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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML17354B1891998-11-0909 November 1998 Simulatory Certification Update 2. ML17354B0171998-06-29029 June 1998 Rev 1 to PTN-FPER-97-013, Evaluation of Turbine Lube Oil Fire. ML20137M2121996-12-17017 December 1996 Monthly Indicator Rept, Nov 1996 ML20137M9261996-10-31031 October 1996 Monthly Indicator Rept ML20137N1941996-10-17017 October 1996 Monthly Indicator Rept, Sept 1996 ML20137N2051996-06-14014 June 1996 Monthly Indicator Rept, May 1996 ML20137N2111996-05-14014 May 1996 Monthly Indicator Rept, Apr 1996 ML20137N2201996-04-17017 April 1996 Monthly Indicator Rept, Mar 1996 ML17354A2841996-04-0707 April 1996 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 941114-960407. ML17353A6341996-03-31031 March 1996 Rev 0 to JPN-PTN-SEFJ-96-015, Control Rod Operability Evaluation as Result of Incomplete Rod Insertion at Other Westinghouse Plants. ML20137N2381996-03-19019 March 1996 Monthly Indicator Rept, Feb 1996 ML20137N3661995-12-18018 December 1995 Monthly Performance Monitoring Mgt Info Rept, Nov 1995 ML20137N4311995-10-18018 October 1995 Monthly Perfromance Monitoring Mgt Info Rept, Sept 1995 ML20137M7111995-07-25025 July 1995 Quality Assurance Audit Rept QAS-ENV-95-1, Radiological Environ Monitoring Program & Site Nonradiological Environ Protection Plans Functional Area Audit, 950525-0714 ML17353A2561995-07-14014 July 1995 Service Water Operational Performance Insp,Self Assessment, Final Rept, for Turkey Point Nuclear Plant ML17353A2641995-06-27027 June 1995 Pyrolysis Gas Chromatography Analysis of 7 Thermo-Lag Fire Barrier Samples. ML17352B0441995-02-20020 February 1995 Engineering Evaluation of Turkey Point Units 3 & 4 Containment Structures. ML17352A8841994-10-28028 October 1994 Plant,Simulator Certification Update 1. ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML17353A9201993-04-30030 April 1993 Plant Specific Seismic Adequacy Evaluation of Turkey Point, Units 3 & 4 to Resolve USI A-46 & GL 87-02. W/O App a ML17349A7961993-04-12012 April 1993 Nonproprietary Addendum 1 to Thimble Reduction Study for Turkey Point Units 3 & 4. ML17349A7951993-04-12012 April 1993 Nonproprietary Thimble Reduction Study for Turkey Point Units 3 & 4. ML17349A4721992-11-0505 November 1992 Fifteenth Year Tendon Surveillance Supplemental Rept. ML17349A4061992-09-23023 September 1992 Rev 0 to JPN-PTN-SEMJ-92-034, Safety Evaluation for Interim Fire Protection Sys Configuration to Support Unit 4 Startup. ML17349A3501992-08-17017 August 1992 Engineering Evaluation for Verification of PSB-1 Computer Model for Setting of Undervoltage Relays. ML17348A8011991-01-0202 January 1991 Simulator Initial Certification, Vol 1 ML17348A8021991-01-0202 January 1991 Simulator Initial Certification, Vol II ML17348B0071990-12-31031 December 1990 Probabilistic Seismic Hazard Evaluation & Uniform Hazard Spectra for St Lucie & Turkey Point Nuclear Power Plant Sites ML17348A2811990-05-31031 May 1990 Suppl 0,Rev 1 to Emergency Power Sys Enhancement Project Design Rept. ML17348A2821990-05-31031 May 1990 Suppl 2,Rev 1 to Emergency Power Sys Enhancement Rept, Safety Analysis. ML17348A2831990-05-31031 May 1990 Rev 1 to Emergency Power Sys Enhancement Project Response to NRC Request for Addl Info. ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML17347B0861989-03-31031 March 1989 Rev 0 to Turkey Point Units 3 & 4 Emergency Power Sys Enhancement Rept,Suppl 1-Testing. ML17345A6631989-03-21021 March 1989 Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects Ref NRC Bulletin 88-008. ML17345A4201988-08-31031 August 1988 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation, Ltr Rept ML17345A3151988-08-15015 August 1988 Independent Mgt Appraisal Re Corrective Action Programs & Investment in Supporting Resources,Recommending Extension of Effective Performance to Include Corporate Level & Site Level Measures ML17347A7851988-06-30030 June 1988 Emergency Power Sys Enhancement Rept. ML17347A7971988-06-16016 June 1988 Seismic Hazard Data Prepared for Resolution of USI A-46. ML17347A7981988-06-16016 June 1988 Radiological Data Prepared for Resolution of USI A-46. ML17342B2901988-04-18018 April 1988 Independent Mgt Appraisal. ML17347A6531987-12-11011 December 1987 Outside Containment Limitorque Wire Rept. ML17347A4521987-04-27027 April 1987 Rept on Instrumentation Port Column Assembly Leakage,Turkey Point Unit 4. ML20213H1731986-08-31031 August 1986 Economic Benefits of Nuclear Phase Out ML20155A1831986-02-28028 February 1986 Human Factors Engineering Guidance Manual,Turkey Point Nuclear Power Plant Units 3 & 4 ML17346B0151985-04-30030 April 1985 Rev 1 to Turkey Point Plant Unit 3 Engineering Evaluation of Instrumentation Sys for Reg Guide 1.97,Rev 3. ML17346B0161985-04-30030 April 1985 Rev 1 to Turkey Point Plant Unit 4 Engineering Evaluation of Instrumentation Sys for Reg Guide 1.97,Rev 3. ML20111B1751984-11-30030 November 1984 Technical Rept on Evaluation of Use of Arching Theory in Analysis of Masonry Walls Under Differential Pressure - Turkey Point Plant Units 3 & 4 ML20090H4561984-07-23023 July 1984 Rev 1 to Spent Fuel Storage Facility Mod Sar ML17346A4041984-05-31031 May 1984 Rev 0 to Auxiliary Power Upgrade Summary & Design Evaluation. W/10 Oversize Figures.Aperture Cards Available in PDR 1998-06-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML17355A4471999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Turkey Point,Units 3 & 4.With 991008 Ltr ML17355A4121999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Turkey Point,Units 3 & 4.With 990909 Ltr ML17355A3981999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Turkey Point,Units 3 & 4.With 990809 Ltr ML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17355A3841999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Turkey Point,Units 3 & 4.With 990713 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17355A3611999-06-30030 June 1999 Refueling Outage ISI Rept. ML17355A3511999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Turkey Point,Units 3 & 4.With 990609 Ltr ML17355A3331999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Turkey Point,Units 3 & 4.With 990511 Ltr ML20217B9871999-04-0808 April 1999 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408 ML17355A2881999-04-0505 April 1999 COLR for Turkey Point Unit 4 Cycle 18. ML17355A2911999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Turkey Point,Units 3 & 4.With 990414 Ltr ML17355A2551999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Turkey Point Nuclear Power Plant,Units 3 & 4.With 990315 Ltr ML17355A2261999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Turkey Point,Units 3 & 4.With 990211 Ltr ML17355A2201999-01-20020 January 1999 Refueling Outage ISI Rept. ML17355A1911998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Turkey Point,Units 3 & 4.With 990112 Ltr ML18008A0461998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Turkey Point,Units 3 & 4.With 981209 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1891998-11-0909 November 1998 Simulatory Certification Update 2. ML17354B1901998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Turkey Point,Units 3 & 4.With 981112 Ltr ML17354B1591998-10-23023 October 1998 COLR for Turkey Point Unit 3 Cycle 17. ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B1311998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Turkey Point Unit 3 & 4.With 981012 Ltr ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML17354B0981998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Turkey Points,Units 3 & 4.With 980915 Ltr ML17354B0771998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Turkey Point,Units 3 & 4.W/980810 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354B0241998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Turkey Point,Units 3 & 4.W/980709 Ltr ML17354B0171998-06-29029 June 1998 Rev 1 to PTN-FPER-97-013, Evaluation of Turbine Lube Oil Fire. ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML17354A9711998-05-31031 May 1998 Monthly Operating Repts for Turkey Point,Units 3 & 4. W/980611 Ltr ML17354A9231998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Turkey Point,Units 3 & 4.W/980511 Ltr ML17354A8821998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Turkey Point,Units 3 & 4.W/980409 Ltr ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354B0001998-03-18018 March 1998 Florida Power & Light Topical Quality Asurance Rept, Dtd June 1998 ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A8311998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Turkey Point,Units 3 & 4.W/980311 Ltr ML17354A7871998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Turkey Point,Units 3 & 4.W/980209 Ltr ML17354A7581997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Turkey Point,Unit 3 & 4.W/980112 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A7381997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Turkey Point,Units 3 & 4.W/971215 Ltr ML17354A7211997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Turkey Point,Units 3 & 4.W/971114 Ltr ML17354A7491997-10-13013 October 1997 SG Insp Rept. ML17354A8851997-10-13013 October 1997 FPL Units 3 & 4 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 960408-971013. ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6791997-10-0606 October 1997 COLR Unit 4 Cycle 17, for Turkey Point ML17354A6811997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Turkey Point,Units 3 & 4.W/971009 Ltr 1999-09-30
[Table view] |
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, AN n IEBL j 1970,s yNISCOPE INVESTIGATION OF THE TURKEY P d p }.g:4, -
UNIT NO. 3 CONTAINMENT MAT ffi27,
%/ (3 INTRODUCTION s
In accordance with an agreement for consulting services between the undersigned and Bechtel Corporation, Soniscope tests have been performed on Section 6-l' of the containment mat of the No. 3 Unit of the' Turkey Point Plant, located near Homestead, Florida. All testing was accomplished on Monday, ,
May 26, ' 196 9.
In a previous report to Becntel, dated April 30, 1968, describing the '
original testing of the containment mat of the No. 3 Unit of this plant, the test equipment and procedure used in performing these tests were described in detail.
The report also provided information concerning the extent of, and limitations of, usefulness of this testing approach, and described procedures for analysing the
' data collected during such tests. For such information, the reader is referred to
'that report.
The same notations were employed for identifying test positions during the testing described herein as were used to identify test positions during the original tests of this unit. Testing was limited to horizontal tests from the wall of the reactor pit liner to the outer wall of the containment mat. A total of 180 tests are described herein.
TEST RESULTS The results of all tests performed are tabulated in Table I and shown graphically in Figures 1 and 2.
Figure 1 shows the results of horizontal measurements from the wall of the reactor pit to the outer wall of the containment mat in which the transmitting transducer was moved successively in two degree increments around the outer wall of the mat. During these tests the receiver, held against the inner wall of the .
reactor pit, occupied only three different positions. Tests were made at elevations 3 ft. , 4 ft. , 5 ft. , 7 ft. , and 9 ft. A successful test was accomplished at each position occupied.
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- Reference to th'e original report will show that in the earlier tests on the section at elevation 3 ft.the' re w~ere two positions (61-3 and 61-12) at which no signal was received and fifteen positions at which the received signal was too weak to be interpreted. In the tests made on May 26, 1969 all received signals were of adequate strength and the average velocity mcasured throughout the eleva-
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tion was slightly greater than the average of those velocities measured in April, 1968.
In the original tests at elevation 4 ft. , no signal was received at test position 61-1 and at position 61-22 the received signal was too weak to be inter-preted . Signals of adequate strength were received at all positions during the more
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recent tests. Velocities measured at positions from 61-1 through 61-21 were the same or a little higher than those me.asured in April,1968. A larger than average difference between adjacent readings ' occurred as the transmitting transducer was moved from position 61-22 to position 61-23, and the velocities measured from position 61-23 through 61-29 were slightly lower than those measured in 1968.
It should be noted that the receiving transducer, held against the wall of the re-actor pit, was moved 30 degrees around the wall between tests involving position 61-22 and position 61-23, and remained at the latter position through the remainder of the tests on the section. It is believed that the reduction in velocities noted from
, position 61-23 through position 61-29 at elevation 4 ft.may be attributed to a slight lessening of bond between the reactor pit liner and the containment mat at position 61-30 on the reactor pit liner. Some substantiation of this belief will be pointed out on Figure 2.
In the original tests at elevation 5 ft. , unreadably weak signals were received at test positions 61-22 through 61-29. Adequate signals were received at all of these positions during the more recent tests. Velocities measured through the section were about the same or slighgly higher at this elevation when measured in May,1969 than when measured in April,1968.
At the 7 ft, elevation, adequate signals were received and high velocities measured at all positions tested in the most recent tests, as was the case in the n
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original tests at this eleveation. No unusual variations in velocity were found.
In the original tests at elevation 9 ft. , no signal was received at test positions 61-2, 61-5, 61-8, 61-14, 61-15, 61-18, 61-19, 61-20, 61-21, and 61-22, and unreadably weak signals were received at eight other inst positions.
Successful tests were made at only twelve of the thirty test positions , in the recently completed tests, readings were completed at all thirty positions. Signals observed in these were, however, weakor than those observed in tests at the other four elevations, and the average velocity measured in the thirty tests, 13,380 ft, per second, was somewhat lower than that measured at the other elevations (13,630 ft. per second at elevation 3 ft. ,13,620 ft per second at 4 ft. ,
13,760 ft. per second at 5 ft. , and 13,850 ft, per second at 7 ft.) .
In the original report, the difficulties associated with achieving adequate test results at the 9 ft. elevation were attributed to the presence in the si,st of a shear key into which the wall would subsequently be erected. It was noted that the shear key was approximately 4 ft, deep throughout most of the section, begin-ning at about position 61-7, and was of sufficient depth to intercept the test signal. With the erection of the wall, the shear key has been 1111ed with concrete and a continuous path should be available for the test sig?al. This construction would result, however,in two vertical construction joints which would intercept the signal path, each of which would be expected to result in some attenuation of the signal. It may be noted that the velocities measured through test position 61-6 are of approximately the same level as those measured at other elevations. At test positions beyond 61-6 the velocity began to fall of f and remained lower throughout the remainder of the section. It is believed that this decrease is attribut-able to the presence of the two vertical construction joints in the signal path. The uniformity of tile velocity measured over a large porition of the slab at the 9 ft.
elevation after the general decrease in velocity had occurred suggests adequate uniformity of the concrete.
Figure 2 shows the results of supplemental horizontal tests in which the transmitting transducer was held at only two positions on the outer wall of the mat and the receiving transducer w:s wed through a succession of ten degree intervals L.
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o against the liner to the reactor pit wall. Successful tests were accomplished at all locations. In general, velocities were about the same or a~ little higher than those measured in April,1968 and variability of the readings was about the same. One difference occurred at elevation 4 ft. Involving test positions 61-20, 61-25, and 61-30. In the recent tests, the velocities measured at these positions were somewhat lower than those measured earlier, and increased as the transducer was moved away from position 61-30, reaching a high level of velocity by the time the transducer reached position 61-15. Attention is redirected to the horizontal tests at elevation 4 ft. in which all tests made to the outer wall (positions 61-23 through 61-29) for which the receiving transducer was held at position 61-30 against the reactor pit liner showed lower readings than average for that elevation. It is believed that these results substantiate the conclusion that there has been some lessening of the intimacy of bond between the reactor liner and the mat at and near position 61-30 at elevation 4 ft.
CONCLUSIONS On the basis of the testing described above and of the test results enumerated in this report, together with a comparison of the results reported under date of April 30, 1968, the following conclusions have been drawn:
(1) The degree of uniformity of the concrete throughout Section 6-1 of the containment mat is materially greater than it was at the time of the initial tests.
(2) No significant evidence of lack of uniformity, as evidenced by inability to obtain a test signal, an unreadsbly weak test signal, or abnor'.rtal variations in velocities, was discovered during these tests.
b i E. A. Whitehurst, Consulting Engineer Knoxville, Tennessee May 29,1969 L
TABLE I
- PULSE VELOCITIES MEASURED HORIZONTALLY THROUGH CONTAINMENT SLAB Transducer Positions Wall of Outer face Pulse Velocity (ft../sec.)
reactor of Path length pit slab (ft.) Elev. 3 ft. Elev. 4 ft. Elev. 5 ft. Elev. 7 ft. Elev. 9 ft.
56-30 56-30 55.0 13,600 13,630 13,850 13,990 13,550 61- 1 2
55.1 55.1 13.550 13,620 13,620 13,550 13,840 13,980 13,710 h
13,790 13,930 13,880 3 55.1 13,660 13,590 13,720 13,970 13,600 4 55.2 13,580 13,560 13,680 14,050 13,730 5 55.2 13,630 13,530 13,600 13,990 13,660 6 55.3 13,500 13,550 13,626 14,050 13,710 4'
7 55.4 13,550 13,530 13,650 14,060 13,600 8 55.5 13,590 13,520 13,600 13,980 13,600 61-15 61- 9 54.8 13,720 13,770 13,860 13,730 13,450 61-10 54.7 13,660 13,760 13,760 13,740 13,420 11 54.6 13,370 13,700 13,740 13,750 13,250 12 54.6 13,380 13,770 13,790 13,750 13,320 13 54.6 13,370 13,810 13,860 13,680 13,270 14 54.5 13,560 13,760 13,800 13,710 13,120 15 54.5 13,640 13,870 13,890 13,730 13,210 16 54.5 13,570 13,850 13,940 13,810 13,180 17 54.6 13,680 13,820 13,980 13,880 13,330 18 54.6 13,450 13,860 14,000 13,790 13,240 m
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TABLE 1 (Continued) .
PULSE VELOCITIES MEASURED HORIZONTALLY THROUGH CONTAINMENT SIAB Transducer Positions Wall of Outer face Pulse Velocity (ft./sec.)
reactor of Path length pit slab (ft .) Elev. 3 ft. Elev. 4 ft. Elev. 5 ft. Elev. 7 ft. Elev. 9 ft.
61-15 61-19 54.6 13,650 13,930 13,960 13,750 13,200 20 54.7 13,740 13,990 13,990 13,730 13,210 h 21 54.8 13,730 13,890 13,940 13,700 13,200 22 54.8 13,580 13,800 13,870 13,750 13,240 61-30 61-23 54.4 13,550 13,330 13,630 13,720 13,270 24 54.3 13,610 13,210 13,590 13,800 13,150 .
25 54.2 13,670 13,220 13,600 13,830 13,090 h
26 $4.2 13,720 13,270 13,720 13,860 13,160 -
27 54.1 13,700 13,260 13,710 13,820 13,120 28 54.1 13,710 13,290 13,750 13,890 13,040 29 54.0 13,780 13,240 13,830 13,900 13,120 61-25 61-23 54.2 13,810 13,450 13,700 13,950 13,350 61-20 54.4 13,820 13,530 13,620 13,900 13,520 61-15 54.9 13,850 13,900 13,780 14,060 13,690 61-15 61- 8 54.9 13,740 13,830 13,780 13,710 13,540 61-10 54.7 13,620 13,590 13,340 13,730 13,390 61- 5 54.9 13,730 13,610 13,590 14,090 13,380 U-