ML20093G940
| ML20093G940 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/05/1995 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20093G931 | List: |
| References | |
| PROC-951005, NUDOCS 9510190294 | |
| Download: ML20093G940 (77) | |
Text
{{#Wiki_filter:: (~') SOUTHERN NUCLEAR OPERATING COMPANY INSPECTION AND TESTING SERVICES FOR GEORGIA POWER COMPANY ISI/IST APPROVAL l 1 Written by:fMC -ITS Depf. j INSERVICE INSPECTION PROGRAM Reviewed by:Od/M*//[ l THIRD 10-YEAR INTERVAL Eng.Supv / kA / M ' E. I. HATCH NUCLEAR PLANT Mgr. EnE: M l 1 QA Review: Ya /*-i-h UNITS 1 and 2 s/ PR8No.: 96 87 / /o.,q.95 AGM-PS:_%5%& s dslq '
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LIST OF EFFECTIVE PAGES Pagca Revision Distribution List 1 0 Table of Contents 1 0 Introduction 1-3 0 Index ofReliefRequests 1-2 0 ReliefRequests RR-1 thru RR-11 0 Table 1 for Class 1 Components 1-14 0 Table 2 for Class 2 Components 1-6 0 Table 3 for Class 3 Components 1-3 0 Table 4 for CIEss 1,2, and 3 Component Supports 1 0 m NUREG d Hatch Unit 1 NUREG-0313 Summary 1-12 0 Hatch Unit 2 NUREG-0313 Summary 1-3 0 l i 4 O HISIPROG < Rey, O Page1of1
] Hatch Nuclear Plant Units 1 and 2 ISI Program Holder Manual Number E. C. Sorrell 1 C. V. Syx 2 C. D. Willyard 3 ITS Shelf Copy. 4 ITS ShelfCopy 5 NRC Resident Inspector - Hatch 6 ANII 7 R. W. Healey 8 W. H. Cole 9 W. M. Wright 10 C] , i l
l I a ! I 4 0- HISIPROG Rey, O Page1of1
TABLE OF CONTENTS Introduction ReliefRequests (including Index) Table 1 for Class 1 Components l Table 2 for Class 2 Components 4 Table 3 for Class 3 Components Table 4 for Class 1,2, and 3 Component Supports
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NUREG O i 1 i t 0 HISIPROG Rev.0 Page1ofI
J 4 GEORGIA POWER COMPANY (v3 PLANT HATCH, UNIT 1 & 2 i THIRD 10 YEAR INTERV AL INSERVICE INSPECTION PROGRAM i INTRODUCTION j This ISI Program document was developed to comply with the requirements of the ASME Boiler and Pressure Vessel Code, Section XI,1989 Edition, to the extent practicable.
; Where Code requirements are impractical, relief requests were developed to provide for
- alternative examinations and/or tests. The use of relief requests and Code Cases are
; documented in the Program Tables where applicable. The Requests for Relief are ;
numbered RR-1, RR-2, etc. Some may be generic in nature and not applicable to a l i particular Code Category. l Third 10-Year Interval This program document is applicable for the Third 10-Year Interval ISI update. The Third 10-Year Interval begins on January 1,1996 and ends on December 31,2005. In
- order to use the same edition of the Code, Georgia Power Company has historically
- received relief from the NRC to early update Hatch Unit 2. Therefore, relief has been
! requested (see RR-8) to continue this practice for the Third Interval and for the remainder p of plant life. Upon approval of relief request, the Third Interval for Hatch Unit 2 will begin on January 1,1996 and end on December 31,2005 (the same as for Unit 1). I I , Code Cases The Code Cases that may be applied for specific Code Categories and Items are listed in j the Program Tables. Code Cases that are generic in nature and would be applied on a case-by-case basis are not listed in the Program Tables. The use of generic Code Cases will be documented in the applicable Owner's Summary Report which is filed with the enforcement and regulatory authorities havingjurisdiction over Plant Hatch. Code Cases applied at Hatch during the Third 10-Year Interval will be those initially selected from Regulatory Guide 1.147, revision 11, dated October,1994, unless relief has been received by Georgia Power Company to use a Code Case not listed in the Reg. Guide. As new or revised Code Cases are approved for use through subsequent revisions of the Reg. Guide, such Code Cases may be used at Hatch when deemed appropriate by Georgia Power Company. Reactor Pressure Vessel Welds The examination coverage for B-A, item numbers Bl.11 and Bl.12, cannot be accurately , determined until completion of the Second 10-Yar Interval exams. At that time, the Program will be updated to describe the exam coverage, including any necessary requests for relief.
-O PROGPHIL Rev.O Page1of3 4
O c'"' ' "'"" S* *a iaa Class 1 piping welds were selected for Interval 1 from the requirements oflWB-1220 and IWB-2500 of the 1974 Edition of Section XI with Addenda through . Summer 1975 (1974/S75). Examination techniques, required examination areas, required examination volumes, acceptance criteria, etc. were also to the requirements of 1974/S75. As allowed by 10CFR50.55a(bX2Xii), Category B-J welds to be examined in Interval 2 were also selected to 1974/S75. In keeping with the later Code philosophy of re-examining components in subsequent intervals, essentially the same 25% scope was picked , for Interval 2 as was picked for Interval 1. The scope was adjusted, as a conservative measure, by selecting terminal ends and high stress welds to the extent practical. Examination techniques, required examination areas, required examination volumes, acceptance criteria, etc. were to the requirements of the 1980 Code with Addenda through Winter 1981. As allowed by 10CFR50.55a(bX2Xii), the scope of B-J welds for Interval 3 will be essentially the same 25% scope as for Interval 2 (accordingly, the footnotes of Table IWB-2500-1 will not be used). Variations may be made to account for ALARA goals and limited access as long as the required number of welds are examined. Control Rod Drive Housing Welds Peripheral Control Rod Drive housing welds, Category B-0, Item B 14.10, IWB-2500-1 requires a volumetric or surface examination. However, according to the FSAR for Unit 2, 5Q and GE supplied information regarding makeup capacities, the available makeup systems l for postulated loss due to CRD break are RCIC (400 gal / min), CRD (160 gal / min), and ; the transfer system to feedwater (1000 gal / min). Therefore, these welds are exempt from the volumetric and surface examination requirements. This same logic is applicable for Unit 1. Snubbers Functional testing of snubbers is not within the scope of 10 CFR 50.55a. Therefore, it is i not considered to be within the scope of this ISI Program. Snubber functional testing is required by and is implemented in accordance with the Plant Hatch Snubber Program. However, since snubbers are considered to be Code components, the repair and i replacement activities associated with snubbers will be performed in accordance with ASME Section XI, articles IWF-4000 and IWF-7000. Visual examination of nonintegral . 4 attachments for snubbers is also covered in the Snubber Program. Visual examination of j integral attachments is covered in the ISI Program (see RR-11). ! Renair/ Replacement Pronram The ASME Section XI repair / replacements requirements are controlled and implemented by plant administrative control procedures. These procedures provide for adequate control and implementation of Code required repairs and replacements. PROGPHIL Rev.0 Page 2 of 3
(] A IWE/ Class MC Only Class 1,2, and 3 pressure retaining components and their supports are included in the scope of 10 CFR 50.55a. The requirements of Subsection IWE, " Requirements for Class MC Components of Light-Water Cooled Power Plants" is not within the scope of the ISI Program as defined by 10CFR50.55a. QL 88-01 Change in Previous Commitments (see NUREG section for details) The GL 88-01 commitments are added to the ISI Program for convenience since the exams are done at the same time as the ISI exams. 4 4 i 8 O 4 PROGPHIL Rev.O Page 3 of 3 i
O- O O: INDEX OF RELIEF REOUESTS ; !
' Item Code Category Description Status t RR-1 B-G RPV Closure Head Nuts Submitted to NRC RR-2 B-E, B-P, C-H, D-A, All AShE Class 1,2, and 3 Piping and Components included within the - Submitted to NRC D-B, D-C scope of the ISI Program (Code Case N-498-1) {
RR-3 : B-D Shell-to-Nozzle and Inside Radius Weld Submitted to NRC ~ RR-4 ; B-K-1,C-C, All AShE Class 1,2, and 3 Integrally Welded Attachments included within Submitted to NRC
- D-A, D-B, D-C the scope of the ISI Program (Code Case N-509)
RR-5 C-A. Shell to Shell, Head to Shell, and Shell to Flange Welds on Heat Exchangers Submitted to NRC RR-6 B-F RPV Nozzle-to-Safe-End Butt Welds Submitted to NRC RR-7 B-J, C-F-2 All ASNE Class 1 and 2 Piping included within the scope of the ISI Program Submitted to NRC (Code Case N-524) RR-8 Various All AShE Class 1,2, and 3 Piping and Components included within the Submitted to NRC scope of the ISI Program RR-9 Various All ASME Class 1,2, and 3 Piping and Components included within the Submitted to NRC scope of the ISI Program (Code Case N-416-1) -l RR-10 Various All welds and areas subject to surface or volumetric examination Submitted to NRC - RRINDEX
- Rev.O Page1 of2
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i O O O INDEX OF RELIEF REOUESTS Item Code Category Description Status
. RR-11 F-A All ASME Class I,2, and 3 Saubbers included within the scope of the ISI Submitted to NRC Program l
4 k RRINDEX i Rev.O Page 2 of 2 4 u- % _m -
'i__ _ _ _ _ _ _ _ , _w ,_ _ _ _ _ _ _ _ _ . .________E_______________________.________._______.___.__'___.____;
'I e GEORGIA POWER COMPANY
< O PLANT HATCH, UNIT 1 & 2 THIRD 10-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-1 i I. System / Component (s) for Which Reliefis Requested:
Examination Category B-G-1. Item B6.10. RPV Closure Head Nuts Unit 1; NUT-1 thru NUT-52 Unit 2; 2-NUT-1 thru 2-NUT-56 . II. Code Requirement: Section XI, Table IWB-2500-1, Examination Category B-G-1, Item e B6.10 requires a surface examination of the Reactor Vessel Closure Head Nuts. i
- II. Code Reauirement from Which Reliefis Reauested
- Reliefis requested from perforndng the Code-required surface examination on above identified Reactor Vessel Closure Head Nuts.
IV. Basis for Relief: The ASME, Section XI,1989 Addenda, Table IWB-2500-1, Category l B-G-1, Item B6.10, allows Visual Examination Method, VT-1 in lieu of the Surface Examination Method required by the 1989 Code. 4 C,Vi Alternate Examinations Georgia Power Company proposes that, in lieu of the 1989 V. Edition, Code-required surface examination, the subject RPV Closure Head Nuts will receive a Visual Exam, VT-1 in accordance with the ASME, Section XI,1989 Addenda. , VI. .lustification for the Granting of Relief: The closure head nut configuration does not
, allow for an adequate Magnetic Particle examination. The MT method requires two l directional coverage to detect the surface flaws. The configuration permits examination in one direction and limits the coverage in the other direction. The Liquid Penetrant method is not practical, due to the lubricant applied to the inside surface. The lubricant 4
is difficult to completely remove in order to get a proper exam. J ISI optimization did a survey on bolting. Results did not reveal any service induced cracking. No cracks have been detected at Plant Hatch, Units 1 &2. No flaws have been detected at Plant Farley or Vogtle. This survey was part of the technical basis for . changing the surface requirement to a VT-1. Later editions of the ASME Code changed the examination requirement to a VT-1. Since the change (visual examination) was issued by ASME, the alternative examination should be technically acceptable for determining flaws. The proposed alternative visual examination, VT- I will provide reasonable assurance that unallowable inservice flaws O RR-1 Rev 0
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] have not developed in the subject components or that they will be detected and repaired prior to return of the reactor vessel to service. If relevant indications are detected, alternate surface / volumetric techniques will be performed as necessary. Thus an acceptable level of quality and safety will have been achieved and public health and i safety will not be endangered by allowing the proposed alternative examination in lieu of the Code requirement. By implementing the alternative examinations, cost savings, personnel radiation dose, and outage time can be realized by Georgia Power Company ; at Plant Hatch. Time spent performing the examinations will be minimized, while ALARA principles will be adhered to by reducing contact with contaminated components.
VII. Imolementation Schedule: The subject examinations will be performed during the Third 10-Year Interval. I t J ) i i O i ) a 4 O RR-1 Rev.0 Page 2 of 2.
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g GEORGIA POWER COMPANY PLANT HATCll, UNIT 1 & 2 TillRD 10-YEAR INTERVAL REQUEST FOR IELIEF NO. RR-2
- 1. System /comoonent(s) for Which Reliefis Requested: All ASME Class 1,2 and 3 piping and components included within the scope of the ISI Program
~ Examination Category B-E, Item B4.11, B4.12 and B4.13 Examination Category B P, item B15.11, B15.51, B15.61, B15.71 Examination Category C-II, item C7.20. C7.40, C7.60 and C7.80 4 Examination Category D A, Item DI.10
- Examination Category D-B, Item D2.10 Examination Category D-C, Item D3.10
, II. Code Requirement: The listed ASME XI item number components are required to be subjected to a hydrostatic test once each inspection interval in accordance with paragraphs IWB-5222,IWC-5222 and IWD-5223 as applicable.
111. Code Requirement for Which Reliefis Requested: Reliefis requested from performing the required hydrostatic test for each of the listed Code item numbers. IV. Basis for Relief: ASME Section XI Code Case N-498-1 was issued on May 11,1994. "O This Code Case has been approved by the NRC staff for use at Plant Hatch and other plants, but has not been formally endorsed by inclusion in NRC Regulatory Guide 1.147. ,
- It was previously approved for Plant IIatch for the 2nd Interval by SER dated 7/5/95.
V. Alternate Examinations: Georgia Power Company will comply with the pressure testing l requirements of ASME Section XI Code Case N-498-1 for the listed Code item numbers. VI. Justification for the Granting of Relief: The proposed alternative testing requirements have been evaluated by the ASME Code Committee and the NRC and have been deemed
- acceptable for determining the pressure boundary integrity of the affected components.
- imp!ementation of pressure testing in accordance with the subject Code Case will ensure an t.cceptable level of quality and safety, does not decrease the margin of public health and j safety and is thus authorized pursuant to 10 CFR 50.55a(a)(3)(i). By implementing the
- alternative examinations, cost savings, personnel radiation dose, and outage time can be
, realized by Georgia Power Company at Plant Hatch. VI. Imnlementation Schedule: Pressure testing in accordance with Code Case N-498-1 will be substituted for the 10-year hydrostatic test on the affected components in accordance with 4 the test schedule defined in the applicable Inservice Inspection Plan, for the Third 10-Year Interval. O v RR-2
- Rev.O Page1of 1 I
i l l CASE l N-498-1 O CASES Of ASME BolLER AND PRESStlRE VESSEL CODE Approval Date: May 11,1994 See NumericalIndex for expiration 1 and any reaffirmation dates. Case N-4981 (2) The boundary subject to test pressurization Alternative Rules for 10 Year System Hydrostatic during the system pressure test shall extend to all Testing for Class 1,2, and 3 Systems Class 2 components included in those portions of sys. Section XI, Division 1 tems required to operate or support the safety system function up to and including the first normally closed Inquiry: What alternative rules may be used in lieu valve, including a safety or relief valve, or valve ca-of those required by Section XI, Division 1, Table pable of automatic closure when the safety function , IWB-2500-1, Category B-P, Table IWC-2500-1, Cat. is required. l I egory C-H, and Table IWD 2500-1, Categories D A, (3) Prior to performing the VT 2 visual exami-D-B, and D-C, as applicable, for the 10-year system nation, the system shall be pressurized to nominal hydrostatic test? operating pressure for a minimum of 4 hours for in-sulated systems and 10 minutes for noninsulated sys-tems. The system shall be maintained at nominal op-erating pressure during performance of the VT 2 Reply: visual examination. (a) It is the opinion of the Committee that as an (4) The VT-2 visual examination shall include alternative to the 10-year system hydrostatic test re- all components within the boundary identified in quired by Table IWB-2500-1, Category B-P, the fol- (b)(2) above. lowing rules shall be used. (S) Test instrumentation requirements of IWA-(1) A system leakage test (IWB-5221) shall be 5260 are not applicable. conducted at or near the end of each inspection in. (c) It is the opinion of the Committee that, as an terval, prior to reactor startup, alternative to the 10-year system hydrostatic test re. (2) The boundary subject to test pressurization quired by Table IWD 2500-1, Categories D-A, D B, during the system leakage test shall extend to all or D C (D B for the 1989 Edition with the 1991 and Class 1 pressure retaining components within the sys- subsequent Addenda), as applicable, the following tem boundary, rules shall be used. (3) Prior to performing the VT-2 visual exami. (1) A system pressure test shall be conducted at nation, the system shall be pressurized to nominal or near the end of each inspection interval or during operating pressure for at least 4 hours for insulated the same inspection period of each inspection inter-systems and 10 minutes for noninsulated systems, val of Inspection Program B. The system shall be maintained at nominal operating (2) The boundary subject to test pressurization pressure during performance of the VT-2 visual ex- during the system pressure test shall extend to all amination. Class 3 components included in those portions of sys-M: (4) Test temperatures and pressures shall not tems required to operate or support the safety system exceed limiting conditions for the hydrostatic test function up to and including the first normally closed curve as contained in the plant Technical Specifica- valve, including a safety or relief valve, or valve ca. tions. pable of automatic closure when the safety function (S) The VT 2 visual examination shall include is required. all components within the boundary identified in (3) Prior to performing the VT 2 visual exami-(a)(2) above, nation, the system shall be pressurized to nominal (6) Test instrumentation requirements of IWA- operating pressure for at least 4 hours for insulated 5260 are not applicable. systems and 10 minutes for noninsulated systems. (b) It is the opinion of the Committee that, as an The system shall be maintained at nominal operating alternative to the 10-year system hydrostatic test re- pressure during performance of the VT 2 visual ex-quired by Table IWC 25001, Category C-H, the fol- amination. C lowing rules shall be used. (4) The VT 2 visual examination shall include 5 (1) A system pressure test shall be conducted at all components within the boundary identified in or near the end of each inspection interval or during (c)(2) above, the same inspection period of each inspection inter- (S) Test instrumentation requirements of IWA-val of Inspection Program B. 5260 are not applicable. 849 SUPP. 9 - NC
GEORGIA POWER COMPANY l PLANT HATCH, UNIT 1 & 2 THIRD 10-YEAR INTERVAL j REQUEST FOR RELIEF NO. RR-3 I. System /Comooncat(s) for Which Reliefis Reauested: ! Examination Catecorv B-D. Item B3.90. Shell-to-Nozzle Welds 2" NPS Bottom Head Drain Vessel-to-Nozzle Weld (NIS (SH-N)) 2" NPS Bottom Head Drain Vessel-to-Nozzle Weld (2N15 (SH-N)) i Examination Category B-D. Item B3.100. Inside Radius Welds 2" NPS Bottom Head Drain Nozzle Inside Radius Section (NIS (IR)) 2" NPS Bottom Head Drain Nozzle Inside Radius Section (2N15 (IR)) l; a II. Code Reauirement: Section XI, Table IWB-2500-1, Examination Category B-D, Item
- B3.90 and B3.100 requires a volumetric examination of the Reactor Vessel Nozzle-to-t Vessel Welds and Nozzle Inside Radius Section as defined by Figures IWB-2500-7(a) through (d).
] I III. Code Reauirement from Which Reliefis Reauested: Reliefis requested from performing i the Code-required volumetric examination of the above identified Reactor Pressure Vessel Nozzle-to-Vessel Welds and Nozzle Inside Radius Section. O IV. Basis for Relief: The subject welds are located in the center of the Bottom Head and are l not accessible due to the Control Rod Drive Housings (see attached drawings). 5 V. Alternate Examinations: Georgia Power Company proposes that, in lieu of the Code-
- required volumetric examination, the subject nozzle welds will receive a visual (VT-2) i examination during the Leakage Test / Hydrostatic Test.
VI. Justification for the Granting of Relief: There is no known technique that can be used on
- i. the inside of the vessel to examine the nozzle. Access in not available to examine from the outside of the vessel. During the Leakage Test / Hydrostatic Test, GPC will ensure there is
, no leakage coming from the area of the subject nozzles. The VT-2 visual examination should provide reasonable assurance that unallowable inservice flaws have not developed in the subject welds or that they will be detected and repaired prior to return of the reactor vessel to service. VII. Implementation Schedule: The subject examinations (Leakage Test / Hydrostatic Test) will be performed during the Third 10-Year Interval. NOTE: This Relief Request was previously approved on 9/29/86 and 6/22/89 for the Second Interval. The Relief Request number was 2.1.3. !O
- .RR-3 Rev.O Page1of3
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/] GEORGIA POWER COMPANY 1 V PLANT HATCH, UNIT 1 & 2 )
THIRD 10-YEAR INTERVAL l REQUEST FOR RELIEF NO. RR-4 I. System /Compa_nent(s) for Which Reliefis R.gquested All ASME Class 1,2, and 3 Integrally Welded Attachments included within the scope of the ISI Program. Examination Category B-K-1, Item B10.10, B10.20 for Piping and Pumps Examination Category C-C, Item C3.10, C3.20 Pressure Vessels and Piping Examination Category D-A, Item Dl.20, Dl.30, Dl.40, DI.50, DI.60 , Examination Category D-B, Item D2.20, D2.30, D2.40, D2.50, D2.60 Examination Category D-C, Item D3.20, D3.30, D3.40, D3.50, D3.60 II. Code Reauirement: Section XI, Table IWB-2500-1, Examination Category B-K-1, Item B10.10 and B10.20 requires a volumetric or surface examination of the integrally welded attachments that meet certain conditions noted in the Table. Table IWC-2500-1, Examination Category C-C, Item C3.10 and C3.20 requires a surface examination of the integrally welded attachments that meet certain conditions noted in the Table. Table IWD-2500-1, Examination Category D-A, Item Dl.20, DI.30, Dl.40, Dl.50, DI.60, Category D-B, Item D2.20, D2.30, D2.40, D2.50, D2.60, and Category D-C, Item D3.20, D3.30, D3.40, D3.50, D3.60 requires a visual examination of the () integrally welded attachments that meet certain conditions noted in the Table. III. Code Requirement from Which Reliefis Requested: Reliefis requested from performing the Code-required volumetric, surface, or visual examination on those Integral Attachments required by the above referenced Tables. IV. Basis far Relief: On November 25,1992, ASME issued Code Case N-509 which approved a set of alternative rules for the selection and examination of Class 1 and 2 Integrally Welded Attachments. I V. Alternate Examinations: Georgia Power Company proposes that, in lieu of the Code-required volumetric, surface, or visual examination on those Integrally Welded Attachments required by Table IWB-2500-1, IWC-2500-1, or IWD-2500-1 in the 1989 Edition, a surface examination be performed on those Integrally Welded Attachments as noted in the Code Case, Table 2500-1, Examination Category B-K., Integral Attachments for Class 1 Vessels, Piping, Pumps, and Valves; Examination Category C-C, Integral Attachments for Class 2 Vessels, Piping, Pumps, and Valves; and a visual examination for Examination Category D-A, Integral Attachments for Class 3 Vessels, Piping, Pumps, and Valves. GPC will ensure that the sample will be a minimum of 10% of the IWB/IWC/IWD items. 1 RR-4 Rey, O Page1of2
l VI. Justification for the Granting of Religf: Code Case N-509 provides an alternative sampling which will retain an acceptable level of quality and safety for Class 1,2, and 3 Integrally Welded Attachments. Since approval was granted by ASME, the alternative requirements should be technically acceptable for determining flaws. By implementing the alternative examinations, cost savings, personnel radiation dose, and outage time can be realized by Georgia Power Company at
- Plant Hatch.
VII. Emplementation Schedule: The subject examinations will be performed during the Third 10-Year Interval. e 4 9 4 O l l i
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RR-4 Rev, O Page 2 of 2
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CASE N-509 {} CASES OF ASME BOILER AND PRESSURE VESSEL CODE 4 Approval Date: November 25.1992 See Numeric Index for expiration and any reaffirmation dates. Case N 509 1.1 Exemption Criteria Alternative Rules for the Selection and Examinaion (a) The exemption criteria provided in IWB 1220, of Class 1,2, and 3 Integrally Welded Attachments IWC-1220, and IWD 1220 may be applied to Class Section XI, Division 1 1,2, and 3 components respectively, with integrally welded attachments, required to be examined in ac. Inquiry: What alternative requirements to those of cordance with Table 2500-1. , IWB, IWC, and IWD may be used to select and (b) Class 1,2, and 3 integrally welded attachment E l examine integrally welded attachments? examinations performed as a result of component support deformation cannot be credited under the requirements of IWB-2411 or IWB-2412, IWC 2411 Replyt It is the opinion of the Committee that the
' IWC 2412, and IWD-2411 or IWD-2412, respec-following rules may be used to select and examine ; ;'
integrally welded attachments: (a) This Case is limited to Examination Categories l B H, B K-1, C-C, D-A, D-B, and D-C. 1.2 Inspection Schedule (b) Class 1,2, and 3 component supports shall be Class 1,2, or 3 integrally welded attachments se-selected for examination in accordance with IWF of the 1989 Edition with the 1990 Addenda, lected for examination by sample selection criteria in l q accordance with Table 2500-1, Examination Cate- l Q (c) Except for the selection of component supports for examination, all references to Section XI within gories B K, C-C, and D A, shall meet the require-
, ments of IWB-2411 or IWB 2412, IWC-2411 or this Case shall be from the edition and addenda spec-ified in the Owner s Inservice Inspection Program. IWC-2412, or IWD-2411 or IWD-2412, repectively.
1.3 Additional and Successive Examinations (a) Class 1,2, and 3 additional and successive ex-1.0 SCOPE l amination requirements of IWB 2430 and IWB 2420 These requirements apply to examination and for Class 1, IWC-2430 and IWC 2420 for Class 2 and sample selection of Class 1,2, and 3 integrally welded 3 as applicable, shall be applied to integrally welded attachments of vessels, piping, pumps, and valves attachments whose examinations reveal flaws or rel-listed in Table 25001 as follows: evant conditions that exceed the acceptance stan-(a) Table 2500-1, Examination Category B-K shall dards of IWB 3000, IWC 3000, and IWD-3000, re-be used for Class 1 integrally welded attachments in spectively. Examination Cateraries B-H and B K-1 of IWB. (b) When integrally welded attachments are ex-(b) Tabb 23001. Examination Category C C shall amined as a result of identified component support be used for Class 2 integrally welded attachments in deformation and the results of these examinations Examination Category C C of IWC, exceed the applicable acceptance standards listed (c) Table 2500-1, Examination Category D A shall above, additional or successive examinations shall be be used for Class 3 integrally welded attachments in performed when determined necessary based on an Examination Categories D A, D-B, and D CofIWD. evaluation by the Owner. 877 SUPP. 4 - NC
O O O C ZQ l 3 8 I a- cm I UI m z TABLE 2500-1 EXAMINATION CATEGORIES OE
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! EXAMINATION CATEGORY B-K, INTEGRAL ATTACHMENTS FOR CLASS 1 VESSELS, PIPING, PUMPS, AND VALVES $ c Examination e Item Reedrements/ Fig. No. Examination Acceptance rnmammer u Extent of Frequency of a No. Parts Eman:'. sed
- Method Standard Examination
- l 810.10 Pressure Yessels 1WB-2500-13, Surface
- IW8-3516 100% of ruluired areas of each Each idewified occurrence and Integrally Weided -14, and -15 wekled attachment each inspection interval
- 810.20 Piping IWB-2500-13, Surface IWB-3516 100% of required areas of each Each ident.aed - and a
o lategra!!y Welded -14, and -15 welded attachment each insp sction interva!* ** Attachments M ili 810.30 Pumps IW8-2500-13, Surface IW8-3516 100% of required areas of each Each identified occurrence and to Integrally Welded -14, and -15 welded attachment each inspection interval. O l Attachrnents so oo 810.40 Valres IWB-2500-13, Surface IWB-3516 100% of required areas of each Each identified occurrence and oo Integrally Welded -14, and -15 wehled attachment each inspection interval' [ NOTES: y (1) Examination is tirnited to those integrally welded attachments that sneet the following conditions- g (a) the attachment is en the outside surface of the pressure retaining w..,,,,.m7,- (b) the attachment provides component sagprt as denned in NF-1110; and (c) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the corrponent. h
#m (2) The extent of the exarnination includes essentially 100% of the length of the attachment weld at each attachment subject to examinatten. $
- 0) Selected samples of integrany welded attachments shall be examined each inspection interval ()
(4) in the case of rnuitiple vessels of similar design, function and service, only one integrally welded attacivnent of only one of the multiple vessels shall be selected for examination. @ , (5) For piping, pumps, and valves, a sample of 10% of the welded attachmerts associated with the e -- - ^ sapports selected for examination under the 1990 Addenda, IWF-2510 shall te be exammed . (tJ Exarnination is required whenever component support enember deformation (e.g., broken, bent, or pulled out parts) is identifled during operation, refuellrg enaintenance, exarmnation, laservice inspectiosg or testing. (7) for the configuration shown in Fig. IWB-2500-14, a volumetric examination of volume A-B-C-D from side (B-C) of the circumferential welds may be serionneo in lieu of the surface examination of sa.rfaces A-D and 8-C. ,
\ _ _ _ _ _ _ ._ __ _ _ _ _ _ _ _ _ _ . _ _ _ . _ . . _ ._ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. .. . _ . - ~ . . . . . . . . . ._-.._-_-m Ci O O -
TABLE 2500-1(CONTD) EXAMINATION CATEGORIES EXAMINATION CATEGONY C-C, INTEGRAL ATTACNMENTS FOR CLASS 2 VESSELS, PIPING, PUMPS, AND VALVES Esamination Item Requirtments/ Emanunation Acceptance Eatest of Frequency of No. Parts Examined
- Fig. No. Method Standard Examinaties" Examination * .
C3.10 Pressere Vesels IWC-2500-5 Surface IWC-3512 100% of required arcas of each Integrally Welded Attachments welded attachnent Earh identified occwrence and each impection interval * { C3.20 Piping IWC-2500-5 Surface - IWC-3512 k Iritegrally Welded 100% et required areas of each Each identified oc6 - ence and g welded attachment each inspection interval
- E Attachments "
C3.30 Pumps Integrally Welded IWC-2500-5 Surface IWC-3512 100% of required aress of each welded attachment Each identified occurrence and each inspection interval * ( 30 Attachments
]
C3.40 Valves IWC-2500-5 Surface l'WC-3512 100% of required areas of each Each identifled occurrence and Integrally Welded welded attachment each inspection interval
- Attachments "
NOTES: (1) Examination is limited to those integrally welded attachments that rneet the following conditions: (a) the attachrnent is on the outside surface of the pressurt retaining component; h m (b) the attachtnent provides component stoport as defined in NF-1110; and (c) The attachment weld joins the attachment either directly to the surface of the corgonent or to an integrally cast or forged attachment to the cornponent. O (2) The extent of the exarnination includes essentially 100% of the length of the attactrnent weld at each attachment subject to examination. (3) Selected samples of integrally welded attachments shall be examined each inspection interval. @ m (4) Ir. the case of multiple vessels of similar desigrg function and service, only one integrally welded attachment of only one of the multiple vessels shall be selected for examination. (5) For piping, pumn and valves, a saimple of 10% of the welded attachments associated with the component supports selected for examination under the 1990 Addenda, IWF-2510 shall be exarnined. j m) Examination is required whenever component support rnernber deformation (e.g., broken, bent, or pulled out part:) is identifled during operation, refueling, maintenance, examinallen, inservice irnpection, or testing. ~ ()
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O EXAMINATION CATEGORIES o 3 EXAMINATION CATdGORY D.A, INTEGRAL ATTACHMENTS FBR CLASS 3 VESSELS, PIMNG, PUMPS, AND VALVES g Examination $ Item ~ Requirements / Examination Acceptance Extent of Frequency of ,g No. Parts Examined' Fig. Me. Method Standard Examinationu Examination" D1.10 Presseee Vessels IWD-2500-1 Visual, VT-1 IWD-3000 100% of required areas of each Each identirred occurrence and Integrally Welded welded attachment each inspection interval Attachments Visual, VT-1 IWD-3000 100% of required areas of each Each identirred occurrence and 5 D1.20 Piping IWD-2500-1 Integrally Welded welded attachment each inspection interval k Attachments g I D130 Pumps IWD-2500-1 Visual, VT-1 IWD-3000 100% of required areas of each Each identified occurrence and Integrally Welded welded attachment each inspection interval o Attachments (n D1.40 Valees IWD-7500-1 Visual, VT-1 IWD-3000 100% of required areas of each . Each identified occurrence and welded attachment each inspection interval h Integrally Welded N Attachments m NOTES: (1) Examination is limited to those integrally welded attachments that meet the following conditions: (a) the attachment is on the outside surface of the pressure retaining component; (b) the attachment provides carryonent support as defined in NF-1110; and (c) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the corgonent, , (2) The extent of the examination includes essentially 100% of the length of the attachment weld at each attachment subject to examination. p (3) Selected samples of integrally welded attachments shall be examined each inspection interval All integrally welded attachments selected for exarnination shall be subject to corrosion, as n determined by the Dwner, such as the integrally weldej attachments of the Service Water or Emergency Service Water systems. In the case of multiple vessels of similar design, o function and service, the integrally welded attachments of only one of the multiple vessels shall be selected for examination. For integrally welded attachrnents of piping, pungs, and % ' valves a 10% sample shall be selected for examination. This percentage sample shall be proportional to the total number of nonexempt integrally welded attachments connected to the piping, pumps, and valves, located within each system subject to these examinations. -[ (4) Examination is required whenever component support member deformation (e.g., broken, bent, or pulled out parts) is identified during operation, refueling, maintenance, examination, , inservice inspection, or testing. ! 4 w_ __ _____ ___-_____ _ _ - _ _ - _ _ - _ - _ _ _ _
4 t GEORGIA POWER COMPANY PLANT HATCH, UNIT 1 & 2 l 4 THIRD 10-YEAR INTERVAL I REQUEST FOR RELIEF NO RR-5 [ I. System / Component (s) for Which Reliefis Requested: Four Head to Shell Welds for Heat !
! Exchangers, j Examination Category C-A. Item C1.20 (Head Circumferential Welds) l 1
Shell Head to Upper Shell Ring Weld (IEl1-2HX-A-1)
; Shell Head to Upper Shell Ring Weld (IEl1-2HX-B-1)
Shell Head to Upper Shell Ring Weld (2HX-A-1) , 1 Shell Head to Upper Shell Ring Weld (2HX-B-1) ! II. Code Requirement: Section XI, Table IWC-2500-1, Examination Category C-A, Item Cl.20 requirce a volumetric examination of one of the two welds on each unit as defined by Figure i IWC-2500-1. i III. Code Reauirement from Which Reliefis Reauested: Reliefis requested from performing the Code-required volumetric examination on the subject welds.
- IV Basis for Relief
- The subject welds cannot be completely ultrasonically examined due to O germanent weided brackets iecated ai 0,90, is0, and 270 desrees (see sttached risere).
These brackets are located in the examination area and prohibit full coverage from either side of the weld. Estimated coverage based on previous examination data is 72% of the required volume,
- V. Alternate Examinations
- Georgia Power Company proposes to supplement the volumetric examination of the Head to Shell Welds with a surface examination, to the extent practical.
VI. Justification for the Grantina of Relief: The proposed supplemental surface examination and I the Code required volumetric examination (to the extent practical considering the physical I limitations) will provide reasonable assurance that unallowable inservice flaws have not developed in the subject welds or that they will be detected and repaired prior to return of the i reactor vessel to service. Thus an acceptable level of quality and safety will have been , achieved and public health and safety will not be endangered by allowing the limited examinations and the proposed alternative examinations in lieu of the full Code requirement. VII. Implementation Schedule: The subject examinations will be performed during the Third 10-Year Interval. NOTE: Relief for this Code Category was previously approved on 9/29/86 and 6/22/89 for the Second Interval. The Relief Request number was 3.1.1. RR-5 Rev.O Page1of2
O O O SHELL HEAD B,,,. . E E E LEll VESSEL TIE-DOVN
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1E11-2HX-A-1 1E11-2HX-B-1 BRACKET (4) AT 0* UPPER SHELL 2HX-A-1 90*, 180*,AND 270 2HX-B-1 SUPPORT RING 1* SUPPORT BRACKETS FOR UNIT 2. LOVER SHELL FLANGE (h
%) -
1 RHR HEAT EXCHANGER - HATCH UNIT 1 AND 2. ATTACHMENT TO RR-5 PAGE 2 RHRHTEx 1 6_. _ _ _ _ . _ _ _ . _ _ __ _ . _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . _ _ . . . _ _ _
p GEORGIA POWER COMPANY L> PLANT HATCH, UNIT 1 & 2 THIRD 10-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-6 I. System /Comoonent(s) for Which Reliefis Requested: Examination Category B-F. Item B5.20. RPV Nozzle-to-Safe-End Butt Welds Unit 1 2.5" Core D.P. & Liquid Control Nozzle-to-Safe-End Weld, NIO 3" Bottom Head Drain Nozzle-to-Safe-End Weld, NIS 2.5" RPV Instrumentation Nozzle-to-Safe-End Weld, N16A 2.5" RPV Instrumentation Nozzle-to-Safe-End Weld, N16B Unit 2 2.985" Core D.P. & Liquid Control Nozzle-to-Safe-End Weld, 2N10 3" Bottom Head Drain Nozzle-to-Safe-End Weld,2N15 2.5" RPV Instrumentation Nozzle-to-Safe-End Weld, 2N16A 2.5" RPV Instrumentation Nozzle-to-Safe-End Weld,2N16B II. Code Reauirement: Section XI, Table IWB-2500-1, Examination Category B-F, Item B5.20 requires a surface examinations of the nozzle-to-safe-end welds on pressure retaining ) O dissimiiar n-tai weids as defined by Pisure iwB-2500-8. l III. Code Requirement from Which Reliefis Requested: Reliefis requested frem performing the i Code-required surface examination of the above identified RPV nozzle-to-safe-end pipe i welds. IV. Basis for Relief: These instmment nozzles (NIO, N16A/B, 2N10, 2N16A/B) have very ! limited access due to the design of the concrete shield. Each nozzle has small doors that can l be opened allowing 12 to 18 inches of access. However, due to the distance the RPV wall is ; recessed from the outside of the shield wall (e.g., insulation thickness, air gap, and shield i thickness), the welds cannot be physically reached with enough room to perform the surface ; examination. The NIS and 2N15 welds are the Bottom Head Drain Nozzles. These welds are located in ! the center of the Dottom Head and are not accessible due to the Control Rod Drive Housings (see attached drawings ). VT-2 examination in conjunction with the Class I system leakage / hydrostatic test each . refueling outage will provide adequate assurance that any flaw (s) that might have ! propagated through the subject welds are identified and repaired prior to returning the plant to power operation. 1 O RR-6 Rev.O Page1of6 1 __________]
l V. Alternate Examinatiom: Georgia Power Company proposes that, in lieu of the Code- ! O required surface examination, the following reactor vessel nozzle-to-safe-end butt welds will l receive a VT-2 examination: NIO, N15, N16A/B, 2N10, 2N15, 2N16A/B. ! VI. Justification for the Granting of Relief: The nozzles are subjected to the Leakage / Hydrostatic Test. In addition, other RPV Instrument Nozzles which have adequate access (N11 A/B, N12A/B, 2N11 A/B, 2N12A/B) will receive a Code required surface exam and a supplemental volumetric examination. Therefore, a 50% sample will receive in excess of Code required surface exams. The visual examination of the subject nozzles as well as the Code surface exam and supplemental volumetric examination of similar nozzles within the sarne Code category, will provide reasonable assurance that unallowable inservice flaws have not developed in the subject welds or that they will be detected and repaired prior to return of the reactor vessel to service. Thus an acceptable level of quality and safety will have been achieved and public i health and safety will not be endangered by allowing the proposed alternative examination in lieu of the Code requirement. VII. Imolementation Schedule: The subject examinations will be performed during the Third 10-Year Interval. O Nots: This Reiief Request (aithough somewhat different) was previousiv aggroved on 9/29/86 and 6/22/89 for the Second Interval. The Relief Request number was 2.1.6. RR-6 ' Rev.O Page 2 of 6
O O. O O 270 180 90 0 209'-1I-l 3 iso- so' (C-l 202'-I' 288* 252* N128 IoB* 7'2* [ Nl2A v m N3D *. N38 N3A N3C 7 0 2p- Tl C-2 189' 594 5B9' 582 SB I' c1 c i y,.c3 cg O O """ O O 5 y 9I5* Ov7 N5A
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N9 ONSB T45 e 7 0 I iso- 0 90- C-9 177'-l' 24o' I20* TYP. LONGITUDINAL VELD ___1 ___# __ __ ____ ___ _ TOP OF 179' -4' FUEL y 9 Nf6A y TYP. CIRCUMFERENTIAL VELD * *
- i 0 0 0 C-4 164'-6'
, BOTTOM 160'-11' NiA N2J
- NIA N2x g y N2G N2F N2Ef N2Dg N28 N2A; NSB 0 b N8A 0 C-5 152'-l' '
i l 258- i38- io3- is' ATTACHMENT RPV N0ZZLE TO VESSEL WELDS TO RR-6 EDWIN I. HATCH UNIT I PAGE 9
O O O O 270 180 90 0~ 209'-8 5/16' I I 3 sii* i9l* 7i- (2C-l 201'-10 5/8' I? 288* 108* 252' l2N128 72*[ l2N12Al v
" " 2N90 2N3C 2N38 2N3A 37 2p* '7 l T 2C-2 189'-9 19/16' 556 5115 'SR4 SB's Si12 '5B 1 O [] ] O U @
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$ BOTTOM 160'-1I 9/16' 2NIA 2N2K 2N2J 2N2F 2N2E 2N2B 2N2A 2NIA j 2N2G 2N2Dg 2NsA N 2Nes 2C-5 151'-7 91/92' J,. 2.e.
,J,- 2e-ATTACHMENT RPV N0ZZLE TO VESSEL WELDS TO RR-6 EDWIN I. HATCH UNIT 2 PAGE 4 A efrv1
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- 5. C RPV DIFFERENTIAL PRESSURE AND
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n . GEORGIA POWER COMPANY U PLANT HATCH, UNIT 1 & 2 THIRD 10-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-7 I. System /Comoonent(s) for Which Reliefis Reauested: All ASME Class 1 and 2 piping included within the scope of the ISI Program. Examination Category B-J, Item B9.12 Examination Category C-F-2, Item C5.52, C5.82 II.~ Code Reauirement: Section XI, Table IWB-2500-1, Examination Category B-J, Item B9.12 requires a surface and volumetric examination as defined by Figure IWB-2500-8; and Table IWC-2500-1, Examination Category C-F-2, Item C5.52 requires a surface and volumetric examination as defined by Figure IWC-2500-7, and Item C5,82 requires a surface examination as defined by Figure IWC-2500-12 and -13. III. Code Reauirement from Which Reliefis Requested: Reliefis requested from performing the Code-required surface and volumetric examination of the above identified piping longitudinal welds IV. Basis for Relief: Code Case N-524 (approved August 9,1993) of the ASME Boiler and O Pr-e vessei Cae add-s the anemative requirernents for wrrace and volumetdc ; examination requirements oflongitudinal piping welds. By implementing the provisions of this Code Case, personnel radiation exposure, outage examination time, and costs can be significantly reduced at Plant Hatch. V. Alternate Examination _s: Georgia Power Company will comply with the requirements of ASME Section XI, Code Case N-524 as follows: (a) When only a surface examination is required, examination oflongitudinal piping welds is not required beyond those portions of the welds within the examination boundaries of the intersecting circumferential welds. (b) 4 When both surface and volumetric examination are required, examination oflongitudinal l i piping welds is not required beyond those portions of the welds within the examination boundaries ofintersecting circumferential welds provided the following requirements are ) met. (1) Where longitudinal welds are specified and locations are known, examination i requirements shall be met for both transverse and parallel flaws at the intersection of the I welds and for that length oflongitudinal weld within the circumferential weld examination volume; (2) Where longitudinal welds are specified but locations are unknown, or the existence oflongitudinal welds is uncertain, the examination requirements shall be met for both transverse and parallel flaws within the entire examination volume ofintersecting circumferential welds. O RR-7
- Rev.O Page1 of2
- 1
- _ __ ._ . _ . _ .~ -_ _ .. _ _ _ _ _ . . _ . . - -.
l ! ,- - ' VI, Ju=*incation for the Grantino of Relief. The proposed alternative testing requirements have ( been evaluated by the ASME Code Committee and have been deemed acceptable for
- ' determining the pressure boundary integrity of the affected components. The proposed alternative requirements, in accordance with the Code Case, will provide reasonable l assurance that unallowable inservice flaws have not developed in the subject welds or that they will be detected and repaired prior to return of the reactor vessel to service. Thus an acceptable level of quality and safety will have been achieved and public health and safety i c'
will not be endangered by allowing the proposed alternative examination in lieu of the Code requirements. VII. Imniementation Schedule: The subject examinations, as noted in the Code Case, will be j performed during the Third 10-Year Interval. l 1 l O l l l O RR-7 Rev.0 Page 2 of 2 l l l
CASE N-524 CASES OF ASME Bull.ER AND PRESSURE VESSEL CODE Approval Date: August 9,1993 U' See NumericalIndex for anpiration and any reaffirmation dates. Case N 524 Alternative Examination Requirements for longitudinal Welds in Class 1 and 2 Piping Section XI Division 1 Inquhy: What alternative requirements may be ap. plied to the surface and volumetric examination of
, longitudinal piping welds specified in Table IWB-2500-1, Examination Category BJ, Table IWC-2500-1, Examination Categories C-F 1 and C-F-2 (Exam-l ination Category C-F prior to Winter 1983 Adden-da), and Table IWC-2520, Examination Category C-G (1974 Edition, Summer 1975 Addenda)?
Reply: It is the opinion of the Committee that the following shall apply: (a) When only a surface examination is required, examination of longitudinal piping welds is not re-quired beyond those portions of the welds within the examination boundaries of intersecting circumfer. ential welds. [ O' (b) When both surface and volumetric examina-tions are required, examination oflongitudinal piping l i welds is not required beyond those portions of the welds within the examination boundaries of inter-secting circumferential welds provided the following requirements are met. (1) Where longitudinal welds are specified and locations are known, examination requirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of lon-gitudinal weld within the circumferential weld ex-amination volume; (.. (2) Where longitudinal welds are specified but locations are unknown, or the existence of longitu-dinal welds is uncertain, the examination require-ments shall be met for both transverse and parallel flaws within the entire examination volume of inter-secting circumferential welds. " ~ O ' 903 SUPP. 6 - NC
I 2 GEORGIA POWER COMPANY , PLANT NAME, UNIT 2 j THIRD 10-YEAR INTERVAL j REQUEST FOR RELIEF NO. RR-8
- 1. System /Comoonent(s) for Which Reliefis Requested: This Relief Request applies to the
, Class 1, 2, & 3 Tables included in the ISI Program II. Code Reauirement: According to 10 CFR Part 50.55a(g)(4)(ii), " Inservice examination of l components and system pressure test conducted during successive 120-month inspection intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section 12 months prior to the start of the 120-month inspection interval, subject to the limitations and modifications listed in paragraph (b) of this section." The ASME, Section XI,1989 Edition, IWA-2413 states, "The inspection plan for each successive inspection interval shall comply with the Edition and Addenda of this Division that has been adopted by the regulatory authority 12 months prior to the start of the inspection interval, or subsequent Edition and Addenda that have been adopted by the regulatory authority. Specific portions of such subsequent Editions or Addenda may be used l
. provided all related requirements are met."
Permission is requested to start the Hatch Unit 2 Third 10-Year Inspection Interval (and O subse9uent inspection intervais. ror the remainder of the niant iife> ahead of scheduie such that the two Hatch units will be under the same edition of the Code. Hatch Unit 2 would normally update for the Third 10-Year Interval in September,1999. Permission was previously sought and granted (9/86) for early update at the start of the Second 10-Year Inspection Interval for Hatch Unit 2. This relief will simply continue the practice already established during Interval 2. Ill. Code Reauirement from Which Reliefis Requested: Reliefis requested to start the Hatch ; Unit 2 Third 10-Year Inspection Interval (and subsequent Inspection Intervals, for the l remainder of the plant life) ahead of schedule such that the two Hatch units will be under the same edition / addenda of the Code. IV. Basis for Relief: Previously, during the second 40-month inspection period for Hatch Unit 2, permission was sought and granted to begin the new Second 10-Year Inspection Interval in the :=0 time frame as Hatch Unit 1. This allowed one Code edition / addenda to be used. By being able to continue using the same Code for the Third 10-Year Inspection Interval (and subsequent Inspection Intervals, for the remainder of the plant life): A more comprehensive examination will be achieved which will enhance the possibility of detecting a generic problem and will also reduce costs involved in maintaining two separate programs. Components will be examined at the same point in time as was planned in the earlier O m l Rev.0 Page1of2
O v. Alternate examinations: Not Applicable. Georgia power Company will continue o i schedule Code-required examinations as required by IWA-2413. l VI. Justification for the Granting of Relief: (See item IV. Basis for Relief). By being able to continue using the same Code edition for the Third 10-Year Inspection Interval (and subsequent Inspection Intervals, for the remainder of the plant life), a more comprehensive examination will be achieved which will enhance the possibility of detecting a generic 4 problem. It will also reduce costs involved in maintaining two separate programs and
, prevent possible errors associated with maintaining two programs with different requirements.
4 Granting of this Relief Request will ensure that an acceptable level of quality and safety will have been achieved and public health and safety will not be endangered. l VII. Implementation Schedule: The Code-required examinations will be performed during the Third 10-Year Interval (and subsequent Inspection Intervals, for the remainder of the plant life). NOTE: This Relief Request was previously approved on 9/29/86 and 6/22/89 for the Second Interval. The Relief Request number was 8.1.2, later changed to 6.1.2.
- O i
? i 1 1 m U RR-8 Rev. O Page 2 of 2
i l I GEORGIA POWER COMPANY D PLANT HATCH, UNIT 1 & 2 THIRD 10-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-9 I. System /comoonent(s) for Which Reliefis Requested: All ASME Class 1,2 and 3 piping and components included within the scope of the ISI Program
- 11. Code Requirement: ASME Section XI components require a hydrostatic pressure test aller welded repairs or installation of replacement items by welding, as noted in IWA-4000.
Ill. Code Reauirement for Which Reliefis Reauested: Reliefis requested from performing the required hydrostatic test for Section XI components after welded repairs or installation of replacement items by welding. IV. Basis for Relief: ASME Section XI Code Case N-416-1 was issued on February 15, 1994. This Code Case has been approved by the NRC staff for use at Plant Hatch and other plants, but has not been formally endorsed by inclusion in NRC Regulatory Guide 1.147. It was previously approved for Plant Hatch by SER dated 6/15/95. V. Alternate Examinations: Georgia Power Company will comply with the pressure testing y} requirements of ASME Section XI Code Case N-416-1 for welded repairs or installation of replacement items by welding. In addition to the alternative rules of Code Case N-416- , 1, GPC proposes to augment the alternative tests by performing an additional surface j examination on the root pass layer of butt and socket welds on the pressure retaining boundary of Class 3 components. VI. Justification for the Granting of Relief: The proposed alternative testing requirements have been evaluated by the ASME Code Committee and the NRC and have been deemed , 1 acceptable for determining the pressure boundary integrity of the affected components. Implementation of pressure testing in accordance with the subject Code Case will ensure an acceptable level of quality and safety, does not decrease the margin of public health , and safety and is thus authorized pursuant to 10 CFR 50.55a(a)(3)(i). By implementing the alternative examinations, reduction in costs, personnel radiation dose, and outage time I can be realized by Georgia Power Company at Plant llatch ! Vll. Imnlementation Schedule: The alternative rules for post repair / installation hydrostatic l testing for Class 1,2, and 3 systems in accordance with Code Case N-416-1 will be used j for the Third 10-Year Interval. ! I l RR-9 l Rev.O Page1of1 ,
CASE N-416-1 l CASES OF ASME BOILER AND PRESSURE VESSEL CODE
- l'
.k Approval Date: February 15,1994 See Numeric Index for expiration and any reaffirmation dates.
Case N416-1 placement items by welding, a system leakage test may Alternative Pressure Test Requirement for Welded be used provided the following requirements are met. Repairs or Installation of Replacement Items by (a) NDE shall be performed in accordance with the Welding, Class 1,2 and 3 methods and acceptance criteria of the applicable Sub-Section XI, Division 1 section of the 1992 Edition of Section III. (b) Prior to or immediately upon retum to se:Vice, a visual examination (VT-2) shall be performed in con-Inquiry: What attemative pressure test may be per- junction with a system leakage test, using the 1992 Edi-formed in lieu of the hydrostatic pressure test required tion of Section XI, in accordance with para. IWA-5000, by para. IWA-4000 for welded repairs or installation of at nominal operating pressure and temperature. 1 replacement items by welding? (c) Use of this Case shall be documented on an NIS-2 Form. Reply: It is the opinion of the Committee that in lieu If the previous version of this case were used to defer of performing the hydrostatic pressure test required by a Class 2 hydrostatic test, the deferred test may be elim-para. IWA4000 for welded repairs or installation of re- inated when the requirements of this revision are met.
'O i
i i NJ N SUPP. 8 - NC
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n GEORGIA POWER COMPANY (.) PLANT HATCH, UNIT 1 & 2 THIRD 10-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-10 I. System / Component (s) for Which Reliefis Requested: All welds and areas in the ISI Program that are subject to surface or volumetric examination. II. Code Requirement: Section XI, Table IWA-2610, requires that a reference system be ) established for all welds and areas subject to surface or volumetric examination. III. Code Requirement from Which Reliefis Requested: Reliefis requested from establishing a weld reference system for all welds and areas subject to examination. IV. Basis for Relief. Physical and radiological limitations prevent the actual marking of the majority of the RPV welds, nozzle welds, and piping welds. Many of these limitations actually prohibit complete examination of the welds. Many of the welds which could be accessed are covered by insulation. V. Alternate Examinations: N/A VI. Justification for the Granting of Relief: Each weld is referenced to permanently located fixtures in the immediate area of the subject weld. These references include such items as O nozzies. giani azimuth, and <ieor identi<ications, weided attachments, and concrete embedments. Each weld is described in the examination plan and on the examination reports in such a manner as to make it unique. For each weld that is examined, the starting point is identified and the direction of travel is noted on the examination report in order that any indications can be accurately located. The configuration of the welds permits the inspectors to locate the weld edges which are used to locate the weld centerline. Each weld subject to inservice examination will receive the Code required reference markings and identification, as inservice examinations are being perfonned. VII. Implementation Schedule: The applicable examinations and subsequent markings will continue being performed during the Third 10-Year Interval. NOTE: This Relief Request was previously approved, with conditions on 6/22/89 for the , Second Interval. The Relief Request number was 8.1.6, later changed to 6.1.6. ! l
'O RR-10 Rev.O Page1 ofI ;
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p GEORGIA POWER COMPANY PLANT HATCH, UNIT 1 & 2 THIRD 10-YEAR INTERVAL REQUEST FOR RELEF NO. RR-11 I. System / Component (s) for Which Reliefis Requested: All ASME Class 1,2, and 3 Snubbers included within the scope of the ISI Program II. Code Requirement: Section XI, IWF-5300 (a) and (c) require that visual exansnations of snubbers and nonintegral attachments (including lugs (nonintegral), bolting, pins, and clamps) shall be examined by personnel certified to ASME XI VT-3 requirements. III. Code Requirement from Which Reliefis Requested: Reliefis requested from using Section XI qualified personnel to perform the Code-required visual examinations of snubbers and their associated nonintegral attachments, including lugs, bolting, pins, and clamps. IV. Basis for Relief: A selective group of Georgia Power Company (GPC) Maintenance Department personnel have received special training in the examination and testing of snubbers. This training has included specialized classes presented by various snubber vendors and contractors and has included training for the identification of potential problems and deficient conditions relative to snubber operability. These classes have included instructions in snubber repair and complete overhaul and these same maintenance personnel have been trained to perform snubber functional testing. These maintenance Os personnel have been far more involved and have accumulated many more hours of
- experience in activities associated with the removal, installation, examination, repair, i overhaul, and testing of snubbers than a typical ASME XI VT-3 certified inspector.
The qualifica: ion of personnel will be in accordance with the Georgia Power Company Quality Assurance Program for training and qualification of plant personnel. The subject maintenance personnel will have all such training documented to the training program requirements. These IWF activities will be documented in the Site Snubber Program. Additionally, the GPC snubber examination procedures require that all examination data sheets be reviewed by the site snubber engineer for concurrence and resolution of any reported conditions. (This Relief Request does not address the IWB, IWC, or IWD examinations which will be performed in accordance with Subarticle IWA-2300, Qualifications of Nondestructive Examination Personnel.) V. Alternate Examinations: Maintenance personnel who have been trained to recognize potential problems and deficient conditions specifically applicable to snubbers and who are involved with the si,ubber functional testing program will be utilized to perform the snubber visual examinations required by IWF-5300 (a) and (c) and Table IWF-2500-1 (excluding welded attachments). RR-11 Rev.O Page1of2 4
VI Justificati n f r the Granting of Relief. Utilization of GPC maintenance personnel who have O been specifically trained to inspect, test, repair and overhaul snubber supports and who perform the examinations in conjunction with the Site Snubber Program will: l l e eliminate a redundant inspection by VT-3 certified personnel, thus reducing man-power requirements, costs, and radiation exposure, i i e. provide examination by personnel with extensive experience in snubber applications and maintenance, and i e meet all aspects ofIWF, other than the certification ofinspection personnel.
, These examinations of snubbers and the nonintegral attachments will provide reasonable l l assurance that unallowable inservice flaws have not developed or that they will be detected
, and repaired prior to return of the reactor vessel to service. Thus an acceptable level of i quality and safety will have been achieved and public health and safety will not be 1 endangered by allowing the proposed alternative qualification of inspection personnel. i VII. Imolementation Schedule: The subject examinations will be performed during the Third 10 Year Interval. ; lO i I 4 l !O RR-11 Rev.O Page 2 of 2
O TAL 1 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method Altemative item No. Cateoorv Description Area (s) to Be Examined Examination Examinations B1.11 B-A Reactor Pressure Vessel Circumferential Shell Welds Volumetric No B1.12 B-A Reactor Pressure Vessel Longitudinal Shell Weld Volumetric No B1.21 B-A Reactor Pressure Vessel Longitudinal Shell Welds Volumetric No and Closure Head 81.22 B-A Reactor Pressure Vessel- Meriodional Head Welds Volumetric No and Closure Head B.1.30 B-A Reactor Pressure Vessel Shell-to Flange Weld Volumetric No B1.40 B-A Reactor Pressure Vessel Head-to-Flange Weld Surface and No Closure Head Volumetric B1.51 B-A Reactor Pressure Vessel Beltline Region Repair Volumetric Not Welds applicable to either Hatch unit. B2.10 B-B Pressurizer Shell-to-Head Welds Volumetric Not - applicable to either Hatch unit. B2.20 B-B Pressurizer Head Welds Volumetric Not applicable to either Hatch unit. B2.30 B-B Steam Generator Head Welds Volumetric Not applicable to (Primary Side) either Hatch unit. PRGTBL1 Rev.O Page 1 of 14 u __ _ _ _ _ _ _ _ _ -
i tai, 1 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method Attemative item No. Cateaorv Description Area (s) to Be Examined Examination Examinations B2.40 B-B Steam Generator Tubesheet-to-Head Welds Volumetric Not (Primary Side) applicable to either Hatch unit B2.50 B-B Heat Exchangers Head Welds Volumetric Not (Primary Side) applicable to either Hatch unit B2.60 B-B Heat Exchangers Tubesheet-to-Shet! Volumetric Not applicable to (Primary Side) (or Head) Welds either Hatch unit. B2.70 B-B Heat Exchangers Tubesheet-to-Shell Volumetric Not applicable to (Primary Side) (or Head) Welds either Hatch unit. B2.80 B-B Heat Exchangers Tubesheet-to-Shell Volumetric Not applicable to (Primary Side) (or Head) Welds either Hatch unit. 83.10 B-D Reactor Pressure Vessel Nozzle-to-Vessel Welds Vo'umetric Not applicable to either Hatch unit.; GPC has elected to perform examinations in accordance with Program B. B3.20 B-D Reactor Pressure Vessel Nozzle inside Radius Volumetric Not applicable to Section either Hatch unit.; GPC has elected to perform examinations in accordance with Program B. PRGTBL1 Rev.O Page 2 of 14
O T^'n<' O ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination ' System or Component Method Altemative item No. Cateoory Description Area (s) to Be Examined Examination - Examinations 83.30 B-D Pressurizer Nozzle-to-Vessel Welds Volumetric Not applicable to either Hatch unit. B3.40 B-D Pressurizer Nozzle inside Radius Volumetric Not applicable to Section either Hatch unit. B3.50 B-D Steam Generators Nozzle-to-Vessel Welds Volumetric Not applicable to (Primary Side) either Hatch unit. B3.60 B-D Steam Generators Nozzle inside Radius Volumetric Not applicable to (Primary Side) Section either Hatch unit. 83.70 B-D Heat Exchangers Nozzle-to-Vessel Welds Volumetric Not applicable to (Primary Side) either Hatch unit. 83.80 B-D Heat Exchangers Nozzle inside Radius Volumetric Not applicable to (Primary Side) Section either Hatch unit. B3.90 B-D Reactor Pressure Nozzle-to-Vessel Welds Volumetric : Yes, RR-3 Vessel B3.100 B-D Reactor Pressure Nozzle inside Radius Volumetric Yes, RR-3 Vessel Section B3.110 B-D Pressurizer Nozzle-to-Vessel Welds Volumetric Not applicable to either Hatch unit. 83.120 B-D Pressurizer Nozzle Inside Radius Volumetric Not applicable to Section either Hatch unit B3.130 B-D Steam Generators Nozzle-to-Vessel Welds Volumetric Not applicable to (Primary Side) either Hatch unit. 83.140 B-D Steam Generators Nozzle inside Radius Volumetric Not applicable to (Primary Side) Section either Hatch unit. PRGTBL1 Rev.O I Page 3 of 14
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TA 1 ISi PROGRAM FOR ASME CLASS 1 COMPONENTS EDW;N 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination Syctem or Component Method Altemative item No. Cateoory Description Area (s) to Be Examined Examination Examinations B3.150 B-D Heat Exchangers Nozzle-to-Vessel Welds Volumetric Not applicable to (Primary Side) either Hatch unit. B3.160 B-D Heat Exchangers Nozzle inside Radius Volumetric Not applicable to (Primary Side) Section either Hatch unit. B4.11 B-E Vessel Nozzles Extemal Surfaces of Visual, VT-2 Yes, RR-2 Partial Penetration Welds B4.12 B-E Control Rod Drive Extemal Surfaces of Visual, VT-2 Yes, RR-2 Nozzles Partial Penetration Welds B4.13 B-E Instrumentation Extemal Surfaces of Visual, VT-2 Yes, RR-2 Nozzles Partial Penetration Welds 84.20 B-E Pressurizer Extemal Surfaces of Visual, VT-2 Not applicable to Heater Penetration Welds either Hatch unit B5.10 B-F Reactor Pressure Vessel Nozzle-to-Safe End Butt Surface and Yes, N-461 Welds (Nominal Pipe Volumetric Size 24 in.) B5.20 B-F Reactor Pressure Vessel Nozzle-to-Safe End Butt Surface Yes, RR-6 Welds (Nominal Pipe Size <4 in.) 85.30 B-F Reactor Pressure Vessel Nozzle-to-Safe End Surface Not applicable to Socket Welds either Hatch unit B5.40 B-F Pressurizer Nozzle-to-Safe End Butt Surface and Not applicable to Welds (Nominal Pipe Volumetric either Hatch unit Size 14 in.) B5.50 B-F Pressurizer Nozzle-to-Safe End Butt Surface Not applicable to Welds (Nominal Pipe either Hatch unit Size <4 in.) PRGTBL1 Rev.O Page 4 of 14
O -Q TAk21 O. ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method Altemative - l tem No. Cateoorv Description Area (s) to Be Examined Examination Examinahons B5.60 B-F Pressurizer Nozzle-to-Safe End . Surface Not applicable to Socket Welds either Hatch unit B5.70 B-F- Steam Generators Nozzle-to-Safe End Butt Surface and Not applicable to (Primary Side) Welds (Nominal Pipe Volumetric either Hatch unit Size 24 in.) B5.80 B-F Steam Generators Nozzle-to-Safe End Butt Surface Not applicable to (Primary Side) Welds (Nominal Pipe either Hatch unit Size <4 in.) B5.90 B-F Steam Generators Nozzle-to-Safe End Surface Not applicable to (Primary Side) Socket Welds either Hatch unit B5.100 B-F Heat Exchangers Nozzle-to-Safe End Butt Surface and Not applicable to i (Primary Side) Welds (Nominal Pipe Volumetric either Hatch unit Size 24 in.) B5.110 B-F Heat Exchangers Nozzle-to-Safe End Butt Surface Not applicable to ! (Primary Side) Welds (Nominal Pipe either Hatch unit i Size <4 in.) B5.120 B-F Heat Exchangers Nozzle-to-Safe End Suiface Not applicable to (Primary Side) Socket Welds either Hatch unit B5.130 B-F Piping Dissimilar Butt Welds Surface and No (Nominal Pipe Size Volumetric 24in.) B5.140 B-F Piping Dissimilar Butt Welds Surface Not applicable to (Nominal Pipe size either Hatch unit ~
<4 in.)
B5.150 B-F Piping Dissimilar Metal Socket Surface Not applicable to Welds either Hatch unit PRGTBL1 Rev.O Page 5 of 14
T 1 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination - System or Component Method Attemative item No. Cateoorv Description Area (s) to Be Examined Examination Examinations B6.10 B-G-1 Reactor Pressure Vessel Closure Head Nuts Surface Yes, RR-1 B6.20 B-G-1 Reactor Pressure Vessel Closure Studs,in Place Volumetric Yes, N-307-1 B6.30 B-G-1 Reactor Pressure Vessel Closure Studs, When Removed Surface and Yes, N-307-1 Volumetric B6.40 B-G-1 Reactor Pressure Vessel Threads in Flange Volumetric No B6.50 B-G-1 Reactor Pressure Vessel Closure Washers, Bushings Visual, VT-1 No B6.60 B-G-1 Pressurizer Bolts and Studs Volumetric Not applicable to either Hatch unit B6.70 B-G-1 Pressurizer Flange Surface, When Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit B6.80 B-G-1 Pressurizer Nuts, Bushings, and Visual, VT-1 Not applicable to Washers either Hatch unit B6.90 B-G-1 Steam Generator Bolts and Studs Volumetric Not applicable to either Hatch unit B6.100 B-G-1 Steam Generator Flange Surface, When Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit B6.110 B-G-1 Steam Generator Nuts, Bushings, and Visual, VT-1 Not applicable to Washers either Hatch unit . 86.120 B-G-1 Heat Exchangers Bolts and Studs Volumetric Not applicable to either Hatch unit PRGTBL1 Rev.O Page 6 of 14
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I ISI PROGRAM FOR ASME CLASS 1 COMPONENTS ; EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 I Examination System or Component Method Altemative item No. Cateoorv Description Area (s) to Be Examined Examination Examinations 86.130 B-G-1 Heat Exchangers Flange Surface, When Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit , B6.140 B-G-1 Heat Exchangers Nuts, Bushings, and Visual, VT-1 Not applicable to ' Washers either Hatch unit B6.150 B-G-1 Piping Bolts and Studs Volumetric Not applicable to either Hatch unit : B6.160 B-G-1 Piping Flange Surface, When Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit B6.170 B-G-1 Piping Nuts. Bushings, and Visual, VT-1 Not ipplicable to + Washers either Hatch unit ' B6.180 B-G-1 Pumps Bolts and Studs Volumetric No B6.190 B-G-1 Pumps Flange Surface, When Visual, VT-1 No ! Connection Disassembled i B6.200 B-G-1 Pumps Nuts, Bushings, and Visual, VT-1 No Washers j B6.210 B-G-1 Valves Bolts and Studs Volumetric Not applicable to either Hatch unit ' B6.220 B-G-1 Valves Flange Surface, When Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit . B6.230 B-G-1 Valves Nuts, Bushings, and Visual, VT-1 Not applicable to I Washers either Hatch unit i PRGTBL1 Rev.0 , Page 7 of 14 , I
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t' g ' TABEE 1 - ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method Altemative item No. Cateaory Description Area (s) to Be Examined Examination Examinations B7.10 B-G-2 Reactor Pressure Vessel Bolts, Studs, and Nuts Visual, VT-1 Not applicable to either Hatch unit B7.20 B-G-2 Pressurizer Bolts Studs, and Nuts Visual, VT-1 Not applicable to either Hatch unit B7.30 B-G-2 Steam Generators Bolts. Studs, and Nuts Visual, VT-1 Not applicable to either Hatch unit B7.40 B-G-2 Heat Exchangers Bolts, Studs, and Nuts Visual, VT-1 Not applicable to - either Hatch unit B7.50 B-G-2 Piping Bolts, Studs, and Nuts Visual, VT-1 No B7.60 B-G-2 Pumps Bolts, Studs, and Nuts Visual, VT-1 Not applicable to either Hatch unit B7.70 B-G-2 Valves Bolts. Studs, and Nuts Visual, VT-1 No B7.80 B-G-2 CRD Housings Bolts, Studs, and Nuts Visual, VT-1 No (When Disassembled) B8.10 B-H Reactor Pressure Vessel Integrally Welded Volumetric or No Attachments Surface as Applicable 88.20 B-H Pressurizer Integrally Welded Volumetric or Not applicable to Attachments Surface, as either Hatch unit Applicable 88.30 B-H Steam Generators Integrally Welded Volumetric or Not applicable to Attachments Surface, as either Hatch unit Applicable PRGTBL1 Rev.O Page 8 of 14
0 1cO, O ISI PROGRAM FOR ASME Ct. ASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method Altemative item No. Cateoory Description _ Area (s) to Be Examined Examination Examinations B8.40 B-H Heat Exchangers integrally Welo 'J Volumetric or Not applicable to Attachments Surface, as either Hatch unit , Applicable B9.11 B-J Piping Circumferential Welds Surface and Yes, N-461 (Nominal Pipe Size Volumetric 14 in.) B9.12 B-J Piping Longitudinal Welds Surface and Yes, RR-7 - (Nominal Pipe Size Volumetric 14 in.) B9.21 B-J Piping Circumferential Welds Surface No (Nominal Pipe Size
<4 in.) i B9.22 B-J Piping Longitudinal Welds Surface Not applicable to (Nominal Pipe Size either Hatch unit
<4 in.)
89.31 B-J Piping Branch Pipe Connection Surface and No Welds (Nominal Pipe Volumetric size 14 in.) B9.32 B-J Piping Branch Pip Ccnnection Surface No Welds (Nominal Pipe Size <4 in.) B9.40 B-J Piping Socket Welds Surface Not applicable to either Hatch unit PRGTBL1 Rev.O Page 9 of 14
O ISI PROGRAM FOR ASME CLASS 1 COMPONENTS TD O~ EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Methoit Attemative item No. Cateaory Description Area (s) to Be Examined Examinat? ort Examinations B10.10 B-K-1 Piping Integrally Welded -Vo'umetric or Yes, RR-4 Attachments Surface, as Applicable B10.20 - B-K-1 Pumps Integrally Welded Volumetric or Yes, RR-4 Attachmente Surface, as Applicable B10.30 B-K-1 Valves Interally Welded Volumetric or Not applicable to Attachments Surface, as either Hatch unit Applicable B12.10 B-L-1 Pumps Pump Casing Welds Volumetric Not applicable to either Hatch unit 812.20 B-L-2 Pumps Pump Casing Visual, VT-3 No B12.30 B-M-1 Valves Valve Body Welds Surface Not applicable to (Nominal Pipe Size either Hatch unit
<4 in.)
B12.40 B-M-1 Valves Valve Body Welds Volumetric Not applicable to (Nominal Pipe Size either Hatch unit
>4 in.)
l l l l PRGTBL1 Rev.O Page 10 of 14
i T 1 l ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method Altemative item No. Cateoory Description Area (s) to Be Examined Examination Examinations B12.50 B-M-2 Valves Valve Body Visual, VT-3 No (Nominal Pipe Size
>4 in.)
B13.10 B-N-1 Reactor Pressure Vessel Vessel Interior Visual, VT-3 No 813.20 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT 1 No (BWR) Within Beltline Region B13.30 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-3 No (BWR) Beyond Beltline Region B13.40 B-N-2 Reactor Pressure Vessel Core Support Structure Visual, VT-3 No (BWR) B13.50 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-1 Not applicable to (PWR) Within Beltline Region either Hatch unit B13.60 B-N-2 Reactor Pressure Vessel InteriorAttachments Visual, VT-3 Not applicable to (PWR) Beyond Beltline Region either Hatch unit B13.70 B-N-3 Reactor Pressure Vessel Core Support Structure Visual, VT-3 Not applicable to (PWR) (Removed) either Hatch unit B14.10 B-0 .<eactor Pressure Vessel Welds in Control Rod Volumetric or No Drive Housing Surface PRGTBL1 Rev.O Page 11 of 14
J.. TALo1 O ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method Altemative item No. Cateoorv Description Area (s) to Be Examined Examination . Examinations B15.10 B-P Reactor Pressure Vessel Pressure Retaining System Leakage No Boundary Test; Visual, - VT-2 . t B15.11 B-P Reactor Pressure Vessel Pressure Retaining System Hydro- Yes, RR-2 Boundary Test; Visual, VT-2 1 B1520 B-P Pressurizer Pressure Retaining - System Leakage Not applicable to Boundary Test; Visual, either Hatch unit VT-2 B15.21 B-P Pressurizer Pressure Retaining System Hydro- Not applicable to Boundary Test; Visual, either Hatch unit VT-2 B15.30 B-P Steam Generators Pressure Retaining System Leak- Not applicable to Boundary age Test; either Hatch unit Visual, VT-2 B15.31 B-P Steam Generators Pressure Retaining System Hydro- Not applicable to Boundary test; Visual, either Hatch unit VT-2 i PRGTBL1 Rev.O i Page 12 of 14 i
TA 1 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2
- Examination System or Component Method Altemative item No. ' Cateaory. Description Area (s) to Be Examined Examination Examinahons B15.40 B-P Heat Exchangers Pressure Retaining System Leak- Not applicable to Boundary age Test; edher Hatch unit Visual, VT-2 B15.41 B-P Heat Exchangers Pressure Retaining System Hydro- Not applicable to Boundary test; Visual, either Hatch unit VT-2 B15.50 .B-P Piping Pressure Retaining System Leak- No Boundary age Test; Visual, VT-2 B15.51 B-P Piping Pressure Retaining System Hydro- .Yes, RR-2 Boundary test; Visual, VT-2 B15.60 B-P Pumps Pressure Retaining System Leak- No Boundary age Test; Visual, VT-2 B15.61 B-P Pumps Pressure Retaining System Hydro-- Yes, RR-2 Boundary test; Visual, .
VT-2 PRGTBL1 Rev.O Page 13 of 14
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O o TA's.e 1 O ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method Attemative item No. Cateaory Description Area (s) to Be Examined Examination Examinations B15.70 B-P Valves Pressure Retaining System Leak- No Boundary age Test; Visual, VT-2 B15.71 B-P Valves Pressure Retaining System Hydro- Yes, RR-2 Boundary test; Visual, VT-2 B16.10 B-Q Steam Generator Tubing Straight Tube Design Volumetric Not applicable to either Hatch unit B16.20 B-Q Steam Generator Tubing U-Tube Design Volumetric Not applicable to either Hatch unit PRGTBL1 Rev.O Page 14 of 14
W b v v) TABLE 2 ISI PROGRAM FOR ASME CLASS 2 COMFONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examinahon System or Component Method of Altemahve item No. Cateoorv Description Ares (s) to Be Examined Exammahon Exammahons C1.10 C-A Pressure Vessels Shell Circumferential Welds Volumetric No C1.20 C-A Pressure Vessels Head Circumferential Welds Volumetric Yes, RR-5 C1.30 C-A Pressure Vessels Tubesheet-to-Shell Weld Volumetnc No C2.11 C-8 Pressure Vessels Nozzles-to-Shell (or Head) Surface Not apphcable to Weld Where Vessel Nominal ether Hatch unit Thickness 51/2 inch - C2.21 C-B Pressure Vessels Nozzle-to-Shell (or Head) Surface and No Weld for Vessels Without Volumetric Reinforemg Plates Where Vessel Nominal Thickness
>1/2 inch C2.22 C-B Pressure Vessels Nozzle inside Radius Volumetric Not apphcable to Section for Vessels with- edher Hatch unit out Reinforcing Plates Where Vessel Nominal Thickness >1/2 inch C2.31 C-B Pressure Vessels Reinforcing Plate Welds to Su face Not applicable to Nozzle and Vessel either Hatch unit Where Vessel Nominal Tinckness >1/2 inch PRGTB234 l Rev.O Page 1 of 6
O O O . I TABLE 2 ISI PROGRAM FOR ASME CLASS 2 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method of Altemative item No. Cateoorv Description Area (s) to Be Examined Examination Examinabons C2.32 C-B Pressure Vessels Nozzle-to-Shell(or Head) Volumetric Not apphcable to , Welds forVessels With Re- ether Hatch unit i enforcing Plates When inside of Vesselis Accessible and Vessel Nominal Theckness
>1/2 inch C2.33 C-B Pressure Vessels Nozzle-to-Shell (or Head) Visual, Not apphcable to Weld forVessel With VT-2 ether Hatch und Reinforcing Plates When inside of Vesselin inaccessable i
and Vessel Nominal Theckness
> 1/2 inch.
C3.10 C-C Pressure Vessels Integrally Welded Surface Yes, RR-4 Attachments C3.20 C-C Piping Integrally Welded Surface Yes, RR-4 Attachments C3.30 C-C Pumps integralty Welded Surface Not apphcable to , Attachments other Hatch unk C3.40 C-C Valves Integrally Welded Surface Not applicable to Attachments other Hatch unk C4.10 C-D Pressure Vessels Bolts and Studs Volumetnc Not applicable to ether Hatch unk 1 C4.20 C-D Piping Bolts and Studs Volumetric Not applicable to ether Hatch unit PRGTB234 Rev.O Page 2 of 6
O O O TABLE 2 ISI PROGRAM FOR ASME CLASS 2 COMPONENTS EDWIN L HATCH NUCLEAR PLANT, UNITS 1 AND 2 Exammation System or Component Method of Akemahve item No. Cateoorv Descnotion Area (s) to Be Exarmned Examenshon Examensbons C4.30 C-D Pumps Bolts and Studs Volumetric Not appicable to esther Hatch unit C4.40 C-D Valves Bolts and Studs Volumetnc Not applicable to esther Hatch unit C5.11 C-F-1 SS Piping Cwcumferential Welds Surface and Not apphcable to 13/8 inch Nominal Wall Volumetnc esther Hatch unit Thickness for Piping
> NPS 4 C5.12 C-F-1 SS Piping Longitudinal Welds Surface and Not apphcable to 13/8 inch Nominal Wall Volumetnc either Hatch unit Thickness for Piping
> NPS 4 C5.21 C-F-1 SS Piping Circumferential Welds Surface and Not apphcable to
> 1/5 inch Nominal Wall Volumetnc either Hatch unit Thickness for Piping 1NPS 2 and 5 NPS 4 C5.22 C-F-1 SS Pipen0 Longitudinal Welds Surface and Not apphcable to
> 1/5 inch Nominal Wall Volumetnc either Hatch unit Thickness for Piping 2 NPS 2 and 5.NPS 4 ,
C5.30 C-F-1 SS Pipin0 Socket Welds Surface Not appbcable to esther Hatch unit. i PRGTB234 Rev.O Page 3 of 6 l
O O TABLE 2 O ISI PROGRAM FOR ASME CLASS 2 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Exammation System or Component Method of Altemative item No. Cateoory Description AreaN to Be Examined Examination Exanmations C5.41 C-F-1 SS Piping Circumferenhat Weids Surface Not apphcable to Pipe Branch Connections either Hatch unit (Nominal Pipe Size 12) C5.42 C-F-1 SS Piping Longitudinal Welds Surface Not apphcable to Pipe Branch Connections either Hatch unit (Nominal Pipe Size 12) C5.51 C-F-2 CS Piping Circumferential Welds Surface and Yes, N-461 23/8 inch Nominal Wall Volumetric Thickness for Piping
> NPS 4 C5.52 C-F-2 CS Piping Longitudinal Welds Surface and Yes, RR-7 13/8 inch Nominal Wall Volumetnc Thickness for Piping
> NPS 4 C5.61 C-F-2 CS Piping Circumferential Welds Surface and Not applicable to
> 1/5 inch Nominal Wall Volumetric either Hatch unit for Piping 2 NPS 2 and
- 5. NPS 4 C5.62 C-F-2 CS Piping Longitudinal Welds Surface and Not apphcable to
> 1/5 inch Nominal Wall Volurnetnc either Hatch unit Thickness for Piping 2 NPS 2 and 5 NPS 4 C5.70 C-F-2 CS Piping Socket Welds Surface Not applicable to either Hatch unit PRGTB234 Rev.O Page 4 of 6
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O O O ' j TABLE 2 ISI PROGRAM FOR ASME Cl. ASS 2 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Exammahon System or Ccii faw-rit Method of Altemative ; Item No. Cateoorv Desenchon Area (s) to Be Exammed Examenabon Examinshons C5.81 C-F-2 CS Piping Circumferenhal Welds Pipe Surface No Branch Connechons (Nommal Pipe Size 2.2) C5.82 C-F-2 CS Piping Longitudinal Welds Pipe Surface Yes RR-7 Branch Connechons (Nominal Pipe Size 12) C6.10 C-G Pumps Pump Casing Welds Surface Not apphcable to i ether Hatch unit ; C6.20 C-G Valves Valve Body Welds Surface Not apphcable to eMher Hatch unit C7.10 C-H Pressure Vessels Pressure Retaining System Pres- Not apphcable to Components sure Test; eMher Hatch unit l Visual, VT-2 l l C7.20 C-H Pressure Vessels Pressure Retammg System Hydro- Yes, RR-2 l Components static Test; , i Visual, VT-2 C7.30 C-H Piping Pressure Retaining System Pres- Not apphcable to Components sure Test; ether Hatch unit Visual, VT-2 C7.40 C-H Piping Pressure Retammg System Hydro- Yes, RR-2 Components static Test; Visual, VT-2 C7.50 C-H Pumps Pressure Retammg System Pres- No Components sure Test; Visual, VT-2 PRGTB234 Rev.O Page 5 of 6
. _ _ _ _ _ _ _ _ . _ _ = . _ . _ _ . _ _ _ _ _ _ . _ . . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . . _
_ _ . . - . __ _ _ ., _ . . _ . . . _ . - .._. .~- l
.O O O TABLE 2 ,
ISI PROGRAM FOR ASIE CLASS 2 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 Ale 2 Examwiahon SyQmt or Component Method of Altematwo item No. Catenorv Descrichon Ares (s) to Be Examined Exammalmn Examinehons l C7.60 C-H Pumps Pressure Retamin0 System Hydm- Yes, RR-2 l_ CuiT.pcGere stahc test; ; j Visual, VT-2 ; C7.70 C-H Valves Pressure Retammg System Pres- No , CviTipur cc sure Test; , Visual, VT-2 C7.80 C-H Valves Pressure Retaemng System Hydro- Yes, RR-2 Components static Test; Visual, VT-2 1 i r t i e t PRGTB234 Rev.O Page 6 of 6
O- O O TABl.E 3 ISI PROGRAM FOR ASME Cl. ASS 3 CORFONENTS i EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 APO 2 l Exammahon System or Component Method of Allemahve # Item No. Cateoory Descrichon Ares (s)to Be Examined Exammation Examinsbons D1.10 D-A Systemsin Support of Pmssure Retawung Visual, VT-2 Yes, RR-2 Reactor Shutdown Function Components D1.20 D-A Systems in Support of Integral Attachment- Visual, VT-3 Yes, RR4 Reactor Shutdown Furumon Component Supports and Restraints D1.30 D-A Systems in Support of integral Attachment- Visual, VT-3 Yes, RR4 ; Reactor Shutdown Funchon Mechanical and Hydrauhc - Snubbers D1.40 D-A Systems in Support of Integral Attachment- Visual, VT-3 Yes, RR4 Reactor Shutdown Function Spnng Type Supports j D1.50 D-A Systems in Support of Integral Attachment- Visual, VT-3 Yes, RR4 Reactor Shutdown Furxton Constant Load Type , M ! D1.60 D.A Systems in Support of inte0ral Attachment- Visual, VT-3 Yes, RR4 Reactor Shutdown Function Shock Absorbers t
-i PRGTB234 I
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O O O TABLE 3 ISI PROGRAM FOR ASME CLASS 3 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 APO 2 Examenshon System or Component Method of Allemahve item No. Cateoory Descrichon Area (s)to Be Examined Examina00n Examinsbons D2.10 D-B Systems in Support of Pressure Retaenen0 Visual, VT-2 Yes, RR-2 ECC, CHR, Atmosphere Components Cleanup, and Reactor RHR D2.20 D-B Systems in Support of inte0ral Attachment- Visual, VT-3 Yes, RR4 ECC, CHR, Atmosphere Component Supports and l Cleanup, and Reactor RHR Restraints ! D2.30 D-B Systems in Support of Integral Attachment- Visual, VT-3 Yes, RR4 ECC, CHR, Atmosphere Mechanical and Hydrauhc Cleanup, and Reactor RHR Snubbers D2.40 D-B Systems in Suppost of integral Attachment- Visual, VT-3 Yes, RR4 ECC, CHR, Atmosphere Spring Type Supports Cleanup, and Reactor RHR D2.50 D-B Systems in Support of Integral Attachment- Visual, VT-3 Yes, RR4 ECC, CHR, Atmosphere Constant Load Type Cleanup, and Reactor RHR Supports D2.60 D-B Systems in Support of integral Attachment- Visual, VT-3 Yes, RR4 i ECC, CHR, Atmosphere Shock Absortaers i- Cleanup, and Reactor RHR i i PRGTB234 Rev.0
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O O- O TABLE 3 ISI PROGRAM FOR ASSE Ct. ASS 3 COtrODENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Exammahon System orComponent Method of Allematrve item No. Cateoory Desenotion Areefs) to Be Exammed Examination Examinations D3.10 D-C Systems in Support of Pressure Retsenm0 Visual, VT-2 Yes, RR-2 ' RHR from Spent Fuel Components Storage Pool D3.20 .D-C Systemsin Support of integral Attachment- Visual, VT-3 . Yes, RR4 RHR from Spent Fuel Component Supports and Storage Pool Restramts D3.30 D-C Systems in Support of integral Attachment- Visual, VT-3 Yes, RR4 RHR from Spent Fuel Mechanical and Hydraubc Storage Pool Snubbers D3.40 D-C Systems in Support of Integral Attachment- Visual, VF-3 Yes, RR4 RHR from Sperd Fuel Spnng Type Supports Stora0e Pool D3.50 D-C Systemsin Support of Integral Attachment- Visual, VT-3 Yes, RR4 RHR from Spent Fuel Constant Load Type Storage Pool Supports D3.60 D-C Systems in Support of integral Attachment- Visual, VT-3 Yes, RR4 RHRimm Spent Fuel Shock Absorbers Stora0e Pool PRGTB234 Rev.O Page 3 of 3 _-- _ _ _ _ - --. - - _ _ _ - - - . - = _ - .
O O O TABLE 4 ISI PROGRAM FOR ASME CLASS 1,2, AND 3 COMPONENT SUPPORTS EDWIN 1. HATCH NUCt. EAR PLANT, UNITS 1 AND 2 Exammahon System or Component Method of Altomatwe item No. Catenorv Descnotion Area (s) to Be Examined Exanunshon Egammahons F1.10 F-A Supports Mechenmal Connedions to Visual, VT-3 Yes, N-491, ! Pressure Retanung RR-11 ! Components and Building Structure l F1.20 F-A Supports Weld Connechons to Vusual, VT-3 Yes, N-491, Building Structure RR-11 F1.30 F-A Supports Weld and Mecharucal Visual, VT-3 Yes, N-491, Connections at intermediate RR-11 Jointsin Mulhconnected integral and Nonintegral Supports F1.40 F-A Supports Clearances of Guides and Visual, VT-3 Yes, N-491 Stops, Alignment of Supports, Assembly of Support items F1.50 F-A Supports Spnng Supports and Visual, VT-3 Yes, N-491 Constant Load Supports F1.60 F-A Supports Sliding Surfaces Visual, VT-3 Yes, N-491 F1.70 F-A Supports Hot or Cold Position of Visual, VT-3 Yes, N-491 SPring Supports and Constant Load Supports PRGTB234 Rev.O Page 1 of 1
Ilatch Unit 1 NUREG-0313 Summarv i O Technical Basis DiscusaiQB The following discussion is presented based on each NUREG category as a topic. A description of l the category definition and a brief summary of the Hatch experience within each category is presented. Inspection results along with new inspection frequencies and scope expansion criteria are
] provided. Also, the proposed reclassification of welds is identified where appropriate.
j l Catenorv A 2 These are welds with no known cracks, that have a low probability ofincurring IGSCC problems, because they are made entirely ofIGSCC resistant materials or have been solution heat treated after welding. Corrosion resistant clad is considered to be IGSCC resistant, and weldsjoining cast pump and valve bodies to resistant piping are considered to be resistant weldments.
, The majority of Category A welds are longitudinal seam welds in the B31 Recirculation (RC), El1 a
j Residual Heat Removal (RHR), and G31 Reactor Water Cleanup (RWCU) systems. The welds were ; j solution annealed and are therefore, by NUREG-0313 criteria, considered resistant to IGSCC. ! These have been inspected using a 25% sample criteria during the previous ten-year interval. ! i In the future these long seam welds will not be inspected. Instead Code Case N-524 logic will be l l O used. This code case effectively eliminates the inspection oflongitudinal seam welds except for the
- portion that is included in the inspection boundary of the intersecting circumferential pipe weld. This should be the limiting location for long seam welds due to the proximity within the HAZ (heat affected zone). This was deemed technically acceptable by the ASME Code committees based on the l
4 extensive industry history of operation without a long seam failure. This case has been approved by ASME and on plant specific basis by NRC, but is not yet endorsed by the NRC in Reg. Guide 1.147. Scope expansion for this type weld is not anticipated. This is based on industry experience used to support the Code Case N-524. Ifindications are found in the long seam area that are separate from j the intersecting circumferential weld, Section XI scope expansion criteria for circumferential welds l will be utilized. The remainder of the Category A welds are circumferential welds in the RWCU system, made of i conforming material. The population is comprised of 19 circumferential welds (excluding 1G31-1RWCU-6-D-15B and -15C which are inaccessible due to piping design) and one weld (1G31-1RWCUM-6-D-9) that has an overlay. The overlay was applied during 1988 when the Class 1 RWCU pipe was replaced. It was added to serve as a stress improvement process to mitigate the 0313. DOC Rev.O Page 1 of12
a .J J..a._ 4a J ,,A.rJ.uma ...ms.A r Hatch Unit 1 NUREG-0313 Summary Catenary A (continued) h effects ofID grinding. The weld overlay will be reclassified as Category E' (refer to details of Category E' elsewhere in this document) and as such, will be inspected during the next ten-year-interval using the inspection and scope expansion criteria for that new category. In 1993, the 19 circumferential welds received MSIP treatment as an additional measure to protect against crack initiation in conforming materialf All 19 welds were inspected during the 1993 outage to verify there were no ' detrimental effects associated with the MSIP process. Post-MSIP baseline examinations revealed no indications. This also, for the 19 circumferential welds, satisfies the GL 88-01 requirement ofinspecting stress improved welds within two refueling cycles after the performance of stress improvement. Coincident with the beginning of this 10-year ISI interval, the 19 circumferential welds will be inspected at a sample rate of 25% (5 welds) over the 10-year interval. This is consistent with the current ASME Sectiori XI sampling technique and guidance of GL 88-01. The scope expansion rules of ASME Section XI for Class 1 piping will be used in the event indications warrant. This is consistent with the GL and is technically valid based on the material considerations. Ikcommended Inspections (Third Ten-Year Interval) for Category A: O - circ ==rere#ti i -eids - Examine 25% of the Category A welds over the ten-year interval with the examinations being spread equally over the ten years. This is consistent with ASME Section XI and GL 88-01.
. Longitudinal Seam Welds - Examine these welds in accordance with Code Case N-524. This effectively will eliminate the inspection of the long seams. The code case requires the inspection of the portion of the long seam that is contained within the boundaries of the intersecting j circumferential weld. This will eliminate the need to examine 12 inches oflong seam either side of the circumferential welds.
d
. ASME Section XI scope expansion criteria will be utilized.
I Previous Inspsetion Schedule (Second Ten-Year Interval) for Category A:
. Examine 25% of the welds every ten years (at least 12% in six years per NUREG-0313).
. Scope expansion consists of an additional sample of welds, approximately equal in number and similar in distribution (according to pipe size, system, and location) to the original sample, unless
. there is a technical reason to select a different sample. !
- Catenorv B None currently in service.
0313. DOC l
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1 } Hatch Unit 1 NUREG-0313 Summary : ! Catenary C {Q j These welds are those which join non-resistant materials, contain no evidence of flaws and were subjected to stress improvement (SI) treatment aRer more than two years of operation. GL 88-01 l required ultrasonic inspection during the outage the SI occurred, once within two outages of the SI and then again within ten years. l When the initial GPC commitment to GL 88-01 was made, the examinations required to be completed within 10 years were compressed to a schedule of approximately eight years after SI.
- This was to coincide with the end of the current ten-year interval. This schedule has been altered 4 several times due to outage constraints and IGSCC indications in some Category C welds. Since the j initial commitment was made, scope expansion examinations combined with the regularly scheduled
- examinations have resulted in a significantly larger number of examinations than anticipated. In fact, all but a small number of Category C welds have been inspected beyond the original commitment.
A large number of welds received Induction Heat Stress Improvement (IHSI) treatment during the l 1986 outage. Since that time, the only 12" welds that received weld overlays were two safe-end to nozzle welds and welds that were previously classified as category F (known cracking). This indicates that the SI treatment was effective for the 12" pipe. The 28" inch pipe had twelve welds overlayed due to IGSCC indications during the 1990 outage ) (IB31-lRC-28 A-2, -4, -6, -7, -8, -14 and IB31-1RC-28B-8, -9, -10, -13, -14, -15) and one ! additional weld (IB31-lRC-28B-2) was overlayed in 1991. The occurrence ofindications has i decreased to the point that no reportable indications were noted during the 1993 outage. This is likely the result of hydrogen water chemistry (HWC). , I i Additional welds were added to the Category C group following the 1993 MSIP of Category D l i welds. These welds had no evidence of cracking following the MSIP. { The total number of Category C welds is 78. GPC will continue the inspection of the Category C
]
- welds consistent with the guidance of GL 88-01, i.e. once per each ten-year interval. The welds j t reclassified as C' (refer to details of Category C' elsewhere in this document) will be examined at a frequency of every other outage.
Scope expansion will be developed by GPC each outage based on the indications that occur. It will l be based on system, size and any other appropriate parameters. GPC will determine the sample
- expansion without NRC advance approval, but will provide the sample expansion to the NRC for concurrence at the beginning of the inspections. (This logic is similar to that used by GPC in previous 0313. DOC
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1 Hatch Unit 1 NUREG-0313 Summary Catenorv C(continued) O outages (1988-1995). In each case the sample expansion proposed by GPC was approved by the NRC). Recomman4d Insnections (Third Ten-Year Interval) for Category C:
. Examine all Category C welds during the ten-year interval with the examinations being spread approximately equally (frequency = 1/3 of category total every other outage) over the ten years.
. Scope expansion will be determined on a case-by-case basis as a function of size, system, etc.
Previous Insoection Scheduls (Second Ten-Year Interval) for Category C:
. Examine all welds within the next two refueling cycles, then all every ten years (at least 50% in ,
1 six years).
. Scope expansion consists of an additional sample of welds, approximately equal in number and j similar in distribution (according to pipe size, system, and location) to the original sam,-!e, unless ; ; there is a technical reason to select a different sample.
i
- Catenary C' (GPC/SNC desinnation) i There are 12 welds, previously Category C, that have stresses exceeding 1.0 Sm. Eight of these welds are "# 1" welds (header to riser pipe welds) that historically have not been an industry problem. The other four welds consist of one riser-to-safe-end weld (#4) and three safe-end-to-nozzle welds. These four welds (IB31-lRC-12AR-H-5, -J-4, -J-5, and IB31-1RC-12BR-D-5) will be classified as Category C'.
Recommended Inspections (Third Ten-Year Interval) for Category C':
- . Examine each weld every other outage.
. Scope expansion will involve Category C welds and should be determined on a case-by-case l I
basis as a function of size, system, etc. Previous Inspection Schedule (Second Ten-Year Interval) for Category C'-
. None. This is a new GPC/SNC designation for the Third Ten-Year Interval.
i 4 i O 0313. DOC
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Hatch Unit 1 NUREG-0313 Summary Catencry D O These are welds made with materials not resistant to IGSCC and that have not been given an SI treatment, but have been inspected by qualified examiners using qualified procedures and been found to be free of cracks. Category D welds will be inspected at least once every two refueling cycles. Approximately half of the Category D welds in the plant will be inspected each refueling outage. All circumferential welds previously classified as Category D received MSIP treatment during the l 1993 outage and are now classified as Category C. One additional weld previously classified D by GPC/SNC, is a dissimilar pipe weld that has an overlay. It will be reclassified as E', The ten RINTSA (Recirculation Inlet Nozzle Thermal Sleeve Attachment) welds will be reclassified as Category R (see details elsewhere in this document). The dissimilar metal weld with the overlay (1G31-1RWCUM-6-D-1) is the joint formed by the intersection of RWCU and RHR systems. The overlay was applied at the same time the RWCU pipe was replaced during the 1988 outage. The overlay was added to provide additional mitigation of IGSCC in this dissimilar joint. There were no UT indications reported in the baseline examination or the subsequent examination in 1991. The weld overlay of the dissimilar metal weld was examined during the 1994 outage, was free ofindications penetrating the effective overlay, and will be reclassified as Category E', 1 With these reclassifications, there are no longer any Category D welds. ! Recommended Insoections (Third Ten-Year Interval) for Category D:
. Examine all Category D welds during the ten year interval with the examinations being spread !
approximately equally (frequency = 1/3 of category total every other outage) over the ten years. I
. Scope expansion criteria will be as described in GL 88-01, Supplement I for Category D welds.
Previous Inspection Schedule (Second Ten-Year Interval) for Category D:
. Examine all welds every two refueling cycles. . Scope expansion criteria as described in GL 88-01, Supplement I for Category D welds.
O 0313. DOC . Rev.O I Page 5 of12 l i
Hatch Unit 1 NUREG-0313 Summary Catenory R (GPC/SNC deslanation) O The ten RINTSA welds were originally in the Category D classification at GPC's option, but are outside the scope of NUREG-0313. They were included due to the crevice that occurs where the thermal sleeve is attached to the nozzle. The current examination of this area will not detect flaws in the attachment weld. Instead, the exam is such that it will find flaws that might propagate from the attachment weld into the low alloy steel nozzle. The examinations performed to date have revealed no changes from the baseline examinations. Calculations inve been performed estimating crack growth into the low alloy steel nozzle from a crack initiating in the crevice area. Based on those calculations, approximately 1/3 of the RINTSA welds will be examined every other outage. Should indications be detected, the scope expansion of GL 88-01, Supplement 1, for Category D welds will i be used for RINTSA welds. The ten RINTSA welds will be reclassified as Category R. Recommended Inspections (Third Ten-Year Intervan for Category R:
. Examine all Category R welds during the ten-year interval with the examiiations being spread approximately equally (frequency = 1/3 of category total every other outage) over the ten years.
. Scope expansion criteria will be as described in GL 88-01, Supplement 1 for Category D welds.
i Previous Inspection Schedule (Second Ten-Year Intervan for Category R:
- . None. This is a new GPC/SNC designation for the Third Ten-Year Interval.
i i O 0313. DOC Rev.O Page 6 of12
Hatch Unit 1 NUREG-0313 Summary Catenory E O These are welds with known flaws that have been reinforced by an acceptable weld overlay or have been mitigated by an SI treatment with subsequent qualified examination to verify the extent of cracking. GL 88-01 specifies that Category E welds should be in9ected at least once every two refueling cycles after repair. Approximately half of thenuraki be inspected during the first refueling outage after repair. The inspection method should provide positive assurance that the cracks have not progressed into the overlay. It is also desirable that the inspection procedure be capable of detecting cracks that originally were deeper than 75% of the original wall thickness, or that have grown to be deeper than 75% of the original wall thickness. An UT procedure qualified for overlay examinations must be used by examiners qualified to examine weld overlays. All Hatch welds classified as Category E or E' (refer to details of Category E' elsewhere in this document) have an overlay. There are 52 Category E weld overlays (not counting the two 6" RWCU welds overlayed, but not due to any indication) at Plant Hatch, Unit 1. Of these overlays,48 are made with 308L and four j are made with inconel weld metal. All overlays applied in 1982 and 1984 were resurfaced or built-up i during the 1986 outage. All overlays are standard overlay design, intended for indefinite service.
. One overlay on the RHR system (IEl1-lRHR-20B-D-5) was added to ensure an adjacent overlay could be properly inspected, and has been reclassified as Category E'. The two 6" RWCU welds,
- IG31-lRWCUM-6-D-1 and 1G31-lRWCUM-6-D-9, have also been reclassified as Category E' for j ease of tracking overlayed welds.
I j An overlay inspection history summary follows: ] l
. Of the 23 overlays applied and inspected in 1982 and 1984,21 were inspected in 1986. Nine new i overlays were added and inspected in 1986.
l . Of the 32 overlays in place in 1986,23 were inspected in 1987. This included seven of the nine } overlays applied in 1986 and 16 old overlays being examined for at least the second consecutive l outage. No new overlays were applied during 1987.
. All 32 existing overlays were inspected in 1988 as were two new overlays for a total of 34 overlay examinations.
. All 34 existing overlays plus 12 new overlays were inspected in 1990 for a total of 46 overlay j examinations.
. All 46 existing overlays plus six new overlays were inspected in 1991 for a total of 52 overlay examinations.
. Of the 52 existing overlays in place in 1993,26 were inspected. This included three of the six overlays applied in 1991. No new overlays were applied during the 1993 outage.
0313. DOC Rev.0 , Page 7 of12
1 Hatch Unit 1 NUREG-0313 Summarv
! Catenory E (continued)
- O . Of the 52 existing overlays in place in 1994 (including IEl1-lRHR-20B-D-5, now classified as E') , all 52 were inspected. Not included in this count are reclassified E' welds 1G31-lRWCUM-l 6-D-1 examined in 1994 and IG31-lRWCUM-6-D-9, last examined in 1991. No new overlays were applied during the 1994 outage.
4 , It is noteworthy that in all the examinations performed to date on the welds overlays, there have been no problems encountered. Considering the length of time some overlays have been in place and the ] l stresses, some indication growth under the overlays could reasonably be expected. However, while there have been some minor changes in a few of the indications under the overlays, only one overlay (IB31-1RC-12AR-F-2) has an indication that now appears to be at the pipe-to-overlay interface; but,
! it has not penetrated the effective overlay. (NOTE: The effective overlay is that portion of the overlay for which full credit is taken. It does not include the dilution zone or initial weld layer unless that layer has been determined to meet appropriate acceptance criteria.)
l The Hatch inspection experience alone warrants a change in the inspection and scope expansion criteria for the weld overlays. When the inherent resistance to IGSCC of the overlay material is i considered, the issue is not whether the inspection frequency should be changed, but by how much
"" "' d 'h* i"'"*'" " *'a"*"'7 6* "8'd '"i' i' "** *"' "* ' ' '"* "* **d* ' -
O This material has been shown to be more resistant than 316NG pipe base metal that is considered I resistant material and is sample inspected using Category A criteria. l } , Based on the performance of the overlays and their resistant nature, the inspection criteria should be j revised. Coincident with this ten-year ISI interval, the inspection frequency for the Category E and E' overlay welds will be once per ten-year interval. The examinations will be scheduled such that approximately 1/3 of the overlays will be inspected every second outage.
- The scope of overlays to be examined in any one outage will be expanded for the following conditions
. An indication extends into the effective overlay material, or j . An indication found that appears to be growing in a manner that would indicate a flaw could reasonably be expected to propagate axially beyond the overlay. Based on guidance from Section 4.2 of NUREG-0313, Rev. 2, it can be argued that axial growth is unlikely. The i
argument is presented there that axial flaws will grow through-wall in marginally resistant material, but crack length will not extend beyond 1.5 times the pipe thickness (1.5t). In addition to the NUREG information it can be shown that although a new heat affected zone is created by 0313. DOC Rev.O Page 8 of12 l l _________m _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . . _ _ - . _ , - ._ -I
i Hatch Unit 1 NUREG-0313 Summarv Catenory E (continued) O application of the overlay, the stresses are low enough and the distance is great enough that crack propagation in the axial direction is not an immediate issue. i For either of the cases described above, a reexamination of that overlay will be conducted for three ' consecutive periods. Reccininergied Inspections (Third Ten-Year Interval) for Categorv E:
. See Category E' description.
Previous Inspection Schedule (Second Ten-Year Interval) for Categorv E:
. See Category E' description.
Catenory E' (GPC/SNC desinnation) This is an arbitrary designation used by GPC. The E portion of the designation signifies that it is a weld with a standard Category E overlay. The " prime" indicates it is not a true Category E in that the weld was not flawed when the overlay was applied. The welds are: 1G31-lRWCUM-6-D-1; i 1G31-lRWCUM-6-D-9; and lEl1-lRHR-20B-D-5. The inspection and scope expansion for Category E' will be the same as the new criteria used for Category E. Recommended Insoections (Third Ten-Year Interval) for Categor and E' (GPC/SNC desinnation):
. Examine all Category E and E' welds during the ten-year interval with the examinations being spread approximately equally (frequency = 1/3 of total population for both categories every other outage) over the ten years. Weld IB31-lRC-12AR-F-2 will be examined during each of the first two outages in which inspections are conducted to verify significant indication growth has not occurred.
. There will be no scope expansion unless an indication extends into the effective overlay or the indication is such that axial propagation out from underneath the overlay is anticipated. If these conditions occur, scope expansion will be based on size, system, age of the overlay, etc. with the sample size dictated by the situation based on the particulars of the flaw.
Previous Inspection Schedule (Second Ten-Year Interval) for Category E:
. Examine 50% of the welds at the next refueling cycle (either 1987 or 1988), then all every two I refueling cycles.
O 0313. DOC Rev.O Page 9 of12
' Hatch Unit 1 NUREG-0313 Summary Previous Inspection Schedule (Second Ten-Year Interval) for Catenorv E (continued);
O - scoe xr a ioa wiiib r 9 ir d for isai'ic at cr ck srowth. or dditiea icr ck rouad duri=8 the inspection of one or more Category E welds. All other Category E welds should be examined. See GL 88-01 for definition of significant crack growth. Previous Inspection Schedule (Second Ten Year Interval) for Categorv E'-
. None. This is a new designation for the Third Ten-Year Interval.
Catenary P (GPC/SNC desienation) This category was arbitrarily defined by GPC to identify those longitudinal seam welds which have been covered by weld overlays. In this condition the long nams are not inspectable and in reality have no need to be inspected. Classification as Category P allows historical information to be maintained without impacting the inspection tables. No inspections will be performed. This is now supported by Code Case N-524 also. Verification of weld integrity is accomplished by overlay examinations. Recommended Inspections (Third Ten-Year Interval) for Category P (GPC/SNC designation):
. No examinations required. Covered by Category E and E' inspections.
O Previous Inspection Schedule (Second Ten-Year Interval) for Category P:
. None. This is a new GPC/SNC designation for the Third Ten-Year Interval.
J i 4 W 4 0313. DOC Rev.O ! Page 10 of12
Hatch Unit 1 NUREG-0313 Summarv i Catenory S (GPC/SNC desinnation) Q The Category S classification was arbitrarily defined by GPC to designate those non-safety RWCU welds that are augmented by GL 88-01, Approximately 30% of these welds have been examined I four times as of 1994 with no reportable indications. GPC has now decided to select approximately 10% of the population for repetitive examination each outage. This provides a better assessment of change occurring within the system while reducing the amount of weld preparatien time and l therefore personnel radiation dose. l The current inspection program will continue until NRC agrees with the GPC position that the j RWCU isolation valves (F001 and F004) meet the criteria of GL 89-10. At that time, the inspection i of these welds may be discontinued at the discretion of GPC, based on guidance in Supplement I to
, GL 88-01.
There are no generic NRC guidelines in place specifying scope expansion in the event reportable i indications are identified. The current agreement between NRC and GPC is that GPC will contact i NRC in the event of reportable indications and a scope expansion will be developed. However, this is the agreement reached several years prior to the GPC initiated sampling plan being endorsed via Supplement I to GL 88-01. Therefore, for the Third Ten-Year Interval, criteria similar to ASME l Section XI will be used for determining additional examinations. This will require that an additional i sample equal in size to the initial sample inspected be examined. If reportable indications are found in the second sample, GPC will then contact NRC to develop a mutually acceptable course of action. i Recommended Inspections (Third Ten-Year Interval) for Category S (GPC/SNC designation):
. Examine 10% of the Category S welds per outage. This sample will come from the welds already examined to continue assessing change from one examination to the next.
. A scope expansion sample will consist of an additional sample of equal size to that used for the 2
outage. If additional indications are detected, the NRC will be contacted and a mutually l agreeable course of action will be developed. Previous Insocction Schedule (Second Ten-Year Interval) for Category S (GPC/SNC designati9nh e None. This is a new GPC/SNC designation for the Third Ten-Year Interval. . 0313. DOC Rev.O Page 11 of12
Hatch Unit 1 NUREG-0313 Summary Catenory L (GPC/SNC desinnation) O This category was arbitrarily defined by GPC to identify welded attachments (lugs). There are no special requirements. ASME Section XI requirements will be used. Reggmmended Inspections (Third Ten-Year Interval) for Catenorv L (GPC/SNC desinnationk
. ASME Section XI requirements will be used.
Previous Iracection Schedule (Second Ten-Year Interval) for Category L (GPC/SNC designationt
. ASME Section XI requirements used.
O O 0313. DOC Rev.O Page 12 of12
Hatch Unit 2 NUREG-0313 Summary This is a supplement to describe Unit 2. Refer to the discussion provided in the Hatch Unit O- 1 NUREG-0313 Summary for specific details common to both Urlt 1 and 2. General A portion of the original stainless steel piping in Hatch 2 was made of conforming (IGSCC resistant) materials. Actions taken by Georgia Power Company to mitigate IGSCC in non-conforming materials consist of the Recirculation System (2B31) pipe replacement (except for the safe-ends) with construction designed for a minimum number of welds, IHSI (Induction Heat Stress Improvement), and the implementation of an inservice inspection program. A Hydrogen Water Treatment system was also put in place. Catevorv A A total of 222 (including 84 longitudinal seams) welds are in this category. Recommended Inspections ('ihird Ten-Year Interval) for Category A:
. Circumferential welds - Examine 25% of the Category A welds over the ten-year interval with the examinations being spread equally over the ten years. This is consistent with ASME Section XI and GL 88-01.
. Longitudinal Seam Welds - Examine these welds in accordance with Code Case N-524. This effectively will eliminate the inspection of the long seams. The code case l requires the inspection of the portion of the long seam that is contained within the I O boundaries of the intersecting circumferential weld. This will eliminate the need to examine 12 inches oflong seam either side of the circumferential welds.
. ASME Section XI scope expansion criteria will be utilized.
- Previous Inspection Schedule (Second Ten-Year Interval) for Category A
. Examine 25% of the welds every ten years (at least 12% in six years per NUREG-
- 0313).
j . Scope expansion consists of an additional sample of welds, approximately equal in
- number and similar in distribution (according to pipe size, system, and location) to the i original sample, unless there is a technical reason to select a different sample.
t ! Catenorv B i None currentlyin service. I ! O 0313#2. DOC Rev.O j .Page1 of3
Fatch Unit 2 NUREG-0313 Summary Catenory C O' A total of 50 welds are in this category. Ten Recirculation System inlet safe-ends and two outlet safe-ends were treated with the 4 IHSI process in 1986. Post-IHSI baseline examintions revealed no indications. I The safe-ends for the four Feodwater nozzles (total of 11 welds); the two Jet Pump instrumentation assemblies; the two Core Spray nozzle safe-ends; and the Control Rod i Drive nozzle cap had MSIP treatment in 1994. Post-MSIP baseline examinations revealed no indications. These welds will need an examination within two refueling cycles, after the stress improvement. RacnmmanM Inanac+ ions (Third Ten-Year Interval) for Catacarv C:
. Examine all Category C welds during the ten-year interval with the examinations being spread approximately equally (frequency = 1/3 ofcategory total every other outage) over the ten years.
. Scope expansion will be determined or case-by-case basis as a function size, system, etc.
! Previous Innnection Schedule (Second Ten-Year Interval) for Catenorv C: l O . sxa,ni- aii weids within the next two rerua,g cycies, then sii eve,y ten years (at ; least 50% in six years).
. Scope expansion consiste cf an additional sample of welds, approximately equal in l
number and similar in distril,ation (according to pipe size, system, and location) to the original sample, unless there is a technical reason to select a different sample. l l i
/
f I 0313#2. DOC Rev. O Page 2 of 3
1 Hatch Unit 2 NUREG-0313 Summary l 4 x' Cateson D/Cateson R (GPC/SNC desinnation)
- A total of ten RINTSA (Recirculation Inlet Nozzle Thermal Sleeve Attachment) welds,
! ' previously in Category D at GPC's option, have been reclassified as Category R. These , l welds, strictly speaking, are outside the scope of 0313 (see Hatch Unit 1 NUREG-1313 j Summary) 1
- ~
i; Rue ==Aad Inaa-+ ions (Third Ten-Year Interval) for Catamary R: . . ' Examine all Category R welds during the ten-year interval with the examinations being l spread approximately equally (frequency = 1/3 of category total every other outage)
- - over the ten years.
i . Scope expansion criteria will be as described in GL 88-01, Supplement I for Category D welds. l i Previous Inan-tion Schedule (Second Ten-Year Interval) for Catenow R: l
. None. This is a new GPC/SNC designation for the Third Ten-Year Interval.
l l Previous In.netion Schadnta (Second Ten-Year Interval) for Catenorv D:
. Examine all welds every two refueling cycles.
i . Scope expansion criteria as described in GL 88-01, Supplement 1 for Category D O weids. Catenory E - One weld is in this category to be examined every 10 years. One Feedwater nozzle safe-end weld (2B21-1FW-12AA-9) was overlayed in 1991 due to a linear indication. Subsequent exams in 1992 and 1994 showed no growth into the overlay. Recommendad Inanections (Third Ten-Year Interval) for Categen E:
. Examine all Category E welds during the ten-year interval.
Previous Innnetion Schadula (Second Ten-Year Interval) for Categorv E:
. Examine 50% of the welds at the next refueling cycle (either 1987 or 1988), then all every two refueling cycles.
. Scope expansion will be required for significant crack growth, or additional cracks found during the ia=aetion of one or more Category E welds. All other Category E welds should be examined. See GL 88-01 for definition of significant crack growth.
e .CaltERrvf,and Catemory G h None ce.ently in service. 0313#2. DOC . Rev.O Page 3 of 3}}