Reactor Bldg Post-Tensioning Sys,End Anchorage Surveillance.| ML19317F281 |
| Person / Time |
|---|
| Site: |
Oconee  |
|---|
| Issue date: |
10/29/1974 |
|---|
| From: |
DUKE POWER CO. |
|---|
| To: |
|
|---|
| References |
|---|
| NUDOCS 8001090614 |
| Download: ML19317F281 (13) |
|
|
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211A9881999-08-18018 August 1999
Rev 5 to DPC Nuclear Security Training & Qualification Plan
ML20204B4141999-03-27027 March 1999
Revised Oconee Nuclear Station Selected Licensee Commitments, List of Effective Pages
ML20155C6391998-10-26026 October 1998
Proposed Tech Specs Tables 4.1-1 & 4.1-2,revised Surveillance Frequency of Refueling Outage to 18 Months
ML20154L7191998-10-0505 October 1998
Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations
ML20154C1021998-09-30030 September 1998
Proposed Tech Specs Changing UFSAR by Increasing Max Rod Internal Pressure in Spent Fuel Pool from 1,200 to 1,300 Psig
ML20236V9611998-07-27027 July 1998
Corrected TS Bases Pages 3.5-30b of 961211 & 3.16-2 of 970205,correcting Amend Numbers
ML20236T5171998-07-20020 July 1998
Proposed Tech Specs Re one-time Extension to Functional Test Frequencies for Hydraulic & Mechanical Snubbers
ML20236R1901998-07-16016 July 1998
Proposed Tech Specs Extending TS Surveillances TS 4.20.2(a), Table 4.20-1,items 1,2 & 4,TS 4.1-1,Table 4.1-1,items 8,9,10 & 11 & TS 4.5.1.2.1,item b(1)
ML20217F2841998-04-20020 April 1998
Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations
ML20141F1521997-06-25025 June 1997
Rev 4 to Nuclear Security Training & Qualification Plan
ML20134K5401996-10-31031 October 1996
Rev 6 to Chemistry Manual 5.1, Emergency Response Guidelines
ML20117J0181996-08-15015 August 1996
Revised Chapter 16 of Oconee Selected Licensee Commitments Manual
ML20095H1291995-12-0505 December 1995
Rev to ONS Selected Licensee Commitments (SLC) Manual, Revising SLC 16.6.1, Containment Leakage Tests to Reflect Current Plant Configuration & Update Testing Info
ML20091P2461995-08-21021 August 1995
Rev to ONS Selected Licensee Commitments Manual
ML16141A8111994-04-20020 April 1994
Proposed Tech Spec Table 4.1-2, Min Equipment Test Frequency.
ML15224A3521993-10-26026 October 1993
Safety Assurance Directive 6.1, Oconee Nuclear Site Safety Assurance Emergency Response Organization.
ML20044C9581993-05-0404 May 1993
Proposed TS 4.7.1, Control Rod Trip Time Test.
ML20045F0721993-04-0707 April 1993
Rev 9 to Corporate Process Control Program Manual.
ML20097D9451992-05-28028 May 1992
Rev 11 to Training & Qualification Plan
ML20096C2561992-04-30030 April 1992
Public Version of Revised Crisis Mgt Implementing Procedures (Cmip),Including Rev 46 to CMIP-1,Rev 39 to CMIP-4,Rev 45 to CMIP-5,Rev 49 to CMIP-6,Rev 48 to CMIP-7,Rev 42 to CMIP-9 & Rev 3 to CMIP-15
ML20096D5451992-04-0707 April 1992
Public Version of Revised Crisis Mgt Implementing Procedures (Cmip),Including Rev 45 to CMIP-1,Rev 27 to CMIP-13 & Notification of Deletion of CMIP-8.Procedure CMIP-8 Reserved for Future Use
ML20092M5891992-02-0606 February 1992
Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 43 to CMIP-1,Rev 43 to CMIP-5,Rev 33 to CMIP-8,Rev 25 to CMIP-13,Rev 6 to CMIP-18,Rev 4 to CMIP-22 & Rev 38 to CMIP-4
ML20094H2391992-01-0101 January 1992
Rev 33 to McGuire Nuclear Station Odcm
ML20094H2511992-01-0101 January 1992
Rev 34 to Catawba Nuclear Station Odcm
ML20087F3931991-12-11011 December 1991
Public Version of Rev 13 to Crisis Mgt Implementing Procedure CMIP-11, Emergency Classification - Mcguire. W/ 920121 Release Memo
ML20086K8831991-11-18018 November 1991
Public Version of Revised Crisis Mgt Implementing Procedures (Cmips),Including Rev 42 to CMIP-1,Rev 29 to CMIP-2,Rev 42 to CMIP-5,Rev 12 to CMIP-11 & Rev 37 to CMIP-21
ML20086G7711991-10-16016 October 1991
Public Version of Revs to Crisis Mgt Implementing Procedures (Cmip),Including Rev 41 to CMIP-1,rev 37 to CMIP-4,rev 41 to CMIP-5,rev 46 to CMIP-6 & CMIP-7,rev 32 to CMIP-8,rev 40 to CMIP-9,delete CMIP-12 & Rev 24 to CMIP-13
ML20082C7441991-06-11011 June 1991
Public Version of Rev 13 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station
ML20076A7241991-06-10010 June 1991
Public Version of Crisis Mgt Implementing Procedures, Including Rev 39 to CMIP-1,rev 28a to CMIP-2,rev 44 to CMIP-7,rev 39 to CMIP-9 & Rev 10 to CMIP-11
ML20081J9841991-06-10010 June 1991
Rev 3 to EDA-1, Procedure for Estimating Food Chain Doses Under Post-Accident Conditions
ML20081K0101991-06-0606 June 1991
Rev 8 to EDA-3, Offsite Dose Projections for McGuire Nuclear Station
ML20072S0521991-03-15015 March 1991
Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station
ML20066G3621991-02-0101 February 1991
Public Version of Crisis Mgt Implementing Procedures, Including Rev 28 to CMIP-2,Rev 34 to CMIP-4,Rev 38 to CMIP-5,Rev 43 to CMIP-6,Rev 42 to CMIP-7,Rev 29 to CMIP-8, Rev 37 to CMIP-9 & Rev 34 to CMIP-21
ML20082P7611991-01-0101 January 1991
Rev 30 to Odcm,Catawba Nuclear Station
ML20072S9621991-01-0101 January 1991
Public Version of Rev 12 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station
ML20082P7711991-01-0101 January 1991
Rev 31 to Odcm,Mcguire Nuclear Station
ML20072P9621990-11-0808 November 1990
Rev 9 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station
ML20028H2211990-10-31031 October 1990
Public Versions of Revised Crisis Mgt Implementing Procedures,Including Rev 37 to CMIP-1,Rev 27a to CMIP-2,Rev 33 to CMIP-4,Rev 37 to CMIP-5 & Rev 42 to CMIP-6
ML20059F4301990-08-22022 August 1990
Public Version of Rev 27 to Crisis Mgt Implementing Procedure CMIP-2, News Group Plan
ML20063Q2721990-08-14014 August 1990
Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8,Rev 35 to CMIP-9 & Rev 7 to CMIP-11
ML20043F4841990-05-23023 May 1990
Public Version of Crisis Mgt Implementing Procedures, Consisting of Rev 20 to CMIP-13 & Deletion of CMIP-15 & CMIP-17
ML20043B2651990-05-0909 May 1990
Revised Crisis Mgt Implementing Procedures,Including Rev 35 to CMIP-1,Rev 26 to CMIP-2,Rev 31 to CMIP-4,Rev 35 to CMIP-5,Rev 40 to CMIP-6,Rev 39 to CMIP-7,Rev 26 to CMIP-8, Rev 33 to CMIP-9,Rev 2 to CMIP-14 & Rev 10 to CMIP-16
ML20043F4621990-04-20020 April 1990
Rev 5 to Oconee-specific Process Control manual.W/900606 Ltr
ML20006C0571990-01-18018 January 1990
Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan.
ML16152A8951990-01-0202 January 1990
Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations.
ML15264A1571990-01-0202 January 1990
Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21
ML20012A3801990-01-0101 January 1990
Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations.
ML20012A3791990-01-0101 January 1990
Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station.
ML20011D2441989-12-0101 December 1989
Crisis Mgt Implementing Procedures.
ML20012A3731989-11-15015 November 1989
Rev 4 to, Process Control Program Oconee Nuclear Station.
1999-08-18
[Table view]
Category:TEST REPORT
MONTHYEARML20212G1041987-01-0606 January 1987
Cycle 9 Startup Test Rept
ML20198S5141986-05-29029 May 1986
Station,Oconee 3,Cycle 9 Startup Testing Rept,Part 1 Zero Power Physics Test,Part II Power Escalation Test
ML20094C1511984-07-12012 July 1984
Extension of Retainer Lifetime to 4 Cycles
ML20087M4431984-03-26026 March 1984
Cycle 7 Startup Testing Rept
ML20040B0711981-12-31031 December 1981
Analysis of Capsule OCII-A from Duke Power Co Oconee Nuclear Station,Unit 2,Reactor Vessel Matl Surveillance Program.
ML20040B0681981-10-31031 October 1981
Analysis of Capsule OCIII-B from Duke Power Co Oconee Nuclear Station,Unit 3,Reactor Vessel Matls Surveillance Program.
ML20147B6681978-09-29029 September 1978
Integrated Leak Rate Test of Reactor Containment Bldg
ML19340A1351978-05-31031 May 1978
Unit 3,Cycle 3,Startup Testing Summary.
ML19316A5431978-04-30030 April 1978
Cycle 3 Startup Testing Summary.
ML19312C8071977-10-0606 October 1977
Integrated Leak Rate Test of Reactor Containment Bldg.
ML19340A1661977-03-0101 March 1977
Unit 3,Cycle 2,Startup Testing Summary.
ML19312C8481976-10-0101 October 1976
Jocassee Dam QA Test Results. List of Info Submitted on 761001 Encl
ML19316A1151976-06-22022 June 1976
Integrated Leak Rate Test of Reactor Containment Bldg.
ML19312C9261975-03-20020 March 1975
Reactor Bldg Post-Tensioning Sys Initial Surveillance.
ML19322C1301975-03-14014 March 1975
Startup Rept,Unit 3,for 750314.
ML19317F2811974-10-29029 October 1974
Reactor Bldg Post-Tensioning Sys,End Anchorage Surveillance.
ML19322C1711974-08-0909 August 1974
Startup Rept.
ML19322C1291974-08-0505 August 1974
Structural Integrity Test Rept of Reactor Containment Bldg. Prepared for Util
ML19316A4581973-11-16016 November 1973
Startup Rept.
ML19317E4791973-10-12012 October 1973
Rept of Testing of Two Atmosphere Supplying Suits.
ML19322C1681973-09-20020 September 1973
Structural Integrity Test Rept of Reactor Containment Bldg. Prepared for Util
ML19317F0811973-08-23023 August 1973
Reactor Coolant Flow Evaluation, Preliminary Rept
ML19322C1801973-02-15015 February 1973
Results of Oconee 1 Hot Functional Testing,Internals Vibration Monitoring Program.
ML19316A2401971-10-29029 October 1971
Structural Integrity Test Rept of Reactor Containment Bldg. Prepared for Util
ML19317F2451971-08-0505 August 1971
Integrated Leak Rate Test of Reactor Containment Bldg.
ML19316A2271970-07-14014 July 1970
Integrated Leak Rate Test of Reactor Containment Bldg. Prepared W/Technical Assistance by Bechtel Corp
ML19317E7741968-02-26026 February 1968
Keowee-Toxaway Project Jocassee Development;Summary of Matls Testing & Stability Design.
1987-01-06
[Table view] |
Text
_.
t.
DUKE POWER COMPANY OCONEE NUCLEAR STATION 1
1 i
UNrr 2 REACTOR BUILDING Post-TENSIONING SYSTEM END ANCHORAGE SURVEILLANCE jo270-ov./ ///t OCToseR 29, 1974 3o910906/y o
// / 7[
4
1.0 INTRODUCTION
The end anchorage concrete surveillance program for the Oconee Nuclear Station, Unit 2 reactor building post-tensioning system was defined and is executed in order to assure the continued structural integrity of the Reactor Building.
The program consists of periodic inspections of selected end anchorages and adjacent concrete surfaces.
The requirements for the program are detailed in Oconee Nuclear Station, Technical Specification 4.4.2.3. The inspection interval, as specified therein, will be one-half year and one year after the operation of the unit and will occur during the warmest and coldest part of the year. Consequently, the specified surveillance was performed on January 22, 1974 and July 31, 1974.
Results were compared with similar surveillance performed prior to the Reactor Building Structural Integrity Test of June 14 through June 22, 1973.
Surveillance was conducted in accordance with approved test procedure TP/2/B/
0150/13, Prestressing Tendon Anchor Zone Surveillance Program, and the results of this program are reported herein.
I f
t 1.0-1 I
2.0
SUMMARY
AND CONCLUSIONS The inspections at the one-half year and one year intervals after operation were performed as specified during the warmest and coldest part of the year.
Due to a very mild winter, there was little difference in outside air tem-peratures during the inspection.
Visual inspection of the end anchorage exterior surfaces revealed no symptoms
! of abnormal cracking or deterioration.
Measurements of tendon anchor movement showed no abnormal motion during the surveillance program.
Based on the tests and inspections described herein, it is concluded that greater than normal cracking or movements have not occurred and that the functional capability of this portion of the post-tensioning system has not diminished. Therefore, the requirements of Technical Specification 4.4.2.3 have been completed.
l
~
I
(
l 2.0-1 l
l I
1 3.0 RESULTS 3.1 END ANCHORAGE CONCRETE SURVEILLANCE Six locations along the 90 buttress and one location on top of the ring ,
girder in line with the 90 buttress were selected and examined during the
, Reactor Building Structural Integrity Test. Each of these areas were
. selected af ter an overall visual inspection of the accessible buttress areas.
l Results of inspections made prior to the Reactor Building Structural Integrity Test and at the one-half year and one year intervals following initial operation, are presented on Figures 1-7.
3.2 TENDON ANCHOR MOVEMEh7S Position measurements for seven of the tendon anchors were made during the Reactor Building Structural Integrity Test and at the one-half year and one year intervals following initial operation. Results of these measurements are given in Table 1. Details of the demountable reference frames and the location of measurements are shown on Figure 8.
a f
I I
t i
1
}
4 4
I
'3.0-1
4 e
i TABLE 1 PRESTRESSING TENDON ANCHOR MOVEMENTS Temp.
Elevation Outside Micrometer Readings (Inches)
OF l_ Tendon (Feet) Date 1 2[ 3[ 4 24H89 811 6-14-73 72 3.322 4.264 4.562 4.936 1-22-74 76 3.314 4.312 4.615 4.933
- 7-31-74 78 3.397 4.294 4.608 4.940
_ 24H75 834 6-13-73' 85 3.534 2.436 2.701 4.692 ,
! 1-22-74 76 3.532 2.433 2.710 4.700 7-31-74 78 3.525 2.429 2.740 4.695 24H61 857 6-13-73 85 3.359 2.827 2.860 5.110 1-22-74 76 3.349 2.832 2.855 5.109 7-31-74 78 3.347 2.819 2.865 5.112' 24H47 880 6-13-73 85 3.721 3.315 3.258 4.928 1-22-74 76 3.218 3.320 3.260 4.928 7-31-74 78 3.240 3.312 3.256 4.927 4
24H33 904 6-13-73 84 3.745 3.715 3.661 4.385 1-22-74 76 3.745 3.715 3.658 4.380 7-31-74 78 3.739 3.719 3.656 4.385 24H19 927 6-13-73 84 3.547 2.116 2.635 4.632
- l-22-74 76 3.547 2.110 2.632 4.652 i
7-31-74 78 3.550 2.110 2.643 4.653 l
12V28 970 6-14-73 73 4.730 5.246 4.507 1-22-74 76 4.743 5.249 4.502 7-31-74 80 4.750 5.243 4.498 l
~
t e
s a
i
!~ g l
__ _-2_.. . ,. .- ~ . . . . . . . _ - . - _ . .- - , . . _
FIGURE 1 -
00 O&y 7 I
- Ok Acg gg
@ .003 of (
.005 N p,
N \
I
@ .004
.002 i s
A'4 s
I TENDON k
(DATA SET) l (CRACK WIDTH) SCALE:1/2* = 1'-0" TENDON 26H37 ELEVATION 841' DATA TEMP TEMP SET DATE INSIDE OF OUTSIDE OF reb %RKS 1 6-12-73 81 85 2 1-22-74 76 67 NO NEW CRACKS 3 7-31-74 130 78 ONE NEW CRACK FOUND
FIGURE 2 -
NR '80 ,
Sz i g\
N 00I4 W
5 %f 4 x
1 .005 i
/ TENDON ,'
k (DATA SET) l
( (CRACK WIDTH) SCALE:1/2* = 1.0" TENDON 26H37 ELEVATION 841' DATA TEMP TEMP SET DATE INSIDE OF OUTSIDE oF REMARKS 1 6-12-73 81 85 l
2 1-22-74 76 67 NO NEW CRACKS 3 7-31-74 130 78 NO NEW CRACKS
FIGURE 3 9
B- g5 6 Y
9 '
e
% \
@.003 3
(
+ 1 .004 d.\,
.005 N
TENDON T.
(DATA SE.)
V (CRACK WlDTH)
ALE- 1 ** = 1 '.0
TENDON 24H70 ,
ELEVATION 896'
[ DATA TEMP TEMP SET DATE INSIDE cF OUTSIDE OF REMARKS 1 6-12-73 81 85 2 1-22-74 76 67 NO NEW CRACKS 3 7-31-74 130 78 NO NEW CRACKS l
I L
FIGLEE 4 ,
i%
Oi+ gi
1 .002 @ .003 1 .005 I
,N TENDON (DATA SET) v (CRACK WIDTH)
SCALE: 1"= 1*.oa TENDON 24H76 ELEVATION 906' DATA TFEP TEMP SET DATE INSIDE OF OUTSIDE CF REMARKS 1 6-12-73 81 85 2 1-22-74 76 65 NO NEW CRACKS 3 7-31-74 130 78 NO NEW CRACKS l
l t
)
FIGURE 5 4p \ #.4 A Cg / #
4, s ; *'*<<
"T k
/
VV b 1 .002
.004
/ TENDON 1
CDATA SET)
(CRACK WIDTH) SCALE: 1\" = 1'-0" TENDON 24H86
- ELEVATION 920' DATA TEMP T~MP SET DATE INSIDE OF CUTSIDE F REMARKS 1 6-12-73 81 85 2 1-22-74 76 67 NO NEW CRACKS 3 7-31-74 130 78 NO NEW CRACKS l
FIGURE 6 .
k 08 9 E
Ng$
$ OY 4
{s **
s
%v 1 .002
/ L+ s 0
/ TENDON 1
(DATA SET)
(CRACK WIDTH) SCA LE: 1 " = 1 '.0" TENDON 26H89 ELEVATION 927' DATA TEMP TEMP SET DATE INSIDE OF OUTSIDE OF REMARKS 1 6-12-73 81 85 2 1-22-74 76 67 NO NEW CRACKS 3 7-31-74 130 78 NO NEW CRACKS
[
~
FIGURE 7 .
R.B. RADIAL LINE [
(DATA SET) SCA LE: b " = 1'-0" (CRACK WIDTH, IN.)
TEtOON 12V28 ELEVATION 970' DATA TEMP TdMP SET DATE INSIDE OF OUTSIDE OF REMARKS 1 6-12-73 81 85 NO CRACKS FOUND 2 1-22-74 76 65 NO NZW CRACKS 3 7-31-74 130 78 NO NEW CRACKS
4 9 9
e FIGURE 8 .
GREASE cap i REFERENCE FRAME FOR' ff mzm zE_,
//
(/Yy \, .
b h .
l l
REFERENCE FRAME FOR g'
WRIZONTAL TENDONS l
gg "f[bjg GREASE CAP gl Ob
'4 zh 7g
% s
%fe:e s I
4 3
I s.
/g a I -l
/ ;
/
2 l
a gf g6
-