Reactor Bldg Post-Tensioning Sys Initial SurveillanceML19312C926 |
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Oconee  |
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Issue date: |
03/20/1975 |
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From: |
DUKE POWER CO. |
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To: |
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Shared Package |
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ML19312C925 |
List: |
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References |
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NUDOCS 8001140585 |
Download: ML19312C926 (12) |
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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 ML16141B0771996-11-18018 November 1996 Errata to TS 3.7,which Removes Criteria for Battery & Battery Charger Specific Svc Tests 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 ML16141A9291995-06-29029 June 1995 Proposed Tech Specs Re Mgt Positions Authorized to Approve Such Items as Procedures & Procedure Changes,Station Mods, TS Amends & Reportable Events ML16141A8581995-01-0909 January 1995 Revs to Oconee Selected Licensee Commitments Manual ML16141A8111994-04-20020 April 1994 Proposed Tech Spec Table 4.1-2, Min Equipment Test Frequency ML16141A7981994-04-12012 April 1994 Proposed Tech Specs Re Technical Review & Control Activities ML15261A4281994-02-24024 February 1994 Proposed TS 4.6, Emergency Power Periodic Testing 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 ML16131A5241992-03-0101 March 1992 Rev 35 to ODCM Generic Section 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 ML16131A5221992-01-0101 January 1992 Rev 32 to Oconee 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 ML20081J9841991-06-10010 June 1991 Rev 3 to EDA-1, Procedure for Estimating Food Chain Doses Under Post-Accident Conditions 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 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 ML16148A9621991-02-13013 February 1991 Public Version of Rev 10 to CMIP-12, Crisis Mgt Implementing Procedure 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 ML15217A1291991-01-0101 January 1991 Rev 29 to Odcm,Oconee 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 1999-08-18
[Table view] Category:TEST REPORT
MONTHYEARML20212G1041987-01-0606 January 1987 Cycle 9 Startup Test Rept ML20198S5141986-05-29029 May 1986 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 ML16223A6041983-03-31031 March 1983 Generic Startup Physics Test Program 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
________
i 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 RETENSIONING AND FILLER REPLACEMENT 4
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.
Surveillance was conducted December 13 through December 20. 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 ly.
- - 1: -
5
2.0
SUMMARY
Ajg) CONCLUSIONS 2.1
SUMMARY
No significant discoloration of the sheathing filler Laboratory analysis of sheathing filler samples sho was observed.
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 as cracking eads.
The lif t-off forces for all surveillance tendons were of predicted values,'considering the effects of concretwithin the range shrinkage, e creep and steel relaxation and initial structural deformation The tendon wires were in excellent condition and no length of the wires was observed.
corrosion along the had occurred during the interval since the initial RIt was determ Structural Integrity Test.
eactor Building Mechanical tests of specimens showed no significant changes in th ultimate _ strength of the wire as compared to results obt i e
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 ation, Unit 2, is'in excellent condition, that the functional capability of the~syst not diminished, and that the system shows no detectable e id em has 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
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 tYg 13H9 Shop Yes Yes Yes Yes Yes Yes e
Field Yes Yes Yes Yes Yes Yes e
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 i
4 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 1
23V14 2.0 0.0 0.0 O
i I
1 i
i f
' i
. Table 2 i
d 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
\\
4 1
i
.l
.: i Table 4 J
r ULTIMATE STRE!!GTH OF TENDON SPECIME ;S r
Break Tensile Specimen Force Diameter Area Strength 2
Tendon Location (Lbs.)
(In.)
(In )
(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
a 51H9 8.0
+ 53H10 25 E ra E$
7.0
\\
Lower Limit = 7.22 kips g
d l
HORIZONTAL TENDONS n.
g Upper Limit = 8.6 kips f
9.0 g
23V14
= 45V16 8.0
+ 61V16 4
Lower Limit = 7.34 kips d l
l VERTICAL TENDONS i
I s
I y
5 5
4 4
4 5
10 20 30 40 TIME (Years)
- -