ML042400214
| ML042400214 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 08/19/2004 |
| From: | Pace P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML042400214 (53) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spnng City, Tennessee 37381-2000 AUG 1 9 20O 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
In the Matter of ) Docket No.50-390 Tennessee Valley Authority WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) - REQUEST FOR RELIEF l-RR-6 In accordance with 10 CFR 50.55a(g)(5)(iii), TVA is requesting relief to use a temporary non-Code repair until the WBN Spring 2005 refueling outage. A through wall leak was discovered in a section of ASME Code Class 3 essential raw cooling water (ERCW) system piping. This twenty-inch nominal size segment of piping is the ERCW flood mode supply to the spent fuel pit heat exchangers and thermal barrier booster pumps. The leak is located between the ERCW Train B supply header and upstream of isolation valve 0-ISV-067-0529 going to the flood mode blind flange. This section of piping cannot be isolated without a plant shutdown to perform a Code repair.
This relief request is submitted in accordance with the guidance of NRC Generic Letter 90-05, "Guidance for Performing Temporary Non-Code Repair of Code Class 1, 2, and 3 Piping." TVA evaluated the operability of the ERCW piping with regards to:
(1) the structural integrity of the pipe, (2) the effects of spray on adjacent equipment, and (3) ERCW flow rate requirements. TVA's evaluation for operability indicates that the ERCW system will perform its design basis function and that the surrounding equipment is not adversely affected by spray.
The structural integrity of the flawed piping was assessed and found acceptable. 0 m P-'ted onrecyed paw
U.S. Nuclear Regulatory Commission Page 2 AUG 19 2004 The enclosure provides the justification for Request for Relief, 1-RR-6. Problem Evaluation Report 63850 documents this condition and tracks the corrective actions to ensure structural integrity is maintained and to ensure a code repair is performed during the WBN Unit 1 Cycle 6 refueling outage. The WBN Code of Record is the 1989 Edition (no addenda) of ASME Section XI. WBN is currently in the third period of the first ISI 10-year interval.
There are no regulatory commitments identified in this letter.
If you have any questions about this request, please contact me at (423) 365-1824.
Sincerely, P. L. Pace Manager, Site Licensing and Industry Affairs Enclosure cc (Enclosure):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Ms. Margaret H. Chernoff, Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. M. M. Comar, Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303
ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)
WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF 1-RR-6
SUMMARY
- A through-wall leak was discovered in a section of American Society of Mechanical Engineers (ASME) Code Class 3 essential raw cooling water (ERCW) system piping. The leak is in a twenty-inch nominal pipe size (NPS) segment of piping. The segment of piping containing the leak is the ERCW flood mode supply to the spent fuel pit heat exchangers and thermal barrier booster pumps. The leak is located between the ERCW Train B header and upstream of isolation valve 0-ISV-067-0529. This valve is normally in the closed position and has a flanged connection downstream of the valve. A Code repair was considered; however, the repair cannot be completed within the required limiting condition of operation for the ERCW system.
Because this segment of piping cannot be practically isolated without a plant shutdown to perform a Code repair, this request for relief is submitted in accordance with the guidance of NRC Generic Letter 90-05, "Guidance for Performing Temporary Non-Code Repair of Code Class 1, 2, and 3 Piping." This generic letter allows authorization for a temporary non-Code repair.
A Code repair is scheduled to be implemented during the Unit 1 Cycle 6 (UlC6) refueling outage in the Spring of 2005. This request for relief is submitted in accordance with 10 CFR 50.55a(g)(5)(iii) to authorize use of this temporary non-Code repair until the WBN U1C6 Spring 2005 refueling outage.
WBN submitted a similar request for a temporary non-Code repair which was approved by NRC letter dated April 23, 2002 (TAC NO. MB3016).
The WBN Code of Record is the 1989 Edition (no addenda) of ASME Section XI. WBN is currently in the third period of the first ISI 10-year interval which began May 26, 1996 and ends December 26, 2006.
E-1
ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)
WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF 1-RR-6 UNIT: WBN Unit 1 SYSTEM: Essential Raw Cooling Water COMPONENTS: Twenty inch NPS, Schedule STD Carbon Steel Pipe ASME CODE CLASS: 3 FUNCTION: This section of piping is the ERCW flood mode supply to the spent fuel heat pit exchangers and thermal barrier booster pumps. The leak is located between the ERCW B Train supply header and closed isolation valve 0-ISV-067-0529. This valve is the isolation valve upstream of the flood mode blind flange that allows installation of the flood mode spool piece if needed. This area is identified on TVA Drawing 47W845-2, coordinates B-5, (Final Safety Analysis Report (FSAR) Figure 9.2-2), see Attachment 1.
IMPRACTICAL CODE REQUIREMENTS: An ASME,Section XI, Code repair or replacement is required to be performed in accordance with ASME,Section XI, 1989 Edition, IWA-4000, "Repair Procedures," or IWA-7000, "Replacement,f" respectively, in order to restore the system's structural integrity back to its original design requirements.
BASIS FOR RELIEF: On June 23, 2004, a through-wall leak was discovered in the ERCW system. The leak is located in a moderate energy twenty-inch NPS diameter carbon steel pipe between the ERCW Train B supply header and valve 0-ISV-067-0529 which cannot be isolated from the supply header for repair. The design pressure and temperature for this section of piping is 160 pounds per square inch gauge (psig) and 130 degrees Fahrenheit (F).
The water is stagnant in this section of pipe.
Under TVA's Corrective Action Program, a Problem Evaluation Report (PER) 63850 has been written to document and correct this condition.
E-2
ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)
WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF 1-RR-6 The leakage from the piping was characterized as a steady stream approximately 3/8-inch to 1/2-inch diameter. Ultrasonic examinations were performed to determine structural integrity. As a stop gap measure to minimize spraying concerns, a pipe clamp and a rubber gasket were installed over the leak in accordance with WBN Temporary Alternation Change Form (TACF) 1-04-001-067 Ri. At this time, leakage is minimal and is captured by leak containment measures to a floor drain.
The guidance of Generic Letter 90-05 was used.
The structural integrity of the flawed piping was assessed and found acceptable. The apparent cause for the piping degradation is considered to be due to microbiological induced corrosion (MIC). An ultrasonic examination was performed upstream and downstream of the leak for use in evaluating structural integrity. Since the root cause is considered to be MIC, no additional areas were examined because MIC cannot be reliably predicted as to its location. The leakage has not caused any detrimental flooding or spraying onto any adjacent equipment. Attachments 2 and 3 provide the Functional Evaluation and the Structural Evaluation.
PROPOSED TEMPOARY NON-CODE REPAIR: At this time, TVA plans to leave the piping as is with a temporary non-Code repair using a clamp with rubber gasket. The flaw evaluation shows that this piping still has sufficient strength to perform its design function.
ALTERNATIVE REQUIREMENTS: In accordance with procedures which implement Generic Letter 90-05, TVA is conducting weekly walkdowns to assess the operability and leakage through the temporary non-Code repair. Any changes which could affect operability or structural integrity are to be evaluated. An ultrasonic examination is also to be performed every three months to assess the piping degradation rate. Based upon those weekly E-3
ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)
WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF 1-RR-6 walkdowns and ultrasonic examinations, an engineering evaluation will be performed to determine if further remedial measures or corrective actions are needed. An ASME Section XI repair or replacement will be performed before the completion of the UlC6 refueling outage which is currently scheduled in the Spring 2005. ThisSection XI repair or replacement is being tracked by PER 63850.
JUSTIFICATION FOR GRANTING OF RELIEF: A Code repair while in operation is impractical based upon the inability to isolate the segment of ERCW piping containing the leak. Based on the evaluation and the proposed alternative requirements of Generic Letter 90-05, the temporary non-Code repair provides an acceptable level of quality and safety. The ERCW system Train B is considered operable, although degraded, and thus, is available for continued operation under the provision of Generic Letter 91-18, "Information to Licensees Regarding NRC Inspection Manual Section in Resolution of Degraded and Non-Conforming Condition," Revision 1, dated October 8, 1997. Authorization to use the proposed alternative is requested per 10 CFR 50.55a(g)(5)(iii) until the repair or replacement is made in the Spring 2005 refueling outage.
E-4
ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)
WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF 1-RR-6 LIST OF ATTACHMENTS
- 1. Drawing 1-47W845-2 (FSAR Figure 9.2-2)
- 3. Generic Letter 90-05 Structural Evaluation E-5
ENCLOSURE ATTACHMENT 1 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 REQUEST FOR RELIEF 1-RR-6 TVA DRAWING 47W845-2
ENCLOSURE ATTACHMENT 2 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 REQUEST FOR RELIEF 1-RR-6 FUNCTIONAL EVALUATION FOR LEAK IN 20-INCH ERCW SYSTEM FLOOD MODE SUPPLY HEADER TO COMPONENT COOLING SYSTEM (CCS)
Functional Evaluation for PER 63850 Leak in 20 Inch ERCW System Flood Mode Supply Header to CCS
1.0 Background
On the evening of June 23, 2004 a leak wvas identified in the Essential Raw Cooling Water System (ERCW) 20 inch flood mode piping which connects a portion of the ERCW to the Component Cooling System (CCS) during flood mode operation. This line is a 20 inch carbon steel line coated with an epoxy coating and black Rubatex insulation. Following removal of the insulation around the leak, it was observed that the outer surface of the pipe did not appear corroded but a hole approximately 3/8 to 1/2 inches in diameter which was located in the 7 o'clock position (when looking east) was spraying water to the floor and onto nearby components. The leak flow rate was estimated to be approximately 20 to 30 gpm; but for the purposes of this evaluations will be considered to be 60 gpm.
2.0 SSC Function The leak is in the safety related portion of the ERCW System. This header is part of the ERCW/CCS interface piping for flood mode operation. During flood mode operation the equipment required to maintain the plant in a safe shutdown condition requires cooling. Some of the equipment heat loads are normally cooled by the CCS. However, the CCS pumps will be flooded and inoperable; therefore, these heat loads wtill be cooled by the ERCW System by using spool pieces to connect the ERCW piping network to the CCS piping network. Some connections are also made from the ERCW System to the Raw Cooling Water (RCW) System. The main function of this 20 inch header is to provide cooling water to the Residual Heat Removal and Spent Fuel Pool Heat Exchangers when the plant is in flood mode operation.
During other plant operating modes, there is no flow through this line. Its function during these times is to serve as part of the pressure boundary for the ERCW System.
3.0 Evaluation of SSC Functionality 3.1 System Function: The leak consists of a flow rate of approximately 60 gpm from the 20 inch flood mode supply line that branches from the 24 inch supply line to CCS Heat Exchanger C. This heat exchanger requires 2,000 to 8,000 gpm depending on the plant operating conditions. A leak rate of 60 gpm will not significantly affect the ability of the ERCW System to provide the required flow to the CCS Heat Exchanger C during regular plant operating conditions, or during Flood Mode operation when the ERCW System is directly connected to the CCS piping network.
3.2 Moderate Energy Line Break: The current leak rate is well within the Moderate Energy Line Break Flood analysis for this location in the Auxiliary Building. The flow rate from the leak, which is describe above, does not adversely affect the results of the MELB analysis. According to Reference 6.4 page B.4-50 through B.4-52, the bounding break flow for this area is from a 24 inch standard weight pipe and is 1.906 cubic feet per second. This is equivalent to a flow of 855 gpm. An additional 60 gpm trill have a negligible impact on the flood analysis in the area of the leak and in the areas adjacent to the area containing the leak.
3.3 Structural Integrity: The structural integrity of the pipe header has been evaluated by Civil Engineering in Attachment A to Calculation N3-PA-091. The evaluation was performed in accordance with Design Standard DS-C1.2.8 (ASME Code Case-5 13), which conservatively uses the inspection data from Page I S:\NUCENG\Mechanical\2004 Functional Evaluations\per 63850 ercw pipe leak\FE for per 63850 rev 01.doc
Functional Evaluation for PER 63850 Leak in 20 Inch ERCW System Flood Mode Supply Header to CCS 6/24/2004 and determines the minimum average wall thickness (around the circumference) is not to be less than 0.135". This ensures structural adequacy is maintained.
Additional NDE data wleas taken on 7/01/2004 for the eight locations around the circumference at the leak location. Based on an average of the readings (conservatively setting the largest to 0"), the measured wall thickness is 0.325". As can be seen from the readings taken on 7/01/2004 the actual wall thickness is much greater than the 0.135" required by the structural evaluation. Therefore, the pipe section has been determined to be structurally adequate.
3.4 Equipment Protection: A temporary pipe repair clamp is being installed under TACF-1-04-001-067 Revision 0 to minimize the leakage flow and provide spray protection to equipment in the vicinity of the leak. Installing the repair clamp over the hole ixill help ensure the hole does not increase in size due to the reduction in flow through the hole. Since the repair clamp is not safety related, additional assurance is provided by the UT measurements made in the vicinity of the hole that show the metal thickness meets or exceeds the minimum required wall thickness to ensure the structural integrity of the piping except for a small area in the immediate vicinity of the hole. Therefore, even if the pipe repair clamp failed, the hole size is not expected to increase enough to affect the results of this evaluation which assumes a flow of 60 gpm through the hole. References 6.8 and 6.9 require that Category IE equipment located in this area be designed, purchased, and installed for a water spray environment. Therefore, the water spray that would result from a failed repair clamp would not adversely impact the safe operation of the plant.
4.0 Extent of Condition Leakage in raw water systems at WBN can either be from internal damage or external damage. External corrosion has resulted from chloride attack beneath Rubatex insulation applied on cold raw or chilled water pipe that is not protected by an epoxy coating. Since this pipe does have a protective coating and external corrosion was not observed, this mechanism is preliminarily ruled out. Experience has showns that in the absence of external corrosion, leaks in ERCW carbon steel lines can either be associated with cavitation/erosion damage or microbiologically induced corrosion (MIC). The leak was not noted to be near a weld and not immediately downstream of a valve or other component which would create the potential for a cavitation condition to exist. Weld backing rings and valves in nearly closed or throttled positions can cause cavitation/erosion of downstream pipe wvall material. Therefore, based on physical configuration, this also is preliminarily ruled out. Microbiological corrosion typically attacks carbon steel in the general pipe wvall by the formation of nodules inside the pipe. The nodule provides a protective barrier to allow the MIC to develop until the pipe wall thins to the point of failure from pressure stress.
Characteristics of this leak match the MIC failure mechanism and MIC damage is judged to be the most likely cause of the pipe wvall damage. MIC damage has been observed in multiple cases in WBN raw cooling water piping. Since the wall thinning is generally localized at the nodule, it has not represented a structural failure risk in previous failures.
One other leak has been documented to currently exist in the ERCW System. PER 34438 documents a leak in the cooling coil for CRDM A-A (I-CLR-030-0083). It is in the opposite ERCW Train; therefore, has no effect on this evaluation.
Page 2 S&NUCENG\Mechanical\2004 Functional Evaluations\per 63850 ercw pipe leak\FE for per 63850 rev Ol.doc
Functional Evaluation for PER 63850 Leak in 20 Inch ERCW System Flood Mode Supply Header to CCS 5.0 Closure Requirements The pipe section with the leak shall be repaired or replaced during the UIC6 Refueling Outage.
6.0
References:
6.1 System Description N3-67-4002, Rev. 15 "ESSENTIAL RAW COOLING WATER SYSTEM SYSTEM 67" 6.2 DrawNing 1- 47W845-2, Rev. 41, "MECHANICAL FLOW DIAGRAM-ESSENTIAL RAW COOLING NVATER SYSTEM" 6.3 Design Criteria WB-DC-40-64, Rev. 9 "Design Basis Events Design Criteria" 6.4 Calculation W.BNOSG4099, Rev. 4 "Moderate Energy Line Break Flooding Studyi' 6.5 WBN UFSAR Chapter 9.2.1, 6.6 WBN Technical Specifications 6.7 PER 63850 6.8 47WV200-100 Rev. 9, "SEISMIC COMPARTMENTATION" 6.9 47W200-102 Rev. 7, "SEISMIC COMPARTMENTATION"
7.0 Attachments
7.1 Attachment A to Calculation N3-PA-091
8.0 Signatures
Revision 0 Preparer: Original signed by Date: 07-Julv-2004 John F. Lund Preparer: Original signed by Date: 07/07/2004 William R. Bibb Reviewer: Original signed by Date: 07/07/2004 James S. Robertson Revision 1 Revised date on page 2. This documentation change does not affect the evaluation.
Preparer:_p__ __ Date: IP,, zk_5 John F' Lund Preparer: 1 Vt (, .4~ Date: 0 /1Rb/n4 Howard A. Cusick Reviewer: A Date: 4z,b a James S. Robertson Page 3 S:\NUCQENG\Mechanical\2004 Functional Evaluations\per 63850 ercwv pipe leak\FE for per 63850 rev 01.doc
-I Calculation N3-PA-091 Attachment A Prepared By: (42 04 J2,Y Checked By: )-ob (/zA/
This Page Added By Revision PURPOSE:
The purpose of this evaluation is to determine the structural adequacy of a location which is leaking. The leaking location is located on ERCW piping near valve 0-ISV-67-529. The leaking pipe is part of Rigorous Analysis Problem N3-67-02A.
REFERENCES:
- 1. Inspection Report BOP-763.
- 2. Design Standard DS-C1.2.8.
- 3. Calculation N3-67-02A, Rev 20, RIMS # T71 030522 802.
- 4. Drawing 47W450-302E.
EVALUATION:
The reference 1 inspection data provided readings for the leaking location, as well as, axial along the pipe adjacent to the leaking location. This evaluation will be performed in two parts. Part I will evaluate the leaking location using reference 2, including a fracture mechanics evaluation. Part II will determine a minimum structural wall thickness value for the piping adjacent to the leak.
Part I:
Reviewing the reference 4 isometric drawing, the leaking location is between node points 466B and 1143 in the analysis model. The actual piping stresses from the reference 3 analysis will be used in both the structural and fracture mechanics evaluation. The fracture mechanics evaluation will determine a maximum allowable thru-wall flaw based on the existing loadings.
Additionally, based on this allowable thru-wall flaw a structural adequacy evaluation will be performed to ensure structural integrity. The maximum stresses between the above node points will be used. No reduction in moment will be made for any modeled SIF's of the span in question (conservative - moments will remain intensified). The following is a list of maximum existing stresses and associated moments for node points 466B - 1143:
mmsun = 2,014 psi as = 2,342 psi asu = 2,902 psi a9F = 3,413 psi caio 283 psi Page A.
Calculation N3-PA-091 Attachment A Prepared By: (11L\)L ( p/O4' Checked By: 4) cri/n=7 / o This Page Added By Revision M. = 36,539 lb-in Mbu 98,923 lb-in Mb =155,849 lb-in M: = 31,526 lb-in Using the previously tabulated values, a fracture mechanics and structural integrity evaluation was performed in accordance the reference 2 methodology (refer to pages A. - A. ). For the fracture mechanics evaluation, a wall thickness value of 0.135" (lower bound which is acceptable for NDE data) was used. The fracture mechanics evaluation determined the maximum allowable crack length of 0.624" (circumferential / axial). This value was based on the input piping stresses / moments developed on the previous page and the actual NDE inspection data provided by reference 1 (leak occurs at 7:00 point of pipe location). With the allowable crack length of 0.624" the evaluation also showed that structural integrity will be maintained for all ASME Code equations with the maximum stress ratio being 0.794. For acceptance the existing crack length cannot exceed 0.624" with the average wall thickness not to be less than 0.135".
From the NDE data only 2 of the 8 points had registered values due to clamp obstruction. The occurred at locations 1 and 7. Additionally, data was taken directly adjacent to the leak on all four sides with the lowest reading being 0.097". For conservatism, in determining the actual NDE minimum wall thickness points 2 thru 6 were set to 0.097" and point 8 was set to 0" (represents the leak). This produces an NDE average wall thickness of 0.146" which is greater than the 0.135" presented above.
Part II:
NDE wall thickness readings were taken additionally taken upstream and downstream of the leaking location. Referring to the reference 1 inspection data, the average NDE values exceed manufactures minimum wall thickness of 0.875 x t A. Since the wall thickness exceeds manufactures minimum wall, the locations are structurally acceptable. The following pages (refer to pages A. - A. ) determine a minimum average wall thickness value of 0. 113" (360 degrees around the pipe). This value is based on the maximum input bending stresses for the identified locations from the reference 3 piping analysis.
Therefore, the piping adjacent to the leak location is structurally acceptable for the inspected data.
Page A.
I
Calculation N3-PA-091 Attachment A Prepared By: ____j___ L_ ___ Checked By: 6 o This Page Added By Revision CONCLUSION:
From the above evaluations, at the location of the leak, the maximum allowable flaw length is 0.624" with the minimum average wall thickness not to be less than 0.135". This criteria will ensure that the fracture mechanics and structural integrity criteria are maintained. For the adjacent piping (straight pipe only), structural integrity is maintained based on the NDE data exceeding the minimum wall thickness value (0.113") required by design. No further evaluation is required.
Page A.
. i N3-PA-091 Attachment A Page:
Prepared By: qot Checked By: 61zy 6/zqlol-THIS ROUTINE COMPUTES THE ALLOWABLE FLAW LENGTH PER DS-C1.2.8 USING THE ADJUSTED WALL THICKNESS (Id) IN AN ITERATIVE PROCESS. ADDITIONALLY, EACH SOLVE BLOCK HAS AN INDEPENDENT CHECKING ROUTINE TO ENSURE ANSWER VALIDITY.
User Defined Units of ksi ksi:= 1000. lbf
.2 In User Defined Input Nominal Pipe Size Do:= 20.00-in tnom:= 0.375-in 20 Inch SCH STD User Defined Input Material Pronerties E:= 27.9-10 6. Ibf Modulus of Elasticity
. 2 A:- 0.3 Polsson's Ratio JIC := 45 bf Fracture Toughness (Minimum Bounding Value From ASME Section Xl) in User Defined Innut Pressure (Design) and Moments p:= 16 0 - bf Pressure 2
Ma:= 36539-in lbf Sustained Mechanical Moment (intensified)
Mbu:= 98923-in lbf Upset Moment (intensified)
Mbf:= 155849-in-lbf Faulted Moment (intensified)
Mc:= 31526-inlbf Thermal Expansion + Anchor Movement Moment (intensified)
This Page Added By Revision
N3-PA-091, Aftachment A Page:
Prepared By:GcX44/Checked By: bXeo,7 `/z/o Define Functons For Cross Section Dimensions and Properies Rm(Do,t)_ Do - t Mean Radius 2 2 Ri(Do,t) Do -t Inside Radius 2
ROT(Do,t):=R(ot Rm/tRatio
+/-
io Do 4 - (Do t) Section Modulus Z(Do,t): ' -.
32 Do Compute Expansion Stress PC:= Mc Pe = 283.133 psi Z(Dotnom)
Define Functions for Coefficients in Circumferential Flaw Crack Stress Intensity Eguaton Am(Do,t):= -2.02917 + 1.67763-ROT(Do,t) - 0.07987-ROT(Do,t) 2 + 0.00176-ROT(Do,t) 3 Bm(Do,t):= 7.09987 - 4.42394-ROT(Do,t) + 0.21036-ROT(Do,t) - 0.00463-ROT(Do,t) 3 Cm(Do,t):= 7.79661 + 5.16676-ROT(Do,t) - 0.24577-ROT(Do,t)2 + 0.00S41-ROT(Do,t)
Ab(Do,t) -3.26543 + 1.52784-ROT(Dot) - 0.072698.ROT(Do,t) 2 + 0.0016011-ROT(Do,t) 3 Bb(Do,t) := 11.36322 - 3.91412*ROT(Do,t) + 0.18619.ROT(Do,t) - 0.004099.ROT(Do,t) 3 Cb(Do,t):= -3.18609 + 3.84763-ROT(Do,t) - 0.18304-ROT(Do,t) + 0.00403-ROT(Dot)3 TOPl,Do,t)' 1 0 over r Rato 2--m-Rm(Do,t)
Fm(l,Do,t):= I + Am(Do,t)-TOP(1,Do,t) 5 + Bm(Do,t).TOP(l,Do,t)2.5 + Cm(Do,t)-TOP(l,Do,t)3.5 t5 Fb(l,Do,t) := I + Ab(Do,t).TOP(Q,Do,t) + Bb(Do,t)-TOPQ(,Do,t) 2 .5 + Cb(Do,t).TOP(l,Do,t) 3 .5 This Page Added By Revision
N3-PA-091 , IAttachment A Page:
Prepared BY:uA SL(42z4Checked By: lj, P 7 (,12410/
Compute Critical Fracture Touahness I JIC E KIC = 37.144ksi-rin KIC:=
I User Defined Input Start Data to Start Iteration Prococs For Circumferential Flaws iguess=:= 1 Initial Guess Value for Flaw Length (Assumed Initating Value) tadj:= 0.135-in Input (value taken to be the lower bound which Is acceptable for NDE data
-conservative)
The following solve blocks are iterative processes to determine the through-wall flaw length that satisfies the crack stress intensity equation with the critical fracture toughness computed above.
Both upset and faulted conditions are considered.
Solve Block Iteration for Upset Condition SFc:= 2.77 Safety Factor for Normal/Upset Conditions Given KIC = Sc.[m(1guessDotadj).p.Ri(Do,tadi) IFLN'guess
- t2 2*Rm(Do,tadj).todj .
+Fb(lguessvDotadj) ( Ma+ Mbu 2
+PC SFC) c-Rxm(Dot8dj) *tadj Solve for Upset Condition Flaw Lensth Icu:= Finld(lguess) Icu = 0.681 in Check Unset Conditon Crack Stress Intensity Usina Flaw Lenath from Iteration SFc Fra(icuDotadj) .PRi(Do,tadj)2 2-RRm(Dotadj).tadj 1 2
=Ji 37.144ksiJ
+Fb(1cu,Do,tadj). Ma+Mbu + Pe) 2 r-Rm(Do,tadj) tadj SFC)
This Page Added By Revision t
N3-PA-091 Aftachment A Page:
Prepared By:to LChecked d3 By: u)Oe41-17 &/Z*4 I
i I
Solve Block Iteration for Faulted Condition SFc:= 1.39 Safety Factor for Emergency/Faulted Conditions Given
- 7. 1 ess
= S K
K Fc Fm(lguessDotadi) pKRi(Do,tndi 2.Rm(Dotadj).tadj 2
+Fb((guessiDoplad) I Ma + Mbf Pc L lz.Rrn(Doptadj) tadj S j Solve for Faulted Condition Flaw Length lcf := Fid(lgucss) Icf= 1.142in Check Feaulted Condition Crack Stress Intensity Using Flaw Length from Iteration 2
=
SFJFFm(lcf, Do,tadj) p Ri(DO,tad)
EJr-f.. * -A -. . lFL7~-f=37.44ks' iiN~
Find Controllina Circumferential Lenath for All Conditions IC:= if(lcf ~ Icu, Icu, lcf) Ic = 0.681 in Note that this Is the maximum circumferential length over which remaining thickness can be less than tdj.
This Page Added By Revision I
N3-PA-091 nr i Attachment A Page:
Prepared By: WU(*xiW4JChecked By: 1Lk& &P-y 4/-T/l Define Functions for Coefflicients In Axial Flaw Crack Stress Intensity Equation
).(l,Do,t):t 2 4!U (Do~t)'t F(1,Do,t):= 1 + 0.0724494X(l,Do,t) + 0.64856-%(1,Do,t) - 0.2327-%(1,Do,t) + 0.038154X 4,Dot)
+ (-0.0023487).-I(1,Do,t) 5 Solve Block Iteraton SFa 3.0 Safety Factor for Normal/Upset Conditions Given SFa.F(IguessDotadj).p.Rm(Dotadj) 'E4 guess tadj 2 Solve for Flaw Lenath la := Find(lgs) la= 0.624 in Check Crack Stress Intensity Using Axial Flaw Lenath from Iteration SFa.F(laDotadj).p.Rm(Dotadj) fVIa = 37.144ksi1 J; tadi 2 This Page Added By Revision
N3-PA-091 ,AJ)AII Attachment A Page:
Prepared By: W04 Checked By: Wj ee 6"'
/Zl?/o Moets Stress Criteria User Defined Ingut Stress Data Sc 15000.- Allowable Stress at Minimum Temperature
.2 n
Sh:= 15000.- Allowable Stress at Maximum Temperature
. 2 i := 1.00 Input Moments Are Intensified Compute Stresses ahodop :- 2t2 + 0.4.p Ohoop = 11.916ksi
-I -tadj
° _(,~J p Ri(Do,tadj) '2
+
](DO+tad Ri(Do,tadj)21ZD~aj if(.75-i 5 1.0,1.0,0.75-i)-Ma s= 6.6S5ksi p-Ri(Dotadj) 2 if(.75-i 5 1.0,1.0,0.75 i)-(Ma Mbu) a9u:= c9u = 9.066ksi Z(DO,tadj)
[ Ri(DO,tadj)2]
p Ri(Dotadj) if(.75-i 5 1.0,1.0,0.75i)-(Ma + Mbf)
Or9f= 10.435ksi Z(Dotaij)
[( 2) - Ri(Do,tadj)2]
p-Ri(Do,tadj) 2 - if(.75 i:5 1.0,1.0, 0.75 i)-Ma + i-Mc I rII r7.444ksi (Do)_-Ri(DOtadf Z(Doatadj)
This Page Added By Revision
N3-PA-091 ,4 J Attachment A Page:
Prepared By: Wi=(24JIChecked By: 1z e7 '24/1of Compute Stress Ratos hoop Sh S I = 0.794 CB S2 = 0.446 S2 Sh S3 9u S3 = 0.504 1.2-Sh S9f S4 = 0.29 S4 2.4.Sh S .*- c11 S5 = 0.199 S 1.25 (Sc + Sh)5 Sma, := max(S) SmtL~c = 0.794 c 1.0, Therefore td, OK This Page Added By Revision
N3-PA-091 APPENDIX A Page:
Prepared By: &i/2L4:/OY Checked By: SOc7 6/Zl/D4 STRUCTURAL INTEGRITY EVALUATION Piping System: Essential Raw Cooling Water Grid Number: 0-67-529-LEAK Analysis Problem No: N3 02A Rev 20 Microfiche No: See Table 8.2-1 Member Name: 1500, 1505 Node Name: I143, 1144, 466B Isometric: 47W450-302E Flow Diagram: 47W845-2 Pipe Material: SA 106 Grm This Page Added By Revision
N3-PA-091 APPENDIX A Page:
Prepared By:G Checked By: /dA L" 7 6/z/o4 The routine below computes required thickness for a straight pipe (SIF = 1.0) underpressure and moment load using code equations. Seven cases (load combination - allowable stress conditions) are evaluated. Cases 14 are primary stress cases (iLe., code equations 8,u, 9E and 9). Case Sis secondary stress (i.e., code equation 10). Case 6 is sustained primary plus secondary (ie., code equation 11) and Case 7 is occasional primary plus secondary (i.e., code equations 9u+ 10) which is used for pipe rupture evaluation. Also Included Is the required thickness forpressure design for piping where the longitudinaljoint efficiency is no less than 1.0. The piping is classified as moderate energy.
- 1. Initialize ksi and psi units:
bf ls: . lbf ksi.- 10002- psi:= I in in
- 2. Input Pipe Data - Outside Diameter (Do), Nominal Thickness Ao Max/IDesign Pressure (P), Cold Allowable Stress (Sc) and lot Allowable Stress (Sh):
Do:= 20.000-in tnom = 0.375-in P:= 160.psi
! Sc= 15.0.ksi Sh:= 15.0-ksi
- 3. Input Analysis of Record Applied Stress (S) Values for 7 Cases:
i:= 1.7 where:
i= 1: Equation 8 Si i=2: Equation 9u in3: Equation 9e 2.342*ksi i 4: Equation 9f 2.902*ksi I 5: Equation 10 2.902.ksi I 6: Equation 11 3.413-ksi 1-i 7: Equation 9u + 10 (Pipe Rupture) 0.283.ksi 2.517*ksi 3.076-ksi
- 4. Compute Analysis of Record Allowable Stress (SW) Values for 7 Cases
Sa:= 1.25-Sc + 0.25.Sh SalU :
15 Sh18 1.2Sh 27
- l~.8-Sh 2 2.4.Sh San1= 36 ksi Sa 22.5 Sa+ Sh 37.5 0.8.(1.2-Sh + Sa) 32.4 This Page Added By Revision
N3I-PA-091 APPENDIX A Page:
Prep- ArPeNd Ay:
Prepared By:( l (4694 Checked By: zj,),b 7
- 5. Initialize Thickness Variable (t):
t := tnom I 6. Set Up Inside Diameter (DI), Moment Factor (Fm) and Pressure Factor (Fp) as Functions of Thickness:
Di(Dot) a Do t
( - Di(Do t)
Fm(D~oDi[t) i3 - Do Do Fp(Do,Dit) , 2 Fp(DoDit)P = 2.014ksi I Do -Di(Dot) I I
I
- 7. Compute Applied Moment (NM) for Equations 8, 9u, 9e, 9f and 10:
I i:1 .. 4 i J S. - P-Fp(DoDit)
Mi Fm(Do,Di,t)
S5 M5 Fm(Do,Di,t)
(3.043 x 0o) 8.239x lo 1 I A ...
8.239x 1O0 -tibX 1.298x 10 2.626x 103o
- 8. Perform Solve Block Iterations to Determine Required Thiclness (tr) for Each Case:
Case I (mQuation 84 Given Saul = M1 .Fm(DoDit) + P.Fp(DoDit) t:= Find(t) tr.1 = t trI -0.061 in This Page Added By Revision __
N3-PA-091 APPENDIX A Page:
Prepared By: CVJ ( /6V Checked By: /
1h6t7 b/Z174-Case 2 (Equation 9u)
Given Sall = M2-Fm(Do,Di,t) + P-Fp(Do,Di,t) t:= Find(t) tr2 := t tr 2 = 0.062in Case 3 (Equation 9e)
Given Sall3 = M3 .Fm(Do,Di,t) + P.Fp(Do,Dit) t:= Find(t) tr3:= t tr 3 = 0.041 in CRse 4 (Equation 9f)
Given Sall4 = M 4 -Fm(Do,Di,t) + P.Fp(Do,Di,t) t:= Find(t) tr4 := t tr4 = 0.019in Case 5 E~quation 10)
Given Sall = M5 .Fm(Do,Di,t) t:= Find(t) tr5 = t tr 5 = 4.461 x 10 3in Case 6 (Equation 11 - Eq 8 + Ea 1O)
Given S~al,= Fm(Do,Di,t)-(M5 + MI) + P.Fp(Do,Di,t) t:= Find(t) t6 = t tr6 = 0.027in This Page Added By Revision
N3-PA-091 APPENDIX A Page:
Prepared By: (4 4 . 4I Checked By: (/fr4 61'gjs Case 7 (Pipe Rupture = Eq 9u + E Given Sa;7 = Fm(Do,Di,t)-(M 5 + M2 ) + P-Fp(Do,Di,t) t=Find(t) tr7:= t tr7 = 0.037 in
- 9. Perform Stress Check Computations:
i:= l..4 Schkc:= M1-Fm(Do,Di,t&l + P-Fp(Do,Di,tr.' -S.,
M5Fm(Do,Di,tr)-sn Schk5 := M5- (D.Dwrs) -Sal5 Shk6 :=P.Fp(DoDi,tr6 ) + Fm(DO,Di,tr 6 ).(M 5 + MI) - Sall P-Fp(DoDi,tr 7 ) + Fm(DoDi~tr 7).(M. + NM 2 ) - Sajl If Sak equals zero for all cases, the routine is valid:
-0 Schlk= 0 psi 0
0 0
- 10. D etermine required thickness (trs) for hoop stress:
P-Do 0.106in 2 (Sh + P-0-4)
- 11. Since Equation 11 is governing relativeto Equation 10 and, from a required vallthickness perspective, Equation 11 is less restrictive than Equation 10, the required thickness from Case 5 may be disregarded in lieu of the required thickness for Case 6:
tr5 :=lf(tr5 > tr6,tr 6,tr 5) fr5= 4.461 x 10 3in tr6 = 0.027in
- 12. The Thickness (eq) Is the Maximum Value of tr (based on piping analysis stresses):
treq:= max(tr) treq = 0.106in This Page Added By Revision
N3-PA-091 APPENDIX A Page:
Prepared By: m yl qf6y Checked By:B:RXhb 6/V,-/04
- 13. Determine 30% of Nominal(trg) as required by Lead Civil Instruction WVBN-CI-004 tr 9 := 0. 3 tnom tr9 = 0.113in
- 14. The Controlling Thickness ( tj) Is the Maximum Value of tr (from 12 & 13):
tcontrol:= max(tr) tcontrol:= if(teq> tr9 itreqtr9 ) controi = 0.113 in MINIMUMALLOWABLE WALL THICKNESS VALUE itaV .913el3 This Page Added By Revision
I.
TENINESSEE VALLEY VMS ULTRASONIC CALIBRATION REPORT AUTrHORITY CALIBATION: NO. BOP 763 PROJECT:- WBN - UNIT: _1 CALIBRATION DATE 6124104 PROC.: I N.tUT. 26 REVJ T.C.: 22 CAL BLOCK NO.: 96-7582 TYPE: COS STEP INSTRUNfENT / TRANSDUCER DATA CAL BLK. TEMP.: 74 F THERMOMETER SIN: 558275 INSTRUMENT MANUF.: KBA THERM. CAL DUE DATE: 12-11-04 SERIAL NO.: E36024 DUE DATE: 08.5.04 COUPLANT: ULTRAGEL 11 TRANSDUCER MANUF.: KBA BATCH NO. 01225 SERIAL NO.: 74791 I SIZE: .50 FREQ.: 5 mhz INSTRUIENT SETTNGS I
i CABLE TYPE FXED LENGTH 72" PROBE: F}72E II ___
THICK CAL.: IPTE 2PTOS1 II RANGE .5 inches I = - - - VELOCITY:
V 2353 inJuS I A GAIN MOI M TCG MODE: SINGLE O P DUAL I0
_ ==
L RECTIFY: POSITIVE O I NEGATIvE 0 T FULL D U AMPLITUDE: NORMAL 0 D SCALE E DISPLAY WIDTH .5 inches CALIBRATION TINEES INITIAL CALTIME: 0030 (1) VERIFICATION TIMES REF. REFLECTOR OSTEP GAIN 54 dB 1)0300 1 2) 1 3) 14)
% METAL PATH: .1 inches 5) 1-6) 7)- 18)
AMPL 100 FINAL CAL TIME: 0530 COMPNJGRID(S) EXAMINED TEMP (2)
REF. REFLECTOR STEP GAIN 60 dB AT LEAK 71 F AMPL 100 %oMETAL PATH:- .5 inches I PIPE DIA DUS 71 F I PIPE DIA U/S 71 F 2 PIPE DIA UIS 71 F COMMENTS: W.O. CIRC AT LEAK 71 F Readings taken on ERCW Piping at leak BETWEEN CLAMP on 737 53TAt Ap.r2 z#3 75" EARS EXAMINER: IT4 LI. ANTI:
EXAMINER: f LvA. j/. DATE:
REVIEWER: )i . _t_ . LvI. PAGE 1 of lLI
I t-te .4 . %wF@*
AIl " , le AT LEAJC.dat . :.% -'Qt,
'. - t.k-i, ;t:. --: .
-- - - - --- File
- -- Header----- - - - - - - - - -
P.C. File Name : AT LF-AK.dat Gauge File Nme : - AT LEAK Description Memo Corrmnt I
- Creation Date 06/21/2004 D
Date Last Saved : 01/01/1997 Probe I Cal. Stnd.
Tehp. Comment I Inspector Company Instrument Type : DMS2 Instrument S.N. : OOYCRH Min. Alarm Val. 0.000 Max. Alarm Val. 0.000 I a Loss Alarm Val. 0.00 & Growth Alarm Val. 0.00 hbs. Loss Alarm Val. 0.000 Abs. Growth Alarm Val. 0.000 Units INCH Velocity (in/us) 0.2352 I. ----------------------------------File Statistics--------------------------------
Nuzmber of Readings 4 Number of Empties 0 Number of obstructs a Numbor of Attachments 0 Range 0.174 Mean 0.187 Median 0.184 Standard Deviation 0.072 Minimum Value 0.097 Minimum Value Loc. 4 : A : 1 maximum Value 0.271 Maximum Value Loc. 2 ; A 1 Minimum Value Alarms 0 Maximum Value Alarms 0 Percent Loss Alarms 0 Percent Growth Alarms 0 I
Absolute Loss Alarms 0 Absolute Growth Alarms ; 0
% and Abs. Loss Alarms 0 % and Abs. Growth Alarms: 0
Pilo comments-----------:------
A%: I:
B: H:
C:. N:
L:
M:
F: N :
C: 0 :
H: P:.
I I
I I
I I
Header Page 1 I
g.O
. .- is.
AT LEAKodat Data Page I
'Ia ..
.,:I . : ,I .. -.
CIRC I DIA DS.dat
File H ead er-----------------------------
P.C. File Name : CIRC 1 VIA DS.dat Gauge File Name : CIRC 1 DIA DS DescriptiOn Mem3 Comnent :
Creation Date I 06/21/2004 Date Last Saved : 01/01/1997 I ProbeI Cal. Stnd.
'emP. Comment Inspector Company Instrument Type : DMS2 Instrument S.N. : OOYCRH Min. Alarm Val. O.000 Max. Alarm Val. 0.000 I Loss Alarm Val. 0.00 % Growth Alarm Val. 0.00 Abs. Loss Alarm Val. 0.000 Abs. Growth Alarm Val. 0. 000' Units INCH Velocity (in/us) 0.2352
File Statistics--------------------------------
Number of Readings 8 Number of Empties a Number of Obstructs 0 Number of Attachments 0 Range 0.062 Mean 0.363 Median 0.356 Standard Deviation 0.027 Minimum Value 0.325 Minimum Value Loc. 2 : A :1 Maximum Value 0.387 Maximum Value Loc. 6 : A :1 Minimum Value Alarms 0 Maximum Value Alarms 0 Percent Loss Alarms 0 Percent Growth Alarms 0 Absolute Loss Alarms 0 Absolute Growth Alarms : 0
% and Abs. Loss Alarms 0 % and Abs. Growth Alarms: 0
File Comments------------ ---------------------
AI I:
B :
C: K:
D : L:
E :
F:
G: 0:
H:
II t
I Header Page 4 All
- . ,+ Ws*~
_~~~ ... ..
CIRC 1 DIA DS.dat
.~.
'I V;/
Date Page 1
,..* jI .
- .: > -1 "I , . .. ,
CIRC 1 DIA US.dat I
- - - - -File Header----------------------------------
P.C. File Name : CIRC I VIA US.dat Gauge File Name : CIRC 1 DIA US Description Memo Comment Creation Date 06/21/2004 Date Last Saved : 01/01/1997 ProbQ Cal. Stnd.
Temp. Commtnt Inspector Company Instrument Type : DMS2 Instrument S.N. : OOYCM Min. Alarm Val. 0.000 Max. Alarm Val. : 0.000
& Loss Alarm Val. 0.00
- Growth Alarm Val. : 0.00 Abs. Loss Alarm Val. 0.000 Abs. Growth Alarm Val. : 0.000 Units INCH Velocity (in/us) : 0.23S2
File Statistics---------_--------------------
Number of Readings 8 Number of Empties 0 Number of Obstructs 0 Number of Attachments 0 Range 0.051 Mean 0.365 Median 0.360 Standard Deviation 0.016 minimum Value 0.334 Minimum Value Loc. 3 :A : 1 maximum Value 0.385 Maximum Value Loc. 5: A: 1 Minimum Value Alarms 0 Maximum Value Alarms I 0 Percent Loss Alarms 0 Percent Growth Alarms 0 Absolute Loss Alarms O Absolute Growth Alarms : 0
- and Ab5. Loss Alarms O % and Abs. Growth Alarms: 0
File Comments---------------------------------
A : I :
B:
C:
I:
X:;
D : L t E : H:
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G; 0:
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Header Page 2
CIRC 1 DIA US.dal 0.379 0.334 a 0.362 0370.
0..;
to.
DtPae
'I
- 5,,
Det Pg 1f
41...
' AVJ'-
CIRC 2 DIA Us.dat
-File H e a d er----------------------------------
P.C. File Name : CIRC 2 DA.US.dat Gauge File Name : CIRC 2 DIA US Description :
Memo Co=ment Creation Date CJ6/21/2004 Date Last Saved: 01/01/1997 Probe Cal. Stnd.
Tfmp. Commente :
Inspector company Instrument Type s DXS2 Instrument S.N. : OOYCRH Min. Alarm Val. 0.000 Max. Alarm Val. 0 .000 t Loss Alarm Val. 0.00 % Growth Alarm Val. 0.00 Abs. Loss Alarm Val. 0.000 Abs. Growth Alarm Val. a.000 Units INCH Velocity (in/us) 0.2352
File statistics--------------------------------
Nunber of Roadings 8 Number of Empties 0 N4urber of obstructs 0 Number of Attachbmnts 0 Range 0.017 Moan 0.380 Median 0.382 Standard Deviation 0.007 J1 kMinimum Value 0.373 Minimum Value Loc. 3 :. A: 1 Maximum Value 0.390
-Maximum Value Loc. 1 : A : I Minimum Value Alarms 0 Maximum Value Alarms : 0 Percent Loss Alarms 0 Percent Growth Alarms 0 Absolute Loss Alarms 0 A bsolute Growth Alarms : 0 t % and Abs. Loss Alarms 0 A and Abs. Growth Alarms: 0
File Co=ments--------------------------------
A I :
B : %T:
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I Header Page I
'. -~~ ~ .
..:.5),Ats
.,-.1.
CIRC 2 DIA US.dat J.S C .R
-A.;Cex
,ih
%g1o'4" 02390
- 2
- .-: 5:A, 02874 0>374 0.383 Cw,..0........ ,3,8,,
0.373 0.
a .
Data Pape 1
.; W-Fj - e-.J CIRC AT LEAK.dat
-__________-- __-------------------File Header --------------------------------
P.C. File Name : CIRC AT LEAK.dat Gauge File Name : CIRC AT LEAK Description Memo Comment Creation Date 06/21/2004 Date Last Saved 01/01/1997 Probe cal. Stnd.
Temp. Comment Inspector Company :
Instrument TyPO DMS2 Instrument S.N. : OOYCRH Min. Alarm Val. 0.000 Max. Alarm Val. 0.000
% Loss Alarm Val. 0.00 % Growth Alarm Val. 0.00 Abs. Loss Alarm Val. 0.000 Abs. Growth Alarm Val. 0.000 Units INCH Velocity (in/us) 0.2352
File Statistics--------------------------------
Number of Readings 2 Number of Empties 6 Number of Obstructs 0 Number of Attachm.ents 0 Range 0. 001 Mean 0.341 Median 0.341 Standard Deviation 0.001 Minimum Value 0.340 Minimum Value Loc. 7 : A : 1 I Maximum Value 0.341 1 Maximum Value Loc. 1 ;A : I 11 Minimum Value Alarms 0 Maximum Value Alarms 0 1 Percent Loss Alarms 0 Percent Growth Alarms 0 Absolute Loss Alarms 0 Absolute Growth Alarms : 0
% and Abs. Loss Alarms 0 % and Abs. Growth Alarms: 0
File Comments---------------------------------
A: I:
B: a:
C: K:
D : L:.
E : M:
F: N:
G: 0:
H : P:
t Header Page I (0040[
' I CIRC AT LEAKdat f3peiceV CLAPIP FAKs Data Page 1
-1 _
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I _
6 7 8 9 I- I I! I I!; I I ! I '. # I
- I I I :I I I ' 'I
_._. ._... . . I I I . _ -L CO4T. ON PROB.
N 03A 5A, 10 a;-150' eBuID FL .l M-1trRtfl=P (FLooo MoOa 1'
0 4' @!
( -1.
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,-44 sce. 40 B b.
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Il 14 !
FOR COI`JT SeE 4 Eolm4r.' I R t E:L..74-N-1"(RP.)-
. 0 a TENNESSEE VALLEY DMS ULTRASONsIC CALIBRATION REPORT AUTHORITY CALIBRATION NO. BOP-769
., . 7///,o PROJECT: WBN UNIT: I CALIBRATION DATE C4Yn j'o4 i PROCEDURE N-UT- 26 REVJT.C.: 22 CALBLOCKtNO.: 94-6403 TYPE: CS STEP INSTRUMENT /TRANSDUCER DATA CAL BLK. TEMP.: 71 F THERMOMETER S.fl: 562776 INSTRUMENT MANUF.: KRAUTKRAMER THERM. CAL DUE DATE: 12/11/04 SERIAL NO.: E36020 DUE DATE: 6/3/05 COUPLANT: ULTRAGEL TRANSDUCER MANUF.: KBA BATCH NO. 01225 SERIAL NO.: 00F23F SIZE: .38 FREQ.: 8 mhz INSTRUMENTSETTINGS CABLE TYPE FIXED LENGTH 72" PROBE: FH2E THICK CAL.: I PTLI 2PTFT
- " RANGE .5 inches VELOCITY: 2330 inJuS
-I A GAIN MO DOh M TCG MODE: SINGLE L P DUAL L RECTIFY: POSITIVE Q1 I NEGITIVE E T FULL Ul U AMPLITUDE: NORMAL [9 D SCALE E3 DISPLAY WIDTH .5 inches CALIBRATION TIMES INITIAL CAL TIME: 1200
- (I) VERIFICATION TIMES REF. REFLECTOR STEP GAIN 58 dB 1)1300 12) _3) 14)
AMPL 100 % METALPATH:.I inches 5) 16) 17) 18)
FINAL CAL TIME: 1400 (2) COMPN.IGRID(S) EXAMINED TEMP REF. REFLECTOR STEP GAIN 58 dB 737 ERCW LEAK 78 F AMPL 100 % METAL PATH: .5 inches _
COMMENTS: WO 04-81 8758-000 _f_
EXAMI N E R : , Lv1. ANII: L)
EXAMINER. A*- LvI. , DTE:
E L . PJ E10- 7A REVIEWER: Lvl.
j; PAGE I of ?
I
Sheett SYSTEM: t 7Report No.
COMPONENT: HrPE w aeb-71tA EAK EVALUATION t- FLOW Upstream
'p I I 0If Inpco 72 -I) 1ae-7/
Page/I
--.. ---- --. ---- .- -a---. . -. .. - .
a-SY-47F430-246tA.
~REFERENCE DRA WINGS
-248ff. -749 -250 0-67-579 \ 47{450-J02A. -JOZ0 -J02t;
%0' PROULM NJ-3-7-07A A -23A O's LECEND S' I&C l ( 0 G4 IM su1~par RICID (FsCJrOMCDfa.
SuPADlr trvJvcrioA' AJ-
/. ffc K VAffIAVLC SrPPO (rL#tILW i' - MMANICA4L SNWJOB( (fUtCI"JO COJ D I. -j .@ASUC CC-J ((OUIVALtfr)
_ 7AL*060-67-076 67-IERC-R0f 4 4YA060-67-OY6-IA 6Z- lE'RC-VO¢J _ Syt,'RCwRO Z f
- v. I 67-IRCVr-RO42
\ .' ?# I - oo66-lrR C R16-SY\f6ZERCff-Rt1 - IA tCY-67-12 S- tRCW-RO8O0 67 ,
X ~ ~~ ~ ~ ~ ~ ~ ~ ~ 7 7cV2C-trinR#@lEXC\B+AX I7Va9IN
\ ,I/-7-re171
,67-I(RCW-R 140 I 76Z-IERCV-ROJI
- a. 57-f-qFCV3'OJ2 II(ERCW-RI 42 47A450-02-J08 ' -/
o^O ~57 IIrtcV-I? 144> ^
\I> Or, / 67- tERCW-Rff45
/ / 4YA450-04-045 4'...67 ER -fOS-8-lERcw-R092 '--
cVns. 67M 0AC fII *Afja ,WW'..J9 DIM I
- N WAITS BAR NUCLEAR PLANT frV67 81 " ~UNIT I 3X24 ' SUPPDflS LOCArIONS O M ,0,01 I OC'D A" s Mr I-rCY-6-J25' r -01 1i-C-07 t ; - -- -37
ENCLOSURE ATTACHMENT 3 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 REQUEST FOR RELIEF 1-RR-6 GENERIC LETTER 90-05 STRUCTURAL EVALUATION
Calculation N3-PA-091 Attachment A Prepared By: (P7J 12 2/o4 Checked By: 2 ). 7 7/2404 This Page Added By Revision PURPOSE:
The purpose of this evaluation is to determine the structural adequacy of a location which is leaking. -The leaking location is located on ERCW piping near valve 0-ISV-67-529. The leaking pipe is part of Rigorous Analysis Problem N3-67-02A.
REFERENCES:
- 1. Inspection Report BOP-769.
- 2. Design Standard DS-C1.2.8.
- 3. Calculation N3-67-02A, Rev 20, RIMS # T71 030522 802.
- 4. Drawing 47W450-302E.
EVALUATION:
The reference 1 inspection data provided readings for the leaking location. This evaluation will be in accordance with the rules established by reference 5. -
Reviewing the reference 4 isometric drawing, the leaking location is between node points 466B and 1143 in the analysis model. The actual piping stresses from the reference 3 analysis will be used in the structural evaluation. The maximum stresses between the above node points will be used. No reduction in moment will be made for any modeled SIF's of the span in question (conservative - moments will remain intensified). The following is a list of maximum existing stresses and associated moments for node points 466B - I143:
w.. 2,014 psi cs 2,342 psi amu 2,902 psi a9F = 3,413 psi aio = 283 psi Using the previously tabulated values, the following pages (refer to pages A. - A. )
determine a minimum average wall thickness value of 0.113" (360 degrees around the pipe).
This value is based on the maximum input bending stresses for the identified locations from the reference 3 piping analysis. This value represents thin, however since the controlling load case is 0.3 x to, the minimum ASME Code required value of 0.106" (Hoop Stress) will be used in the Generic Letter 90-05 evaluation. Reference 5 requires the use of toi be based on "code-required minimum wall thickness" and in addition, using the 0.106" is more conservative than using 0.113" in a Generic Letter 90-05 evaluation.
Page A.
Calculation N3-PA-091 Attachment A Prepared By: 772. Checked By: aJL ( 7 7/04 This Page Added By Revision In determining the value of "a" for the Generic Letter 90-05 evaluation a conservative approach was taken: From the reference 1 inspection data, the diameter of the hole is 5/8" and on three sides (2, 3, 4) the readings adjacent to the leak exceed to. On the final side the reference 1 inspection data identifies a distance of 3/16" to reach a value of 0.106" or ta.
Therefore, for conservatism the values of 2a is taken to be the hole size (5/8") plus twice the 3/16". This is a conservative approach of using the 3/16" on each side of the hole instead of just the one where it was measured. Referring to the structural integrity evaluation performed in accordance the reference 5 methodology (refer to pages A. - A. ) the calculated value for fracture toughness, based on the piping properties, is less than the lower bound generic value of 35 ksi(in)f5 , thus the flaw location is considered acceptable.
CONCLUSION:
From the above evaluation, at the location of the leak, the flaw satisfies the criteria of Generic Letter 90-05 for evaluation approach and is considered acceptable. No further evaluation is required.
Page A.
Calculation N3-P O0 Attachment A Page:
Prepared By: XW7J) 0f Checked By: lW11r.,, 7/13/104 THIS ROUTINE PERFORMS A STRUCTURAL INTEGRITY EVALUATION OF FLAWED PIPING IN ACCORDANCE WITH THE RULES DESCRIBED IN GENERIC LETTER 90-05.
- 1. Initialize ksi and psi units 1000.bf bf ksi:= 100-pi=:= *
.2 .2
- nm Sketch of Flaw Parameters:
I 2a = 1.0 in I I- ' -
0.625 in I Tg,, =0.106 in II J
The value of 2a ha been.conserativ&ly tak"C'n to be -the'.5/9"lok plus, 3116"ouitoffie 0306".minitniLim'thickness on-each side.
- 2. Input Pipe Data - Outside Diameter (Do), Nominal Thickness (),J, Code Required Minimum Wall Thickness (tin..,), Equation 10 + 9F PipingStress (S) and through-wall flaw length (a):
Do:= 20.000-in tnom:= 0.375.in tmin:= 0.106-in S := 3.696-ksi a:= 0.500 in This Page Added By Revision
Page:
Attachment A Calculation N3.PA-991, Calculation N3-PA-9 1)2/ Attachment A Page:
Prepared By: i/2/D4 D44 Checked By: / 7/1 31/
- 3. Define Functions For Cross Section Dimensions andProperties R= (Do- t\ ) R= 9.947in Mean Pipe Radius 2) r:= - R r= 93.84 Rm / t Ratio a
c =
(3.1416-R) c=0.016 Flaw over rRatio
- 4. Define Functions for Coefficients In Circumferential Flaw Crack Stress Intensity Equation 23 A:= -3.26543 + 52784-r- 0.072698-r + 0.0016011.r 3 2_- 0.004099r33 B := 11.36322 - 3.91412-r+ 0 18619.r C :=-3.18609 + 3.84763-r- 0.18304*r2 + 0.00403-r3 A= 822.99 B = -.2.104 x 13 C = 2.076 x 103 1.5 2.5 3.5 F:= 1 +Ac-c.+B.c +C.c35 F = 2.599 This Page Added By Revision
Calculation N3-P-9 1 achment A Page:
Prepared By: L J1f ri Checked By: lm t 7 7/3/o
- 5. Based on Linear Elastic Fracture Mechanics and assuming a pipe thickness of Mt mn, the stress intensity factor "K" is computed:
K := .4-S.F.[(3.1416.a).-5]
pit6.8S23si inv1
Conclusion:
Since the calculated value of K = 16.9 ksilinp)5 is less than the Generic Letter 90-05 required value for carbon steel of 35 ksiinYp5. The flawsatisfies the criteria of this evaluation approach.
This Page Added By Revision _
i TENNESSEE VALLEY lDMS ULTRASONI1C l CALIBRATION REPORT AUTHORITY CALIBATIONE NO. BOP-769
. .. .7///0. _
PROJECT: WBN UNIT: I CALIBRATIONIDATE nl 7/e I PROCEDURE N-UT- 26 REVJ T.C.: 22 CAL BLOCK NO.: 94.6403 TYPE: es STEP INSTRUMENT /TRANSDUCER DATA CALB LK. TEMP.: 7t F THERMOMETER SN: 562776 INSTRUMENT MANUF.: KRAUTKRAMER THERM. CAL DUE DATE: 12111/04 I SERIAL NO.: E06020 DUE DATE: 6/3/10 COUPLANT: ULTRAGEL TRANSDUCER MANUF.: KBA BATCHNO. 01225 SERIAL NO.: 00F23F SIZE: .38 FREQ.: 8 mhz INSTRU'MENT SETTINGS CABLE TYPE FIXED LENGTH 72" PROBE: FH2E THICK CAL.: IPTH 2PTM-J RANGE .5 inches VELOCITY: 2330 inJuS
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M TCG MODE: SINGLE C P DUAL 1 L RECTIFY: POSITIVE 0
_EGITIVE N s T FULL U AMPLITUDE: NORMAL-D SCALE El E
DISPLAY WIDTH .5 inches CALIBRATION TIMES
.___ INITIAL CAL TIME: 1200 (I) VERIFICATION TIMES REF. REFLECTOR STEP GAIN 58 dB 1)1300 2) 13) 14)
AMPL 100 % METALPATH:.l inches 5) 6) 7) 8)
FINAL CAL TIME: 1400 (2) COMPN.IGRID(S) EXAMINED TEMP REF. REFLECTOR STEP GAIN 58 dB 737 ERCW LEAK 78 F AMPL 100 % METAL PATH: .5 inches COMMENTS: WO 04-818758-000 E X AMMI Ll~v. _g ANII :
EXAMINER: -A-k- LVI. t3ATE:
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Sheetl TVA PROJECT ti 1 i M SYSTEM: 7 Report No.
Office of Nuclear Power Inspection Services Organizaton UNIT: I COMPONENT: I-ZPE ,t6P-- 719; ULTRASONIC INSPECTION LEAK EVALUATION
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