 9.
11 Limited due to configuration.
CRD Scram Header B Elbow-to-Elbow 09/22/94 B 9. 10 I
131-93268-3-A
~ W-29 LS UaD 94-0146 17T45 GEO CRD Scram Header B Elbow-to-Elbow 09/22/94 B 9. 10
-.--..- - -.m CRD Scram Header B Elbow-to Elbow 10/01/94 9 9. 10 Report for long seam ommitted l
---g
-.-----.------.v.
on or..i..ginal exam.
RHR Return A Snubber / Clamp 09/29/94 F-A,B C ISIT97003 A~
W-4 94-0172 MT NAD RHR Return A Pipe-to-Elbow 09/25/94 B 9. 11 1' 7
; W 4'
94-0207 trT4 5 GEO ISI297003 A~~~
2 l09/25/94
}gg.97003.B~ ~~' -
']' Pipe-to-Elbow
~
90 0242^
'VTf~~~~~ ~ ~ ~ ~ ~ ~ ~ ~ jIND~'
B 9. Il RHR Return A l B-4 RRR Suction A jValve Bolts
'09/29/94 B 7.
70
- 9*0'"
01/17/95 Page 15
e I)-
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company i
Old Nwy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticelle, MN $5362 Couaiercial service Dates June 30, 1971 Minneapolis, MN 55401 l
ISO Item Report Number Method Results System Item Description Exam Date ASKE Section II Item ISI-97003-8 B-4 94-0262R1 VT1 NAD RHR Suction A Valve Boats
/ /
B7 70 i
Use-as-is w/ Technical ISI-97003-B
'W-12 Justification.
_ _1. _ _
94-0204 MT NAD RHR Suction A Branch-to-Pipe 09/26/94 B 9. 31
'W 1f 5 F0250 IfT4 5
~NA6 ~
T
~
-Isi!9760ii'B RHR Suction A Branch-to-Pipe 09/28/94 B 9. 31 Limited due to configuration.
~
~ 66552
'MT NAD-ISI 9766Y-D W 17 9
RHR Suction A Valve-to-Elbow 09/28/94 B 9.
11 ISI-97003-B W-17 94-0237 W4 5 NAD RHR Suction A Valve to-Elbow 09/28/94 B 9. 11 Limited due to configuration.
1S1-97003-B W-38 94-0233 MT NAD RHR Suction A Elbow-to-Pipe 09/28/94 8 9. 11 ISI-97003-B W-18 94-0238' W45 NAD l
RNR Suction A Elbow-to-Pipe 09/28/94 B 9. 11 ISI-97004-A W-4 94-0171
~MT NAD RHR Return B Fipe-to-Elbow 09/25/94 B 9. 11 l
ISI-97004'-A W-4 94-0203 ITT4 5 NAD I
RHR Return B Fipe-to-Elbow 09/25/94 8 9. 11 i
IB-1 isI-97005 A2^
94-0270 VT1 NAD Recirculation A Valve Bolts 09/29/94 B7 70 Examined in place.
ISI-97005-A B-2 94-0269 VT1 NAD Recirculation A Pump Bolting 09/29/94 B 6.180 B 6.200 Examined in place.
ISI-97005 A B-4 94-0100 VT1 NAD Recirculation A Valve Bolts 09/20/94 B 7. 70 ISI-97005-A H-7 96'64ii YT3 ND Recirculation A Double Spring 10/11/94 F-A,B,C B10.10 9
~
._ _ d.._.
Drawing conformance.
IS17 7605~A H-7 94-0411R1 VT3 NAD Recirculation A Double Spring
/ /
F A,B,C B10.10 l
Use-as-is w/ Technical i
Justification.
I ISf'97605-A H-10 94-0407 VT3 IND Recirculation A Dbl Spring / 4 Lugs 10/11/94 F-A,B,C B10.10 Drawing conformance.
f
" lU'16 ' ~ ~
~
5U6465Ri
-5/T3~~
NAD Recirculation A Dbl Spring / 4 Lugs
/ /
F-A,B,C B10.10 Use-as-is w/ Technical Justificaiton.
}VT3
~1SI-97U'66 A H-11 94 0098 NAD I
Recirculation A Sway Brace 09/20/94 F-A,B,C "ISi-97605-A lW-1 94 0227 PT NAD Recirculation A Nozzle-to-Safe End 09/27/94 B 5.
10 1SI-97005 A W-1 94-0240
+ ITT4 5 NAD Recirculation A Nozzle-to-Safe End 09/27/94 B 5. 10
,,,,,,,y,__
_9,,,,
Recirculation A Elbow-to-Pump 10/05/94 8 9.
10 i
ig f.,7 0,,.,-- - ~ '- -I w.14 LS U 94 0357
~~~~UT45'~~ ~' '
~ ~
'NAD-'
Recirculation A
.R1 bow-to-Pump 10/06/94 l B 9. 10 I
I Limited due to configuration.
-__.________.l.____
_...-_._.__._..___..l 01/17/95 Page is 1
i
+
l l
i Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Ccepany Old Bwy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, MN 55362 Commercial Service Date: June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results System Item Description Exam Date ASME Section II Item Ifil-97 00 5 - B
- H-3 94-0244 VT3 NAD Recirc M4nifold A Restraint 09/28/94 F-A,B,C
} H-5
' ' ~ - ~ ' - '
95-h 54
'~VT3
~NA
~
333 97o05.B Recirc Manifold A Restraint 09/28/94 F-A,B,C ISI - 9 7 0 0 'l-B H-6 94-0408 VT3 NAD Recirc Manifold A Spring / Luge 10/11/94 F-A,B,C B10.10 "ISi~-97065 B-~
~~
~
'HIY~
~*Y4!624 5~ ~
~VTi~
NAD
~
Rectre Manifold A Restraint 09/28/94 F-A,B,C JSI 97005-B H-8 94-0242 VT3 NAD ReCirc Manifold A Restraint 09/25/94 F-A,B,C ISI-97005-B H-9 94-0241 VT3 NAD-Recire Manifold A Restraint 09/28/94 P-A,B,C
~
ISI-97005-B W-21 LS U6D 94-0103 PT NAD Recirc Manifold A Pipe-to-Tee 09/20/94 B 9.
10 IS1 97005-B W-21 LS UED 94-0108 17f45 NAD Recire Manifold A Pipe-to-Tee 09/21/94 B 9. 10 ISI-97005-B W-24 94-0295 PT NAD Recire Manifold A Pipe-to-Safe End 10/01/94 B 9. 11
_.. _ _.. ~. -... -
Recirc Manifold A Fipe-to-Safe End
.30/03/94 B 9.
11 l
Limited due to configuration.
ISI-97005-B W 25
~ ~ " 94-0294 PT NAD Recire Manifold A Safe End-to-Nozzla 10/01/94 B 5. 10 1S1 97005-8 W 25 94-0363 UT45 NAD Recire Manifold A Safe End-to-Nozzle 10/05/94 B 5. 10
~ -.. - - - - -
Recirc Pump A Snubber / Lugs 09/21/94 F-A,B,C B10.20 Missing scale for fluid indicator.
ISI-97005-C H-4 94-0116R1 VT3 NAD Recirc Pump A Snubber / Lugs
/ /
F-A,B,C B10.20 Use-as-is w/ Technical Justification.
94 6iN BY,
'VTi~
IN6-~
7 ISI-97005-C H-5 Recire Pump A Snubber / Lugs 09/21/94 F-A,B,C B10.20 Thread engagement, missing pin and loose bolt.
ISI-97005 C
+H-5 94-0115BLR1 VT3
'IND~
Recirc Pump A Snubber / Lugs 10/06/94 P-A,B,C B10.20 l
Reworked but still has thread engagement issue.
151-97005-C H-5 94-0115BLR2 VT3 NAD Recirc Pump A Snubber / Lugs
/ /
F-A,B,C B10.20 Use-as-is w/ Technical IS 1 - 9 7 0 0 5'- C H-10
" - ~ ~ ~ ' ~ - ' - -
96 6355
NAD-Recirculation A Restraint 10/07/94 F-A,B,C ISI-97006-A B-2 94-0268 l VT1. _.. _. -
__1....._
__M NAD Recirculation B RC Pump B Studs 09/29/94 l B 6.180 B 6.200 p
1 Examined in place.
Recirculation B lRCPumpBStuds
{10/07/94 l B 6.18 0 B 6.200 l
_.. _ 'L._ _ _.__._,
I 01/17/95 Page 17
e e
Monticello Nuclear Generating Plant Inservice Inspection Repcrt Log Northern Statee Power Company Old Ewy 152 B1t of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, MN 55362 Commercial Service Date June 30, 1971 Minneapolis, NW 55401 ISO Item Report Nuster Method Results System Item Description Exam Date ASME Section XI Item ISI*97006-A B-3 94-0099 VT1 NAD Recirculation B Flange Bolts a W-16 09/20/94 B 7. 50 Recirculation B Bolts 09/29/94 B 7. 70 Examined in place.
'1SI-67004-A H-2 94-0097 YT3 IND Recirculation B Sway Brace 09/20/94 F-A,B,C
.._. --. - -- _.j Loose nut and misaligned rod.
Recirculation B Sway Brace 10/07/94 F-A 3,C Reworked 151-97006-A H-3 94-0410 VT)
NAD Rectreulation B Db1 Spring / 4 Luge 10/11/94 P-A,B,C B10.10
'1Sf-97006-A H-4 94 6102 VT3
~NAD
~
Recirculation B Restraint 09/20/94 F-A,B,C ISI-97006-A H-7 94-0412 VT3 IND Recirculation B Db1 Spring / Lugs 10/11/94 F-A,B,C B10.30
.__...._._.9
."_.'"_9 C "I
- "C
Recirculation B Db1 Spring / Lugs
/ /
F-A,B,C B10.30 Use-as-is w/ Technical Justification.
._...___.__m Recirculation B Snubber / Luge 09/20/94 F-A,B,C B10.10 ISI-97006-A W-14 LS D 94-0236 PT NAD F
Recirculation B Pump-to-Pipe 09/27.'94 B 9. 10 ISI-97006-A W-14 LS D 94-0217 UT45 NAD Recirculation 9 Fump to Pipe 09/27/94 B 9.10 Limited due to configuration.
ISI-97006-A W-17 LS U 94-6234- ~ ~ ~ " ' 'PT
- - ~ ~ ~ ~ ~NAD-Recirculation B Pipe to-Valve 09/27/94 B 9. 10
_. - _. ~ _.. _ _ _.
- g. -_
Recirculation B Fipe to-Valve 09/27/94 B 9. 10 Limited due to configuration.
!$1-97006 A W-18 LS D 94-C235 PT NAD Recirculation B Valve-to-Bent Pipe 09/27/94 B 9.10
. ~.-_-... - -
- -_ _b Recirculation B Valve-to Bent Pipe 09/27/94 B 9.
10 Limited due to configuration.j'NAD"~
ISI-97006-A W 19 LS UED 94-0271 PT Recirculation B Elbow-to-Pipe 09/29/94 D 9. 10 IS!-97006-h'^
'W-19 LS'U6D" 94-0279 UT4f NAD l
Recirculation B Elbow to-Pipe 09/30/94 B 9.
10 151-97006-B H4 94-C230 VT3 NAD Recirc Manifold B Restraint 09/27/94 P-A,B,C
..N Recirc Manifold B Spring / Lugs 10/11/94 F-A,B,C B10.10 IS1-97006-B H-6
~
94'-025 I ~ '
VTi~
~
~
' NAD' ~
~
Recirc Manifold B Restraint 09/27/94 P-A,B,C Recare Manifold B Restraint 09/27/94
! F-A,B,C i
I
]94 T02 h '
~*
~
~ ~ ~ ~
NAD~
1S1 97006 B
~
H-9 2
VT3 Rectre Manifold B
! Restraint
{09/27/94 F-A,B,C l
l l
_ _ _ _.. _. _ __ L 01/17/99 Page la
t t
Monticello Nuclear Genisrating Plant Inservice Inspection Report Log Nosthorn States Power Company 014 Nwy 152 WW of Monticello Thiad Interval By Iso / Item 414 Nicollet Mall Monticello, MN 55362 Comunercial service Date June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results system Item Description Exam Date ASME 8ection XI Item 151-97006 B H-12 94-0229 VT3 IND Recire Manifold B Snubber 09/27/94 F-A.B,C B10.10 Loose bolt.
ISI 9*l006-B H-12 94-0229BLR1 VT3 NAD Recire Manifold B Snubber 10/06/94 P-A,B,C B10.10 Reworked
~ 5 SIT P/0 66-8 W-11 94-0293 "PT NAD Recirc Manifold B Safe End-to Nozzle 10/01/94 B 5. 10
'Wif~~ ~
'942 ~351
" UT'5 NAD~~~
1g1;91606:B
~'~
T 0
4 pecirc Manifold B Safe End-to-Nozzle 10/06/94 B 5. 10 lSI 91006 B
~~~
W 12'15 U66
~
94-0092
~PT NAD T
T T
Recirc Manifold B Tee-to-Reducer 09/21/94 B 9, 10
! i'82
~UT45 FNAD
'-igf.' p 7 0 g f. B'
W-15 V Uiti 94 0
Recirc Manifold B Tee-to-Reducer 09/24/94 B 9. 10 IS1-97006-D W 13 LS"U&D
~ ~ ] 94-0091 PT
'NAD Rectre Manifold B Reducer-to-Pipe 09/21/94 B 9. 11 ISI-97006-B W-13 LS U&D 94-b094 UT45 NAD Recirc Manifold B Reducer-to-Pipe 09/20/94 B 9. 11 Limited due to support restriction.
'lai-97006-B~ - - -~ '-~ ~ ~ ('is t&D 94-0090 PT NAD w-1 Recirc Manifold B Pipe-to-Elbow 09/21/94 89, 11 ISI-97006-B W-14 LS U&D 94-0095 UT45 NAD Pacirc Manifold B Pipe-to-Elbow 09/20/94 B 9. 11
-_ - - __-..-.k Recire Manifold B Safe End-to-Nozzle 10/01/94 B 5. 10 IS! 97006-B W-18 94-0362 UT45 NAD-Recirc Manifold B Safe End-to-Nozzle 10/06/94 B 5.10 ISI-97006-C H-4 94-0321BL VT3 IND Recirc Pump B Snubber / Lugs 10/03/94 F-A,B,C B10.20 Missing fluid level indicator scale.
iSI-97006 C H-4 94-0321BLR1 VT3 NAD 9ecirc Pump B Snubber / Lugs
/ /
F-A.B,C B10.20 Use-as-is w/ Technical Justification.
ISI-97006-C H-5 94-0322BL VT3
~~NAD~~
Recirc Pump B Snubber / Lugs 10/03/94 P-A,B,C B10.20 ISI-97006-C H-7 94-0256 VT3 NAD Recire Pump B Snubber / Lugs 09/28/94 F-A,B,C B10.20 ISI-97006-C H-10 94-0255 VT3 NAD Recire Pump B Restraint 09/24/94 F-A,B,C l'SI-97008-A W-1
~3470i 9I-
' ~'T'~
NAD~
P Inst rmt Nozzle N-11 A Nozzle-to-Safe End 09/26/94 B 5. 20 l
iSI' 9700li!A W-2
'94-0195 PT NAD Instrmt Nozzle N-11A Safe End-to-Coupling 09/26/94 9 9. 40 7
Instrmt Nozzle N-11A l Coupling-to-Pipe 09/26/94 B 9. 40 l
1SI 97027-A jH-1 941~02 61 VT3
'NAD
~
I RER Equalizer l Spring / Clamp 09/29/94 F-A,B,C 1
.._....1._.
_A 01/17/95 Page 19
e Nonticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Bwy 152 WW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, set 55362 Commercial Service Date: June 30, 1971 Minneapolis, MK 55401
(
ISO Item Report Number Method jResults
[
gystem item Description Exam Date ASME Section XI Item j
ISI-97D27-A H-3 94-0396BL VT3
~~ i ~
"9V 6111 M
NAD
[
'isf-~97027'- A it l
R.HR Equalizer Pipe-to+ Elbow 09/20/94 9 9. 11 ISI-97027-A W-2 94-0112 UT45 NAD RER Equalizer Pipe-to-Elbow 09/20/94 B 9. 11 ISI-97027-A W-6 94-0110 W
NAD RHR Equalizer Pipe-to-Elbow 09/20/94 B 9. 11 "151 97027 A
~ ~ ~
W-6 94-011)
UT45 NAD
- J RHR Equalizer Fipe-to-Elbow 09/20/94 B 9. 11 New Fag i B-1 94-0275 VT1 NAD Top Head N-6B Flange Bolts 09/30/94 B 7. 10 New Fig 1 W-1 9f'0276
~UTO NAIi~
Reactor Vessel T.H. Circ. Weld 09/29/94 B 1. 21 NEd~Figl
~ ~ ~1 W-1 94-0278 UT45 NAD e
lT.H. Circ. Weld 09/29/94 B 1. 21 Reactor vessel I
'ew~ Fig 1 W-1 94-0277' UT60 NhD~
N Reactor Vessel T.H. Cire. Weld 09/29/94 9 1. 21 Ne FFfg'1 W-8 94-0273 UTO NAD Reactor Vessel T.H. Flange Weld 09/30/94 B 1. 40 j
'New' Fig 1
'W-8 94-0272 17T45 NAD Reactor Vessel T.H. Flange Weld 09/30/94 B 1. 4 0 Limited due to configuration.
Nei Flg i W-8 94-0274 UT60
- - [ MAD t
Reactor Vessel T.H. Flange Weld 09/30/94 B 1. 4 0 Limited due to configuration.
NeV Fig 1 W-8 94-0298 MT NAD Reactor Vessel T.H. Flange Weld 10/01/94 B 1. 40 i
N,WplD ~ ~~ ~ ' ~ ~ ~~-~~~ i OI-s 75 94-0419BL VT1 NAD CRD Housings CRD Housing Bolts 10/19/94 B 7.
80 I
NeiFig 3 W-3
~^
94-0337 UTC NAD Reactor Vessel B.H. Circ Weld 10/04/94 B 1, 21 Reactor Vessel B.H. Circ Weld 10/03/94 9 1. 21
_ _... ~. -.
Limited due to configuration.
Reactor Vessel jB.H. Circ Weld 10/03/94 B 1. 21 j
l Limited due to configuration.
Nei F[g 4
'VCDB-1 94-0316 ITTO NAD Reactcr Vessel B.
Head / Vessel 10/01/94 B 1. 21 Limited due to access restrictions.
j NeF Fig 4 VCBB-1 94-032'O b tTT4 5 NAD Riactor Vessel B. Head / Vessel 10/01/94 B 1. 21 Limited due to access restrictions.
Reactor Vessel B. Head / Vessel 10/01/94 B 1. 21 j
j
[
Limited due to access
--.----.-.~.9 i
restrictions.
Reactor Vessel j Circ Weld e N4C 09/24/94 B 1.
11
..__-__d__________..
01/17/05 Page 20
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company old Rwy 152 NW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, MN 55362 Commercial Service Date: June 30, 1971 Minneapolis, MN 55401 Iso Item Report Number Method Results System Item Description Raam Date ASME Section II Item New Fag 4 VCBB-4 94-0215 UT45 NAD Reactor Vessel Circ Neld 0 N4C 09/24/94 B 1. 11
~ - - - -
Reactor Vessel Circ Weld e N4C u9/24/94 B 1, 11 I
NEE' Fig 4 VOBB-4 M 0286 UT6 NAD Reactor Vessel Circ Weld a N4B 09/24/94 B 1. 11 New' Fig 4 VCBB-4 94-0267 UT45 NAD Reactor Vessel Cire Weld 6 N4B 09/24/94 B 1. 11 "New" Fig 4 VCBB-4 194-0286 M60 NAD Reactor Vessel Circ Weld a N4B 09/24/94 B 1. 11
'New~ Fig 4 VCBC-5 94-0089 UTO NAD Reactor vessel Vessel / Flange Weld 09/16/94
. B 1. 30 Leactor Vessel Long Seam 09/25/94 B 1. 12 Limited due to access restriction.
i New Fig 4 VLCB-2 94-0209 UT45 NAD Reactor Vessel Long Seam 09/25/94
- 81. 12 Limited due to access restriction.
Nei Fig 4 VLCB-2 94-0210 UT60 NAD Reactor Vessel Long Seam 09/25/94 B 1. 12 Limited due to access restriction.
New Fig 6 N-1A'IR 94-0348 UT70
'NAD~
Reactor Vessel
'N.
1A Inner Radius 10/04/94 8 3.100 New' Fig 5 N. IA NV 94-0315 UTO NAD Reactor Vessel N-1A Val /Nos Weld l 10/01/94 B 3. 90 l
L Reactor Vessel N-1A Val /Nos Weld 10/01/94 8 3. 90
~
Limited due to configuration.
nee' Fig 5 1N-~~1A"NV '~ ~ ~ ~ ' ' ~
94-0310 UT60 NAD Reactor Vessel N-1A Vsl/Not Weld 10/01/94 B 3. 90 Limited due to configuration.
Reactor Vessel N-2D Inner Radius 09/30/94 B 3.100 Limited due to thermal wire connection.
New' Fig 5 '
N-2D'NV 94-0312 UT 6-~
' NA6-~~~
Reactor Vessel N-2D Nog /Vsl Weld 09/30/94 B 3. 90 Reactor Vessel N. 2D Nor/ Val Weld 09/29/94
- 83. 90 Limited due to configuration and thermal wire connection.
I nee ~ Fig 5 N-2D NV 94-0314 UT60 NAD
[
Reactor Vessel lN-2D Not/ Val Wald 09/29/94 9 3. 90 l
Limited due to configuration and thermal wire connection.
New Fig 5
' NI2E iR~
K-0309 UT70 NAD
~
Reactor Vessel 4-2E Inner Radius 09/30/94 B 3.100 Limited due to thermal wire
. connection.
3-.--..
Reactcr vessel
.N-2E Noz/ Val Weld 10/01/94 B 3.
90
... - ~
Reactor Vessel
- N-2E Not/ Vel Weld 10/01/94 B 3.
90 l
Limited due to configuration 01/17/95 Page 21
J Nonticello Nuclear Generating Plant Inservice Inspection Report Log Nortbarn States Power Company j
cid Ewy 152 ant of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, MN 55362 Cosmarcial service Date: June 30, 1971 Ninneapolis, not 55401 i
ISO Item Report Number Method Results System Item Description Ezam Date ASNE Section E! Item
\\
1 and thermal wire connection.
4...
Reactor Vessel N. 2E Nos/ Val Weld 09/29/94 B 3. 90 Limited due to configuration
~
and thermal wire connection.
Difw Fig 5
'N72J IR~
~N!0310 W70 NAD Reactor vessel N-2J Inner Radius 09/27/94 B 3.100 Limited due to thermal wire connection.
l New Flf s" N-2J NV 94-0308 LTTO NAD Reactor Vessel N. 2J Nos/Vol Weld 09/27/94 B 3. 90 "Niw'Flfs - ~
N-2J'~NV 94-0306 UT45' NAD Reactor Vessel N-2J Nor/ Val Weld 09/27/94 B 3. 90 Limited due to configuration and thermal wire connection.
'Ned Fig 5 N-2J NV 94-0307
~UT60
NAD~'
Reactor Vessel N-2J Moz/ Val Weld 09/27/94 8 3. 90 Limited due to configuration and thermal wire connection.
._..-._.._Q Reactor Vessel N-3A Inner Radius 09/24/94 8 3.100 New Fig 5 N-3A NV 94-0252 LTTO NAD Reactor Vessel N-3A Vel /Not Wald 09/23/94 9 3. 90
.... - _ _ _.. ~... _ _
+
Reactor Vessel N. 3A Val /Nos Weld 09/23/94 8 3. 90 Ne'w" Fig 5 N-3A NV 94-0251
'W6 0
'NAD l
Reactor vessel lN-3A Val /Nos Weld 09/23/94
- 83. 90 l
N5t' Fig ~5 N-4B IR 94-C191
'UT70 NAD Reactor Vessel N-4B Inner Radius 09/25/94 B 3.100 Limited due to thermocouple.
New Fig S N-4C 1R 94-0190 UT70 NAD l
Reactor Vessel N-4C Inner Radius 09/25/94 B 3.100
{WC2ii
~' UTO NAD Limited due to thermocouple.
New' Fig 5 N-4 C NV l
Reactor Vessel N-4C Noz/Vol Wald i O9/24/94 B 3. 90 Limited due to configuration.
New' Fig 5" N-4 C NV 94-0212 UT45 NAD
~
Reactor Vessel N-4C Nox/ Val Weld 09/24/94 B 3. 90 i
Limited due to configuration.,
New Fig'5 N-4C'NV
~
960Ili ITT60 NAD-Reactor Vessel N-4C Noz/ Val Weld 09/24/94 B 3. 90 j
Limited due to configuration.
Reactor Vessel N-5B Inner Radius 09/24/94 B 3.100 Limited due to thermal wire I.
connection.
l Reactor Vessel N-LB Nor/ Val Weld 09/24/94 B 3.
90 Limited due to therinal wire I connection.
s
.. +
.v j
Remetor Vessel N-SB Not/ Val Weld 09/24/94 B 3. 90
{
Limited due to thermal wire y
'CI_I. _"l.... _ _ _. _ _.... _..,...
Reactor Vessel jN-SB Nor/Vsl Weld 09/24/94
' B 3. 90 Limited due to thermal wire i
connection.
i l
01/17/93 rage 22
0 4
l Konticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Ewy 152 WW of Monticello Third Interval By Iso / Item 414 Nicollet Mall Monticello, KV 55362 Commercial ServAce Date: June 30, 1971 Ninneapolis, MN 55401 280 Item Report Number Nothod Results system Item Description Exam Date ASME Section BI Item New Fig b N-BA Ik 94-0349 UT70 NAD Reatter Vessel N-8A Inner Radius 10/04/94 B 3.3 00 New Fig 5 N-BA NV 94-0341 UTO NAD Reactor Vessel W-BA Noz/ Val Weld 10/04/94 B 3. 90 New Fig 5 N-SA NV 94-0342 UT45 NAD Reactor Vessel N-BA Noz/Vs1 Weld 10/04/94 B 3. 90 Limited due to configuration.
I
~
i "New Fig 5 NIS ' NV 94-0343 LTT60 NAD Reactor Vessel N-BA Noz/Vol Weld 10/04/94 B 3. 90 Limited due to configuration.
Ned Fig 6 Bushings 94-0117 VT1 NAD Reactor Vessel 64 Bushings 09/16/94 B 6. 50 Limited to top edge only.
'NeFfg 6 Ligaments 94-0086 UTO NAD w
Reactor Vessel Ligaments 09/16/94 B 6. 40 Limited due to access restriction.
NeU~Flg 6 Nuts 94-0338 KT NAD Reactor Vessel 64 RPV Nuts 10/03/94 B 6.
10 lNeU' Fig E~"
Studs 94-0088 UTO NAD t
Reactor Vessel 64 RPV Studs 09/16/94 8 6. 20 New Ffg 6 Washers 94-0323 VT1 IND
'i Reactor Vessel 20 Washers 10/03/94 B 6. 50 Pitting Wasbers 94-0323R1 VT1 NAD New Fig 6 i
Reactor Vessel j20 Washers
/ /
B 6.
50 Use-as-is w/ Technical Justification.
New ISI-16 W-1 94-0334 PT NAD Jet Pmp Instrmtation Safe End / Nozzle BA 10/04/94 B 5. 10 New ISI-16 W-1 94-0355 UT45 NAD Jet Pmp Instrmtation Safe End / Nozzle BA 10/05/94 B 5, 10 New ISI-19 W-1 94-0296 PT NAD~
?
Inst Nozzle N-12A Nozzle-to-Safe End 10/01/94 B 5. 20 New 151-19 W-1 94-0291 UT45 NAD Inst Nozzle N-12A Nozzle to-Safe End 10/01/94 P 5.
20 f NND'~~
New ISI-19 W-2 94 0297 PT Inst Nozzle N-12A Safe End-to-Reducer
,10/01/94 8 9.
40
. -....~ - -.
(. ~. - -..
RHR Pumps Pump Support 08/19/94 F-A,B,C C 3.30 New ISI-46 RHR Support B 94-0062 MT NAD RHR Pumps Pump Support 08/19/94 P-A,B,C C 3.30 Limited due to configuration.
New 1S1-4 9 Support, Pump B 94-0071 MT NAD Core Spray Pumps Pump Support 08/23/94 F-A,B,C C 3.30 New 181-4 9. _ _ _ _ _.. _ _.. _. _ Support,... - _.. - ~. _,.
4 _ _ ~0 6 5
{Limitedduetoconfiguration.
Pump B 94-0._
VT3 IND Core spray Pumps Pump Support 08/19/94 F-A,B,C C 3.30 Thread engagement.
' New' ! S I -4 9 Support, Pump B
~ ~ ~
94-0065R1 VT3 NAD Core Sptay Pumps Pump Support
/ /
F-A,B,C C 3.30 Use-as-is w/ Technical l Justification, i
I t
01/17/95 Page 23 i
1 NORTHERN STATES POWER MONTICELLO INSERVICE INSPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 Appendix B List of Interval 3, Period 1 Inspections Sorted by ASME (pages 1 through 23) 6 i
l
Monticello Nuclear Generating Plant Inservice Inspection Report Log Nortborn States Power Company Old Bwy 152 NW of Monticello Third Interval By source Doc 8 414 Nicollet Mall Monticello, MN 55362 Cossnercial service Date June 30, 1971 Minneapolis, MN 55401 Iso item Report Number Method Results system Item Description Exam Date ASME Section 11 Item New Fig 4 VCHB-4 94-0114 LTI O NAD Reactor Vessel Circ Weld a N4C 09/24/94 B 1. 11
'Nei Fig 4 VCBB-4 94-0215 UT45
'NAD Reactor Vessel Circ Neld e N4C 09/24/94 B 1. 11 New Flg 4 VCBB-4 94-0216 W6 0 NAD Reactor Vessel Cire Weld e N4C 09/24/94 B 1. 11 New Fig 4 VCBB-4 94-0286 UTO NAf~~
Reactor Vessel Circ Weld e N4B 09/24/94 B 1. 11 New' Fig 4 VCDB-4 94-0287
- tTr4 5' NAD Reactor Vessel Cire Weld e N4B 09/24/94 B 1. 11
'Nei F'ig 4 VCBB-4 94 0288 LTT60
'NAD"~~
Reactor Vessel Circ Weld e N4B 09/24/94 B 1. 11 Ne7 Fig"4" ~ ~ ~
VLCB-2 94-0208 UTO NAD Reactor Vessel Long Seam 09/25/94 B 1. 12 Limited due to access restriction.
Nei p[g 4 VLCB-2 94-0209 17T45 NAD Reactor Vessel Long Seam 09/25/94 B 1. 12 Limited due to access restriction.
Reactor Veseel Long Seam 09/25/94 B 1. 12 Limited due to access restriction.
New Fig a W-1 94-0276 UTO NAD Reactor Vessel T.H. Cire. Weld 09/29/94 B 1. 21 New Fig 1 W-1 94-0278 UT45 NAD Reactor Vessel T.H. Circ. Weld 09/29/94 B 1. 21 New Fig 1
-- ] W-1 94-0277 UT60 NAD Reactor Vessel T.H. Cire. Weld 09/29/94 B 1. 21
'Nei Fig 3 W-3 94-0337 LTTO NAD Deactor Vessel B.H. Circ Weld 10/04/94 B 1.
21
'NeW Flg 3 W-3 94-03F9 I trT45 NAD Reactor Vessel B.H. Cire Weld 10/03/94
- 81. 21
.._ _ __._.._ _ m Limited due to configuratio_n.__.,
Reactor Vessel B.H. Cire Weld 10/03/94 B 1. 21 Limited due to configuration.
New ' Fig 4 VCBB-1 94-0316' UTO NAD Reactor Vessel jB. Head / Vessel 10/01/94 B 1.
21 Limited due to access rictions.
I Reactor Vessel jB. Head / Vessel 10/01/94 B 1. 21 l
Limited due to access l
restrictions.
New Fig 4'~
~
-~
" VCBB-1 94-0317 (TT60 NAD Reactor Vessel B. Head / Vessel 10/01/94 B 1. 21 Limited due to access I
.. _ _... _. _.. ~ _.... _
__9 re s t_ri.ct ions.
h Reactor Vessel l Vessel / Flange Weld 09/16/94 B 1.
30 l
New Fig 1
~ ~
~IW-8 l94-0273 LTr0 NAD Reactor vessel
B 1. 40 l
_._m____.
01/17/05 Page 1
s Monticello Nuclear Generating Plant Inservice Inspection Report Log liorthern States Power Company old Nwy 152 NN of Monticello Third Interval By cource Doc #
414 Nicol',et Kell Monticello, MN 55363 commercial Service Dates June 30, 1971 Minnespolis, MN 55401 ISO Item Report Number Method Results System Item Description Exam Date ASKI Section XI Item New Fig 1 W-6 94-0272 W45 NAD Reactor Vessel T.H. Flange Weld 09/30/94 B 1. 40 Limited due to configuration.
New Fig 1 W-8 94-0274 UT60 NAD Reactor Vessel T.H. Flange Weld 09/30/94 B 1. 4 0 Limited due to configuration.
Nei Fl'g 1 W-8 94-0298 MT NAD~
Reactor Vessel T.H.
Flange Weld 10/01/94 B 1. 4 0 Reactor Vessel N-1A Vsl/Not Weld 10/01/94 B 3. 90
'New Flg 5 N-1A NV 94-6319 UT45 NAD
~
Reactor Vessel N-1A Val /Noz Weld 10/01/94 B 3. 90 Limited due to configuration.
Nei tig 5 N-1A NV 94-0318 W6 0 NAD Reactor Vessel N-1A Val /Noz Weld 10/01/94 8 3. 90
~
Limited due to configuration.
New Pig 5 N-2D NV 94-0312 WO NAD Reactor Vessel N-2D Nos/ Val Weld 09/30/94 B 3. 90 New Pig 5 N 2D'NV 94-0315
^ "~
W4 5' NAD Reactor Vessel N-2D Noz/ Val Weld 09/29/94 B 3. 90 Limited due to configuration andthermalwireconnection.g'NAD~
Nei Fig'5 N-2D NV 94-0314 M60 Reactor Vessel N-2D Nor/Vol Weld 09/29/94 B 3. 90 Limited due to configuration and thermal wire connection.
Ned' Fig 5 N-2J'NV 94-0308 WO' NAD Reactor Vessel N. 2J Ncz/ Val Weld 09/27/94 9 3. 90 NeiFig 5 N-2J NV 94-0306 UT45 NAD Reactor Vessel N-2J No2/Vol Weld 09/27/94 B 3. 90 Limited due to configuration and thermal wire connection.
NeiiFifb~ ~~~
' N-2J NV 94-0307 UT60 NAD Reactor Vessel N-2J Nos/ Val Weld 09/27/94 9 3.
90 Limited due to configuration and thermal wire connection.
Nes Fig 5 N.
3A NV 94-0252 WO NAD Reactor Vessel N-3A Val /Not Weld 09/23/94 B 3.
90 net Pig 5 N-3A NV 94-0250 UT45 NAD Reactor Vessel N-3A Val /Nor Weld 09/23/94 B 3.
90 net Fig 7 N-3A NV 94-0251 W60 NAD Reactor Vessel
!N-3A Vs1/Nor Weld 09/23/94 B 3. 90
~.. _.
Reactor Vessel lN-4C Nor/ Val Weld 09/24/94 B 3.
90 I
Limited due to configuration, g ppg-g- - - - - - - -
4 N-4 C NV 94-0212 UT45 NAD Reactor vessel N-4C Nos/Vol Weld 09/24/94 8 3.
90 New Fig 5' N '-"4C NV 94-0213 ~
Limited due to configuration.
W6 0 NAD Reactor vessel N-4C Nor/ Val Weld 09/24/94 B 3.
90
)
..-.-- - -. _. ~
-. - ~
$$_*0-
- t? '*E.$9"I*Yb*":_
Reactor Vessel N-5B Nos/Vol Weld 09/24/94 B 3.
90 Limited due to thermal wire I
connection.
~T0247~"
'UT45 ~ ~ ' ~ - ~ ~ '
NAD" ~
New Fig 5" ~ ~ ~
'NJ ' 5 B NV ' '
~
94 Reactor Vessel N-SB Noz/ Val Weld 09/24/94 B 3.
90 t
Limited due to thermal wire
___._L_
_____d____
connection. _,-, _,__,j_,__
01/17/95 Page 2
.~
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern states Power Company old swy 152 NN of Monticello Third Interval By source Doc #
414 Nicollet Mall Monticello, MN $5362 Commercial service Date June 30, 1971 Ninneapolis, MN 55401 Iso Item Report Number Method Results system Item Description Exam Date ASNE section XI Item New Fig 5 N. 5B NV 94-0246 ITT6 0 NAD Reactor Vessel N-5B Nor/ Val Weld 09/24/94 B 3.
90 Limited due to thermal wire connection.
New Fig 5 N-6 A NV 94-0341 UTO NAD Reactor Vessel N-6A Not/ Val Weld 10/04/94 B 3. 90
~ i Ff5 E N-BA NV 94-0341 UTES
' nab -
Ne Reactor Vessel N-8A Noz/ Val Weld 10/04/94 B 3. 90 Limited due to configuration.
New'Ffg~5 N-8A NV 94-0343 ITT60 NAD Reactor Vessel N-SA Nos/Vol Weld 10/04/94 B 3.
90 g
jLimitedduetoconfiguration.
Reactor Vessel N-2E 1os/ Val Weld 10/01/94 B 3. 90 Reactor Vessel N-2E Nos/ Val Weld 10/01/94 B 3. 90 Limited due to configuration and thermal wire connection.
Reactor vessel N-2E Nos/ Val Weld 09/29/94 8 3. 90 Limited due to configuration and thermal wire connection.
New' Fig 5 N-1 A IR' 94-0348 UT70 NA0 Reactor Vessel N-1A Inner Radius 10/04/94 8 3.100 NeiFff5~
N-2D IR 94-0311 UT70 NAD Reactor Vessel N-2D Inner Radius 09/30/94 B 3.100 Limited due to therv.al wire connection.
New' Fig 5 N-2J IR 94-0310 UT7 ')
NAD~
Reactor Vessel N-2J Inner Radius 09/27/94 B 3.100 Limited due to thermal wire connection.
New" pig 5 N-3A'IR 94-0249 LTT70 NAD Reactor Vessel N-3A Inner Radius 09/24/94 B 3.100 New'Ffg'5 N 4B IR 94-0191 (TT70 NAD Reactor Vessel N-4B Inner Radium 09/25/94 B 3.100 Limited due to thermocouple.
' 5 Ffg 5 NQ6 IR 94 0190 UT70 NAD N
Reactor Vessel N-4C Inner Radius 09/25/94 B 3.100 Limited due to thermocouple.
Reactor vessel N-5B Inner Radius 09/24/94 B 3.100 Limited due to thermal wire
. ------_---..l connection.
Reactor Vessel N-SA Inner Radius 10/04/94 B 3.100
- -. -.. ~.}
Reactor Vessel N-2E Inner s
09/30/94 8 3.100 Limited due to thermal wire connection.
Core Spray B Safe End to-Nortle 09/25/94 B 5.
10
.. ~..
-... ~ - - -
l Core Spray B Safe End to Nortle 09/26/94 B 5. 10 f
W-.. 1 94-0227 PT NAD Limited due to configuration.
l 1$1 97005 A l
Recirculation A Notale-to-Safe End 09/27/94 B 5.
10
(- -
I 10 Recirculation A Norzle-to-Safe End
!O9/27/94 l B 5.
3 i
_..___.___._t____.___-
i i
i 1
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern Statee Power Company old Bwy 152 NN of Monticello Third Interval my Source Doc 8 414 Nicollet Mall Monticello, MN 55362 Commercial service Dates June 30, 1971 Minneapolis, MN 55401 Iso Item Report Number Nothod Results System Item Description Exam Date ASKE Section II Item 1S1-97005-8 W-25 94-0294 PT NAD i
Recirc Manifold A Safe End to-Nozzle 10/01/94 B 5. 10 "1S! 9f665;B W-25 94-0363 UT45 NAD Recirc Manifold A Safe End-to-Nozzle 10/05/94 B 5. 10 ISI+97006-B W-11 94-0293 PT NAD~~~~
Recirc Manifold B Safe End-to-Nozzle 10/01/94 B 5. 10 ISI-97006-B W-11 94-0361 UT45 NAD Rectre Manifold B Safe End-to-Nozzle 10/06/94 B 5. 10 1S1-97006-8 W-18 94-0292 PT NAD Recirc Manifold B Safe End to-Nozzle 10/01/94 8 5. 10 ISI-97006-B
~~~~~-~iW-18 94-0362 UT45 NAD Recire Manifold B Safe End-to-Nozzle 10/06/94 B 5. 10 New ISi!16-~
W-1 94-0334 PT NAD Jet Pmp Instrmtation Safe End / Nozzle 8A 10/04/94 B 5. 10 New 7GI-16 W-1 94-0355 UT45 NAD Jet Pmp Instrmtation Safe End / Nozzle 8A 10/05/94 B 5. 10 ISI-97008-A W-1 94-0197 PT NAD Inst rmt Nozzle N-11 A Nozzle-to-Safe End 09/26/94 9 5. 20 New ISI-19 W-1 94-0296 PT NAD Inst Nozzle N-12A Nozzle-to-Safe End 10/01/94 B 5. 20 New IS!-19 W-1 94-0291 UT45 NAD Inst Nozzle N-12A Nozzle-to-Safe End 10/01/94 B 5. 20 New Flg 6 Nuts
~94-0338 HT NAD
~
Reactor Vessel 64 RPV Nute 10/03/94 B 6. 10 New'Fli'6~
~
Studs 94-0008 UTO NAD Resetor Vessel 64 RPV Studs 09/16/94 B 6.
20 New' Fig 6 Llgandnis~
~
~
2 94 6086 UTO NAD Reactor Vessel Ligaments 09/16/94 B 6. 40 Limited due to access triction.
e Reactor Vessel 64 Bushings 09/16/94 B 6. 50 Limited to top edge only.
New Fig 6 Washers 94-0323 VT1 IND Reactor Vessel 20 Washers 10/03/94 8 6. 50 ah
~
Pitting Waeir's- "-'-
' ~ '
94'- 0h 3Ii1 VT
'NAD~
NeifFig"6 ~
'~~
~
Reacter Vessel 20 Washers
/ /
B 6. 50 Use-as-is w/ Technical Justification.
ISI-97005-A B-2
'""9420269 VT1 '
NAD Recitculation A Pump Bolting 09/29/94 B 6.180 B 6.200 Examined in place.
97606 A ~~~ ~ ~ M B-2 94-0268 VT1 NAD 2 ~
1812 Recirculation B RC Pump B Studs 09/29/94 B 6.180 B 6.200 i
Examined in place.
ISI-97006-A B-2 94-0364 UTC NAD
]
Recirculation B
' RC Pump B Studs
..s/07/94 B 6.100 B 6.200 i
New Fig 1 B+ 1
' ~ ~ ~ ' ~ 9 6027 F - ~ ~'VTI'~
~~~~~ ^ '- ~ ~ ~ ~'-"
~NAD~
Top Head iN-6B Flange Bolts
!09/30/94 B7 10 i
01/17/05 Page 4
t menticello Nuclear Generating Plant Inservice Inspection keport Log Northern States Power Company old Hwy 152 Nw of Monticello Third Interval By source Doc #
414 Nicollet Mall Monticello, MN 55362 Commercial Service Date June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Resulta System item Description Exam Date ASME Section II Item ISI-762A-A B-2 94-0289 VT1 NAD Head Vent Flange Bolts 09/30/94 B 7. 50 ISI-93268-1-A B-1 94-0040 VT1 NAD CRD Scram Header A Flange Bolts 8 W-7 08/08/94 B 7.
50 CkD 3 cram Header A Flange Bolts e W-7 09/01/94 B7 50 ISI-93268-3-A
'B-2
~
~ ~ ~ ~ ' ~
7 94-0077
[VT1
~
NAD CRD Scram Header A Flange Bo4 e e W-1 08/C9/94 B 7.
50 i
ISI-97006-A B-3 e94-0099 1 VT1 NAD l09/20/94 l
B 7.
50 Recirculation B Flange Bolto e W-16 251-13142-33-A~
'B-1
- ~ - *94-0378BL
' VT1 IND
~
Main Steam A Flange Bolts e W 12 10/08/94 B 7.
50 Examined in placej Thread j
engagement.
ISI-13142-33-A-._
_ _ _ _.. _l B-3 94 - 03 8 CBL VT1 NAD lFlangeBolteeW-16 10/08/94 B 7.
50 Main Steam A
_. _ Examined in place.
i Main Steam B Flange Bolts a W-13 10/08/94
, B 7.
50 Examined in place.
ISI-13142-34-A B-3 94-0377BL VT1 NAD Main Steam B Flange Bolte a W-16 10/08/94 B 7.
50
.jE***$_nedinplace.
ISI-13142-35-A B-4 94-0386BL VT1 NAD Main Steam C Flange Bolte e W-18 10/08/94 B 7.
50 Examined in place.
IS1'-13142-35 A"
'- ~ ~ -~ ~ l B - 6 94-0367BL VT1 NAD
~~
Main Steam C Valve Bolts 10/08/94 B 7.
50 Examined in place.
ISI-13142 35-A B-7 94-0385BL VT1 NAD Main Steam C Valve Bolts 10/06/94 B 7.
50 j
Examined in place.
ISI-13142 36 A
'B-1 94-0382BL D T1 NAD Main Steam D Flange Bolts e W-13 10/08/94 B 7.
50 Examined in place.
ISI-13142-36-A B-3 94-0383BL VT1
- NAD~
Main Steam D Flange Bolts e W-17 10/C8/94 B 7.
50 Examined in place, ISI-13142 33-A B-1 94-0378BLR1 VT1 NAD Main Steam A Flange Bcits e W-12
/ /
B 7.
50 Use-as-is w/ Technical Justification.
3 s 3 : 1314'2'~3 5 A~
~
^ ' '!BO~~
~~ ~~
94-O B5BUEI' - ' VT1 NAD Main Steam C Valve Bolts 10/21/94 B 7. 50 Examined in place after l
-retensioning. __
4-Cote Spray A lValveBolts 09/25/94 B 7.
70 i
Examined in place.
l Inadequite thread engagement.
ISI-13142-26-A - ^
B-2 94-0194 "VT1-~~
INAD~ ~ -
i Cor-e Spray A Walve Bolts 09/25/94 B 7. 70 g
~
~
i Examined in place.
e ISI-13142-34'A - ' ~ ~ ~ ~ '
B- ~ s~
~~
-~
94-0141 l VT1 NAD Main Steam B iValve Bolts 10/08/94 lB7 70
{ VT1 Examined in place.
~~
ISI-13142! 3 4 k' '
B-7 94-0142
~
k NAD l
Main Steam B Valve Bolts 10/08/94 1B7 70 i
l Examined in place.
Isi.131's;T f.A ~ ~~
~
p.~ 9-'-
~~-
--}940125
~
~ ~* VT1 NAD 3
Main Steam D jValve Bcits 10/08/94 B 7.
70 L
_l3**_minedinplace.
g_,
I 01/17/95 Page 5
e Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Nwy 152 NM of Monticello Third Interval By source Doc 8 414 Nicollet Mall Monticelle, MN 55362 Commercial service Dates June 30, 1971 Minneapolis, MN 55401 ISD Item Report Number Method Results system Item Description Exam Date ASME Section II Item ISI-13142-36 A b-10 94-0123 VT1 NAD
[
Main Steam D Valva Bolts 10/08/94 B 7.
70 Examined in place.
'iS1 13142-42-A B-2 94-0281 VT1 NAD 2
HPCI Steam Valve Bolts 09/30/94 B7
'O
'181? N 00 f-B B-4 94-0242 VT1 IND RMF Suction A Valve Bolts 09/29/94 B 7. 70 J
] Thread engagement.
1S1-97005 A B1 94-0270 VT1 NAD Recirculation A Valve Bolts 09/29/94 B 1. 70 Examined in place.
ISI-97005-A B-4 94-0100 VT1
[NAD 1
Recirculation A Valve Bolts 09/20/94 B 7. 70 kecirculation B Bolts 09/29/94 B 7. 70 1
Examined in plac t
[
I 181!!31'42-33-i~
~
~ ~" B - 8 94-0373BL VT1 NAD Main Steam A Valve Bolts 10/06/94 B 7. 70 i
Examined in place.
181-13142-34-A B-5 94 0372BL VT1 NAD Main Steam B Valve Bolts 10/06/94 B 7.
70 Examined in place.
IS1-13142-35-A B-2 94-0371BL VT1 NAD' ~
Main Steam C Valve Bolts 10/06/94 B 7. 70 Examined in place.
ISI'-13'14 2 - 3 4 - A B-8 94-0370BL VT1 NAD Main Steam D Valve Bolts 10/Of/94 B7 70 Examined in place.
~1Sf-13142 31-A B-1 94-0139
'VT1 NAD~
Core Spray B Valve Bolts 09/22/94 B 7.
70 ISI-13142-33-A B-9 94-0379BL VT1 NAD Main Steam A Valve Bolts 10/08/94 9 7. 70 Examined in place.
ISI-13142-33.A B-30 94-0181BL VT1 NAD Main Steam A Valve Bolts 1b/08/94 B 7. 70 Examined in place.
161-13142 35-A
'B-5 94-0364BL'
'VT1 NAD~~
Main Steam C Flange Bolts a W-14 10/08/94 B7 70 l
Examined in place.
Core Spray A Valve Bolts
/ /
p7 70 Un-as-is w/ Technical Justification.
4 7 --
kHR Suction A Valve Bolts
/ /
B7 70 Use-as-is w/ Technical i
Justification.
IS1-13142-34'-A B-6
~ ~ ' '
94-0141BLR1
'VT1
~
- NAD~
Main Steam B Valve Dolts 10/18/94 B 7.
70 Reexamination after replacement.
Nei Fig 2
,06-27B 94-0419BL VT1 NAD CRD Housings lCEDHousingBolts 10/19/94 B 7.
80 l
..- _4 Main Steam A Nozzle-to-Safe End ID9/20/94 B 9. 10 t
ISI-13142-33-A
" W-1 LS D 94-0226
~ 7 UT45 NAD i
Main Steam A lNor21e-to-Safe End 09/26/94 9 9. 10 t
3st.33142 33.A~--'
~
~ wT g'ng v~ - -
'J94 010b KT NAD Main Steam A Safe End-to-Elbow
{09/20/94 B 9, 10
_.i_____.._
_.._u._..
__.____._.___I__
)
l i
01/17/95 Page 6
s Monticelle Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Nwy 152 NW of Monticello Third Interval By Source Doc #
414 Nicollet Mall Monticello, MN 55362 Commercial Service Dates June 30, 1971 Ninneapolis, MN 55401 180 Item Report Number Method Results System item Description Exam Date ASNE Section XI Item Is!-13142-33-A W-2 LS U 94-0119 UT45 NAD Main Steam A Safe End to-Elbow 09/21/94 9 9. 10
'151 93268 1 A-
"~
CRD Scram Header A Reducer-to Pipe 09/23/94 B 9. 10 ISl+93268-1 A W-9 LS U&D 94-0177 UT45 GEO CRD Scram Header A Reducer-to-Pipe 09/23/94 B 9. 10 IS!-93268 1-A W-30 LS U6D 94-0096 PT NAD CRD Scram Header A Pipe-to Elbow 145e) 09/19/94 B 9. 10 CRD Scram Header A Pipe-to-Elbow (4 5e) 09/20/94 8 9, 10 1st;g3268-3'A-
~^
~
W '- 2 9 LS ' U6 D'~~ --" ~
' '9410138- ~ ~ ~ ~ PT~ ~ ' ' ~~
~ ~ ~ ~
"NAD~
~'
CRD Actam Header B Elbow-t o Elbcr-09/22/94 B 9.
10 ggg;93268 3 A ~ ~ ^ ' ~ ' ~ ~ W 2 9LS '~U&D-~
94-0146 UT45 GEO I
' ~ ~
CRD Scram Header B Elbow-to Elbow 09/22/94 B 9. 10 ISI 97005-A W-14 LS U 94 0356 PT NAD Recirculation A Elbow-to-Pump 10/05/94 B 9, 10
- - -.... ~... -.
Recirculation A Ellow-t o Pump 10/06/94 B 9.
10 Limited due to configuration.
IS1-97005-B W-21 LS UsD 94-010)
PT NAD Recarc Manifold A P2pe to-Tee 09/20/94 B 9. 10 1S! 97005 B W-21 LS UkD 94-0100 (TT4 5 NAD Recite Manifold A Pipe-to-Tee 09/21/94 9 9.
10 ISIE97006 A"
' ' ~ ~ ~ "~ M14'US'ti'~
~~- ~ ] 94-0236 PT NAD i
2 Recirculation B Pump-to-Pipe
'09/27/94 9 9. 10 ISI-97006-A ~ ~ ~ ' ~ ~ WA14'LS D~ ~ ~ ' ' ^ ~
~ ~ ' ~ '
94!0217~~~
'UT4h'- ~ ~ ~ ~ ~ ' - -~ NAD-Recirculation B Pump to-Pipe 09/27/94 8 9.
10 Limited due to configuration.
ISI 97006 A'
'~
~ H-17'LS'd"
'94-0234 PT
" ~ ~ ~ ~
'NAD-T Recirculation B Pipe-to-Valve 09/27/94 B 9.
10 ISI 97006-A"
-- ~ '
~
W 17'LS'U' ~ ~ ~ ~ " - ~ ~
~ N-0218-~~
~VT45'
~ ~ ~ ~ "
nab ~
l Recirculation B Pipe-to-Valve 09/27/94 B 9.
10 Limited due to configuration, 181-97006 A W 18 LS D 94-0235 PT NAD Recirculation B Valve-to Bent Pipe 09/27/94 B 9.
10
'W 18'LS D~
94-0219~ ~ ~ ~ ~ ~ UT45 ~ ~'~ ~'~"~~~ ~ ~~NAD-J IS1297C06 A ~
I Recirculation B L'a l ve - t o-B en t Pipe 09/27/94 9 9. 10 Limited due to configuration.
IS1-97006-A W-19 LS UkD 94-0271 PT NAD Recirculation B
, Eltmw t o-Pipa 09/29/94 D 9. 10 1
ISi-970)6 A~
~
~
W-19 LS U6D 94-0279
' UT45 NAD Recirculation B Elbow-to Pipe 09/30/94 B 9. 10 1st:9 7 0 66 - B
~
~
'W 12 IS U6D" 94-0092 PT NAD Recarc Manifold B Tee-to-Reducer 09/21/94 B 9.
10
~1gg.97006 B' W-12 LS U6D '
9410182'
' ~ - ~N UT45 NAD Recire Manifold B Tee-to-Reducer 09/24/94 B 9, 10 l
~J ISI-93240-3 A' '
W 29 LS UkD 94-0146R1 "l UT45 NAD A
j CRD Scram Header B Elbow-to Elbow 10/01/94 f B 9.
10 g
jReport for long seam ommitted j
l on original exam.
l 01/17/95 Page 7
Monticello Bruclear Generating Plant Inoervice 2nspection Report Log Northern States Power Company Old Ewy 152 Ent of Monticello Third Interval By Source Doc #
414 Nicollat Mall Monticello, MN 55362 consmarcial Service Date: June 30, 1971 Minneapolis, MN 55401 280 Item Report Number Method Results System Item Description Raam Date ASME Section II Item ISI-13142-26-A W-13 94-0157 PT NAD Core Spray A Pipe-to-Valve 09/23/94 B 9,11 ISI-13142 26-A W-13 94-0147 UT45 NAD Core Sprey A Pipe-to-Valve 09/23/94 B 9.
11 Limited due to configuration.
ISI-13142-26-A W-14 94-0158 PT NAD Core Spray A Valve-to-Pipe 09/23/94 8 9.
11 ISI-13142-26 A
'-' W-14 94-0148 UT45 NAD Core Spray A Valve to-Pipe 09/23/94 B 9, 11 Limited due to configuration.
ISI-13142-31-A W-14 94-0187 E
NAD k
Cose Spray B Bent Pipe / Safe End 09/25/94 B 9.
11
--....~...y Core Spray B Bent Pipe / Safe End 09/26/94 B 9, 11 ISI-13142-33-A W-5 94-0106 i MT NAD 5
Main Steam A Elbow-to-Pipe 09/20/94 B 9. 11 ISI-13142-33-A W-5 94-9118 UT45 NAD Main Steam A Elbow-to Pipe 09/21/94 B 9. 11
' ~io
-'~~~- ~ - -
94 603 MT
'NAD-~~~~
W ISI-13i42 35 A'~' - ~
Main Steam C Pipe-to-Elbow 09/22/94 B 9. 11 ISI-13142-35 A W-10 94-0129 UT45 NAD Main Eteam C Pipe-to-Elbow 09/22/94 B 5. 11 ISI-13142-35-A lW-11 94-0132 W
NAD Main Steam C Elbow-to-Elbow 09/22/94 B 9. 11 e
ISI-13142'!35 A W'-11 94-0128 UT45 NAD l
7 Main Steam C Elbow-to-Elbow 09/22/94 8 9. 11
~
ist.'ii142-35"A- ~
W 12~ ~ ~ ~ ~ - ' ~ ~ ~ ~ ~
9476135
-~MT N4fi~
Main Steam C Elbow-to-Pipe 09/22/94 9 9. 11
-. - ~
Main Steam C F1 bow-to-Pipe 09/22/*4 8 9. 11 Limited due to support restriction.
ISI-13142-36-A
,W-8 94-0192 MT NAD Main Steam D Elbow-to-Pipe 09/25/94 B 9, il ISI-13142-36-A W-8
~~
l94-0199 LTT45 NAD Main Steam D Elbow-to-Pipe 09/26/94 B 9.
11 ISI-13142-36 A W-25 94-0189 MT NAD I
Main Steam D Elbow-to-Pipe 09/25/94 8 9.
11
' If1 'i 314 2'- 3 6'- A '
~ W-25 94-0200~-
ifT4 5
- NAD 2
Main Steam D Elbow-to-Pipe 09/26/94 B 9.
Il 1
~- ~ ~-~ - ~'
~~NAD-3 3 3. } '314 2 4 2 - A' - - ~ ~~'
-I y '. 2 3-~
' ~ ' ~ - ~ ~ 94!bg ' i -
'MT 3
Feedwater Pipe to-Elbow 09/22/94 B 9. 11 3
1 W-21'-~-"
~
~~
'94 4144~-~
'UT4 5 "
'NAD Igg.1'542 42 A'
~~
~^
Feedwater Pipe-t o-Elbow 09/22/94 B 9, 11 i
Limited due to configuration.
~
~'
94-0136 M ~~ " "
"- - '~ ~ ~~"'~ " NAD 151 13'142 - 5 2; A '
W-22 ' ~
~ ~ ~ ~ '
'~#
Feedwater Elbow to-Pipe 09/22/94 B 9.
11 1
'~ } UT4 b'~
"NAD 151-13142-52 A' i W-22
~94-0145 Feedwater Elbow-to-ripe 09/22/94 l B 9, 11
]Limitedduetoconfiguration.
Page 8
01/17/95
o Monticello Nuclear Generating Plant Inmarvice Inspection Report Log Northern States Power Campany old Ewy 152 NW of Moaticello Third Interval By Source Doc #
414 Nicollet Mall Monticello, por 55362 Commercial Service Date June 30, 1971 Minneapolle, NW 55401 ISO Item Report Number Method Resulte System item Description Eaam Date ASKI Section XI Item ISI-13142-52-A W-23 94 0173 MT NAD Feedwater Pipe-to-Safe End 09/25/9; B 4. 11
'lSIT )ief!S2'-A~
W-23 94-0168 tfr4 5' NAD 1
Feedwater Pipe to-Safe End 09/25/94 8 9. 11 b**
- #*"'S"**
Feedwater New S.E.-to-Old S.E.
09/25/94 B 9. 11 ISI-13142-52-A W-24 94-0166 ITT45 NAD Feedwater New S.R.-to-Old S.E.
09/25/94 B 9. 11 ISI-13142-52-A W 25 94-0170 MT NAD
+
J Feedwater Safe End to-Nozzle 09/25/94 B 9. 11 151 13142-52-A W-25
'94-0167 UT45 NAD Feedwater Safe End-to-Nozzle 09/25/94 B 9. 11 Limited due to conf _iguration.
Feedwater Pipe-to-Pipe 09/29/94 9 9. 11 ISI-13142-53 A W-26 94-0266 ITT4 5 NAD Feedwater Pipe-to-Pipe 09/29/94 B 9. 11 Limited due to eurface.
ISI-13142-53-A W-32 94-0206 MT NAD Feedwater Pipe-to-Elbow 09/26/94 B 9. 11 ISI-13142-53-A W 32 94-0258 UT45 NAD Feedwater Pipe-to-Elbow 09/29/94 8 9.
11 ISI-13142-53-A W-33 94-0205 IMT NAD-Feedwater Elbow-to-Pipe 09/26/94 9 9. Il 94-C259 UT45 NAD ISI-13142-53-A
}W 33 Feedwater Elbow-to-Pipe 09/29/94 B 9. 11 ISI-93268-1-A W-6 94-0165 PT NAD CRD Scram Header A Pipe-to-Tee 09/23/94 B 9. 11 IS1-93268-1-A W-6 94-0176 LTT45 NAD CRD Scram Header A Pipe-to-Tee 09/24/94 8 9. 11 CKD Scram Header A Flange-to-Tee 09/23/94 B 9. 11
[NAD~~~~~
ISI-932(F 1 A W-7 94-0175 UT45 CRD Scrae tier A Flange-to-Tee 09/24/94 9 9. 11
. Limited due to configuration.
i CRD Scram Header B Pipe-to-Tee 09/19/94 B 9. 11
~~~' iri-151 93268-3-h'
~ ~
W-6
~ 94!010E
~UTO T
~'
N CRD Scram Header B Pipe-to-Tee 09/20/94 9 9. 11
+'~4-0212~ ~ ~ ~ ~ ~
'~
~ '
NAE ~~ '
9 -
1510 7003-B~
jW-17 RHR Suction A Valve-to-Elbow 09/28/94 B 9. 11
~1SI!97003'H
~~iW-17 94 0237 UT45 NAD 9.HR Suction A l Valve-to-Elbow 09/28/94 B 9.
11
_.-__.._ _ _ -3 Limited due_t_o_ configuration.
q.
l09/28/94 RHR Suet ion A Elbow-to-Pipe 8 9.
11
..-_.m l
l RHR Suction A Elbow-to-Pipe 09/28/94 B 9. 11 l
I
-.-. i.. - -... -. - -. - -..
1 I
01/17/D5 Page 9
i l
=
I
~.
I Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern Statee Power Company Cid Ewy 152 NW of Monticello Third Interval By source Doc #
414 Nicollet Mall Monticello, MN 55352 Consnercial service Dates June 30, 1971 Minneapolis, MN $5401 180 Item Report Number Method Resulte 6ystem Item Description Exam Date ASME Section II Item ISI-97004 A W-4 94-0171 Mr NAD RRR Return B Pipe-to-Elbow 09/25/94 8 9. 11 f
IS!!97004-A W-4 94-0203 UT45 NAD RHR Return B Pipe-to Elbow 09/25/94 B 9. 11 ISI-73080-A W 21 94-0183 MT NAD~
P.eactor Wtr Cleanup Pipe-to-Elbow 09/24/94 B 9. 11 ISI 73680-A W 21 94-0165 UT45 NAD Reactor Wtr Cleanup Pipe-to-Elbow 09/24/94 8 9. 11 L
~1SI 73880-A W-22
~
~
94-0181 MT NAD Reactor Wtr Cleanup Elbow-to-Valve 09/24/94 8 9. Il ISI-73680 A W-22 94-0184 W4 5 NAD Reactor Wt r Clear.up Elbow-to-Valve 09/24/94 B 9.
11 Limited due to configuration.
181 97005-B W-24 94-0295 Fr NAD Recirc Manifold A Pipe to-Safe End 10/01/94 B 9.
11 Recirc Manifold A Pipe-to-Safe End 10/03/94 B 9. 11 Limited due to configuration.
ISI-97006-B W-13 LS U&D j94-0091 PT NAD Recirc Manifold B Reducer-to-Pipe W/21/94 B 9.
11
,,,,., _ _ ~,.,,,,,,,
4,,,,,,
Recire Manifold B Reducer-to-Pipe 09/20/94 B 9. It Limited due to.iupport restriction.
+ _. _
i Pi 09/21/94 B 9.11 h
pe-to-Elbow Recire Manifold B
~j,,,,7 c, i,. g- --~ ~ --" - ' - - ' - w.14 LS U6D 94-0095 W45 NAD Rectre Manifold B Pipe-to-Elbow 09/20/94 B 9.
11 RHR Equaliser Pipe-to Elbow 09/20/94 8 9. 11
._ _ _ _. _ _...._.. f RHR Equaliger Pape-to-Elbow 09/20/94 9 9.
11 RHR Equaliger Pipe to-Elbow 09/20/94 B 9.
11 kHR Equalizer Pipe to-Elbow 09/2C/94 8 9.
11 ISI-97003 A '
' ~
- W-4 94-0172 MT tNAD-~
2 RHR Return A Pipe-to Elbow 09/25/94 8 9. 11 ISI-97003-A W-4 94-0207 UT45 GEO RRR Return A Pipe-to-Elbow 09/25/94 B 9, 11 ISIll3142-33-A~ ~'
iW-34~~~~~
94-0366BL MT NAD Main St eam A Pipe-to-Valve 10/08/94 8 9. 11 ISI-13142-33-A
~ " W-32 94-0404BL~
UT45
~ ~ ~ -
GEO~
~
! Pipe-to-Valve 10/10/94 B 9, 11 i
Limited due to configuration.
ISIL1.314 2 A'
~'~
]W-33
]94-0367hb
~
MT NAD Main Steam B IPipe-to valve 110/07/94 B 9. 11 l
181 13i42-3e A~
~
~
W-33 94-0405BL ~ ~ ~ ~ ~ ~
W4 5 NAD
~
Main Steam B l Pipe-to-Valve 10/10/94 9 9.
Il b _ _. _.
Limited due to configuration.
01/17/05 Page 10
Monticello Nuclear Generating Plant inservice Inspection Report Log Nosthern States Power Company Old Nwy 152 NW of Monticello Third Interval By Source Doc #
414 Nicollet Mall Monticello, MN $5362 Commercial Service Date: June 30, 1971 Minneapo11e, NM 55401
{
ISO Item Report Number Method Results System item Description Emas Date ASME Section II Item 94-D368BL MT NAD IS1-13142-M-A lW 34 Main Steam C Pipe-t o-valve 10/07/94 B 9. 11 iSI-1'314 f A W-34 94-0406BL UT45 NAD ~ ' ~
Main Steam C Pipe-to-Valve 10/10/94 B 9. 11 Limited due to configuration, ggggg,3g3-- - - - -
Wi35 94-0369BL
' MT NAD Main St *am D Pipe to-Valve 10/07/94 8 9. 11 161-13142-36-A W-35 94-0402BL UT45 GEO Main Steam D Pipe-to-Valve 10/08/94 8 9. 11 Limited due to configuration.
[
ISI-73880-A W-7 94-0290 UT45
'NAD
~
I Reactor Wtr Cleanup Elbow-to-Valve 09/27/94 8 9. 11 ISI-13142 33 A W-32 94-0397BL UTO NAD 7
Main St eam A Pipe-to-Valve 10/10/94 B 9.
11 Limited due to configuration.
ISI-13142-34-A W-33 94-0398BL UTO NAD Main Steam B Pipe-to-Valve 10/10/94 B 9. Il Limited due to configuration.
151-13142 36-A W-35 94-040'0DL UTO NAD I
Main Steam D Pipe-to-Valve 10/08/94 B 9. 11 Limited due to configuration.
IS! 13142-35-A
'"W-34 94-0399BL tTI'O '
NAD Main Steam C Pipe t o-Valve 10/10/94 B 9. 11 Limited due to configuration.
IS1-13142-43-A W-9 94-0150 MT NAD RCIC Steam Pipe-to-Elbow 09/23/94 B 9.
21 IS2 13142-43-A W 10 94-0149 MT NAD RCIC Steam Elbow to-Pipe 09/23/94 8 9. 21 "94 0156
~--
MT' NAD 2
ISA-7e6-A W 10 MS Condensate Lkoff Elbow-to-Pipe 09/23/94 B 9. 21 Main Steam D Pipe-to-Sweepolet 09/22/94 B 9. 31 l
Main Steam D Pipe-to Sweepolet 09/22/94 B 9. 31 l
Limited due to configuration.
151-97003 H W 12 94-0204 MT NAD RHR Suction A Branch-to-Pipe 09/26/94 B 9. 31 151-97003-9'
~
W-12 94-0260
'UT45- ~ ~ ~ ~ ~ ~ ~ ~ ~
NAD RHR Suction A Branch-to-Pipe 09/28/94 B 9. 31 IS1-74209-1-A 1' W - B 94-0223
~
~NAD-Recirc A Drain Line
' Pipe-to-Valve 09/27/94 B 9. 40 181 74209-1-A~
"i lW-7 94-0222 PT NAD Recirc A Drain Line ITee-to-Pipe 09/27/94 8 9. 40 ISI-74215 A W-7 94-0135 PT IND Standby Liquid Cntrl Pipe-to-Head Pitting 09/22/94 B 9. 40 Multiple indications.
]PT 181 14215 A iW-15 94-0282 NAD Standby Liquid ent rl Pipe-to-Valve 09/30/94 8 9. 40
. _... _ _... _ _. - - -.- q Head vent l Tee-to-Pipe 09/23/94 B 9. 40 ISI-782-A' ' ~
~
~1
~
9420162
~ ~ - ' ~
~PT NAD jW-27' Head Vent 1 Pipe to-Valve 09/23/94
, B 9.
40 i
i I
L_.______
l 01/17/95 Page 11
t Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old swy 152 NW of Monticello Third Interval By Source Doc 8 414 Nicollet Mall Monticello, MN 55362 Commercial service Date: June 30, 1971 Ninneapolis, MN 55401 130 Item Report Number Method Results system Item Description Exam Date ASME Section II Item ISI-782-A W-29 94-0160 FT NAD Head Vent Valve to-Pipe 09/23/94 B 9. 4 0 3SI-786-A W-28 94-0151 M
NAD MS Conder. sate Lkoff Elbow-to-Pjpe 09/23/94 9 9. 40
....--_)
MS Condensate Lkoff Pipe-to-Elbow 09/23/94 99 40 3SI-786-A W-30 94-0163 MT NAD MS Condensate Lhoff Elbow to-Pipe 09/23/94 B 9. 40 ISI-786-A W 31 94-0154 MT NAD MS Condensate Lkoff Pipe-to-Elbow 09/23/94 B 9. 40
'Isil?8 6 A "
W 32 94-0155 MT NAD MS Condensate Lkoff Elbow to-Pipe 09/23/94 B 9. 40 1SI-821-A W 23 94-0331 M
NAD Bottom Head Drain Pipe-to-Coupling 10/04/94 9 9. 40
___._-_.t-Bottom Head D:ain Coupling-to Pipe 10/04/94 B 9. 40 Bottom Head Drain Pipe to-Elbow 10/04/94 B 9. 40 Bottom Head Drain Elbow-to-Pipe 10/04/94 B 9. 40 ISI-93268-1 B W-16 94-0085 PT NAD CRD Sesam Hdr Disch Elbow to-Pipe 09/17/94 B 9. 40 ISI-97006-A W-2 94-0195 PT NAD instrmt Nortle N 11A Safe End to-Coupling 09/26/94 B 9. 40 Instrmt Netzte N-11A Coupling-to-Pipe 09/26/94 B 9. 40
_ _ _. ]
Inst Norsle N-12A Safe End to-Reducer 10/01/94 B 9. 40
_4 Standby Liquid Cntrl Pipe-to-Head Fitting 09/28/94 B 9. 40 Reworked ISI-782-A W-23A 94-0300BL PT NAD Head Vent Pipe to-Coupling 30/03/94 B 9. 40
-4 Head Vent Coupling-to-Pipe 10/C3/94 B 9.
40 I
(.--..
Head Vent Pipe-to-coupling 10/03/94 B 9.
40 i
,,, y _ _
.y Head Vent Coupling-t o-Pipe 10/03/94 l B 9.
40 fv73 - - -
-~~~ ~ ~ ~ ~ NAD~
1st ni42.n A~
~ ~
" v i ~4 ~~ - -'
I94 0324BL Main Steam A Valve Int Surfaces 10/04/94 i B12. 50 I
I sl:13142a4 - A '
' V74'
~~
~~ f 94J0325BL ~ ~ VT3 ~~' ~~
~~~
'NAD~~~~~
j10/04/94
( B12. 50 Main Steam B Valve Int Surfaces i
~
IV+ 4 94!0 32'6 BL ' '-- '~
VT3 NAD
~
lValveInt 10/04/94 B12. 50 Surfaces 5
Main St eam C
..A.-._.--.__-
a
.-.__..m-.--
l 01/17/05 Page 12 l
1 1
l i
I Wonticello Nuclear Generating Plant inservice Inspection Report Log Northern States Power Company Old Bwy 152 Nw of Monticello Third Interval By source Doc #
414 Nicollet Mall 1
Monticello, MN 55362 Cosmarcial service Dates June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results system item Description Exam Date ASME Section EI Item ISI-13142-36-A
-V-4 94-0327BL VT3 NAD Main Steam D Valve Int surfaces 10/04/94 B12, 50 "151-13142-31-A V-1 94-0140 VT3 NAD Core Spray B Valve Int Surfaces 09/22/94 B12. 50 ISI U3142-33-A V-3 94-0414~
VT3
~~
~ ~~~"NAD~ ~ ~
Main Steam A Valve Int surfaces 10/06/94 B12. 50 ISI-13142 35-A V-1 94-0225 VT3 NAD Main Steam C Valve Int Surfaces 09/26/94 B12. 50 ISI-13142-36-A' V-2 94-0224 VT3 NAD " '
Main Steam D Valve Int Surfaces 09/26/94 B12, 50 T 5i42-36 A' ~
] V-1 T
3 94-0174 "VT3 NAD ISI Main Steam D valve Int Surfaces 09/24/94 B12. 50
'3sg.1314).42-A
~
V7 I~
~ ~ ~ ~
-~ ~ ~ ~
94-0280 VT3 NAD HPCI Steam Valve Int Surfaces 09/30/94 B12, 50 ISI-13142-26-A V-3 94-0375BL VT3 NAD Core Spray A Valve Int Surfaces 10/10/94 B12. So ISI-13142-53-A V-3 94-0374 VT3 NAD Feedwater Valve Int Surfaces 10/08/94 B12, 50 T '3142 4s-A '
~ ~~
VU'
~ ~ ^ ~ ~ " ~ ~ ~ ~ ~ ~
94-0413BL
'VT3
-NAD 1
T
^
ISI HPCI Valve Int Surf 10/12/94 B12. 50 ISI-7905-32-A W-1 94-0049 LTr45 NAD RHR Heat Exchanger A Top Flange to Shell 08/10/94 C 1. 10 Limited due to configuration.
} MT NAD ISI 7905 52-A~ ~ ~ ' " '
N-2 94-0014 J
7 RHR Heat Exchanger A Shell-Pad-Noz 08/04/94
' C 2. 31 3SI-13142-17-A W-14 94-0031 MT NAD RHR Suction A Elbow-to-Elbow 08/08/94 C 5. 51 ISI-13142-1% A'~
~ ~^ ~
'lW-14 94-0050 UT45 NAD kHR Suction A Elbow-to-Elbow 08/10/94 C 5. 51 ISI-13142 18-A W-22
~794-0041 KT NAD RHR Discharge 9 Pipe-to-Elbow 08/12/94 C 5. 51 JS3i13142 16 A~
~ W-22
" I'~94 - 0 0 56 UT4h NAD 2
RHR Discharge B Pipe-to-Elbow 08/15/94 C 5. 51 ISI-13142-19-A'-
W- '7
~
94-0068 (TT4 5
~NAD HPCI Steam Disch Pipe to-Elbow 08/22/94 C 5. 51 2 S g'-13 3 4 2 '-2 0 B ~
~~fW
' i 71
~ ~ - ' ~ ~ - ~ ~ "
94-0081 MT IND Core Spray A Torus Penn-to-Elbow 09/16/94 C 5. 51 1
Two linears.
131-13142-20 9
- W-1 94-0084 UT45 NAD l
Core Spray A i Torus Penn-to-Elbow 09/16/94 C 5.
51
- - ' ~ ~ ' ' ~ ~ ' ' ~ ~ ~ ~ - - ^
ISId 3142-20-B
~ ~~
W-~4'-~-
~ '-~~
' 94-bO8f ~ ~'~ ~
MT NAD Core Spray A
. Pipe-to-Elbow 09/16/94 C 5. 51 ISI-13142-20 B W-4 94-0083
' 'tTr4 5 NAD 2
Core Spray A l Pipe-t o-Elbow 09/16/94 C 5. $1 1
1 '069" ~
] KT NAD ISI 13142-20 B 1' h -2 3~~
~~ ~ 'i 0
94 i
Core Spray A Elbow-to-Pipe 08/23/94 C 5. 51 u.
...L__._
01/17/95 Page 13
8 e
Monticello Nuclear Generating Plant Insarwice Inspection Report Log Northern States Power Company Old Rwy 152 mw of Monticello Third Interval By Source Doc 0 414 Nicollet Mall Monticello, NW 55362 Comunercial service Datet June 30. 1971 Ninneapolis, NM 55401 ISO Item Report Number Method Resulte System Item Description Exam Date ASME Section II Item 181-13142-20 B W-23 94 007f, UT4h NAD Core Spray A Elbow-to Pipe 08/25/94 C 5. 51
_ _ _ _ - _ _. ~
-_..4
.I.ed_due to configu, ration.
Core Spray A Elbow to-Pump 08/23/94 C 5. 51 Core Spray A Elbow-to-Pump 08/25/94 C 5. 51 Limited due to configuration.
'W 2 2 ' ' ~ ~ ~
94;0006~ ~ ~
Mr"~~~'~~~~'~~~~~NAIi' ~
igg 131'42 4 0'A
' ~ ~ ' '
J
~
HPCI Water Side Ds.h Valve to Pipe 08/02/94 C 5. 51 W 22~~~~
'^
^~^
94A000f ^ '~
UT45'~ ~ ~ ~ ~ ~ ~ ~ ' 'NAD~~
IS! l'3142-40 A"~
~ ~
l
~
HPCI Water Side Dsch Valve to-Pipe 08/03/94 C 5. 51 IS! 13142-4N A
' W 18' 94-0395BL"
' ' ~
Kf~'^ ~ ' ~ ~ ~ ~ " ' ~
NAD~
HPCI Steam Valve-to-Tee 10/10/94 C 5. 51 28Ik13142142'-A '
WJ18'
~ ~
' 94'-0403BL~
~
UT45 ~
^ ~ ~ ~ ^ ~
GEO-'
HPCI St eam Valve-to-Tee 10/11/94 C 5, 51 Limited due to configuration.
1 043~ ~ ' ~ ~
'MT"~~-'^~~~-~~NAD
'-^'
0
~
13142 49 A'
~
~
'Wilb~"
~'~
~
94 2 2 IS1 kHR Suetion A Elbow to Pipe 08/12/94 C 5. 51 1SI 13142-49-A W 15 94 0064 UT45 ~ ~ ' " ' ' '
'~
NAD~
RHR Suction A Elbow to-Pipe 08/18/94 C 5. 51 W 25 ~
'~
~~ ~ '
9420073
' ~
'MT~~
~-~~~
~~~1 ND' ~
Isi 13146 51 A' J
~
T RHR Discharge A Reducer-to-Nossle 08/24/94 C 5. 51 Linear ISI 13142-51-A W-25 94-0072 UT45 GEO kHR Discharge A Reducer to-Nozzle 08/24/94 C 5. 51 Limited due to configuration.
3.st 13142-18 A ~
"W-14~ ~ ~ '
' ~ ~ ~ ~ ~ ~ '
~ 94f0042
^
MT'
~'~
~ " ~ ~ ' ' ~
NAti~
3
~
Mut Discharge B Tee-to-Pipe 08/12/94 C 5. 51 ISI-13142-18-A~
'W-14^^
~
~~"94J0055 ~
~~
UT4 s~ ~ ~ ~ " ~' ~~
' NAli RHR Discharge B Tee t o-Pipe 08/15/94 C 5.
51
}sI-33142 19;A'
'W-'7 -
~~
~~
94100$7~ ~ ~ ~ ' ' '
' MT ' '- ~ ~ ~
~ ~ ~ -
NAD-J HPCI Steam D h
Pipe to-Elbow 08/22/94 C 5. 51 1s! 13142 51 A"
' j W'- 2 5 '
94 0073R1~
Kr'-~
~ ~ ~ ~ ~ ~ ~
~NAD
1 1 RHR Discharge A
' Reducer -t o Norrle 08/24/94 C 5.
51 Reworked.
IS1113142-20-B ~
WJ l'~~~
~
' 94-0081R1~'
MT~
~^
' - ' ~ ~
~
'NAD' ~
Core Spray A Terus Penn-t o-Elbow 09/28/94 C 5.
51 keworked i
ISI-13142-42 A~
W-45 ~
' 94-0360BL~
Drr' ~ ~ '-~~~~~ "
NAD ' ~
HPCI Steam Pipe-to Valve 10/06/94 C 5. 51 ISI-13142 ' 42 A '
' ' ~ ~ ~
W45'
~'
~
" 94704i6B6 "UT4f'~ ~~ ' ~ ~~
~~
NAD~~
HPCI Steam itipe-to-Valve
/ /
C 5. 51 13142 42-A' W 45-
~
94 Os59BL~~
MT ' '
~ ~ ~ '
~
NAD~~
2 IS!L HPCI st eam Va lve-t o-Pipe 10/06/94 C 5. $1 ISi-13142 42-A ~
,W-4s"
~
' 94 0417B5
'~
' tTT4 5~~
~ ~
~
NAD J
fValve-to-Pipe
/ /
C 5.
51 HPr! Steam i 94 0032
~ MT
'NAD iSI-13142-17;A~
WIS kHR Suction A
) Pipento Weldolet 09/08/94 C 5.
81 IS111!!i4 6 42-A
,W-21A 94 0394BL MT NAD HPCI St eam IPipe-to-Pipe 110/10/94 C 5.51 I
l
_ _ __ L.. _ _ _ _. _
F*9e 14 01/17/05
e Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Rwy 152 NW of Monticello Third Interval By Source Doc 8 414 Nicollet Mall Monticello, MN 55362 Consrercial Service Dates June 30, 1971 Minneapolis. NN 55401 ISO 2 tem Report Number Method Results System Item Descriptica Emma Date ASME Section XI Item ISI-13142 42-A W-21A 94-0391BL UT45 NAD HPCI Steam Pipe-to-Pipe 10/10/94 C 5.51 ISI 13142-42-A W-218 94-0393BL MT NAD HPCI steam Pipe-to Pipe 10/10/94 C 5.51 j
'ISI 13142-42 A' W-21B" 94-03899L UT45
~NAD HPCI Steam Pipe-to Pipe 10/10/94 C 5.51 HPCI Steam Pipe-to Pipe 10/10/94 C 5.51 W 21A
- - - - ' ~ ~94'!0390BL~~~
'UTO NAD
~1SEi3142 42 A!~~~~
i 7
HPCI Steam Pipe-to-Pipe 10/10/94 C 5.51 ISI-13142-17-A H-9 94 0011 VT3 IND~
RHR Suction A Slide 08/04/94 P-A,B,C Thread engagement and missing weep hole.
ISI-13142-17-A H2 94-0013 VT3 IND RHR Suction A Slide / Clamp 08/04/94 P A,B,C Missing weep hole.
ISI-13142-17-C H-4 94-0059 VT3 NAD RHR Suetion B Slide 08/17/94 F A,B,C RHR Suetion B Strut / Clamp 08/17/94 F-A,B C 1Si.'1)i42 18 B H-2
'94-0005
~VT3 NAD
! 7
~
RHR Discharge B Variable Clamp 08/25/94 F-A,B,C ISI-13142-18-C H-1 94-0058 VT3 NAD RHR Discharge B Strut / Clamp 08/17/94 F A,B,C
~ F0007^
VT3 NAD l
1s g ;i j i 4 2'.'19. A'
~ ' ~ ~
HT'l~ ~ ~ ~
~ ~ ~ ~ - ~
9 HPCI Steam Disch
. Snubber / Clamp 08/02/94 F-A,B,C
_. _ _ _ _. 1 HPCI Steam Disch Db1 Snubber / Clamp 08/22/94 F-A,B,C 181-13142 20-B H-1 94-0003 VT3 NAD Core Spray A variable 08/01/94 F-A,B,C ISI-786-A H-2 94-0265 VT3 NAD MS Condensate Lkoff Box Support 09/29/94 F-A,B,C 7 114BL~
~VT3~-
~NAD~
l ISI'13142 3F A~
~
'H73~~~ ~ ~~~-- ~
94
~
7 0
Main Steam A Snubber / Clamp 09/21/94 F-A,B,C f
iS1513142-33 A
~ ~~ { H-4 94 0126 VT3 IND
' 1 Main Steam A IVarible / Spring 09/21/94 P-A,B,C l
Drawing compliance.
IS! i3i42 36"A H-5 94-0121 VT3 NAD Main Steam D Snubber / Clamp 09/21/94 P-A,B.C t
'1SI-13342-36 A H-6 94-0122 VT3 IND Main Steam D Snubber / Clamp 09/21/94 F-A,B,C Loose bolt andfluidleakage.!
Isil '31'42 37-B^
~
fH-l 1
1 94 ')C 2 8 VT3 1ND Containment Stray lVersableSpring 08/05/94 F-A,B.C M. _#2"W ""Eh_ _.. -.
Containment Spray St rut / 8 Lugs l08/05/94 lF-AB.C f
I
^
igg.13i42-37-B~
~~~
' HT4' ~ ~ ~
~~ '
'94-0027
"~ ~~
VT 3 ' -~ '-' ~
~ ' ' ' '
~
IND '
Containment Spray IVariable Spring 08/05/94 F-A.B.C Improper load settings f
Page 15 01/17/05 m__________________
p- -
l Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Nwy 152 NW of Monticello Third Interval By Source Doc #
414 Nicollet Mall Monticelin MN 55342 Commercial service Dates June 30, 1971 Minneapolis, MN $5401 130 Item Report Number Method Results system Item Description Exam Date ASME Section XI Item stamped.
ISI-13142-37-C H-1 94-0010 VT3 IND FHR Discharge A spring / Clamp 08/04/94 F A,B,C Drawing conformance, extra parts and missing welds.
H 14'
~^
~ ~
- ISI 1314f-40-A
2 94-0004 VT3 IND HPCI Nater Side Dsch Seismic Restraint 08/01/94 F-A,B,C ISI-13142'42-A~
'H 2
'94'-0392
~ Thread engagement VT3 IND HPCI Steam Spring / Clamp 20/10/94 P-A,B,C Loose bolt and load below I
allowable.
ISIll3142-42-A' HJ5'
~
9410035-^
~
~
~ VT3 ~ '
'" ~ ~ ~
~ ~ ~1 nab ~
~
HPCI Steam Spring / Clamp 08/09/94 P-A,B,C
~T6 ~"
'vi '.35 VT3'~~~~
~ ~' ~~~
~
~~
NAD H
ISI 13142 42 A ^
~~
i HPCI Steam Spring / Clamp 08,,9/94 F-A.D,C ISII13142-42-A
HT7
~ ~ ~ ~ ~
94-0037'
'~
~
VT 3 '~~' ~ ~ ' '
- - ' - ~
" I ND' '
HPCI Steam Spring / Clamp 08/09/94 F A, B, C Setting outside of allowable.
ISIE13142 49 A
' H-4'~
~
'94-0048~ ~'~
VT 3 ' ' ~ ~ ~ ~ ~ ~ "
~~ ~
'IND J ~
RHR Suetion A Snubber / Clamp 08/12/94 F-A,B,C Loose nuts and drawing
.l H -.. 7
.94-0044. _... _ _ _.. _.. LC ".I.ormance.. _ - -,.
.n NAD.,_
VT3 ISI-1314 2-4 9-A i
RHR F.uction B Db1 5t ut/Db1 Strut 08/11/94 P-A,B,C ISIJ13142-Si-A^
lH-1
'94-0012 VT3
' ' " ~ ~ ~ ~
~
NAD- ~ '
^
RHR Discharge A l Snubber / Db1 St rut 08/04/94 F-A B C 94~20045' ~ ~ ~
VT3~ - ' -
~ ~ ' '
~ ~
'I ND~~
ISI-13142251-B
~
HT4"
~
~
Containment Spray St rut / Clamp C8/11/94 F-A,B,C 1
Loose nut.
ISI-13142-52 A'
'H-~ 2' 9470186 -
'VT3~ ~ ~ ~ ~ ' '
^ ~~~ ~
NAD~~~~
T Feedwater Variable / Spring 09/22/94 P-A,B,C ISI-13142-52-A H-4 ~
94-0143 VT 3 '
"~ ~ ~
NAD"
~
Feedwater ISnubber / Clamp 09/22/94 F-A,B,C I
ISI 13142-53 A~
' Hi 5'
~
~'
94-0180~~~'
~
'VT3'
~'
~
~~NAD
2 Feedwater Snubber / Clamp 2 09/24/94 P-A,B,C ISI-13142 53-A
' H-'6
~
'~
'94-0178' ~' ~
Vr3- ~~~
~
NAD'~
Feedwater Spring / Clamp 09/24/94 F A B.C
~
IS1-13142 5J-A iH-7
'94-0179 VT3' NAD Feedwater l Snubber / Clamp 09/24/94 F-A,B,C ISI-74215-A H-~ 1' 94-0228~ ' " ~ ~ ~ ~ ' 'VTF
' ' ' ~ ~
~~~
'NAD
~
Standby Liquid Cnt rl Dox Restraint 09/27/94 P-A,P C 1
ist-182-A ~
H-1 l94'~0333 -
~
VT3
" ~ ~
~~
'NAD Head Vent iHanger 10/04/94 F-A,B,C l
I IS! 786 A
' { H-3'~
'94-0264
~
' VT 3 ' ~
' NAD
?
MS Condensate Lkoff l Linear Support 09/29/94 F A,B,C l
c
')94-0332
' ' 'VT 3 '
NAD'~
Is1-621 A ^
{H 1
I 4 Bottom Head Drain
- Bex Restraint
{10/04/94 lF-A,B.C i
i IS'-829242-A' Dvs Supp A~
!94-0001 ~
] VT3 '~
'{NAD l
~
HrCI Pumpe D/S Pump Support l07/29/94 i F-A,D.C 01/17/95 Page 16 l
e Monticello Nuclear Generating Flant Inservice Inspection Report Log Northern States Power Ccapany Old Bwy 152 NW of Monticello Third Interval By Source Doc #
414 Nicollet Mall Monticello, MN 55362 Commercial Service Date: June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Resulta pyatem Item Description Exam Date ASME Section II Item JSI-8292-42-A DVfi Supp B 94-0002 VT3 NAD HPCI Pumps DV9 pump Support 07/29/94 P-A,B,C
^1817 3268-1-A
" ilIl
~
W O6fi VT3
'NAD-CRD Scram Header A Box Restreint 09/08/94 F-A,B,C ISI 93268-1-A H-4 94-0021 VT3 NAD CRD Scram Header A Box Restraint 08/08/94 F-A,B,C
_. -... _. _ _ _ _. ~
.. 7 CRD Scram Header A Rod / Clamp 08/08/94 F-A,B,C
{VT3 NAD ISI-93268-1-A H-6 94-0023 CRD Scram Header A Double Strut 08/08/94 F-A,B,C CRD Scram Hdr Disch Box Restraint 09/30/94 T-A,B.C m
CED Scram Hdr Disch Box Restraint 09/30/94 P-A,B.C ISI-93268-3-A H-1 94-0038 VT3 NAD CRD Scram Header B Box Restraint 08/09/94 F-A,B,C ISI-93268-3-A H-2 94-0034 VT3 NAD CRD Scram Header B Strut / Clamp 08/09/94 F-A,B,C ISI-93248-3-A H-4 94-0039 VT3 NAD CF.D Scram Header B St rut / Clamp 08/09/94 F-A,B,C ISI-97005-A H-11 94-0098 VT3 NAD Rocirculation A Sway Brace 09/20/94 F-A,B,C ISI-97005-B H-3 94-0244 VT3 NAD Recirc Manifold A Restraint 09/28/94 F A,B,C ISI-97005 B H-5 94-0254 VT3 NAD Recirc Manifold A Restraint 09/28/94 F-A,B,C ISI-97005-B H-7 94-0243 VT3 NAD Recirc Manifold A Restraint 09/28/94 F-A,B,C
~fNAD ISI-97005-B H-8 94-0242 VT3 Recirc Manifold A Rest raint 09/28/94 F-A,B,C ISI-97005-B H-9 94-0241 VT3 NAD Recire Manifold A Restraint 09/28/94 P-A,B,C Reactor wtr Cleanup IDouble Spring /4 Luga 09/25/94 F-A,B,C Thread engagement and tack welded nuts.
.... _ ~.--
.}-
+
Recirculation B lBwayBrace 09/20/94 F-A,B,C
._ "'_ nut and misaligned rod Recirculation B Restraint 09/20/94 F-A,B,C Recisc Manifold B jRestraint 09/27/94 F-A,B,C l
151-97bo6-B~
'[
H-6 94-0253
~'
VT3
'NAD Recarc Manifold B fRestraint 09/27/94 lF-A,B,C
--..h Recire Manifold B
! Restraint 09/27/94 F A,B,C l
01/17/05 Page 17
I
+
s Monticello Nuclear Generating Plant Inservice Inspection Report 1,og Northern States Power Company Did Hwy 152 NW of Monticello Third Interval By Source Doc #
414 Nicollet Mall Monticello, MN 55362 Cossiercial Service Date: June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results System item Description Exam Date ASME Section XI Item 181-97006-3 H-9 94-0239 VT3 NAD Recirc Manifold B Restraint 09/27/94 F-A,B C 1SI-97006-C H-10 94-0255 VT3 NAD Recire Pump B Restraint 09/28/94 P-A,B,C ISI-97027-A H-1 94-0261 VT3 NAD RHR Equalizer Spring / Clamp 09/29/94 F-A,B,C l'Si 93268-1;A H-13 94-0422BL VT3 IND CRD Scram Header A Strut / Clamp 08/27/93 P-A,B,C Drawing Conformance ISI-13142-37-A H-8 94-0053 VT3 NAD KHR Discharge A Variable / Clamp 08/16/94 F-A,B,C
~111-13142-37-A H-4 94-0015 VT3 IND RHR Discharge A Db1 Spring / Clamp 08/05/94 P-A,B,C Drawing confomance.
1st-13142-10 A H-10 94-0078 VT3 IND RHR Discharge B Spring / Clamp / Slide 09/01/94 F-A,B,C Extra hot and cold tags.
ISI-13142-37-B H-2 94-0030 MT NAD Containment spray Strut / 8 Lugs 08/08/94 F-A,B,C ISI-13142-18-A H-11 94-0054 VT3 NAD kHR Discharge B Seismic Restraint 08/02/94 F-A,B,C 151-13142-51-B H-4 94-0045R1 VT3 NAD Containment Spray Strut / Clamp 08/23/94 F-A,B,C Reworked ISI '.3142-51-A H-1 94-0012R1 VT3 NAD RHR Discharge A Snubber / Db1 St rut 08/24/94 F-A,B,C Deexam after clamp removed and reinstalled.
Cr)ntainment Spray Db1 Spring / C1. amp 09/07/94 F-A,B,C Drawing conformance.
ISI-13142-51-B H-5 94 0080 VT3 NAD Containment Spray Db1 St rut / Dbl Clamp 09/07/94 F A,B,C iM-1314 2 - 4 2 2A H 11 94-0350BL VT3 NAD HPCI Steam Snubber / Clamp 10/05/94 P-A,B,C ISI-97003-A H-3 94-0263BL VT3 NAD RHR Returti %
Snubber / Clamp 09/29/94 F-A,B,C ISI 13142 37 A H-3 94-0344BL VT3 NAD RHR Discharge A Snubber 10/04/94 F-A,B,C IS!-13142 36-A H-2 94-0120BL VT3 NAD Main Steam D Snubber / Clamp 09/21/94 F-A,B,C ISI-13142 49 A H-10 94-0351BL VT3
~~~
IND RHR Suction B Snubber / Clamp 10/05/94 F-A,B,C Thread engagement and drawing con!ormance.
l ISI-97027-A H-3 94-039sBL VT3 NAD RHR Equalizer Snubber / Clamp 10/08/94 F-A,B,C I
- - - _ ~
f10/03/94 F-A,B.C RHR Discharge A Db1 Strut-6-Snubber 131-13142-51 B jH-3 ' - ~ ~ ~ ~ ~ ~
94-0079R1 VT3 NAD Cont ainment Spray lDb1 Spring / Clamp 09/14/94 F-A,B,C
)
j Rewonked 01/17/99 Pale 18
e I
J Monticello Nuclear Generating Plant Eneervice Inspection Report Log Northern States Fower Company Old Ewy 152 NN of Monticello Third Interval By Source Doc 8 414 Nicollet Mall Monticello, MN 553(2 Commercial Service Dates June 30, 1971 Minneapolis, MN 55401 ISO Item Report trumber Method Results system Item Description Ruan Date ASME Section XI Item ISI-13142-37-B H-4 94-0027R1 VT3 NAD Containment Spray Variable Spring 09/14/94 P-A,B.C Reworked 94~Td048Ri VT3 iND~
'iSUI)i42-4 E A~
HI4
~~
RRR Juction A Snubber / Clamp 09/15/94 F-A,B,C Reworked loose nuts, still have drawing conformance issues.
ISI 13142-37-A H. 6 94-0346 VT3 NAD RHR Discharge A Strut / Clamp 10/04/94 P-A,B,C ISI-13142-18 A H-7 94-0347 VT3 NAD RHR Discharge B Strut / Clamp 10/04/94 F-A,B,C ISI-13142-20 B H-3 94-0335BL VT3 NAD Core Spray A Snubber / Clamp 10/03/94 P-A,B,C ISI-13142-33 A H-7 54763OBb VT3 NA E Main Steam A Snubber / Clamp 10/05/94 F-A,B,C ISi!i3142-3EA'
~
~*H-2 94-0352BL VT3 NAD Main Steam A Snubber / Clamp 10/05/94 F-A,B,C ISI 13142-35-A H-3
- S4-0354BL VT3 NAD Main Steam C Snubber / Clamp 10/05/94
.F-A,B,C IS! 13142-37-A H-4 94-0015R1 VT3 IND RRR Discharge A Db1 Spring / Clamp 10/05/94 F+A,B,C Fartial nework.
ISI-97006-A H2 94-0097R1 VT3 NAD Recirculation B Sway Brace 10/07/94 F-A,B,C Reworked
~
IS1'976b52
~ ] H-1 94-0365 VT3 NAD Recirculation A Restraint 10/07/94 F-A, B, C ISI-13142-17+A H-9 94-0011R1 VT3 IND RER Suction A Slide 10/07/94 F-A,B.C Reworked weep hole, thread engagement remains.
IS1-13142-17 A H-2 94-0013R1 VT3
+ NAD RHR Suction A Slide / Clamp 10/07/94 F-A,B,C
-. _ - l Reworked Main Steam D ISnubber / Clamp 10/07/94 P-A,B,C l
Reexamined after
.;. _. _... ~. _...l removal / reinstallation.
Main Steam D l Snubber / Clamp 10/07/94 F-A,B,C Reworked ISI - 1314 2 - 4 0 - A' H-14
~
N'~d604R1 VT3
~NAD-
~
HPCI Nater Side Dsch Seismic Restraint
/ /
F-A,B,C Use-as-is w/ Technical Justific.ation
i~ - ~ ~ ~ ~ ~ ~
94-0011R2 VT3 NAD IS113i42-16 A~ ~
~
H-l RHR Suction A Slide
/ /
F-A,B,C Use-as-is w/ Technical Justification.
.-_-~_.__._4
. - - - -... -i _
RUR Discharge A Spring / Clamp
/ /
F-A,B,C Use-as-is w/
151-1314 2 - 3 7 - B H-1 N 60I8Ri
~ ~~
'NAD~
Containment Spray Variable Spring j / /
F-A,B,C j
(
Use-as-is w/ Technical t
I
- __ - -. -..- _sti_ficati.on.-
_6 Ju
---_-~A 01/17/95 Page 19
8 e
Monticello Nuclear Generating Plant Inservice Inspection Report Log morthern States Power Courpany old Rwy 152 NW of Monticello Third Interval By Source Doc 9 414 Nicollet Mall Monticello, MN 55362 Cose.orcial Service Dates June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results system 2 tem Description Raam Data ASME Section II Item ist-13142 37-A H-4 94-0015R2 VT3 NAD RHR Discharge A Db1 Spring / Clamp
/ /
F A,B,C Use-as-is w/ Technical Justification.
161-13142-49 A H-4 94-0048R2 VT3 NAD RHR Suction A Snubber / Clamp
/ /
F-A,B,C Use-as is w/ Technical Justification.
^1SI-13142-18-A H-10 94-0078R1 VT3 ~
NAD RHR Discharge B Spring / Clamp / Slide 10/11/94 F A,B,C Reworked IS!'-l3f42"42-A" ~~~ 7 H. 2 94 0392R'1 VT3 NAD
~
HpCI Steam Spring / Clamp 10/13/94 F-A,B,C Reworked
!$1-13142-42-A H-7 94 0037R1 VT3 NAD HPCI steam Spring / Clamp 10/17/94 F A,B,C Reworked ISI-93268-1-A H-1 94-0022BLR1 VT3 NAD CRD Scram Header A Box Restraint 10/08/94 F-A,B,C Reexamination after modification.
IS!-93268-1-A H-6 94-0023BLR1 VT3 NAD CRD Scram Header A Double strut 10/08/94 F-A,B,C Reexamination after modification, ISI-13142-33-A H-4 94-0126R1 VT3 NAD Main Steam A Varible / Spring
/ /
F A,B,C Use-as-is w/ Technical Justification.
1SI'73886TA~
' ' ~ ~
~~'H-3 94 0198R1 VT3 NAD Reactos Ntr Cleanup Double Spring /4 Lugs
/ /
F A,B C Use-as-is w/ Technical Justification.
/ /
F-A,B,C Use-as-is w/ Technical Justification.
2 FA"' ~ ~ ~ ~ ~ '
H-3 94-0420BL VT3 NAD ggg;3jl42 3
Main Steam b Snubber / Clamp 10/21/94 F-A,B,C Limited to verification of fluid level following addition-ISI 13142217 C '
H '~ f ' ~~'
~ ~ ' " "
'N ie010BLRi- -
~VT3
'NAD J
~
RHR Discharge A Spring / Clamp 10/21/94 P-A,B.C New inspection after modification.
Gl'Y3142-i7 A
' H '-'3 94-0344BLR1
~VT3' NAD~'
~
RHR Discharge A Snubber 10/21/94 F-A,B.C Reexamination after snubber bolt replacement.
ggg." 314 M 7;C
~
H. 4"
~ ~ ~ ~ ~ ' ' ~ ~ ~ ~ '
'941606BLR1 VT3 NAD
~
RHR Discharge A Db1 Strut-& Snubber 10/21/94 F-A,B,C Reexamination after snubber bolt replacement, 94 042iBL~
'VT3
~1ND 2
IS!'-I)142 20 A~ ' ~
'H-~3~ ~ ~ ' ~ ~ ' ~ ~ ~ ~ ~-~
Core Spray B Snubber 10/21/94 F-A,B,C ISI-13142-20-A H-3
'94'-0421BLRi~
~ Threed engagement.- ' ' ~ ~ ~ ~ ~
~
NAD-
)
VT3 Core Spray B Snubber
/ /
F-A,B.C USE AS IS W/ TECHNICAL j
JUSTIFICATION 93268 1'-A'- ~
" " [ H 13~ ~~~~
~ ~ ~ '
94'-0422BLRI'~ ] VT.i ~ ~
~
~~ ~~ " ] W AD ~
T 2
IS!!
CRD Scram Header A fStrut / Clamp 01/12/95 F-A,B C
, Use as is w/ technical 3""EIII#*EA "
Page 20 01/17/95
a Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Nwy 152 NN of Monticello Third Interval By Source Doc 8 414 Nicollet Mall Monticello, MN 55362 Commercial Service Dates June 30, 1971 Minneapolis, MN $$401 ISO Item Report Number Nothod Results System Item Description Esam Date ASKE Section XI Item IS1-13142 33 A H-1 94-0221 VT3 IND Main Steam A Double Spring /4 Lugs 09/25/94 P-A,B,C B10.10 Thread engagement.
ggg'13142"-367A~ ' - ~ ~
H-7 94-0124 VT3
' 'I ND Main Steam D Double Spring /4 Lugs 09/21/94 P-A, B, C B10.10 Drawing conformance.
ISI'-13'142 52-A H-3 94-0159 VT) ~ ~ ~ ~ - ~
~~ NAE '~
~
Feedwater Double Spring /4 Lugs 09/22/94 P-A,B,C B10.10 L
~
"VTf'~
~~
NAD~
T )85
!s1193268-i;A H-20
- 94 C
CRD Scram Header A Tank Support 09/30/94 F-A,B,C B10.10 ISI 93268 3-A H-3 94-0633 VT3 NAD CRD Scram Header B Hestraint / 4 Lugs 08/09/94 F A,B.C B10.10 ISI,97005 A H-7 94-0411 VT3 IND Recirculation A Double Spring 10/11/94 F-A,B,C B10.10 Drawing conformance.
{H-10 94 0407 VT3 IND 151-97005-A Gecirculation A JDb1 Spring / 4 Lugs 10/11/94 F-A,B,C B10.10 Drawing conformance.
ISI-97005 B H'-
6
~
- 9410400 VT3 NAD Recirc Manifold A Spring / Lugs 10/11/94 F-A,B,C B10.10 ISI-97006 A H-3 94-0410 VT3 NAD Recirculation B Db1 Spring / 4 Luge 10/11/94 F-A,B,C B10.10 ISI-97006 A H-8 94-0101 VT3 NAD Recirculation B Snubber / Lugs 09/20/94 F-A,B,C B10.30
..g---------.
Recire Manifold B Spring / Lugs 10/11/94 F-A,B,C B10.10 g.- -.-
Rectre Manifold B Snubber 09/27/94 P-A,B,C B10.10 Loose bolt.
. - - -... -. - - =. - - - - - - ~
Reelre Manifold B Snubber 10/06/94 F-A,B,C B10.10 Reworked 151-93268 3-A H-11 94-0401BL VT3 NAD CRD Scram Header B Restraint /4 Lugs 10/08/94 F-A,B,C B10.10 151-13142 36-A H-7 94-0124R1 VT3 NAD~ ^
Main Steam D Double Spring /4 Lugs
/ /
F-A,B,C B10.10 Use-as-is w/ Technical Justification.
ISI-13142-33-A H-1 94 0221R1 VT3 NAD Main Steam A Double Spring /4 Lugs
/ /
F-A,B,C B10.10 Use-as-le w/ Technical Justificatlon.
ISI-97005 A H 10 l?4-0407R1 VT3 NAD Recirculation A Db1 Spting / 4 Lugs l / /
F-A,B,C B10.10 j
Use-as is w/ Technical l
'~VTl NAD Justifica1 ton.
g g g. 9 7 0'0 5 - A' ' ~ ~ ~ '
iHT7~ ~ ' ' ~ ~
~
M 96 0'411Ri~~
Recirculation A
!!hJuble Spring
/ /
F-A,B,C B10.10 Use-as-is w/ Technical Justification.
ISI-97005-C H-4 94-0116 VT3 IND Rectre Pump A Snubber / Lugs 09/21/94 F-A,B,C B10.2 0 Missing scale for fluid indicator.
Is!-M 005-C'
~f45
~ - ' ~ ' ~ ~ " '
' ~
94-0115BL~
j VT3
~
~
IND Rectre Pump A ISnubber / Lugs 09/21/94 i F-A,B,C B10.20 fThreadengagement, missing
_ } pin and loose bolt.
01/17/95 Page 21
8 e
Nonticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Hwy 152 Nw of Monticello Third Interval By Source Doc #
414 Mico11st Hall Monticello, MN 55362 Cosmarcial service Dates June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results System Item Description Exam Date ASNS Section II Item ISI-97006-C H-7 94-0256 VT3 NAD Recire Pump B Snubber / Lugs 09/28/94 F-A,B,C B10.20 2SI-97006 C H-4 94-0321EL VT3 IND Recire Pump B Snubber / Lugs 10/03/94 P-A,B,C B10.20 Missing fluid level indicator'
)
scale.
l ISt-97006-C H-5 94-0322BL VT3 NAD Rectre Pump B Snubber / 1.uge 10/03/94 F-A,B.C B10.20 i
ISI-97005 C H-5 94-0115BLR1 VT3 IND Recirc Pump A Snubber / Luge 10/06/94 F-A,B,C B10.20 j
Reworked but still has thread l
engagement issue.
f ISI-97005-C
H-5 94 0115BLR2~
~
' VT 3 NAD I
Recire Pump A Snubber / Lugs
/ /
F-A,B,C B10.20 Use-as-is w/ Technical Justification.
ISI 97005-C
' H4~ ~ ' ' ~ ~ ~ ~ ' - ~^'
94 VT3 NAD 1
-0116R1
/ /
F A,B,C B10.20 Recire Pump A Snubber / Lugs Use-as-is w/ Technical j
Justification.
ISI-97006-C H-4 94-0321BLR1 VT3 NAD Recirc Pump B Snubber / Luge
/ /
F-A,B.C B10.20 Use-as-is w/ Technical Justification.
I SI-- 970 06 - A H-7 94-0412 VT3 IND
]
Recirculation B Db1 Spring / Lugs 10/11/94 F-A,B,C B10.30 Drawing conformance.
j ISI-97006-A H-7 94-0412R1 V"*3 NAD Recirculation B Db1 Spring / Lugs
/ /
F-A,B,C B10.30 Use as-is w/ Technical Justification.
IS1-7905-32-A Support A 94-0016 VT3 IND RHR Heat Exchanger A Support A,E200A, Os 08/05/94 F A,D,C C 3.10 Drawing conformance.
~~~~~-~~4 ISI-7906-32-A'~
~ Support'B'~
'"94-00'17 VT3 IND RHR Heat Exchanger A Support B,E200A 100s 08/05/94 F-A,B,C C 3,10 Drawing conformance.
lSu'pport~A"
~
' 94200i8'- ~ ~~ ' 'MT~ ~ ~ ~
'- ~~~
'NAD~
IFI-7905 322A RHR Heat Exchanger A
{ Support A.E200A, De 08/04/94 F-A,B,C C 3.10 IS1 7905232 A
_ f Limited by configuration.
2 jSupport B 94-0019 KT NAD RHR Heat Exchanger A (Support B E200A 180s 08/04/94 P-A,B,C C 3.10 Limited by configuration.
ISI-7905132-A Support A 94-0016R1 VT3 NAD ERR Heat Exchanger A Support A,E200A, ce
/ /
F-A,B,C C 3.10 Use-as-is w/ Technical Justification.
I ISI-7905-32-A
' iSusiort B 94-001'7R1'~
" VT3
~~-
NAD
~
RHR Heat Exchanger A Support B,E200A 180s
/ /
lF-A,B,C C 3.30 I
lUse-as-isw/ Technical 1 Justification.
ISI-13142-17-C H-9 94 0057 VT3 NAD RHR Suction B Db1 St rut / 6 Lugs 08/17/94 P-A,B,C C 3.20 ISI'-l3142 l7-C ~
'H- "9'
~
94-6063~ ~ - ~ '
MT ^
' - ~
~N AD '
i '
RHR Suction B Db1 Strut / 8 1,ugs t08/19/94 P-A,B C C 3.20 I
ISI-13142-18 A'
'fH-' '9
+94-0D06"
'~ VT) '
~~
' IND 2
RHR Discharge B
)Db1 Spring /4 Lugs 10/11/94 F-A.B,C C 3.20 ISI-13142-18 A IH-~9"
'{
'0220 ~
i MT ' ^-
on dwg.' ' ~~ ~ ' ' {
! Welded lugs not t94-NAD' RHR Discharge P Db1 Spring / 4 Lugs f09/26/94 F-A,B,C C 3.20 j
l Limited due to support access, i
rest _riction.
._.J'.
6 01/17/93 Fage 22
o
\\
tionticello Nuclear Generating Plant Inservice Inspection Report fog Northern States Power Company Old Ewy 152 NW of Monticello Third Interval By Source Doc #
414 Nicollet Mall Monticello, MN 55362 Commercial Service Date: June 30, 1971 Minneapolia, MN 55401 J
ISO Item Report Number Method Results System Item Description Exam Data ASME Section II Item 181-13142-37-9 H-3 94-0029 MT NAD Containment Spray Strut / 8 Lugs 08/08/94 P-A,B,C C 3.20 "ISI;~314f-37 B H-3 94-0026 VT3 NAD 1
Containment Spray Strut / 8 Lugs 08/05/94 F-A,B,C C 3.20 l
"isisi31"42-51-B H2 94-0047 Kr NAD Containment spray Db1 Spring / 4 Lugs 08/11/94 P-A,B,C C 3.20 181-13142-51-8 H-2 94-0046 VT3 IND Containment Spray Db1 Spring / 4 Lugs 08/11/94 F-A,B,C C 3.20 Drawing conformance.
ISI-13142-37-A H-7 94-0052 MT NAD RHR Discharge A Db1 Spring / 4 Lugs 08/16/94 F A,B C C 3.20 ISI-13142-37-A H-7 94-0051 VT3 IND RHR Discharge A Db1 Spring / 4 Lugs 08/16/94 F-A,B,C C 3.20 Loose nuts and drawing conformance.
ISI-13142-37-B H-5 94-0345BL VT3 NAD Containment Sprey Snubber / Lugs 10/04/94 F-A,B,C C 3.20 ISI-13142-37-A H-7 94-0051R1 VT)
IND SHR Discharge A Db1 Spring / 4 Lugs C9/14/94 F-A,B.C C 3.20 Reworkedloosenutsbutsti1}
have drawing conformance isasues.
ISI-13142-37-B H-7 94-0418 VT3 NAD Containment Spray Db1 Spring / 4 Lugs 10/13/94 P-A,B,C C 3.20 ISI-13142-37-B H-7 94-0415 MT NAD Containment Spray Db1 Spring / 4 Lugs 10/12/94 F-A,B,C C 3.20 ISI-13142-51-B
'H-2 74Td6MR1 VT3 NAD Containment Spray Db1 Spring / 4 Lugs
/ /
F-A,B,C C 3.20 Use-as-is w/ Technical Justification.
]'VT3 N'AD ISI-13142-37-A
.H-7 94-0051R2 RMR Discharge A Db1 Spring / 4 Luge
/ /
F-A,B,C C 3.20 Use as-is w/ Technical Justification.
ISI-13142-18-A H-9 94-0006R1 VT3 NAD RHR Discharge B Db1 Spring / 4 Lugs
/ /
F-A,B,C C 3.20 Use-as-is w/ Technical Justification New 151-48 RHR Support B 94-0061 VT3 NAD RHR Pumps Pump Support 08/19/94 P-A,B C C 3.30 New 1S1-49 Support, Pump B 94-0071 MT NAD-Core Spray Pumps Pump Support 08/23/94 F-A,B,C C 3.30 Limited due to configuration.
New ISI-49 Support, Pump B 94-0065 VT3 IND Core Spray Pumps Pump Support 08/19/94 P-A,B,C C 3.30 Thread engagement.
___q New 181-48 RHR Bupport B 94-0062 MT NAD RHR Pumps Pump Support 08/19/94 F A,B.C C 3.30 Limited due to configuration.
New ISI-49 Support, Pump B 94-0065R1 VT3 NAD Core Spray Pumps Pump Support
/ /
F-A,B,C C 3.30 Use-as-is w/ Technical
_ _.1 ustification.
J 01/17/95 Page 23
NORTHERN STATES POWER MONTICELLO INSERVICE INSPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 Appendix C List of Interval 3, Period 1 Inspections Sorted by Inspection Report (pages 1 through 23) 6 I
6 i
a i
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Bwy 152 NN of Montice110 Third Interval By Report #
414 Nicollet Mall Monticello, MN 55362 Commercial Service Date June 30, 1971 Minneapolis, MN $5401 i
ISO Item Report Number Method Results System item Description Exam Date ASME Bection II Item ISI-s292-42-A DVS Supp A 94-0001 VT3 NAD HPCI Pumps DV8 Pump Support 07/29/94 P-A,B,C
^R I 629E52 A "DVS 'siip~ ~ 5' 94T f02 VT3 NAD T
p 0 ~
HPCI pumps DVS Pump Support 07/29/94 P-A,B,C 181-13142-20-B H-1 94-0003' VT3 NAD-Core Spray A Variable 08/01/94 F-A,B,C ISI-13142-40-A H 14 94-0004 VT3 IND HPCI Water Side Dsch Seismic Restraint C8/01/94 F-A,B,C
'H 15
[9E600iR1
~ Thread engagement isi 5314IT EA'
~~'
1 VT3 NAD 4
HPCI Water Side Dsch Seismic Restraint
/ /
F-A,B,C Use-as-is w/ Technical Justification IS!-11142-16-B H-2 94-0005 VT3 NAD RHR Discharge B Variable Clamp 08/25/94 F-A,B,C ISI-13142-18-A H-9 94-0006 VT3 IND RHR Discharge B Db1 Spring / 4 Lugs 10/11/94 F-A,B,C C 3.20 Welded lugs not on dwg.
ISI-13142 18-A H-9 94-0006R1 VT3 NAD RHR Discharge B Db1 Spring / 4 Lugs
/ /
F A,B,C C 3.20 Use-as-is w/ Technical
{
Justiff;ation f
ISI-13142-19-A W-1 94-0007 VT3 NAD HPCI Steam Disch Snubber / Clamp 08/02/94 F-A,B,C ISI-13142-40-A W-22 94-0008 MT NAD HPCI Water Side Dsch Valve-to-Pipe 08/02/94 C 5. 51 ISI-13142-40-A W-22 94-0009 LTT4 5 NAD HPCI Water Side Dach Valve-to-Pipe 08/03/94 C 5. 51 ISI-13142-37 C H-1 94-0010 vr3 IND RHR Discharge A Spring / Clamp 08/04/94 P-A,B,C Drawing conformance, extra parts and missing welds.
)
ISI 13142-37-C H-1 94-0010BLR2 VT3 NAD RER Discharge A Spring / Clamp 10/21/94 F A,B,C New inspection after modification.
i l'SI-13i42'h TC"~
H-1 94-0010R1 VT3 NAD 2
RHR Discharge A Spring / Clamp
/ /
F-A, B, C Use-as-is w/
Tech. Justification.
ISI-13142-17-A H-9 94-0011 VT3 IND RER Suction A Slide 08/04/94 P A,B,C Thread engagement and missing i
weep hole.
7 94-0011R1 VT3 IND ISI-13142-17-A H-9 RHR Suction A Slide 10/07/94 F-A,B,C Reworked weep hole, thread
- 9 2 # ""*'"*'
k RHR Suction A Slide
/ /
F-A,B,C Use-as-is w/ Technical j
ggg;13I42 51 A-
~ ~ ~ ' ' ~'
Hi 1
~ ~ ~ ~ ~~
N!6052~
~
NAD~
2 RHR Dascharge A
' Snubber / Db1 Strut 08/04/94 F-A B.C ISI-13142 51-A H-1 94-0012R1 VT3 NAD RER Discharge A Snubber / Dbi St rut 08/24/94
' F A,B,C I
l Reexam after clamp removed j
_.1__
I landreinstalled.
i L_.__
j 01/17/95 Page 1
i l
j 4
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Bwy 152 Nw of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, act 55362 Commercial service Deter June 30, 1971 Minneapolis, Nu 55401 I
180 Ites Report Number Method Results system Item Description Exam Date ASME Section XI Item ISI 13142-17-A H-2 94-0013 VT3 2ND RHR Suction A Slide / Clamp 08/04/94 F-A,B,C
'isi'-W145 17'!h -
- H-2 94-0013R1
~ Missing weep hole.
VT3 NAD RHR Suction A slide / Clamp 20/07/94 F-A,B,C Reworked ISI-7905 32-A N-2 94-0014
>TT NAD RHR Heat Exchanger A Shell-Fad-Nor 08/04/94 C 2. 31 I$1-13142-37-A H-4 94-0015 VT3 IND kHR Discharge A Db1 Spring / Clamp 08/05/94 F-A,B,C Drawing confcreance.
Is!-13142-37-A H-4 94-0015R1 VT3 IND RHR Discharge A Db1 Spring / Clamp 10/05/94 F-A,B,C
}
Partial rework.
ISI-13142-37-A H-4 k94-0015R2 VT3 NAD RHR Discharge A Db1 Spring / Clamp
/ /
F-A,B,C Use-as-is w/ Technical Justification.
'ISI-7905-32 A Support A 94-0016 VT3 IvD RHR Heat Exchanger A Support A.E200A, De 08/05/94 F-A,B.C C 3.10 Drawing conformance.
ISI-7905-32 A Support A 94-0016R1 VT3
~~~
NAD RHR Heat Exchanger A Support A,E200A, Os
/ /
F-A,B,C C 3.10 Use-as-is w/ Technical Justification.
ISI-7905-32-A M
Support B 94-0017 VT3 IND RHR Heat Exchanger A Support B,E200A 180s 08/05/94 P-A,B,C C 3.10 Drawing conformance.
ISI 7905-32-A Support B 94-0017R1 VT3 NAD RHR Heat Exchanger A Support B,E200A 180s
/ /
F-A,B,C C 3.10 Use-as-is w/ Technical Justification.
ISI-7905-32-A Support A 94-0018 FT NAD RHR Heat Exchanger A Support A,E200A, ce 08/04/94 F-A,B,C C 3.10 Limited by configuration.
ISI-7905-32-A Support B 94-0019 MT NAD RHR Heat Exchanger A Support B,E200A 180s 08/04/94 F-A,B,C C 3.10 Limited by configuration.
IS1-93268-1-A H-5 94-0020 VT3 NAD CRD Scram Header A Rod / Clamp 08/08/94 F-A,B,C l
ISI-93268-1-A H-4 94-0021 VT3 NAD CRD Scram Header A Box Restraint 08/08/94 F-A,B,C l
ISI-93268 1 4
)HJ '1 '
~
94-0022 VT3 NAD 1
CRD Scram Header A Box Restraint 08/08/94 F-A,B,C l
3st.91268-l'JA~'
~~ ~ i H-'^
94 - 0 02 2BLR1 VT3 NAD 1
CRD Scram Hender A Box Restzaint 10/08/94 F-A,B,C I
Reexamination after modification.
ISIl93268-1'-A'
~~~
'7
~
l H-6 94-0023 VT3 NAD CRD Scram Header A
[ Double Strut 08/08/94 F-A,B,C ISI-93268-1'A
- ~~
^ H - 3~~ ~ ~ ~ ~
~~
94!00i3BLR1~~
VT3 NAD
~
^
CND Scram Header A Double Strut 10/08/94 F-A,B C Reexamination after 3sg.93258'3 A~
~ ~~] B - ~ ' ' ~ ~ " ~ ~ ' ~ ~ ~ ~ ~
,94-0054" ~ ~ ~ ] VTi~~
~ ~ ~ ~ ~
NAD ~
modification.
7 1
~
CRD Scram Header A Flange Bolte e W-7 l09/01/94 i B7 50 l
l I
ISIL1314 2 '- 3 7 - B 1HJ2 ~'~ "'
i94-0025' ^-
i VT3"
~ ~
~'~
NAD ~'
containment Spray I St rut / e Lugs l08/05/94
' F-A.B C i
.... ~
-..a.
z.
._..-..._.J.
01/17/05 Page 2
.=.
e Monticello Nuclear Generating Plant inservice Inspection Report Log Northern States Power Company old wwy 152 kw of Monticella Third Interval By Report 9 414 Nicollet mall Monticelle, NN $5362 Commercial Service Dates June 30, 1971 Minneapolis, MN $5401 ISO Itam Report Number Method Resulta syntes Item Description Raam Date ASME Section II Item 181-13142 37 b H-5 94 0026 VT3 NAD Cont ainment spray Strut / 8 Lugs 08/05/94 F A,B,C C 3.20 181-lh 42-17;B"~~ ~
H-4 94 0027 VT3- ~ ~~
~ ~ ~ ~ '
'IND~
~
Cont ainment Spray variable Spring 08/05/94 P A,B,C 1mproper load settings
[
stamped.
' T3 ~
~ ~ ~ '
NAD ~~
181 13142-37 B H-4
~~
~
'9440027N1 V
Containment Spray variable Spring 09/14/94 P-A,B,C Reworked jgJ g'31422 7.h ' ~
^ -~ j ~ 1~ ~ ~ ~ ^ ~
90 0028'
" ' ~ ~ ' ~
'VT) ~ ~~
IND
! ~
3
'H-Containment Spray Verleble Spring 08/05/94 P A,B,C 181113142 37 B'
'H-~
' ' ' ~ ~ ~
94 0028R1 ~ '
Drawing compliance. ~ ' ~ ~
NAD
~
1 VT 3 ' ' ~ ' ' ' -~
Containment Spray Variable Spring
/ /
F A,B,C Use-as-is w/ Technical Justification.
ISI-13142'-37 H H.
3~~
~
~
94 0029 MT ~
^'
NpW
~ 1 containment Spray St rut / 8 Lugs 08/09/94 F-A,D,C C 3.20 iSI-11142 37 D
Hi2
" 94 0030 ~
~Kr ~ ~ '
~~ " ~ ' ~ 'NAD Containment Spray Strut / 8 Lugs 08/08/94 F A,B,C W 14 ' "'
- $4 0031 MT
~ ' ' ~ ~ ~
' ~ ~
NAD IS1-13i42-17A' i ~~
RHR Suction A Elbow-to Elbow 08/08/94 C 5, 61 iSI'13142-17-A W~8
'96 0032~~~
' ~ ~
" MT~~
'~
~~
^'NAD' ~
2 RHR Suction A Fipe t o Weldolet 08/08/94 C 5, 81 ISI 9N68'~3 A'
~~~
~~
Hk ~ 3"
'~'
94 0033^'
VT)~~
~ ~' ~
NAD~
(kD Sesam Header B Restraint /4 Lugs 08/09/94 F A,B,C B10.10 t
ISI 9326823-A~
'HTI'
94-0034~~
"~
' VT)-~
^ ^ ' - ~ ~
~~
'NAD
~
CkD Scram Header D Strut / Clamp 08/09/94 F A,B,C 3s633g43-42'A'~~
H
'5
~
~~ ~ -~ 94-0035~'~~ ~
VT3' ~ ~ ^-
NAD"
HPCI Steam Spring / Clamp 08/09/94 F-A,B,C IS1-13142-42;A
' Hi 6
~ ~ ~ ~ ~
94 0016"~ ~ ~ ~ '
VT3'
' N AD 7
^
HPCI Steam Spring / Clamp 08/09/94 F A,B.C
^ 7 9420037' VT3 - "
~
IND
151 13142-42 A
] H-Hit! St eam
{t;pring / CImmp 08/09/94 F-A,B C Setting outside of allowable.
ISI-13142-42 A' j H-7'
~~'
'94-00f7RI' VT) "" ~
~
NAD HFCI Steam l Spring / Clamp 20/17/94 F<A,B,C Neworked IS1293268-3 A '
H-'i'
' 94-003c VT3 NAD CRD Seram Header D box Restraint 08/09/94 P-A,B,C iSI-93268-3-A~
H-4 94-0039^
'Vr3' NAD CkD Scram Hamder B
{ Strut / Clamp 08/09/94 F-A,B.C i
iSI-91268 liA B-1
" 94-0040~'~
' VT1' NAD
^
CRD Scram Headet A Flange Bolts e W-7 l08/08/94 B 7. 50
'SI-13141 18 A
'W-22 l94-0041 MT ~
~ ~
NAD I
~
C 5.
El RHR Discharge B Pape to Elbow l08/12/94 ISI-13142-18-A
'W-14 94 0042 MT NAD
~
P HR DischarDe B Tee to Pipe 08/12/94 C 5.
51 1
I i
151 1314 2 4 9-A'
' l W 15 I94 004
MT "INAD 3
i i
i i
RHR Suction A Eltow to-Pipe 1P2,12/v4 C 5.
51 l
l l
_a 2.
01/17/gg Page 3
l Monticello Nuclear Generating Plant inservice Inspection Bog. ort Log Northern states Power Compemy Old Nwy 152 prw of Monticello Third Interval By Report #
414 Nicollet Mall i
Monticello, not 55362 Cosmiercial Service Date: June 30, 1971 Minneapolis, MN 55401 ISO Item Report alumber Method Results System Item Description Exam Date ASME Section XI Item 11il-1314 2 -4 9-A H-7 94 0044 VT3 NAD EHR Suction 9 Db1 St rut /Db1 St rut 08/11/94 F - A, D. C
' If;1:1314 2'- 51 ;D~
~~
~~H!'4~
~
9440645~~
~ VT3"
~
~ ~" ~ ~ ~ ~ ~ ~ ~
'I ND "
Containment Spray Strut / Clamp 08/11/94 F-A,B,C Loose nut.
Ig1;i3142 51'.g~~"
~
H'- 4' ' '~
~ ~ ~
94!8 45R1~^
~
VT3
'NAD Containment Spiny St rut / Clamp 08/23/94 F A,B,C Reworked 1s1 13142 51 D' H-2 -~
'94!0046"- ~ ~
'VT3'
~'
1ND 2
~
Containment Spray Db1 Spring / 4 Lugs 08/11/94 F A,9,C C 3.20 Drawing conformance.
'ISI'1'3142 51 P ~
~ H2 2
~
94!0046k!"
Vt f ' ' ' '
NAD '
~
Containment Spray Db1 Spring / 4 Lugs
/ /
F-A,B,C C 3.20 Use-as is w/ Technical Justification, 1$1-13145 51 D'
' HT2^"
'9410047'~ ~ ~ ~ -
prT~'
'NAD-~
Containment Spray DL1 Spring / 4 Lugs 08/11/94 F-A,p,C C 3.20 IS).13142-4 9 A H-4 94TOD4 8 '~ ~ ~
'VT3'
~
"IND RHR Suetion A Snubber / Clamp 06/12/94 F A,D,C Loose nuts and drawiry conformance.
ICI 131464 9: A ~ ' ~ ~ '
~
HJ ' ~4
-~~ ^
94 6048R1-
' VT3
'~'
' ' I ND
~~
RHR Suction A Snubber / Clamp 09/15/94 F-A,B,C Reworked loose nuts, still have drawing conformance issues.
H'4'~
" 9410048k2
_VT) '
~
NAD C
I g g '.'i 3,14 2 4 9. A~
~~ ~
FHR Suction A Snubber / Clamp
/ /
F A,8,C Use as-is w/ Technical Justification.
IAI 740E 32 A" W-'1 94-0049~~
~
trt4 5 "
NAD RHR Heat Exchanger A Top Flange to Shell 08/20/94 C 1. 10 Limited due to configuration.
W 14 '
94'0050"
" trie b
~~ ~ ~~
'NAD 181 13142 17 A'
'~
J kHR Suction A Elbow to-Elbow 08/10/94 C 5. 51 151 13142 37-A H-i
'~~ ~~f94'0061~~
~ ~ -
' VTI
' ~ ~ ~ ~
' I ND ' '
l A
RHR Dischasgo A Db1 Spring / 4 Lugs 08/14/94 F-A,B,C C 3.20 Loose note and drawing conformance.
IS$ i3i42-37 A pH- ?
94 00tik1'
' VT)
JND RHR Dischange A Db1 Spring / 4 Lugs 09/14/94 F A,D C C 3,20 Reworke$ loose nute but still, i
have drawing conformance j
i.e.ucs.
15! 13142 37 A jH-7 94-00$ik2 VT3 NAD RHR Discharge A Db1 Spring / 4 Lugs
/ /
F-A,P C C 3.20 Use-as-is w/ Technical JustifAcation.
[94'005h' MT NAD
'151-13142-37 A H-7 kHR Discharge A Dbl Spring / 4 Lugs l09/16/94 P-A,B,C C 3.20
{
ISI-13142 37-A H-"8" 94-0053'~
~
VT3'
~
NAD "~
I RHR Discharge A 1,ariable / Clamp 09/16/94 F A,B,C I51-131'42 18-A
'.' H 11' '
94!C054
' VT3 NAD' RHR Discharge B Seismic Restraint
- 0H/02/94 F-A,B,C l
I 1S1'i3142 18 ; A
-IW-14 ~
I94 0055 '
tTT4 % '
NAD Fila Discharge p f Tee to-Pipe l08/15/94 C S. b1 ISl-13i42-18'-A W-22 j94-0056
' tTr4 5 NAD ~~
~
EHR Discharge B Fipe-t o-El bow 08/15/94 C 5, 51 01/17/95 Page 4
j i
4 A
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Ewy 152 NW of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, MN 55362 Commercial service Date June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results Systes.
Item Description Exam Date ASME Section II Item 281-13142-17-C H-9 94-00b7 VT3 NAD R1lR Suction 8 Db1 Strut / 8 Lugs 08/17/94 F-A,B,C C 3.20 94 0058 TfTi
~
NAD
^!
RHR Discharge B
! St rut / Clamp 08/17/94 F A,B,C 5
j g t'T33je2 i7'-C ~~
H74 AT005)
VT3
' N Afi-
~ T RHR Suction B Slide 08/17/94 P-A,B,C I$1-13142-17-C H-5 94 0060 VT3
~ NAD '~
~
RHR Suction B Strut / Clamp 08/17/94 P-A,B,C RHR Pumps Pump Support 08/19/94 P-A,B,C C 3.30 Naw ISI 48 RHR Support B 94-0062 Prf NAD RHR Pumps Pump Support 08/19/94 F-A,B,C C 3.30 Limited due to configuration.
'is!-13142 17-C H-9 94-0063 KT NAD RHR Suction B Db1 Strut / 8 Lugs 08/19/94 F-A,B.C C 3.20 i
i Isi 13142 49 A W-15 94-0064 ITT45 NAD RHR Suction A F1 bow-to-Pipe 08/10/94 C 5.
51
. - _.- 4,
Core Spray Pumps Pump Support 08/19/94 F A,B, C C 3.30 Thread engagement.
Core Spray Pumps Pump Support
/ /
F-A,B,C C 3.30 Use as-is w/ Technical I
Justification.
HPCI Steam Disch Db1 Snubber / Clamp 08/22/94 F-A,B,C ISI-13142-19 A W-7 94-0067 MT NAD HPCI Steam Disch Pipe-to-Elbow 08/22/94 C 5. 51 161-13142-19-A W-7 94-0068 tJf 4 5 NAD HPCI Steam Disch Pipe-to-Elbow 08/22/94 C 5.
51 ISI-13142-20-B W-23 94-0069
'~~T NT~
'~~NAD""~~
~
~
Core Spray A Elbow-to-Pipe 08/23/94 C 5. 51
.----a Core Spray A Elbow to-Pump 08/23/94 C 5. 51
- - - - -.--i Core Spany Pumps fPumpSupport 08/23/94 F-A B.C C 3.30 Limited due to configuration.
IS1-13142-51-A W-25 94-0072 UT45 GEO RHR Discharge A Reducer-to-Nortle 08/24/94 C 5. 51 Limited due to configuration.
151 13142-51 A W-25 94-0073 MT IND RHR Discharge A Reducer-to Nozzle i08/24/94 C 5. 51 Linear ISI 13142-51-A
']W-25 94-0073R1
~
'-~ '~ l NAD~
~
RHR Discharge A l Reducer-toNor21e 08/24/94 C 5.
51 9';bO75' ~ ~~'~
~~
--~GEO~
3 S t '.1314 2 2 0 - B' ' ~ "
f-N " ~
~ ~ ~ ~ ' ~
2 4
Core Spray A Elbow-to-Pump 08/25/94 C b. 51 Limited due to configuration.
Isi.iji42-20 B-~
'~~
'~'$W-23~ ~ ~ ~ ~ ~ ~ " ~ ~ ~ ~~, 54-0076'- ~ ~~ ] UT45
~
NAD Cote Spray A l Elbow-to-Pipe 08/25/94 j C 5.
51 t ed j,ue_,,t0,,,gg,9u, r ap _on.
CRD Scram Header A l Flange Bolts a W-1 l08/09/94 B 7.
50 l
i l
01/17/95 Page 5
j l
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Ewy 152 NW of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, MN 55362 Commercial Service Deter June 30, 1971 Ninnewpolis, MN 55401 ISO Item Report Number Nothod Results System Item Description Exam Date ASME Section II Item ISI-13142-14-A H-10 l94 0078 VT3 IND RHR Discharge B Spring / Clamp / Slide 09/01/94 F A,B,C Extra hot and cold tags.
'tSI-lili)2it A H-10 94 0078R1 VTI ~ ~ ~ ~ ~ " ~ ~~~~~ N Ar.i ~
~~
RER Discharge B Spring / Clamp / Slide 10/11/94 F A,B,C Reworked 151-13i42 51;B' H-3 94 0079 VT3
~ ~ ~ ~ ~ ~ ~ -
'IND~
Containment Spray Db1 Spring / Clamp 09/07/94 F-A,8, C Drawing conformance.
ISi2 f142T51-B E-3 94 0079R1
~VT3
'NAD~
1 Containment Spray Db1 Spring / Clamp 09/14/94 F-A,B,C t
Beworkea 1$1 13142-51-B
~
H-5 94-CC80 VT3
~NAD
~
Containment Spray Dh1 Strut /Db1 Clamp 09/07/94 F-A,B,C 181-13142-20-B W-1 94-0081 MT
~ ~ ' ' ~ " ~
^tND-'
Core Spray A Torus Penn-to-Elbow 09/16/94 C 5. 51 Two linears.
ISI-13142 20+B W-1
~~94-00H1R1' MT
~ ~ ' ~
'NAD
~
Core Spray A Torus Penn-to-Elbow l 09/28/94 C 5. 51 l
Reworked ISI-13142-20-B W-4 94-008f- - ~' ~ "
K!'
NAD Core Spray A Pipe-to-Elbow 09/16/94 C 5. 51 ISI-13142-20-B W-4 94-0083 UT45 NAD Core Spray A Pipe-to-Elbow 09/16/94 C 5.
51 ISI-13142-20 D W-1 94-0084 UT45 NAD Core Spray A Torus Penn to-Elbow 09/16/94 C 5. 51 CRD Scram Hdr Disch E l t,ow - t o-Pi pe 09/17/94 B 9. 40
.... _ -.. -.... ~.
Reactor Vessel Ligaments 09/16/94 B 6. 40 Limited due to access restriction.
Nes Fig'6
' Studs 94i0088 WO
~ NAD Reactor Vessel 64 RPV Studs 09/16/94
NAD Recire Manifold B Pipe-to-Elbow 09/21/94 8 9.
II ISI-97006-B W-13 LS U6D 94-0091 PT NAD Recite Manifold B Reducer-to-Pipe 09/21/94 9 9.
11 ISI 97006 B W-12 LS UED 94-0092 PT NAD Recire Manifold B Tee-to-Reducer 09/21/94 B 9.
10 181-93268-3 A W-6 94-0093 PT NAD CRD Scram Header B
, Pipe to Tee 09/19/94 B 9. 11 l
3sg;97006-D~
~~
-'lW-13LSU6D 94-0094 W45 NAD Recire Manifold B Reducer-to-Pipe 09/20/94 B 9.
II l
Limited due to support I
testriction.
ISI 97006-B ~^~
' ' ' ~ '
U14~LS"UsD~ ' ' - ~ '
~ - ~
94-0095~'
~
'UT45~~~
'NAD~
Recire Manifold B jtipe-to-Elbow 09/20/94 B 9.
11 ISI 9.U6 El A'-
'~
W 30 LS'U6D ~
~
94-0096 M
NAD l
CRD Scram Header A F1pe-to-Elbow (45e) 09/19/94 B 9.
10 01/17/pg Page 6
e Monticello Nuclear Generating Plant inservice Inspection Report Log Northern States Power Company Old Ewy 152 NW of Monticello Third Interval By Report #
414 Nicollet Mall monticello, MN 55362 Connercial Service Date: June 30, 1971 Minneapolis, MN 55401 Iso item Report Number Method Results system item Description Exam Date ASME section XI Item 151=97006-A H-2 94 0097 VTJ IND Recirculation B Sway Brace 09/20/94 F-A,B.C
-~
Loo 6e nut and misaligned rod.
ISI-97606-A
~ ~ ~ ~ ~ ' ~
HT2~~~"---~~~~~
94 0d97R1 VT3 NAD Recirculation B Sway Brace 10/07/94 F-A,B,C Deworked IS' lI 9700$ A" ~~
H-11 94-0098 VT3 NAD Recirculation A Sway Brace 09/20/94 P-A,B,C ISI-97006-A B-3
" ' ~
94-0099 VT1 NAD Recirculation B Flange Bolts e W-16 09/20/94 B 7.
50 Recirculation A Valve Bolta 09/20/94 B 7.
70 ISI-97006-A ~'
H-8 94-0101 VT1 NAD Recirculation B Snubber / Lugs 09/20/94 F-A,B,C B10.10 ISI-97006-A'
~ ~ ~
H-4 94-0102 VT3 NAD Recisculation B Restraint 09/20/94 F.A,B,C 181-97005-B W-21 LS UkD
~ 94 - 010 I' ~~ -- ~ ~ PT '~ ~ ~ '~
~
NAIi
~
Recirc Manifold A Pipe-to Tee 09/20/94 B 9. 10 151 93268 O A
W-6 94-0104 17T45 NAD CkD Scram Header B Pipe to-Tee 09/20/94 89, 11 Limited due to configuration.
ISI-13142 33-A W-2 LS U 94-0105 MT NAD Main Steam A Safe End to-Elbow 09/20/94 B 9, 10
!SI'-13142 33 A
W-5 94-0106 brf NAD 7
Main Steam A Elbow to Pipe 09/20/94 9 9. 11 IS!-13142-3b A W-1 LS D 94 0107 MT NAD Main Steam A Nortle to-Saf e End 09/20/94 B 9.
10 ISI-97005-B W-21 LS U&D 94-0108 UT45 NAD Recirc Manifold A Pipe-to-Tee 09/21/94 B 9. 10 IS!-93268-1-A W-30 LS U6D 94 0109 LTT45 NAD CRD Scram Header A Pipe-to-Elbow (4 Se) 09/20/94 B 9.
10 ISI-97027-A l W-6 94-0110 MT NAD RHR Equalizer Pipe-to-Elbow 09/20/94 B 9. 11 ISI-97027-A W-2 94-0111 MT ' '
~'
~}NAD~
RHR Equalizer Pipe-t o-Elbow 09/20/94 B 9. 11 IS1-97027 A W-2 94-0112 UT45 NAD RHR Equalirer Pipe-to-Elbow 09/20/94 B 9.
11 l
i 1
---..~s.
RHR Equaliser PIPE-to-Elbow 09/20/94
'9
- 9. 11 IS!-13142-)3AA~
~
' H-3~ ' ~ ~ ~ ~~ ~ ~ ~
$47011iBf.~~~~~~~ ~
"VT3
' ~ ~ ~ ' ~ ~ ~
NAD~
Main Steam A Snubber / Clamp 09/21/94 F-A,B,C ISI 97005 C H-5 94-0115BL VT3 IND Recire Pump A Snubber / Lugs 09/21/94 F-A.B,C B10.20 Thread engagement, missing
- -~
pin.and loose bolt..
Recire Pump A Snubber / Lugs 10/06/94 F-A,B,C B10.20
[
Reworked but still has thread l
\\
..__d..._.
_.L_._~__.-_____
f_"9 *8 *.**". -. - _" Y" '_
_...-..L--_
01/17/95 Page 7
n, 4
Monticello Nuclear Generating Plant Inservice Inapaction Report Log Northern States Power Company Old Ewy 152 NW of Montleello Third Interval By Report #
414 Nicollet Mall Monticello, MN $5352 Comunercial service Dates June 30, 1971 minneapolis, MN 55401 ISO Item Report Number Method Results System Item Description Eaam Date ASME Section KI Item 151-97005-C H-5 94-011bBLH2 VT3 NAD Rectre Pump A Snubber / Lugs
/ /
F-A,B,C D10.20 Use-as-is w/ Technical Justification.
~131T97^05-C H4 94-0116 VT3 IND Rectre Pump A Snubber / Lugs 09/21/94 F-A,B.C B10.20 Missing scale for fluid indicator.
ISI'- 9 70 6 5-d ~~ ~
H-4 94-0116R1 VT3
~~~NAD~ ~ ~
Recirc Pump A Snubber / Lugs
/ /
F-A,B,C B10.20 Use-as-is w/ Technical Justificatta.
Reactor Vessel 64 Bushings 09/14/94 B 6. L0 Limited to top edge only.
Main Steam A Elbow-to-Pipe 09/21/94 B 9.
11 IS!-13142-33 A N 2 La U 94 0119 UT45 NAD Main Steam A safe End-to-Elbow 09/21/94 B 9.
10
~
IS1-15142-36-A H-2 l94-0120BL VT3 NAD Main Steam D Snubber / Clamp 09/21/94 P-A,B,C ISI-13142-36-A H-S 94 0121 VT3 NAD Main Steam D Snubber / Clamp 09/21/94 P-A,B.C
.~____s_. -
Main Steam D Snubber / Clamp 10/07/94 F-A,B,C Reexamined after removal / reinstallation.
181-13142 36-A H-6 94 0122 VT3 IND Main Steam D Snubber / Clamp 09/21/94 P-A,B,C Loose bolt and fluid leakage.
ISg;13i42 1 6-A'~~
HJ'6 '
94-0122R2 VT3 NAD 3
Main Steam D Snubber / Clamp 10/07/94 P A,B,C Reworked 1SI-13142-36-A B-10 94-0123 VT1 NAD Main Steam D Valve Bolts 10/08/94 8 7.
70 Examined in place.
ISI-13142-36-A~ ~ ~'
H7
' 94-0124
'VT3 IND Main Steam D Double Spring /4 Lugs 09/21/94 P-A B.C B10.10 Drawing conformance.
ISI-11142-36-A H-7 94 0124R1 VT3 NAD Main Steam D Double Spring /4 Luga
/ /
F-A,B,C B10.10 Use-as-1s w/ Technical Justification.
tsg.13142 36.A ' ^
BJ9' '
94-0125~ ~'
"VT1- ~ ~ ~ ~ ~ ~'
'NAD~
Main Steam D Valve Bolts 10/08/94 B 7. 70 Examined in place.
1s!-13142-33-A H-4 94-0126 VTJ IND Main Steam A Varible / Spring 09/21/94 F-A,B,C Drawing compliance.
1S1-13142 33 ^ ~
H-4
'94-0126R1
'VT3
^ NAD 2 2 Main Staam A varible / Spring
/ /
F-A,B,C j
Use-as-is w/ Technical Justification.
- tsi-3 3i42,3$.k' ~ -~ ~ ~
NU12'
' 94; o g 2 7' ' -
'-" (TT4 5 NAD Main Steam C Elbow-to-Pipe
- 09/22/94 h 9. 11 Limited due to support restriction.
IS1-13142-35-A
' N 11 94-0128 UT45 NAD Main Steam C
, Elbow-to-Elbow 09/22/94 B 9.
11 181 il142<3b A N-10"
~~
~
'94' 0129
~
trr4 5" ~
~~~ ~
NAD~
' f Mann Steam C Pipe to-K1 bow 09/22/94 B 9.
11
. b -.
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Hwy 152 NW of Monticello Third Interval By Report #
414 Nit.-llet Mall Monticello, MN 55362 Comunercial service Dates June 30, 1971 Minneapolis, MN $5401 ISO Item Report Number Method Results system Item Description Exam Date AS'IE Section XI Item ISI-13142-36-A W-12 94-0130 t UT45 NAD Main Steam D Pipe-to-Swe?polet 09/22/94
' B 9.
31 Limited due to configuration.
iSI 13141 35-A TW-12 94-0131 KT NAD-~
Main Steam C Elbow-to-Pipe 09/22/94 8 9. 11
'Isf-ili42-35"~A'~ '
~ " W-11 94-0132
~KT NAD Main Steam C Elbow-to-Elbow 09/22/94 B 9.
II l
ISI-13142-35-A
~~' ^ ' ITO-
'94-Di33
~KT NAD j
W
~~
Main Steam C Pipe-to-Elbow 09/22/94 9 9. 11
.. _ _ ~ _
Main Steam D Pipe-to-Sweepolet 09/22/94 i 9. 31 ISI-74'2i5;A ~~ ~-
W-7 94-0135
-PT IND
~
l Standby Liquid Cntrl Pipe-to-Head Fitting 09/22/94 8 9. 40 Multiple indications.
W-7 94-0135R1 PT NAD l
Standby Liquid Cntrl Pipe-to-Head Fitting 09/28/94 B 9. 40 331 13142-52'A~ ~ ~ ~~ } Ii-'2 5'~'~~
5ED136 NAD
~
l Feedwater Fibow-to Pipe 09/22/94 B 9.
11 ISI-13142-52-A W-21
~ ~ ~ ~ ~'~l94-0137 KT NAD Feedwater Pipe-to-Elbow 09/22/94 B 9. 11 ISI-93268-3-A W-29 LS ULD 94-0138 PT NAD CRD Scram Header B Elbow-to-Elbow 09/22/94 9 9. 10 jgi'13142-31-A~ ~ ~ ~ ~
IB-1 94-0139 VT1 NAD Core Spray B Valve Bolts 09/22/94 B7 70 I
I
{V-
~ ~ ~ '*94-0140 VT3 NAD 1
ISI 13142-31 A Core Spray B jValve Int Surfaces 09/22/94 B12. 50 iSI'13142-34-A ~ ~
'- ~ ~ f
~
'NAD-
^
) B-6 94-0141 VT1 Main Steam B Valve Bolts 10/08/94 9 7. 70 Examined in place.
ISI;13i42-34 A j B-6 94-0141BLR1 VT1 NAD Main Steam B Valve Bolts 10/18/94 B7 70 Reexamination aftrr j.
+...
! Valve molts 10/C8/94 B 7. 70 Examined in place.
... _....... 4 Feedwater Snubber / Clamp 09/22/94 F-A,B,C ISI i3142-Si-A~ ~ ~
~ - ' '-' ' W :21~ ' ~ ~
~~~D4T0144 UT45 NAD fPipe-to-Elbow 09/22/94 B 9.
11 Feedwater
~
l Limited due to configuration, 9'4 0i45~
'tTT4 5 "NAD~
j jss'.l3142-52-A~~
- ~ ~ ~ 1 W 22~ - ~ ~ '
~~~
2 T
l Feedwater Elbow-to-Pipe 09/22/94 8 9. 11 l
Limited due to configuration.
I 181-932&B-3-A W 29 LS U&D 94-0146 UT45 GEO CRD Scram Header B Elbow-to-Elbow
!09/22/94 B 9. 10 l
Ig g '. 9 3;f g !3.'h ^ ^
-~
-' T w'. 2 9 " LS' UC'-' ~ ~ ' ~~ ~ ~ ~~~ '
9f-~ 0 5 4 6 R i~
' tTT4 '5 '
NhD~
~
~
CRD Scram Header B B1 bow-to-Elbow 10/01/94 B 9.
10
- Report for long seam ommitted 151-i3142 il A~
~
l'W-13~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~
94-0147^ ~ ~ ~ ! on original exam.
l
~'
~M ~NAD lUT45 1
t i
Core Spray A jPipe-to-Valve
~09/23/94 l B 9. 11 Limited due to configuration.;
01/17/95 Page 9
s Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old swy 152 NW of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, NW 55362 Comanercial Service Date: June 30, 1971 Minneapolis, MN 55401 Iso Item Report Number Method Results System Item Description Exam Date ASME Section XI Item ISI 13142-26-A W-14 94-0148 UT45 NAD Core Spray A Valve-to-Pipe 09/23/94 B 9. 11 Limited due to configuration.
7 549 PrT '
NAD 0
I$1 13142-43-A W 10 94 RCIC Steam Elbow-to-Pipe 09/23/94 B 9. 21 1Si-13142+43 A W-9 94-0150 Kr NAD RCIC Steam Pipe-to-Elbow 09/23/94 B 9.
21 ISI-786-A W-28 94-0151 MT NAD MS Condensate Lkoff Elbow-to-Pipe 09/23/34 B 9.
40
'Is1;786 ; A W-29 94-0152 MT NAD MS Condensate Lkoff Pipe to Elbow 09/23/94 B 9. 40 ISI-786-A W-30 94-0153 MT NAD MS Condensate Lkoff Elbow-to-Pipe 09/23/94 B 9. 40 MS Condensate Lkoff Pipe to-Elbow 09/23/94 B 9. 40
... -. - -..-_--- i. -. -.~ - -
-.-_-4 MS Condensate Lkoff Elbow-to-Pipe 09/23/94 B
5.
40
. _. ~. _..
MS Condensate Lkoff Elbow-to-Pipe 09/23/94 B 9. 21
' is t.'1314 2 - 2 6 - A W-13
~ ~ ~ ~ ~
-~~i94-0157~ ~ -~
~PT- - ~ ~ ~
NAC I
~
Core Spray A Pipe-to-Valve 09/23/94 B 9.
11 ISI-13142-26-A W-14 94-0158 PT NAD Core Spray A Valve-to-Pipe 09/23/94 B 9.
11 ISI-13142-52-A H-3
~~
94-0159 VT3 NAD Feedwater Double Spring /4 Lugs 09/22/94 F-A,B,C B10.10 ISI-782-A iW 28 94-016'0
~' PT
-~~NAD -
Head Vent
' Valve-to-Pipe 09/23/94 B 9. 40 ISI-782-A W-26 94-0161 PT NAD Head Vent ITee-to Pipe 09/23/94 B 9.
40
._ J i
Head Vent Pipe-to-Valve 109/23/94 9 9. 40 IS1-93268-1-A
.W-7
^~9410163 PT NAD~~-
CRD scram Header A Flange-to-Tee 09/23/94 B 9. 11 i
ISt-93268-i A~~
~ ' ~ " ' ~ IWT 9S UED~ - ~ ~ ~ - ~ ~ - - '4-Ci64
~PT '
~~~'NAD-~
L ~~
9 l
CRD Scram Header A l Reducer-to-Pipe 09/23/94 9 9.
10 l
IS1591268-1-A l W-6 94-0165 PT NAD CRD leram Header A
- Pipe to Tee 09/23/94 B 9. Il ISI.~13i42 g2;A'^ ~~~~ ' - ~
W-24"
~~ '- ~~~ ~ - " i94-0166
" ' ~ ~
NAD
?
UT45 INew S.E.-to-01d S.E.
09/25/94 B 9.
11 Feedwater ISI-13142-52 A W 25 94-016' UT45 NAD Feedwater Safe End-to-Nor:1e 09/25/94 B 9. 11 l
1 Limited due to configuration.
l 2
~
)94 0168 IS1 13142 52-A '
~
W-23 i
j lUT45 NAD reedwater l Pipe-to-SafeEnd lC9/25/94 l B 9.
Il I
j
!Limitedduetoconfiguration.
^{ News.E.-to-CldS.E.
j % Ci69- ~ ~ ~ ~ ~
~' i ~ MT' ' ' ' ~ ~ ' ' ~ ~ ' ~ ~ ~ ~ ~
~_hD~~~
161 13142-52-A W 24 j
l09/25/94
, B 9, 11 Feedwater 2.
__1.__._
__..__._.n
___...___._____..__a..__..
01/17/95 Page 10
e Montleello Nuclear Generating Plant inservice Inspection Report Log Northern States Power Company Old Swy 152 NW of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, NW 55362 Coumarcial service Date June 30, 1971 Minneapolis, MN $5401 180 Item Report Number Method Results System item Description Exam Date ASME Section XI Item 151-13142-62-A W-25 94-0170 MT
~NAD
(
Feedwater Safe End to-Nor:1e 09/25/94 9 9. Il 181-97004 A W-4 94-0171 MT NAD RHR Return B Pipe to Elbow 09/25/94
- 99. Il
-~-~~-4 gpgyon3.g
- w. 4~ ~ - - - - ~ - -
94 0172 MT NAD RHR Return A Pipe-to-Elbow 09/25/94 9 9, 11 ISI-13142-52-A W-23 94-0173 MT
' - " ' - ' - ~ '
NAD~
Feedwater Pipe-to-Safe End 09/25/94 P 9.
11
~1Sf!13142-36-A V-3 94-0174 VT3 NAD Main Steam D Valve Int surfaces 09/24/94 B12. 50 l$1-93260-1-A W-7
'94-0)15~ ~'~ ~ ~ ' tfr45~~-"'-~~
~-
NAD ~
CRD Scram Header A Flange-to-Tee 09/24/94 9 9.
11 Limited due to configuration.
1SI 93268-1-A W-6 94-0176 trT4 5 NAD CRD Scram Header A Pipe-to-Tee 09/24/94 9 9.
11 ISI-93268 1-A W-9 1S U&D 94 0177 17T4 5 GEO CRD Scram Header A Reducer-to-Pipe 09/23/94 B 9. 10 Is!'3)n). 3.A'
'~~
' H' T ~- ~ ~ ~ ~ ~
94-0178~ ' ^ -VTi ~ -~
NAD
~
Feedwater Spring / Clamp 09/24/94 F-A,B,C
-. _... -. ~ _. -.
Feedwater Snubber / Clamp 09/24/94 P-A,B,C ISI 13142-53-A H-5 94-0180 VT3 NAD Feedwater Snubber / Clamp 09/24/94 F-A,B,C 1st-73880 A W-22 94-0181 MT NAD Reactor Wtr Cleanup Fibow-to-Valve 09/24/94 B 9. II Recirc Manifold B Tee-to-Reducer 09/24/94 B 9.
10 18!-73880-A W 21 94-0183 MT NAD 9eactor Wtr Cleanup Pipe-to-Elbow 09/24/94 B 9.
11 IS!-73880-A - _ _. _..
.i 94-0184...
. UT45... _.. _ _
NAD lW 22 f
Reactor Wtr Cleanup IElbow to valve 09/24/94 99, 11 Linited due to configuration.
W 21 94-01'85 UT45 NAD j
ISI-73080-A" 1
%eactor Wtr Cleanup Pipe to-Elbow 09/24/94 99, 11 ISI-13142 52-A H-2
'94-0186 VT3 NAD Feedwater Variable / Spring 09/22/94 F-A,B,C 1s1.1314 N )1-A
~
W-14"~
94V0187
' MT
'NAD Core Spray B Bent Pipe / Safe End 09/25/94 9 9.
11 9 4 '- 0 i ' 8 - ~ ' ~ ~'-~ ' ' MT ' ' " ~~'
~~~~'
NAD~~
i
~1SI-l3142-31 A~
W-15'
~ ~~~
~
8 Core Spray B
, Safe End-to-Nortle
!09/25/94 B 5.
10 l
iSI-13i42 36-A^
' W-I5'
'~ ~ ~ ~ ' '
94-0189 MT NAD Main Steam D j Elbow -to Pipe 09/25/94 9 9.
11 I
._ _._ q
._..___4 Reactor Vessel N-4C Inner Radius 09/25/94 B 3.100 l
Limi_ted.due to thermocouple.
_---4 f-
~...
_-.---y Resetor Vessel f N-4B Inner Radius 09/25/94 B 3.100 h
.2. -.
Limit _ed due to t h.e_r.mo.coupl_e.,
.u__-_
01/17/95 Page 11
3 I
a i
l i
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Ccar.pany old twy 152 NW of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, MN 55362 Comunercial Service Date: June 30, 1971 Minneapolis, NW 55401 ISO Item Report Number Method Results l
system Item Description Exam Date ASME Section XI Item 151-13142-36-A W-8 94-0192 Mr NAD Main Steam D Elbow-to-Pipe 09/25/94 B 9. 11
'151 lilO -R-A B-1 94-0193 VT1 IND Core Spray A valve Bolts 09/25/94 B 7. 70 Examined in place, g
Inadequate thread engagement.
'iSI l3 R2;f'6 A7 -~ ~ ~
B-1 94-0193R1 VT1 NAD Core Opray A Valve Bolts
/ /
B 7. 70 Use-as-is w/ Technical Justification.
"iSi-Y3'id1 26-A B-2 94-0194 VT1 NM~~~
fre Spray A Valve Bolts 09/25/94 B 7. 70 Examined in place.
'iSi-97008-A W-2 94-0195 PT NAD Instrmt Nozzle N-11A Safe End-to-Coupling 09/26/94 B 9. 40 ISI 970C8-A W-3 94-0196 PT NAD Instrmt Nozzle N-11A Coupling +to-Pipe 09/26/94 B 9. 40 1St-97008-A W-1 94-0397 PT NAD Instrmt Nozzle N-11A Nozzle-to-Safe End 09/26/94 8 5. 20 ISI-73880-A H-3 94-0198 VT3 IND r
Reactor Wtr Cleanup Double Sr - qt4 Lugs 09/25/94 F-A,B,C Thread engagement and tack welded nuts.
ISI-73880-A H-3 94-0198R1 VT3 NAD Reactor Wtr Cleanup Double Spring /4 Lugs
/ /
F-A,B,C L
Use-as-is w/ Technical Justification.
j IS1-13142-36-A
} W-8 94-0199 (TT4 5 NAD Main Steam D F1 bow-to-Pipe 09/26/94 B 9. 11 ISI-13142-36-A W-25 94-0200 UT45 NAD Main Steam D Elbow-to Pipe 09/26/94 B 9.11 i
I ISI-13142-31-A W-15 94-0201 UT45 NAD Core Spray B Saf e End-to-Nozzle 09/26/94 9 5. 10 ue t c guration.
7 Core Spray B Bent Pipe / Safe End 09/26/94 B 9.
Il f
ISI-97004-A W-4 94-0203 UT45 NAD l
RHR Return B Pipe-to-Elbow 09/25/94 B 9. 11
[
94-0204 MT NAD ISI-97003-9 jW-12 RHR Suction A Branch-to Pipe 09/26/94 B 9. 31 l
1 l
-... _. -. - _ _. _ _. - +.
--___-.-_.----___..-_.4 Feedwater Elbow-t o-Pipe 09/26/94 B 9. 11
.. -. ~. - - -.
Feedwater Pipe-to-Elbow 09/26/94 9 9. 11 I
~4
... _. - -.. _ - - - _ _ _ _. +
g.
J RHR Return A Pipe-to-Elbow 09/25/94 B 9, 11
- p
- - -..., VLCB - 2 94-0208 trTO NAD Reactor Vessel Long Seam 09/25/94 B 1. 12
]
l Limited due to access j
j l restriction.
N'ew' Fig 4 IVLCD-2 J94-0209 ' --~~~
UT45~ ~ ~ - - - - "
NA6 -
Reactor Vessel lLongSeam
{09/25/94 fB1.12 s
l l
{Limitedduetoaccess j
{
I m _ restriction.
.___.2 01/17/93 Page 12
4 Monticello Nuclear Generating Flant Inservice Inspection Report Log Northern States Power Company old Ewy 152 Nw of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, NN 55362
% ercial service Date: June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results System Item Description Exam Date ASME Section X1 Item New rig 4 VLCB-2 94-0210 LTT6 0 NAD Reactor Vessel Long Seam 09/25/94 B 1. 12 Limited due to access restriction.
New Fig 5 N-4C NV 94-0211 UTO NAD Reactor Vessel N-4C Noz/ Val Weld 09/24/94 B 3. 90 Limited due to configuration.
__.-_____3 Reactor Vessel N-4C Ncz/Vs1 Weld 09/24/94 B 3. 90 i
-.-..-.---_n
--Limited due to configuration.
Reactor vessel N-4C Nos/ Val Weld 09/24/94 B 3. 90 Limited due to configuration.
New Fig 4 VCBB-4 94-0214 UTC NAD Reactor vessel Circ Weld e N4C 09/24/94 B 1. 11 Neii Fig 4 VCBB o 94-0215
~UT45 NAD i
Reactor Vessel Circ Wald e N4C 09/24/94 B 1. Il
'New'~ Fig 4 VCBB-4
~-~
Yi 02id' ~ ~~ ~ "UT60 NAD Reactor Vessel Circ Weld a N4C 09/24/94 B 1. 11 J
1SI-97004-A W 14 LS D 94-0217 UT45 NAD Recirculation B Pump-to-Pipe 09/27/94 B 9. 10 Limited due to configuration.
ISI-97006-A W-17 LS'U
~'
~~ ~
94-02*8 UT45 NAD Recirculation B Pipe-to-Valve 09/27/94 B 9. 10 Limited due to configuration.
. _. _ _ - _ g Recirculation B Valve-to-Pent Pipe 09/27/94 B 9. 10 Limited due to configuration.
ISI-13142-18-A H-9 94-0220 MT
' ~ '~ ~ ~NAD '~
RNit Discharge B Db1 Spring / 4 Lugs 09/26/94 F-A,B,C C 3.20 Limited due to support access re s.t_r i_c t i on.._
Main Steam A Double Spring /4 Luge 09/25/94 F A,B,C B10.10 i
I
,' Thread engagement.
iSI'-13142-33-A H'-
~1 94-0221R1 VT3
~ ~ ~ ~ ~ -
NAD~
Main Steam A Double Spring /4 Lugs
/ /
P-A,B,C B10.10 Use-as-is w/ Technical l
Justification.
l
..... - ~... _.. - _ - - - _ - - +
Recire A Drain Line Tee-to-Pipe 09/27/94 B 9. 40
.(.---.----------)
Recite A Drain Line Pipe to-Valve 09/27/94 B 9. 40
~}sg'.13342 36 A~
~
~'VJ 2'-
~
~ ~ ' ~ ~ ~~
94-0224 VT3 NAD j
~2 Main Steam D Valve Int Surfaces 09/26/94 B12. 50 l
ISI-13142 35-A V-1 94 0225 VT3 NAD Main Steam C Valve Int Surfaces 09/26/94 B12. 50 151-i3i42-3E h~ ~
~ ~~
W'"1 LS D
'94-0226
~ ~ ~ ~
Ind s -- ~ '~ -
~ ~~'NAD~
~
~
Main Steam A iNortle-to-Safe End 09/26/94 B 9, 10
%,g l
I
{09/27/94 l B 5.
kecirculation A Nozzle-to-Safe End 10
.. - ~. - - -. - -,. i
..-g
..-...--4
~..
I i
Standby Liquid Cntrl
- Box Restraint 09/27/94 F-A,B.C
-.-.. I.
y.
.-.---..7 Recirc Manifold B Snubber 09/27/94 F-A,B.C B10.10 Loose bolt.
01/17/95 Page 13
1 l
l Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Nwy 152 NW of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, sof $5362 Comunercial Servlee Date: June 30, 1971 Ninneapolis, MN $5401 1
ISO Item Report Number Method Results Systna item Description Exam Date ASME Section XI Item 1S1-97006-8 H-12 94-0229BLR1 VT3 NAD Recirc Manifold B Snubber 10/06/94 F-A,B,C B10.10 Reworked "lSI 97006'-B H+ 4 94 0230 VT3 NAD T
Recirc Manifold B Restraint 09/27/94 F-A,B.C 181 97006-B H-7 94-0231 VT3 NAD Recire Manifold B Restraint 09/27/94 F-A,B,C 151-97003-B W-17 94-0232 MT NAD RHR Suction A Valve-to-Elbow 09/28/94 B 9. 11
'ISi2 7003-B'~
~~~~
W-16 94-0233 "MT NAD 9
RHR Buction A Elbow-to-Pipe 09/28/94 8 9. 11
.,-__...._..___._)
Recirculation B Pipe-to-Valve 09/27/94 8 9, 10 ISI-97006-A W 18 LS D
~ ~ N 94-0235 PT NAD Recirculation B Valve-to-Bent Pipe 09/27/94 8 9.
10 ISI'97D06'-A~
~
W'~14 I.5 D 94-0236 TPT NAD
~
Recirculation B Pump-to-Pipe 09/27/94 B 9. 10 151-97003 8 W-17 94-0237 UT45 NAD RHR Suction A Valve-to-Elbow 09/28/94 B 9.
11 Limited due to configuration.
ISI 97003-B W-18 94-0238 UT45 NAD RFR Suction A Elbow-to-Pipe 09/28/94 B 9.
11 ISIl97006-B
H-9 94-0239 VT3 NAD Recirc Manifold W Restraint 09/27/94 F-A,B,C ISI 97005-A W-1 94-0240 UT45 NAD Recirculation A Notzle-to-Safe End 09/27/94 B 5. 10 181-97005-B IH-9 94-0241 VT3 NAD i
Recire Manifold A
{ Restraint 09/28/94 P-A,B,C l
ISI-97005-B" ~ '~
~
} H-8 94-0242 VT3 NAD Recirc Manifold A Restraint 09/28/94 F-A,B,C 1S1 97005-B H-7 94-0243 VT3 NAD P.eelre Manifold A Restraint 09/28/94 F-A,B,C 1$1-97005-B H-3 94-0244 VT3 NAP Recirc Manifold A Restraint 09/28/94 F-A,B,C New Fig 5
^ i N-SB IR
"194-0245 UT70 NAD Reactor Vessel N-SB Inner Radius 09/24/94 9 3.100 l
Limited due to thermal wire connection.
Reactor Vessel N-SB Nor/ Val Weld 09/24/94 B 3.
90 Limited due to thermal wire connection.
____.____.__.._4 Reactor Vessel
!N-SB Nos/ Val Weld 09/24/94 B 3.
90 Limited due to thermal wire I
~
e connection.
New Fig 5' ~ ~
jN-5B NV j94-0248~
UTO NAD Reactor vessel lN-SB Not/ Val Weld JC9/24/94
- 93. 90 Limited due to themal wire e r ssel N-nner Radius 9
/94 00
_.._._1._.
01/17/95 Page 14
I e
I Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern states Power Company old Ewy 152 NW cf Monticello Third Interval By Report 9 414 Nicollet Mall 1
ponticelle, MN 55362 Cosanarcial service Date: June 30, 1971 Minneapolis, MN 55401 Iso Item Report Number Method Results system Item Description Exam Date ASME Section XI Item j
New Fig 5 N-3A NV 94-0250 UT45 NAD Reactor Vessel N-3A Val /Noz Weld 09/23/94 9 3. 90 New Fig 5 N-3A NV 94-0251 UT60 NAD Reactor Vessel N-3A Val /Not Weld 09/23/94 B 3. 90
\\
. _ _ ~. _ _
Reactor vessel N-3A Vel /Noz Weld 09/23/94 B 3.
90
_____..__q Recirc Manifold B Aestraint 09/27/94 F-A,B,C 181-97005-B H5 94-0254 VT3 NAD Rectre Manifold A Restraint 09/28/94 F-A,B,C ISI-97006-C H-10 94-0255 VT3 NAD Recitu Pump B kestraint 09/28/94 F-A, B, C g-
4 H-7 94-0256 VT3 NAD Rectre Pump B Snubber / Lugs 09/28/94 F-A,B,C B10.20
!$1-13142-53-A W-28 94-0257 KT NAD Feedwater Pipe-to-Pipe 09/29/94 B 9. 11 ISI-13142-53-A W 32 94-0258 W45 NAD Feedwater Pipe-to-Elbow 09/29/94 8 9.
11 IS!-13142-53-A W-33 94 0259 LTT4 5 NAD Feedwater Elbow-to-Pipe 09/29/94 B 9, il
~ _..
RHR Suction A Branch-to-Pipe 09/28/94 9 9.
31
~_ _.... _ _ _
Limited due to configuration.
RHR Equaliger Spring / Clamp 09/29/94 F-A,B,C 181-97003-B B-4 94-0262 VT1 IND RHR Suction A Valve Bolts 09/29/94 B 7. 70 Thread engagement.
151-97003-9 B-4 94-0262R1 VT1 NAD RKR Suction A Valve Bolts
/ /
B 7. 70 Use-as-is w/ Technical Justification.
ISI-97003-A H-3 94-0263BL VT3 NAD RHR Return A Snv.bber / Clamp 09/29/94 F-A,B,C 181k788-A H-3 94-0264 VT3 NAD MS Condensate Lkoff Linear Support 09/29/94 F-A,B,C IS14 86 A~"
~
' } H-2 94-0265
'VT3 NAD MS Condensate Lkeff Box Support 09/29/94 F-A,B,C 3 3 3'.~ 1314 2. g 3. g
- w. } g'- ~ ~~--
94-0266
~UT45 NAD Feedwater Pipe to Pipe 09/29/94 B9 11 LinJted due to surf ace.
IS1-97006-A B-4 94-0267 - - ~^WI ~ ~~~-
~NAD I
Recirculation B Bolts 09/29/94 9 1. 70 1Sik97006-A' ~
~ ~~
BI2
' ' ~ ~ ~ ~ ~ ~ ' ~
-94T0268~~~
[
~ ~ ~ ~ - ~ ' ~ " ~NAri-Recirculation B j RC Pump B Studs 09/29/94 jB6.180 B 6.200
["VIl~ ~ ~ ~ ~ ~ ~ ' ~
NAD~
Examined in place.
ISI U7005 A?~
B-2 94-0269 j
Recirculation A Pump Bolting 09/29/94
! B 6.180 B 6.200
..- 9 Examined in place.
Recirculation A
!valveBolts 09/29/94 l B 7.
70
!Examinedinplace.
01/17/95 Page 15
e Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company
[
Old Ewy 152 Nw of Monticello Third Interval By Report 8 414 Nicollet Mall Monticello, MN 55352 Commercial Service Date June 30, 1971 Minneapolis, MN 55401 Iso Item Report Number Method Resulte Bystem 2 tem Description Exam Date ASME Section II Item ISI-97006-A W 19 LS U6D 94-0271 FT NAD Recirculation 8 Elbow-to-Pipe 09/29/94 B 9. 10 Reactor Vessel T.H. Flange Weld 09/30/94 B 1. 40 Limited due to configuration.
{94-0273
~
' t170 "NAD New Fig 1 W-e Reactor vessel T.H. Flange Weld 09/30/94 B 1. 40 New Fig 1 W-8 94-0274 UT60 NAD keector vessel T.H. Flange Weld 09/30/94 B 1. 4 0 Limited due to configuration.
' NTw' 'FTg' 1 B-1 94-0275 VT1 NAD Top Head N-6B Flar'ge Bolts 09/30/94 B 7.
10
' nee ~Flg 1
- W-1 94-0276
~VTO NAD Reactor Vessel T.H. Circ, Weld 09/29/94
- 1. 21 i
t
.. _ _ _~_._.__.j Reactor Vessel T.H. Cire. Weld 09/29/94 9 1, 21 New Fig'l jWH.Cire. Weld 1
94 0278 UT45 NAD lT.
09/29/94 B 1. 21 Reactor vessel ISI-97006-A
~~
W-19"LS U&D~ ~ ~ - ~ ~ ~ ~ ~ ~ T-'0279 tfT45 NAD
~
9 Recirculation B Elbow-to-Pipe 09/30/94 8 9. 10 l
iSI-13142 42-A V-2 94-0200 VT3 NAD HPCI Steam Valve Int Surfaces 09/30/94 B12. 50 IS1-13142+42-A B-2 94-0281 VT1 NAD HPCI Steam Valve Bolts 09/30/94 B 7. 70
. ~.. -.. -. _ _ _ _....
Standby Liquid Cntrl Pipe-to-Valva 09/30/94 B 9. 40
_ ~.... _ _ _ _...
CRD Screm Hdr Disch Box Restraint 09/30/94 F-A,B,C
[
t 151 - 9 3 2 6 8 -l'- B' H-6 94-0284 VT3' fNAD~'
CRD Scram Hdr Disch Box Restraint 09/30/94 F-A,B,C
'!S!!9326821-A~
~ -~
H-20 94 0285
'VT3 NAD CRD Scram Header A Tank Support 09/30/94 F-A,B,C B10.10 t
New Fig 4 VCBB-4 94-0286 17f0 NAD l
Reactor Vessel Circ Weld e N49 09/24/94 B 1. 11
_ _ - -... -. ~.
Reactor Vessel Cire Weld e N4B 09/24/94 B 1, 11 New Flg 4 VCB B'- 4 94-0268 UT60
'"- ~ ~ ~~ I NA6~~
f
]
Reactor Vessel iCirc Weld a N4B 09/24/94 B 1, 11 Head Vent Flange Bolts 09/30/94 87 50
~. --
- _ ~ _.
.._...q Reactor Wtr Cleanup l Elbow-to-Valve 09/27/94 B 9.
11 l
.... _.. _. 4
....~._.{.
Inst Noarle N-12A Nortle-to-Safe End
!10/01/94
{ B 5. 20 f
151-97006-B lW-18 l94-0292 '~ ] ' PT ' "
~ ~
NAD~~ ~
Rectre *tanifold B Safe End to Nortle j10/01/94 j B 5. 10 l
- _. _. -. _... _ _ _._____..._________i._._.
l 01/17/95 Page 16 j
9 Mouticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Rwy 152 Nw of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, 908 $5362 Comunercial Service Dates June 30, 1971 Minneapolis, MN 55401 ISO Ites Report Number Method Results System Item Description Exam Date ASME Section XI Item 181-97006-B W-11 94-0293 PT NAD Recire Manifold B Safe End-to-Nozzle 10/01/94 B 5. 10 ISI 9700$-B W-25 94-0294 PT NAD Recirc Manifold A Safe End-to-Nozzle 10/01/94 B 5. 10
'ISI!97005-B W-24 94-0295 PT NAD Recire Manifold A Pipe-to-Safe End 10/01/94 9 9. 11 New 1SI-19 W-1
- M0296 "PT
'NAD
~
Inst Nozzle N-12A Nozzle-to-Safe End 10/01/94 8 5. 20 NT ~O 7' PT
~NAD New IS1-19 W-2 C
Inst Norsle N-12A Safe End-to-Reducer 10/01/94 B 9. 40 New Pfg 1 W-e 94 0298 MT
~'
i
~
NAD Reactor Vessel T.H. Flange Weld 10/01/94 B 1. 4 0 ISI-782-A W-26B 94-02998L PT NAD Head Vent Coupling-to-Pipe 10/03/94 B 9. 40 iSI-782-A
'W-23A 94-0300BL PT NAD~
Head Vent Pipe-to-Coupling 10/03/94 B 9, 40 ISI-782-A W-23B 94-0301BL PT NAD Head Vent
' Coupling-to-Pipe 10/03/94 B 9. 40 151-782-A W-26A 94-0302BL PT NAD Head Vent Pipe-to-Coupling 10/03/94 B 9.
40 Ne7 Fig 5 N-2E NV 94-0303
~tTTO NAD Reactor vessel N-2E Noz/Vs1 Weld 10/01/94 B 3.
90 New' Fig 5 N-2E NV 94-0304 UT45 NAD Reactor Vessel N-2E Nor/ Val Weld 10/01/94 9 3. 90 Limited due to configuration and thermal wire connection.
New'Flg'S '
N-^'2E NV 94-0305 "VT60 NAD-~~
Reactor Vessel N-2E Noz/ Val Weld 09/29/94 B 3. 90 Limited due to configuration and thermal wire connection.
Reactor Vessel IN-2J Nos/Vs1 Weld 09/27/94 B 3. 90 Limited due to configuration l
and thermal wire connection.
Reactor Vessel N-2J Noz/ Val Weld 09/27/94 B 3. 90 Limited due to configuration
~
~
jandthermalwireconnection.
New Flg'S 3 N- '2J NV 94-0300
' UTO NAD Reactor Vessel N-2J Nos/ Val Weld 09/27/94 B 3. 90 1..
Reactor Vessel
'N-2E Inner Radius 09/30/94 B 3.100 Limited due to thermal wire ec,tpn._
Eeactor vessel iN 2J Inner Radius 09/27/94 9 3.100 i
Limited due to thermal wire i
_... --_.___.-~--_ _i
. connection.
Reactor Vessel
'N-2D Inner Radius 09/30/94 9 3.100
. Limited due to thermal wire
.'.h.*".'...
Reactor vessel IN-2D Noz/Vs1 Weld j09/30/94 l B 3. 9J l
01/17/95
~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ' ~ ^ ~~~ ' ~ ~ ' ' ' ~ ~ ~
~~-- ~~ ~ ~
~Page 17 1
l i
J Monticello Nuclear Generating Plant Inservice Inspection Report Log Norchern States Power Company old swy 152 Nw of Monticello Third Interval By Report 8 414 Nicollet Mall Monticello, MN $5362 Cossnercial service Dates June 30, 1971 Minneapolis, MN $5401 130 Item Report Number Method Results system Item Description Exam Date ASME Section XI Item New Fig b N-2D NV 94-0313 (TT4 5 NAD Reactor Vessel N-2D Nor/Vs1 Weld 09/29/94 B 3. 90 Limited due to configuration and thermal wire connection.
Reactor Vessel N-2D Nos/ Val Wr:1d 09/29/94 B 3. 90 Limited due to configuration 1
and thermal wire connection.
J Reactor vessel N-3A Val /Nos Wald 10/01/94 B 3. 90 Seactor Vessel B. Head / Vessel 10/01/94 8 1. 21 Limited due to access restrictions.
New'Fjg'4 VCBB-1 94-0317 UT60 NAD Reactor Vessel B. Head / Vessel 20/01/94 B 1. 21 Limited due to access restrictions.
"New Fig 5 N-1A NV 94-0318 tTT60 NAD Reactor Vessel N-1A Val /Naz Weld 10/01/94 B 3. 90 Limited due to configuration.
Ne~w' Fig 5 N-1A NV 94-0319 LTT4 5 NAD Reactor Vessel N-1A Vel /Not Weld 10/01/94 B 3. 90 L2mited due to configuration.
New Fig 4 VCBB-1 94+0320 ITT4 5 NAD Reactor Vessel B. Head / Vessel 10/01/94 B 1. 21 Limited due to access restrictions.
151-97006-C H-4
-94'O i2iBL VT3 1ND-Recirc Pump B Snubber / Lugs 10/03/94 P-A,B,C B10.20 Missing fluid level indicator scale.
(
~1SI 97006'-C H-4 94 - 03'21BLR1 "VT3 NAD f
Recirc Pump B snubber / Lugs
/ /
F-A,B,C 810.20 Use as-is w/ Technical Justification.
IS! 97006-C H-5 94-0322BL VT3 NAD Recirc Pump B Snubber / Luge 10/03/94 F-A,B,C B10.20 N8w Fig 6 Washers 94-0323 VT1
'IND Reactor Vessel 20 washers 10/03/94 B 6. 50 Pitting Reactor vessel 20 Wushers
/ /
9 6. 50 Use-as-is w/ Technical Justification.
._....._...-_q Main Steam A Valve Int Surfaces 10/04/94 B12. 50
'1SI-13142-34. A V-4 94-Os25BL VT3 NAD
{10/04/94 B12. 50 Main Steam B Valve Int surfaces l
l
-.-m Main Steam C JValve Int Surfaces 10/04/94 B12. 50
-.. q Main Steam D Valve Int Surfaces 10/04/94 B12. 50
_.,,i Bottom Head Drain
{ Elbow to-Pipe 10/04/94 8 9. 40 i
y Bottoe Head Drain Pipe-to-Elbow 10/04/94 B 9.
40
...-..._n.-_.-
01/17/03 Page is
,e Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company 014 Nwy 152 Nw of Monticello Third Interval Rf Report 8 414 Nicollet Mall
(
Nonticello, MN $5362 Commercial Service Date: June 30, 1971 Minneapolis, MN $5401 ISO Item Report Number Method Results System Item Description Exam Date ASKE Section II Item IS1-821-A W 24 94-0330 MT NAD Bottom Head Drain Coupling-to Pipe 10/04/94 B 9.
40
..._..m.
Bottom Head Drain Pipe-to-Coupling 10/04/94 B 9.
40 i$l-82iTA H-4 94-0332 VT3 NAD~ ~ ~ ~
Bottom Head Drain Box Restraint 10/04/94 P-A,B,C
' l.51 78EA~
H-1 94 0333 VT3 NAD~
2 Head Vent Hanger 10/04/94 F-A, B, C 5
New 151-16
'W-1
~~94-0334~
' ' 'PT' ~
'NAD~~
Jet Pmp Instrmtation Safe End / Nozzle BA 10/04/94
- 95. 10 ISI-13142-20.B H-3 94-0335BL VT3
NAD~
Core Spray A Snubber / Clamp 10/03/94 F-A,B,C
..~. _...., _
RHR Discharge A Dbl Strut-6-Snubber 10/03/94 F-A,B,C 151-13142-37-C H-4 94-0336BLR1 VT3 NAD RHR Discharge A Db1 Strut-&-Snubber 10/21/94 F-A,B,C Reexamination after snubber bolt replacement.
New' Fig 3 W-3 94-0337' UTO NAD Reactor Vessel B.H. Circ Weld 10/04/94 B 1. 21
_._.y Reactor Vessel 64 RPV Nuts 10/03/94 B 6, 10 New' Fig 3 W-3 94-0339
~'UT45 NAD Reactor Vessel B.H. Circ Weld
. 10/03/94 B 1. 21 Limited due to configuration.
New Fig 3 W-3
' M 94-0340 UT60 NAD Reactor Vessel B.H. Circ Weld 10/03/94 B 1. 21 Limited due to configuration.
New Fig $
N-8A NV 94-0341
'~UTO NAD Reactor Vessel N-6A No2/Vol Weld 10/04/94 B 3. 90
~Nes Fig 5 N-BA'NV 94-0342 UT45 "NAD Reactor Vessel N-8A Nos/ Val Weld 10/04/94 B 3. 90 Limited due to configuration.
Reactor Vessel N-BA Noz/ Val Weld 10/04/94 9 3. 90 Limited due to configuration.
181k13142J37-A~
H-"3 94-0344BL VT3
'~~~~~~~~*NAD-~
RHR Discharge A Snubber 10/04/94 F-A,B,C 151-13142-37-A H-3 l94-0344BLR1 VT3 NAD FHR Discharge A Snubber 310/21/94 F-A,B,C Reexamination after snubber bolt replacement.
IS! 13142-37-B H-5 94 0345BL VT)
NAD Contaifment Spray snubber / Lugs 10/04/94 F-A,B,C C 3.20
-~ ~ ] ~
tsi-13142 37 A H-6
T94 - 034 ti VT3 NAD ~
RHR Discharge A St rut / Clamp 10/04/94 F-A,B,C I s i - i 314 2 '- 1'8 A "
~'
H-~1'~'~~~
~ ~ ' ~ ' ~ ~ '
9470347~~~~
' VT i~ - ~-~ ~~ ~
NAD~
RHR Discharge B Strut / Clamp 10/04/94 F-A,B,C Reactor vessel N-1A Inner Radius 10/04/94 B 3.100 01/17/93 Page 19
e Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Hwy 152 NW of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, MN 55352 Commercial Service Dates June 30, 1971 Minneapolis, MN 55401 ISO Item Report Number Method Results System Item Description Exam Date ASNE Section II Item New Fig 5 N-6A 1R 94-0349 trr70 NAD Reactor Vessel N-8A Inner Radius 10/04/94 B 3.100 i
i lsj';Tji42 42 A'
~~~HT1 94 635d5L VT3 NAD T 7 4
HPCI Steam Snubber / Clamp 20/05/94 F-A,B,C ISI-13142-49 A H 10 94-0351BL VT3 IND L
RHR Suction B Snubber / 01 amp 10/05/94 F-A,B,C Thread engagement and drawing conformance.
T 4 !
H 1'0' 94-0351BLR1 VT3 NAD
^1Sf!ili'~~2 4 9T RHR Suction B Snubber / Clamp
/ /
F-A,B,C Use-as-is w/ Technical Justification.
IS! ~11141-3 3 - A H-A
^
94T6]S2BL Vf3~'
'NAD~
~
Main Steam A Snubber / Clamp 10/05/94 F-A,B,C 1SI-13142-33-A H-7 94-0353BL VT3 NAD Main Steam A Snubber / Clamp 10/05/94 F-A,B,C iSiT1314f-35 A H-3 94-0354BL VT3 NAD Main Steam C Snubber / Clamp 10/05/94 F-A, B, C New ISI-16 W-1 94-0355 tries NAD Jet Pmp Instrmtation Safe End / Nozzle SA 10/05/94 8 5. 10 ISI-97005-A W-14 LS U 94-0354 l'T~
'NAII Recirculation A Elbow-to-Pump 10/05/94 9 9.
10
~isf-97005-A W-14 LS U 94-0357 UT45 NAD Recirculation A Elbow-to-Pump 10/06/94 B 9. 10 Limited due to configuration.
ISI-97005-B W-24 94-0358 UT45 NAD Recirc Manifold A Pipe-to-Safe End 10/03/94 B 9. 11 Limited due to configuration.
........_..___.-.._1._..._.______.
ISI-13142-42-A W-46 94-03598L MT NAD HPCI Steam Valve-to-Pipe 10/06/94 C 5. 51 ISI-13142-42-A W-45 94-0360BL MT NAD HPCI Steam Pipe-to-Valve 10/06/94 C 5. 51 ISI-97DD6-B W-11 94-0361
- IUT45 NAD Recire Manifold B Safe End-to-Nozzle 10/06/94 B 5.
10 ISI-97006-8 W-18 94-0362 UT45 NAD Recire Manifold B Safe End-to Nozzle 10/06/94 B 5. 10 ISfT 70M-B W-25 94-0363 trf 4 5 NAD 9
Recirc Manifold A Safe End-to-Nozzle 10/05/94 B 5. 10 IS!-97006-A B-2 94-0364 UTO NAD Recirculation B RC Pump B Stude 10/07/94 B 6.180 8 6.200
'tsi-97005-C H-10 94-J365 VT3 NAD Recirculation A Restraint 10/07/I*
F-A,B,C
- - - ] 94T0366BL l MT NAD 1SI-13142-33-A W-3J Main Steam A Pipe-to-Va.tve 10/08/94 l B 9.
11
,- -. - -.... -.. -.1
- - -- I
\\
Main Steam B Pipe to-Valve 10/07/94 B 9, 11 ISIa13142a35 A-
~' ~ ^ "W-34~ ' ' ~ ~ ~ ~
"'i94-0368BJ' ~ ~
MT-'-~~~
~ ~ ~ ~
NAD~
Main Pteam C
, Pipe to-Valve 10/07/94 B 9, 11 I
i
__ _. - _. ~.
..__..L..._
._....._._...-...I.____-.1--_...-
____..1___
j 01/17/95 Page 20
e I
Monticello Nuclear Generating Plant inservice Inspection Report Log Northern states Power Comipany Old Ewy 152 NW of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, NW 55362 Commercial Service Date June 30, 1971 Minneapolis, MN 55401 180 Item Report Number Method Results System Item Description Exam Date ASME Section XI Item 94-0369BL MT NAD ISI-13142-36-A lW 35 Main Steem D
( Pipe-to-Valve 10/07/94 B 9. 11
'IS913142-36-A B-8 94-0370BL VT1 NAD Main Steam D Valve Bolte 10/06/94 B 7. 70 Examined in place.
~1SI 1Ti4f: 35 A~
B-2 94-0371BL VT1 NAD 2
Main Steam C Valve Bolts 10/06/94 B 7.
70 Examined in place.
ISI-13142-34-A B-5 94-0372BL VT1 NAD Main Steam B Valve Bolts 10/06/94 B 7.
70 Examined in place.
. g ;j3343,33,A--- - - - - -
l B - 8 94 - 0 373'BL VT1 NAD Main Steam A Valve Bolts 10/06/94 B 7. 70 Examined in place.
ISI-13142-53-A V-3 94-0374 VT3 NAD Feedwater Valve Int Surfaces 10/08/94 B12. 50 ISI-13142-26-A V-3 94-0375BL VT3 NAD Core Spray A Valve Int surfaces 10/10/94 B12. 50 ISI-13142-34-A B-1 94-0376BL VT1 NAD Main Steam B Flange Bolts # W-13 10/08/94 B 7.
50 Examined in place.
ISI-13142-34-A B-3 94-0377BL VT1 NAD Main Steam B Flange Bolte e W 16 10/08/94 B7 50 Examined in place.
'ISI1314 b 3 3 - A D-1 94-0378BL VT1 IND Main Steam A Flange Bolts e W-12 10/08/94 B 7. 50 Examined in placei Thread engagement.
1SI-13142-33-A B-1 94-0378BLR1 VT1 NAD Main Steam A
' Flange Bolts e W-12
/ /
B7 50 Use-as-is w/ Technical Justification.
~*
^iSI i)142-33-A B-9 94-0379BL VT1 NAD-Main Steam A Valve Bolts 10/08/94 B 7. 70 Examined in place.
ISI-13142-33.A
'B-3 94-03'80BL VT1 NAD~~'
Main Steam A Flange Bolte e W-16 10/08/94 B 7.
50 Examined in place, f
IS1-13142-33-A B-10 94-0381BL VT1
'NAD~'
Main Steam A Valve Bolts 10/08/94 B 7.
70 Examined in place.
ISI-13142-36-A B-1 94-0382BL VT1 NAD i
Main Steam D Flange Bolte # W-13 10/08/94 B 7.
50 Examined in place.
ISI-13142-35;A"--
B-3 94-038385 VT1 NAD i
Main Steam D jFlange Bolts e W-17 10/08/94 B7 50
{
r Examined in place.
~5 94-0384BL VT1 NAD~
j Main Steam C Flange Bolts a W-14 10/08/94 B 7. 70
[
j
[Examinedinplace.
iSI 11142-35-A B-7
~~
N0I8 5Ei, VT1 INAD
[
Main Steam C Valve Bolts IC/08/94 9 7. 50 jExaminedinplace.
ISI-13142-35-A B-7 94-0385BLR1 VT1 NAD hain Steam C Valve Bolts 10/21/94 B 7.
50 1
Examined in place after g s g.1'314 2 - 3 5'- A B-4
~ - ~ ~
~' ~ ~^' 94' 0 86BU- ~
~~~~NAD-
~
Main Steam C Flange Bolte e W-18 l10/08/94
{ B 7.
50 l
l Examined in place.
I
'iSI f3'42-35 A"'
" ~ ~
~
B T~ ~'
~ ~'~~~ ~ l 9f-"0387BL'' ~
VT1
'NAD 1
?
Main Steam C Valve Bolts 10/08/94 B 7.
50 Examined in place.
01/17/9Q Page 21
a Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Company Old Nwy 152 NW of Monticello Third Interval By Report #
414 Nicollet Mall Monticello, NM 55362 Connercial Service Dates June 30, 1971 Minneapolle, MN 45401 ISO Item Report Number Method Resulta System Item Description Exam Date ASME Section XI Item IS1-13142-42 A W-21h 94-0388BL UTO NAD HPC1 Steam Pipe-to Pipe 10/10/94 C 5.51 HPCI Steam Pipe to Pipe 10/10/94 C 5.51 HPCI Steam Pipe to Pipe 10/10/94 C 5.51 IS G13142 4'2 A '"~~ ~ " ~ ~ ~
~ 1 -
T W 21A 94-0391BL
~'~UT45
~ ~ ~ ~ - ~
'NAD~
HPCI Steam Pipe-to-Pipe 10/10/94 C 5.51 ISI-i~142-42-A
~
H-2 94-0192^
VT1' IND~
1 HPCI Steam Spring / Clamp 10/10/94 P-A,B,C Loose bolt and load below allowable.
"JSt-1'3142-4f A H2 94-0392R1
'VT3 NAD
~
HPCI Steam Spring / Clamp 20/13/94 F-A,B,C Reworked W 219~
96 0393BL~~
MT~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ' ~
'NAD~
S 15 61314642 A'"
~ ~ " - "
HPC1 Steam Pipe to Pipe 10/10/94 C 5.51
~ISI'13i42-42 A W-IIA 94-0394BL MT NAD HPCI Steam Pipe to Pipe 10/10/94 C 5.51
~._._.-..--}
HPCI Steam valve to-Tee 10/10/94 C 5. 51 ISI-97027-A
' H-3 94'-0396BL ~
'VT3 NAD RHR 6'qualiger Snubber / Clamp 10/08/94 P A,B,C Main Steam A Pipe-to-Valve 10/10/94 B 9. 11
.Limi t.ed due to.c__onf_igu_ rat.i_on...
Main Steam B Pipe-to-Valve 10/10/94 B 9. 11 Limited due to configuration.
ISI-13142-35 A W-34 94-0399BL trT0 NAD Main Steam C Pipe to-Valve 10/10/94 B 9. 11 Limited due to configuration.
f Ist 13142-36 A W 35 94-0400BL trTO NAD Main Steam D Pipe-to-Valve 10/08/94 B 9. 11 Limited due to configuration.
'H-11 94-0401BL VT3 NAD CRD Scram Header B pests-aint / 4 Luge 10/08/94 F-A,B,C B10.10 ISI-13142-36-A W-35 94-0402HL UT45 GEO Main Steam D Pipe-to Valve 10/08/94 B 9. 11 2
Limited due to configuration.
ISI i314I 42'-A W-18 94 - 04 0'3BL UT45 GEO HPC1 Steam Valve-to-Tee 10/11/94 C 5. 51
.. f. $"*__bO_$ _"Q9"5*3 I. "_:
.GEO_ _. _ _
IS!-13142-13 A_.. -. _,. _ - jW-32.... _ _.
__ _. _ _ _.94 04,3L_. _ -, _.. _
UT45 Main Steam A l Pipe-to-Valve 10/10/94 B 9.
Il
.. - ~ -. - - -
Limited due to configuration.
Main Steam B Pipe-to-Valve 10/10/94 B 9. 11 Limited due to configuration.
ISI 13142 35 A W-44 94-0406BL trT4 5 NAD I
Main Steam C jPipe-to-Valve 10/10/94 B 9.
11 l
ISI-97005-A_. ~..
.)
_94 0407_.
.bI"k.I.*d dye to_configura_ tion.
'H-10 VT3 IND j
Recirculation A Db1 Spring / 4 Luge 10/11/94 F-A,B,C B10.10 Drawing conformance, ggg.g7ons.A~
~~~
' H-iO~
~~' '
'94!0407R1' ' ~ ' ~ f VT3
'NAD Recirculation A Db1 Spring / 4 Lugs
/ /
F-A,B,C B10.10 Use-as-to w/ Techrical 01/17/95 Page 22
l a
Monticello Nuclear Generating Plant Inservice Inspection Report Log Northern States Power Cosipany Old Rwy 152 Nw of Monticello Third Interval By Report #
414 Nicollet Mall monticello, MM $5362 Commercial Service Date: June 30, 1971 Minneapolis, MN 55401 i
ISO Item Report Number Method Results System Item Description Exam Date ASME Section XI Item Justificaiton.
__.._.__._._ __ _ a Recirc Manifold A Spring / Lugs 10/11/94 P-A,B,C B10.10
.(_.
--.4
.g
. - ~ _..
Recirc Manifold a Spring / Legs 10/11/94 P-A,B,C B10.10 ISI-97006-A H-3 94-0410 VT3 NAD Recirculation B Db1 Spring / 4 Lugs 10/11/94 F-A,B,C B10.10 ISI-97005-A H-7 94 0411 VT3 IND Recirculation A Double Spring 10/11/94 F-A,B,C B10.10 Drawing conformance.
ISI-97005-A H-7 94-0411R1 VT3
~NAD kecirculation A Double Spring
/ /
F-A,B,C B10.30 Use-as-is w/ Technical Justification.
, _....ISI-97006-A.. _
H-7 94-0412 VT3
+1ND-~
Recirculation B Db1 Spring / Lugs 10/11/94 F-A,D,C B10.30 Drawing conformance.
ISI-97006-A H-7 94-0412R1 VT)
NAD Recirculation B Db1 Spring / Lugs
/ /
F-A,B,C B10.30 Use-as-is w/ Technical Justification.
ISI-l'3i42-42-A~~~
V-3 94-0413'BL VT3 NAD
~
HPCI Valve Int Surf 10/12/94 B12. 50 l
ISiT '142ji-A'~
^V-3 94-0414 VT3 NAD 13
~
Main Steam A Valve Int Surfaces 10/06/94 B12, 50
-.---..----a
- - - - - - -. - - - ---k Containment Spray Db1 Spring / 4 Lugs 10/12/94 F - A, B, C C 3.20 ISI-13142-42-A W-45 94-0416BL trr4 5 NAD HPC1 Steam Pipe-to-Valve
/ /
C 5. 51
____..._____.{
HPCI Steam Valve-to Pipe
/ /
C 5. 51 ISI-13142-37 B H-7
~ I54-0418 VT3 NAD Containment Spray Db1 Spring / 4 Lugs 10/13/94 P-A,B,C C 3.20
.---..---.m CRD Housings CRD Housing Bolts 10/19/94 B 7.
80
.------m Main Steam B Snubber / Clamp 10/21/94 F-A,B,C Limited to verification of fluid level following addition.
I s g.. 14 6 ; o A
' ~ ~
HT'~ ~ ~ ~
^
' ~~-
9 6042iBi, VT3 IND 3
Core Sprey B Snubber 10/21/94 F-A,B,C Thread engagement.
I nubber
/ /
F-A,B,C S
Case Spray B USE AS IS W/ TECHNICAL 8
JUSTIFICATION
~~"~~~i94-0422BL TVT3 IND IS!-93269+1-A H-13 CRD Setam Header A Strut / Clamp
!08/27/93
!F-A,B,C
._j
. Drawing C_onformance CRD Scram Header A iStrut / Clamp 01/12/95 F-A,B,C j
Use as is w/ technical 3"'tifiCI "
01/17/95 Page 23
1 I
NORTHERN STATES POWER MONTICELLO INSERVICE INSTPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 Appendix D Section XI VT-2 Examinations (1 page) i I
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NORTHERN STATES POWER MONTICELLO INSERVICE INSPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 List of VT-2 Examinations Test Number Type System Results 0255-03-llB Functional Core Spray Sat 0255-04-IIB-1 Functional A RHR Sat 0255-04-11B-2 Functional B RHR Sat 1
0255-06-llB Functional HPCI Sat 0255-08-ilB Functional RCIC Sat 0255-20-IIC-2 Leakage RPV Sat l
1 l
h-l h
NORTHERN STATES POWER MONTICELLO INSERVICE INSPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 Appendix E 1
Reactor VesselInspection I
(pages 1 through 4) l
.4 1
m J
REPORT OF IN-VESSEL EXAMINATION RESULTS PERFORMED FOR MONTICELLO NUCLEAR GENERATING PLANT SEPTEMBER 1994 EXAMINATION
SUMMARY
REPORT INTROI)UCTION During the period of Septenber 13,1994 through October 4,1994, General Electric Nuclear Energy personnel performed an In-Vessel Examination (IVVI) of the Monticello reactor pressure vessel (RPV) internals. This section describes the procedures and techniques utilized, examination personnel, and the results of the examinations.
EXAMINATION PROCEDURES The following Northern States Power procedures were used for the examination.
ISI-VT-4.0, Rev. 2 Visual Examination of Monticello Reactor Vessel Interior ISI-VT-4.1, Rev. O Visual Examination of Monticello Reactor Vessel Shroud EXAMINATION PERSONNEL The following lis' identifies the certification levels of the General Electric visual examination personnel who performed the IVVI.
1 Name Visual /IVVI Examiner Level M. J. Anderson LevelII J. L. Briggs ImelIII L. L. Clawson LevelII D. O. Henry ImelIII V. W. Hurlburt LevelII D. A. King LevelII D. T. McNeil LevelII R. A. Whitaker LevelII EXAMINATION TECHNIQUES The examinations were performed using a remote ETV 1250 black -and-white camera and CCTV l
equipment. The cameras were used with straight lenses using hand held techniques and remotely operated vehicles (ROVs). The camera resolution standard used for examinations performed using procedme ISI-VT-4.0, with the exception of the core spray sparger and piping examinations, was a I/32 inch black line on an 18% neutral g:tay background. The camera resolution used for the core spray sparger and piping examinations was a 0.001 inch wire. Examinations of the reactor vessel shroud were performed using an " enhanced" technique in accordance with procedure ISI-VT-4.1, utilizing a 0.0005
)
inch wire resolution standard. The resolution was verified at the beginning and ending of each sideotape I
(except for those tapes with *information" examinations), each examination or series of examinations, and when equipment was changed.
-)
EXAMINATION RESULTS Be.evant Indications l
- 1. A crack in the core spray piping was observed at 89 degrees. This crack is approximately 1.9 in length. During the last examination in 1993 the crack was measured as approximately 1.8 inches in length. The measurements of the crack length were made by NSP personnel using a computer enhanced imaging system. The crack is on the left section of the header pipe on the side which faces into the vessel and is adjacent to the tee-box at 90 degrees.
- 2. A crack. was obsen ed in the lower bracket to vessel pad weld of the upper riser brace of Jet Pump No.
- 8. The crack was observed parallel to the weld at the weld toe extending over half the width of the brace.
This crack had been observed and documented during previous outages. The video tape of this riser brace from the last examination in 1993 was compared to this examination and no significant growth was obsened.
- 3. Crack indications were observed in thejet pump restrainer set screw tack welds on 12 jet pumps. The results of the set screw tack weld exammations for all 20 jet pumps are shown in Table 1.
- 4. Crack indications were observed on the outside of the core shroud near welds H4 and H5 between Jet Pump 4 and Jet Pump 5 (corresponding approximately to lug sets 8 and 9). In the lower heat -affected zone (HAZ) of weld H4,4 circumferentially oriented linear indications were obsencd over an area approximately 51/2 inches in length beginning approximately 5 inches from Jet Pump 5. A spot (1/8 in.)
indication near the toe of the weld was also noted in that area. Also in the lower HAZ of weld H4 at i1 inches was a transverse crack indication approximately 1/2 inch in length starting at the toe of the weld i
following a series of arc strikes. Two additional ciremnferentially oriented linear indications were
.)
observed in the lower HAZ of weld H4 approximately 1/2 inch in length approximately 12 inches from Jet Pump 5. A transverse, branched, linear indication approximately 1 inch in length was observed in the lower HAZ (core plate support ring side) of weld H5 approximately 6 inches from Jet Pump 5.
- 5. Crack indications were observed on the inside of core shroud near the H4 weld in the upper HAZ between sl roud head bolt hold-down lug set 9 (near Jet Pump 5) and lug set 7 (near the riser between Jet 3
Pumps 3 ahd 4). In the scan from lug set 9 to lug set 8, circumferentially oriented linear indications were obsened over an area approximately 7 inches in length beginning approximately 5 inches from the beginning of the scan at lug set 8. The second scan from lug set 8 to lug set 7 followed the indications for approximately another three inches. Within that three inch area, the indications became intermittent, with the longest spot approximately 1/2 inch in length. Approximately 9 - 10 additional inches were covered in the second scan toward lug set 7, and ro additional indications were obsen'ed.
- 6. During the top guide examination, IRM 17 was obsened to be unlatched. This was noted as an information item and is listed in the tape log for tape 19-RPV-19.
Nonrelevant Indications There were some areas that contained indications that were determined to be nonrelevant. These areas included the core spray sparger and piping, a jet pump riser brace and jet pump sensing line bracket.
Many of these indications can be attributed to the coating of material that builds up selectively on the component surfaces. Many of these indications are commonly referred to as witness marks which result from disturbance of the coating by camera cables, invessel tools or fixtures. Other indications can be caused by scratches or component features whose appearance is affected by the camera angle or lighting.
Any indications which were suspected of being relevant senice-related conditions, such as cracks, were investigated by reexamination using adjustments in camera angle, viewing distance, and/or lighting.
Numerous scratches and grind marks were observed on many of the various components.
y REPORT OF IN-VESSEL EXAMINATION RESULTS ws..
~)
PERFORMED FOR MONTICELLO NUCLEAR GENERATING PLANT SEPTEMBER 1994 WORKSCOPE RPVInternal Component Examination The list contained in this section identifies the Monticello Invessel RPV Internals that were scheduled for
. examination. Except where noted, these examinations were performed in accordance with NSP Procedure ISI-VT-4.0 Revision 2.
- 1. Vessel Cladding was examined in the area of vessel attachments including the steam dryer lugs, feedwater end brackets andjet pump riser braces.
- 2. Top Guide, RICSIL 059, examination, Top Guide hold down latches and ring bolting.
- 3. Core Spray Sparger and piping.
- 4. Guide Rod Brackets at 0 degree and 180 degree locations, including attachment welds, and reciad areas.
- 5. Twenty Jet Pumps, including hold down beams, wedge assemblies, restrainer set screws, suction inlet, riser braces, slipjoints, diffuser to adapter welds, adapter to and shroud support ledge welds.
- 6. Shroud Shelf Welds, i.e., shroud support ledge to shroud weld, access hole cover welds, and shroud support ledge to vessel weld. These welds were examined with enhanced resolution requirements in accordance with NSP Procedure ISI-VT-4.1.
l
- 7. Surveillance Sample Holders and Brackets at the southwest, southeast, and northwest locations. Note:
j the south 4st sample holder has been removed.
- 8. Feedwater Sparger and Accessible Areas of the Nozzle Inner Radius.
f
- 9. Steam Dryer Support Brackets and Attachment Welds.
]
1 Shroud Welds Selected locations on the H4 and 115 shroud welds were examined with enhanced resolution in accordance with NSP Procedure ISI-VT-4.1. Locations examined were between shroud head bolt lugs 5 and 6, lugs 8
)
I and 9, and lugs 14 and 15.
1 i
)
4
1
)
Nonrelevant Indications (cont.)
A considerable amount of debris, including weld wire, tie wrap, screws, and other foreign material particles, were observed on the shroud support plate. The debris locations are identified on the tape log.
l TABLE 1. JET PUMP SET SCREW EXAMINATION RESULTS Jet Pumn Num_hgr Shroud Side Set Screw Vessel Side Set Screw 1
No Indications NoIndications 2
2 Indications 2 Indications 3
2 Indications 2 Indications (1 small) 4 No Indications No Indications 5
2 Indications (1 small)
No Indications 6
No Indications 2 Indications 7
1 Indication 2 Indications 8
NoIndications No Indications 9
NoIndications NoIndications 10 NoIndications NoIndications I
11 No Indications Ne Indications 12 1 Indication 1 Indication (small) 13 NoIndications NoIndications j
14 2 Indications 2 Indications T
15 NoIndications No Indications
-.)
16 2 Indications 2 Indications 17 IJoIndications 2 Indications (1 smah) 18 2 Indications 2 Indications 19 No Indications 2 Indications 20 1 Indication 1 Indication w
NORTHERN STATES POWER MONTICELLO INSERVICE INSPECTION
SUMMARY
REPORT THIRD INTERVAL 1994 t
i Appendix F Snubbers inservice Testing i
(1 Page) f r
f i
L t
i n
a
?
NORTHERN STATES POWER MONTICELLO i
INSERVICE INSPECTION
SUMMARY
REPORT THIRD INTERVAL.
1994 List of Functionally Tested Snubbers ISI isometric ISIItem Plant item Results ND-ISl-144 SS-211 SS-211 Sat ISI-13142-42A H-11 SS-707 Sat NCR 94-235 ISI-97003-A H-3 SS-18B Sat ISI-13142-37A H-3 SS-25 Sat ISI-13142-37B H-5 SS-31 Sat ISI-13142-36A H-2 SS-1 Sat ISI-13142-49A H-10 SS-22 Sat ISI-97005-C H-5 SS-4AR-B Sat ISI-13142-33A H-3 SS-2 Sat SS-315-1 Sat RV-24A-H7 Sat SS-347 Sat l
SS-345 Sat RV-24-H3 Sat RV-25-H1 Sat RV-27A-H2A Sat RV-25A-H2 Sat SS-44 Sat RV-27A-N1 Sat RV-27-N1 Sat 1
RV-25A-H7 Sat l
SS-43 Sat PS-34 Sat NCR 94-234 RV-26-H2 Sat i
RV-26A-NS1B Sat SS-187 Sat i
b i
1
--m
.