Reactor Bldg Post-Tensioning Sys Initial Surveillance.| ML19312C926 |
| Person / Time |
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| Site: |
Oconee  |
|---|
| Issue date: |
03/20/1975 |
|---|
| From: |
DUKE POWER CO. |
|---|
| To: |
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|---|
| Shared Package |
|---|
| ML19312C925 |
List: |
|---|
| References |
|---|
| NUDOCS 8001140585 |
| Download: ML19312C926 (12) |
|
|
|---|
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
________
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- O DUKE POWER COMPANY OCONEE NUCLEAR STATION UNIT 2 REACTOR BUILDING POST-TENSIONING SYSTEM INITIAL SURVEILLANCE s
!
March 20, 1975 8001340N 1
. -
TABLE OF CONTENTS Section Pa g e_
1.0
_
INTRODUCTION 1
2.0
SUMMARY
AND CONCI.USIONS 2.1
SUMMARY
2 2,2 CONCLUSI0SS 2 2
3.0 RESULTS 3.1 SHEATHING FILLER 3 3.2 END ANCHORAGE COMPONENTS 3 3.3 LIFT-OFF FORCES 3 3.4 WIRE SURVEILLANCE AND TESTING 3 3.5 4 RETENSIONING AND FILLER REPLACEMENT 4
i w
. -
- 1. CL INTF0 DUCTION The 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 quality of the system. 1te program consists of periodic inspections of nine pre-selected tendons - three horizontal tendons, three vertical tendons and three dome tendons - for symptoms of material deterioration or force reduction. The program assesses the condition and functional capability of the system and, therefoce ,
verifies the adequacy of the system and provides an opportunity to take proper corrective action should adverse conditions be detected .
The requirements for the program are detailed in the Oconee Technical Specifications, Sections 4.4.2.1 and 4.4.2.2.
December 13 through December 20.
Surveillance was conducted 1974 in accordance with approved test procedure PT/0/A/150/14, Reactor Building Tendon Surveillance Program, and the results of this initial inspection are reported herein .
l y.
- - 1: -
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5
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_
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. -
2.0
SUMMARY
Ajg) CONCLUSIONS 2.1
SUMMARY
No significant discoloration of the sheathing filler was observed.
Laboratory analysis of sheathing filler samples sho be well within acceptable limits. wed impurities _to The end anchorage components were found to be in ex cellent condition with no sign of the development of adverse conditions or excessive corrosion, or missing or deformed buttonhsuch eads.
as cracking The lif t-off forces for all surveillance tendons were of predicted values,'considering the effects of concretwithin shrinkage, e creep and the range steel relaxation and initial structural deformation .
The tendon wires were in excellent condition and corrosion nothe along length of the wires was observed.
had occurred during the interval since the initial RIt was determ Structural Integrity Test. eactor Building Mechanical tests of specimens showed no significante changes in th ultimate _ strength of the wire as compared to results obt i initial acceptance tests. a ned during
2.2 CONCLUSION
S Based on the tests and inspections described her i the post-tensioning system for Oconee Nuclear Ste n, it is concluded that excellent condition, ation, Unit 2, is'in that the functional capability of the~syst em has not diminished, and that the system shows no detectable e id j.
occurrence of any adverse deterioration. v ence of the
!
9
,
. -
3.0 RESULTS 3.1 SHEATHING FILLER The sheathing filler at the ends of the nine surveillance tendons was visually examined. The filler coating on the end anchorage components, and the color and consistency of the filler, were found to be acceptable, with no evidence of water being present - see Table 1.
Samples of sheathing filler were obtained from each of three tendons from which a wire was removed. This filler was visually examined and no signs of water nor any discoloration of the sheathing filler was evident.
Laboratory analysis of the filler samples found impurities to be within acceptable limits - see Table 2.
3.2 END ANCHORAGE COMPONENTS The results of the end anchorage component inspections are given in Table
- 3. Buttonheads were inspected for acceptable shape, general appearance, l
cracks and corrosion. No buttonhead defects or missing buttonheads were observed. Stress washers,. shims and bearing plates were visually inspected for cracking and corrosion. (Some millscale and minor surface corrosion were present on the edges and faces of shims and bearing plates. However, this condition existed at the time of installation ar.d no deterioration has occurred in the interval since installation).
3.3 LIFT-OFF FORCES Lift-off forces were obtained for each surveillance tendon - see Table 4.
From these readings an average force per wire was determined. The long-term trend of these wire forces is shown graphically in Figure 1. Lift-off forces were within the range of predicted values, considering the effects i
of concrete creep and shrinkage, steel relaxation and initial structural deformation.
!
', i l
!
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. -
3.4 WiltE SURVEILLANCE AND TESTING One survefilance tendon of each directional group was relaxed -'lD28 ,
13H9 and 23V14.
One wire was removed from tendons 1D28, 23V14, and 13H9.
The wires. removed were visually checked for corrosion and pitting'-
and to determine their general condition.
The tendon wires-were found to contain minor surface scratches, resulting from insertion of the tendons into their sheaths at the time of installation, and heat treating _ i discoloration.
The general condition of the wires was determined to be equivalent to their condition at time of initial installation.
Three specimens were cut from each of the extracted wires for tensile testing.
The samples were taken from the ends and the middle of each of the wires.
The ultimate strength of each of the specimens was determined by tensile testing by the Prescon Corporation, Simpsonville, South Carolina.
These tests are summarized in Table 5 and revealed no signifi-
'
cant changes in the ultimate strength of the wire as compared to results obtained during initial acceptance tests.
3.5 RETENSIONING AND FILLER REPLACEMENT Following wire removal the tendons were retensioned to approximately the same stress level indicated by the lift-off force data obtained during this surveillance.
The sheathing filler which was removed during the surveillance process was replaced with new filler.
h
.
_- .=
.
.
SHEATHING FILLER INSPECTION
,
Filler Coating Acceptable
.,
Filler Color and Button Stress. Bearing '
Tendon End Heads Washer Shims Plate Cap Acceptable 1D28 Shop Yes Yes Yes Yes Yes Ys Field Yes Yes Yes Yes Yes Y 2D28 Shop Yes Yes Yes Yes
- Yes Yes Field Yes Yes Yes Yes Yes Yes 3D28 ' Shop Yes Yes Yes Yes Yes
.
Yes Field Yes Yes Yes Yes Yes Yes tY g 13H9 Shop Yes Yes Yes Yes Yes e Yes Field Yes Yes Yes Yes Yes e Yes 51H9 Shop Yes Yes Yes Yes Yes Yes Field Yes Yes Yes Yes Yes Yes 53H10 Shop Yes Yes Yes Yes Yes Yes Field Yes Yes Yes Yes Yes
. Yes 23V14 Shop Yes Yes Yes Yec Yes Yes Field Yes Yes Yes Yes Yes Yes 45V16 Shop Yes Yes Yes Yes Yes Yes Field Yes Yes Yes Yes Yes
.
Yes 61V16 Shop Yes Yes Yes Yes Yes Yes Field Yes Yes Yes Yes Yes Yes
. _
7, _ _
i . .
' LABORATORY ANALYSIS OF SHEATil1NC FILLER
Water Soluble Water Soluble . Water Soluble CHLORIDES NITRATES SULFIDES Tendon (Limit 5.0 ppm) (Limit 5.0 ppm) (Limit 5.0 ppm)
,
1D28 < l.0 0.0 0.0
. .
13H9 < l.0 0.0 0.0 23V14 2.0 0.0 0.0 1
.
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.,
.
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.
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.
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,
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c . ~ r , ,, e - . 7.. - , ., --,
_ _ - . _ _ _ _ __ _. - _ _
. .
.
END ANCHORAGE COMPONENT INSPECTION
. . _ _
Buttonheads Stress Washer Shims Bearing Plate Tendon 'End Corrosion Cracks Shape Corrosion Cracks Corrosior Cracks :orrosion Cracks
.
1D28 Shop None None Good None None None None None None Field None None Good None None None None None None 2D28 Shop None None Good None None None None None None e Field None None Good None None None None None None
-
3D28 Shop None None Good None None None None None None Field None None Good None None None None None None
@ 13H9 Shop None None Good None None None None None None f
"
Field None None Good None None None None None None 51H9 Shop None None Good None None None None None None Field None None Good None None None None None None 53H10 Shop None None Good None None None None None None Field None None Good None None None None None None 23Vl'4 Shop None None Good None None None None None None Field None None Good None None None None None None 45V16 Shop None None Good None None None None None None Field None None Good None None None None None None 61V16 Shop None None Good None None None None None None Field None None Good None None None None None None
.
_ _ - - _ - _ . _ _ _ _ _ _ _ _ _ _ - -
.
. -
1DiDON LIFT-OFF FORCES
.
Tendon Force (Psi) 1D28 5225 i 2D28 5700 3D28 5817
,
1 3119 5500
._
i SlH9 5700 l
53H10 5750 23V14 5714 45V16 5650 61V16 5817 i
. l
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4 ,
1 i
-
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.
Table 4
--
J
r
. .
,
ULTIMATE STRE!!GTH OF TENDON SPECIME ;S
.
r Break Tensile Specimen Force Diameter Area Strength Tendon Location (Lbs.) (In.) (In2) (pgt)
Shop 12,100 0.250 0.0491 246435 1D28 Center 12,100 0.250 0.0491 246435 Field 12,100 0.250 0.0491 246435
.
Shop 12,600 0.250 0.0491 256619 23V14 Center 12,650 0.250 0.0491 257637 Field 12,600 0.250 0.0491 256619 - '
Shop 12,350 0.250 0.0491 251527 13H9 Center 12,350 0.250 0.0491 251527 Field 12,450 0.250 0.0491 753561
.
I
%
a e
.
. .
,
.
.
.. .
Table 5
.
- - - - - - - - -
. . .- . . _ _ _ _ _ . __ . _ _ . . _ . _
.
.
.
.
TENDON SURVEILLANCE FORCE-TDE PLOT Upper Limit = 8.6 kips- f 9.0 _ __
. [_ ,
. .. :D2s a 2D28 8.0
+ 3D28 j
y -
7.0 Lower Limit - 7.2 kips-I DOME TENDONS l Upper Limit = 8.6 kips j 9.0 / _
__
e 13H9 7
& 8.0
+ 53H10 25 E ra - $ -
E$: 7.0 Lower Limit = 7.22 kips \
g
. d n.
l HORIZONTAL TENDONS
! Upper Limit = 8.6 kips g -
f g 9.0
-- -
. 23V14
" = 45V16 8.0 + 61V16
_
4 - - -
, -
- Lower Limit = 7.34 kips d l
l VERTICAL TENDONS
' '
i y 5 4 4 4
.
TIME (Years)
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ - - - - - _ - _ _ - _ _ - . . . _ _ _ _ - - _ _