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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999 Proposed Tech Specs,Consisting of 1999 Changes to TS Bases ML17265A6941999-06-28028 June 1999 Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping ML17265A6401999-05-12012 May 1999 Rev 11 to Technical Requirements Manual for Ginna Station. ML17265A6261999-04-18018 April 1999 Rev 10 to Technical Requirements Manual (Trm), for Ginna Station ML17311A0701999-04-14014 April 1999 Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure. ML17309A6521999-04-14014 April 1999 Rev 14 to AP-RCS.1, Reactor Coolant Leak. ML17309A6531999-04-13013 April 1999 Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr ML17265A6111999-03-26026 March 1999 Rev 9 to Technical Requirements Manual for Ginna Station. ML17265A5911999-03-0101 March 1999 Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A5571999-02-25025 February 1999 Rev 4 to Technical Requirements Manual (Trm). ML17265A5491999-02-12012 February 1999 to EOP FR-H.5, Response to SG Low Level. ML17265A5481999-02-12012 February 1999 to EOP ATT-22.0, Attachment Restoring Feed Flow. ML17265A5461999-02-12012 February 1999 0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required. ML17309A6481999-01-25025 January 1999 Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr ML17265A5151999-01-14014 January 1999 Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index ML17265A5081999-01-0808 January 1999 Rev 7 to Technical Requirements Manual, for Ginna Station ML17265A4961998-12-18018 December 1998 Rev 6 to Technical Requirements Manual. ML20198C0361998-12-14014 December 1998 Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required ML20198C0121998-12-14014 December 1998 Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow ML20198C0581998-12-14014 December 1998 Rev 5 to FR-Z.1, Response to High Containment Pressure ML20198C0411998-12-14014 December 1998 Rev 16 to FR-C.1, Response to Inadequate Core Cooling ML20198C0521998-12-14014 December 1998 Rev 13 to FR-S.1, Response to Reactor Restart/Atws ML17265A4661998-11-24024 November 1998 Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR ML20155G0301998-10-30030 October 1998 Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop ML17265A4091998-08-24024 August 1998 Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr ML17265A3721998-07-16016 July 1998 Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr ML17265A3151998-06-0404 June 1998 Proposed Tech Specs Basis Re Main Steam Isolation Setpoint ML17265A2941998-05-21021 May 1998 Tech Specs Consisting of Submittal Changes for 1998 ML17265A2861998-05-0606 May 1998 Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr ML17265A2461998-04-27027 April 1998 Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17265A1821998-02-20020 February 1998 Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria. ML17265A1491997-12-31031 December 1997 Rev 1 to Inservice Testing Program. ML17264B0731997-10-14014 October 1997 Rev 4 to Technical Requirements Manual (TRM) for Ginna Station. ML17264B0671997-10-0808 October 1997 Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements ML17264B0441997-09-29029 September 1997 Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept ML17264B0391997-09-29029 September 1997 Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study ML17265A1541997-09-16016 September 1997 Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification. ML17264B0031997-08-19019 August 1997 Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3 ML17264A9991997-08-19019 August 1997 Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A9791997-08-0505 August 1997 Rev 7 to AP-RCS.3, High Reactor Coolant Activity. ML17264A9781997-08-0505 August 1997 Rev 12 to AP-RCS.1, Reactor Coolant Leak. ML17264A9771997-08-0505 August 1997 Rev 11 to AP-RCP.1, RCP Seal Malfunction. ML17264A9751997-08-0505 August 1997 Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses. ML17264A9851997-08-0404 August 1997 Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants. ML17264A9391997-07-0707 July 1997 Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev ML17264A9341997-07-0101 July 1997 to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624 ML17264A9461997-06-20020 June 1997 to Inservice Insp (ISI) Program. ML17264A9241997-06-0303 June 1997 Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection ML17311A0471997-05-22022 May 1997 Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr ML17264A8671997-04-24024 April 1997 Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements 1999-06-28
[Table view] Category:TEST REPORT
MONTHYEARML17263A3221993-04-30030 April 1993 Reactor Containment Bldg Integrated Leakage Rate Apr 1993, Ginna Nuclear Station. ML17250B0221989-05-31031 May 1989 Reactor Containment Bldg Integrated Leakage Rate. ML17251A7911986-03-31031 March 1986 Reactor Containment Bldg Integrated Leakage Rate Test. ML17309A3531984-08-15015 August 1984 1984 Steam Generator Eddy Current Exam Summary Rept. W/850306 Ltr ML17254A8901984-06-26026 June 1984 Startup Physics Testing Program. ML17255A7181984-01-31031 January 1984 Containment Vessel Tendons, 1983 Surveillance Final Rept ML17255A7191983-12-31031 December 1983 Containment Vessel Tendons Stress Relaxation Properties of Retensioned Wires. ML17256A6831983-04-15015 April 1983 Level Control Valve 427 Fuse Coordination - Ginna Station. ML17256A4281982-12-15015 December 1982 Reactor Containment Bldg Integrated Leak Rate Test,May 1982. ML17255A6891982-11-16016 November 1982 Dynamic Collapse of Steam Generator Tubes. ML17256A9771982-05-18018 May 1982 Addendum 1, Lab Collapse Tests, Revision 0,to Steam Generator Evaluation,Ginna Steam Tube Failure Incident, 820125,RE Ginna Nuclear Power Plant. ML17256A9811982-05-18018 May 1982 Addendum 3, Phase II Metallurgical Exams, Revision 0,to Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125,RE Ginna Nuclear Power Plant. ML17256A9831982-05-18018 May 1982 Addendum 4, External Tube Loading Test, Revision 1 to Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125,RE Ginna Nuclear Power Plant. ML17256A9791982-05-18018 May 1982 Addendum 2, Lab Fatigue Testing, Revision 0,to Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125,RE Ginna Nuclear Power Plant. ML17256A8541982-04-26026 April 1982 Steam Generator Evaluation,Ginna Steam Tube Rupture Incident,820125,RE Ginna Nuclear Power Plant. ML17258A2041981-09-21021 September 1981 Adequacy of Station Electric Distribution Sys Voltages. ML17258A7461981-01-29029 January 1981 to App C-Ginna Station Inservice Pump & Valve Testing Program for 810101 Through 901230. ML17250A5991980-07-31031 July 1980 Piping Stress Analysis Rept,Rhr Sys,Section 200. ML17250A5901980-07-31031 July 1980 Re Ginna Nuclear Power Plant,Seismic Upgrading Program Piping Stress Analysis,Main Steam Sys,Section 200. Main Steam Containment Drawing Encl ML17250A5861980-07-31031 July 1980 Piping Stress Analysis Rept,Rhr Sys,Section 250. ML17249A9101980-04-11011 April 1980 Revised Pages 4,6 & I-2,Table 3 & Figure 1-A for Evaluation of Prestressed Tendon Forces. ML17249A3371979-11-20020 November 1979 Evaluation of Prestressed Tendon Forces. ML20081C0311976-02-28028 February 1976 Reactor Containment Bldg Integrated Leak Rate Test ML17258A1351973-11-12012 November 1973 Qualification Tests for Modular Penetration 5 Diameter (Prototype B1). ML17244A5781966-09-16016 September 1966 Submits Info Re Seismic Qualification of Mechanical & Electrical Equipment & Fluid & Electric Distribution Sys. Includes Test Repts,Tech Specs & Oversized Drawings 1993-04-30
[Table view] |
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GAI REPORT NO. 2074 EVALUATION OF PRESTRESSED TENDON FORCES FOR ROBERT E. GINNA NUCLEAR POWER STATION NOVEHBER 20, 1979 Revision I 4-11-80 GILBERT ASSOCIATES, INC.
READING) PENNSYLVANIA Qbert /Commonwealth
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- 2) Concrete Shrinka e For the Ginna site region, the Hean Daily Relative Humidity is in the 70/ to 80% range. Therefore, from Table 1 of Reference 5, the 40 year shrinkage strain is
-6 100 x 10 in/in. For purposes of plotting on a log-time (log t) scale, shrinkage is taken to start 1. hour v
(0.00011 yr.) after the date corresponding to the average date of containment wall concrete placement. The containment wall construction and stressing dates are given in Figure 2. The shrinkage strain varies linearly
-6 with log t from zero at t = 0.00011 yr. to 100 x 10 in/in at t = 41.4 years (40 years after initial stressing) and K
is shown in Figure 3.-
Only the containment shrinkage which occurs after initial stressing (t = 1.41 years) influences the loss of tendon force. Based on the assumed shrinkage strain variation, a strain of 78 x 10 -6 in/in at t = 1.41 years is calculated. The tendon force loss at t = 41.4 years is predicted to be:
-6 -6 (100 x 10 in/in - 78 x 10 in/in) (29 x 10 6
psi)
. 2 (4.42 in ) = 2.8 kips which is shown in Figure 3.
A variation of +20% in the predicted values is allowed by Reference 5:
The recommended specific creep formula from Appendix A of Reference 5 is:
s c =
Ae 1 - e o + B log 10 (t/to )
f c Rbcrt ICeamewealth Rev1eed 4-11-80
1 vJ' C
E
0.45 and 0.34 for the"5000 psi concrete used in the Ginna containment. The specific creep curves in Appendix C of Reference 6 were used in the calculations.
From Figure 2, the average age of the containment wall at time'f initial stressing was 515 days 'oncrete (1.41 years). A specific creep curve for a concrete age 515 days was obta'ined by extrapolating from the curves in Appendix C of Reference 6. Based on this extrapolated curve, the concrete in the containment wall is predicted to have a 1 year specific creep of 0.08 x
-6 10 in/in/psi and a 40 year specific creep of 0.23 x
-6 10 .
in/in/psi., The corresponding losses of tendon force are:
At 1 ear after initial stressin (t = 2.4)
-6 6 (0.08 x 10 in/in/psi) (628 psi) (29 x 10 psi)
(4.42 in ) = (0.08 x 10 ) (80497 x 10 ) = 6.4 kips At 40 ears after initial stressin (t = 41.4)
(0.23 x 10 ) (80497 x 10 ) = 18.5 kips The creep loss is zero at t = 1.41 years after concrete placement and varies with log t as shown in Figure 3. A variation of +25/ and -15% in the predicted value is allowed by Reference 5.
4.3 QUESTION
Was there a chemical analysis of the groundwater at the site?
RESPONSE: Not to our knowledge. Corrosion protection for the anchor was provided by grouting. This method has been successfully used on a number of projects. See References 7 and 8.
Qbert ICommonwegtth Revised 4-11-80
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TABLE 3 TEN YEAR LIFT-OFF FORCE EST TE FORCE LAST LAST PREDICTED TENDON FIGURE TEST FORCE 'EST NUNBER AMBER (ki s) (Year) (ki s) REHARKS 53 4-1 625 8 621 All predicted forces are based on the Base Value predicted slope through last test data unless noted otherwise.
133 4-2 ,630 626 45 4-3 637 634 4-4 632 627 36 4-7 632 679(627) Based on predicted slope thru 3 year test data (based on 8 year test data).
95 4-13 615 611 142 4-18 612 607 4-24 612 655 (607) Based on predicted slope thru 3 year test data (based on predicted slope thru 8 year test data).
84 4-30 588 584 126 4-31 687 683 160 4-33 612 607 76 4-35 605 602 117 4-42 663 658 110 4-37 657 653 60 4-19 647 621 63 4-14 647 3 630 150 4-40 658 3 640 159 4-10 673 650 51 4-12 665 636 83 4-11 653 624 100 4-16 627 610(575) Based on actual slope thru 1 and 3 year test data (based on predicted slope thru 3 year test data).
132 4-25 653 6 mo. 614 631 Average Lift Off Force in 22 Tendons teated (estimated) nr vi srd 4-11-80 TASLE 3
4 I
a FIGURE 1-A TENDON STRESSING SE UENCE Jack /tl Jack ft2 Jack 83 Jack /I4 13 53 93 133 149 25 69 105 1 45 81 127 21 57 101 137 17 65 97 145 9 61 89 141 5 49 85 129 157 44 77 121 153 26 73 108 151 '27 71 107 185
'139 36 75 79 ill 128 43 3 47 85 125 7 51 87 131 11 55 91 135 15 59 95 139 19 63 99 143 23 67 103 147 24 68 104 148 22 66 102 146 20 64 100 144 18 62 98 142 16 60 96 140 14 58 94 128 12 56 92 136 10 54 90 134 8 52 88 132 6 50 86 130 4 48 84 123 2 46 82 126 160 41 ,
80 124 158 42 78 122 156 . 40 76 112 154 30 74 110 152 28 72 109 150 29 70 106 32 31 113 117 33 37 114 118 34 38 115 119 35 39 116 120
= Retensioned at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />".
FIGURE l-A Revised 4-11-80 TENDON STRESSING SEQUENCE
~v T
0 4
k 7,
The tendons were also overstressed to approximately 6% above the force required to produce lift-off, and the tendon elongations recorded. The results are presented in Table I-2. The elongations ranged from 3/16 inch to ll/16 inch, and the corresponding tendon force increases ranged from 8.9 to 51 kips.
The average tendon force increase was 33.7 kips, and the average elongation was 8/16 inch. The predicted elongation for a straight tendon under the 33.7 kip force ~s 6/16 inch. Therefore, the tendon elongations appear to be reasonable, and no abnormal tendon behavior is indicated. Differences in elongations (for approximately the same tendon force increase) are attributed to (1) inaccuracy in determining the point of lift-off, which could be significant for the relatively small tendon force increment, and (2) variations in the friction at each tendon.
The retest indicated higher values than the 8 year tests and general agreement with the slopes of the predicted curves. Where several previous tests are available, Figures 4-4, 4-7, 4-24, the retest value appears to be in line with other earlier tests. Of the 22 tendons, only tendons 51 and 63, Figures 4-12 and 4-14, show greater slopes than predicted. =The results would indicate that many of the 8 year test values were in error.
The average force in the tested tendons was found to be 634 kips.
The predicted average force was 631 kips. The average force based on the technical specification requirement that the tendon stress be at least 144,000 psi is 636 kips. The technical specification also allows for 5% broken wires. If no wires are broken and the allowance were applied to the stress, the minimum required force per tendon would be 604 kips.
Qbett /Commonwealth I-2 Revised 4-11-80
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