ML20127M639
| ML20127M639 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 11/16/1992 |
| From: | PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20127M631 | List: |
| References | |
| NUDOCS 9211300351 | |
| Download: ML20127M639 (56) | |
Text
Trojan Nucicar Plant I)ocument Control Desk Docket $0 344 #* #'
License NPF.! Appendix A Page Al cr Al REACTOR COOLANT SYSTEM SURVEILLANCE REOUTRFMENTS (Continued) 4.4.5.3 InsDection Frecuencies - The above required inservice inspections of steam generator tubes shall be perf ormed at the following frecuencies:
- t. The first inservice inspection shall be perfortned af ter 6 Ef fective Full Power Months but within 24 calendar Tonths of initial criticality. Subseauant inservice inspections shall be perfnrmied at intervals of not less than 12 nor more than 24 calendar months af ter the previous inspection. If two consecu-tive inspections folloutng service under AVT conditions, not including the preservice inspection, result in all inspection results f alling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued dnd no additional degradation has occurred, the inspection interval rey be extended to a maximum of once per- 40 months,
- b. If the results of the inservice inspection of a steam gen-erator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category C-3, the inspection f requency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specifica-tion 4.4.5.3.a; the interval may then be extended to a maximum of once per 40 months.
- c. Additional, unscheduled inservice inspections shall be performed on ecch steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:
- 1. Prdmary-to-secondary tube leaks (not including leaks originating f rom tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2.
- 2. A seismic occurrence greater than the Operating Basis Earthquake.
- 3. A loss-of-coolant accident requiring actuation of the engineered safeguards, t
4 A main steam line or feedwater line br*dk.
l TROJAN-UNIT 1 3/4 4-8 Amendment No. 67. 133 !
August 7, 1987 j 9211300351 DR 921126 1 ADOCK 05000344 von
i Trojan Nuclear l'lant Document Control Desk l I-Docket 50 341 November 26,1992 1.ieense NI'F.1 Appendix 11 l'ap Blof111 i REACTOR COOLANT SYSTEN Sl'RVETLLANCE REQUIREMENTS (Continued) i
! 4.4.5.3 Inspection Frecuencies - The above required inservice inspections
] of steam generator tubes shall be performed at the following frequencies! '
s
) a. The first inservice inspection shall be performeri after 6 i Effective Full Power Months but within 24 calendar months of 1 initial criticality. Subsequent inservice inspections shall be i performed at intervals of not less than 12 nor more than 24 j calendar months after the previous inspection. If two consecu-tive inspections following service under AVT conditions, not
- including the preservice inspection, result in all inspection j results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation
-! has not continued and no additional degradation has occurred.
the inspection interval may be extended to a maximum of once j per 40 months.
- b. If the results of the inservice inspection of a steam gen-
[ erator conducted in accordance with Table 4.4-2 at 40 month d
intervals fall in Category C-3, the inspection frequency j shall be increased to at least once per 20 months. The increase in inspection fr(quency shall apply until the
'! subsequent inspectionc satisfy the criteria of Specifica-I tion 4.4.5.3.a; the interval may then be extended to a maximum of once per 40 months.
l c. Additional, unscheduled inservice inspections thall be performed
! on each steam generator in accordance with the first sample 4
inspection specif hd in Table 4.4-2 during the shutdown subsequent j to any of the following conditions: '
l 1. Primary-to-secondary tube leaks (not including leaks originating from tube-to-tube shee ) in excess of the limits of Specification 3.4.6. *
- 2. A :elsmic occurrence greater than the Operating Basis l Earthquake.
j 3. A loss-of-coolant accident requiring actuation of the
. engineered safeguards. ,
- 4. A main steam line or feedwater line break.
b For the plant shutdown following identification of primary-to-secondary i leakage on November 9, 1992, the inspection. requirements of this
! 7 specification may be satisfied by the inservice inspection scheduN d
- ,, for the fourteenth refueling outage in accordance with the requirements i i of Specification 4.4.5.3.b.
T IT 1 8 -
Amendment No. 57, 733, 188
l I Trojan Nuclear Plant Document Control Desk
, . Docket 50 344 November 26,1992
, License NPF.1 Attachment 11 1 Page 1 of 17 i
! TECllNICAL EVALUATION OF Tile NOVE3111ER 9.1992 STEAM j GENERATOR tulle LEAK AT Tile TROJAN NUCLEAR PLANT
)
j 1.
SUMMARY
- On November 9,1992, the Trojan Nuclear Plant (TNP) was shut down due to a steam generator j tube leak that exceeded the primary-to secondary leakage limits of Technical Specification j 3.4.6.2, " Reactor Coolant System Operational Leakage." The tube leak in the "I1" Steam Gen-j erator was rapidly detected by radiation monitors installed to detect nitrogen-16 in the secondary j system. This allowed plant operators to promptly imtlate a plant shutdown and isolate the af-j fected steam generator. Operators minimized the subsequent primary-to secondary it kage by l equalizing the steam generator pressure with the pressure in the reactor coolant system. The ini-
! tial leakage rate was approximately 100 gallons per day. During the plant shotoown, however, the leakage rate increased beyond the technical specification limit of 130 gal!ons per day
! (Technical Specification 3.4.6.2," Reactor Coolant System Operational Leakage"). The radio-j active releas. from the plant was limited to less than 0.1 percent of the releas: permitted by the 5 technical specifications (i.e., approximately 5x104 mrem at the boundary of the unrestricted
- - area). A Licensee Event Repon, as required by 10 CFR $0.73, " Licensee Event Report System",
! will provide more detailed information on the plant shutdown.
4 i
The leak was caused by the failure to stress relieve the wcids properly in a tube support plate l
j sleeve which was installed during the 1991 refueling outage, The inadequate stress relief was
- caused by failure to position properly the stress relief heater probe that was inserted into the ,
j to perform the stress relief process.
l A program was developed to evaluate and confirm that the other tube support plate sleeves it'-
i stalled in the TNP steam generators were properly stress relieved. The program included eddy l current testing of the remaining sleeves to detect changes in the tube material associated with the
! stress relief process. The program also included a review of records indicating the heater pneu-l matic sensing device pressure and heater coil temperatures recorded during installation of the
i i Eddy current inspections of the inservice tubes adjacent to the leaking tube were also performed i to ensure that these tubes were not damaged by the tube leak or during the plant shutdown. No j defects were found. The leaking tube was stabilized in the defect area to prevent potential dam-age to adjacent tubes and removeu from service by plugging.
! In summary, the cause of this tube leak has been identified as a sleeve weld which was improp-erly stress relieved. Appropriate corrective actions have beca taken to stabilize and plug the
, leaking tube, in addition the integrity of other steam generator tube sleeves has been demon-strated through engineering evalurition, testing and an analysis performed to demonstrate that the
, sleeves remaining in service have been adequately stress relieved. As such, the integrity of the j steam generators has been demonstrated and the plant is ready to return to power operation.
I 4
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. Trojan Nuclear Plant Document Control Desk i a Docket 50-344 November 26,1992 1.icense NPF 1 Attachment 11 Page 2 of 17
- 2. HACKGROUND Steam generator tube sleeves are one methed used in the industry to repali steam generator tubes when inspections identify degradation in excess of the repair limits established in technical specifications. The sleeves used at TNP are made of thermally treated Alloy 690 which provides enhanced corrosion resistance compared to the original tubing. The tube support plate sleeves were designed by the B&W Nuclear Service Company. The sleeve design is described in Topi-cal Report BAW 2094PA - Revision 1," Recirculating Steam Generators Kinetic Sleeve Qualifi.
cation for 7/8 inch OD Tubes", which has been revicwed and approved by the NRC. On May 25,1990 the Nuclear Regulatory Commission (NRC) issued Amendment 160 to the Trojan Technical Specifications authorizing the use of this sleeving process.
The installation of a sleeve in a steam generator tube is accomplished by tooling attachments
- mounted on a steam generator manipulator (ROGER *'. The installation process includes the four major steps described below'.
The first step is cleaning of the parent tube in the area where there will be kinetic welds. Clean-ing is performed on the inside diameter of the parent tube with an abrasive tungsten carbide hone to remove the oxide layer and any loose material in the kinetic weld region. The hone is rotated and oscillated in the tube, centering the oscillation on the weld region. Removal of the clean-ing debris is achieved through a continuous vacuum process during cleaning.
The second step involves the insertion and welding of the sleeve. The sleeve is inserted into the parent tube using an actuator tool mounted onto the ROGER
- manipulator. ROGER
- posi-tions the actuator under the proper tube and then raises the actuator until it is in contact with the tube end. The actuator tool uses two gripping devices; one movable, one stationary. By se-quencing the actions of these grippers, the sleeve is stepped into the tube until a hardstop on the sleeve assembly contacts the actuator and indicates the sleeve is in the proper position. Contact is sensed by a proximity switch on the actuator.
Detonation of the kinetic weld device is performed simultaneously for both tube support plate sleeve welds . After detonation, the actuator sequences the remains of the explosive essembly out of the tube and delivers it to the manway for disposal.
The kinctic welding process causes an expansion of the sleeve and tube diameter in the weld area. This expansion results in residual stresses in the tubing material which may make the ma-Di'ferences between the process described here, which was used for the installation of sleeves at TNP in the 1991 Refueling Outage, and to that described in Topical Report i BAW-2094PA, Rev 1," Recirculating Steam Generator Kinetic Sleeve Qualification for 7/8 inch OD Tubes" are discussed in . Appendix A to this repon.
Trojan Nuclear Piant Document Cor, trol Desk Docket 30-344 November 26,1992 License NPF l Attachment 11 Page 3 of 17 terialt susceptible to damage by a corrosion process known as stress corrosion cracking. There-fore, after completion of the kinetic welding process, any residual stresses are relitved by heating the affected areas to a temperature of 1275'F to 1525"F for a minimum of 5 minutes.
This stress relief process is the third major step. Stress reliefis accomplished by positioning a heater into this region and operating the heater under strict controlling guidelines. The tube sup-port plate sleeve heater is designed to heat both welds simultaneously. Six thennocouples are used to measure the heater te.uperature, three at each location. Two of the three thennocouples at each locatiori are used to control power to the heater and thus the stress relief temperature.
Through laboratory testing the correlation beiween heater temperature and parent tube tempera-ture has been determined. This infonnation is used by a controlling system which monitors the ramp up and steady state temperature of the heater and conelates this information into parent tube temperature. The controlling system monitoin the heater temperature, times the period when tube temperature has reached the appropriate temperature range and shuts the process off when the stress reliefis complete or when anomalies are detected.
The fourth and last step involves the post stress relief eddy current inspection. This inspection is used to detect defects in the pressure boundary region of the tube and sleeve, and also verifies that the installed sleeve is properly positioned with respect to the tube support plate. _ _1 j Figure 1 provides an illustration of a typical TNP tube support plate sleeve installation after kinetic welding has taken place. / .
This figure shows the approximate location of the heater probe , _Jt ,
[d coils in the sleeve, properly positioned for the stress relieving ., p ,
process and indicates the approximate location of the magnetic ._
permeability line (perm line). This line represents the boundary ,,, j , _ . ,
~
of the heat affected zone. Metallurgical evaluations of welded specimens stress relieved in this manner indicate that the resid- ,
y hy ual stresses are reduced to a very low value. These evaluations lic l also indicate that there are no detrimental effects on the material ,,
j microstructure or mechameal properties. _,, r l
The following is a discussion of'he number of sleeves that were - b__
installed in the TNP steam generators before the Novembcr 9, 1992 tdbc leak. During the 1990 refueling outage two tabes in ( y";-
the "C " Steam Generator (R15 Cl3 and R4-C85) were repaired !
by sleeving. One tube sheet sleeve and one tube support plate sleeve were installed in the hot leg side of each tube These four q sleeves were stress relieved using a heater probe which used an '
electrical continuity hardstop switch. This heater probe design ensures proper probe positioning in contact with the bottom edge Figure 1 TSP Sleev of the sleeve. In the 1991 Refueling Outage,1017 tubes were
Trojan Nuclear Plant Document Control Desk
. . Docket 50 344 November 26,1992 License NPF 1 Attachment 11 Page 4 of 17 repaiied with sleeves. These sleeves were installed at the tube support plater A. , result of the 1990 and 1991 repairs, a total of 1098 tube sleeves have been installed in 1019 tubes in the three of the four steam generators. In 1991 one tube (R15 Cl3) containing two sleeves installed in 1990 (one at the tube sheet) was plugged leaving 1096 sleeves in service prior to the event on November 9,1992.
- 3. CAUSE OF tulle LEAK The location of the leakage was detennined to be from a single tube (row 25, column 17, hereaf-ter referred to as R25 C17) in the "B" Steam Generator at the sleeve which was installed in this tube in 1991 spanning the first tube support plate.
The sleeve area was examined using a rotating cross wound coil eddy cuncat probe. This ex-amination identified multiple indicat;ons in the parent tube material in the area of the lower sleeve to tube kinetic weld. The indications were at proximately 4 inches from the bottom of the first tube support plate and spanned a region estimated to exceed 180 degrees of the tube circum-ference.
The came of the leak was detennined to be the failure to properly stress relieve the tube after the sleeve was kinetically welded. This conclusion is based upon the following evidence:
- a. Eddy current testing of the leaking tube using a bobbin coil probe showed al-tered magnetic penneability in two regions of the parent tube several inches below the tube sleeve location. These eddy current indications, or "signatu-res", have been verified by testing performed by B&W Nuclear Service Com-pany to be consistent with the heating of the parent tube material by the two coils of the heater probe used to perfonn stress relief of sleeve-to tube kinetic welds. Past testing shows that the magnetic permeability of Alloy 600 tube material changes between 950*F and 1050"F. This penneability change can be readily detected by bobbin coil cddy current inspection. This method has pre-viously been used by B&W Nuclear Service Company to verify correct heater position when stress relieving the U-bends in steam generator tubes and has proved very reliable. These indications show that the stress relief heating was applied to the parent tube below the sleeve.
- b. Further testing and analysis of eddy current data demonstrated that a similar eddy current " signature" associated with the stress relieving process could also be detected in the tube material behind a sleeve using a bobbin coil eddy cur-rent examination. The methodology for detecting the permeability changes in the area of a tube support plate sleeve is discussed in more detailin the Corree-tive Actions section of this report. Eddy c: mnt test data for tube R25-C17 indicated that this eddy current signature was not present in the sleeved area but, as discussed above, was detectable in the parent tube materialjust below the sleeve. Based on this information,it was concluded that this tube did not undergo the proper stress relief process after kinetic welding.
Trojan Nuclear Plant Document Control Desk
. . Docket 50-344 November 26.1992 l License NPF-1 Attachment 11 I
Page 5 of 17 !
- c. Characterization of the Daw indications in the lower kinetic weld are consis-tent with conosion test results obtained during the qualification of the kinetic welding process. These tests showed that accelcrated corrosion occuned at this location if the required stress relieving process was not perfonned.
1 The leak was caused by accelerated conosion caused from the failure to stress relieve the sleeve welds for tube R25 Cl7, This occurred because the remotely operated heater probe intended to ,
perform tha post-weld stress relief of the sleeve installed in tube R25-C17 was not positioned within the sleeve during the stress relief process.
l c
- 4. CORRECTIVE ACTIONS i 4.1. ACTIONS FOR TUHE R25-C17 The leaking tube has been fitted with a stabilizer rod extending from the tube sheet through the upper kinetic weld of the sleeve at the first tube support plate and extendbg approximately 12 inches above the sleeve. The rod will prevent any potential damage to adjacent tubes in the event that propagation of existing Daws due to.conosion or now induced vibration lead to a complete failure of the parent tube at the welded joints. The tube was then removed from ser- ;
vice by installation of tube plugs. In addition to the examination of the leaking tube, bobbin coil eddy current probe inspections of the inservice tubes adjacent to the leaking tube were per-formed to ensure these tubes were not damaged by the tube leak or during the plant shutdown.
No defects were found.
A review oflogs recorded during the installation of the sleeve in tube R25-C17 revealed that
- upon removal of the heater probe from tube R25-C17, the probe was observed to be bent and -
coald not be used in further tube stress telief operations. Seven additional tube sleeves in the -
"B" Steam Generator which were stress relieved using the same heater probe as used on tube R25-C17 were examined using a rotating cross-wound coil probe. These examinations revealed no detectable indications.
4.2. - CONFIRMATION OF PROPER STRESS RELIEF FOR OTilER TUBES j 4.2.1. tinstallation Process
-The tube support plate sleeve heater probe contains two heater coils, positioned to allow heating _ ,
, of both sleeve weld areas simultaneously. Six thermocouples, three at each coil location, are l contained in the heater probe. The output from two of the three thermocouples at each beation are used to control the stress relief process. The heater probe is rigid and is connected to the power t.ource through Hexible tubing carrying the power leads, thermocouple leads and cooling air hose. Figure 2 illustrates a typical heater probe used for the stress relieving processing, in
Trojan Nuclear Plant Document Control Desk Docket 50-344 November 26,1992 License NPF-1 Attachment 11 Page 6 of 17 preparation for the stress relieving process, the heater probe is inserted into the parent tube by a remotely operated positioning system. The heater is inserted into the tube until the heater seats against the bottom cdge of the sleeve. Once the heater probe is properly inserted, the operator initiates the heater cycle completing the stress relief process.
The methodology and tooling used to perform the strees relief process pro-vides multiple methods to assure proper heater probe positioning within the sleeve. The primary means of positioning the heater probe is by the physical p,]
design of the heater probe base which provides a mechanical interface or g "hard stop" against the bottom edge of the sleeve v, hen the probe is properly inserted.
(( t Proper heater probe position against the sleeve is contirmed by operator -
monitoring of a " pneumatic hard stop" indication to ensure that the heater has , , , ,
hard stopped , gainst the sleeve rather than some other type of restriction in the tube. This indication of proper probe positioning is obtained by moni. g toring the air pressure tap in the base of the heater probe during the insertion /
of the heater into the sleue. Changes in air pressure occur as the heater probe is inserted into a sleeve. #
An example of air pressure response is shown in Figure 3 as a function of the -
distance between the physical heater hard stop ar'd the bottom edge of the tube sleeve. This figure shows that there is a relatively small initial pressure l4.;.-.
/
peak (Point A) as the heater first enters the sleeve end. The pressure then h drops and remains low until the upper coil reaches the expanded area of the f" lower kinetic weld (Point B). The air pressure then rises rapidly until the i upper cooling air port passes the sleeve end (Point C). The air pressure re- s tr.ains high as the heater passes through the next six inches of the sleeve, The figure shows small changes in pressure in this region of the curve as ,
the upper heater coil (Points D) and then the upper cooling air port (Point Figure 2 Heator E) enter the the unexpanded area of the sleeve between the two weld areas. Probo The air pressure then begins to fall rapidly as the lower heater coil enters -
the sleeve end Point F) and continues to fall as both
E Trojan Nuclear Plant Document Control Desk
. . Docket 30 344 November 26,1992 License NPF.1 Attachment 11 Page 7 Of 17 d
Typical Hardstop Pressure Distribution ja _ _ ._
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0 0 2 4 6 6 10 12 Distance from Heater Hardstop to Bottom of Sleeve (in)
HEATlA ENTEk!NG SLEEVE END
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t'PPER C0ll ENTERS thWER EXPANDED AREA
[ Mb M1 LA- ' '2 wGHEI1][33 B (TPER COOLING PORT ENTERS SLEEVEIM) l _ _
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l @ $ E _3AfiT l_ __;5 M [UIMIO b,_ b I SLEEVECONTACTb EDGEOFHARDSTOP iGEklT5 M W78 Q []@BJ HEATER FTLLYINSERTED Figure 3 Hardstop Pressure Distribution
l Trojan Nuclear Plant Document Control Desk
. . Docket 50-344 November 26, IM2
- License NPF-1 Attachment 11 Page 8 of 17 heater coils reach the expanded areas of the kinetic welds (Point G). After the lower heater coil l is fully inserted into the sleeve (Point H), the pressure begins to rise again until the heater probe j hard stop approaches the bottom edge of the sleeve (Point 1). A Gnal pressure drop occurs as the i heater is fully seated with the hard stop butted against the sleeve (Point J).
2 i
Figure 4 shows the details of the pressure changes that occur during the Gnal one inch of heater travel as the heater probe hard stop is seated against the sleeve. The labeled points are the air
- pressures that occur as the lower siceve edge passes the corr
- sponding points on the heater hard stop detail. The Agure shows two pressures at the Onal heater probe position (Points J1 and J2).
J1 represents the pressure prior to the Gnal "prelotling" stroke by the probe positioning system.
- This final stroke increases the pressure holding the heater probe against the sleeve end and re-
- sults in an additional pressure drop (Point J2).
j
~
An additional process control of proper probe positioning is provided by computer monitoring of thermocouples in the heater probe. Due to the geometry of the sleeve and the connguration of the heater coils, mispositioning of the pmbe within a sleeve can cause t'mperatures different
- than expected between the upper and lower heater coils. If these temperature differences exceed pre-established limits the process is automatically terminated.
j 4.2.2. Inspections a
a The tube sleeves in tne "B", "C" and "D" Steam Generators were examined using a bobbin coil eddy current probe (there are currently no tube sleeves installed in the "A" Steam Generator).
This examination was performed to detect 'he eddy current signature resulting from the applica-i tion of the stress relief process to the parent tube at any location below the tube sleeves as was observed in tube R25-C17 (the physical dimensions of the heater probe physical hard stop pre-clude it passing through the sleeve and into the region above the parent tube). A total of 1093 tube sleeves installed in 1991 (in addition to tube R25 C17) were examined and no other cases l were identified where the stress relief process was periormed below the sleeve location. Two
{ sleeves in the "C" Steam Generator (R4-C85), which were installed in i990, were inspected with
! a bobbin coil eddy current probe which confirmed that the sleeves exhibited the characteristic
. eddy currem signature indicative of the stress relief process. Since these two sleeves were in-l stalled in 1990 using a heater probe which had electrical continuity contacts to assure proper i placement of the heater probe, this inspection confirms that these sleeves were in' fact stress re-
- lieved.
In conjbnction with the actions described above, a review oflogbooks and stress relief records
'vas performed. The purpose of the review was to ensure that problems encountered during the stress relief process had been properly dispositioned.
I Data records on cach affected sleeve were reviewed to determine whether or not proper stress relief had occurred. If problems with hard stop pressure readings were noted, the various lobks 4
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l l
Trojan Nuclear Plan' Docurnent Control Desk Docket 50-344 November 26,1992 License NPF-1 Attaciunent 11 I Page 9 ef 17 Typical Hardstop Pressuro Distribution e }-_ r
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I O 0000 0 100 0 200 0.300 0.400 0 500 0 600 0 700 0 800 0 900 1 000 Distance from Heate' Harostop to Bottom of Sleeve (in) 7-
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L N P R Figure % - Hardstop Pressure Distribution
. Trojan Nuclear Plant Document Control Desk
. . Docket 50 344 November 26,1992 License NPF-1 Attachment 11 page 10 of 17 problems and associated dispositions were prepared and reviewed by PGE and B&W Nuclear Service Company. Each of the problems were shown to have been satisfactorily dispositioned.
4.2.3. Evaluation Criteria As previously discussed, bobbin coil eddy current probe testing ha confinned that for tube sup-port plate sleeves other than R25 C17, the stress relief process did occur within the tube support plate sleeves. To provide con 0nnation that the heater probe position within the sleeves was within required tolerances to provide adequate stress relief, three criteria were developed. Satis-fying one of these criteria in conjunction with confirming that the stress relief process occurred within the tube sleeves, not in the parent tube material below the sleeves, assures that the stress relief heater probe was properly posiiior,ed within the sleeve.
4.2.3.1. Criterion 1: liard Stop Pressure Testing was performed during original tooling development to verify that the pneumatic hard stop could be relied upon to accurately position the heater within 1/8" as pmcedurally required.
This testing established the characteristic pressure signature that determines when the heater is properly positioned. The original criteria relied on the presence of this unique signature rather than any absolute value of Gnal pressure.
Testing has been perfonned to determine the lowest absolute pressure at the end of the insertion cycle for which proper heater positioning is assured. Testing was perfonned to 4 prove that a distinct signal was observed by the pneumatic hardstop, that the signal was consis.
tent, and that an operator could distinguish when a mechanical hardstop was achieved. The testing proved to be repeatable whether one or two cooling air supply lines were used.
The air signal showed a distinct rise in pressure as the heater cntered the sleeve. The signal
, showed a consistent drop in pressure of approximately 75 percent as the heater reached the hardstop. The pressure drop was observed to occur in two successive 50 percent increments.
Over half of the of the overall pressure drop is observed in the last 1/8 in, of heater movement prior to obtaining a well seated inechanical hardstop. The equipment operators are trained to look for the second pressure drop, with the overall pressure drop of 75 percent also being e,mphasized as critical.
Additional testing was performed over the last inch of heater trc el to show that the !.ardstop pressure would always be less than what is observed if the heater is still 1/8 in to 1 in, away from the hardstop. During this testing the characteristic 75 percent pressure drop was not observed for one heater even though the heater was shown by measurement to be against the bot-tom of the sleeve. The cause of this was that the heater's mechanical hardstop apparently would not seal fully against the bottom of the sleeve. On the basis of this testing, the lowest expected
(
i
- . Trojan Nuclear plant Document Control Desk Docket 50-344 November 26,1992 i
License NPF-1 Attachment 11 i Page il of 17 hardstop pressure in the last I in, to 1/8 in. of heater travel was conservatively detennined to be
- in excess of 5 psig.
s Further testing covering the largest and smallest hardstop to sleeve gap expected, connrmed that the lowest expected pressure recorded over the last 1 in. o 1/8 in. of heater travel was in excess of 5 psig. This testing supports the criteric fer positive hards op indication of 5 psin. No pres-sure reading of 5 psig or lower was recorded when the hardstop was between 1 in. and 1/8 in.
- from the hardstop position.
! Another test was perfonned to simulate the heater conditions that prevented the stress relief of the sleeve in the R25 C17 tube in the "11" steam generator. A heater was bent to a point wh%h would allow the heater to be inserted in the tube but would not allow the heater to enter the sleeve. The heater end cap hit against the bottom of the sleeve and became lodged. This testing l was felt to closely represent the scenario that occurred.
1 in conclusion, the test data shows a consistent performance by the pneumatic hardstop and a rec-l ognizable 75 percent overall pressure drop before achieving a mechanical hardstop position. A criterion of 5 psig or lower to indicate that a hardstop has been achieved is valid.110 wever, heaters may also be positioned at the hardstop and exhibit a pressure indication of greater than 5 psig as a result of not achieving a seal again::t the sleeve. The sleeves and heaters used in this testing included the full range m heater and sleeve design tolerances.
4.2.3.2. Criterion 2: llequirements for the llcal Affected Zone (II AZ)
The performance of the stress relief cycle has n effect on the magnetic permeability of the Alloy 600 parent tube material. Past testing has indicated that the change in magnetic perme-ability occurs between 950"F and 1050*F. This thange can be readily detected by bobbin coil eddy current inspection. This method has been used by B&W Nuclear Service Company to l verify correct heater position when stress relieving U-bends and has proved reliable for that pur-y,ose.
4 The magnetic permeability effects on Alloy 690 (sleeve material) are more difficult to detect with eddy current exanination, liowever, the eddy current signal or " signature" from the parent tube material behind the sleeve is distinct and repeatable. The tube support plate sleeves in-stalled in the TNP steam generators have been inspected with a bobbin coil cddy current probe.
l With the exception of the leaking tube, the sleeves show the characteristic penneability signal.
The standard bobbin coil eddy current test t oable of detecting the location of these perme-
. ability changes provided the eddy current signals are not masked by more dominant influences
< such as significant geometrical changes. The transitions into the llAZs beginning above the lowerjoint and below the upper joint are typically far enough away from such innuences so that permeability changes in the parent tube are readily detectable, in addition, the location of the
. Trojan Nuclear Plant Document Control Desk ,
. . Docket 50 344 November 26,1992 License NPF 1 Attachment 11 Page 12 of 17 transition into each II AZ, i.e., the "penn line", can be measured relative to a known landmark such as the tube support plate. The signal is distinct, and the measurement is very repeatable.
Either a 0.560" or 0.580" diameter bobbin coil probe was used to identify and measure the loca-tion of the upper and lower joint li AZs f" the sleeves in Steam Generators "B", "C" and "D."
Figure 5 shows the results of a typical bobbin coil eddy current test in the area of the lower weld joint of an installed tube support plate sleeve. Point 1 on the figure is the centerline of the tube support plate. Point 2 shows the beginning of the lowerjoint IIAZ transition region (entered from above). Point 3 is the centerline of the transition into the lowerjoint li A7, referred to as the lower " perm line." Point 4 shows the entrance into the upper portion of the lower kinetic weld expansion joint.
The 10kliz absolute channel is used to measure the location of the penn line. First, the support plane centerline is set to 0.00" on the measu,: ment scale. Next, the " peak to peak volts" func-tion of the computer analysis software is used to isolate that portion of the eddy current signal between Points 2 and 4. Point 3, the perm line,is defined as the midpoint between ?oints 2 and 4 and is measured by the computer software in inches below the support plate centerline refer-ence. In the example shown, the perm line is located 2.11 inches below the centerline of'.he tube support plate.
To assure that the sleeves were adequately stress relieved at TNP, testing was performed in the laboratory on sleeved tube samples. The purpos of the tests was to detennine the location of the ilAZ permeability change for a properly stress relieved weld.11 eater pos; don in the sleeve was varied to determine the minimum allowable distance f om the centerline of the sleeve to-tubejoint to the peint where eddy current testing detects the permeability change.
The results of these tests showed a clear relationship between the po:;ition of the heater and the location of the liAZ for heater positions from 0" to 1/4", which is the area ofinterest. The crite-rion chosen relates to the 1/8" misposition value, which is the same as the previously established criteria for positioning of the heater in the field. This is conservative in that temperature correla-tion testing has shown that the sleeve receives an adequate stress relief up to a 1/4" heater mis-position. The distance from the llAZ (detennined by bc.bbin coil eddy current probe testing) to the lowerjoint centerline (determined by rotating crosswound bobbin coil eddy current probe testing) must be 1.65" or greater to satisfy this criterion.
When a sleeve is positioned low relative to the tube support plate, the measured length of the
!!AZ increased. Thus for all sleeves positioned low an additio4.. ' +equirement that the deviation in both the upper and lower liAZs from the norm of all sleeves provides assurance that the sleeve received adequate stress relief.
^
I l
l l _ _ _ _ . _ . . _ . _ . .-
.- - . . . - - - - -- . - .. . _ -. - - _ = _ . - .
. . Trojan Nuclear Plant Docutuent Control Desk Docket 50 344 Novernber 26,1992 License NPF.1 Attachment 11 Page 13 of 17
\
" i PRODE DIRirDON l k -
\ , i
$ $5 e G 3' + >
< E$ { s, U E
\ l _ _
e
_- ?
. e i ;
/ H Ei 8?
3 s, .i 8 --
u
/ I E .: I!
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. hi , l o-f yI s
j/a , s.
y ,. u m
_ .I a
r f i
= si .. is -
-i -
Figure - 5 Typical Eddy Current Trace
t . -
Tr N Nuclear Plant Document Control Desk
. . Docks.30-344 November 26,1992 License NPF-1 Attachment 11 Page 14 of 17 4.2.3.3. Criterion 3: lleater Performance
! Heater perfonnance is expected to be fairly consistent for sleeves stress relieved with the same heater probe. One of the major factors that can affect the heater performance during the stress
- relief cycle is heater misposition. Mispositioning the heater low in the sleeve causes the tem-perature of the lower coil to increase relative to the upper coil. Testing shows that this increase is approximately 34 F per 1/4 inch of heater misposition. The heater probes are known to have been properly positioned for most sleeves (as demonstrated by application of the first two crite-ria). Therefore, consistent heater perfonnance is indicative of proper stress relief. Criterion 3,
, therefore, states that for any sleeve, if the coil temperature of the lower coil relative to the upper coil does not change more than 30 F from the previous sleeve, and the absolute temperature of l the lower coil does not deviate by more than 30'F from the norm of the heater, then the sleeve is assured of a proper stress relief. The data for this review came from computer data files that were stored for each sleeve stress relief cycle.
This criterion was developed based on testing of heater probe assemblies in a mockup of steam j generator sleeved tubes and in process verification test (PVT) standard tubes. The testing was done using the same process control software used at Trojan in 1991. A number of tests were run va ing the degree of heater mispositioning increments from 0" to 1". This testing con-finned that proper stress relief temperatures in the parent tube are reached with the heater probe mispositioned by up to 1/4". The testing program also included tests of mockups of tubes with sleeves mispositioned relative to the tube support plate.
! The testing showed that mispositioning the heater low in the sleeve causes the temperature of the lower coil to increase relative to the upper coil. Testing show that this increase is approximate-ly 34'F per 1/4 inch of heater misposition. Therefore, if the temperature lower heater coil rela-tive to the upper does not increase by more than 30 F from one tube to the next, the consistent heater performance indicates that the heater probe was properly positioned.
It is normal for some variation in heater perfonnance to occur over with the number of cycles run. This is expected, and as long as the performance remains within established guidelines, the heater probe is acceptable for continued use. From a review of both site and test data, a 30 F
, absolute temperature variation limit was chosen as a conservative indication of consistent heater
, performance. This criterion is applied to the lower heater coil since the lower coil temperatare is more sensitive to the heater position.
Meeting both of these heater performance conditions shows that the heater probe was properly positioned during the stress relief process.
I 4.2.3.4. Summary of Criteria
- 1. The pressure monitored during heater insertion was less than or equal to 5 psi; or l
l
. Trojan Nuclear Plant Document Control Desk Docket 50 344 November 26,1992 License NPF-1 Attachment 11 Page 15 of 17
- 2. The distance from the heat affected zone (llAZ) to the lower joint centerline is 1.65 inches or greater; and for sleeves that are positioned low relative to the tube support plate, a deviation ofless than 1/8" for both the upper and lower HAZa from the norm (based on a linear regression) of sleeves stress relieved with the same heater; or
- 3. For sleeves which were stress relieved with the same heater:
a the lower heater coil temperature did not increase by more than 30"F relative to the upper coil from the previous sleeve; and
- b. the absolute temperature of the lower coil does not deviate from the nonn for the heater by more than 30 F.
i 4.2.3.5. CONCLUSIONS The kinetic tube support plate sleeves installed in the "B", "C", a_nd "D" Steam generators were evaluated utilizing the above criteria to detennine if the stress relief heater probe was propeily inserted within the tube when the stress relief process was performed. A summary of the results is provided below. More detailed infonnation is provided in Table 1. A "2B" designation on Ta-ble 1 indicates that the sleeve was not accepted under Cnterion 2, even though the liAZ tojoint centerline distance exceeded 1.65".
In the "B" Steam Generator 87 of the 100 sleeves were found to be acceptable based on the ap-l plication of the hard stop pressure criterion. Ten of the remaining 13 sleeves met the heat af-l fected zone criterion; the remaininp three sleeves met the heater performance criterion.
l In the "C" Steam Generator 383 of the 461 sleever >cre found to be acceptable based on the ap-l l plication of the hard stop pressure criterion. Sixty-four of the remaining 78 sleeves met the heat affected zone criterion; the remaining 14 sleeves met the heater performance criterion.
l In the "D" Steam Generator 402 of the 532 sleeves were found to be acceptable based on the ap-plication of the hard stop pressure criterion. One hundred-five of the remaining 130 sleeves met the heat affected zone criterion; the remaining 25 sleever met the heater performance criterion.
In conclusion, with the exception of the sleeve installed in R25-C17 in the "B" Steam Generator, it was demonstrated that the heater probes used in the stress relief process were properly posi-tioned hithin the sleeves. In conjunction with the records documenting the proper temperature I
and duration of the stress relief process,it has been determined that the sleeves which remain in service were adequately stress relieved. Based on this additional testing and analyses it has been shown that the failure to properly stress relieve the tube sleeve installed in "B" Steam Generator tube R25-C17 was an isolated occurrer.ce. Testing and analyses have verified that similar prob-l lems did not occur during the installation of the remaining tube sleeves in the "B", "C" and "D"
.. Trojan Nuclear Plant Document Control Desk
. . Docket 50.t44 November 26,1992 License NPF-1 Attachment 11 l Page 16 of 17 4
1 4.3. ACTIONS FOR OTilER CONDITIONS IDENTIFIED l During the course of the eddy current inspections of the tube sleeves, a decrease in sleeve diame-
- ter (" necked down" condition) was noted in two tube sleeves ("C" Steam Generator, R12 C23 at
- the second tube support plate and "D" Steam Generator, R13 C8 at the first tube support plate).
! A 0.$40" diameter probe would pass through the narrowed area of the sleeve in "C" Steam Gen-erator, R12 C23. A 0.560" diameter probe would pass through the nairowed area of the sleeve in"D" Steam Generator, R13-C8. This condition is believed to be caused by the expansion of water in the sleeve-to-tube annulus between the two kinetic welds. Although this condition has been previously analyzed by B&W Nuclear Service Company as being acceptable for a number of heat up and coc,1 dewn cycles, these tubes were removed from service (i.e., plugged) as a pre-
~
cautionary measure.
I
- An evalut. tion of the potential Dow loss due to the postulated " necking down" of all tube support plate sleeves was perfonned. This evaluation assumed the inner diameter of each sleeve was i reduced such that a 0.560 in. diameter probe could not pass through the sleeve. The sleeve inner 4
diameter was assumed to have a Dow resistance equivalent to an inner diameter gradual reduction followed by a gradual enlargement to the sleeve nominal diameter. The evaluation concluded that the now reduction already r.nalyzed for installation of steam generator tube sleeves (i.e.,15 tube sleeves results in an equivalent now reduction to one plugged tube) has sur-Scient margin to account for this additional postulated How loss due to sleeve " necking down" Furthermore, Technical Speci0 cation 3.2.5, Departure from Nucleate Boiling Parameters, re-quires the Reactor Coolant System total now rate to be maintained above a certain value. Dur-
- ing power operation this now rate is verified to be within the specified limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Therefore, a reduction in How as a result of the " necking down" phenomena would be bounded by the Technical Specification limit which is frequently monitored.
i l' An indication at an unsleeved tube support plate in the "C" Steam Generator (R29-C24, at the second tube suppoit plate) was noted during the sleese eddy current inspections . This indic -
tion was identined during an inspection of a sleeve at another support plate location in this tutie.
This indication was evaluated as having increased from 0.54 volts at the beginning of Cycle 14 4
to 1.0 volts (voltages normalized to 4.0 volts for a 20% ASME calibration hole at 400 khz) dur-ing this inspection. Technical specifications implemented for the current cycle (Cycte 14) of op-eration require repair of Haw like bobbin coil indications of greater than i volt in amplitude when voltages are normalized to 5.0 volts for a 20% ASME calibration hole at 400 khz. The indication was equivalent to 1.25 volts using voltages normalized to 5.0 volts for a 20% ASME calibration hole at 400 khz. The bobbin and rotating pancake coil eddy current probe inspection results of this indication in both 1991 and 1992 are shown in Appendix D. This indication was characterized m 1992 as a multiple axial indication.
The original indication at this location increased in amplitude by 0.46 volts in 178 effective full power days of operation. This observed growth rate was compared to the growth rate predic-tions discussed in WCAP-13449, Rev.1, " Trojan Nuclear Plant SG Tube Plugging Criteria for
Trojan Nuclear Plant Document Control Desk
, . Docket 50-344 November 26,1992 l
- 1.icense NPF-1 Attachment 11 1 Page 17 of 17 ODSCC at Tube Support Plates." WCAP-13449, Rev. I was provided to the NRC as part of PGE's License Change Application 223, dated October 22,1992 for the upcoming Cycle 15. The growth rate was also compared to the growth rate predictions discussed in WCAP-13129, Rev.
1, " Trojan Nuclear Plant SG Tube Repair Criteria for Indications at Tube Suppon Plates "
WCAP-13129, Rev. I was provided to the NRC as an attachment to PUFs Report," Portland General Electric Company Steam Generator Tube Integrity Safety Analysis Repan for Tube 1 Support I' late Intersections," dated December 15,1991 (revised January 6,1992). This report served as the basis for the technical specification interim plugging criteria applicable to Cycle 14 4 operation. The observed growth rate is within the range of expected growth rates predicted for i Cycle 14. The growth rate for this tube corresponds to a cumulative 1trobability of about 86%
for predicted voltage growth. The analyses presented in WCAP-1310.9, Rev. I indicate that sig-
! nificant margins remain in the structural integrity of this tube, Nevenheless, the tube was re-moved from service by plugging.
j 5. CONCLUSION
. A thorough evaluation of the cause of the "B" Steam Generator R25-C17 tube leak on l November 9,1992 was been completed. This evaluation deterrrined that the leak was caused by the failure to position the stress relieving heater within the sleeve of the tube during the stress relieving process when the sleeve was installed during the 199i Refueling Outage.
The defective tube was stabilized and removed from service by tube plugs. The a 'jacent tubes were inspected to confirm they were not damaged by the tube leak event.
An evaluation was completed of the process used to install the sleeves in 1991 compared to the process described in the B&W Nuclear Services Company Topical Report BAW-2094, Revision I which was reviewed and approved by the NRC. This evaluation confirmed that the 1991 in-stallation process did not alter the critical parameters of the sleeve design and taus was consis-
- tent with the approved topical report.
i An evaluation of eddy current data and sleeve installation records was comp verify that the stress relieving heater was properly insened within each sleeve during th- . relieving process. On this basis, it was confirmed Gat the sleeves in service in the steam generators have been properly stress relieved.
As a rev. of these inspections and evahiations, it is concluded that the steam generators are op-etable ar.d the plant may resume operation.
J
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_ _ _ _ ._ _ . . _ _ . . _ . . . _ _ - _ _.._ _._ _ . . . _ . . _ _ _ _ _ _ . _ . _ _- ~. -
a 4
I i . Table 1 Steam Generator B - Page 1 of 3 4
4
> STEAM GENERATOR "B" d
i STRESS HELIEF HARD STOP PRESSURE SLEEVE LOCATION HAZ CRITERION DATA CRITERION
- ANALYSIS a
J i VALUE VALUE ACCEPT ACCEPT j r.....WW l C'CL l TSP ACCEPT
- o
.m...
- ht -
-- 03H .
. -3. 1t . .
X ... . .- 1.5 8 :.
1 2.04 L 4
1 J - 377 05H : :5.7o . X
-! 4 > 1.
. 05H . . 3 9x X -- .
17.6.1 X ._
i.
4 . 2 51._. 05H ..~ 4 3.24 .- '._
X._ .m s..1 : 7 7.._'
.X .
t 4 ,
.- 2 9 . 03H . 6.6 ; .
.. _s 1.87 '
X .
n 3
5 . -4 ., 05H --. '3.7 - .. > X -: 1.74 : - - X i 5 .- ~67 01H . m ~4.9 - < X .- G.71 ^- X l '
X I
- 8 ..17 02H = , 2. 9 K. . . .-
X 1 ~.69 c -.
4 8 , J 21' - 02H . . 3.3 ' X /1' 6 ::. .
l 8 . 24:: '
02H i :2.51. X 7. a l.82i X f
8 .. 691. ,~.-- 01 H
. c4.2 n -
X .
' 1.6 :: .
l 9 ~. 25 i , 01H -
L 1.81 ~. . 1 X s 1,6W 11 X
- 9 : OTH X 7
- 55.. t. = 3.6 ..-- : , ..i 3.. 1. 8._2 a. ..
! 10 .
324~-'" 02H - - 2.7 < ' X . . .J 1.97? : Le
- 10 .26. 03H - -
13.5
.-_m t .. X .. . Ei .t 7. 3_?. .
X
.v 1
11 s~ 271 4 05H -. -
T2.2J 1 n . . .
./1..82:- .. C ....-- X
^
c31:
~
l .11 >
04H - M 3.6 % . X T 1.511
! 12 . .. 1 1 -
02H F4.9 7 ..
X J 1.74) X 1 12 ;.:30t 02H F4i30 X . J:1.791 .
X i 12 > 33 N, 02H .02 3: .
X i E.,.:.t1,.7_3 i ~.
X I
4 12 : 551. : , 0_1H .a 4 *- . .- X . M I'.59 s i
e 13 E :::3E 01H L2. 9 L - X :+ .11.69 e .1 X
- 13 .932; O2H f 4.72 X X
. ._ ..13_1.7 E E. . . . . _. .. .
14 ,
J 44 E ; 02H . 54.5 x ~
X J:El l.51 it ,
{ 14 , v72 ; ._ 02H ..a1t,
- , X- -31.7 8 t. -. X :
i 14- 3763'! 02H E .r22 ~ ' . . . -
X r.;1.59 t i 15 ' J15'J 03H 6 14.8? ' X - m1;86 L . . . X 15 / Sli: - 02H 1:74.P h . . X : .J P1:481.3 16 , 35 < .a 03H i 03.2pa X .1 101.8F .. E X i 17
- 16 T ~ 01H . ?4.9 4 11. X Jig.66;-. X i 17 . .. L16 :c - 02H . d 2.6 6 . 2 X - D.1 7._5 w, ,. _X
. 17 L A23C 02H J2.9:E ~. - X /1:7e M X i
17 .- 027 4- _02H ..
r4; JM X 31;792 N X 17 437 L o . 02H .
, -s.v4' 81./t . X 111'.62 L ct 18 . :r38 % 01H- .::4;5 n . .. X . . 3:1;85F-.1 X
, 21. ?!4891 ~ : 01H _ J4 4.2 L L ' X 131;92-E X 22 .
<8= 01H _.~_ .# 4 6.. c ' . .
X ' :=.1_.8. 9 X i-22 . i:17 n .~ OSH : J 31.1- X . m .11.6 7 23 : 28 ;:-O 02H E 3 3 21 E . . . 'X : '1.69 C . ... X C
24 E?25C ~ 01H ?!. W1.61 lLJL X J 41:67 C ' X 24 b 48 @ 03H . 43.9 L ~. X ~ : f:1.62 s E
~~
24 ~ 1855 01H X ' ' c1;79 i X 1
- . . - , ~ .,s - - . , -- , -. -. - , . . _ . - . . , , . . m,.,_., ,_m.._- ,, .
1 s
- . Table 1 Steam Generator B Page 2 of 3 1
4 1
i STEAM GENERATOR "B" J
l STRESS RELIEF HARD STOP PRESSURE SLEEVE LOCATION HAZ CRITERlON DATA CRITERlON ANALYSIS 1
J i
ROW COL TSP VALUE ACCEPT VALUE ACM T ACCEPT
._25 .9' 03H = .-
2 2.4 ._. . _ -
X =_1 9... '. -
X
~
2 25 7 31 1 - 01H - 3.41- . X - -. 1-82s . X i 25 L ' 31 :: 02H - 4.5 . - X - ' li?3 - X 4
1
.. 2.7 ~251 ' 02H .
._3,.,.
2.. : -
X -ss ..1 73 c ..
X ..
28 02H X "
i 4
<19 . _ 3. 8 . .
- li641.
4 28 .
701_a 02H - - 1.27 .' X ., c 1.57 <
4 4
29 251 02H ....3'. :
X. 11 873 X .- .
1 29 -26t' 02H 2. 51,... X 11'.955 ., X-d m- .1. - . _
X a
29 - r57 - 03H- , : 4.1 u X . < 1.71 r -
.~ 14E 02H .- 14.6 n - t L48 % .. ..
30 X t 30 . . E 21 02H P 4.6 ~.'.- . X . J 1 '.64 f ..
l 31 n17v ' 02H . J 3.4 ? . X 'L h69: X
. . a3.49 - 51.76i
~
. 31 ;17.~ 03H X -
X
- 31 90245- 01H ? f 3
- L. -
X ~ $1.75 e .
X 11.951..:
4
- 31 n25 u .. 05H ....t4
- X X E26; 1
. ..31 02H 3.6..
. x
- X ._:: 1 .. ;.7. 4. b .
X ..
i . - -31 138 F ~ 02H.- 3._2. 8_E m. .
X .. .. Y t.6.8. t ~ _. X 4
4 31 x J44.E 02H ' D 4 t ._~ :.
X Oe.87: U D .~
X
- 31 ";75 i_ 02H_ M4~.4 #2 X _. ... _1 L. 581,_J i ..
i 32 . ;543 05H .-
'.5 7 H ? t5.9..1 :. X i . . .
32 a773 . 02H ' .7:3.41 - X i J 1.52F i
33 234 - 01H ~ "2.31 X :::1173 a X
33 L32. 02H - ?3.8 ? X , 21'65r 0 X X~ X 33 tS9en _01H _3._3 A t . . -E .A.1 68 C . .
,. 34 :172 ~ OEH . - T3.5< X ._.
e2.022 X
. 34 6
?27 > 05H E.~ <3.67 .. X JL67J -
X -
l 34 177; . 01H i. F 3.6 w - - X J 2M69 0 -- - X 35 - , A170 . . 02H 2:5t?E ~J l h96 E : - X
- - 35 - i322 02H 14.7' _ 2 X _,A L75.i i. - X l 35 b 566 n . 05H ./4.5? 4 X ' 71 a77? ! X 36 (182 02H , . ' _ . . ~ .5.2
. . .. 21 9_5_C _
4 X_ .
l 36 - 120L 02H 1 1.61 s X at73 E. X 36 s- < 21 ; . 04H . 3 ( 3:3 E .J .. X- . .. 41.9 : . X 3
36 t.H.I. 221 02H A3" ~; X 14.6464 36 _.._.122 . 5 . ~ 03H ' : 3 3t _ X 3 1_ 66 . .
X - <
- 36. ~
- 41E 03H _
- 3. 3.u._ ...;
X -
Th8 ? . X 1 36 .c49 - 01H T3.65 1 X L1;73E . .. X 37 J 3 28sJ . 02H E2.5 s . . , X X J L. 85.1 ..
37 *
- 39.J 02H 1_3.87 i . . .-
X %217 m~
e X ;
4 37 m39 .i 03H -- 1J4~.EJ X M%37E E ,
i 4s'^E
~
!- 37 _.154 _1 _ 02H X J 1.P". ,c _. X l
38 a425: 03H <
> NDF b ~ 15 41.W ~ ~ X l i
i
i r f'. Table 1 Steam Generator B Page 3 of 3 Jl 4
STEAM GENERATOR "B" i
i STRESS RELIEF 4 HARD STOP PRESSURE j SLEEVE LOCATION HAZ CRITERION DATA CRITERION ANALYSIS 4
- now cot l TSP VALUE l ACCEPT VALUE l ACCEPT ACCEPT 4
38 12-72. >. 03H NDF'-
1.97.r . J X i
38 28 . 03H - - - 5.7 : - . _ . 1.66.r .
X . . . -
2 38 ~45.< .. 05H .:: 3.3 : X ! A- 1.69 ? .
X l
38 :: 69; . 02H - 15.1 : . .
. 1. . --2 >.. - i ..
X i 39 -
- 01H - :NDF :4-
.. f 1.73 . . , X j 40 46s 05H - 4. 2 ,. ' X :1.766 X i 41 :2 9 0.. . 04H . ~ 3.3 . , . . X g J-1.8 . . . X i 41 :30^~'- 02H X f 1;84 6 - ! X
.? 2.8 " .
1 41 . 42 01H J 4.7 ; . - , X = :: 1.67 9 . .- X
- 42 1351 02H ~L ; 5.3
- e .. . .
1 1 ~.68 t: . X 4
4 42 h 41. ; 02H . - 3.2 i .u X x1.96 t X l
4 44 ':38i ' 01H -: NDFr - ~ . c 1.96 : .
. X 1
4 44 -464 02H -- .
. 4 5? . . .
X ..- :1;51L j 44 - 58 E ~ 02H # . 9 . , ... X ! e1.755 . '. X f
1 44 U60: 02H - -- . i 6.1 ! --. .- 41 ' 51 . . .
X
- 45 t. 37 - " 02H .
- 1.7 7 ~~ X
.: 1.72 ; ' X t
i i
i h
i 4
4 Y
4 k
3 i
?
a 1
i
)
i i
i-j f.
N d
y ,n ,-r:.s' --
w - --
= --- s - - - , w o-.+-. w --=w--- n~-mr--r v -w-~e --o-2'-*v er -v
- - - . - - - - . - . . . - - - . - . -. . - - ~ . . . _ . . _ _ -
. Table 1 Steam Generator C Page 1 of 11 STEAM GENERATOR "C" STRESS RELIEF HARD STOP PRESSURE SLEEVE LOCATION HAZ CRITERION DATA CRITERlON ANALYSIS how l cot l TSP VALUE l ACCEPT VALUE l ACCEPT ACCEPT 2 24- 02H 2.9' .
X 31.59 c 2 - 1361. - 02H 3.6 ' - - X T 1.68 n X 2 154i: 02H 2.7 - - . -X l 1.81 : - X
[
2 158 C 02H . . - 3.1- .. X ~ J- 1 ~.62 ;
2 80- ~
03H - 'NDF: .. e 2.01 " - -
X-3 7 51 04H -NDF; .- 1.90 1 ! X 3 . 38 : 02H -.-- - 4.0 . ' . X . a1.751 X 3 60 : 02H 2.6" - . -
X + LE: 2.21 . . .. X 3 --60-: 03H . a 3.01 X .i . 1 ;.71 v. . .
3 r -- 60 ' 04H . ; 2.6 - X >0.69*.
3 . l/ 64 - --
01H .
0.5 -- -
X . ; 11.371.
3 j731 02H ' 3;11 :, i X .. E T 1.77L - X 3 :74- 04H 12.9 :- X - 2.05 L . ' X M 21'84t. J- 28-
~~
3 ' 851 - 01H - J4.8 5 ' E X . X 3 :857 02H !t NDF:: - . .
a1.19 t l a X 3 8 74 02H _ . . J ? I s. . ^ '-
X ^ ,3 2-3 : < 89 - 05H -NDF:/ ,
- ,1;96 L ' e X 4 01H _J 3 9 2 X 31s784. _X 11.% ' - - -
4 . 24b 04H . D 2.0 * - X a : 2.02 E -. X 4
' o S4':1. 02H E 4.5 ? - - X ' =.
!. 21.68 R- . ~ . X 4 :.. i 6. 3. --
01H _ . -1;2? . X . '1.58 f . .
4 651J 02H . J:2.3 ? .. X ~ bli?8L i X 5 -
-E. 26 ! 02H
' . -- 2.5 4 i . . .
X .. 21._58. 4 !
5 /36 ' 1 02H-f 4.35... X . A1.562 5 ..:54;i=
- 01H l11.81 . X i/ 2;13e ' X 5 254% 02H . :14:1 :E...~ X J1.023: .
5 + L 59 c =. 03H c.; NDF L .. -- .a1.84% X 5 :61; E 02H 2 3.6 7 ' ' ::J- X U 1.40 L 5 c 62 # . 01H ::.O.6 4 < .
X J M1.73 r ! ' . X 6 m e4a a 01H -
E2.3:Ti X 41;593 '
6 0261 ' 02H 323.0 L - X . . _
- 1.53 %
4 l
l 6 ?645 - 02H ~i L2.Si .L X ..s1177, .
X 6 .
89<_.'03H o2.92 ' X .. d 2.04E .. X 7 4 19(11 02H ~. J 3.0 x - X .r:1~ 65 . _ X_-
7 .J. 23 i. . 02H ~
2 4 0.. :..
X .- .. ,_1 m 72 :
X 7 " 29.? 01H . . 31.51. , ' '
.. . .X 31.621-7 3 30 L 01H . 23.41::1.2 X .?:1:54 E 7 431v 01H 4-1;4 W .!_ X ' T1:491 7 2 32.:n . 01H ~ s.. . e 4.9 s . X A1;684 - X l 7 @ 37; 2 02H . J 4'.9 6 .. X L ;172 >. m
. X 7 o 54 L . 05H E3.5 ! . . .. ~ X ~~ :. T1.38 e 7' .. J 66 u 02H . J 2;3 c -.~ X ' ' : 1.67 J X.
.g J
. . Table 1 Steam Generator C Page 2 of 11 i
i STEAM GENERATOR "C" i STRESS RELIEF HARD STOP PRESSURE
- ANALYSIS i
ROW COL VALUE PT VALUE ACCEPT ACCEPT l TSP t
t 7 68: 01H 2.1 ; 41. 59: _ . . .
3 7 7 02H . 1.41 - _ ^ ' f :(1.45 ' - .
7 :
- 89. : 02H ,
.4 N. D.. O . .t1.82_ . . .
X 8 141 04H . -
...JND.E1.L. ..
-- /1.87 ; '.: -
X
+
8 - 02H .
- 4.0 u _
X - 1.601
._-. 8_ . . t 3 4_i -. _ 01H .
' 3 _9 G. .
X 91.48 u. m . . .
8 36.__- 02H _ L2.4. -1. . ,
X . . .11.565 8 ; 38.~ 4 02H ~ *2.2 < J- -
X , l a 1'.53 3
=. .
i 8 -54i . 03H -
43;1' . -.
X 1.84. .. X X
! 8 _62 01H ..
1 0. ~i _
X : J_1.79 U i . .-
4 8 ..651 01H ? O.3 = - X . al.795 . p X .,
- X 8 '8_53 03H _ 3.8 t -. X f . 01.85 2 . -
9 J :.91 05H L 3.9 ' - X z . 31.831 o. X --
i 9 .;24o. - 02H 3.5 ' . E -
X ~J 1.47 . .
9 h 26 =_,.
02H . . 4 N. D._F.r 11$7e J.-
X 9 'i29C..T.. 03H : M.0 F_11.
X . J1;.77x.w.
~. .
X ..
9 0 32 ? -- 03H 14.8 f .
X v .31.71s X - , .
35a .- 02H
- 9 .~ - 2.6 9 -_ X 1 --.
- 1 65 x 4 . X l i 9 e 60.L .s 01 H .. . 11 5_.+ . .
X . a l_.6. 4 f. .. -.
9 : 63 L > 02H J2.0 L J X 11.81 1 _ X
. 9 /69 ! . - 01H < . Er2.-16 . X J 11.79 m X 1 9 .170 E < 01H I4.0 t ~~ X 251' 88 F .~ . - X 9 .
.r 89 4 ' 03H - - .. . ? 2.4 %
X 21.847 -. i X .
9 10 89. t . 04H ... T ? NDFS ..21 48 t X 1 . .
10 ~ '41 .. 05H .. al.8 C m
- X = J2.58s JJ X .
i 10 515 6L - 02H - . 31;24 1.i X N-1;61t i
- ^NDF) .-
4, 10 W 27 ' 03H -. J 2:18 ;
- X 1 10 r 29.t 01H _- 2 3.1 e X . 1.31 8_.2 i . X _.
! .= . .
. 10 ~T33/ -- 01H _ .2 2.8 k .- X .
1.561 .
a 10 A40M 03H '?N.DFL ~ -
J D 1 60 C _' ,.
X ..
10 , M*3 ( 03H -. e2.~4E 4 X . 31.79 c M X
!, =10- t612 01H ,_
X ~.4._1 ;421 C. ". -
-J' ll 2 UL i.J ...AX 10 M63 E 01H ' c2.5 1 al.64 n
! 10 664n 02H O 2.2 bJ-oJ X ..i'd1.61? w 1 10 9 66 -E-- 02H
.~
i r.2. 3i. U .- -
X .s J1.66r . - .
. X- _
1 a
10 468 E!: 03H ~ 23;2:" ' J . X T : c1153E - E >
1, 10 <>72 i ' 02H L . t 31s 2 X t1.80 4 - ' X 10 ? Sir J 02H- v1l 0.51.~. 2 X _#1i531 3 10 J85A - 02H m 3.40 R X 71.68 L i X 4-i: 10 .sm 93..siE 03H 13NDFe. C M178CS X I, 11 il65 i 02H ' 43.4 RC X 11;740 . X -
W192 L 3.0 ;i ' -[D 1.60 ?
~
11 02H X b
4
-. - - ,. , . -r - - . - - . . , , ,. , .,e -
j i
- . . Table 1 Steam Generator C Page 3 of 11 i
i i
STEAM- GENERATOR "C" e
i STRESS RELIEF HARD STOP PRESSURE
) SLEEVE LOCATION HAZ CRITERlON DATA CRITERION 5
ANALYSIS 1
4
! aow l Cot l TSP VALUE l ACCEPT VALUE l Af' CEPT ACCEPT i, 11. .-.
-41: 02H - _ :
_0. 5. 4.~ .
X . ? 1.64 - _
a 11 - 53: 02H ~. ?- 4.8 E . X 1 ;6. 2..
2 1
a 11 s 552 - 03H- .! 3.9 e i X .. ;1;76 < ' ' ; X . . . -
11 ._ 55: 04H = - . L3.0 a X . . .
> 1;76 t X.
11 . E- 5 5 . . 05H . 13.5 : -- X 1 1-45 x . - .
l - 57: X
~
11 03H 3.9: . J X =
1 1. . 8.1 :,_ ..
11 . 58i 02H - 13. 2. .E. . ~.
X ..-. .1 T.7. . . 61 .
X -
i 11 - 67 E 03H - -2.8 . _ _
X c 1 67 c .
X -
11 .. 69 ; .- 02H <
X .. < 1.521 -
-' < 0. 8.t
- 11 .- J79 -- 02H -
- 4.'1 - ~ ,
X m 21'846 ' ~ . X i
88.,_. 02H X 11 . 3.5 L -- ., .. 1.61s . J t
- 11 D 91r 05H ... ! NDFm 2.21 C . ~ . X
- 12 14 - 03H - 4.1 > ~ - X . 22.30
- ., Xa -
, 12_ .
61.. 01H .. i1.6 ?~ . ~
X +1.52 n -
l . 12.._ W_
02H ..~ . . .
5.2 .. . 2._1._;71 -E , . . _ . X .
}
.12 4 'SJ 03H ;NDFL 4 . 02.04 c O X
! 12 115- 02H ,
- 1;8t . - -
X O 1'.691 X t
12 _ . {161- 02H 4 3.2 < ~ X ~ 11;6_6 t ~. .
X .
4
. 12 E 23 ; . 02H- E3.6s..:0 X - .31 -. 65 E -- .~ < X
- 01.741 12 .J28 ; 03H , >NDFG 2B X i _12 1.3 71 . 02H ? 4.9.L
. ~_ X A 116V L f . .. . -
- 12 x41J .
04H ? ND_F._J A. ^ 11.48 E X .
l 12 U54 s 04H '
. 2 NDFi ? . J1;976 X
~~
1 12 ~~~~E. 73 02H "~~~6.EE~ . . .
X 11$53 X l 12 ' /85? . . . 02H- 51 4: 11. X1.87 s - . - X 13 _._4 9 , ..02H . 2 2 6_:;_ ". --
X T1 -.
61N _ -
! 13 216' 02H .:r2.81 X 41;754; 1 . X
! 13 E23C 02H 4 4.01-- U X . . ?1.45 J -
13 ~42 02H < 3.3 x X 21'.291 13 ' 53 . .
02H__ :J~ 60?. . . .m1.45 C_J X ...
i 13 P:: 57 . - 01H 53.0L . X - 41.43 f 13 ' 68 ':r 01H t1;41 ~' X W1.68 r i X =-
13 -!87e 03H L2.5:. . . . . - .
X #.1;81t , .
X a
13 4.u880 -. 02H ~ E 4:3; - X J 1.57 e s i 13 4,
_ 89 0 -. 04H . 2NDFi . -F.2 0611.
X _.
~,.
-14 M 4 E 05H D NDFn ':: 3 E c1;77f ' E X 14 2154 .x 02H . . D O.8 L - X . r1.66 s ' _ X_
14 ? T23 s n 02H 12.8 t J. . .~ X 1 31:42 L 14 v 03H X
.~.. 2 5. 2 " - 'INDFhi.J . L L1.704.
I 14 W 26 L .. 02H 4 2.4t . # ~~~
X . W9441 E1 X ~
14-~ N31).I 01H- . ...- 21.8 X 3I~fiSC X
- . 14 343;.; 02H ! C2.2 2 M X 21.51r d
. lable 1 Steam Generator C Page 4 of 11 STEAM GENERATOR "C" STRESS REllEF HARD STOP PRESSt'RE SLEEVE LOCATION HAZ CRITERION DATA CRITERlON ANALYSIS VALUC ACCEPT ROW l COL l TSP VALUE l ACCEPT l ACCEPT 14 55 02H 2.3 X 1.77 -- '
X -
14 55- 3II~' NDF ~ ' 2.20 X 14 55 04H ,,,,,,,, 4 . 4 X , 1.19 ,,, _ ,,
14 64 01H _ 1.7 X - 1.65 - X . . - -
14 65 02H ~
2.0 X 1.'29 14 65 . 03H 3.6 X .. . 1 63 -- .
14 67 02H .1.9 X 1.83' - X 14 88 02H 3.3 X 2.18- ,,
X 14 90 03H 2.15_ _ X
' N.DF 15 ~
17 02H ".. . G X 1.61 15 19 ,, 055~ ,,,, 2 . 8,,,,,,, X,_,,,,,, . ,,,,,,,,, 1 . 6 0,,;,,,,,,
15 24 02H .. 3.2 . X 1.45 L 15 27 02H 2.8 -- X 1.84 X 15 36 01H = .. 2 8 . .
X .
1.70. I X 15 38- 02H - _ - 3.1 ~.... . X :
- 1. 71-X 15 39- 01H 3.7' X .;.-.,--- 1.83 .-s .. .
X 15 .-
40 02H 2.5 .
X ; 1.94.?.
X 15 -41 02H ' 2.9 - X 1.77 X 15 47' 05H 3.4 ' X -. t1.55 -
15 -- 4 9 02H .,,,,,,,,_4 0 ,,,,,,,,,,,,_
X _ ,,_1.5 8 7 ,,;,,,,,
15 :53 01H 2.1 :. .... .
X .11;7:h .. X 15 57 ..
01H
. _. 2.81._ X i 1 29. '. .....
15 .. '60 - 01H .
13'
. X x:1.69 : X 15 ,, -- 61 ,, 01H 72.2 - ,,_
X 3
_ ,,,,,,,, 1 '. 6 2 -- , , , , , , _
15 64 01H -
' 2. 5..... X -1 641 .
15 '6,7,,,,,,, _ . 01H 1,&,,,,, ,,,,,,,, X ,,,,,,,
1.69 y,,,. X 15 70- 02H - 6.0 - .. 11.84' . X 15 '85 02H 4.1: ... X : 1.78 t .
X 16 05H N DF -- 12.01 t X 16 '10- OSH NDF 1.75 u X 16 15 _- 02H . ,
2.4 .. . X - -2 24-m..,.....
X 16 15: 03H_ .,,,,,,, 2 .4 : X al .44 -
16 .,36 02H .
2.7 X 1.54 ^
16 -i 41 02H 3.2 - X -= ~1.53 16 . 62' 01H .
.1.2 - X > 1.80 - .
X 16 ... . 62 .4 .
4.1 . X L 1.76 : X 16 ~63~ 05H. . . ..' ..---.2.3 . . L_ - X 2.424 X 16 '66 . 02H ..
. 4.0 : .
. X . .. 2.101 .
X 16 ,,,, 7 0,,, _ 02H 3. 8,,,,,,,,
X _,,,
- 2.03 ,,,,,a,,,,_
X 16 :72- 02H i 2.5 : . .- X :.1 .~ 89 : X 16 .,:73 02H. .
.J 4 1. .
X 1.91_ - X 16 ' 81 02H 1.5 - X _ 1.45
i 1
. i
!'. Table 1 Steam Generator C Page 5 of 11 1 l
i STEAM GENERATOR "C"
! STRESS RELIEF HARD STOP PRESSURE SLEEVE LOCATION HA1. CRl1 ERION DATA CRITERION 4 ANALYSIS 4
ROW COL TSP VALUE ACCEP T VALUE ACCEPT ACCEPT
. 17 - . 17 - - . 02H 3.4 H X . - . . 1.77: X 4
17 21 02H .. ::4.0 : . X 1 i
17 22 .
02H -
3.6 ,,. X - 1..4 6._' . .
17 .-'30
- 03H- .' " N DF L.. !1.94< X
!- 17 31' 02H 4 3.01 -. X = : 1.60 n- . .
I 17 '34r 1 02H -3.1' - . X 11.82 .. X i 17 135i 03H .- 4.0 J ..J X :1.801- ~ , X
- 43 . . 02H -1;2? . -
].
-._1 7 .
1 X 1 54; ' '
~
{
17 47E 01H ._~ .. 1;61 X L140 4 . .s. -
, 17 LJ-53-- 4 02H .
3.0 :s . . . X .
r 1.73 t- -
X l ..~.1 7 5 5 .- . , 02H .~ .-
=3.4< X .
/1..6.1m _
17 . 560
- 05H . t N D F _.
-. . .. .: 41.91.::.: i -.. _ X f
17 :64:i.- 02H . 4.21 .. -
X J:2.02V1. X
,' 17 ; J 65 -. ~ 01H
.- - =
?1.21 >
X :
-._D 1. _.54 E
! . 17 -67:.E m_02H .
- 3.0 t ,
X - 12.28 < - X
- 18 - J 6 -: 02H ' ' ? 2.4 : . . . '
X ' - -.11.76 N- - X
,! 18 e10? . C2H 44.5 = ,. ..
X - - . ::1.58 e 18 216' - 04H --. 3 NDFi . < 11.96s C: X
- 18 .
- 191 02H . . . & 1.4 + .. X 1;74" _ X 18 e 27 "- 02H . J:.4..;.0 :
- X . 31.49 <
18 J:28 e; 02H
_ _2.9~'
3
,: X .s_it_.4. .. G.un -
i 18 1 v29 03H 1 iNDF ' , . L 31.8% 4 X 18 ..J301. . 02H .
12.9f . X _ al 6._7L i .
X i 18 h35: 03H i .-sNDF1 '
T:::J:1 >.78 312 X 18 338u . 01H ir 3 2: . .
X . . si;480
- - 18 144
- 02H - i1.41 .. X M1.661. a X
. 18 14. 74 02H P S.6 x i . - . 111871,.
-. .. X I 18 453 .. 02H 33.57 X .. ? 1;70 c .1 X
{ 18 -
- 73s 02H e 0.2E 1 X : < 1.54 :3 .:'
19 1 5.. - 02H .. :.i 41 8 3 .~ .. _
X i:1~.62 w I -
l 19 . -116,> .^ 02H _. 1.2.8 u. .
X .a #1'.644
! 19 v19 '... 02H 12 2 8..i.
X .t1.18.. 0 t J. :.: .
X .
- 19 .036" 03H J__J 1.12 -
1 X v1.74a L .. X G361, 04H . a 1.53 < .
1, 19 E 4.4 - X 1
, 19 s. L431 02H : 5.3 ~ 31.712:11 X 1
1 19 J.9 481.J:/ 02H 1.14.5E X 41;7 9 ; 1 X 19 L.150_1 _ 01H 1 1 3 81.
=.~ .
X .e. 11.93 L- -
X ,
t 19 17541?. 01H L? 1.K E X i :1;52 L .,
i 19 [+54C J O2H .4.01 .. . i
- X s J 1.69 - X 19 1.? 60 9 . : 01H . :s 0.61: ; X J 71.82s ' i X 19 .. : s 63 t a 04H ;:2.61 1 X 31.95: .D X i
19 ' 65 N 02H . .-7.6L ' X .' : 1.97J - X J
s 1
i
-- - , - . ~ , . , . , , ,,--,n -e.
s i
, . Table 1 Steam Generator ^ Page 6 of 11 i
. STEAM GENERATOR "C" _
i 4 STRESS RELIEF
! HARD STOP PRESSURE
- CRITERION ANALYSIS i
ROW l COL l TSP VAit'E ACCEPT VALUE l ACCEPT ACCEPT l, 19 66: 02H ~ 2.0 _ -
X 1.84 4 .
z,_. X _..._ _.
1 1
19 E74: 01H . . 2.2 .
X l 1.68t T - X 1 19 : 80 - - 03H . '- N DF - . -.
2.04; a X s
20 . 10 03H - 4.1 - X ,
..J-20 17: 02H 2.8 : X : 1.62 >
20 .t 22 02H ' 2.6' X .
"1.64 ?-.
2 i 20 '22 03H .
-3.4 -. X l1.97 - .- { -X J
20 25- 03H .
. NDF: . a 1.801. - 2B X 20 -38 02H . ' 2.7 ' .
X 11;743 i : X i
6 20 c 41 - 02H . . 6.2 ' . c- 1.58 3 X 20 :484 02H . . NDF " . . > X
_., '1:.62 4
20 55 02H ~.'s 2.1 . . X ~ .131.62 ?
! 20 -633- 01H . . c 0.6 X ;1.451 ,
20 _ . 68E 01H 1-0.9:L .~ X -::1:75 c >
X
. 20 2 70 _ . 02H _
- -- 4.6 i ' . - - -
- . X 21178 L - X 20 ~ 77A ~ .: 03H : NDF . . ' T :: 2.00 Y ' ' X 1
- 20 '80' . 02H . - 6.21 ' a . , 11.851. - . X
} 20 >86 02H . 3 2.2 ': . L X 21.3dL :
' . ^ 1.O ' ,
20 '873 . 02H .. X c197 L. X 21.96 U :
20 : 87:1 ^ 03H - J NDF:o .. X 21 ;-18 3 _ 02H 14.0 L- X 31;701.2 X l
21 11:303 1 03H .NDP, .. 31.97U E X i 21 . s35 < .. 04H . L3.5:L . X J F1.81c X 4
21 ' '38r' 01H ;
= . 3.8 L L . . X 1. i1.591 d 21 3 45- 03H -
2.5:: . . . X - .L1;52?
21 . <::: 46V 03H < 1.61-. . X L' J 1.58C. e i
4 21 :
..c 4. 7 ' .
02H ' e 4.11._, .
X ..1;714
+
.M X
21 D 51. ' 03H ; _m 1.91 ' X .. J 1.96!i. J X i 21 =58: 03H . E 2.6 9 ~ . . X e - >1.65C X
, 21 :c70: . 03H ~.- / NDFf. D 21.921 ' l1 X 21 '"742 02H r0.6i - X .r 21.776- X
- 21 4871 02H 2 0.5 W .. X J 01.521:3 l-22 .- 18: 02M .-. 2 2.1+ .L X f:1;.65 M.
X 22 ::i 311- . 03H . 2. NDF4- . , 419214 z . X 22 : 833t~ 03H >
. . .iNDFE - .ll.89E. X i 22 m36 n . 01H . J 2.81.1 X .Jr1.73e" i X 22 339; ' 01H J-1:7 a .L X .>. 71.869 . . . X I
t 22 460/ . 01H - - )NDF-5. -1;70 ::M X l 22 .. i: 65 9 , - 02H - ..~ .2;31
- : X . 1.88 / .1. . X
- . =
22___i167! 02H 1 .J.3.31. . _
X J12.02'? ~
m X
22 ..$_73 6 03H . G.ND. Fi .. -
M 9 2.28 2 - . - X l
23 ^'9- < -
01H -- 12.9.) .1 X -- - r..1.69 E .
X l
l 4
4 1
4
. Table 1 Steam Generator C Page 7 of 11 I
i
?
i STEAM GENERATOR "C" 4
STRESS RELIEF HARD STOP I'RESSURE -
SLEEVE LOCATION HAZ CRITERION DATA CRITERION ANALYSIS 4
j ROW COL TSP VALUE l ACCEPT VALUE l ACCEPT ACCEPT l -
l 23 .. : 21 -. -. 02H 3.2.- X 1.71: X
- 23 ,J23 . 05H . - NDF . - 2.06 < . X l 23 '33c 02H . 4.7 i '. X 31.78
- _ X 23 < # 37 :' 01H '1.6x
. . X /.1.33s .: -
i 23 J45 . ' 01H . ~ 3.0: . X ..
i1.471 .
23 O- 46 ' ; 01H -
- . n3.7 . . X <
. s 1.49 V1 I
23 1 353-; .
02H . . 2 9_. ' . . . . X _.. .,.- .A1 791 ..
X ..
~
23 E- 614: ' 03H ~ NDF ' . . . . 1 ~1i761 ' - . X 23 X 31 84.; .. X 2.76 .- 02H P.1.. 4_.t L. ~ . .
4 23 s /78N 01H- t :11.4 ': 4
.i X 'J : t179 : ' ~
X 23 J79 - - 02H ; ;3.5- -- X J 2.22 : X-24 134 < 1 - 04H Ji NDF C ' . ?1;95E . : X 24 02H J.1 771 X
_13. 7/ ~ v 5.7 ' . f. -
24 !38 m 03H , ?1.21 : - .~1 X X_ }J 1.73 Ci!
, 24 t 39-.L ,,. 01H ..' J 1 :7 -
X _.
.,,. > 1 5. 8. ? . . . _ . -
24 139? j 02H .. J 2.3 : 7 X 31.73e 1 X i
, 24 x 401 2 01H J1117- - X .. 21 '.5 5 "-
24 -J_60 * , 02H ,.. a 3.0 5_, -
X .A_1 ;.36 F ' 4 . _ -
24 ,J79) 01H I J 01 .- . X Q1j74r > ~ X
> 25 ' A341 02H . 16.74 . J1 83.1 ..
m .
X 60 . . 21.77L ~ X l 25 01H ~1.0E. n X 20 t 671. . 02H .
" 2.3 2 - . J X 1. M.66 0 - - X 26 ,2237J 02H -
1.. 2.1 5_,n.. ..'-
X _L. 31.57 C ..t. _ _ _.- -
26 :425 J 02H . 34.0 :.1~.- X J ' 41.64i " 4 26 P34: . 03H D NDFs .. i J 2.01 c e X 26 s 435O 05H ' H3;26 '--' X Q1 8_3
. . _. L_ J.,i. X _.,
26 eF38;- 04H J4 3._0_i J X W 1.591. O 26 >t39 _ -
02H-.. '. ' i_N_DF 7 W .131 47 C . * . -
X 26 c 55- ' 02H 1 i V1 6 :-Ei 1 X . A 1.62 A 1
l' 26 "'60: 02H -.34;2i 1. X M1.82 L . X 26 . ?61A . 03H ' . - ? O.S i1 ' : X :J2.03 E c X 26 (64N. . 02H ' '32.80 X 7: kl .55CJ 4.
26 166J 04H C NDF~ .- a1.77E . X 27 ln161... 05H . :3.8:L - . X J .X1;79 ' .~_ X
. 27 , H19. / 1 02H_ .. 3 2.6.t _ s . .
-X .J.1_.5. 41 _. 3 i 27 ' 124 a 02H .J112.4 s i X 1.Y2;41C 'i X 27 e25L -
05H ~ . e 3.9 2 -- X a 2.04 e ' - X.
27 e '.32 D X .~._.J1;.811_. o; X 02H .. . _ J 4 6 M_.._
27 t>46n 02H . 54;9 0 ._ X .. 211.77a -
_ X-N X 27 .
558L2 01H
. J 32.4.C '..M1'.28 t _.
27 _.0 61E.. 02H- . ..s_ _0 51 . . A_.- X . 4.49s 27 i 1.4.6 L E.' X. . . - -11172.4 X
sd 68 G_ 0_2H --
l
. . _ . . - . - ~ . - - - - _ . . - - . - _ . ~ . _ . .-. - .- . . . . . _ . . . .
1 l
4 n
i . Table 1 Steam Generator C Page 8 of 11 i
i j STEAM GENERATOR "C" t
i STRESS RELIEF 1-
VALUE ACCEPT ACCEPT j RO'N l COL l TSP VALUE l ACCEPT I
27 :69=_ 02H.. . - . . .4.5 .- X . .1 93 ' -.
.' X li 27 .,72 02H 3.9 X. L 2.00 < X j 28 111.- 02H 2.8_
X . 1.77:: X
- t 2.6
~
28 J18 ~. 02H X . 11.
l 28 2. 8. . 02H .- ' 5 0 4 .
X . .
- 211J .
X .
28 :. 30 " . , 02H c 3.0 ? - . , . X . - 1.90 n X i
28 n51;-. 01H . . . 21.8: X ~ 5.1 ~.4 B L .- .
4 28 60* 02H : 3.0 x . X J 1.94L 1 X 28 . 61s .J . 01H 40.41 _ X 1 1,53) 28 : . 64 -E - 05H < :N DF:... 5 2.11 G ' X i
i 28 : 67J . 02H Y2.6 : . - X = 1 ;80 L _ X 28 c .701 02H . : 1.0 f ':. . :. .
X 11:31.54 C . :
- 28 -r729 02H L 153.7
- i X - X1;92C - X 28 - . 777 02H ,jj0.2 = , X .31273 JJ. X 28 - G79 / . 02H o3.83 . ~ . . X :< 1.9 E ' . . X l
' 12 := . . 02H :; 1.90 s. E -
~
i 29 4 ~ ../1.3 s: X X 4
l 29 . ?241 03H JNDF5 . .- ;-113 E '
X
' 29 v26S~ 02H a 3.0 :1 X 11.63 E. ,
4- 29 . V43: 02H .- .12.21 J X a 1;72w. - _. X 4
r 29 E481 ~ 01H "2.5 i. . , -
X .31 ~.90 C . .
X
! 29 :-489 02H n 4.1 . ~ X ' ?1.54 81. .; .
! 29 2551 : 01H ' E2.7 k - :. X m F1.680 ' X i 29 *i66L 02H n 3.2 X -. 9 1.612 , X j 29 a 68; 02H d2.t --- ! X a1.68L - - X 29 4774
- 03H .
J 3,1. 4. , .1._ X -- . I49 L =.
l 29 w?78C e 02H 11.6 C ' : X .4 h1172L + X l 30 _ 11 3 / 05H c 3.4 i.- - X . ~ 71.72 .. ' . X
- 30 01 5; 02H -.., J 3.~.9'.
X .n 2._1.;.G8 L, ~ ' ' X
! 30 ~ ' 218 k 02H 2 D 2.1: - X
. -.th67Q. .X 30 (22L . 02H _ t:4.5 t -- X ' T O.80 N
, 30 923s , 02H 1.84 g X (1.69f X 30 . 39? - 02H .J1.6 2. 1 J X .. 11:411.
l 30 242; > 02H -1;63 <
X i. < 1 ;42.E .
Qt.. -
i -
30 4 656 .. 02H 13.0 ..x X :1.821: E X
. 31 ,/161 02H - 1 0.68 . 4 X 21 4. 8.t . t..
. ' NJ.A .
31 2 31 01H X . ..11.74 E ' ' X
- 31 .3. 431 . 02H ..
f 3.2 :: e. . X 1.11;81 U!.O .
X l 31 (544 . 02H #3.5 .y X .k1 80 -~ T X
~
4 31 1 J 63 ! . . 02H a 1.1 t i X s 1.63 C .
31 1: 64 - . 01H ! O.2 (- i . - X f2.01? ' ' X
' 31 3 641. 02H 12.3 ? . X . > 1;43 8..
t 32 C21) 02H - 34.0 L - X 41.46 L J.
l l'
i
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.. - . . .. - .. .-. . . . - . . - . . - . . - -- ~ _ - . . . . - . - - - . . .-
T A
i 3
- . Table 1 Steam Generator C Page 9 of 11 r
i i
i a
STEAM GENERATOR "C"
' STRESS RELIEF HARD STOP PRESSURE SLEEVE LOCATION HAZ CRITERION DATA CRITERION ANALYSIS
{
4
03H - 'NDFh _ 2 2.131.._. . .,_. X .
j 32 ,2.3.._3 J. '. 02H 12 7. ? :_..3 __ X - a1 7.7C X _
a a
32 1436i.1 02H . ' 2.5 . ' '! X . A1.48E ,
- - 32 ..?41
- , 01H : i0.3 T X ? v1.86 ' . - X 32 M1: 02H 4.0 D i -. X 31.72 ' r X
2 4
32 347s. 02H -
5.7_z _. . M1.523 . U -
-- X -
X . _.
I e
32--- 454LJ. 02H 4 13.6i , , .
. . 41 ;78..L-- X l 32 Ma. 7. 5 < 9 03H e
_x.14.1 . - n X . 31 9..3....e .-
- X .
- 32 t? e 77 4 - 03H i J NDFx - .. X_ _1. 9_3 m~ .
X j 33 ::-1641 05H - :a 4.55 X - 21.96 4 M X 4
33 1183 . 02H - :1.81 X ~ 31.59 4 +2 33 <
0 22 : . ' -02H r 0.6 LW X f 31!.63
- s i 33 A55s 02H ..
- 4.S t E ^ X 31.92 J. X
.' 33 OW 02H m a 1;4F -
X pi.41;86 2 -
X 1 33 M 60 # -03H , A1.8 L 4 X kl .83W - X
. 1 61C _ ._,
3 33 M61E 1 03H U3.4? t . -X , 3% . -
1 4
33 RF64C 2 04H SNDFA. A h i'.M n. .X 33 c65C 02H ::-4;5 4 '
- X 132:14!w : ..
X j 33 E 694.: 01H 1m1L2a J X AT.75C ; X I
4 33 072 L.! ' 02H . N3.4 C. L X _ M. :164&X_ . -
i 33 J.73Je 01H . 9 2.6. t ' W X .El.l.?1 82 E ? .
X 33 ;?751 03H M N. DF.a -- ' ' x.1. ;80 C X l . .. . -
i 34 #0171. 01H 3 3.25 ' ? X %1 ~ 32s .
34 P19 C 01H ' A 3.21 a_ .
X =: J1.30R . a l 34 E29 . 02H J3.6 2. - -X- 41.72 L l 1 X 34 J.:'3 5 1 si 02H
. ' .. -- ?1.4.' 6
-X 31;47T 34 R38 1 01H . 3 2.4'a - X 11.21:49 W .
f 34 W38t
- 02H 72A v.4 X' 1:11.35'Cu F
34 438 %. 03H- ..L . 3 NDFJ ' , D 2. 12 L._ 1s X- -
34 _N 39M. 02H 31 ^. E . . . . X .
- 4. 1.149.
L. ,
._.3.
g 34 *$40 C 01H b :?2.6?
H . . . . t. . _
X e..
=.M.e.eg-.445 .
.e.
f i.
34 -W43.C 02H -. -5.11. :
. lJ . ' 5:2411. ~ l .
X l
3 34 M 491 5 02H- ~ 33.01.4. X =..;1 92 s i . . -
X 34 f r51/ N 03H JJV3.0 GE X 'r1.751 L; X i 34 e556 ,
01H .. a3.01 ~ J
-,. X 11;615 4 34- ..156 6 03H T Jlf 2.8 lE . X C 1;57Ef J 34 b 62 @ 02H _
. E 2 2.0 r - , . .
X_ s158i 34 s 6.5 0'. 03H . = M~N_.DF. t..Le _
. . u1.65C.. t. X . __..
i 35 M. 23. m - 01 H "sl21;85.~.11 .
X 31.6 t h I-35 AU25 M 02H 133.8 t 112 X =L O1;68F i _
X l 35 L i36L 03H s NDFA L . !. W 1;72 n .J X i -
t-i _15 C &52W 02H.- 3 2.9:5 ~ z.i -
X L.. Al . i.9. _1 L ~ X _
i I
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1 4
. . Table 1 Steam Generator C Page 10 of 11 i
I 4
- STEAM GENERATOR "C" i.
4 i STRESS REllEF i HARD STOP PRESSURE 4
SLEEVE LOCATION HAZ CRITERlON DATA
. CRITERlON a
< ANALYSIS i
?l ROW l COL l TSP VALUE l ACCEPT VALUE l ACCEPT ACCEPT 4 35 53, 01H . 3.1; . . X -1.73 .
X j .
35 - 55 ' 05H .-
- 8. 4 ': .. . . 1.88 : . X 1
36 ' 60 . - 02H - c 3.4 :: - X : l .8S m X 12;1- X X 35 . ' 71 <- . 01H 4 31.83 t 36 x18 _. 02H
. _.:0.5- X . J.1.81 s- -
X 4 3S : 2 7 -. . .
02H - - 2.4 . . . X - . 1.61 n.
36 -30; 02H -
- 0.' 4 - . .. X . 51.7 0 ? X i 36 ; 31 E O2H - D 2.1:. X -f:1- 59 : 1
- 36 ;339 04H - - 3.9 ; - . . X - 1
- 41.66 . . .. X
- 36 136?= ~ 02H . s2.5 i X
- : 2.04' X i 36 :4 13 02H -
"3.51 -.
X . - . "1.51 ;
36 : :- 42 ^ . 03H -. - '1;9^ :. X . r 1.88 L ~ , X 36 <x53:- 02H --. 2 2.5 : X , . 41.85 T . : . _
X
, 36 . ; 57 :. 02H 1 '.9 :- .
X E 01.853 ~ X i
3 36 ' L 61 E . 03H . A3.4:: X . Al 771 a . X i 36 ..J64/- 02H <
J 4.5 :- X . -
- !1.78 ? E. l.,.
X i 36 U 66 L , 03H <.. J 2.9 :1, -. X . /2;133 X
~-
i.
37 ':31E' OiH :2.5E X 101.769 X A2.01 - ..
~
+ 37 037' - 02H X t1.63 s
, 37 ::39n : 03H J NDF:: ~. J;1;89 ; : X
- 37 141/l . 03H . 2NDF- - -31
- 85 E -
X i 37 U47:a . 03H 4 2.4':n , X - . J:t2.07 h ...i
. X 2
i 37 *2491 ~ 03H s 42.9?.-..~ X a t .78 0 -.-- . X 37 a! 52 L 05H .
- 4.8 N D . - X . . J1.76 C . - X 37 cn 53 :! , 02H L.34.6; X . . 21,75 f -. X 37 r57-t.. 02H ' t 3.9 s . . X , ;:1- 80 L ?
. X 4
l 37 s 67t 01H . 12.5 E -- . X .- .; 1 '.79 -
X i 37 cc67 - 02H 1 11.8 E ~ ~ X 11.b9 ? '-
37 ~ 167/. -
03H 1 1 2. 7 5 -.
X _ 32.07 E -... X R 69 6 ' ' 02H : 4.31E .
37 4 X i1:531: E 38 . . A211 02H . - .J 3.6 L . X ~ 31.41:
! 38 C: 27:i 02H ' / 4.5 s :. ' ' '~ X 1 J1;672..,
X 38 L. K49 02H .~ M4.1: X " 31;973 X 38 -__X t 4 5 ; - 02H
. 14.5 1 . - X A2.13 E .- X 38 946L ' 02H : 4.61 i. . - . X .. J 1.58 4.
38 d 614 02H 0.3.51' 1 X L L 11.8111 X 38 4 62X 03H . . f N DF L . .-. '
- ' 51.94i. - X 38 . ! 6. 3.. 0 _ 01H .~ J51'_55 .~
X 41._.42 L .
38 . ! 63 E..; 02H X 11'.56 L . _
i
_[.2.61LL. :-
3 38 C 68L . 02H ' RL t.2.21 L' X - J1.551.13f 39- 13:23 ' . ~ 01H i4.0 :' X f a1.68!: - X 39 ' 1275 _. 01H 3.2 E . -s X 11.94 L .- - X I
P
- - .. . ~ _ . , . . _ _ - . _ - . - - - . _ . . , - - . .
1 l . Table 1 Steam Generator C Page 11 of 11 d
- c' -
1 STEAM GENERATOR "C" STRESS RELIEF HARD STOP FRESSURE
4 --
now l Cot l TSP VALUE l ACCEPT VALUE l ACCEPT ~ ACCEPT 39 351 03H iNDFt . 0.4 9 r X 39 /47E 04H ?NOFm . . . D 1'.86 a . 7 X t
! 39 768< _02H ~ ' ' 3.9 ; . ... -
X 1 t 2.13 s - ~ X 39 :70t 01H e :: 2.0 J1 0 X__ . .: 1.65 -- -- X
. a 0.9 3.; _ ' 41:.9 2" - __
1 39 D: :i70 E 02H X X i
X 4
. 40 _, 3._9
. ~. 03H :NDF:_-_ -. -:n1.89 E - -
40 ^ 441 .- 02H - : 1.8 L ' . X J1 '.68 .
X =
40 04H X X 11> 2 9._C ..
. i M731. .. -. . ~ --
'. ?.46 F 1_- 03H ~. 11;63 -
i 40 i 74.45 / X t =
1 41 .'64 E_
- 12 6 3 . .. . 01H Sb:-3.8 :: ~4 X l .J 1s79 L
~
X i 41 v27 c 02H , 3 0.8 y .. - ! X <1.58' .
(
41 d,s47 C 05H #4.4 t : 7- _X . 11.98s - ;
z
- X 41 6 a 53 C _ 03H 0: NDFs - . .<D1.95 u . X 41 48.%. 01H -
? 1.6 :- X -, O 1_.5 9_L .,. i l 41 ^ 259 ; J 03H H NDFL . .-- . 22 14c: .. s X 41 L670 ' 02H l! ? 1.42.1 i X e 2.07 ' ' . X 42 228 ~ 01H X -- 31;85i. ' X
. .. -F_ 4.0 c . . . .
! 42 m 41: ~ 02H : , ? 1.89 C -. . X
' i 5'.9 E. 7~
42 %* , 02H 173.8 . X - - el .72 c . X 42 01H .. . ?2.9 0 X . .!:1:89 3 : - . X 509 :
! 42 , ; 55.1 02H 11 13 5 ~
--- X ,1.86 e . . X i
42 - 467'- 01H L1;20 . = .
X 01:75.,1 ,
X l 43 030+- 01H - f 4.O N . . X J 21.70 g - X
< 43 345? - 02H . V4.0 E . - X i: 11.97 ' .) ~ X i
43 3. 467 M 02H ( D4.67 ^ ' X_ .' ? 1.67L- .. X 43 ' 1470 s 02H J;i2.5? M X ' L:::1 731 .E X
- 43 *Y50s .
05H R
. 4 9. & '
X _ . i 12 08 E.,.,,.
~'
X i
- 43 " 103 - . 03H 2 0.>7 W X - .11;64X
- .
i
_. ;37.L._- 01H 41;0 4 X
_ 44 .
L .11.40 ..s . i..
( 44 ' ' ? 44 E 02H t 1:0.6 4 ~ X 71:58x E.
i 44 7451 02H 134:4E -
=
X /1.6o i X l 45 3.37L ' 01H. .L J1;2 , i :.4.
X ??...1 ;.431. . _
45 142? 02H ~ 23.7 . ..- X . 41;90 - X 45 4 50? 01H ~ J3.9 7 c X 11.91 1. .
X
!, 45 01541_. 02H i.. kli7E ! .. ;
X K1. . 4.5_t
- 45 .1: 57 5 m OiH- 1.i t2.3 s E ' a X ,.u'22 E . X 45 i573 1 02H- ..3 2. 6.t i. _J-X :
. 1.87 C~. .
X 45 ..D 57M '~ 03H L F 0.6 C . .M X U L1.06 % 4
! 45 L;58< 01H ~. 7 NDF" . 11.60?: X 46 O.43t -
'02H iS. 2.1 L. .
X M.1.90.C X 46- "1460 02H ~ 64 6^ ~. X (1.95" - X l-
A s
Page 1 of 13 3-. . Tabic 1 Steam Generator D STEAM GENERATOR "D" STRESS RELIEF HARD STOP PRESSURE
! SLEEVE LOCATION HAZ CRITERION DATA
- CRITERION i, ANALYSIS 4
ROW COL TSP VALUE ACCEPT VALUF ACCEPT ACCEPT 4
2 ' 28 " . 01H . - 7.9 -~ .
1.67 9 X 4 2 .: '38 01H . . ' 2.6 0. .-
X i:' 1,71 ; X-
- 2
- : 391 - 01H :4~ -- .. X .. -1.785
- X 2 1411 . 03H .:'3~ X .. ~ 1;77 -
4 X 2 :72- 02H .
3.3 + . .
X - 1;71' - - - - X i 3 .--.-3165 02H 2.84 : X ' : 1.58 :1 ..
4
. .3 17 :: 01H . - . . . : 2.4 - - _ . - X : : 1.54 >. - i 4 3 , - ^ 18 :- 01H -. ; + 0.3 -E ~ . X . - --- 1 ' .81 ::. .~ X
^
l, 3 ' <20. . 01H ;---.J '.1. 2 = X . = 1.S4 3 ,
i.' 3 - i22 . 01H _ _L _: 0.3 4 --
X -.
.. 5 1.95 :E:-
X _
4 V36t J 1.4 J --. . a1;72s 3 01H .
X - .
X
! 3 463r 01H .1 6 N DF n. . - -
. . . - 1.7 C-- X
, 3 _
s377i 02H J.1 ; _
X m 21.681 t .
X 3 .. '89-
. 02H - - . L2. 5:: X 1, " n 1.53 Le 4 J G L .A 04H . ' t NDF 1. ..
. 31:349 .m X 4 E - 8 :: 9 04H .s NDF s . : 7 2 2.15 P:. 1.
X
. 4 - ?13 :n 01H - :t 2.01 X .. et.86 if X i.
4 1s157 - 01H i1D119: X .2 M 1 " 61 L ~ .
, _, 4 J 15
- 02H . iNDFs > .31 571 9 . X j 4 .. x 161 - 03H . . . . . 4 2.4 v- ~ . X D~ 21.5 { . -
.' 4 (19F 01H s c.1 % . . - X .11i51i . .
l 4 is25 L_ 01H ..
c 2.9, J. X N 1. 48;1 _. .
! 4 .. X-28en 01H 1 c 1.44 .. X bl.58U -~;
4 ,0 32 L....m 02H .,l. _i. s 3.7 3._. . . . .
X ' 21:539 .
4 4 ~~?33i 01H 1.2 1.41 ' ' X D t .591 j 4 3 1.33 t a 02H ., i 15:- r X - :41 7 9 . ~ .
. X-4
.4 :354. 01H . . . . 14 ;51. -. . - X - : 1'.93 E t X 4
i
._. 4 ?:5 F ~ 01H ;
- ' ' ~ 5 Ji/.1f : .
X . d. .. 614 1 4 . -: 50 ? . - 02H ~ i NDP - - ,.:.?1.8 3 < X
- 4
- : ..: 57 l. 01H ~ 72;4i : , - X :51.55N 4
4 161':: . ~ 03H ;
. i 2.3 " ' . X 11;84 L .- X 4 J 63 01H n ?-NDFs. -~ 21.76E:1 X-
' 264;J 01H 4 F2.9 3: X .. J 1;7 E 3 X 4 ;4 69 C 01H .. f NDFL .
31.6S C - -X
, 4 J71?E 01H .. 3.5:Li' X -. . -:1'.66 F .1 X i 4 :o:842 ' 04H D J NDF L D 128L.. :; X 5 S t. .. 01H . ~ .1 2.72 , . X < 11;98 ta X 5 _.510e> 01r1 13.6 L i X J1.642 C ;
. 5 ?" ! 13E 01H <
90:36. . X ;-1.921 . 1 X
- JJ 1 627 7 5 , -..e1Be 1. 01H . . -- c1.8 E J --' X .
- 5 220L 01H F O T -- . , X 71.54?. -
5 (2 23 C. 01H :--
.~-.: 0.9a X ' :1.511 -
1 k
4 7 =* -p.+ g'
4 1
1 1
i . . Table 1 Steam Generator D Pace 2 of 13 i
STEAM GENERATOR "D" 8
STRESS REUEF HARD STOP PRESSURE SLEEVE LOCATION HAZ CRITERlON DATA CRITERION
- ANALYSIS ROW l COL l TSP VALUE ACCEPT VALUF ACNDT ACCEP'
, 5 2. 4 x. 01H 4
-1.1< _..- - X . . _1
_ : 6_6.t..._. 4.,
X .
.; 25 .
5 -
01H . . . .
.!.8 n X :
. ._ 1 4_8. _L ._ _ -. . _ . . . . .
l 5 26.2 01H .,., :_- 0 8.._1 _.,_:_ X ... _ J_1 5.. 3._?...i..._.
.5 27- .
01H .V
._. ' ~ 2 3 E. . X _. . ..
....%. ,. 6 ' .. .
5 29: 01H E 0.7 X .
- .M. , . 4. 7 !. _ _
j 5 .. U .9, 3. E _.: X
._.a-29 . . 02H . . . N DF ._ - . _. . . ._.
I 4
5 4- e34 s _! 01H _. ? 3 4 J .
X -_ ..' 4_. 5 9 ' .~ . , -
.' 5 63 C._ 01H 1.33-..,' X .
~ 11.82 e X
_-. 2.9 E 5 ! 64'- 0?H +
X Ea 1,69. E._,. ; X I~ 5 ; 651 - . 01H > A NDF L U .r1'88? , , . X 5 i2.5a..; '. . -
1 m A7_0
. 02H_ _ X... .M n 1_.6.. 4_.3,,.
5 ! ?77K . 01H ~ J 3.8E ~ .. X _.. . L....:1.471, .
5 -87 ' 02H 3.3 : X - - .
.',_ :1;77.c -
X 5 1881 .
02H ..._4 2.4r X 1 /1,77 : .X 1 .,_ _ -
6 .
-.J 1 ._,.
04H .
21i7 a . . .,
X ..
..i,,,,?,.1_5 7.._^
6 9 < . _0._1.H : 13 4 -_ -
X j ~21.53 K ' ~.
~~
6 5141 ' 01H J 42n - X 1 L1.97i a X ~ ~
! 6 ~ I~I 01HT 1 ~TdI ~ X l > 1.8 I~ X i
6 x29/ ' 01H _- $2.10 _
X . 11 ;.84. ;.,_ ..
X -, . . . _ . _
l-
._ 6 = 33: 01H v2.1:2 -
X 1
- 1. .5..1.. 9.__
. . . _ . . . . - _ 4
~
6 SS8-. 01H ~
< . J 2.2: _ _. X 21.56 ~ 1.
4 e k 56"~~~d3II' ~~~5 57~~ X W 1.63 i ~. _., _, , _ . _ _
> . ._.6. _._~ 65 /
01H . m 2 5 L.__... .. _ _X_ .. .
- 1.6._ . .
6 C..s .
X .
r _6_ 5662 , 01H J_.~R NDF,e . . . ;
131L72 M 20 X-6 --.29c 02H . , 3 6.4 >l 11 .31.71t , X .
6 '69: . 03H udi. 1 X :e M.992 . X l 6 M3C 01H 1'(NDF1.1 -- 1r1_.65_4 . . .. . ._ 2 B _ _,X. ,
i 6 ~ 177 03H 13 ;71._ t. --- X .1 0._ 1 673 i_.L._ X . _.
6 ' i 825 _
01H =.. J 3.83 X s1.55 U = ..
l 6 L183 3 03H ' 11.5% . . X - 11.647
, 6. .s._18_4.1_J, 02H . 2 41 1 X . ~. . 1 4_9...,i . , _ . - . _ . _ . _ . .
i 6 '
E85 C 02H i 2,5 :t .R..,.
X - , -. f 1.6 5 .
X _ ._..
7 .J41? M 01H - ~ 10.9 J _. X D 31.64E l-7 e4.n 04H . 13._._2.L _. X 2 t._1.;._82 2._; -X r
7 S SL 04H._ . . _c.4 1 r ..
X -
. 2.t 8.1?_ _._- X
. i6 J_:. 01H 7 T e4,6.x . .
X .1 D 1. . 6.._4.U....,. .
7 L.0130 03H M NDFs _., .
- 2. 1.87 A T.
X 7 ~~ x19 C _ 04H V ND.Fi_ .. ~ ~ ~ .J178s 1.
X i
7 3 25._a 2 01H
_2_.0 8. _1 m._.
X ,_. ._m71.E.,_ -- .
X ..
I 7 ,32631 01H ' 7 0.91 J - X i A1.78 O i X t
7._. .M32_E 01H A1 6 L _~ X 1_,s1176 C /, --
X , _ _ . . . .
l 7 334J D 01H .'1 1!41 J Ti X .1 1.61f J l
l I
f.
s , -
_ -.~,.,, _.,. .~.--..... .... _ .. ,.,
. . . - .. . - .... ~ - . . . - - - - - - - ~ ~ . ~ . - -- . ..-- - - -
i
'. Table 1 Steam Generator D Page 3 of 13 i STEAM GENERATOR "D" STRESS RELIEF HARD STOP PRESSURE SLEEVE LOCATION HAZ CRITERION DATA CRITERlON ANALYSIS i
I ROW COL l TSP VALUE l ACCEPT VALW. l ACCEPT ACCEPT 7 39- 03H - . - 2.8 - X . -1.76 t - X
- 7 - -.._. 4_.1 O'H ..
- 5. 2._ .
- 1. ,. 6. 3.. : .
X _.
l 7 .
46" - 01H . 03" X 1.48-7 ' 165 ' = 01H ~NDF .1.74 ~ X
/
4 6. 6..:._ .-
01H .
N..._D. F.. . . .._ .
,. ~ 195 : . X 7 68- O '. H . ..
- 2.3 -
X .
1 8 2 :.. .
X m .
7 72 -- 02H 4._-: 1 ;._8 : _ _. X _. 1 72.-. 4 X - . .
_m ..
~
7 476- 01H . .
- -_- 2._;-., X 11 74 ..
. X-7 . 86: - 02H .. -- 1 '. 5 t - X : '1.59 : -
8 t4- _ 02H : 3.5 V ._
X _a..1 73 E > _ . .
X 8 -81' 04H.. . -- N. .D. F._. , ..._ . ?..1 6. 8. : ,_. _..._ X = _ . _ . .
. -.8 _. - < 9 1,. 01H . ..
t 0.9. :
. __X V 1 9. E _
X 8 . 413:K Om
- 11;4 L ~ . o X . J 1.91 ..- X 8 E
- 1571..:--04H M. .,? TNDF ..
B _. a1 98.3 . _.._
X 8 W 2.3 : '; X
...'2.1 R . 01H--- .
. . . L.1 9 21 _. -- _ X. . ._ .... . . - _ ._
8
- 2 2 5 ~ '. 4 01H J 0.9 c - X ~ 11.43 ' -
8 t27o . 01H 1 ,16;7/: .f .7 11.65 L L X
8 1 2 8. *. '. 01H n.1 ' 4_' _. .M X ;
.. 1 8.. 21 . __
X , ..
i 8 i 3.1. ; : 01H
. . .E / 1...._ , . . X_ . . /1...8. 4_.: . ..
X .
l 9 ~ A350 01H - . . e 3. 7. - -- X - t1.7a X 8 ._' 35 :._. . .
02H J2 9L.._.
X 11.64.1.. 1 _ . m 8 - 4371 - . 01H .. ?4i X . -1;76 e X 8 438H+ 01H T '. a 5.9 ~. ~ . ~ < : 1' 75i - . X 8 5571 ' 01H .
-..E N. DFL_
. . i. ._i t _8 8.' 4. . _ .X _..
8 e60 t 01H N O-. F i ?_ _
.: 31'.771 ' X 8- 3 67 r i, .01H '.4!DF-E. -
1_1;74_1_. . .+ .X -
8 _
- 68'
- .t. > 03H .
- e NDF
a._4..7.;. ~ . mX ~ ~ = 1. 7. 5.T...~.'_*
. J 1,68 e X ---
8 - /731 .01H -
--X l
8 7791 01H . 2_2 7. 1 .. - X :
21.72 C ~ X l 8 R 82 02H . a1.5E ~ X . 1 29i.
. . 8... i.. *.8_5 i - 02H 141..7 21..... s . . .
X ..a_l.~.5.C.
8 > 590; 01H 12.61-. - X - t.1 25 s -
l 9
.~
x ..s 2. i ._ 04H
.. : ANDFe- .
~. G132 L . X l 9 J15K 04H a1.7 L -
X '- 1.96; X l
r 9 ' N7 L ~ 01H =E 1 2._;.4..E . . .X . J 1.93 2 . . X
^ 13 n. - 01H 9 O l'.6 i X %1:681..
. X
~
9 .c20s 01H .J_1 4 E .
. X ._. J1 721 .
X.
.. 10.74 2.
i 9 ., 526t 01H X 1 584
. m 9 ./ 33i2 01H .' ' O.7s i X ,[ i i1.91 t M ' X
' D-381 1 01H 74;42 X-
~
9 .y1.81s X 9 : . / 67 .1 04H .4NDFi - -1 '.81. . X i
- .- .- - . . . - . _ . - - - . - ~ . - - - - . - . - . . -- . . . - . - - - . . .
i
- ' Table 1 Steam Generator D Page 4 of 13 STEAM GENERATOR'"D" STRESS RELIEF HARD STOP PRESSURE SLEEVE LOCATION HAZ CRIT 8:RION DATA
,i CRITERION ANALYSIS ROW COL l TSP VALUE ACCEPT VALUE ACCEPT ACCEPT 9 . ' 7 2 . -. 01H -- NDF1 . - . J 1.68 : X 9 84^ 02H - - L3Ji X ~ 1. 6 5 < . - X 9 :86. 02H '
. - . X > 1. 6 ' ., ~,
9 90 : . 01H 2f- .... _ X -
z, 1.69 m . X ..
10 110 < 01H 11.3 ; - - e X 2.15 X 10 . -12E - 01H 11;3c - .. X . - 1. 5 5 -
10 .
15m 01H -. J1 A 1. ~ ~ X - :1.53 s J -
10 115: 02H
NDFu .
. J ' 1;8..1. t..:-- .
X
- 10 '
- 174 . 01H - . 1.3 i '
X : 1/133 - X 10 21- 01H .
-1.4* X - 11.62:.
10 '21 - 02H . ; NDF; 4 .. .< .11 ~. 81 e X 10 ,J251- OlH : r2.11:1. .
X ~ :1.561 -
10 : v26C. 01H ; 0.8 s . . X . . 11.4 8 : . . .
-10 130e. 01H .
( 1;4 :, , X !.:O 11 J 1 c . . X-10 431: J 05H :NDF .1 - m1.521- ' X 10 133 a 01H :
2 1 R : - .?,. X.. ..: 3.. 1 62,1
. 21.41; M ._
10 Pt37 1 01H ;4'.3 ~ MS -
X 10 ? r 4 21. . l 03H ::4.5 L . X - t1.661 1 :. = - .X -
10 . :62;. 01H ./ N DF r ' . . J:133 - . X 10 ~' ~ 88 3 ...: 02H : 1.9 J . X 1.
n.. 1.1.44 0 11 t8-- OlH n M 2.3 L 1 ^ X E 2168 % ; . X 11 > 116?J 01H . s 0.4 E ' t X 11.87 -: 1. t X W 171 11 01H i 0.3 :: -
X J,m_.
1 74...F. ,.- .
X 11 ._ - _'211 .
01H .2 s 0.9 0 E X J '31.831 M X 11 -
- .F25- -
02H L3.5 > X ~ d._.720 : X 11
- 22 8 . . 01H-- 3 2.2 :r .. . . . X J:: :51.7L a X
.- 11 : m 29C. 01H ..
-=, . . 324 L .f X -( f1.7a -.14 X 11 " 3 9 E. 04H -- :iNDFC 1 - 11;78 2 x . X _
11 L 154 1 01H :4NDFe . 9 . 1;78 . X 11 e 54 ? . . 02H 33 3- A - X : 1.65 !: X 11 M 6dlJ 01H ...rNDFA A ' c1 J 26 , X 11 , 2 81i. . 02H s1;5 E - X 11".86L - X 11
- l 821 _04. .H_.. ...' _ a 1 8. _:n .
i X .f .c l_i7:.1 ~~ X _ _. ,,
11 J t': 87J 02H ~ --i: 1.4C. . X . n1.51A 12 e a72 . 01H .: 10.51 i X '
31.99 n <
X 12 .Ja 3 4.. 01H i .;:1.5 t J X E 21.67C ~
X 12 Y20 t:. ? 01H -.
?O.4u X ~ ? 1.921.. ? -X 12 5 326 O 01H " 5-15 a X 11:433- '
12 ~.T28n. 01H . .,.. _2, 5. 4 +
X --. L1361 , _..
X -
. 3Ae ~ 1s 12- t139s 01H _. - -
X 1.6.C-12- . 348E 01H . -1;7 a X d.:1.469 12 ;Ji3 66 E _ 01H ..O NDFCEl 1. L 1 48 2:> -- - X
. . - _ - . . . - - - . - - - ~_ --- - - . - - . - - . . . - .~ . -
i I
4 i . . Table 1 Steam Generator D Page 5 of 13
,r i STEAM GENERATOR "D" STRESS RELIEF i HARD STOP PRESSURE i SLEEVE LOCATION HAZ CRITERl0N DATA CRITERION ANALYSIS J.
1 ROW TSP VALUE ACCEPT VALUE l ACCEPT ACCEPT i
- l COL i 12 .
- 61' - 01H , ~ NOF - - 1.72 r X i
12 -
65 : . '. 01H N.O. .F ._._. * ._ _m...1.85 a_._. ._ .
X 12 70 ... 01H 2.84 . -< X ,.v 1 661.-.c .. X
= .
12 70. - 02H 11.7 . . X ~ 18. 4 X i 12 . ??O 03H :3.3 X # 1'.88 : X l
12 862 02H . 2.3 ~ - . X :1.61b :
1 13 >
- 81 01H 2.2 > .
X . n1.03 - -
I 13 8 - 02H '
... N D F ~' - . :31.54 - ~ .
X X
- 13 ~ 8.". ' 03H ' N D. F:. .1 74_.n
- . . - .. . . x 4
13 .
?9- 01H .c 2;3; ~ . : X . , t 1.62 L i 13 :10 e . 01H . 40.3! - . X . < 1.75" ~
X i 13 , 2137 01H =
- 21 ;'4 r X E 31.81n-. J X 13 ' 11 3-. ' 02H _ - NOF1 .
.. . _ '_ 1...63 0. . . X i 13 115s. 01H 1 0 2.3 X . 31.5:t 2
13 4150 _02H .
' NDE . . J . D;.-1,68
- . X 13 > -18 > ~ 01H .: 0.61_ _ X i. ;- 1.4 9. ..
4 .
- i. 10 _21 : 01H L13.11 -.i X J1;63.:._
i 2
13 . s21c. 02H - . / N DF K '.' . i . . ; 1.69 t ' X e
13 - 22 _! 01 H .. ~. 23.1k X <1 E1.66 -L . .. X l 13 - . 24 .. 01H 13.4 a . ..
x _.,i 11.7::i .i.
X
! 13 30t. 02H . (3.50 X '. 31;86 $ '
X 3
4 13 ;321: 01H .. s 1.9 < X i.11'.711.~ . X
! 13 239i- 01H u ~ E2? ^
X *1;621
,- 13 i52 k 01H t NDF' . -- . . 21'.63 L_4 -
X
{ 13 >60? . 01H N DF "_.a.,_ . c 1. 78 i _. a .
X l
i 13 ~ ; 60 > 02H - >2.41 X J ~ 31 ~.681 a X
! 13 . J 64D 01H -NDFc 11;73 L .. . X 13 . 65 i 01H J < 3.11.1 E X . "1;72 ma .'
X
. 13- . 691 01H -. : NDF:s - . . . . r I P8 3 1. X
! 14 D7: .. 01H o 0.9 : . -
X _. 21! 87 U . . . X i
i 14 . 017 .:._, 01H ,- "-.2 3.. 7. - .~ X .. .31 69-( _ - . . .
X _.
14 - 130 1 03H . . . _
a: 2,3 i . -
~
X . L 31,65 3 E X
-14 -.
132 C 01H .
.__1 5 X i. 41.61/ ..
14 T501 : 01H ' ' N DF.E .. . -
~71.65 t ~ X
.- n1.75 :
. 14 ; 160 L 01H LNDFC 1 .X 14 . . ; 68C 03H ." 03.9C~i-X- i a t t71' . .. .. X 15 .; 2_ 4. : 01H .
0 0.8 L ,
X 9 1. 7 5 t . _. _. X 15 s. 255- 01H .. - X 3277 EL X :
3_.1 9. 3 L . .. X 15 .._1.. . m. 01H 3 2. .6.. E. M _- X 21. 613.
15 .i s9 C 02H ~:r4 5 C _._ .
X i a l 5 9.. t _~ ..
d
_15 3115* ASH . . ,. .J 4 21.. .. .
X E. 31.76 5 X
~
15 015- o 01H = . 3 0.11 X J 1._.88. ._d .i -X f
r .-. - . rv-> , y -
,. .,,--mv, e..e,.,,.r...y,w, n.w.w,.+.e,,,, .,w.,,,., - =
- . ~
4 ,
j 4 . Table 1 Steam Generator D Page 6 of 13 !
4 i
4 STEAM GENERATOR "D" J
! STRESS RELIEF 1 HARD STOP PRESSURE
^
SLEEVE LOCATION HAZ CRITERION DATA CRITERl0N
- i. ANALYSIS J l ]
ROW VALUE ACCEPT VALUE ACCEPT ACCEPT COL l TSP l i 15 117 02H E 2.4 : __. - X_ *
.. J.m_1 7 2....a X
15 <
. 21- 01H .
1.9 s X ..~ a1.53 ' .
15 - -214' 02H . . ;- NDF : . . . . . . . <1.7c > X 4 15 J 28 ' . 02H- - .
1: 14.31 ,. 7 X : 1.65 c . . X 1 15 ..;29t 01H ..
- 0.1' . X -. . t 1.77.
- - X 15 '3.8- 1 X :. - X-
< .._': 30 _ ~ 01H 1.-
. ::. 2 1..9. . . .3 .
' 15 1321. + 01H . .. - 2.2 ...... X <
X
- .1. 96 .
15 -46= 02H . xl;7 l -- -
X .- t1:36 1-. X a
15 47- - 01H NDF'E- -
-- 1;76? ~ X
- 15 - ' ~ 51 - 01H ~NDFu. : . .,. .1:.9 2 c . . ~
X 15 . "59E. 01H - - NDF i . . .
- 11:76i X 2
15 2 601 -
01H ' . _' NDF f . :11.76 ? --
X 4
15 s651 .. 03H :2.3; -m. X J1;877. t X .-
15 . >66L - 01H e NDFV: ' 1 , 1?1;74 .. X l 15 ' 68 :: - . 04H .3. 2.8 s .1 X F .-. 1 6. 6. L. L X L, 15 473? ' 01H J NDF : . ' - . . . e1.79 ? X
! 15 174 :- 01H . ?-2.3 K - X .1 (1.63 L 15 181 r 1 03H .
33.9' - X 2:E1'.75 M K X i 16 f6: 04H 52.61 -
X 22.23n : X
, 16 -
7 1 _. 01H :
0.,27
> X . _. :1 :.66 E. A X
- 16 . - 91 . 02H - . 4.41_ X .. 11.68s .
X 16 .110e. 02H ~ ? 4.8 E: -. - X ~ 11.73 L X i
16 .. 511): ~ 01H . - NDFL1 f 11.56 E '. -
X 16 111L . 02H " i NDF:4 - 111.937 . X 1 16 . c231- 01H :;0.9 i X . .. J 1.37 4 .2 16 2 4 >-- 01H e 1.7L.. i X 51.6 F ' '
i 16 ,x24J, 02H rNDF1 : J x1,8 .:-- X 1
16 D 25 ' .. 01H ... L 2.7/:: .-. ..~ X J31.46: M i 16 2 25t ' 02H _
4 NDF" J R1 '.5 9 r , . X 4
1 16 231 L- . 02H ...L44'-
. X ..J 1.57 ti:
16 f411 01H 4:2. 3 1 . '
X ,.. 21.584 5 16 . J:491 01H O NDFt i; . E 31.8' ., X t 16 . 1-700 .. 01H : , ? NDFL .< . 31 8.81.s .
X 16 ~o p 77L 04H 1-- NDF t . . ~ ~. . 51.89 : X d
a 16 3..83.:.A 04H .
?NDFe? 11.944 f.
X 4
16 J-881 02H - " 21- -. - X
- J , r1.34 5 .-
16 ?89; 02H ?1 ' 81 .
. X E1:.E5 0 -i 17 - V4e . 01H ? 3:4.5 C . .. '
X . a15761 ' X
. 17 f 37 E . 01H e 2.5 :i - -- X -...;1 . 81e - X d
i 17 i J. S t._.i 01H _ J1.61.u .
X ' ~ "liS9 f -
1.
17 , D::15 s . 01H ?1.6 C . . X . _J 1.55 :1 1.
i 17 . -15 02H ~ R- N D C E J E ' 1 -. 86 ?- X l n
I 4
. . Table 1 Steam Generator D Page 7 of 13 STEAM GENERATOR "D" STRESS REllEF HARD STOP PRESSURE L
SLEEVE LOCAT'ON HAZ CRITERlON DATA CRITERION ANALYSIS
~
now l Cot l TSP VALUE l ACCEPT VALUE l ACCEPT ACCEPT 17 _. :24 01H ,,,,,,,,,_2.9,,,,,,_ X _,,,,7 1. 7_7_,,,,,,, X 17 -25' 04H - NDF t. 1.73 ':. . X 129 - . . 01H '3.7 17 .-
X 11.781 -. X 17 39' 01H .
-2:7.. 1 X - - t 1.52 i . -
17 . r45:t 01H .-. : 2.91- X . :: 1.5 .: .
17 c55- 02H J:51 .. X 11.82' X 17 - 65 .. 03H .- ' 3.6; / X . !- 1 63 E.
17 73: 01H c 2.b . X 21.73 D '. X 17 47 3 ': 02H X .---l 11.87 :.L X J 1 3t .._-- ~
17 :
87i 02H . - 1.L ' t X J1'.63 c i i 18 a5 .. 03H NDF~ ' J1.72c 1 X 18 > 61 , 01H : Ox . - X ' a.1 - 82s . ..
. X 18 -
8 E:- 01H .S2.8:1 X .. 21.614:: . . ~ . .
18 :
18;; , 01H - - - . 2.4 E 2 J .-
X . 11'.81G: X 18 '19n/ 02H .R.NDF ? - - :A a1:48i 1 -- X 18 1: 216 : 02H _- H 2.6 E L A X J11.851 ~ ~~ X 4 18 - 26 :: 03H '4.41
- - > X . 11'.06 e 18 '
29> 02H - 44.2: X ' 71.56i 18 ':42' 03H -.
.a 51. X 31;92i? X 18 -
441 02H v3.4 L X ' t1.76;: - e X 18 t S41 01H DNDF4 . 21.6 L . L. . X 18 55> 01H ~. R NDFi E ~ ~ -
~ ' A1 ~.68 t X 18 .-!59: 02H - E 2.4: X J1: 97 4 . - X 18 + e61o 02H . . . . E1 :1 & .. X '! ! l l .71V E W X 18 '65 01H c NOF:; - 3 1.647' X 18 ,:66a 02H .. i 1.6 : I X ~~51 - ,72 i:i .. . N X 18 173r 04H - ~ 54.5 ; X - AllG6C X 18 077c 03H . OSC ., X :JJ 1.73 C .X 18 ? 84't 4 02H C2.4t ' X . . L. s1:.41:
- 12 :: .-- 01H - 60.94 19 X X 1:Jc2:45b 19 '34n 01H . _: 3;8x X ,.! !. 61.8 t - X 19 c401 01H . P S.1 131 926 . _ X ~~~
19 ':43t - 01H <NDF- "1.65 E X 7~
19 .Y. 66 01H . . . T[~~... . X V1.7 3 E .- X 19 1674 03H -
,'W '
X . ..el ;79 : ,
X 19 e 68 ? " 02H J .iJ 1.8 6 _ .. X J-.11;8 t l. X 19 u?81 02H ~ %3 4 .~.. - X n1.531 ' '
~
19 :. 084L 01H s t1 :17~~~~~ X -- 41 333 20 7 8V ~ ,
01H =
~ ::3.3 8 . . X '11.815 .-
X 20 ?10L 02H 1. M 2.81 . . 2
~
X- . -- N1164 20 ^ k161 - .- 01H 11.7n ' X 11.73i . X 20 ,"17E 03H J '4.6?. X .. T1.63^
- . --_______--__J
j i
i t
i . .
. . Table 1 Steam Generator D Page 8 of 13 l
STEAM GENERATOR "D" =
. STRESS RELidF HARD STOP PRESSURE SLEEVE LOCATION HAZ CRITERlON DATA i CRITER10N
. ANALYSIS i
j now l Col l TSP V.LUE l ACCEPT VALUE l ACCEPT ACCEPT f
20 c2.2 X
~. 2. 3.. -. ? 01H
.- . _. ~. . s 1. 48 0 . J 4
20 :26- 01H '
2.13 1 X .- T.1.55 O 1
a 20 , . 30 4- 01H 11;5 : . . M X- . 3177sllJ . X
{ _ 20 , 033 t 01H . . 1-.8::. ' X . . .- 4117 7:L . i. .
X i
4 20 r 381- 01H -.. O.51 ~ . .
X 7 41 88c . -. X 4
20 t 40 .? .. 01H . '3.5x X : 11.77 J. .; X
, 20 -481 01H . .:NDFi . .. 1.969 X ,
- 20 - 51
- 02H 1 e 0.6 . ' i X .' r 1.79 :" X
, 2') - 59 01H :NDF= . . 11.6 ^ i J X 1
e 20 t 65 d - 01H O_2.3 L_. .
X i ' ? 1;7 C '
=
X i
20 -
65- 02H - . } 1 '.5 E i X . O1.74X . . , X
'. 21
- 76s i 01H 41.6 3 W X i. _t1 L_77a 4..
X
,! 21 101 01H i33t. X i 31.57 t . - ,
- 21 J10 ? 02H .14.57 ..* .
X--
.J 1.85C J X
, 21 2116 01H ;0.14 , A X : e 1.993 91 X 21 h .17 A 01H , t 3.41 .
~2 X t1s4913::. .
21 : 919? 01H . . St.B' a X - . . ll:.63 t -
4 21 ' s23 L 01H ..' 73.9 k X .. s1276 C' X i
4 21 J24? .
.. 01H 3.6 s
. .2 .
X 51.64 s .. .
21 4241 02H NDFtJ .
s it .66 n. J. J. X 21 02H i X , 31 655 X
' . , - - -J26: . - .(3.4 if.
21 < m.::312 04H ' T NDFi ~ ~ DJ1.67 e si X
! 21 E35 c .. 01H . > 0.9 a . - X . E 11.6' :
j 21 . t 43 '. :^ 01H ' E NDFt E ' J~. 31' 920 m X l!J12L i 21 ' F48 i ~. 01H t NDFc X E:1.45 % n.ll .57C JJ
~
21 s 266? 02H -
X i
21 .375r 02H 11'.8 x ' ' X L ~ 31;67As M X 21 ~ ' 81 N 03H . :: 3 2 0 . . . -X W 1.82ERJ X
'1:22 i s
, 22 c:11c 01H --
X .. .J 41.78 ': . ' !.
X 22 . 314u 01H . D 2 4L ' X .. 21.51:t
. 22 : v15 . 01H 1. < 1;6 9 . . . X _
.: .1 ;47a .- l l
22 ' V176 . 01H m.~ 3 0 7. e... ' ~. . ,
- X ;. . 31.57 T _
i 22 ,.. ,. 01H- ' 0 0 4._1 . '
X . 11.680 X-a' 22 W= 3183 22: 1 ' 02H . . ! 2.7 '! i - X 2 2:.1.291 ,1.
' e23 H - 01H
'~
l 22 1. J 2.14 X . !11;55 _ ;
l 22 3380 01H ' 13.3 t. X .
. N1.45 F 22 4BLJ_ 04H .J NDF6 .. ( 1 f1174 L -
X l
22 - - 548: ' 01H .-. a: NDFs . n12751.:ll.< X 22 4 9 , 02H- X
_. 21199
?
.LL 31.161 A- . '
, .m . .
22 . . SS1 C 02H
- : 43.2 t - - X X1;71 .- X
- 22 1.? 62 E ' 03H i . 14 '- J. X ; . 71;6 7 i X
! 22 263'. -
02H . . 5 2.6 4 & X . : Wi;1'.C3 2 1.
4 L
I
, . - _ . - . , ~ - . . . . . , - , . - , , - _ , . . , , , , . - - - - -
. -- . . _ ~ . - - . . .= .- - _- . - .. - ... __ =_ ..
1 4
i .
j
- Table 1 Steam Generator D Page 9 of 13 1
i STEAM GENERATOR "D" 3
4 STRESS RELIEF f
HARD STOP PRESSURE SLEEVE LOCATION HAZ CRITERION DATA j CRITERION 1
ANALYSIS ROW COL TSP VALUE ACCEPT VALUE ACCEoT ACCEPT
, l l l 22 r69 02H- - - - D 1.6 < X . . --1.764._,. X i 23 ? s16- .- - - - 01H -.: ~~ 0.3: 1. .
X - 11.73- .. X
- i. 23 , 517- 01H ..
'1.1, . - X .01.477
! 23 .. 17 ~ 02H r NDF~ .-- 1.8s : X
. 23 t18'. 02H -
23~ >
X :.1.461 ~.
23 ;30; 02H . . 4.1",- . X . . =1.86 ? . . X 4
23 : ?32-. 02H .; -4.1 .- X . 1. 71. .~ . . X V 1.9; X X 23 i_'38 ' 01H
... . ' 11t?8 4 ~
23 -
1660 03H ~ !4' X .
- 1.68i X
- 23 . .66 04H ...--5.8
- - .
- .a1.68; ., X
- 23 4 66' -, OSH ::NDFE _... D 0 6.- 9 9 .
X 1 23 ; 172= 02H , s 0.9 > . . ' X T:11.99 L . - X 4
23 . > 83 : 02H -- . r 1. 9 / . - . - X ' ' . - 1.44' L 24 01H -- .. ;2.15 E X . . T 1.63 ;
R83 I 24 .
'9E .. 01H
.. 1: 3.6 ' -
X ~ . 71.93 s X
. 24 ' 410 E. 02H- E = N DF'.s .-.: .
.L 131 81L-. i . . .
X c
24 L 14 ;
02H e 2.wS i X W 1.61: ..
24 - ? 21 s . . 01H ? 2.8 L.- .. X 21.52 J
- 24 ' 21 , 02H -NDF; . _ . A .68 x - .- X
, 24 ^24 01H .y2.1t X ; 11' 57 : .
- 24 -c28' 01H F31 -. -
X ?- .41;71; .. X l 24 . 35 : . 04H
- v 3.B o X . . J 1.717 . X 24 ::354 . 05H . . - NDFi . E . 31.96 E. X
.4 lE$368 01H .- J 1.4 := X 31;867 R X
! 24 S372 .-. 02H . . # 3.5 4 ..
X . 31;494 .
l 24 .:: 40 ; . 02H ' u 1'.6 - X ^ 1'.654 X i 24 2491 . 04H _ NDF a . . g . c 2.14 : . . . X 24 ~.1 511 _-
~ 04H WNDF'J m?.1 76 E.! s X
- 24- > 58 ? . 05H
_ c ND.
- Fo 1 > 1.98 a . X i
24 a 68 , 02H- o 3.11 .. X . 2161 c ?
24 J 69 2. 02H . - 1- 1.5 3 - ~ X . . . < 1. 8 ' ~ X
~ '
! 24 1861 . 01H .
11.;.7 E X - 31.57L ?
03H 25 -
. -: 81- .
z4;4L X .' .M1.68 L .. -
X i 25 r3147 02H ... ; NDF x .-.
.x L 1.68 E- X-25 . ' n 15? ~ 03H '. c 4.7 X 61.631 l 25 .J 19 < ' 02H ,
J3 s W - X . . l.11.81; X
, 25- . 1211 . 02H = 3 2.6.s L ..
X -lL W 55s - '
25 44 . :121E 4 03H - . '^^ . 13 V . ~ .. X Ds.'41-671..
X =
25 X37 c1 J' 02H J. 1<1L... X . - .. f 1 ;7 9 :n ...
X 25 ,.34301 02H y!a3.3t - X - 1.87i E X i
25 s1;6 : . . . X
, 13 54. E '~. 02H
. .. .- .. 21.551. . '
- 25 ; M 62? 04H . h NDFL - ; ; <1.72 < . . . X 1
I i
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. . Table 1 Steam Generator D Page 10 of 13 STEAM GENERAT OR "D" STRESS RELIEF HARD STOP PRESSURE SLEEVE LOCATION HAZ CRITERlON DATA CRITERION ANALYSIS ROW l COL l TSP VALUE ACCEPT VALUE l ACCEPT ACCEPT 25 73 ;-- 02H '2.31 X 31.667 X 25 m.D 85 - 01H .
- 1.6 L . X ~ . . ; 1.471 -
26 3.4 E . X W1.68 416 X
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X i J.::e1.684 ~ X 26 ..? 44 04H .NOFs
. .J31;840 ' X 27 5137.1 01H 4 1.84 ' -
X R E1.743- e X 27 s131 . 02H ' '?3.84 .J X J1;75K 3 X
27 :14 01H . .. . /1.51 - ' ' X ' " ' 31.85 C ' ' X 27 -
n17 . 05H a 2 NDF A . . s 1 11 811 X 27 : #21 ?::1 04H ~ ~ ~ ' k 2.31 X . i31;72. r. . X 27 1221 01H .' T2.7 > C L; X ':.J1.54L N 27 J22! 02H . JNDF0 ~ W1.6 9 . ' : X 27 c 24 ;- 02H JNDF4 ^
. z A1;341 -. X 27 . :257 -
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1 27 4 127 ".. . 03H Liv 2.6 > ~ ' X _466t z . . ,
X l 27 53 :; 02H J15t . X :.131.81- X 27 02H 3 35 ~- X 41.8 % - X 27- . .:165 r . 01H .. . . . ? 3.1 : - . . X- 1.121ASL - X
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28 169: 1 02H ~1 :22.3 L M
. X '11.537 29 ,. 114R 02H ANDEC.T 21.68 L .; X 29 11 5 ' 01H ' ~ 0.6 t : ' : X ! - cliB3C
- X 29 L:211,. 02H - 'T3.9 E 1 X 41.82 O D X
I 3
. . Table 1 Steam Generator D Page 11 of 13 STEAM GENERATOR "D" STRESS RELIEF HARD 1. TOP PRESSURE SLEEVE LOCATION HAZ CRITERION DATA CRITERlON ANALYSIS VALUE ACCEPT VALUE ACCEPT ACCEPT ROW l COL l TSP l l 4
29 1 26: 02H 24.3 X . . 12;11-X
= <NDF! .- .i 11.98:L X 29 -.. 35 - - 01H 30 - -: 13- 03H -- ' 2 :s . . X ;1.871 ' X 30 -19' 02H NDF -
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. X i e 1.68 C ? X 30 :541_ 03H
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, . . Table i Steam Generator D Paga 12 of 13 i
STEAM GENERATOR "D" STRESS RELIEF HARD STOP PRESSURE SLEEVE LOCATION HAZ CRITERION DATA CRITERlON ANALYSIS ROW COL TSP VALUE l ACCEPT VALUE ACCEPT ACCEPT 32 +J68s 02H 1;4 :: X -- -; 1. 62 : . - .
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STEAM GENERATOR "D" l
3 STRESS RELIEF f HARD STOP PRESSURE i SLEEVE LOCATION HAZ CRITERlON DATA CRITERlON i; -
ANALYSIS h
ROW COL VALUE ACCEPT VALUE ACCEPT ACCEPT l TSP l l 38 < . r 26 :: 01H ::1.6:: = .
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. Trojan Nuclear Plant Document Control Desk Docket 50 344 November 26,1992 License NPF 1 Appendix A Page Al of A3 APPENDIX A - RESULTS OF COMPARISON OF TROJAN NUCLEAR PLANT SLEEVE INS 7 nLLATIONS TO BAW-2094PA, REV 1,"RECIRLULATING STEAM GENERATORS KINETIC SLEEVE QUALIFICATION FOR 7/s INCH OD TUBES" Since the approval of Topical Report BAW 2094PA, Revision 1," Recirculating Steam Genera-tors Kinetic Sleeve Qualification for 7/8 inch OD Tubes", a number of changes in tooling design and field procedures have been implemented by B&W Nuclear Service Company These changes were based on field experience with earlier tooling designs and were intended to im-prove the reliability of the process. B&W Nuclear Service Company concluded that these changes did not citer the critical parameters of the sleeve design and an immediate revision to the Topical report was not deemed necessary. Descriptions of the revised toolit.it and procedures were later incorporated lato the next revision (Revision 1) of BAW 2045PA, " Recirculating Steam Generator Kinetic Sleeve Qualification for 3/4 Inch OD Tubes," which has been approved by the NRC. As pad of the investigation to determine the cause of the heater probe misposition-ing at TNP, the field procedures were compared to the process der.cription in BAW-2094PA, Rev.1. The process differences are described below.
g BAW-2094PA, Rev. I describes the tube rupport plate stress relief heater as a 1300 watt car-
]
3 tridge heater (with two nominal 600 w.-N heating elements,100 watts lost due to rocting be-1 tween t 4ements). TMs heater had thermocouples embedded in the heater sheath at the upper and lower heater location that were used to control heater power. Yhe strew relief heater used at
, TNP for tabe support piste sleeves was a coil heater design with two "a watt heating elements.
This heater design uses thermocouples mounted in the mandrel apporting the heater coils with
< the thermocouple near the lower heater used to control the heater power (the thermocouple at the opposite end is monitored to by the process computer to assure the temperatures remain within defined limits).
The change in heater design was made due to problems with swelling of the cartridge heaters which resulted in heaters becoming stuck in the steam generator tube sleeves. The qualified sleeve design requires achieving a stress relief tube temperature of 1275'F to 1525 F for a mini-mum of 5 minutes. This is achieved by controlling the heater based on thermocouples in the heater probe. The more thermally efficient resistance coil hea,ers require the heater coils be controlled to a lower temperature in order to achieve this same tube temperature. The appropri-ate heater terrsratures for this configuration were established by testing and the temperature
.,pecified in the field procedures has been specified based on this testing. Therefore according to B&W Nuclear Service Company, this tonling change did not result in a chtrge in the criticsl pa-rameters ofine stress relief process.
The topical report notes that a " process verification test" (i.e., a test of heater o~ ration, is per-formed at prescribed intervals and upon completion of the heater operation). Field procedures used at TNP allow the tuting on completion of heater og e ation to be omitted at the direction of the process engineer. According to B&W Nuclear Service Company, this change was made since a mechanical or electrical failure could make it impossible for a heater to be tested upon
Trojan Nuclear Plant Document Control Desk
. . Docket 50 344 November 26,1992 License NPF 1 Appendix A Page A2 of A3 removal from service. In these cases, the process engineer is responsible for ensuring that the ,
heater was functioning properly by reviewing heater thermocouple data. If there is no evidence of heater malfunction, the stress relief process is not repeated on the tubes in which that heater was used. If there is any reason to suspect that the heater was not performing properly, then those tubes would be stress relieved with a new heater.
Several changes were also made in the pocess used to clean the inner surface of the tube in preparation for ine sleeving operation. BAW-20%PA, Rev. I describes the use of a silicon car-bide hone for the tube cleaning proce tith a water Hush used to remove debris. The hone is described as operating at a minimum ,* u of $00 rpm while oscillating axially over at least a two inch region for a minimum of 20 seconds. The 6 eld tooling used at TNP employed a tung-n:n carbide hone and a vacuum system for debris removal. This change was made to improve the quality of the tube cleaning pmcess. The tungsten carbide hone is better at removing tightly adhering oxides from the tube surface. The hone speed was also increased to 900 tpm over a five inch region for at least 60 seconds. '"nese parameters were increased ta improve the clean-ing of the tube surface in preparation for sleeve welding. A vacuum system is now used in lieu of the water Rush to eliminate :he liquid waste generated by the original me' hod. The vacuum system provides for adequate hone cooling and debris removal and does not alter the final clean-liness of the tube surface.
BAW-2094PA, Rev. I notes that steam generator tubes are "go gaged" prior to inserting a sleeve to detect aay possible tube denting at the tube support plants, liowever. #ce eddy curra't test-ing is performed on each tube pnor to sleeving, the Held procedures used at TNP used th. data to screen for possible obstructions. The v.e of the "go-gage" was optional based on the results of the eddy current inspection.
BAW-2094PA, Rev. I describes the heater deda as being c.ipable of supporting itself within a steam generator tube. This tooling feature was miended to allow simultaneous stress relief of several different tubes at once.110 wever, this capability was never successfutly developed and was not u td at TNP. The heater design used at TNP, therefore, was not self supporting.
BAW-2094PA, Rev. I describes a ten hour 1300"F themial treatmnt used during fabrication of Alloy 690 sleeve material. The duretion of this thennal treatment has been changcd to specify a minimum of five hours (there was no change in the required temperature). This change was 2
made consistent with Electric Power Research Institute EPRI) guidelines for Alloy 690 materi-al. Th originally speciGed duration was conservative.
BAW-2094PA, Rev. I describes the use of a continuity switch to confirm positioning of the i
heater probe hard stop against the lower edge of the sleeve. The contacts were also monitored by the control computer and used to shutdown the stress relief process in case of movement of the heater probe from the physical hard stop. The electrical catacts were found to be unreliable due to the high ten perature in the area of the heater coil. Therefore, the tooling design was mo-dified to use a pneumatic sensing system to conGrm the proper positioning of the probe hard stop against the sleeve. This method of positioning was tested w conGrm a positioning accuracy
_ _ _ _ _ . a
, . Trojan Nuclear Plant Document Control Desk i . . Docket 50 344 November 26,1992 .-
License NPF-1 Appendix A Page A3 of A3 ofi 1/8 inch relative to the sleeve. The ' pneumatic hard stop" air pressure is monitored and re-corded following heater irsenic.n into the sleeve. At the end of the stress relief process, the air pressure is again read and compared to the value recorded prior to the stress relief process to de-tect any change which might indicate that the heater moved during the stress relief process. The procedure calls for the operator toideatify such changes for further review. B&W Nuclear Scr-vice Company concluded that this modi 0 cation to the stress relief tooling and procedure would -
have no impact on the sleeve qualification process, testing, or analyses and that there would not i result in any difference in the quality of the installed sleeves. As noted above, the description of this revised method of position con 0miation was later incorporated into Revision 1 of BAW-2045PA, " Recirculating Steam Generater Kinetic Sleeve Quali0 cation for 3/4 inch OD Tubes." '
As discussed above, B&W Nuclear Service Company has reviewed these changes from the tool-ing and process described in the BAW 2094PA, Rev,1. For the reasons discussed above, B&W Nue' ar Service Company concluded that the changes did not alter any critical parameters or devwe from the qualified sleeve design.
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- Trojan Nuclear Plant Document Control Desk Docket 50-344 November 26,1902 i
- License NPF 1 Appendix 11 j Page B7 of B7
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