ML20246D802
| ML20246D802 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/21/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246D800 | List: |
| References | |
| NUDOCS 8908280273 | |
| Download: ML20246D802 (15) | |
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I SAFETY. EVALUATION BY.THE OFFICE OF WUCLEAR REACTOR REGULATION REGARDING REQUEST FOR RELIEF FROM INSERVICE. INSPECTION REQUIREMENTS SYSTEM ENERGY RESOURCES, INC.
, GRAND. GULF NUCLEAR STATION. UNIT I DOCKET N0. 50-416
1.0 INTRODUCTION
The Technical Specifications for the Grand Gulf Nuclear Station, Unit 1, state that the inservice inspection (ISI) of ASME Code Class,1, 2, and 3 components shall be performed in compliance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Comission pursuant to 10 CFR 50.55a(g' "'(1).
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Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practical for its facility, information shall be submitted to the Commission in support of that determination and a request made for relief from the ASME Cede require-ment. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i),
the Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will ndt endanger life or property or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
By letter dated May 24, 1988, System Energy Resources, Inc., (the licensee) requestec relief from certain inservice inspection requirements of Section XI, 1977 Edition, including the Summer 1979 Addenda, of the ASME Code for the Grand Gulf Nuclear Station, Unit 1. ISI Relief Request Nos. I-00007 (Rev. 1), 1-00010 (Rev. 2) and I-00019 and supporting information were evaluated by the staff.
Our conclusions are reported in this Safety Evaluation.
Unless otherwise stated, reference to the Code refers to the ASME Code,Section XI, 1977 Edition, including Addenda through Summer 1979.
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2.0 EVALUATION-RELIEF REQUEST NO. I-00007, REVIS10t! 1 l
Component - Circumferential welds in piping inside guard pipes in the following systems:
Feedwater Loops A and B (B21)
Main Steam (B21)
Reactor Core Isolation Cooling (E51)
Residual heat Removal (E12)
Reactor Water Cleanup (G33)
The welds are identified in Table 1.
Code Requirement - Section XI ASME Code Examination Category B-J, Table IWB-2500-1: volumetric and surface examination once each ten-year inspection interval.
Relief Requested - Request is rade to perform volumetric and surface examination through 4-in. by 6-in access ports to the extent possible. The extent of examination will be recorded at the time the welds are examined. 4 Basis for Relief - The circumferential welds joining the flued head and the process pipe are encased in portions of the guard pipe extending beyond 1 cor.tainment. In order to comply with Section XI ASME Code examination require-ments, two 4-in by 6-in. access ports spaced 180 apart were provided for weld inspection. Prior to fabrication, it was thought that the access ports would permit examination of the welds. However, after fabrication and installation, it was found that the entire length of the welds was not accessible through the access ports.
Relief is requested for the examination requirements on inaccessible portions of welds located inside the guard pipes for the following reasons:
a) All but two of the lines were designed to high energy pipe break criteria; the exceptions were classified as moderate energy pipe.
b) The welds were designed and fabricated to ASME Section III, Class 1 requirements and were examined by radiographic and liquid penetrant techniques.
c) The welds have satisfactorily passed both liquid penetrant and ultra-sonic examinations to ASME Section XI, Class 1 requirements.
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' d) Class 1 isolation' valves in the process pipe on both sides of the guard pipes are capable of completely isolatin'g each pipe in the E w event of a pipe failure.
e) The guard pipes have been designed and fabricated in'accordance with ASME Section III, Class 2 requirements and were hydrostatically tested in accordance with ASME Section III, Class.2 requirements.
x f) The guard pipes are open to the drywell environment;.thus, any leakage
< l' due to weld failure will be contained within the drywell.. The guard pipes will prevent any leakage from escaping to the Containment Building.
g) 'The process pipes inside the guard pipes were hydrostatically ' tested to ASME Section III, Class 1 requirements.
h) The process piping inside each guard pipe assembly will be subject to periodic pressure tests ~in accordance with ASME Section XI, Table JWB-2500-1, Category B-P, requirements.
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Alternative Examination - The accessible' length of each weld will be ultrasoni-cally and surface examined in accordance with ASME_ Section XI, Table IWB-2500-1, Examination Category' B-J. Should signs of weld deterioration be noted during regular inspections, evaluation of the conditions will be made.
Conclusion -~We' conclude from our evaluation that the Section XI ASME Code requirements are impractical for welds in piping inside guard pipes. Compliance to the code requirement for 100% examination of these welds would require the.
redesign and prefabrication of the guard pipes. The proposed alternate examina-tion of the accessible length of each weld will provide reasonable assurance of structural'initegrity. Therefore, relief should be granted, as requested in Relief Request No. I-00007. Revision 1.
i RELIEF H QUEST NO. I-00010. REVISION 2 Component - Inaccessible part of ASME Code,Section III Class 1 and Class 2 pressure retaining and integral attachment piping welds. The welds and systems are identified in Table 2.
Code Requirement - Class 1 and Class 2 pressure retaining piping welds are requirea to be volumetrically and surface examined, essentially 100% of the weld, once every ten year interval pursuant to ASME Code,Section XI, Table IWB-2500-1, Category B-J, anc Table IWC-2500-1. Category C-F.
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. ., l lL Class 1 integral. attachment welds.shown in Table 2 are required to be surface examined once each ten year interval in accordance with Section XI, Table IWB-2500-1, Category B-K-1.
Relief Requested - The accessibility of the welds for surface and volumetric examination is shown in Table 2. The areas were determined during preservice examination. The code requirement for 100% surface and volumetric examination is. not practical. Request is made to perform the surface and volumetric examinations'as recorded in' Table 2.
Basis for Relief - The licensee stated that the requested relief should be granted for the following reasons:
a) The inaccessible portions of listed pressure retaining welds were examined by radiography, passed in accordance with ASME Section III, Class I and 2 requirements.
b) The inaccessible portions of the pressure retaining and integral attachment welds were surface examined (magnetic particle or liquid penetrant), passed in accordanc.e with ASME III and/or XI, Class 1 and Class 2 requirements. '
c) The inaccessible portions of listed piping welds will be subject to a system leakage test after each refueling outage for Class 1, and each inspection period for Class 2 in accordance with ASME Section XI requirements, d) The inaccessible portions of listed piping welds will be subject to a system hydrostatic test each inspection interval in accordance with ASME Section XI, Class 1 and 2 requirements.
e) Accessible portions of listed welds will be volumetrically and surface examined each inspection interval in accordance with ASME Section XI. Should indications be found, an engineering evaluation will be made to determine if the inaccessible portions of the listed welds have been affected.
f) Leak detection is provided, by way of the leakage detection system with continuous monitoring, for the RHR, RCIC, MS, RWCU, RECIRC and FW systems.
g) The failure of any one of these pressure retaining piping welds would have no adverse effect on plant safety as there is isolation capability and/or shut down capability as part of the plant design.
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h)- The calculated maximum piping stresses and usage factor at the integral attachments on the piping, including consideration of the local pipe. wall stresses, have been determined in the Class 1 stress report and are equal to the following:
- 1) Primary plus secondary (equation 30); 32,775 psi (1.72 S ,),
- 2) Usage factor is 0.0442.
s Circumferential and longitudinal welds in piping with stress levels below 2.4 S and usage factors below 0.4 are excluded from ISI examination, in accordance with Table IWB-2500-1, Category B-J.
- 1) Examinations at GGNS of category B-J, B-K-1 and C-F welds have not identified any flaws or evidence of service induced degradation.
Alternative Test - The accessible parts of the subject welds identified in Table 2 will receive volumetric or suface examination at least twice every l ten-year interval in accordance with the requirements of Section XI ASME Code.
Conclusion - We conclude, from our review of the information submitted that the section XI ASME Code requirements are impractical for the piping welds identified in Table 2. Compliance to the Code requirements would require the redesign and prefabrication of the piping systems to eliminate physical obstruc-l tions due to pipe supports, pipe fittings and components. The proposed alternative limiteo volumetric examination, along with the Section XI ASME Code, surface examination ano the hydrostatic test, ensure an acceptable level of inservice structural integrity. Therefore, relief should be granted as requested in Relief
' Request No. I-00010, Revision 2.
RELIEF REQUEST NO. I-00019, REVISION 0 Component - Inaccessible parts of the Reactor Pressure Vessel as follows:
a) Jet Pump Instrument Nozzles (N-9 A&B), safe end to penetration seal welds.
b) RPV flange stud hole ligament area Code Requirement a) ASME Code,Section XI, 1977 Edition, including Summer 1979 Addenda, Table IWB-2500, Category B-J requires the saf e end to penetration 1 seal weld to be volumetrically and surface examined once each inspec-tion interval.
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.,. d b) ASME Code,Section XI,;1977 Edition, including Sumner 1979 Addenda, Table IWB-2500. Category B-G-1, requires the threads in the RPV flange stud hole, and one-inch of base material around the stud hole, to be volumetrically examined for. a depth equal to the diameter of the stud once each inspection interval.
-Relief Requested - Reliet is requested from the ASME Code Section XI required 100% volumetric examination r V (a) the safe end to penetration seal weld in the N9 nonles and-(b) the ligament section in the Reactor Pressure Vessel flange between the stud hole and the inside surface. The extent of the volumetric-examination in these areas is described in Relief Request No. I-00019, Revisien 0.
Basis for Relief - The Licensee stated that the ASME Code Section XI required volumetric examination should be limited to the accessible areas for the following reasons:
P9 Nozzle to Penetration Seal a) The subject welds were installed, radiographer, surface examined and tydrostatically tested to the requirements of ASME Section III, Class 1. O b) The subject welds are surface examined during inservice activities once each inspection interval, c) The welds are subject to a system ledage test at completion of each refueling outage and a system hydrostatic test once each inspection interval.
, d) The safe end material is SA 336-f8 (304) stainless steel, and the penetration seal is 304L stainless steel. Due to the configuration of the weld joint, the examination can only be conducted from the
! safe end side of the joint, and therefore, not obtaining full cover-
! age. The examination is able to obtain 44.7% of the ccde required i volure. The examinable area includes the inside surface of the safe end (304 stainless steel material) including the heat affected zone.
The primary degradation mechanism at this location is intergrar.ular l stress corrosion' cracking {ICSCC). Fatigue is not a significant l: factor due to the limited fatigue loading at this location. There-fore, the potential for cracking at this location should consider IGSCC cnly. The occurrence of IGSCC is caused by the simultaneous presence of three factors; 1) high stress, 2) aggressive environment, and 3) susceptible material. The safe end and penetration seal side of the weld both are subjected to essentially the same stress and environmental conditions. However, there is a difference in material
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.j susceptibility between the 304 SS safe end and the 304L' penetration seal. . Generic Letter 88-01, NUREG 0313 Fevision 2, recognizes 304L
. type materials as being IGSCC resistant. ' The 304 portion of the asse21y including that side of the weld root is examined from one direction utilizing IGSCC techniques and qualified personnel. In addition, Generic Letter 88-01 excludes all piping smaller than 4-inches in nominal diameter. The N9 A&B safe ends are less than febr inches in nominal diameter, and therefore, under the rules of .
the generic letter, the safe ends are not susceptible to IGSCC.
e) The accessble portions of the subject welds will be volumetrically examined and the complete weld and adjacent base material will be surface examined in accordance with ASME Section XI. Should indica-tions be found, an engineering evaluation will be made to determine if the inaccessible portions of the subject welds have been affected.
f) Any leakage occurring from the N9 nozzles would be detected by the existing leakage detection system.
g) Mechanical preparation of the weld would allow additional coverage to be obtained by facilitating' transducer placement on top of the weid. The efforts necessary for obtaining the improved coverage g would require a man rem expenditure of approximately 21.2 whole body and 37.2 for the extremities. The total man rem exposure required to obtain the additional examination coverage is not justified based on the low probability of IGSCC occurrence and the limited fatigue loading at the subject welds.
h) Examination history at GGNS has not recorded any flaws or evidence of service induced degradation in Category B-J welds.
I' i) The limited examination of the two N-9 nozzles (A&B) is considered to be sufficient to determine the structural integrity of welded assemblies.
Stud Hele in the Reactor Pressure Vessel Flarce l'
a) The RPV flange was fabricated as part of the KPV assetly and tested to the requirements of ASME Section III, Class 1.
b) The RPV, including the flange asse21y, is subject to a system leakage test at ccmpletion of each refuelirg outage and a system hydrostatic test once each inspection interval.
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c) The entire code volume around the stud hole is examined except for the area associated with the sealing surface. This area is examined for a distance of f inch from the stud hole before interference from the seal surface is encountered. With the RPV head in place, and fastened with the studs to the RPV shell flange, the seal surface and underlying material is subjected to compressional loads. The material in the vicinity of the threads or adjacent to the stud hole is subjected to shear loading with the head in place. Therefore, the limiting location with respect to applied steess is the material nearest the stud hole threads. Since this limited crea is examined, any anticipated flaw initiation will be detected.
d) The amount of obtained volumetric coverage that includes the bounded area is adequate to ensure structural integrity of the stud hole regions of the RPV flange.
Alternative Test - The N-9 nozzle welds and the RPV shell flange ligament area will be surf ace examined and volumetrically examined to the extent practical as described in Relief Request No. I-00019 Rev. O.
Conclusion - We conclude from our review bf the information submitted that the Section XI ASME Code requirements are impractical for the jet pump instrument nozzle safe end to penetration seal welds and the reactor pressure vessel flange stud hole ligament sections. Compliance to the Code requirements would requtre redesign and prefabrication of the jet pump instrument nozzic welds and the reactor pressure vessel flange to eliminate obstructions to the required examinations. The proposed alternative limited volumetric examination of these welds and ligament sections, together with the required surface examina-tion and pressure test, will provide assurance of an acceptable level of structural integrity. The welds will be volumetrically exam 1ned to 44.7 per cent and the ligament sections in the flange to 96.0 per cent of the Code requirements.
i Therefore, relief from the Code requirements should be granted as requested in l
Request No. I-00019, Revisica 0.
3.0 CONCLUSION
By letter dated May 24, 1989, the licensee has determined that certain require-ments for inservice inspection in the ASME Code Section XI are impractical and has requested relief. We conclude from our evaluation of the licensee's submittal that these examination requirements are impractical to perform at the Grand Gulf Nuclear Station Unit 1. We further conclude that for the components for which relief was requ,ested, the proposed alternative examinations identified in this Safety Evaluation give reasonable assurance of the piping and component
! pressure boundary and component support structural integrity. Pursuant to 10 CFR 50.55a(g)(6)(1), the staff has determined that the granting of the relief l
requested is authorized by law, will not enoanger life or property or the I common defense and security, anc is otherwise in the public interest. The l
staff has given due consideration to the burden upon the licensee that could l
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- result if the requirements were imposed on the facility. Accordingly, relief <
.is granted for Relief Requests Ne. 1-00007 Revision 1,'No. I-00010. Revision 2, and No. I-00019. Revision 0. The. relief granted is conditioned on the proposed alternative examinations.
4 principal Contributor: F. Litton
. Dated:
August 21, 1989 N
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