|
|---|
Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML20210G6631999-07-28028 July 1999
Cycle 9 90-Day ISI Summary Rept
ML20197J5621998-12-0303 December 1998
Unit 1 Cycle 9 90-Day ISI Summary Rept
ML20199F8531998-01-13013 January 1998
ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8
ML20217G1551997-07-22022 July 1997
ASME Section XI ISI Summary Rept for Sequoyah Nuclear Plant,Unit 1 Refueling Outage Cycle 8
ML20117J2571996-08-22022 August 1996
ASME Section XI, ISI Summary Rept for Sequoyah Nuclear Plant,Unit 2 Refueling Outage Cycle 7
ML20117L6011996-07-0202 July 1996
Cycle 7 Refueling Outage Apr- June 1996 Results of SG Tube Isi
ML20097F5291996-02-0909 February 1996
Cycle 7 Refueling Outage Sept-Nov 1995
ML20097A1781996-01-25025 January 1996
ASME Section XI ISI Summary Rept Unit 1 Cycle 7
ML20087D3621995-08-0707 August 1995
Sqn,Unit 2 Cycle 6 Insp SG Tubing Insp Results
ML20080G8581994-11-16016 November 1994
SQN NIS-1 Owners Data Rept Unit 2,Cycle 6, Vols 1 & 2
ML20070J1731994-04-20020 April 1994
Cycle 6 ISI Rept, Vols 1 & 2
ML20099E3871992-08-0505 August 1992
Vols 1 & 2 of Sequoyah Nuclear Plant Unit 2,Cycle 5,ISI Summary Rept
ML20086L2331991-12-31031 December 1991
Cycle 5 Refueling Outage Oct - Dec 1991
ML20246C1361989-04-17017 April 1989
NIS-1/90 Day Rept Amend Unit 1 Cycle 3, Vols 6 & 7.W/one Oversize Drawing Encl
ML20235H9931989-01-26026 January 1989
Vols 1-5 to NIS-1/90-Day Inservice Insp Rept,Unit 1 Cycle 3
ML20244C5361988-07-31031 July 1988
Cycle 3B Insp,Steam Generator Tubing Insp Results
ML20236N9951987-08-0404 August 1987
Cycle 2A Insp,Aug 1986,Steam Generator (S/G) Insp Results. No Steam Generator Tube Recorded Defects or Degradation
ML20116A2121985-04-17017 April 1985
Inservice Insp Rept,Describing Ultrasonic Exams of Steam Generator J-tubes
ML20080C9281983-08-23023 August 1983
Rev 0 to Inservice Insp Program
ML20084C3461983-07-31031 July 1983
Steam Generator Tube Inservice Insp Rept,Sequoyah Unit 2 Cycle 1 Refueling Outage
ML20078B8661982-09-30030 September 1982
Steam Generator Tube Inservice Insp Rept,Core 1 Refueling Outage
ML20003J3321981-04-21021 April 1981
Preservice Baseline Insp Program,Revision 11
ML19254D5351979-09-12012 September 1979
Preservice Baseline Insp & Inservice Insp Program,Revision 8
1999-07-28
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999
SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1
ML20217G3721999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With
ML20212F0831999-09-23023 September 1999
Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval
ML20212F4761999-09-23023 September 1999
Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively
ML20212C4761999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With
ML20210L4361999-08-0202 August 1999
Cycle 9 12-Month SG Insp Rept
ML20216E3781999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20210L4451999-07-31031 July 1999
Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20210G6631999-07-28028 July 1999
Cycle 9 90-Day ISI Summary Rept
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20209H3831999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With
ML20211F9031999-06-30030 June 1999
Cycle 9 Refueling Outage
ML20196J8521999-06-28028 June 1999
Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i)
ML20195K2951999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20206Q8951999-05-0505 May 1999
Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10
ML20206R5031999-04-30030 April 1999
Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With
ML20205P9811999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20204C3111999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20205B6631999-02-28028 February 1999
Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys
ML20203H7381999-02-18018 February 1999
Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions
ML20211A2021999-01-31031 January 1999
Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections
ML20198S7301998-12-31031 December 1998
Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20199G3641998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20197J5621998-12-0303 December 1998
Unit 1 Cycle 9 90-Day ISI Summary Rept
ML20197K1161998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20195F8061998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With
ML20154H6091998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20154H6251998-09-17017 September 1998
Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr
ML20153B0881998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With
ML20239A0631998-08-27027 August 1998
SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2
ML20236Y2091998-08-0707 August 1998
Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08
ML20237B5221998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Snp
ML20237A4411998-07-31031 July 1998
Blended Uranium Lead Test Assembly Design Rept
ML20236P6441998-07-10010 July 1998
LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134
ML20236R0051998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant
ML20249A8981998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2
ML20247L5141998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant
ML20217K4471998-04-27027 April 1998
Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05
ML20217E2221998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant
ML20248L2611998-02-28028 February 1998
Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2
ML20199J2571998-01-31031 January 1998
Cycle 9 Voltage-Based Repair Criteria 90-Day Rept
ML20202J7911998-01-31031 January 1998
Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2
ML20199J2441998-01-29029 January 1998
Snp Unit 2 Cycle Refueling Outage Oct 1997
ML20199F8531998-01-13013 January 1998
ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8
ML20199A2931997-12-31031 December 1997
Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2
ML20198M1481997-12-31031 December 1997
Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2
ML20197J1011997-11-30030 November 1997
Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2
ML20199C2951997-11-13013 November 1997
LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns
ML20199C7201997-10-31031 October 1997
Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant
L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997
SG Secondary Side Loose Object Safety Evaluation
1999-09-30
[Table view] |
Text
l k .
e 4
o-e l
STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT SEQUOYAH NUCLEAR PLANT UNIT 1
- CYCLE 1 REFUELING OUTAGE SEPTEMBER 1982 i
l 1
h I'
I l
~
8309270287 030921 il\? PDR ADOCK 05000327 G .. _ .
PDR
. CONTENTS TABLE I - Inspection Summary TABLE II - Inspection Summary S/G 1 TABLE III - Inspection Summary S/G 4 TABLE IV - tubes Recording Da'm age in S/G 1 TABLE V - Tutes Recording Damage f ri S/G 4 FIGURE 1 - Dent Size Frequency Distribution for S/G 4 Tubes Tested in 1981 and 1982 4
e 4
o I
i l
l l
I l,-
4 U
f TABLE I '
I INSPECTION
SUMMARY
- SEOUOYAll UNIT #1 Steam Generators il & #4 f
S/G #1 S/G $4 Totals Inlet Outlet Inlet Outlet i
Tubes In Steam Generator '
(Straight Lengths) 13,552 3388 3388 3388 3388 Total Tubes Inspected (Straight Lengths) 525 267
, 0 220 39 Tubes Recording Severe Damage .'
(Approximate Wall Loss 40% a Greater) 0 0 0 ,0, 0 Tubes Recording Moderate Damage (Approximate Wall Loss 20% to 39%) 8 3* 0 5* 0 ,
Tubes Recording Minor Damage (Approximate Wall Loss Less Than 20%) 29 16 0 12 1 S/G ll: 2 tubes with lane blocker damag'e unchanged since 1981 1 tube recorded indication unchanged f rom baseline inspection S/G #4:
- all 5 tubes recorded indications unchanged from baseline inspection 4
e
a.
. TABLE II INSPECTION
SUMMARY
Sequoyah Unit'#1 - Steam Generator $1 Total Hot Leg Cold Leg Tubes In Steam Generator $
(Straight Lengths) 6776 3388 3333 Tubes Inspected -
3 (Straight Lengths) 267 267 0 Tubes Recording Severe Damage (Approximate Wall Loss 40% & Greater) 0 0 0 Tubes Recording Moderate Damage (Approximate Wall Loss 20% to 39%) 3 3* 0 Tubes Recording Minor Damage (Approximate Wall Loss Less Than 20%) 16 16 0 Tubes Inspected For Row #1 U-Bend 184 92 92 Additional Inspected By Hand Probing 6 6 0 2 tubes with lane blocker damage present in 1981 1 tube recorded indication at baseline and is unchanged l
-~"" ~ - --- . - --.- - ~ . -
,- .. ....n-,..
l <-
. ~ -
TABLE III INSPECTION
SUMMARY
Sequoyah Unit #1 - Steam Generator #4 Total Hot Leg Co'1d Lee Tubes In Steam Generator (Straight Lengths) 6776 3388 3383 s i Tubes Inspected
( Straight Lengths) 258 220 38 Tubes Recording Severe Damage (Apprcximate Wall Loss 40% & Greater) 0 0 0 Tubes Recording Moderate Damage (Approximate Wall Loss 20% to 39%) 5 5* 0 Tubes Recording Minor Damage -
(Approximate Wall Loss Less Than 20%) 13 12 1 Tubes Inspected For Row #1 U-Bend 8 8 0 All indications were recorded by baseline inspection and are unchanged.
I sm , . -
. . . . . ~
XAdLE IV TUBES RECORDING DAMAGE IN STEKM GENERATOR S1
, Sequoyah Unit #1 Tube i Defect R C Oricin % Location Notes INLET (HOT LEG)
, 1 1 OD 30 TS-1 External damage near lane bl-
device. Present in 1981 inspection.
1 5 ID 20 TS-1 : Internal imperfection unchanged-since 1981 inspection.
1 6 ID 20 TS-1 Internal imperfection unchanged since 1981 inspection. '
1 26 OD 20 2-3 Small volume external imperfection.
, Nct recognizable on-baseline.
1 78 OD 20 3-4 Small volume external imperfection.
Not recognizable at 400 kHz channel in 1982 inspection. Not recognizable on baseline.
1 90 OD 30 TS-1 External damage near lane blocker device. Unchanged since 1981 inspection.
1 91 00 20 TS-1 External damage near lane blocker device. Unchanged since 1981 inspection. -
1 92 OD 20 TS-1 External degradation near lane blocker device, unchanged since 1981 inspection.
1 94 OD 20 TS-1 External degradation near lane blocker device, unchanged since 1981 inspection.
5 26 OD 20 1-2 External imperfection, present on baseline.
5 61 ID 25 6-7 Internal flaw, present on baseline.
5 76 ID 20 TS-1 Internal imperfection present on baseline.
9 36 ID 20 6-7 Internal imperfection, not recognizable on baseline.
13 11 ID 20 TS-1 Internal imperfection, not recognizable on baseline.
17 16 ID 20 5-6 Internal imperfection, not recognizable on baseline.
25 36 ID 20 5-6 Internal imperfection, not recognizable on baseline.
25 51 ID 20 6-7 Internal imperfection, not recognizable on baseline.
29 11 ID 20 2-3 Internal imperfection, not recognizable on baseline.
41 26 ID 20 TS-2 Multiple internal imperfections.
Not recognizable on baseline.
,- -- , - ,,--e- .-- ,- - .-.Q----. . - , - - - , - . - - - - . . - , . ,
TUBES RECORDING DAMAGE IN STEAM GENERATOR 44 Sequoyah Unit #1
. ' Tube f Defect R C Oricin % Location- Notes INLUT (HOT LEG)
-1 3 ID <'20 TS-1 & 2-3 Multiple' internal imperfections,
-' unchanged since 1981 inspection.
51 56 ID < 20 1-2, 2-3 & .
3-4 Multiple internal imperfections,.
present on baseline.
13 61 ID < 20 TS-1 Internal imperfection. Not -
. recognizable on baseline.
- . 17 56 ID 30 4-5 Inte rnal flaw, present on baseline.
17 81 ID < 20 1-2 & 3-4 Multiple internal imperfections, present on baseline.
25 31 ID < 20 7-U-bend Internal imperfection unchanged since 1981 inspection; present on baseline.
25 81 ID < 20 5-6 Internal imperfection. Not
, recognizable on baseline.
~
29 11 ID < 20 TS-1 Internal imperfection unchanged since 1981 inspection; present on baseline.
29-56 ID < 20 TS-1 Internal imperfection present on baseline.
29-83 ID 30 5-6 Internal flaw, unchangel since 1981pinspection; present on baseline.
30-46 ID 25 2-3 & 3-4 Mult'iple internal flaws, present i on baseline.
H 33 46 ID < 20 4-5 Internal imperfection. Not recognizable on baseline.
Intbrnal imperfection.
~
33 76 ID < 20 2-3 Not recognizable on baseline.
34 79 ID < 20 TS-1, 1-2
& 5-6' Multiple internal imperfections, unchanged since 1981 inspection; present on baseline. '
37 20 ID <20' l-2 & 67 b Multiple-internal imperfections.
37 35 ID 30 TS-1 Internal f'l aw , recorded in 1981 inspection (25 % ) '; present on
,. . baseline.
46 45 ID 25 4-5 ' Internal flaw; present on baseline.
UTLET (COLD LEG)
. 41 13 ID < 20 CTS-Cl Internal imperfection unchanged sincp 1981 inspection.
Et 4 - , ~, rws . , .
~ ~ ^
__;_ 3 ~ - -
. _ , - -' : 7 -- -erp .a
. _ . - - - = . . . _ . _ ._.. _ _ _ ._ t > a __
2 0 / ~S.
/ 2 0 0 9
1 31 7
/
, Y ,
A 4 S
0 1
1 ot F 0 0 /
L 6 o0 .
/ 9 1
I l7 /* 2H r 4 0
V B :
I : ; 1 R d T
D S /o
/ ET
/
a 0 3 S 4 Fd EC 3
l m r
%. L
- t
/ E ~7JC L Y.
4 1
/ 1 D # E 3 T 1 i Y t d I
C o T
N A
/7 E
E L rC 2 U E 7 /
L /
- /
G N X l f h S E E S.
7 M G T
S f
f W A D E y
E / / E E 7 T T3 D 2
/
T 7
4 lf A!
t i 6 b
S $ t
/.
6' d0
/
4 r
N E
D X t.
2 4
- f rrE to d A E D
7 D 7
4 4
o
' p f o #
3 y
%1?k V %g k' gN%%k'h _
II. e
. l . , :; 1
