ML20150B742
| ML20150B742 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/30/1988 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-88-01, GL-88-1, SL-4489, NUDOCS 8807120160 | |
| Download: ML20150B742 (86) | |
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[3 [A Atlanta. Georga 30308 Telephone 404 526 0526 Po t ff x 4545 Atlanta, Georg:a 30302 Georgia Power Nuclear Operations Department the sourNm e/gtre system SL-4489 0969m X7GJ17-H210 June 30, 1988 /
U. S. Nuclear Regulatory Comission ATTN: Document Control Desk Hashington, D. C. 20555 i PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366
)i OPERATING LICENSES DPR-57, NPF-5 RESPONSE TO GENERIC LETTER 88-01, "NRC POSITION ON IGSCC IN BHR AUSTENITIC STAINLESS STEEL PIPING" l
Gentlemen:
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t By Generic Letter 88-01 dated January 25, 1988, the Nuclear Regulatory Comission (NRC) requested that each Boiling Hater Reactor (BWR) licensee submit information concerning how the licensee intends to i implement the NRC's position on intergranular stress corrosion cracking (IGSCC) in BHR austenitic stainless steel piping and components as delineated in the subject Generic Letter and NUREG-0313 Revision 2.
Specifically, each BHR licensee was requested to submit information concerning its current plans relating to replacement of piping susceptible to IGSCC, inspection, repair, and leakage detection to mitigate IGSCC and to provide assurance of continued long-term piping integrity and reliability. In addition, coments were solicited concerning the NRC positions, t Georgia Power Company (GPC) provides herein as Enclosure 1 its response for Plant Hatch Units 1 and 2 to the NRC positions delineated in Generic Letter 88-01 and NUREG-0313, Revision 2. Enclosures 2 and 3 provide the long-term examination schedule for IGSCC-susceptible piping an!1 components for Plant Hatch Units 1 and 2, respectively.
By letter dated September 4,1987, the NRC requested GPC submit its plan for inspection and/or modification to the recirculation and other austenitic stainless steel piping systems operating over 2000F for the upcoming Unit 1 outage at least three months prior to that outage. This submittal is also intended to fulfill that comitment. Since changes to outage plans can have adverse ef fects, GPC respectfully requests NRC staff acceptance of our plans, as delineated in Enclosure 2, prior to the next Unit I refueling outage, currently scheduled to begin on September foQ j 28, 1988. U h
8807120160 880630 W PDR ' ADOCK 05000321 '
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e Geon;ia Power b U. S. Nuclear Regulatory Commission June 30, 1988 Page Two Exception is taken by GPC to the scope of examination identified in the subject Generic Letter and NUREG. Those documents indicate that BHR piping made of austenitic stainless steel four inches or larger in nominal diameter and containing reactor coolant at a temperature above 2000 Fahrenheit during power operation is to be examined regardless of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Code classification of the piping. Arguments for excluding the Reactor Hater Cleantp (RHCU) system piping located downstream of double isolatie valves from the scope of examination are presented by GPC in Section B of Enclosure 1. In consideration of those arguments, GPC requests that relief be granted from including the RHCU system piping as described above within the scoM of our Generic Letter 88-01/NUREG-0313. Revision 2 examination program.
Enclosed in accordance with 10 CFR 170 is payment for the application fee of $150.00 for the NRC review of our request for relief.
In addition to the above exception, GPC wishes to advise the NRC i that, except where noted otherwise in Enclosure 1, it does not intend to submit Technical Specification changes to specifically delineate conformance to Generic Letter 88-01/NUREG-0313, Revision 2. Plant Hatch Unit 2 is the BHR Owners' Group lead plant for the Technical Specifict.tions Improvement Program (TSIP), which will probably result in the removal of the inservice inspection and inservice testing portion of the Technical Specifications. By this letter, GPC commits to performing certain actions as specified in Enclosure 1 toward complying with the aforementioned NRC documents.
Mr. H. G. Hairston, III, states that he is duly authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.
GEORGIA P0HER COMPANY By: d2 N W H. G. Hairston, III Senior Vice President Nuclear Operations l Sworn to and subscribed before me this 30th day of June 1988.
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GeorgiaPower d U. S. Nuclear Regulatory Commission June 30, 1988 Page Three
Enclosures:
(1) GPC Response to Generic Letter 88-01 for Plant Hatch, Units 1 and 2 (2) Hatch Unit 1 Long-Term Examination Schedule (3) Hatch Unit 2 Long-Term Examination Schedule (4) GPC check no. 057255 dated June 14, 1988 c: Georaia Power ComDany Mr. R. P. Mcdonald, Executive Vice President, Nuclear Operations Mr. J. T. Beckham, Jr., Vice President - Plant Hatch Mr. L. T. Gutwa, Manager Nuclear Safety and Licensing GO-NORMS U. S. Nuclear Reaulatory Commission. Hashington. D. C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch U. S. Nuclear Reaulatory Commission. keaion II
, Dr. J. N. Grace, Regional Ad '.ntstratc-Mr. J. E. Henning, Senior Resident Inst ettor - Hatch 0969m nxms
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i ENCLOSURE-1 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 GEORGIA POWER COMPANY .ESPONSE TO G.L. 88-01 I
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ENCLOSURE 1 (Continued)
GEORGIA POWER CO:PANY RESPONSE TO G.L. 88-01 TABLE OF CONTENTS A. INTRODUCTION B. EXCEPTION TO GENERIC LETTER SCOPE STATEMENT C. MITIGATING ACTION TAKEN TO DATE: HATCH UNIT 1 D. MITIGATING ACTION TAKEN TO DATE: HATCH UNIT 2 E. GEORGIA POWER COMPANY RESPONSE TO STAFF POSITIONS
- 1. Material s
- 2. Processes
- 3. Water chemistry
- 5. Partial replacement
- 6. Stress improvement of cracked weldments
- 7. Clamping devices
- 8. Crack evaluation and repair criteria
- 9. Inspection methods and personnel
- 10. Inspection schedules
- 11. Sample expansion
- 12. Leak detection
- 13. Reporting requirements F. TECHNICAL SPECIFICATION CHANGES
- 1. Inservice Inspection
- 2. Leak detection G. GEORGIA POWER COMPANY FUTURE PLANS 06260 SL-4489 El-2 June 30, 1988 L
ENCLOSURE 1 (Continued)
GEORGIA POWER COMPANY RESPONSE TO G.L. 88-01 A. INTRODUCTION NUREG-0313, Revision 2 entitled, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping" and the Implementing Generic Letter 88-01 entitled, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," issued on January 25, 1988, documents the current position of the NRC regarding Intergranular Stress Corrosion Cracking (IGSCC) in Boiling Water Reactor (BWR) austenitic stainless steel.
As discussed herein, implementation of NUREG-0313, Revision 2 will begin during the upcoming Fall 1988 Hatch Unit 1 refueling outage and continue in subsequent outages for both Hatch uni ts. When the draft version of NUREG-0313, Revision 2 was published in 1986, Georgia Power Company (GPC) decided to use the draf t, as commented upon by the EPRI/BWR Owner's Group and GPC, for technical guidance. As a result, that draft version of the NUREG was implemented during the Hatch Unit 1 1987 refueling outage and also during the recently completed Hatch Unit 21988 refueling outage. The NRC Staff Position on Inspection Methods (as clarified in this submi ttal) was incorporated into the ultrasonic examination (UT) techniques utilized during both of these outages. It is GPC's position that inspections performed during those outages constitute implementation of the requirements of NUREG-0313, Revision 2 relative to inspection extent and schedule.
B. EXCEPTION TO GENERIC LETTER SCOPE STATEMENT Georgia Power Company takes exception to the scope as identified in the NRC Generic Letter 88-01 statement: "This Generic Letter applies to all BWR piping made of austenitic stainless steel that is four inches or larger in nomt " diameter and contains reactor coolant at a temperature above 2000F during power operation regardless of Code classification."
This scope definition would require inclusion of approximately 130 Reactor Water Cleanup (RWCU) system welds which are located downstream of the double containment isolation valves. GPC considers this scope expansion unwarranted for the following reasons:
- 1. The events listed below will cause the RWCU system to automatically isolate from the reactor:
- a. Reactor water level 2 low
- b. Standby Liquid Control System actuation
- c. High temperature in the RWCU area
- d. Hign differential temperature between the RWCU supply and exhaust ventilation air 0626D SL-4489 El-3 June 30, 1988
ENCLOSURE 1 (continued)
GEORGI A POWER' COMPANY RESPONSE TO G.L. 88-01
- c. High temperature fluid leaving the non-regenerative heat exchanger
- f. High differential flow between the RWCU inlet and outlet Any of the above signals will initiate the closure of both RWCU containment isolation valves, except the Standby Liquid Control System actuation signal and high tenperature following the non-regeneration heat exchanger signal, which initiate the closure of the outboard isolation valve only. ,
- 2. Personnel exposure for inspection of these wel ds, which are in relatively high dose areas, would be excessive and not in keeping with As Low As Reasonably Achievable (ALARA) considerations. The estimated dosage received per weld would range from 0.4 to 6 REM, depending on location.
In consideration of these arguments, GPC hereby requests that relief be granted from including RWCU system piping outside of the containment outboard isolation valve from within the scope of our Generic Letter 88-01 Program.
C. MITIGATING ACTIONS TAKEN TO DATE: HATCH UNIT 1 Hatch Unit 1 has not replaced its austenitic stainless steel primary coolant piping. Instead, GPC has opted to address the IGSCC concern by utilizing a combination of the Induction Heating Stress Improvement (IHSI) to limit additional cracked weldnents and weld overlays to repair cracked weldments. GPC has categorized the welds determined to be within the scope of the NUREG as follows:
CAT A -
162 CAT B -
0 CAT C -
95 CAT D -
21 -
CAT E -
36 CAT F -
12 TOTAL 326 A detailed list of the Unit I welds, including our current examination schedulo, is provided as Enclosure 2.
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ENCLOSURE 1 (continued)
GEORGIA POWER COMPANY RESPONSE TO G.L.88-01 Weld overlay repairs were first applied to Hatch Unit 1 during the Winter 1982 refueling outage. Addi tional weld overlay repairs were applied during the 1984,1985, and 1987 refueling outages. Weld overlay repairs applied through the 1985 outage have been installed per standard
., overlay criteria and thereby, are IGSCC Category E welds per NUREG-0313, Revision 2. These overlay repairs do not require that credit be taken for the load carrying capability of the underlying base or weld metal. ~The weld overlay repairs applied during the 1987 refueling outage were applied to three RWCU welds and were installed as limited service overlays. No volumetric inspection was performed on these welds following weld overlay application. The overlay repairs applied to RWCU in 1987 will be upgraded to standard overlays or the affected portion (s) of the RWCU piping containing those welds will be replaced during the 1988 refueling outage.
During the 1985 refueling outage, the IHSI process was applied to primary austenitic stainless steel piping welds at Hatch Unit 1.
Following the IHSI treatment, nine welds were identified as having possible flaws. The indication in weld 12BR-C-5 was evaluated and determinod-to be of non-IGSCC origin. The weld was classified as Category C. Of the remaining eight welds with indications, four welds, 208-0-4, 28A-4, 288-8, and 288-10, contain axial indications and are therefore Category F welds. Welds 12AR-G-4 and 12BR-E-4 have circumferential indications exceeding 10% of the circu iference and are also Category F.
Lastly, welds 12BR-A-4 and 28A-2 are marginal Category E welds and will be treated conservatively as Category F.
In sammary, 36 welds on Unit 1 have Category E overlays. One weld was overlayed to enhance the examination of the weld, not as a repair.
Eight welds have IGSCC indications which have been mitigated by the IHSI technique. The majority of the remaining welds within the non-isolable portion of the Reactor Cooiant pressure boundary within the examination scope of section 5.1 of the NUREG have also had the IHSI process applied.
The two Jet Pump Instrumentation penetrations and two Core Spray nozzle safe-end assemblies have not had the IHSI process applied. A list of Unit 1 welds that GPC has detemined to be in the scope of the NUREG, along with the planned long-tem examination schedule, is provided in Enclosure 2.
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. , i ENCLOSURE 1 (continued)
GEORGIA POWER COMPANY RESPONSE TO G.L. 88-01 i
l D. Mitigating Actions Taken To Date: Hatch Unit 2 l l
During the 1984 refueling outage, GPC replaced type 304 stainless steel recirculation system piping,. the stainless steel portion of I residual heat removal (RHR) system piping, and the RWCU system piping out to the containment outboard isolation valve (excluding the piping penetration) with GE Type 316 Nuclear Grade (NG) material. Replacement did not include the recirculation system stainless steel safe-ends as they are considered to be confonning material. Welds within the scope of the NUREG have been categorized by GPC as follows:
CAT A -
222 CAT B -
0 CAT C -
33 CAT D -
31 CAT E -
0 CAT F -
0 TOTAL 286 A detailed list of the Unit 2 welds, including our current examination schedule, is provided as Enclosure 3.
The existing GE Type 316 NG Piping is an austenitic stainless steel with a high resistance to IGSCC that occurs in the BWR environment.
This material's resistance to IGSCC is due to the low carbon conterst and the addition of molybdenum. This material has a carbon content not exceeding .02 weight percent. In addition, the nitrogen content of this alloy is controlled to counterbalance the loss in strength due to the relatively low carbon content. Increased pitting and sensitization resistance is provided by the addition of melybdenum.
An intensive pipe testing program in nominal and off-chemistry environmental BWR conditions demonstrated that Type 316 NG stainless steel shows a significant improvement in IGSCC resistance as compared to type 304 or 316 stainless steel. The results of small specimen tests in BWR high purity water provided evidence for complete support of the use of Type 316 NG stainless steel in the BWR environment.
The replacement Type 316 NG piping installed at Hatch Unit 2 was girth welded using Type 308 or 309 stainless steel weld filler materials containing controlled carbon and ferrite levels. A survey of the material and fabrication records for the weld metal employed shows that the applicable ferrite and carbon levels are within the guidelines specified in the NUREG.
06260 SL-4489 El-6 June 30, 1988 l
ENCLOSURE 1 (continued)
GEORGIA POWER COMPANY RESPONSE TO G.L. 88-01 As an additional mitigation, the new welds were subjected to the IHSI process and subsequently ultrasonically examined. During the 1986 refueling outage, the 10 Recirculation System inlet safe-ends and the two Recirculation System outlet safe-ends were treated with the IHSI process and then ultrasonically examined, with satisfactory results.
In summary, non-isolable reactor coolant pressure boundary weldments in the exainination scope defined by Section 5.1 of the NUREG have been either replaced with Nuclear Grade Material (Category A) or, when made with non-resistant materials, stress improved using the IHSI process (Category C). The exceptions are for the two Jet Pump instrumentation penetrations, two Core Spray nozzle safe-ends, and four feedwater safe-end assemblies. These non-resistant weldments have been ultrasonically examined with no IGSCC detected; therefore, they have been classified as Category D.
E. GEORGIA POWER COMPANY RESPONSE TO STAFF POSITIONS
- 1. Staff Position on Materials Georgia Power Company intends to follow the staff position -on materials whenever replacement of IGSCC susceptible stainless steel piping is deemd necessary with the following provisions:
- a. Standard grade stainless steels will not be excluded from temporary use on an emergency basis (e.g., if "L" grade or "NG" material is not readily available),
- b. Standard grade stainless steel may be used to make repairs when installed using stress improvement processes such as Heat Sink Welding, IHSI, and others (e.g., mechanical stress improvement). Further, standard grades may be used if it meets the material specifications found in Section 2.1 of the NUREG.
- c. Specific sensitization tests for replacement materials will generally be performed. However, when generic sensitization information is available for materials in the NUREG table, that infonnation may be used in lieu of a specific test.
06260 SL-4489 El-7 June 30,1988 l
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ENCLOSURE 1 (continued)
G_EORGI A POWER COMPANY RESPONSE TO G.L. 88 401
- d. -The. only "potential" crevice area identified at Plant-Hatch that ,
possibly falls within the NUREG guidelines is the Recirculation System inlet nozzle themal sleeve attachment- (RINTSA) welds.-
These welds have been examined at Plant Hatch since the issuance of NUREG-0313 Revision 1 ;with no evidence of cracking. The examinetion of these welds will continue and will be considered _
u Category D.
- 2. Staff Position-on Processes Georgia . Power Company intends to follow the staff position on >
processes.
- 3. Staff Position on Water Chemisty, Georgia Fower Compator is aggressively addressing the issue of improved water chemistry. Modifications and procedures are either planned or in place to maintain stringent controls on water chemistry. One such modification is that of hydrogen injection.
During January-February of 1987, a Hydrogen Water Chemistry (HWC) mini-test was performed on Hatch Unit 1, establishing
, parameters such as:
- Oxygen level
. - Electro-Chemical Potential (ECP) 1
- Steam line, plant, and boundary radiation level increases :
- Shielding requirements ,
- Reconnended hydrogen injection rates
- Optimum injection locativas
- Offgas system performance A tempcrary HWC Injection System was installed on Unit 1 in September of 1987, and remains in operation. Design is in progress for a permanent Unit 1 HWC system with operatico scheduled following ,
the Fall 1988 outage. Currently, the injection rate on Unit 1 is lower thari that r.ecessary to achieve th.: target ECP for full pipe ;
- protection. This is because of the operational prob 1 cms caused by the radiation level increases at the higher injection rates. In ,
order to quantify the partial pipe protection afforded by the current l
- injection rate, a Crack Arrest- Verification (CAV) system will be
! provided for use on Unit 1 with operation also scheduled following ;
Evaluation of the data during hydrogen the Fall 1988 outage.
injection on Unit 1 will be used, in part, to define HWC system operation on Unit 1, as well as a schedule for HWC implementation on Unit 2.
No reductions in piping inspection frequency is taken on Hatch Units 1 & 2 based on the use of HWC at the present time. :
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ENCLOSURE 1 (continued)
GEORGIA POWER COMPANY RESPONSE TO G.L. 88-01
'4. Staff ?osition on Weld Overlays Georgia ' Power Company intends to follow the provisions of the staff position. Except for three limited service overlays (Category F) in the RWCU system, overlays currently installed on Hatch Unit i satisfy the requirements of the staff position and are considered to be Category E weldments. GPC intends that these Category E overlays be used for long-tenn service and will examine them per Section 5.3.2.5 of the NUREG to ensure that the overlays will continue to prov.ide the necessary safety margin.
The three limited service overlays will either be upgraded or affected piping sections replaced to meet the staff position during the Fall 1988 refueling outage. Any additional overlays required at Plant Hatch that are to be used for extended service will be designed to meet the requirements of Section 3.2.1 of the NUREG. In special cases, limited service overlays may be applied. If they are used at Plant Hatch, they will either be inspected as Category F weldments per Section 5.3.2.6, upgraded to meet the staff position during the next refueling outage, or affected piping will be replaced.
- 5. Staff Position on Partial Replacement Georgia Power Company has used limited partial replacement in the past and considers it a viable option for the future.
- 6. Staff Position on Stress Improvement (SI) of Cracked Weldments Stress improvement has been used as a mitigation process for eight weldments to date on Hatch Unit 1 and is considered a viable option in the future. Six of these welds have unallowable crack sizes per Section 4.5 of the subject NUREG and are characterized as Category F. The remaining two welds have indications that are marginally close to the maximum allowable crack size, and GPC has elected to treat these conservatively as Category F weldments. After the IHSI process was applied to these cracked weldments, a qualified UT examination was performed. (See GPC response to the "Staff Position on Inspection Methods and Personnel" in this enclostre).
- 7. Staff Position on Clamping Devices Georgia Power Company has not used clamping devices to date for temporary reinforcement of cracked weldments; however, it remains a viable option in the future.
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0626D SL-4489 El-9 June 30, 1988
k ENCLOSURE 1 (continued)
GEORGIA POWER COMPANY RESPONSE TO G.L. 88-01
- 8. Staff Position on Crack Evaluation and Repair Criteria ,
The philosophy for crack evaluation and repair criteria at Plant Hatch has followed NRC guidance in effect at the time of each refueling outage for each plant. With the 1987 outage tne philosophy incorporated both Generic Letter 84-11 entitled "Inspection of Stainless Steel Piping", and the draft NUREG-0313, Revision 2. The issuance of NUREG-0313, Revision 2 and the implemer. ting Generic Letter 88-01 in January, 1988, has prompted GPC to evaluate the status of existing weld overlay repairs and stress improved cracked weldments. Structural Integrity Associates, Inc. was retained to perform a review to ensure compliance with the position. To date, weldments with IGSCC indications have been repaired or mitigated in accordance with the staff position or have been classified as Category F.
- 9. Staff Position on Inspection Methods and Personnel Ultrasonic examinations perfonned under the scope of Generic Letter 88-01 will be accomplished to the extent practical in accordance with the code in effect at Plant Hatch for inservice inspection activities, currently the 1980 Edition of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Yessel Code with Addenda through Winter 1981, except where specific relief has been granted by the NRC.
In addition, examination personnel to bc 1 sed at Plant Hatch are required to achieve a level of competence commensurate with their function. Level II and Level III non-destructive examination (NDE) personnel must successfully demonstrate their ability, at the Electric Power Research Institute (EPRI) NDE Center, to detect IGSCC in accordance with the upgraded September 1985 NDE Coordination Plan (or such future plans as agreed to by the NRC and GPC). Personnel who will be required to perform flaw sizing for use in Section 4.0 evaluation, "Crack Characterizat7on and Repair Cri teria ," must qualify in planar flaw sizing at the EPRI NDE Center.
0626D SL-4489 El-10 June 30, 1988
EHCLOSURE 1 (continued)
GEORGI A POWER COMPANY RESPONSE 'TO G.L. 88-01 Personnel perfoming examinations at Plant Hatch, or as a general rule at other BWR's, have qualified at the EPRI NDE Center using - various procedures or EPRI modules and with various instruments. The procedures to be used at Plant Hatch are derived from the basic techniques taught at the EPRI NDE Center. To ensure that examinations are effectively performed, Level II and III NDE personnel qualifications are verified prior to their perfoming IGSCC examinations. This qualification verification ensures that the techniques and instruments used during qualification are compatible with the procedures and instruments being used at Plant Hatch. This is accomplished using each examiner's Performance Documentation Summary Fom obtained from the EPRI NDE Center.
- 10. Staff Position on Inspection Schedules l
Georgia Power Company intends to follow the staff position.
Furthermore, the inspection schedule in draft version of NUREG-0313, Revision 2, was used during the Hatch Unit 1,1987 refueling outage and the Hatch Unit 2 1988 refueling outage. The inspections were performed by qualified personnel as delineated in the "Staff Position on Inspection Methods and Personnel" in this document; therefore, credit is taken for these examinations.
- 11. Staff Position on Sample Expansion Georgia Power Company intends to follow the staff position.
- 12. Georgia Power Company Response to Staff Positions on Leak Detection The current Unit 1 and Unit 2 requirements met the intent of the staff's position on leak detection. The Unit 1 requirement is as specified in Amendment No. 93 of the Technical Specifications (TS)
(implemented February 23, 1983). These requirements would allow operation with one leakage monitoring instrument inoperable to continue for up to 30 days, instead of the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> dictated in Generic Letter 88-01 for plants with category D, E, F, or G welds.
Flow measurements for either the equipment drain sump or floor drain sump can be accurately made using the flow integrator on each sung, or by manually monitoring the time between sump pump starts. Thus, if a flow integrator instrument is inoperable on one sump, leakage into that sump can still be accurately detemined using the manual method. GPC, therefore, intends to continue to operate Unit I under the requirements of the existing TS.
0626D SL-4489 El-11 June 30, 1988
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ENCLOSURE 1 (continued)
GEORGIA POWER COMPANY RESPONSE TO G.L. 88-01 Plant Hatch Unit 2 is currently under a Confimatory Order issued July 8,1983 which specifies the same requirements as Generic Letter 88-01 and GPC is planning to submit a TS change on leakage detection to reflect those requirements.
As a matter of clarification, GPC's interpretation of the requirements allows for averaging of the unidentified leakage limits of 5 gpm total or a 2 gpm increase over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
Averaging is necessary since the measured leakage may vary at each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> surveillance interval (e.g., floor or equipment drain sump flashing, etc. ). GPC intends to continue to conform to its current leak detection requirements.
- 13. Georgia Power Company Response to Staff Position of Reporting Requirements Georgia Power Company intends to follow the staff position on reporting. We would not explicitly inform the NRC of our future inspections unless substantive modifications to our IGSCC inspection / mitigation program were proposed. If any crack indications are identified that do not meet the criteria fo continued operation without evaluation given in Section XI of the ASME Code, GPC would report its findings and mitigation / repair plan prior to resumption of operation. Otherwise, the inspection results will be reported in our Owner's Data Report for Inservice Inspection (Form NIS-1).
F. TECHNICAL SPECIFICATION CHANGES
- 1. ISI Georgia Power Company's position is to not modify the Unit 1 and Unit 2 TS to specifically delineate conformance to Generic Letter 88-01. Plant Hatch is ' BWR industry lead plant in the Technical Specifications Improver Program, which will probably result in the removal of ISI/IST .tions of the TS. The ISI .e.ecti ons of alternative documents (e.g., the NIS-1 Owner's Data Report or ASME Section XI Program Document) will specify the confomance of GPC's augmented inspections to Generic Letter 88-01/NUREG-0313, Rev. 2 as applicable.
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ENCLOSURE 1 (continued)
GEORGI A POWER COMPANY ' RESPONSE TO G.L. 88-01
- 2. Leak ' Detection i
Plant Hatch Unit 2 will continue to operate in accordance with the requirements of the Confirmatory Orders (and Generic letter 88-01 ) until a TS amendment can be prepared by GPC and approved by the NRC. The proposed amendment will reflect the Confirmatory Order / Generic Letter 88-01 requirements and will be submitted to the connission as a separate package. No TS changes for Unit 1 relative to Reactor Coolant leakage are anticipated.
G. GEORGIA POWER COMPANY FUTURE PLANS Georgia Power Company has used a combination of piping replacement, weld overlay repairs, and IHSI since the IGSCC problem was identified at Plant Hatch. The mitigating actions taken meet the requirements of the NUREG as interpreted by GPC (and discussed herein) and it is therefore the intent of GPC to operate as-is for the long-term. . If any additional mitigating actions or repai rs are deemed necessary, they will be accomplished in accordance with this response.
0626D SL-4489 El-13 June 30,1988
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a ENCLOSURE 2 t
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i PLANT HATCH - UNITS 1, 2 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 GEORGIA POWER COMPANY RESPONSE TO G.L. 88-01 UNIT 1 LONG-TERM EXAM SCHEDULE t
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, . 1.z ENCLOSURE 2-NOTES Notesi (1) . Note A-1 wa> referred to in "Coments" column and pertains to size of examination area (2) This enclosure is extracted from the Hatch Unit 1 ISI
.Long-Tem Plan which is updated _ periodically to assure it remains current. This enclosure will not be resubmitted as a result of those revisions.
(3)~ The asterisk-(*) under "Exam Req is used for computer sorting purposes only, t
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INFORMATION SERVICES-BIRMINGHAM EDWIN 1. HATCH NUCLEAR PLANT - UNIT 1. MARED-C313, REV. 2 PAGE 1 ~*
(FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRO REMARKS .
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOO PERIOD PERIOD CALIBRATION BLOCK =
B5.10 B-F NUREG-0313D 1C11-1CRD-3-R-18A A-1/04 UT-H-400/7 87 X X 5.4-IN-X-0.750-97-H CAP TO NOZZLE PT-H-SOO/2 EXAMINE EVERY 2ND OUTAGE w
a
(NFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1. NURE2-C313. EEV. 2 FAGE 2 (FDR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION TIRST SECOND THIRD REMARKS -
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK -
NUREG-03130 N2A -
UT-H-415/02 X X X EXAMINE 1988 RO AND
- RINTSA WELD THEN EVERY 2ND OUTAGE RINTSA-125-H NUREG-0313D N28 -
UT-H-415/02 X X X EXAMINE 1988 RO AND
- RINTSA WELD THEN EVERY 2ND OUTAGE RINTSA-125-H NUREG-03130 k2C -
UT-H-415/02 X X X EXAMINE 1988 RO AND e RINTSA WELD THEN EVERY 2ND OUTAGE RINTSA-125-H NUREG-0313D N2D -
UT-H-415/02 X X X EXAMINE 1988 RO AND
- RINTSA WELD THEN EVERY 2ND OUTAGE RINTSA-125-H NUREG-03130 N2E -
UT-H-415/02 X X X EXAMINE 1988 RO AND e RINTSA WELD THEN EVERY 2ND OUTAGE m RINTSA-125-H Y
x-NUREG-0313D N2F -
UT-H-415/02 87 X X EXAMINE 1990 RO AND e RINTSA WELD THEN EVERY 2ND OUTAGE RINTSA-125-H NUREG-0313D N2G -
UT-H-415/02 87 X X EXAMINE 1990 RO AND
- RINTSA WELD THEN EVERY 2ND OUTAGE RINTSA-125-H NUREG-0313D N2H -
UT-H-415/02 87 X X EXAMINE 1990 RO AND e RINTSA WELD THEN EVERY 2ND OUTAGE RINTSA-125-H NUREG-03130 N2d -
UT-H-415/02 87 X X EXAMINE 1990 RO AND e RINTSA WELD THEN EVERY 2ND OUTAGE RINTSA-125-H NUREG-0313D N2K -
UT-H-415/02 87 X X EXAMINE 1990 RO AND e RINTSA WELD THEN EVERY 2ND OUTAGE RINTSA-125-H
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1 NURE2-C313, CEV. 2 PAGE 3 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECONO THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDEMTIf!C?.!!OM Mn /REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.11 8-J NUREG-0313C 1831-1RC-4A-1A A-148/OO UT-H-401/6 87 X 4-SS-80-0.338-60-H e BC TO CAP PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2NQ PERIOO 89.11 5-J NUREG-0313C 1831-1RC-4A-10A A-148/OO UT-H-401/6 87 X 4-SS-80-0.338-80-H
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIDO 89.11 8-J NUREG-0313C 1831-1RC-48-1A A-158/OO UT-H-401/6 X X 4-SS-80-0.338-80-H
- BC TO CAP PT-V-600/2 EXmMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMIhK 3RD PERIOD 89.11 8-J NUREG-0313C 1831-1RC-48-10A A-158/OO UT-H-401/6 X X 4-SS-80-0.338-80-H
- BC TO CAP PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 85.10 8-F NUREG-0313D 1E31-1RC-4JP-A-1 A-39/OO UT-H-409/2 87 X X 5.437-CS-X-0.625-120-H
- N8A N0ZZLE TO PT-H-600/2 5.437-SS-X-0.813-121-H S AFE-END EXAMINE EVERY 2 OUTAGES N
s LM 89.11 5-J NUREG-03*3D 1831-1RC-4JP-A-2 A-39/OO 87 X X UT-H-401/6 4-SS-80-0.337-80-H
- SAFE-END TO PT-H-600/2 EX4MINE EVEP.Y 2 OUTAGES PENETRATION SEAL 85.10 8-F NUREG-0313D 1831-1RC-4JP-8-1 A-39/OO UT-H-409/2 87 X X 5.437-CS-X-0.625-120-H
- N88 NOZZLE TO PT-H-600/2 5.437-SS-X-0.813-121-H SAFE-ENO EXAMINE EVERY 2 OUTAGES 89.11 5-J NUREG-0313D 1831-1RC-4JP-8-2 A-39/OO UT-H-401/6 87 X X 4-SS-80-0.337-80-H
- SAFE-END TO PT-H-600/2 EXAMINE EVERY 2 OUTAGES PENETRATION SEAL 89.11 5-J NUREG-0313C 1831-1RC-12AR-F-1 A-18/02 UT-H-400/7 87 X 17-H
- 8-C TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.12 8-J NUREG-0313A 1831-1RC-12AR-F-1LD A-18/02 UT-H-400/7 X SEE NOTE A-1.
L3NG SEAM WELD PT-H-600/2 17-H EXTENDING DOWN e
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH F!CLFe.R PLANT - UNIT 1, MJRE2-C313. REV. 2 PAGE G (FOR llCORMATION ONLY)
ASME ASME EXAM EXAMINATION JIGURE EXAMINATION FIRST SECOND THIRD REMARKS -
ITM NO. CAT. REQUIREMENT AREA ICENTIFICATION AG./REV PROCED./REV PERIOD FERIOD PERIOD CALIBRATION BLOCK ~
89.It B-J NUREG-0313E 1831-1RC-12AR-F-2 A-18/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INC54
- PIPE TO ELBOW PT-H-BOO /2 BASE MATERaAL ON EACH 84 OVERLAY /88 RESUpf SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1831-1RC-12AR-F-2LD-1 A-18/02 OVERLAYED-EXAMINE AS LONGITUDINAL WELD PART OF F-2 DOWNSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 1D31-1RC-12AR-F-2LD-O A-18/02 OVERLAYED-EXAMINE AS LONGITUDFNAL WELD 7.Uti OF F-2 DOWNSTREAM ON OUTSIDE OF ELBOW B9.12 B-J NUREG-0313A 1831-1RC-12AR-F-2LU A-18/02 OVERLAYED-EXAMINE AS LONGITUDINAL SEAM PART OF F-2 WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313E 1831-1RC-12AR-F-3 A-18/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
= ELBOW TO PIPE PT-H-BOO /2 GASE MATERIAL ON EACH 84 OVERLAY /88 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H O 89.12 B-J NGREG-0313A 1831-1RC-12AR-F-3LD A-18/02 OVERLAYED-EXAMINE AS LONGITUDINAL SEAM PART OF F-3 WELD EXTENDING DOWNSTREAM 89.12 B-J NUREG-0313A 1831-1RC-12AR-F-3LU-I A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF F-3 UPSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-12AR-F-3LU-O A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF F-3 UPSTREAM ON OUTSIDE OF ELBOW 89.11 8-J NUREG-0313E 1831-1RC-12AR-F-4 A-18/02 UT-H-408/1 87 X X PT OVERLAY AND I INCH
+ PIPE TO SA/E-END PT-H-SOO/2 BASE MATERIAL ON EACH 1988 OVERLAY SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.1.1 B-J NUREG-0313A 1831-1RC-12AR-F-4LU A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF F-4 WELD EXTENDING UPSTREAM
INFORMATION SERVICES-BIRMINGHAM EDWIN I . HATCH NUCLEAR PLANT - UNIT 1, PAIRE2-C'13, CEV. 2 PAGE O (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EKAMINATION FIRST SECOND THIRD REMARKS -
ITM NO. CAT. REOUIREMENT AREA IDENTIFICATION NO./REV PROCEO./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK
- SAFE-ENO TO NOZZLE PT-H-600/2 RE-EXAMINE 2ND PERIOD IHSI 1985/1986 RO 85-H, 108-H 89.11 B-J PAJREG-0313C 1831-1RC-12AR-G-1 A-18/02 UY-H-400/7 X X 17-H
- B-C TO PIPE PT-H-600/2 EXAMINE 1988 OUTAGE IHSI 1985/1986 RO AND 3RD PERIOD B9.12 B-J NUREG-0313A 1831-1RC-12AR-G-1LD A-18/02 UT-H-400/7 SEE NOTE A-1.
LONG*TUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING DOWNSTREAM 89.11 8-J NUREG-0313C 1831-1RC-12AR-G-2 A-18/02 UT-H-400/7 X X 17-H e PIPE TO ELBOW PT-H-600/2 EXAMINE 1988 0'JTAGE IHSI 1985/1986 RO AND 3RD PERIOD B9.12 B-J NUREG -0313A 1831-1RC-12AR-G-2LD-I A-18/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 17-H m DOWNSTREAM ON INSIDE y OF ELBOW 89.12 B-J PAJREG-0313A 1831-1RC-12AR-G-2LD-O A-18/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 17-H DOWNSTREAM ON OUTSIDE OF ELBOW B9.12 B-J PAJREG-0313A 1B31-1RC-12AR-G-2LU A-18/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING UPSTREAM 89.12 B-J PAJREG-0313 E 1831-1RC-12AR-G-3 A-18/02 UT-H-408/1 X X X PT OVERLAY AND 1 INCH
- ELBOW TO PIPE PT-H-600/2 BASE MATERIAL ON EACH 1988 OVERLAY SIDE. EXAMINE 1988 THEN EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1831-1RC-12AR-C-3LD A-18/02 OVERLAYED-EXAMINE AS LONGITUDINAL SEAM PART OF G-3 WELD EXTENDING DOWNSTREAM B9.12 B-J NUREG-0313A 1931-1RC-12AR-G-3LU-I A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF G-3 UPSTREAM ON INSIDE OF ELBOW
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH PAJCLEAR PLANT - UNIT 1 NUREJ-C313, REV. 2 PAGE O (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST S%DND THIRD REMARKS -
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD #ERIOD PIRIOD CALIBRATION SLOOC B9.12 8-J PAJREG-0313A 1831-1RC-12AR-G-3LU-O A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF G-3 UPSTREAM ON OUTSIDE OF ELBOW 89.11 B-J NUREG-0313F 1831-1RC-12AR-G-4 A-18/02 UT-H-400/7 87 X X EXAMINE 4 OUTAGES IN A
- PIPE TO SAFE-END PT-H-600/2 ROW STARTING IN 1987.
IHSI 1985/1988 RO IF UNCHANGED RECLASSIFY AS CATEGORY E. 17-H 89.12 8-J NUREG-0313A 1831-1RC-12AR-G-4LU A-18/02 UT-H-400/7 87 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTEPOING UPSTREAM B5.10 B-F NUREG-0313C 1831-1RC-12AR-G-5 A-18/02 UT-H-400/7 X X 12-SS-X-1.2OO-85-H
- SAFE-END TO N0ZZLE PT-H-600/2 10-CS-160-1.125-108-H IHSI 1985/1988 RO EXAMINE 1988 OUTAGE AND RE-EXAMINE 3RD PERIOD 89.11 B-J NUREG-0313C 1831-1RC-12AR-H-1 A-18/02 UT-H-400/7 X X 17-H
89.12 B-J NUREG-0313A 1831-1RC-12AR-H-1LD A-18/02 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING DOWNSTREAM B9.11 B-J NUREG-0313E 1831-1RC-12AR-H-2 A-18/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH e PIPE TO ELBOW PT-H-600/2 BASE MATERIAL ON EACH 84 OVLRLAY/86 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1831-1RC-12AR-H-2LD-1 A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD OOWNSTREAM ON INSIDE g PART OF H-2 OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-12AR-H-2LD-O A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF H-2 DOWNSTREAM ON OUTSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-12AR-H-2L*J A-18/02 OVERLAYED. EXAMXNE AS LONGITUDINAL SEAM PART OF H-2 WELD EXTENDING UPSTREAM
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1, paJRE3-C313, REV- 2 PAGE 7 (FOR INFORMATION ONLY)
ASNE ASME EXAM EXAMINATION FIGURE EXAMINATION FICST SECONO THIRD RIMARKS
- ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALI8 RATION ELOCK 89.11 8-J NUREG-0313E 1831-1RC-12AR-H-3 A-18/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
- ELBOW TO PIPE PT-H-600/2 8ASE MATERIAL ON EACH 84 OVERLAY /86 RESURF SIDF. EXAMINE IVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1831- GC-12AR-H-3LD A-18/02 OVERLAYED. EXAMINE AS LONGITUUINAL SEAM PART OF H-3 WELD EXTENOING DOWNSTREAM 89.12 8-J NUREG-0313A 1831-1RC-12AR-H-3LU-I A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF H-3 UPSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-12AR-H-3LU-O A-18/02 OVERLAYED. EXAPSINE AS LONCITUDINAL WELD PART OF H-3 UPSTREAM ON OUTSIDE OF ELBOW 89.11 8-J NUREG-0313E 1831-1RC-12AR-H-4 A-18/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH e PIPE TO SAFE-END PT-H-600/2 BASE MATERIAL ON EACH 1988 OVERL** SIDE. EXAMINE EVERY 2fe Q OUTAGE. 134-H d 89.12 8-J NUREG-0313A 1831-1RC-12AR-H-4LU A-18/02 OVERLAYED. EXAMINE AS LDNGITUOINAL SEAM PART OF H-4 WELD EXTENDING UPSTREAM 85.10 8-F NUREG-0313C 1831-1RC-12AR-H-5 A-18/02 UT-H-400/7 X X 12-SS-X-1.2OO-85-H e SAFE-ENO TO NOZZLE PT-H-600/2 10-CS-1GO-1.125-108-H IHSI 1985/1986 RO EAAMINE 1988 OUTAGE AND 3RD PERIOD 89.11 8-J NUREG-0313C 1831-1RC-12AR-J-1 A-18/02 UT-H-400/7 X X 17-H e 8-C TO PIPE PT-H-600/2 EXAMINE 1988 OUTAGE IHSI 1985/1986 RO AND 2ND PERIOD 89.12 8-J NUREG-0313A 1831-1RC-12AR-J-1LD A-18/02 UY-H-400/7 EEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING OOWNSTREAM 89.11 8-J P4JREG-0313C 1831-1RC-12AR-d-2 A-18/02 UT-H-400/7 87 X 17-H e PIPE TO EL80W PT-H-600/2 EXAMINED 1987 RO.
INSI 1985/1986 RO RE-EXAMINE 2ND PERIOD
INFORMATION SERVICES-B'RMINGHAM EDWIN 1. HATCH P1JCLEAR PLANT - UNIT 1. PMtE3-C313. REV. 2 PAGE 8 (FOR INF MtMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECONO THIRD REMARKS .
IIM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOO PERIOD PERIOD CALIBRATION BLOCK
- 89.12 B-J PMtEG-0313A 1P31-1RC-12AR-J-2LD-I A-18/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 17-H DOWNSTREAM ON INSIDE OF ELBOW s
89.12 8-J NUREG-0313A 1831-1RC-12AR-J-2LD-0 A-18/02 tit-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 17-H DOWNSTREAM ON OLITSIDE OF EL8OW 89.12 B-J NUREG-0313A 1831-1RC-12AR-J-2LU A-18/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING UPSTREAM 89.11 8-J PeJREG-0313E 1831-1RC-12AR-J-3 A-18/02 UT-H-408/1 X X X PT OVERLAY AND 1 INCH
- ELBOW TO PIPE PT-H-600/2 BASE MATERIAL ON EACH 84 OVFRLAY/86 RESURF SIDE. EXAMINE 1968 THEN EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1831-1RC-12AR-J-3LD A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF J-3 m WELD EXTENOING ro DOWN'TREAM i
8 89.12 8-J NUREG-0313A 1831-1RC-12AR-J-3LU-I LONGITUDINAL WELD A-18/02 OVERLAYED. EXAMINE AS PART OF J-3 UPSTREAM ON INSIDE OF ELBOW 89.12 8-J NUREG-0313A 1831-1RC-12AR -J-3LU-O A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF J-3 UPSTREAM ON OUTSIDE OF ELBOW 89.11 8-J NU;tEG-0313C 1831-1RC-12AR-J-4 A-18/02 UT-H-400/7 87 X 17-H
- PIPE TO SAFE-END PT-H-600/2 FXAMINED 1987 RO IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.12 3-J NUREG-0313A 1831-1RC-12AR-J-4LU A-18/02 UT-H-400/7 SEE NOTE 1-A.
LONGITUDINAL SEAN PT-H-600/2 17-H WELD EXTEfCING UPSTREAM 85.10 5-F NUREG-0313C 1831-1RC-12AR-J-5 A-18/02 UT-H-400/7 87 X 85-H.108-H
INFORMATION SERVICES-BIRMINGHAM
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EDWIN I. HATCH NUCLEAR PLANT - UNIT 1 MJREG-(D313. REV. 2 PAGE O (FOR INFORMATION ONLY)
ASME ASME EXA51 EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS
- ITM NO. CAT. REQUIRENENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIDO CALIBRATION BLOCK 89.11 8-J NUREG-0313C 1831-1RC-12AR-K-1 A-18/02 UT-H-400/7 X X 17-H
- 8-C TO PIPE PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1988 RO RE-EXAMINE 2ND PERIDO 89.12 B-J NUREG-0313A 1831-1RC 12AR-K-1LD A-18/02 UT-H-400/7 7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-41-600/2 17-H WELD EXTENDING DOWNSTREAM 89.11 8-J NUREG-0313E 1831-1RC-12AR-K-2 A-k8/02 UT-H-408/1 X X X PT OVERLAY ANO 1 INCH
- PIPE TO ELSOW PT-H-600/2 SASE MATERIAL ON EACH 84 OVERLAY /88 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H s 89.12 8-J NUREG-0313A 1931-1RC-12AR-K-2LD-1 A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF K-2 DOWNSTREAN ON INSIDE OF ELBOW 89.12 8-J MJPEG-0313 A 1331- 1RC- 12 AR-K-2LD-O A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF K-2 DOWNSTREAM ON m OUTSIDE OF ELBOW N
1 89.12 B-J MJREG-0313A 1831-1RC-12AR-K-2LU A-18/02 OVEELAYED. EXAMINE AS
-- LONGITUDINAL SEA 4 PART OF K-2 WELD EXTEM)ING UPSTREAM ft9.11 8-J NUREG-0313E 1831-1RC-12AR-K-3 A-18/02 UT-H+408/1 X X X PT OVERLAY AND 1 INCH e ELBOW TO PIPE PT-H-600/2 BASE MATERIAL ON EACH 84 OVERLAY /88 RESURF SIDE. EXAP*INE 1988 THEN EVERY 2ND OUTAGE. 134-H 89.12 8-J NUREG-0313A 1831-1RC-12AR-K-3LD A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF K-3 WELD EXTENOING DOWNSTREAM 89.12 8-J NUREG-0313A 1831-1RC-12AR-K-3LU-I A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF K-3 UPSTREAM ON INSIDE OF ELBOW 89.12 8-J NUREG-0313A 1831-1RC-12AR-K-3LU-O A-18/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF K-3 UPSTREAM ON OUTSIDE OF ELBOW
INFORMATION SERVICES-BIRMhMA EDWI;* I. HATCH NUCLEAR PLANT - UNIT 1, ?AJRE3-C313, REV. 2 PAGE 13 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIR 3T SECOND THIRD REMARKS
- ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.11 B-J NUREG-0313C 1831-1RC-12AR-K-4 A-18/02 UT-H-400/7 87 X 17-H
- PIPE TO SAFE-END PT-H-600/2 EXAMINED 1987 RO, IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD B9.12 S-J NUREG-0313A 1831-1RC-12AR-K-4LU A-18/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 17-H WELD EXTENDING UPSTREAM B5.10 B-F NUREG-0313C 1831-1RC-12AR-K-5 A-18/02 UT-H-400/7 87 X 17-H
- SAFE-END TO NOZZLE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RE-EXAMINE 2ND PERIOD 89.11 8-J NUREG-0313C 1831-1RC-12BR-A-1 A-39/02 UT-H-400/7 87 X 17-H
- B-C TO PIPE PT-H-600/2 EXAMINED 1987 RO IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 89.12 B-J NUREG-0313A 1831-1RC-12BR-A-1LD A-19/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H n1 WELD EXTENDING j' DOWNSTREAM E$ B9.11 B-J NUREG-0313C 1831-1RC-12BR-A-2 A-19/02 UT-H-400/7 87 X 17-H a PIPE TO ELBDW PT-H-SOO/2 EXAMINED 1987 RO IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD B9.12 B-J NUREG-0313A 1831-1RC-12BR-A-2LD-I A-19/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 17-H DOWNSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-12BR-A-2LD-O A-19/02 UT-H-400/7 SEE NOTE A-1.
LDNGITUDINAL WELD PT-H-BOO /2 17-H DOWNSTREAM ON DUTSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-12BR-A-2LU A-19/02 UT-H-400/7 SEE NOTE A-1 LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313C 1B31-1RC-12BR-A-3 A-19/02 UT-H-400/7 87 X 17-H
- ELBOW TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD
INFORaAATION SERVICES-BIRMINGHAM
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EDWIN 1. HATCH NUCLEAR PLANT - UNIT 1 NURE3-0313. REV. 2 PAGE 11 (FOR INFORMATION ONLY)
ASME AS80E EXAM EXAMINATION FIGURE EXAMI*4ATION FIRST SECOND THIRD REMARKS .
ITM NO. CAT. REQUIREteENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOO PERIOD CALIBRATION BLOCK -
89.12 8-J NUREG 0313A 1831-1RC-128R-A-3LD A-19/02 UT-H-400/7 87 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EX'ENDING DOWNSTREAM 89.12 5-J PRJREG-0313A 1831-1RC-128R-A-3LU-I A-19/02 UT-H-400/7 87 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 17-H UPSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-128R-A-3LU-O A-19/02 UT-H-400/7 87 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-SOO/2 17-H UPSTREAM ON OUTSIDE OF EL80W 99.1- B-J NUREG-0313F 1831-1RC-128R-A-4 A-19/02 UT-H 400/7 87 X X EXAMINE 4 OUTAGES IN A e PIPE TO SAFE-END PT-H-600/2 ROW STARTING IN 1987.
IHSI 1985/1986 RO IF UNCHANGED RECLASSIFY AS CATEGORY E. 17-H 89.12 8-J 94JREG-0313A 1831-1RC-12BR-A-4LU A-19/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 17-H WELD EXTENDING m UPSTREAM N
e 85.10 8-F NUREG-0313C 1831-1RC-128R-A-5 A-19/02 UT-H-400/7 87 X 85-H.108-H C e SAFE-END TO NOZZLE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIO3 89.11 8-J NUREG-0313C 1831-1NC-128R-8-1 A-19/02 UT-H-400/7 X X 17-H e 8-C TO PIPE PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 2ND PERICO 89.12 8-J NUREG-0313A 1831-1RC-128R-8-1LD A-19/02 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING DOWNSTREAM 89.11 8-J NUREG-0313C 1811-1RC-128R-8-2 A-19/02 UT-H-400/2 87 X 17-H e PIPE TO ELBOW PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 290 PERIOD 89.12 B-J NUREC-0313A IS31-1RC-128R-8-2LD-I A-19/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDItLM. WELD PT-H-600/2 DOWNSTREAM ON INSIDE OF ELBOW
INFORMATION SERVICES-BIRMINGHAM
~
EDWIM I. HATCH WCLEAR PLANT - UNIT 1, DANTE 3-0313. REV. 2 PAGE 12 (FOR INFORMATION ONLY)
I ASesE ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRO REMARKS -
ITN NO. CAT. PEQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERICO PERIOD PERIOD CALIBRATION SLOCK 89.12 8-w MJREG-0313A 1831- 1RC-128R-8-2LD-O A-19/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-Sto/2 17-H DOWNSTREAM ON OUTSIDE OF EL80W 89.12 8-J 94JREG-0313A 1831-1RC-128R-8-2LU A-19/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 17-H WELD EXTENDING UPSTREAM 89.11 8-J NUREG-0313E 1831-1RC-12SR-B-3 A-19/02 UT-H-408/1 87 X X PT OVERLAY A M 1 INCH
- ELBOW TO PIPE PT-H-SOO/2 BASE MATERIAL ON EACH 1986 OVERLAY SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1931-iRC-128R-B-3LD A-19/C2 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF 8-3 WELD EXTENDING DOWNSTREAM 89.12 5-J P4JREG-0313A 1831-1RC-128R-8-3LU-I A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF 8-3 UPSTREAM ON INSIDE OF ELBOW 89.12 5-J NUREG-0313A 1831-1RC-128R-8-3LU-O A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF 8-3 UPSTREAM ON OUTSIDE OF ELBOW 89.11 5-J NUREG-0313C 1831-1RC-128R-8-4 A-19/02 UT-H-400/7 87 X 17-H
- PIPE TO SAFE-E W PT-H-SOO/2 EXAMINED 1987 RC.
IHSI 1985/1986 RO RE-EXAMINE 29C PERIOD 89.12 8-J NUREG-0313A 183i-1RC-128R-B-4LU A-19/02 UT-H-400/7 SEE NOTE A-1 LONGITUDINAL F"4M PT-H-SOO/2 17-H WELD EXTENDING UPSTREAM 85.10 B-F NUREG-0313C 1831-1RC-12BR-8-5 A-19/02 UT-H-400/7 77 X 85-H.108-H
- SAFE-END TO N0ZZLE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOG 89.11 B-J MJREG-0313C 1531-1RC-12BR-C-1 A-19/02 UT-H-400/7 X X 17-M
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1, PAJRE2-C313. T.EV. 2 PAGE 13 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECONO THIRD RF'1 ARKS - -
ITM NO. CAT. REQUIREMENT AREA IDEN1IFICATION NO./REV PROCED./REV PERIOD PERIDO PERIOO CALIBRA(ION BLOCK 69.12 B-J NUP.EG-0313A 1831-1RC-12BR-C-1LD A-19/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-dOO/2 17-H WELD EXTENDING DOWNSTREAM B9.11 B-J NUREG-0313E 1B31-1RC-12BR-C-2 A-19/02 UT-H-408/1 X X X PT OVERLAY AND 1 INCH
- PIPE TO ELBOW PT-H-600/2 BASE MATERIAL ON EACH 84 OVERLAY /86 RESURF SIDE. EXAMINE 1988 THEN EVERY 2ND OUTAGE. 134-H B9.12 B-J NUREG-0313A ?B31-1RC-12BR-C-2LD-I A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF C-2 DOWNSTREAM ON INSIDE OF ELBOW B9.12 B-J NUREG-0313A 1831-1RC-12BR-C-2LD-O A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF C-2 DOWNSTREAM ON OUTSIDE OF ELBOW B9.12 B-J NUREG-0313A 1B31-1RC-12BR-C-2LU A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF C-2 WELD EXTENDING n UPSTREAM N
I B9.11 B-J NUREG-0313E 1831-1RC-12BR-C-3 A-19/02 UT-H-408/1 X X X PT OVERLAY AND 1 INCH G e ELBOW TO PIPE PT-H-BOO /2 BASE MATERIAL ON EACH 84 OVERLAY /88 RESURF SIDE. EXAMINE 1988 THEN EVERY 2ND OUTAGE. 134-H 89.12 0-J NUREG-0313A 1831-1RC-12BR-C-3LD A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF C-3 WELD EXTENOING DOWNSTREAM 89.12 B-J NUREG-03134 1831 RC-12BR-C-3LU-I A-19/02 OVERLAYED. EXAMINE AS LONG1 JDINAL WELD PART OF C-3 UPSTO.EAM ON INSIDE OF ELBOW 89.12 B-J NUREG-031:TA 1B31-1RC-12BR-C-3LU-O A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELO PART OF C-3 UPSTREAM ON OUTSIDE OF LLBOW 89.11 B-J NU'tEG-0313E IB31-1RC-12BR-C-4 A-19/02 UT-H-408/1 X X X PT OVERLAY AND 1 INCH e PIPE TO SAFE-END PT-H-BOO /2 BASE MATERIAL ON EACH 1988 OVERLAY SIDE. EXAMINE 1988 THEN EVERY 2ND OUTAGE. 134-H 3
ms
lhTORMATION SERVICES-BIRMINGHAM EDWIN 1. HATCH NUCLEAR PLANT - UNIT 1, NURE3-C313, E.EV. 2 PAGE 1C (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATIDN FIGURE EXAMINATION FIRST LECOND THIRD REMARKS ,
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATIDN BLDCK 89.12 B-J NUREG-0313A 1831-1RC-12BR-C-4LU A-19/02 GVERLAYED. EXANJF AS LONGITUDINAL SEAM PART OF C-4 WELD EXTENDING UPSTREAM B5.10 B-F NUREG-0313C 1831-1RC-12BR-C-5 A-19/02 UT-H-400/7 X X EXAMINE 1988 OUTAGE AND
- SAFE-END TO N0Z2LE PT-H-600/2 RE-EXAMINE 3RD PERIOD IHSI 1985/1986 RO 3RD PERIOD B9.11 B-J NUREG-0313C 1831-1RC-12BR-D-1 A-19/02 UT-H-400/7 X X 17-H
l B9.12 B-J NUREG-0313A 1831-1RC-12BR-D-1LD A-19/02 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING DOWNSTREAM 89.11 B-J NUREG-0313E IB31-1RC-12BR-D-2 A-19/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH e PIPE TO ELBOW PT-H-600/2 BASE MATERIAL ON EACH n1 1986 OVERLAY SIDE. EXAMINE EVERY 2ND b3 OUTAGE. 134-H I B9.12 B-J NUREG-0313A 1B31-1RC-12BR-D-2LD-I A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF D-2 DOWNSTREAM ON INSIDE OF ELBOW B9.12 B-J NUREG-0313A 1831-1RC-12BR-D-2LD-O A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF D-2 DOWNSTREAM DN OUTSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-12BR-D-2LU A-19/02 OVERLAYED. EXAMINE AS LDNGITUDINAL SEAM PART OF D-2 WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313E 1831-1RC-12BR-D-3 A-19/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH e ELBOW TO PIPE PT-H-600/2 BASE MATERIAL DN EACH 84 OVERLAY /86 RESURF SIDE. EXAMINE EVERY 2ND DUTAGE. 134-H 89.12 B-J NUREG-0313A 1831-1RC-12BR-D-3LD A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF D-3 WELD EXTENDING DOWNSTREAM l
l l
i i
EDWIN I. HATCH NUCLEAR PLANT - UNIT 1, NURE2-0313, Rl*V. 2 PAGE 13 (FOR INFORMATION ONLY)
ESHE ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD FERIOD PERIOD CALIBRATIDN BLOCK B9.12 B-J NUREG-0313A 1831-1RC-12BR-D-3LU-I A-19/02 OVE9 LAYED. EXAMINE AS LONGITUDINAL WELD PART OF D-3 UPSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 1931-1RC-12BR-D-3LU-O A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF D-3 UPSTREAM ON DUTSIDE OF _ 30W 89.11 B-J NUREG 03 ud 1B31-IRC-12BR-D-4 A-19/02 UT-H-400/7 87 X 17-H
- PIPE TO SAFE-END PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1938 RO RE-EXAMINE 2ND PERIOD 89.12 B-J NUREG-0313A 1831-1RC-12BR-D-4LU A-19/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING UPSTREAM G5.10 B-F NUREG-0313C 1831-1RC-12BR-D-5 A-19/02 UT-H-400/7 X X 85-H.108-H
- 2. B9.11 B-J NUREG-0313C 1B31-1RC-12BR-E-1 A-19/02 UT-H-400/7 X X 17-H
- a
- B-C TO PIPE PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD B9.12 B .J NUREG-0313A 1831-1RC-12BR-E-1LD A-19/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING DOWNSTREAM 89.11 8-J NUREG-0313E IB31-1RC-12BR-E-2 A-19/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
- PIPE TO ELBOW PT-H-600/2 BASE MATERIAL ON EACH 84 OVERLAY /86 RESURF SIDE. EXAMINE EVERY 2ND 0TAGE. 134-H B9.12 B-J NUREG-0313A 1831-1RC-12BR-E-2LD-I A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF E-2 DOWNSTREAM ON INSIDE OF ELBOW 09.12 B-J NUREG-0313A 1BC1-1RC-12BR-E-2LD-O A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF E-2 DOWNSTREAM ON OUTSIDE OF ELBOW
Ir; FORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLE.dt PLANT - UNIT 1, NUREG-C313, EEV. 2 PAGE 13 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDEPITIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOO CALIBRATION BLOCK -
89.12 B-J NUREC-0313A 1531-1RC-12BR-E-2LU A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF E-2 WELD EXTEN9ING "PSTREAM J
89.11 B-J NUREG-0313E 1831-1RC-12BR-E-3 A-19/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
- El. BOW TO PIPE PT-H-600/2 BASE MATERIAL ON EACH 84 OVERLAY /86 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H -
89.12 B-J NUREG-0313A 1831-1RC-12BR-E-3LD A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF E-3 WELD EXTENDING DOWNSTREAM 89.12 B-J NUREG-0313A 1B31-1RC-12BR-E-3LU-I A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF E-3 UPSTREAM ON INSIDE OF ELBOW B9.12 B-J NUREG-0313A 1831-1RC-12BR-E-3LU-O A-19/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF E-3 UPSTREAM ON OUTSIDE OF ELBOW m
N 89.11 B-J NUREG-0313F 1831-1RC-12BR-E-4 A-19/02 UT-H-400/7 87 X X EXAMINE 4 OUTAGES IN A 1
- PIPE TO SAFE-END PT-H-600/2 ROW STARTING IN 1987.
Do IHSI 1985/1986 RO IF UNCHANGED RECLASSIFY AS CATEE.ORY E. 17-H 89.12 B-J NUREG-0313A 1831-1RC-12BR-E-4LU A-11/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 17-H WELD EXTENDING UPSTREAM B5.10 B-F NUREG-0313C 1831-1RC-12BR-E-5 A-19/02 UT-H-400/7 X X 85-H.108-H
- SAFE-ENG TO NOZ2LE PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD B9.11 B-J NUREG-0313E 1B31-1RC-22AM-1 A-16/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
- PIPE TO CAP PT-H-600/2 BASE MATERIAL ON EACH 82 OVERLAY /86 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H B9.31 B-J NUREG-0313C IB31-1RC-22AM-1BC-1 A-16/02 UT-H-400/7 87 X 22-H
- PIPE TO B-C PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD
INFORMATION SFRVICES-BIRMINGHAM EDWIN 1. HATCH NUCLEAR PLANT - UNIT 1, NURE2-0313 REV. 2 PAGE 17 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FI R',T SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.31 B-J NUREG-0313C 1831-1RC-22AM-1BC-2 A-16/02 UT-H-400/7 87 X 22-H
- PIPE TO B-C PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1988 RO RE-EXAMINE 2ND PERIOD B9.12 B-J NUREG-0313A IB31-1RC-22AM-1LU A-16/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF 22AM-1 WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313C 1831-1RC-22AM-2 A-16/02 UT-H-400/7 87 X 22-H
- CROSS TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.12 B-J NUREG-0313A 1831-1RC-22AM-2LD A-16/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING DOWNSTREAM 89.11 B-J NUREG-0313C 1831-1RC-22AM-3 A-16/02 UT-H-400/7 87 X 22-H
- CROSS TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD C e 89.31 B-J NUREG-0313C 1831-1RC-22AM-3BC-1 A-16/02 UT-H-400/7 87 X 22-H
($
- PIPE TO B-C PT-H-GOO /2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.31 B-J NUREG-0313C 1831-1RC-22AM-3BC-2 A-16/02 UT-H-400/7 87 X 22-H
= PIPE TO B-C PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD
- 89. e2 B-J NUREG-0313A 1831-1RC-22AM-3LD A-16/02 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING DOWNSTREAM B9.11 B-J NLREG-0313E 1B31-1RC-22AM-4 A-16/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
- PIPE TO CAP PT-H-60C/2 BASE MATERIAL ON EACH 82 OVERLAY /86 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H B9.12 .B-J NUREG-0313A 1831-1RC-22kM-4LU A-16/02 OVERLAYED. EXAMINE AS LONGITUDIkAL SEAM PART OF 22AM-4 WELD EXTENDING UPSTREAM
INFORMATION SERVICES-BIRMINGHAM EDWIN 1. HATCH NUCLEAR PLANT - UNIT 1 NURE2-C313, KEV. 2 PAGE 18 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECGND THIRD REMARKS -
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK
~
89.11 8-J NUREG-0313E 1831-1RC-22BM-1 A-17/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH e PIPE TO CAP PT-H-600/2 BASE MATERIAL ON CACH 82 OVERLAY /86 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.31 B-J NUREG-0313C 1831-1RC-22BM-1BC-1 A-17/02 UT-H-400/7 X X 22-H
- PIPE TO B-C PT-H-600/2 EXAMINE 1980 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD B9.31 B-J NUREG-0313C 1831-1RC-22BM-1BC-2 A-17/02 UT-H-400/7 X X 22-H
- PIPE TO B-C PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD B9.12 B-J NUREG-0313A 1831-1RC-22BM-1LU A-17/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF 22BM-1 WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313C 1P31-1RC-22BM-2 A-17/02 UT-H-400/7 X X 22-H
N c) B9.12 B-J M9 REG-0313A 1B31-1RC-22BM-2LD A-17/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING DOWNSTREAM 89.11 B-J NUREG-0313C 1831-1RC-22BM-3 A-17/02 UT-H-400/7 X X 22-H e CROSS TO PIPE PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1988 RO RE-EXAMINE 3RD PERIOD 89.31 B-J NUREG-0313C IB31-1RC-22BM-3BC-1 A-17/02 UT-H-400/7 X X 22-H e PIPE TO B-C PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 89.31 B-J NUREG-0313C 1831-1RC-22BM-3BC-2 A-17/02 UT-H-400/7 X X 22-H e PIPE TO B-C PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 89.12 B-J NUREG-0313A 1831-1RC-22BM-3LD A-17/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING DOWNSTREAM
INFORMATION SERVICES-CIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT t, NURE2-0313. EEV. 2
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PAGE 19 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXANTNATION FIRST SECOND THIRD REMARKS -
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROGED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK
~
B9.11 B-J NUREG-0313E 1831-1RC-22BM-4 A-17/92 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
- PIPE TO CAP PT-H-600/2 BASE MATERIAL ON EACH 82 OVERLAY /88 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1831-1RC-22BM-4LU A-17/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF 22BM-4 WELD EXTENDING UPSTREAM B5.10 B-F NUREG-0313C IB3k-1RC-28A-1 A-14/03 UT-H-4GO/7 87 X 29-H.22-H
- NOZZLE TO SAFE-END PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD.
B9.11 B-J NUREG-0313F 1B31-1RC-28A-2 A-14/03 UT-H-400/7 87 X X EXAMINE 4 OUTAGES IN A
- SAFE-END TO PIPE PT-H-600/2 ROW STARTING IN 1987.
IF UNCHANGED RECLASSIFY AS CATEGORY E. 22-H 89.12 B-J NUREG-0313A 1831-1RC-28A-2LD A-14/03 UT-H-400/7 87 SEE NOTF. A-1.
LDNGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING m DOWNSTREAM da 89.11 8-J NUREG-0313C 1831-1RC-28A-3 A-14/03 UT-H-400/7 87 X 22-H
- PIPE TO ELBOW PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD.
'd9.12 B-J NUREG-0313A 1831-1RC-28A-3LD-I A-14/03 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H DOWNSTREAM ON INSIDE OF ELBOW B9.12 B-J NUREG-0313A 1831-1RC-28A-3LD-0 A *4/03 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H DOWNSTREAM ON
- DUTSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-28A-3LU A-14/03 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING l UPSTREAM i
l 89.11 B-J NUREG-0313F 1831-1RC-28A-4 A-14/03 UT-H-400/7 87 X X EXAMINE 4 DUTAGES IN A l
- ELBOW TO PIPE PT-H-600/2 ROW STARTING IN 1987.
IF UNCHANGED RECLASSIFY AS CATEGORY E. 22-H I
I
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1 NUREO-C313, REV. 2 PAGE 20 (FOR IN/ORMATION DNLY)
ASME ASME EXAM EXnMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIERATION BLOCK 89.12 B-J NUREG-0313A 1831-1RC-28A-4LD A-14/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING DOWNSTREAM 89.12 B-J NUREG-0313A 1831-1RC-28A-4LU-I A-14/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H UPSTREAM ON INSIDE OF ELBDW 89.12 B-J NUREG-0313A 1831-1RC-28A-4LU-0 A-14/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H UPSTREAM ON OUTSIDE OF ELBOW B9.11 B-J NUREG-0313C 1831-1RC-28A-5 A-14/03 UT-H-400/7 X X 22-H e PIPE TO PIPE PT-H-600/2 EXAMINE 1988 DUTAGE AND IHSI (985/1986 RO RE-EXAMINE 2ND PERIOD B9.11 B-J NUREG-0313C 1831-1RC-28A-5A A-14/03 UT-H-400/7 X X 22-H
$ B9.12 B-J NUREG-0313A 1831-1RC-28A-5ALD A-14/03 UT-H-400/7 SEE NOTE A-1 LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING DOWNSTREAM B9.12 R-J NUREG-0313A 1831-1RC-28A-5ALU A-14/03 UT-H-400/7 SEE NOTE A-1 LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING UPSTREAM B9.12 B-J NUREG-0313A 1831-1RC-28A-5LD A-14/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING DOWNSTREAM 89.12 B-J NUREG-0313A 1831-1RC-28A-5LU A-14/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING UPSTREAM B9.11 B-J NUREG-0313F 1831-1RC-28A-6 A-14/03 UT-H-400/7 87 X X EXAMINE 4 OUTAGES IN A
= PIPE TO ELBOW PT-H-600/2 ROW STARTING IN 1987.
IF UNCHANGED RECLASSIFY AS CATEGORY E. 22-H
INFORMATION SERVICES-BIRMINGHAM 4 EDWIN I. HATCH NUCLEAR PLANT - UNIT 1, NUREO-C313, LEV. 2 PAGE 21 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS
- ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO /REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.12 B-J NUREG-0313A 1831-1RC-28A-6LD-I A-14/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-SOO/2 22-H DOWNSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 1931-1RC-?SA-6LD-O A-14/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H DOWNSTREAM ON OUTSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-28A-6LU A-14/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING UPSTREAM
=
89.11 8-J NUREG-0313C 1831-1RC-28A-7 A-14/03 UT-H-400/7 87 X 22-H I
- ELBOW TO VALVE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.12 B-J NUREG-0313A 1031-1RC-28A-7LU-I A-14/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H UPSTREAM ON INSIDE OF ELBOW IS B9.12 B-J NUREG-0313A 1831-1RC-28A-7LU-O A-14/03 UT-H-400/7 SEE NOTE A-1.
8 LONGITUDINAL WELD PT-H-600/2 22-H
($ UPSTREAM ON OUTSIDE OF ELBOW B3.11 8-J NUREG-0313C 1831-1RC-28A-8 A-14/03 UT-H-400/7 87 X 22-H
- VALVE TO PIPE PT-H-600/2 EXAMINED 1987 P2.
IHSI 1985/1986 RO RE-EXAMINE 2NO PERIOD 89.12 B-J NUREG-0313A 1B31-1RC-28A-8LD A-14/03 UT-H-400/7 SEE NOTE A-1.
LDNGITUDINAL SEAM PT-H-BOO /2 22-H WELD EXT *NDING DOWNSTREAM 89.11 B-J NUREG-0313C 1B31-1RC-28A-9 A-14/03 UT-H-400/7 87 X 22-H
+ PIPE TO ELBOW PT-H-SOO/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.12 B-J NUREG-0313A 1831-1RC-28A-9LD-I A-14/03 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-SOO/2 22-H DOWNSTREAM ON INSIDE OF ELBOW
INFORMAT!ON SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1. MJRED-C313 f.EV. P PAGE 22 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIG'RE EXAMINATION FIRST SECOND THIRD REMARKS ~
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.12 B-J NUREG-0313A 1831-1RC-28A-9LD-O A-14/03 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H DOWNSTREAM ON OUTSIDE OF ELBOW B9.12 B-J NUREG-0313A 1831-1RC-28A-9LU A-14/03 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313E 1831-1RC-28A-10 A-14/03 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
- ELBOW TO PUMP PT-H-600/2 BASE MATERIAL ON EACH 84 OVERLAY /86 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1831-1RC-28A-10LU-I A-14/03 OVERLAYED. EXAMINE AS LONGITUOINAL WELD PART OF 28A-10 UPSTREAM ON INSIDE OF ELBOW B9.12 B-J NUREG-0313A 1831-iRC-28A-IOLU-O A-14/03 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF 28A-10 m UPSTREAM ON OUTSIDE y OF ELBOW
.t:- 89.11 8-J NUREG-0313C 1831-1RC-28A-11 A-148/OO UT-H-400/7 X X 22-H
- PUMP TO PIPE PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD B9.31 B-J NUREG-0313C 1831-1RC-28A-11BC A-14B/OO UT-H-400/7 X X 22-H
- PIPE TO BC PT-H-600/2 EXAMINE 1988 .at.GE AND IHSI 1985/1986 RO PE-EXAMINE 3RD PERIOD 89.12 B-J NUREG-0313A 1831-1RC-28A-11LD A-148/OO UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 22 H WELD EXTENOING DOWNSTREAM 89.11 B-J NUREG-0313E 1831-1RC-28A-12 A-14B/OO UT-H-408/1 87 X X PT OVER'_AY ANO 1 INCH
+ PIPE TO VALVE PT-H-600/2 BASE MATERIAL ON EACH 1986 OVERLAY SIDE. EXAWINE EVERY 2ND OUTAGE. 134-H 89.12 5-J NUREG-0313A 1831-1RC-28A-12LU A-148/OO OVEkLAYED. EXAMINE AS LONGITUDINAL SEtM PART OF 28A-12 WELD EXTENDING UPSTREAM
~
INFORMATION SE.9 VICES-CIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT f, NURE2-C313, REV. 2 PAGE 23 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS .
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATIDN NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK
- 89.11 8-J NUREG-0313C 1831-1RC-28A-13 A-148/OO UT-H-400/7 X X 22-H
- VALVE ".0 ELBOW PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSt 1985/1986 RO RE-EXAMINE 3RD PERIOD B9.12 B-J NUREG-0313A 1831-1RC-28A-13LD-I A-145/OO UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELO PT-H-600/2 22-H DOWNSTREAM ON INSIDE OF ELBOW B9.12 8-J NUREG-0313A 1831-1RC-28A-13LD-O A-148/OO UT-H-40C/7 SEF NOTE A-1
, DOWNSTREAM PT-H-600/2 22-H LONG TUDINAL WELD ON OUTSIDE OF ELBOW 89.11 8-J NUREG-0313C 1831-1RC-28A-14 A-148/OO UT-H-400/7 X X 22-H
- ELBOW TO PIPE PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 89.31 8-J NUREG-0313C 1831-1RC-28A-14BC A-148/OO UT-H-400/7 X X 22-H
/3 89.12 B-J NUREG-0313A 1831-1RC-28A-14LD A-148/OO UT-H-400/7 SEE NOTE A-1.
i tn LONGITUDINAL SEAM PT-H-600/2 22-H
- WELD EXTENDING DOWNSTREAM i
89.12 8-J NUREG-0313A 1831-1RC-28A-14LU-I A-148/OO UT-H 400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT ~.s-600/2 22-H i
UPSTREAM ON INSIDE OF ELBOW s
89.12 B-J NUREG-0313A 1831-1RC-28A-14LU-O A-145/OO UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H UPSTREAM ON OUTSIDE OF ELBOW l 89.11 1-J NUREG-0313C 1831-1RC-28A-15 A-148/OO UT-H-400/7 X X 22-H
- PIPE TO 1EE PT-H-600/2 EXAMINE 1988 OUTAGE AND IRSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 89.12 e-J NUREG-0313A 1831-1RC-28A-15LU A-148/OO UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 22-H WELD EXTENDING UPSTREAM I
INFORMATION SERVICES-BIRMINGHAM EDWIN 1. HATCH NCCLEAR PLANT - UNIT 1, NURC2-C313, CEV. 2 PAGE 2C (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATIDN FIRST SECOND THIRD REMARKS '
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV FERIOD PERIOD PERIDO CALIBRATION BLOCK 89.11 B-J NUREG-0313C 1831-1RC-28A-18 A-148/OO UT-H-400/7 X X 23-SS-X-2.30-92-H
- TEE TO CROSS PT-H-600/2 EXAMINE 1988 DUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RC PERIOD 89.11 ,B-J NUREG-0313C 1B31-1RC-28A-17 A-14B/OO UT-H-400/7 X X 28-SS-X-2.30-92-H
- CROSS TO REDUCER PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD B5.10 B-F NUREG-0313C 1871-1RC-288-1 A-15/03 UT-H-400/7 87 X 29-H, 22-H e NOZZLE TO SAFE-END PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD l 89.11 B-J NUREG-0313C 1831-1RC-288-2 A-15/03 UT-H-400/7 87 X 22-H
- SAFE-END TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1586 RO RE-EXAMINE 2ND PERIOD 89.12 B-J NUREG-0313A 1831-1RC-280-2LD A-15/03 UT-H-400/7 SEE NOTE A-1.
F1 LONGITUDIN/.L SEAM PT-H-BOO /2 22-H S' WELD EXTENDING ro DOWNSTREAM B9.11 8-J NUREG-0313E 1831-1RC-288-3 A-15/03 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
- PIPE TO ELBOW PT-H-600/2 BASE MATERIAL ON EACH 84 OVERLAY /86 RESURT SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1531-1RC-288-3LD-I A-15/03 OVERLAYED. 2XAMINE AS LONGITUDINAL WELD PART OF 288-3 DOWNSTREAM ON INSIDE OF EL8OW 89.12 B-J NUREG-0313A 1B31-1RC-288-3LD-0 A-15/03 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF 288-3 DOWNSTREAM DN OUTSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-285-3LU A-15/03 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF 288-3 WELD EXTENDING UPSTREAM B9.11 8-J NUREG-0313E 1831-1RC-288-4 A-15/03 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH e ELBOW TO PIPE PT-H-600/2 BASE MATERIAL DN EACH 84 OVERLAY /86 RESURF SIDE. EXAMINE EVERY 2ND OUTAGT. 134-H 1
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1, FRJREE-C313, REV. 2 PAGE 25 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS .
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOO PERIOD CALIBRATION BLOCK ,
89.12 8-J NUREG-0313A 1831-1RC-288-4LD A-15/03 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF 288-4 WELD EXTENDING DOWNSTREAM 89.12 B-J NUREG-0313A 1831-1RC-288-4LU-I A-15/03 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF 288-4 UP"TREAM ON INSIDE OF ELBOW 89.12 8-J NUREG-0313A 1831-1RC-288-4LU-O A-15/03 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF 288-4 UPS1 REAM ON OUTSIDE OF EL80W 89.11 8-J NUREG-0313C 1831-1RC-288-5 A-15/03 UT-H-400/7 87 X 22-H
= PIPE TO TEE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.12 8-J NUREG-0313A 1831-1RC-288-5LU A-15/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 22-H m WELD EXTENDING 7 UPSTREAM I$ 89.11 8-J NUREG-0313C 1831-1RC-288-6 A-15/03 UT-H-400/7 X X 22-H
- TEE TO PIPE PT-H-600/2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 89.12 8-J NUREG-0313A 1831-1RC-288-6LD A-15/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-BOO /2 22-H WELD EXTENDING DOWNSTREAM 89.11 8-J NUREG-0311C 1831-1RC-288-7 A-15/03 UT-H-400/7 X X 22-H
- PIPE TO ELBOW PT-H-BOO /2 EXAMINE 1988 OUTAGE AND IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 89.12 8-J NUREG-0313A 1831-1RC-288-7LD-1 A-15/03 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H DOWNSTREAM ON INSIDE OF EL80W 89.12 8-J NUREG-0313A 1831-1RC-288-7LD-O A-15/03 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-SOO/2 22-H DOWNSlREAM DN OUTSIDE OF ELBOW
INFORMATION SERVICES-IIRMINGHAM
~
EDVIN I. HATCH NUCLEAR PLANT - UNIT 1, NUREO-0313, CEV. 2 PAGE 26 (FOR INfORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK B9.12 B-J NUREG-0313A 1831-1RC-288-7LU A-15/03 UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING UPSTREAM B9.11 8-J NUREG-0313F 1831-1RC-288-8 A-15/03 UT-H-400/7 87 X X . EXAMINE 4 DUTAGES IN A
- ELBOW TO VALVE PT-H-600/2 ROW STARTING IN 1987.
IF UNCHANGED RECLASS'FY AS CATEGORY E. 22-H B9.12 B-J NUREG-0313A 1831-1RC-288-8LU-I A-15/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H UPSTREAM ON INSIDE OF ELBOW B9.12 B-J NUREG-0313A 1831-1RC-288-8LU-0 A-15/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H UPSTREAM ON OUTSIDE OF ELBOW B9.11 B-J NUREG-0313C 1831-1RC-288-9 A-15/03 UT-H-400/7 X X 22-H .
$$ 89.12 B-J NUREG-0313A 1931-1RC-288-9LD A-15/03 PT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING DOWNSTREAM B9.11 B-J NUREG-0313F 1831-1RC-288-10 A-15/03 UT-H-400/7 87 X X EXAMINE 4 OUTAGES IN A
- PIPE TO ELBOW PT-H-600/2 ROW STARTING IN 1987.
IHSI 1985/1986 RO IF UNCHANGED RECLASSIFY AS CATEGORY E. 22-H B9.12 B-J NUREG-0313A 1831-1RC-288-10LD-I A-15/03 UT-H-400/7 SEE NOTE A-1.
DOWNSTREAM PT-H-600/2 22-H LONGITUDINAL WELD ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 1831-1RC-288-10LD-0 A-15/03 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H DOWNSTREAM ON OUTSIDE OF ELBOW l 89.12 B-J NUREG-0313A 1831-1RC-288-10LU A-15/03 UT-H-400/7 SEE NOTE A-1.
l LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING UPSTREAM
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1 NURE2-C313, CEV. 2 PAGE 27 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS -
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATIDN BLCCK B9.11 B-J NUREG-0313E 1831-1RC-288-11 A-15/03 UT-H-408/1 X X X PT OVERLAY AND 1 INCH
= ELBOW TO PUMP PT-H-600/2 BASE MATERIAL ON EACH 84 OVERLAY /86 RESURF SIDE. EXAMINE 1988 THEN EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1B31-1RC-288-11LU-I A-15/03 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF 288-11 UPSTREAM ON INSIDE OF ELBOW B9.12 B-J NUREG-0313A 1831-1RC-288-11LU-O A-15/03 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PART OF 283-11 UPSTREAM ON OUTSIDE OF ELBOW B9.11 B-J NUREG-0313C IB31-1RC-288-12 A-15B/OO UT-H-400/7 87 X 22-H
- PUMP TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.31 B-J NUREG-0313C 1831-1RC-288-12BC A-15B/OO UT-H-400/7 87 X 22-H
[] IHSI 1985/1986 RO RE-EXAMINE 2ND PERIDO a
\D E9.12 8-J NUREG-0313A 1B31-1RC-288-12LD A-15B/OO UT-H-400/7 X SEE NOTE A-1 LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING DOWNSTREAM B9.11 B-J NUREG-0313C 1831-1RC-28B-13 A-15B/OO UT-H-400/7 87 X 22-H
- PIPE TO VALVE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD B9.12 B-J NUREG-0313A 1831-1RC-288-13LU A-15B/OO UT-H-400/7 SEE NOTE A-1 LONGITUDINAL SEAM PT-H-600/2 WELD EXTENDING UPSTREAM B9.11 B-J NUREG-0313C 1831-1RC-288-14 A-158/OO UT-H-400/7 87 X 22-H
- VALVE TO ELBOW PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD B9.12 B-J NUREG-0313A 1831-1RC-288-14LD-I A-15B/OO UT-H-400/7 X SEE NOTE A-1 LONGITUDINAL WELD PT-H-600/2 22-H DOWNSTREAM ON INSIDE OF ELBOW
INFORMATION SERVICES-CIRMINGHAM
~
EDWIN I. HATCH NUCLEAR PLANT - UNIT 1 NURE2-C313, EEV. 2 PAGE 28 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS .-
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCZD./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.12 B-J NUREG-0313A IB31-fr.C-288-14LD-O A-15B/OO UT-H-400/7 X SEE NOTE A-1 LONGITUDIN?.L WELD PT-H-600/2 22-H DOWNSTREAM ON DUTSIDE OF ELBOW B9.11 B-J NUREG-0313C 1B31-1RC-28B-15 A-158/OO UT-H-400/7 87 X 22-H
- ELBOW TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.31 B-J NUREG-0313C 1831-1RC-288-15BC A-15B/OO UT-H-400/7 X X 22-H
+ PIPE TO BC PT-H-600/2 EXAMINE 1988 DUTAGE AND IMSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 89.12 B-J NUREG-0313A 1831-1RC-288-15LD A-158/OO UT-H-400/7 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING DOWNSTP.EAM 89.12 B-J NUREG-0313A 1831-1RC-288-15LU-I A-158/OO U T- H-400/ 7 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 22-H m UPSTREAM ON INSIDE 7
w 0F ELBOW C3 89.12 B-J NUREG-0313A 1831-1RC-28B-15LU-O A-158/OO UT-H-400/7 X SEE NOTE A-1.
~
LONGITUDINAL WELD PT-H-600/2 22-H UPSTREAM ON OUTSIDE OF ELBOW B9.11 B-J NUREG-0313E 1831-1RC-28B-16 A-158/OO UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
- PIPE TO TEE PT-H-600/2 BASE MATERIAL ON EACH 1986 OVERLAY SIDE. EXAMINE EVERY 2ND QUTAGE. 134-H 89.12 B-J NUREG-0313A 1B31-1RC-288-16LU A-15B/OO OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF ?88 16.
WELD EXTENDING UPSTREAM B9.11 B-J NUREG-0313C 1831-1RC-288-17 A-15B/OO UT-H-400/7 87 X 28-SS-X-2.30-92-H l
- TEE TO CROSS PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD B9.11 B-J NUREG-0313C 1B31-1RC-288-18 A-15B/OO UT-H-400/7 87 X 28-SS-X-2.30-92-H
- CROSS TO REDUCER PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD l
t
~
EDWIN I. HATCH NUCLEAR PLANT - UNIT 1. NURE2-C313. KEV. 2 PAGE 29 (FOR INFORMATION ONLY) .
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS -
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATIDN NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK B9.11 B-J NUREG-0313C 1E11-1RHR-208-D-1 A-23/02 UT-H-400/7 87 X 21-H
- TEE TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.31 B-J NUREG-0313C 1E11-1RHR-208-D-1BC A-23/02 UT-H-400/7 87 X 21-H
j IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD
~
89.12 8-J NUREG-0313A 1E11-1RHR-208-D-1LD A-23"O2 UT-H-400/7 E7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 21-H WELD EXTENDING DOWNSTREAM B9.11 B-J NUREG-031'C J 1E11-1RHR-2OB-D-2 A-23/02 UT-H-400/7 87 X 21-H
- PIPE TO ELBOW PT-H-600/2 EXAMINED 1987 R3.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD B9.12 B-J NUREG-0313A 1E11-1RHR-208-D-2LD-I A-23/02 UT-H-400/7 87 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 21-H
[]
e DOWNSTREAM DN INSIDE OF ELBOW w
~
89.12 B-J NUREG-0313A 1E11-1RHR-208-D-2LD-O A-23/02 UT-H-400/7 87 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 21-H DOWNSTREAM ON OUTSIDE OF ELBOW 89.12 B-J NUREG-0313A 1E11-1RHR-208-D-2LU A-23/02 JT-H-400/7 87 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 21-H WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313E 1E11-1RHR-208-D-3 A-23/02 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
- ELBOW TO PIPE PT-H-SOO/2 BASE MATERIAL ON EACH 82 OVERLAY /86 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1E11-1RHR-208-D-3LD A-23/02 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF D-3 WELD EXTENDING DOWNSTREAM B9.12 B-J NUREG-03t3A c11-1RHR-208-D-3LU-I A-23/02 OVERLAYED. EXAMINE AS LONGITUDINAL WELD PAetT OF D-3 UPSTREAM ON INSIDE OF ELBOW
INFORMATION SERVICES-CIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1, NURE2-C313, CEV. 2 PAGE 30 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATIDN FIGURE EXAMINATIDN FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATIDN BLDCK .*
B9.12 B-J NUREG-0313A 1E11-1RHR-208-D-3LU-0 A-23/02 OVERLAYED. EXAMINE AS UPSTREAM PART OF D-3 LONGITUDINAL WELD ON OUTSIDE OF ELBOW 89.11 B-J NUREG-0313F 1E11-1RHR-208-D-4 A-23/02 UT-H-4SO/7 87 X X EXAMINE 4 OUTAGES IN A
- PIPE TO PIPE PT-H-600/2 ROW STARTING IN 1987.
IHSI 1985/1986 RO IF UNCHANGED RECLASSIFY AS CATEGORY E. 21-H 89.12 B-J NUREG-0313A 1E11-1RHR-208-D-4LD A-23/02 UT-H-400/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 21-H WELD EXTENDING DOWNSTREAM 89.12 B-J NUREG-0313A 1E11-1RHR-208-D-4LU A-23/02 UT-H-400/7 87 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 21-H WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313C 1E11-1RHR-208-D-5 A-23/02 UT-H-400/7 X X 21-H
29.12 B-J NUREG-0313A 1E11-1RHR-208-D-5LU A-23/02 UT-H-490/7 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 21-H WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313C 1E11-1RHR-24A-R-12 A-21/03 UT-H-400/7 X X 22-H
- VALVE TO PIPE PT-H-600/2 EXAMINE 1988 OUTAGE AND DIS. METAL SHOP WELD RE-EXAMINE 3RD PERIOD IHSI 1985/1986 RO 89.11 B-J NUREG-0313E 1E11-1RHR-24A-R-13 A-21/03 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH
+ PIPE TO PIPE PT-H-SOO/2 BASE MATERIAL DN EACH 84 OVERLAY /86 RESURF SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1E11-1RHR-24A-R-13LD A-21/03 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF R-13 WELD EXTENDING DOWNSTREAM B9.11 B-J NUREG-0313C 1E11-1RHR-24A-R-14 A-21/03 UT-H-400/7 87 X 22-H_
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD I
INFORMATION SERVICES-BIRMINGHAM 4
EDWIN I. HATCH MJCLEAR PLANT - UNIT 1. MJRE3-C313 CEV. 2 PAGE 31 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS .
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./ REY PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.12 B-J NUREG-0313A 1E11-1RHR-24A-R-14LU A-21/03 UT-H-400/7 87 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-H WELD EXTENDING UPSTREAM 89.11 E-J NUREG-0313E 1E11-1RHR-248-R-12 A-22/03 UT-H-403/1 87 X X PT OVERLAY AND 1 INCH
- VALVE TO PIPE PT-H-600/2 BASE MATERIAL ON EACH 1986 OVERLAY SIDE. EXAMINE EVERY 2ND OUTAGE. 135-H 89.11 8-J NUREG-0313E 1E11-1RHR-248-R-13 A-22/03 UT-H-408/1 X X X PT OVERLAY AND 1 INCH
- PIPE TO PIPE PT-H-600/2 BASE MATERIAL ON EACH 82 OVERLAY /86 RESURF SIDE. EXAMINE 1988 THEN EVERY 2ND OUTAGE. 134-H 89.12 B-J NUREG-0313A 1E11-1RHR-248-R-13LD A-22/03 OVERLAYED. EXAMINE AS LONGITUDINAL SEAM PART OF R-13 WELD EXTENDING DOWNSTREAM 89.11 8-J NUREG-0313C 1E11-1RHR-248-R-14 A-22/03 UT-H-400/7 X X 22-H f m
- PIPE TO TEE PT-H-SOO/2 EXAMINE 1988 OUTAGE AND to IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 1-W B9.12 8-J NUREG-0313A 1E11-1RHR-248-R-14LU A-22/03 UT-H-400/7 X SEE NOTE A-1.
1 LONGITUDINAL SEAM PT-H-600/2 22-H i
WELD EXTENDING UPSTREAM 4
L i
3.-______
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH FAJCLEAR PLANT - UNIT 1. NURE2-C313, C.EV. 2 PAGE 32 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS .
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK
- B5.50 B-F NUREG-0313D 1E21-1CS-10A-18A A-28/03 UT-H-400/7 87 X X EXAMINE 1988 RO AND
- PIPE TO SAFE-END PT-H-600/2 RE-EXAMINE EVERY 2ND EXTENSION OUTAGE. 10-H, 18-H 89.11 B-J NUREG-0313D 1E21-1CS-10A-19A A-26/03 UT-H-400/7 87 X X EXAMINE 1988 RO AND
- SAFE-END EXTENSION PT-H-600/2 RE-EXAMINE EVERY 2ND TO SAFE-END OUTAGE. 85-H B5.10 B-F NUREG-03130 1E21-1CS-10A-20A A-26/03 UT-H-400/7 87 X X EXAMINE 1988 RO ANO
- SAFE-END TO NOZZLE PT-H-600/2 RE-EXAMINE EVERY 2ND OUTAGE. 85-H, 108-H B5.50 B-F NUREG-03130 1E21-1CS-108-19A A-27/03 UT-H-400/7 87 X X STARTING IN 1987
- PIPE 10 SAFE-END PT-H-600/2 EXAMINE EVERY 2ND EXTENSION OUTAGE. 10-H, 18-H 89.11 8-J NUREG-03130 1E21-1CS-108-20A A-27/03 UT-H-400/7 87 X X STARTING IN 1987
- SAFE-END EXTENSION PT-H-600/2 EXAMINE EVERY 2ND F1 TO SAFE-END OUTAGE. 85-H Y
w 2r B5.10 B-F NUREG-03130 1E21-1CS-108-21A A-27/03 UT-H-400/7 87 X X STARTING IN 1987
- SAFE-END TO NOZZLE PT-H-600/2 EXAMINE EVERY 2ND DUTAGE. 85-H, 108-H l
l
INFORMATION SERVICES-IIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1, NURE2-C313, EEV. 2 PAGE 33 (FOR INFORMATION ONLY)
ASMI ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS .
ITM h0. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCEO./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK .
89.11 B-J NUREG-0313C 1G31-1RWCU-6-D-1 A-32/03 UT-H-400/7 87 X 2-H
- B-C TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD B9.11 8-J NUREG-0313C 1G31-1RWCU-6-D-2 A-32/03 UT-H-400/7 87 X 2-H e PIPE TO ELBOW PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PFRIOD 89.11 B-J NUREG-0313C 1G31-1RWCU-6-D-3 A-32/03 UT-H-400/7 87 X 2-H
- ELBOW TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.11 B-J NUREG-0313E 1G31-1RWCU-6-D-4 A-32/03 UT-H-408/1 87 X X PT OVERLAY AND 1 INCH e PIPE TO VALVE PT-H-600/2 BASE MATERIAL ON EACH 1986 OVERLAY SIDE. EXAMINE EVERY 2ND OUTAGE. 134-H 89.11 B-J NUREG-0313E 1G31-1RWCU-6-D-5 A-32/03 UT-H-400/7 87 X X PT OVERLAY AND 1 INCH
[]
- VALVE TO ELBOW 1986 OVERLAY PT-H-600/2 BASE MATERIAL ON EACH e SIDE. EXAMINE EVERY 2ND (y OUTAGE. 134-H 89.11 B-J NUREG-0313F 1G31-1RWCU-6-D-6 A-32/03 PT-H-600/2 87 TEMP MANUAL OVERLAY
- ELBOW TO PIPE 1987. TO BE REPLACED TEMP OVERLAY OR FULL STRUCTURAL OVERLAY APPLIED.
89.11 B-J NUREG-0313C 1G31-1RWCU-6-D-7 A-32/02 UT-H-400/7 87 X 2-H PIPE TO ELBOW PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.11 B-J NUREG-0313C 1G31-1RWCU-6-D-8 A-32/03 UT-H-400/7 87 X 2-H
- ELBOW TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD B9 11 B-J NUREG-0313C 1G31-1RWCU-6-D-9 A-32/03 UT-H-400/7 87 X 2-H
- PIPE TO ELBOW PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD 89.11 8-J NUREG-03:3C 1G31-1RWCU-6-D-10 A-32/03 UT-H-400/7 87 X 2-H
- ELBOW TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD e
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 1, NURE2-C313, CEV. 2 PAGE 33 (FOR INFOf"(ATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS -
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK B9.11 B-J NUREG-0313C 1G31-1RWCU-6-D-11 A-32/03 UT-H-400/7 87 X 2-H
- PIPE TO ELBOW PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1956 RO RE-EXAMINE 2ND PERIOD B9.11 B-J NUREG-0313C 1G31-125CU-6-D-12 A-32/03 UT-H-400/7 87 X 2-H
- ELBOW TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RE-EXAMINE 2ND F ERIOD B9.11 B-J NUREG-0313C 1G31-1RWCU-6-D-13 A-32/03 UT-H-400/7 87 X 2-H
- PIPE TO ELBOW PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 2ND PERIOD 89.11 B-J NUREG-0313F 1G31-1RWCU-6-D-14 A-32/03 PT-H-600/2 87 TEMP MANUAL OVERLAY
- ELBOW TO VALVE 1987. TO BE REPLACED TEMP OVERLAY OR FULL STRUCTURAL OVERLAY APPLIED.
ni B9.11 B-J NUREG-0313C 1G31-1RWCU-6-D-15A A-32/03 UT-H-400/7 87 X 2-H ha e VALVE TO PIPE PT-H-600/2 EXAMINED 1987 RO.
!HSI 1985/1986 00 RE-EXAMINE 3RD PERIOD 89.11 B-J NUREG-0313A 1G31-1RWCU-6-D-15B A-32/03 304L TO 304L WELD PIPE TO PIPE LOCATED IN PENETRATION SEE RR 2.1.7 B9.11 B-J NUREG-0313A 1G31-1RWCU-6-D-15C A-32/03 CORROSION RESISTANT PIPE TO FLUED HEAD CLAD (308L) FLUED HEAD TO 304L PIPE B9.11 B-J NUREG-0313C 1G31-1RWCU-6-D-16 A-32/03 UT-H-400/7 87 X 2-H
- FLUED HEAD TO PIPE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD B9.11 B-J NUREG-0313F 1G31-1RWCU-6-D-17 A-32/02 PT-H-600/2 87 TEMP MANUAL OVERLAY
= PIPE TO ELBOW 1987. TO BE REPLACED TEMP UVERLAY OR FULL STRUCTURAL OVERLAY APPLIED.
89.11 B-J NUREG-0313E 1G31-1RWCU-6-D-18 A-32/02 UT-H-408/1 X X X PT OVERLAY AND 1 IACH e ELBOW TO PIPE PT-H-600/2 BASE MATERIAL ON EACH 1946 OVERLAY SIDE. EXAMINE 1988 THEN EVERY 2ND OUTAGE.
EDWIN I. HATCH NUCLEAR PLANT - UNIT 1, NURE2-C313, CEV. 2 PAGE 35-(FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOO PERIOD PERIOD CALIBRATION BLOCK 89.11 8-J NUREG-0313E 1G31-1RWCU-6-D-18A A-32/02 UT-H-408/1 X X X PT OVERLAY AND 1 INCH
- PIPE TO PIPE PT-H-600/2 BASE MATERIAL ON EACH 19>,6 OVERLAY SIDE. EXAMINE 1988 THEN EVERY 2fe OUTAGE.
89.11 8-J NUREG-0313C 1G31-1RWCU-6-D-19 A-32/02 UT-H-400/7 87 X 2-H
- PIPE TO EL80W PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RF-EXAMINE 3RD PERIOD 89.11 8-J NUREG-0313C 1G31-1RWCU-6-D-20 A-32/02 UT-H-400/7 87 X 2-H
- EL80W TO VALVE PT-H-600/2 EXAMINED 1987 RO.
IHSI 1985/1986 RO RE-EXAMINE 3RD PERIOD C
w
D ENCLOSURE 3 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366
. OPERATING LICENSES-DPR-57, NPF-5 GEORGIA POWER COMPANY RESPONSE TO G.L. 88-01 UNIT 2 LONG-TERM EXAM SCHEDULE i-06440 SL-4489 E3-1 June 30,1988 l
l
d -
o-ENCLOSURE 3 NOTES Notes: (1) Note A-1 was referred to -in "Comments" column and pertains to size of examination a*ea (2) Note A-2 pertains to exam Leing'done Pre-and Post-IHSI (3) Note A-6 specifies that these exams not required by code or.NUREG listed for completeness only (4) This enclosure is extracted from the Hatch Unit 2 ISI Long-Ter.n Plan which is updated periodically to assure it remains current. This onclosure will not be resubmitted as a result of those revisions.
(5) The asterick (*) under "Exam Req" is used for computer sorting purposes only.
l l
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l 0644D SL-4489 E3-2 June 30,1988 i
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INFORMATION SERVICES-BIRMINGHAM
~
EDWIN I. HATCH NUCLEAR PLANT - UNIT 2, NURE2-C313. [EV. 2 PAGE 1 (FDR INFORMATIDN ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINfTION FIRST SECDND THIRD REMARKS ,
ITM ND. CAT. REQUIREMENT AREA IDENTIFICATIDN ND./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATIDN BLDCK NUREG-0313D 2N2A -
UT-H-415/2 86 X X RINTSA-125-H e RINTSA WELD EXAMINE NEXT RO AND THEN EVERY 2ND DUTAGE NUREG-03130 2N28 -
UT-H-415/2 86 X X RINTSA-125-H
- RINTSA WELD EXAMINE NEXT RO AND THEN EVERY 2ND OUTAGE NUREG-0313D 2N2C -
UT-H-415/2 86 X X RINTSA-125-H
- RINTSA WELD EXAMINE NEXT RO AND THEN EVERY 2ND ruTAGE NUREG-0313D 2N2D -
UT-H-415/2 86 X X RINTSA-125-H e RINTSA WELD EXAMINE NEXT RO AND THEN EVERY 2ND DUTAGE NUREG-0313D 2N2E -
UT-H-415/2 86 X X RINTSA-125-H e RINTSA WELD EXAMINE NEXT RO AND THEN EVERY 2ND DUTAGE O.
Ad -- --
NUREG-0313D 2N2F -
UT-H-415/2 88 X X RINTSA-125-H
- RINTSA WELD EXAMINE EVERY 2ND DUTAGE NUREG-0313D 2N2G -
UT-H-415/2 88 X X RINTSA-125-H
- RINTSA WELD EXAMINE EVERY 2ND DUTAGE NUREG-0313D 2N2H -
UT-H-415/2 88 X X RINTSA-125-H
- RINTSA WELD EXAMINE EVERY 2ND DUTAGE NUREG-0313D 2N2J -
UT-H-413/2 E8 X X RINTSA-125-H e RINTSA WELD EXAMINE EVERY 2ND DUTAGE NUREG-03130 2N2K -
UT-H-415/2 88 X X RINTSA-125-H e RINTSA WELD EXAMINC EVERY 2ND DUTAGE
EDWIN I. HATCH NUCLEAR PLANT - LA3T 2, NURE2-C313, 7.EV. 2 PME 2 -
(FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCEO./RLV PERIOD PERIOD PERIOD CALIBRATION DLOCK .*
85.50 8-F NUREG-0313D 2821-1FW-12AA-8 A-10/03 UT-H-409/3 86 X X EXAMINE 1989 RO, THE
- TRANSITION PIECE TO PT-H-600/2 NEXT RO AND THEN SAFE-END EXTENSION EVERY 2ND RO 70-H,78-H (NOTE A-3) 89.11 B-J NUREG-0313D 2821-1FW-12AA-9 A-10/03 UT-H-400/7 86 X X XAMINE 1989 RO, THti
- SAFE-ENO EXTENSION PT-H-600/2 TXT RO, AND THEN TO SAFE-END FIERY 2ND RO 7 3-H (NOTE A-3) 85.50 8-F NUREG-03130 2821-1FW-12AA-10 A-10/03 UT-H-409/3 86 .X X JXAMINE 1989 RO. THE
B5.50 B-F NUREG-0313D 2821-1FW-12AB-11 A-10/03 UT-H-409/3 86 X X EXAMINE 1989 RO, THE
- TRANSITION PIECE TO PT-H-600/2 NEXT RO, AND THEN SAFE-END EXTENSION EVERY 2ND RO 70-H,78-H (NOTE A-3) i 89.11 B-J NUREG-03130 2821-1FW-12A8-12 A-10/03 UT-H-400/7 86 X X EXAMINE 1989 RO, THE
T 85.50 B-F NUREG-0313D 2821-1FW-12A8-13 A-10/03 UT-H-409/3 86 X X EXAMINE 1989 RO, THE t J:-
' NUREG-0313D 2821-1FW-12BC-11 B5.50 8-F A-11/04 UT-H-409/3 86 X X EXAMINE 1989 RO AND e TRANSITION PIECE TO PT-H-SOO/2 THEN EVERY 2ND RO SAFE-END EXTENSION 70-H,78-H (NOTE A-3) 89.11 8-J NUREG-0313D 2821-1FW-12BC-12 A-11/04 UT-H-400/7 86 X X EXAMINE 1989 RO ANO e SAFE-END EXTENNSION PT-H-600/2 THEN EVERY 2ND RO TO SAFE-END 78-H (NOTE A-3) 85.50 8-F NUrtEG-0313D 2821-1FW-128C-13 A-11/04 UT-H-409/3 86 X X EXAMINE 1989 RO AND
- SAFE-END TO PT-H-600/2 THEN EVERY 2ND RO TRANSITION PIECE 78-H,53-H (NOTE A-3) 85.50 8-F NUREG-0313D 2821-1FW-12BD-8 A-11/04 UT-H-409/3 86 X X EXAMINE 1989 RO AND e TRANSITION PIECE TO PT-H-600/2 THEN EVERY 2ND RO SAFE-ENO EXTENSION 70-H,78-H (NOTE A-3)
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 2, NURE3-C313. REV. 2 PAGE 3 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATIDN FIRST SECOND THIRD REMARKS ,
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION ND./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION SLDCK BQ.11 B-v NUREG-0313D 2B21-1FW-12BD-9 A-11/04 UT-H-400/7 86 X X EXAMINE 1989 RO ANO
- SAFE-END EXTENSION PT-H-600/2 THEN EVERY 2ND RO TO SAFE-END 78-H (NOTE A-3) 55.50 B-F NUREG-0313D 2B21-1FW-1?GD-10 A-11/04 UT-H-409/3 86 X X EXAMINE 1989 RO ANO
- SAFE-END TO PT-H-600/2 THEN EVERY 2ND RO TRANSITION PIECE 78-H,53-H (NOTE A-3) 85.10 B-F NUREG-03130 2831-1RC-4JP-A-1 A-37/OO UT-H-409/3 88 X X 5.437-SS-X-0.813-121-H
- N0ZZLE 2N8A TO PT-H-600/2 EXAMINE EVERY 2ND RO S AF E-END STARTIEG WITH 1988 RO 89.11 B-J NUREG-0313D 2531-1RC-4JP-A-2 A-37/OO UT-H-401/6 88 X X 4-SS-80-0.337-80-H
- SAFE-END TO PT-H-SOO/2 EXAMINE EVERY 2ND RO PENETRATION SEAL STARTING WITH 1988 RO B5.10 B-F NUREG-03130 2831-1RC-4JP-B-1 A-37/OO UT-H-409/3 88 X X 5.437-SS-X-0.813-121-H
ra sb B9.11 3-J NUREG-03130 2831-1RC-4JP-B-2 A-37/OO UT-H-401/6 88 X X 4-SS-80-0.337-80-H e SAFE-END TO PT-H-600/2 EXAMINE EVERY 2NO RO PENETRATION SEAL STARTING WITH 1988 RO B5.10 B-F NUREG-0313C 2831-1RC-12AR-F-5 A-14/02 UT-H-400/7 88 X 12-SS-X-1.2OO-85-H
- S-E TO NOZZLE 2N2F PT-H-600/2 EXAMINE NE.NT OUTAGE.
IHSI 1986 9E-EXAMINE 3RD PERIOD B5.10 B-F NUREG-0313C 2831-1RC-12AR-G-5 A-14/02 UT-H-400/7 86 X 12-SS-X-1.2OO-85-H
- S-E TO N0ZZLE 2N2G PT-H-600/2 EXAMINE NEXT DUTAGE.
IHSI 1986 RE-EXAMINE 3RD PERIOD B5.10 B-F NUREG-0313C 2831-1RC-12AR-H-5 A-14/02 UT-H-400/7 88 X 12-SS-X-1.2OO-85-H
- S-E TO N0ZZLE 2N2H PT-H-600/2 EXAMINE NEXT DUTAGE.
IHSI 1986 RE-EXAMINE 3RD PERIOD B5.10 B-F NUREG-0313C 2831-1RC-12AR-J-5 A-14/02 UT-H-400/7 86 X 12-SS-X-1.2OO-85-H
- S-E TO N0ZZLE 2N2J PT-H-600/2 EXAMINE NEXT OUTAGE.
IHSI 1986 RE-EXAMINE 3RD PERIOD
.e - _ _ . - . - _ -
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 2, NURE3-0313 REV. 2 PAGE O (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATIDK NO./REV PRDCEP./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK B5.10 B-F NUREG-0313C 2831-1RC-12AR-K-5 A-14/02 UT-H-400/7 86 X 12-SS-X-1.2OO-85-H
- S-E TO N0ZZLE 2N2K PT-H-600/2 EXAMINE NEXT GUTAGE.
IHSI 1986 RE-EXAMINE 3RD PERIOD B5.10 B-F NUR[G-0313C 2B31-1RC-12BR-A-5 A-15/02 UT-H-400/7 86 X 12-SS-X-1.2OO-85-H
- S-E TO N0Z7LE 2N2A PT-H-600/2 EXAMINE NEXT OUTAGE IHSI 1986 RE-EXAMINE 2ND PERIOD B5.10 B-F NUREG-0313C 2831-1RC-12BR-B-5 A-15/02 UT-H-400/7 36 X 12-SS-X-1.2OO-85-H
- S-E TO NOZZLE 2N2B PT-H-600/2 EXAMINE NEXT OUTAGE IHSI 1986 RE-EXAM 1HE 2ND PERIOD B5.10 B-F NUREG-0313C 2B31-1RC-129R-C-5 A-15/02 UT-H-4DO/7 86 Y 12-SS-X-1.2OO-85-H
- S-E TO N0ZZLE 2N2C PT-H-600/2 EXAMINE NEXT OUTAGE IHSI 1986 RE-SXAMINE 2ND PERIOD B5.10 B-F NUREG-0313C 2831-1RC-12BR-D-5 A-15/02 UT-H-400/7 86 X 12-SS-X-1.2OO-85-H
- S-E TO N0ZZLE 2N2D PT-H-600,'2 EXAMINE NEXT OUTAGE IHSI 1986 RE-EXAMINE 2ND PERIOD
[] B5.10 B-F NUREG-0313C 2831-1RC-12BR-E-5
- S-E TO N0ZZLE 2N2E A-15/02 UT-H-400/7 PT-H-600/2 86 X 12-SS-X-1.2OO-85-H EXAMINE NEXT OUTAGE C' IHSI 1986 RE-EXAMINE 2ND PERIOD B5.10 B-F NUREG-0313C 2831-1RC-28A-1 A-16/03 UT-H-400/7 88 X 29-H. 84-H
- N0ZZLE 2N1A TO S-E PT-H-600/2 EXAMINE NEXT OUTAGE IHSI 1988 RE-EXAMINE 3RD PERIOD B5.10 B-F NUREG-0313C 2B31-1RC-285-1 A-18/03 UT-H-400/7 86 X 29-H. 84-H
- N0ZZLE 2N1B TO S-E PT-H-SOO/2 EXAMINE NEXT OUTAGE IHSI 1986 RE-EXAMINE 2ND PERIOD B9.11 B-J NUREG-0313A 2831-1RCM-12AF-1 A-14/02 UT-H-401/6 X 12-SS-0.792-132-H MANIFOLD TO PIPE PT-H-600/2 B9.12 B-J NUREG-0313A 2831-1RCM-12AF-1LD A-14/02 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM
INFORMATION SERVICES-BIRMINGHAM
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EDWIN I. HATCH NUCLEAR PLANT - UNIT 2, NURE2-C313, CEV. 2 PAGE 5 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRO REMARKS
- ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIDO PERIDO CALIBRATION BLOCK 89.12 E-J NUREG-0313A 2831-1RCM-12AF-1LU A-14/02 UT-H-401/8 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 22-SS-1.75-129-H WELD EXTENDING 12-SS-0.792-131-H UPSTREAM 89.11 8-J NUREG-0313A 2831-1RCM-12AF-2 A-14/02 UT-H-401/6 12-SS-0.792-132-H PIPE TO PIPE PT-H-600/2 89.12 B-J NUREG-0313A 2831-1RCM-12AF-2LD A-14/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H 600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM 89.12 8-J NUREG-0311A 2831-1RCM-12AF-2LU A-14/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 12-SS-0.792-132-H WELD EXTENDING UPSTREAM 89.11 8-J NUREG-0313C 2831-1RCM-12AF-J A-14/02 UT-H-401/6 88 12-SS-0.792-132-H 91PE TO SAFE-END PT-H-600/2 EXAMS CONLPldTE FOR 10-YEAR INT!?VALL
[S 89.12 8-J NUREG-0313A 2831-1RCM-12AF-3LU A-14/02 UT-H-401/6 88 SEE NOTE A-1.
' LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H
,a WELD EXTENDING EXAMS COMPLETE FOR UPSTREAM 10-YEAR INTERVAL 89.11 8-J NUREG-0313A 2831-1RCM-12AG-1 A-14/02 UT-H-401/6 X 12-SS-0.792-132-H MANIFOLD TO PIPE PT-H-SOO/2 89.12 5-J NUREG-0313A 2831-1RCM-12AG-1LD A-14/02 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM 89.11 8-J NUREG-0313C 2831-1RCM-12AG-2 A-14/02 UT-H-401/6 88 12-SS-0.792-132-H PIPE TO SAFE-END PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL 89.12 8-J NUREG-0313A 2831-1RCM-12AG-2LU A-14/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-SOO/2 17-SS-0.792-132-H WELD EXTENOING UPSTREAM l
l 1
EDWIN I . HATCH NUCLEAR PLANT - UNIT 2. PAJRE2-C313, REV. 2 PAGE O (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAJ41 NATION FIRST SECOND THIRD REMARKS .
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOO PERIOD PERIDO CALIBRATION BLOCK '
89.11 8-J NUREG-0313A 2831-1RCM-12AH-1 A-14/02 UT-H-401/6 12-SS-0.792-132-H CROSS TO PIPE PT-H-600/2 89.11 8-J NUREG-0313A 2831-1RCM-12AH-1LD A-14/02 UT-H-401/6 SEE NOTE A-1.
LONRITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM 89.12 8-J NUREG-0313A 2831-1RCM-12AH-1LU A-14/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.75-129-H WELD ?"T*NDING 12-SS-0.792-132-H UPSTRta' 89.11 8-J NUREG-0313C 2831-1RCM-12AH-2 A-14/02 UT-H-401/6 88 12-SS-0.732-132-H PIPE TO SAFE-END PT-H-600/2 EXAMS COMPLETE FOR iO-YEAR INTERVAL 85.12 8-J NUREG-0313A 2831-1RCM-12AH-2LU A-14/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H m WELD EXTENDING y UPSTREAM 89.11 8-J NUREG-0313A 2831-1RCM-12AJ-1 A-s4/02 UT-H-401/6 12-SS-0.792-132-H MANIFOLD TO PIPE PT-rl-600/2 89.12 8-J NUkEG-0313A 2831-1RCM-12AJ-1LD A-14/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM 89.11 8-J NURsG-0313C 2831-1RCM-12AJ-2 A-14/02 UT-H-401/8 88 12-SS-0.792-132-H PIPE TO SAFE-END PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL 89.12 8-J PAJREG-0313A 2831-1RCM-12AJ-2LU A-14/02 UT-H-401/6 88 SEE NOTE A-1.
LONGITUOINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING EXAMS COMPLETE FOR UPSTREAM 10-YEAR INTERVAL 89.11 8-J NUREG-0313A 2931-1RCM-12AK-1 A-14/02 UT-H-401/6 12-SS-0.792-132-H MANIFOLD TO PIPE PT-H-600/2 x
e
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 2, NUREL-C313, CEV. 2 PAGE 7 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS -
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATIDN NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATIDN BLDCK B9.12 B-J NUREG-0313A 753s-1RCM-12AK-1LD A-14/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM B9.12 B-J NUREG-0313A 2B31-1RCM-12AK-1LU A-14/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.75-129-H WELD EXTENDING 12-SS-0.792-132-H UPSTREAM 89.11 B-J NUREG-0313A 2831-1RCM-12AK-2 A-14/02 UT-H-401/6 X 12-SS-0.792-132-H PIPE TO PIPE PT-H-600/2 B9.12 B-J NUREG-0313A 2831-1RCM-12AK-2LD A-14/02 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM B9.12 B-J NUREG-0313A 2831-1RCM-12AK-2LU A-14/02 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING m UPSTREAM w
a
'O 89.11 B-J NUREG-0313C 2831-1RCM-12AK-3 A-14/02 UT-H-401/6 88 12-SS-0.792-132-H PIPE TO SAFE-END PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2831-1RCM-12AK-3LU A-14/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING UPSTREAM B9.11 D-J NUREG-0313A 2B31-1RCM-12BA-1 A-15/02 UT-H-401/6 X 12-SS-0.792-132-H MANIFOLO TO PIPE PT-H-SOO/2 89.12 B-J NUREG-0313A 2831-1RCM-12Bk-1LD A-15/02 UT-H-401/6 X SEE NOTE A-1.
LONGITUCINAl SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTiNP4NG DOWNSTREt*,
B9.12 B-J NUREG-0313A 2831-1RCM-12BA-1LU A-15/02 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.75-129-H WELD EXTENDING 12-SS-0.792-132-H UPSTREAM
(
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 2, NURE3-C313, CEV. 2 PAGE 8 (FOR INrJRMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECONO THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PERIOD PERIOD PROCED./REV PERIOD CALIBRATION BLOCK B9.11 B-J NUREG-0313A 2B31-1RCM-12BA-2 A-15/02 UT H-401/6 X 12-SS-0.792-132-H PIPE TO PIPE PT-H-600/2 B9.12 B-J NUREG-0313A 2831-1RCM-12BA-2LD A-15/02 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM 89.12 B-J NUREG-0313A 2831-1RCM-12BA-2LU A-15/02 UT-H-401/6 X SEE NOTE A-1.
BONGITUOINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING UPSTREAM B9.11 B-J NUREG-0313C 2831-1RCM-12BA-3 A-15/02 UT-H-401/6 88 12-SS-0.792-132-H PIPE TO SAFE-END PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL 89.12 B-J NUREG-0313A 2831-1RCM-12BA-3LU A-15/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.7S2-132-H m WELD EXTENDING ta UPSTREAM I
2] B9.11 B-J NUREG-0313A 2931-1RCM-12BB-1 A-15/02 UT-H-401/6 12-SS-0.792-132-H MANIFOLD TO PIPE PT-H-600/2 B9.12 B-J NUREG-0113A 2B31-1RCM-12BB-1LD A-15/02 UT-H-401/6 SEE NOTE A-1.
LDNGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM 89.11 B-J NUREG-0313C 2831-1RCM-12BB-2 A-15/02 UT-H-401/6 88 12-SS-0.792-132-N PIPE TO SAFE-END PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2831-1RCM-12BB-2LU A-15/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 12-SF-0.792-132-H WELD EXT [NDING UPSTREAM 89.11 B-J NUREG-0313A 2E31-1RCM-12BC-1 A-15/02 UT-H-401/6 12-SS-0.792-132-H CROSS TO PIPE PT-H-600/2
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 2, NURE3-C313, REV. 2 PAGE 9 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS -*
ITM NO. CAT. REOUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.12 B-J NUREG-0313A 2831-1RCM-123C-1LD A-15/02 UT-H-#01/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM B9.12 B-J NUREG-0312A 2831-1RCM-12BC-1LU A-15/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.75-129-H WELD EXTENDING 12-SS-0.792-132-H UPSTREAM 89.11 B-J NUREG-0313C 2831-1RCM-12BC-2 A-15/02 UT-H-401/6 88 12-55-0.792-132-H PIPE TO SAFE-END PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2831-1RCM-12BC-2LU A-15/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING U) STREAM B9.11 B-J NUREG-0313A 2831-1RCM-12BD-1 A-15/02 UT-H-401/6 12-SS-0.792-132-H MANIFOLD TO PIFE PT-H-600/2 m
89.12 B-J NUREG-0313A 2831-1RCM-12BD-1LD A-15/02 IAT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM 'T-H-SOO/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM B9.11 0-J NUREG-0313C 2831-1RCM-12BD-2 A-15/02 UT-H-401/8 88 12-SS-0.792-132-H PIPE TO SAFE-END PT-h-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2831-1RCM-12BD-2LU A-15/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132 't WELD EXTENDING UPSTREAM B9.11 B-J NUREG-0313A 2831-1RCM-12BE-1 A-15/02 UT-H-401/6 X 12-SS-0.792-132-H MANIFOLD TO PIPE PT-H-600/2 B9.12 B-J NUREG-0313A 2831-1RCM-12BE-1LD A-15/02 UT-H-401/8 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM
-m
INFORMATION SERVICES-BIRMINGHAM
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EDWIN I. HA(CH NUCLEAR PLANT - UNIT 2. NURE3-0313. CEV. 2 PAGE 13 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ,
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.12 B-J NUREG-0313A 2831-1RCM-12BE-1LU A-15/02 UT-H-401/8 X SEE NDTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.75-129-H WELD EXTENDING 12-SS-0.792-132-H UPSTREAM B9.11 B-J NUREG-0313A 2831-1RCM-12BE-2 A-15/02 UT-H-401/6 12-SS-0.732-132-H PIPE TO PIPE PT-H-600/2 89.12 B-J NUREG-0313A 2831-13CM-12BE-2LD A-15/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-GOO /2 12-SS-0.792-132-H WELD EXTENDING DOWNSTREAM 89.12 B-J NUREG-0313A 2831-1RCM-12BE-2LU A-15/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313C 2831-1RCM-12BE-3 A-15/02 UT-H-401/6 88 12-SS-0.792-132-H ni PIPE TO SAFE-END PT-H-600/2 EXAMO COMPLETE FOR Ly 10-VEAR INTERVAL U
89.12 B-J NUREG-0313A 2831-1RCM-12BE-3LU A-15/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 12-SS-0.792-132-H WELD EXTENDING UPSTREAM B9.11 B-J NUREG-0313A 2B31-1RCM-22A-1 A-14/02 UT-H-401/6 X 22-SS-1.75-129-H CROSS TO MANIFOLD PT-H-600/2 39.12 B-J NUREG-0313A 2831-1RCM-22A-1LD A-14/02 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.75-129-H WELD EXTENDING DOWNSTREAM B9.11 B-J NUREG-0313A 2831-1RCM-22A-2 A-14/02 UT-H-401/6 22-SS-1.75-129-H CROSS TO MANIFOLD PT-H-SOO/2 89.12 B-J NUREG-0313A 2831-1RCM-22A-2LD A-14/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAN PT-H-600/2 22-SS-1.75-129-H WELD EXTENDING DOWNSTREAM
INFORMATION SERVICES-BIRMINGHAM E FDWIN I. HATCH NUCLEAR PLANT - UNIT 2, NURE3%*:313 REV. 2 PAGE 11 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS .
ITM HO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK B9.11 B-J NUREG-0313A 2531-1RCM-228-1 A-15/02 UT-H-401/6 22-SS-1.75-129-H CROSS TO MANIFOLD PT-H-600/2 B9.12 B-J NUREG-0313A 2B31-1RCM-228-1LD A-15/02 UT-H-401/6 SEE NOTE A-1.
LONGITL'DINAL SEAM PT-H-600/2 22-SS-1.75-129-H WELD EXTENDING DOWNSTREAM 89.11 B-J NUREG-0313% 2031-1RCM-22B-2 A-15/02 UT-H-401/6 22-SS-1.75-129-H CROSS TO MANIFOLD PT-H-600/2 B9.12 B-J P41HEG-0313A 2B31- 1RCM-228-2LD A-15/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.75-129-H WELD EXTENDING DOWNSTREAM B9.11 B-J NUREG-0313A 2831-1RCM-28AD-1 A-17/02 UT-H-401/6 88 22-SS-1.184-128-H PUMP TO PIPE PT-H-600/2 EXAMS COMPLETE FOR C 10-YEAR INTERVAL W NUREG-0313A 2831-1RCM-28AD-1LD B9.12 B-J A-17/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.184-128-H WELD EXTENDING DOWNSTREAM B9.11 B-J NUREG-0313A 2031-1RCM-28AD-2 A-17/02 UT-H-401/6 88 28-SS-1.184-128-H PIPE TO VALVE PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2831-1RCM-28AD-2LU A-17/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENDING UPSTHEAM B9.11 B-J NUREG-0313A 2831-1RCM-28AD-3 A-17/02 UT-H-401/6 88 28-SS-1.184-128-H VALVE TO ELBOW PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2831-1tCM-28AO-3LD-I A-17/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-SOO/2 28-SS-1.184-128-H DOWNSTREAM ON INSIDE OF ELBOW
INFORMATION SERVICES-BIRMINGHAM EDWIN I . HATCH NUCLEAR PLANT - UNIT 2. 643 RED-C313 CEV. 2 PAGE 12 (FOR INFORMATION ONLY)
ASME ASME EXAM EXANINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS .*
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIDO PERIOD PERIOD CALIBRATION BLOCK 89.12 5-J MJREG-0313A 2831-1RCM-28AD-3LD-O A-17s O2 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-SOO/2 28-SS-1.184-128-H DOWNSTREAM ON OUTSIDE OF ELBOW 89.11 8-J MJREi-0313A 2831-1RCN-28AD-4 A-17/02 UT-H-401/6 28-SS-1.184-128-H ELBOW TO PIPE PT-H-SOO/2 89.12 8-J NUREG-0313A 2831-1RCM-28AD-4LD A-17/02 UT-H-401/6 SEE NOTE A-1.
LDNGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENDING DOWNSTREAM 89.12 8-J MJREG-0313A 2831-1RCM-28AD-4LU-I A-17/02 UT-H-401/6 St'E NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON INS!!)E OF ELBOW 89.12 B-J NUREG-0313A 2831-1RCM-28AD-4LU-O A-17/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON m OUTSIDE OF ELBOW w
1 89.11 8-J NUREG-0313A 2831-1RCM-28AD-5 A-17/02 UT-H-401/6 X 28-SS-1.184-128-H J:- PIPE TO CROSS PT-H-600/2 89.12 5-J NUREG-0313A 2831-1RCM-28AD-5LD A-17/02 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.75-129-H WELD EXTENDI'4 t
DOWNSTREAM 89.12 8-J MJREG-0313A 2931-1RCM-28AD-5LU A-17/02 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM DT-H-600/2 28-SS-1.184-128-H WELD EXTENDING UPSTREAM 89.11 8-J NUREG-0313C 2831-1RCM-28AS-2 A-16/03 UT-H-101/6 88 28-SS-1.184-128-H SAFE-END TO EL80W PT-H-1A*M)/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL 89.12 5-J NUREG-0313A 2831-1RCM-28AS-2LD-I A-16/03 UT-H-401/6 88 SEE NOTE A-1. .
LDNGITUDINAL WELD PT-H-SOO/2 28-SS-1.184-128-H DOWNSTREAM ON INSIDE EXAMS COMPLETE OF ELBOW FOR 10-YEAR IP6 ERVAL t
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EDWIN I. HATCH NUCLEAR PLANT - UNIT 2. NURE3-C313. REV. 2 PAGE 13 -
(FOR INFDRMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECONO THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOO CALIBRATION BLOCK 89.12 8-J DAJREG-0313A 2831-1RCM-28AS-2LD-O A-16/03 UT-H-401/6 88 SEE NJTE A-1.
LONGITUDINAL WELD PT-H-SOO/2 28-SS-1.184-128-H DOWNSTREAM ON EXAMS COMPLETE OUTSIDE OF ELBOW FOR 10-YEAR INTERVAL 59.11 8-J NUREG-0313A 2831-1RCM-28AS-3 A-16/03 UT-H-401/6 28-SS-1.184-128-H EL80W TO PIPE PT-H-600/2 i
89.12 8-J NUREG-0313A 2831-1RCM-28AS-3LD A-16/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENDING DOWNSTREAM 89.12 5-J NUREG-0313A 2831-1RCM-28AS-3LU-I A-16/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON INSIDE OF EL8OW 89.12 5-J NUREG-0313A 2831-1RCM-28AS-3LU-O A-16/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON OUTSIDE OF EL80W m
W 89.11 8-J NUREG-0313A 2831-1RCM-28AS-4 A-16/03 UT-H-401/6 28-SS-1.184-128-H 1 PIPE TO TEE PT-II-600/2 vi 89.12 8-J NUREG-03134 2831-1RCM-28AS-4LD A-16/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 22-SS-1.75-129-H WELD EXTENDING DOWNSTREAM 89.12 8-J NUREG-0313A 2831-1RCM-28AS-4LU A-16/03 UT-H-401/6 SEE NOTE A-1, i
LONGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENDING UPSTREAM 89.11 8-J NUREG-0313A 2831-1RCM-28AS-5 A-16/03 UT-H-401/6 X 28-SS-1.184-128-H TEE TO PIPE PT-H-SOO/2 89.12 8-J NUREG-0313A 2831-1RCM-28A3-5LD A-16/03 UT-H-401/6 X SEE NOTE A-1.
- ONGITUDINAL SEAM
. PT-H-SOO/2 28-SS-1.184-128-H WELD EXTENDING DOWNSTREAM
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH MJCLEAR PLANT - UNIT 2. NURE3-C313. REV. 2 PAGE 10 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECONO THIRD REMARKS ,
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOO PERIOD CALIBRATION BLOCK 89.12 8-J MJREG-0313A 2831-1RCM-28AS-5LU A-16/03 UT-H-401/8 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.75-129-H WELD EXTENOING UPSTREAM 89.11 8-J MJREG-0313A 2831-1RCM-28AS-6 A-16/03 UT-H-401/6 28-SS-1.184-128-H PIPE TO PIPE PT-H-600/2 89.12 8-J MJREG-0313A 2831-1RCM-28AS-6LD A-16/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SIAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENDING DOWNSTREAM 89.12 B-J MJREG-0313A 2831-1RCM-28AS-6LU A-16/03 UT-H-401/6 SEE NOTE A-1.
LONGITUOINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENOING UPSTREAM B9.11 8-J NUREG-0313A 2831-1RCM-28AS-7 A-16/03 UT-H-401/6 X 28-SS-1.184-128-H PIPE TO ELBOW PT-H-600/2 EXAMS COMPLETE FOR r'1 10-YEAR INTERVAL m 89.12 8-J NUREG-0313A 2831-1RCM-28AS-7LD-I A-16/03 UT-H-401/8 X SEE NOTE A-1.
L()NGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H DOWNSTREAM ON INSIDE OF ELBOW 89.12 8-J M. REG-0313A 2831-1RCM-28 AS-7LD-O A-16/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H OOWNSTREAM ON OUTSIDE OF ELBOW 89.12 8-J NUREr. 0313A 2831-1RCM-28aS-7LU A-16/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUOINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENDING UPSTREAM 89.11 8-J NUREG-0313A 2831-1RCM-28AS-8 A-18/03 UT-H-401/6 88 28-SS-1.184-128-H ELBOW TO VALVE PT-H-6dO/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL l
I 89.12 8-J MJREG-0313A 2831-1RCM-28AS-8LU-I A-16/03 UT-H-401/6 88 SEE NOTE A-1.
l LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H
! UPSTREAM ON INSIDE EXAMS COMPLETE FOR
! OF ELBOW 10-YEAR INTERVAL l
l
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLAPT - UNIT 2, NURE3-C313. CEV. 2 PAGE 13 (FOR INFORMATION ONLYn ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS .*
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO . / RE*/ PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.12 B-J HUREG-0313A 2831-1RCM-28AS-8LU-O A-10/03 UT-H-401/6 88 SEE NOTE A-1.
l I LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON OUTSIDE EXAHS COMPLETE FOR OF ELBOW 10-YEAR INTERVAL B9.11 B-J NUREG-0313A 2831-1RCM-28AS-9 L-16/03 UT H-401/6 88 28-SS-1.184-128-H VALVE TO ELBOW PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.32 5-J NUREG-0313A 2831-1RCM-28AS-9BC-2 A-16/03 PT-H-600/2 X PIPE TO BC 89.12 B-J NUREG-0313A 2831-1RCM-28AS-9LD-I A-10/03 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H DOWNSTREAM ON INSIDE OF ELBOW 89.12 B-J 1UREG-0313A 2B31-1RCM-28AS-9LD-O A-16/03 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H DOWNSTREAM ON g,
OUTSIDE OF ELBOW U B9.11 B-J MUREG-0313A 2831-1RCM-28AS-10 A-16/03 UT-H-401/6 88 28-SS-1.184-126-H ELHOW TO PUWP PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2831-1RCM-28AS-10LU-I A-16/03 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON INSIDE OF ELBCW 89.12 B-J NUREG-0313A 2831-1RCM-28AS-10LU-O A-16/03 UT-H-401/6 SEE NOTE A-8.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON OUTSIDE OF EL60W 89.11 3-J NUREG-0313A 2831-1RCM-28BD-1 A-19/02 UT-H-401/6 88 28-SS-1.184-128-H PUMP TO PIPE PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2831-1RCM-28BD-1LD A-19/02 UT-H-401/6 88 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 28-55-1.184-128-H WELD EXTENDING EXAMS COMPLETE FOR DOWNSTREAM 10-YEAR INTERVAL l
l
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 2, NURE3-C313 REV. 2 PAGE 13 (FOR INFORMATIDN DNLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATIDN FIRST SECOND THIRD REMARKS ITM NO. CAT. REOUIREMENT AREA IDENTIFICATICN NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.11 B-J NUREG-0313A 2831-1RCM-28BD-2 A-19/02 UT-H-401/8 88 28-SS-1.184-128-H PIPE TO VALVE PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2831-1RCM-28BD-2LU A-19/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-6DO/2 28-SS-1.184-128-H WELD EXTENDING UPSTREAM B9.11 B-J NUREG-0313A 2831-1RCM-28BD-3 A-19/02 UT-H-401/6 88 28-SS-1.184-128-H VALVE TO ELBOW PT-H-600/2 EXAMS COMPLETE FOR 10-YE#R INTERVAL B9.12 B-J NUREG-0313A 2831-1RCM-28BD-3LD-I A-19/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H DOWNSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 2831-1RCM-28BD-3LD-O A-19/02 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H rn DOWNSTREAM ON to DUTSIDE OF ELBOW s
~'
o B9.11 B-J NUREG-0313A 2831-1RCM-28BD-4 A-19/02 UT-H-401/6 28-SS-1.184-128-H ELBOW TO PIPE PT-H-600/2 B9.12 B-J NUREG-0313A 2831-1RCM-28BD-4LD A-19/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENDING DOWNSTREAM 89.12 B-J NUREG-0313A 2831-1RCM-28BD-4LU-I A-19/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON INSIDE OF [LBOW B9.12 B-J NUREG-0313A 2831-1RCM-28BD-4LU-O A-19/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTPEAM ON OUTSIDE OF ELBOW 89.11 B-J NUREG-0313A 2831-1RCM-28BD-5 A-19/02 UT-H-401/6 28-SS-1.184-128-H PIPE TO CROSS PT-H-600/2
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 2 NURE2-E,313, REV. 2 PAGE 17 -
(FOR INFORMATION ONLY)
ASME ASME EXAM EKAMINATION FIGURE EXAMINATION FIRST SECONO THIRD REMARKS AREA IDENTIFICATION NO./ REY PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLDCK .*
ITM NO. CAT. REQUIREMENT B9.12 B-J NUREG-0313A 2831-1 tCM-28BO-5LD A-19/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 22-SS-1.75-129-H l WELD EATENDING DOWNS *MEAM B9.12 B-J NUREG-0313A 2831-iRCM-28BD-5LU A-19/02 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD Ei(TENDING UPSTREAM l B9.11 8-J NUREG-0313C 2831-1RCM-28BS-2 A-18/03 UT-H-401/8 88 28-SS-1.184-128-H l SAFE-END TO ELBOW PT-H-600/2 EXAMS COMPLETE FOR l
10-YEAR INTERVAL l
89.1.1 8-J NUREG-0313A 2831-1RCM-288S-2LD-I A-18/03 UT-H-401/6 88 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H DOWNSTREAM ON INSIDE EXAMS COMPLETE FOR OF ELBOW 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2B31-1RCM-28BS-2LD-O A-18/03 UT-H-401/6 88 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H DOWNSTREAM ON EXAMS COMPLETE FOR m 10-YEAR INTERVAL to OUTSIDE OF ELBOW s
~y B9.11 B-J NUREG-0313A 2831-tRCM-28BS-3 A-18/03 UT-H-401/6 X 28-SS-1.184-128-H ELBOW TO PIPE PT-H-600/2 89.12 B-J NUREG-0313A 2831-1RCM-28BS-3LD A-18/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENDING DOWNSTREAM B9.12 B-J NUREG-0313A 2831-1RCM-28BS-3LU-I A-18/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON INSIDE OF ELBOW
- B9.12 B-J NUREG-0313A 2831-1RCM-28BS-3LU-O A-18/03 UT-H-401/6 X SEE NOTE A-1.
LDNGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON OUTSIDE OF ELBOW 89.11 B-J NUREG-0313A 2831-1RCM-28CS-4 A-18/03 UT-H-401/6 28-SS-1.134-128-H PIPE TO PIPE PT-H-600/2 l
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH MJCLEAR PLANT - UNIT 2. NURE3-C313, [EV. 2 PAGE 18 *
(FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS .
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIDO PERIOD PERIOD CALIBRATION BLOCK
- 89.12 8-J NUREG-0313A 2831-1RCM-28BS-4LD A-18/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 28-SS-1.184-128-H-WELD EXTENDING DOWNSTREAM 89.12 8-J NUREG-0313A 2831-1RCM-2885-4LU A-18/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENDING UPSTREAM 89.11 8-J NUREG-0313A 2831-1RCM-2885-5 A-18/03 UT-H-401/6 28-SS-1.184-128-H PIPE T3 PIPE PT-H-600/2 89.12 B-J NUREG-0313A 2831-1RCM-288S-5LD A-18/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTEPOING DOWNSTREAM 89.12 8-J NUREG-0313A 2831-1RCM-288S-5LU A-18/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H rri WELD EXTENE NG y UPSTREAM
$ 89.11 8-J NUREG-0313A 2831-1RCM-288S-6 A-18/03 UT-H-401/6 28-SS-1.184-128-H PIPE TO EL80W PT-H-600/2 89.12 B-J PAJREG-0313A 2831-1RCM-288S-6LD-1 A-18/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H DOWNSTREAM ON INSIDE OF ELBOW 89.12 8-J MJREG-0313A 2831-1RCM-2885-6LD-O A-18/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-F5-1.184-128-H DOWNSTREAM ON OUTSIDE OF EL80W 89.12 B-J NUREG-0313A 2831-1RCM-2885-6LU A-18/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 28-SS-1.184-128-H WELD EXTENDING UPSTREAM 89.11 8-J NUREG-0313A 2831-1RCM-2885-7 A-18/03 UT-H-401/6 88 28-$5-1.184-128-H ELBOW TO VALVE PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH NUCLEAR PLANT - UNIT 2, MURE2-0313, REV. 2 PAGE 13 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRO REMARKS .,
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIDO CALIBRATION BLOCK 89.12 El-J 9eJREG-0313A 2831-1RCM-2885-7LU I A-18/03 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON INSIDE OF ELBOW 89.12 R-J NUREG-0313A 2831-1RCM-288S-7LU-O A-18/03 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON OUISIDE OF ELBOW 89.11 8-J NUREG-0313A 2831-1RCM-2885-8 A-18/03 UT-H-401/8 88 28-SS-1.184-128-H VALVE TO EL80W PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL t 89.32 B-J PAJREG-0313A 2831-1RCM-2885-88C-2 A-18/03 PT-H-SOO/2 l PIPE TO BC l
89.12 8-J *JJREG-OJ13A 2831-1RCM-28BS-8L'1-I A-18/03 UT-H-401/6 SEE N3TE A-6.
LONGITL,OINAL WELD PT-H-600/2 28-SS-1.184-128-H m DOWPGTREAM ON INSIDE Y
m OF ELBOW
~
89.12 8-J NUREG-0313A 2831-1RCM-2885-8LO-O A-18/03 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H OOWNSTREAM ON OUTSIDE OF ELBOW 89.11 8-J NUREG-0313A 2831-1RCM-288S-9 A-18/03 UT-H-401/8 88 28-SS-1.154-128-H e ELBOW TO PUMP PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL 89.12 8-J NUREG-0313A 2831-1RCM-28BS-9LU-I A-18/03 UT-H-401/6 88 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON INSIDE EXAMS COMPLETE FOR OF ELBOW 10-YEAR INTERVAL 89.12 8-J PAJREG-0313A 2831-1RCM-288S-9LU-O A-18/03 UT-H-401/6 88 SEE NOTE A-1.
t_ONGITUDINAL WELD PT-H-600/2 28-SS-1.184-128-H UPSTREAM ON OUTSIDE EXAMS C0eIPLETE FOR OF ELBOW 10-YEAR INTERVAL
. .ig
INFORMATION SERVICES-BIRMINGHAM E EDWIN I. HATCH NUCLEAR PLANT - UNIT 2, NURE3-C313, CEV. :P PAGE 20 -
(FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENf!FICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK B5.10 B-F MJREG-0313D 2C11-1CRD-3-R-1 A-1/3 UT-H-400/7 88 X X 5.4-IN-X-0.750-97-H 2N9 NOZZLE TO CAP PT-H-600/2 EXAMINE 1989 RO AND THEN EVERY 2N3 RO m
INFORMATION SERVICES-BIRPAINGHAM
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EDh!N I. HATCH NUCLEAR PLANT - UNIT 2, NURE3-C313, REV. 2 PAGE 21 -
(FOR INFORMATION ONLY) 4 ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK ~*
89.11 R-J NUREG-0313A 2E11-1RHRM-20RS-1 A-21/03 UT-H-401/8 K 20-SS-0.879-130-H TEE TO PIPE PT-H-600/2 89.31 B-J NUREG-0313A 7E11-1RHRM-20RS-1BC-1/ A-21/03 UT-H-401/6 20-SS-0.879-130-H 2G31-1RWCUM-6-D PT-H-EOO/2 PIPE TO BC B9.12 B-J NUREG-0313A 2E11-1RHRM-20RS-1LD A-21/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 20-SS-0.879-130-H WELD EXTENDING DOWNSTREAM B9.11 B-J NUREG-0313A 2E11-1RHRM-20RS-2 A-21/03 UT *4-401/6 X 20-SS-O.879-130-H PIPE TO ELBOW PT-H-600/2 B9.12 B-J NUREG-0313A 2E11-1RHRM-20RS-2LD-I A-21/03 UT-H-401/6 SEE NOTE A-1.
m LONGITUCINAL WELD PT-H-600/2 20-SS-0.879-130-H w DOWNSTREAM ON INSIDE 4 OF ELBOW 89.12 B-J NUREG-0313A 2E11-1RHRM-20PS-2LO-O A-21/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 20-SS-0.879-130-H DOWNSTREAM ON OUTSIE4 OF ELBOW 89.12 B-J NUREG-0313A 2E11-1RHRM-20RS-2LU A-21/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 20-SS-0.879-130-H WELD EXTENDING UPSTREAM B5.50 B-F NUREG-0313C 2E11-1RHRM-20RS-3 A-21/03 UT-H-401/6 88 20-SS-0.879-130-H
- ELBOW TO PIPE PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 B-J NUREG-0313A 2E11-1RHRM-20RS-3LU-I A-21/03 UT-H-401/8 88 SEE NOTE fa-1.
LONGITUDINAL WELD PT-H-600/2 20-SS-0.879-130-H UPSTREAM ON INSIDE EXAMS COMPLETE FOR OF ELBOW 10-YEAR INTERVAL 89.12 B-J NUREG-0313A 2E11-1RHRM-20RS-3LU-O A-21/03 UT-H-401/6 88 SEE NOTE A-1.
t.ONGITUDINAL WELD PT-H-600/2 20-SS-O.879-130-H UPSTREAM ON OUTSIDE EXAMS COMPLETE FOR OF ELBOW 10-YEAR INTERVAL
INFORMATION SERVICES-BIRMINGHAM
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EDWIN I. MATCH DeJCLEAR PLANT - UNIT 2. PAfRE3-C313. REV. 2 PAGE 22 .-
(FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRO RfMARKS ,
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIDO PERIOD PERIDO CALIBRATION BLOCK '
PJ5.50 8-F paJREG-0313C 2E11-1Rs6tu-24A-10 A-22/03 UT-H-401/6 88 24-SS-1.186-131-H
- PIPE TG'EL80W PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL 89.12 0-J 9eJREG-0313A 2E11-1RHRM-24A-10LD-I A-22/03 UT-H-401/6 $[E NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 24-SS-1.186-131-H DOWNSTREAM ON INSIDE OF ELBOW 89.12 8-J NUREG-0313A 2E11-1RHRM-24A-10LD-O A-22/03 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-SOO/2 24-SS-1.186-131-H DOWNSTREAM ON OUTSIDE OF ELBOW 89.11 8-J NUREG-0313A 2E11-1RHRM-24A-11 A-22/03 UT-H-401/6 24-SS-1.186-131-H ELBOW TO PIPE PT-H-SOO/2 89.12 8-J NUREG-0313A 2E11-1RHRM-24A-11LD A-22/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 24-SS-1.186-131-H m WELG EXTENDING y DOWNSTREAM
$- 89.12 8-J NUREG-0313A 2E11-1RHRM-24A-11LU-I A-22/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 24-SS-1.186-131-H UPSTREAM ON INSIDE OF ELBOW 89.12 8-J #4) REG-0313A 2E11-1RHRM-24A-11LU-O A-22/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-SOO/2 24-SS-1.186-131-H UPSTREAM ON OUTSIDE OF ELBOW 89.11 8-J PAJREG-0313A 2E11-1Rl5tM-24A-12 A-22/03 UT-H-401/6 24-SS-1.186-131-H PIPE TO EL8OW PT-H-SOO/2 819. 1 2 B-J NUREG-0313A 2E11-1RHRM-24A-12LD-I A-22/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 24-SS-1.186-131-H DOWNSTREAM ON INSIDE OF ELBOW 89.12 8-J NUREG-0313A 2E11-1RHRM-24A-12LD-O A-22/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-SOO/2 24-SS-1.186-131-H DOWNSTREAM ON OUTSIDE OF EL80W
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATLH NUCLEAR PLANT - UNIT 2. MJRE3-C313. REY. 2 PAGE 23 (FOR INFORMATION ONLY) 4E FNOW EXANINATION FIGURE EXAMINATION FIRST SECO*dD THIRD REMARKS .,
j 4T. 94QUIfdNENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 2 U* M#t[G-0313A 2E11-1RHRM-24A-12LU A-22/03 UT-H-401/6 SEE MJTE A-1.
LONGITUDINAL SEAM PT-H-600/2 24-SS-t.186-131-H WELD EXTENDING UPSTREAM 1 89.11 8-J rduREG-0313A 2E11-1RHRM-24A-13 A-22/03 UT-H-401/6 X 24-SS-1.186-131-H l EL80W TO TEE PT-H-600/i 29.12 8-J NtREG-03 t3A 2E11-1RHRM-24A-1!.dJ-I A-22/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 24-SS-1.186-131-H a
UPSTREAN ON I?M DE OF EtL?'
59.12 8-J MAF4-0313A 2Et t-1RHRM-24A-13LU-O A-22/03 1.ff-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 24-SS-1.186-131-H UPSTREAM ON OUTSIDE OF ELBOW 85.50 B-F NUREG-0313C 2E11-1RHRM-24F-10 A-23/03 UT-H-401/6 58 24-SS-1.186-131-H
- PIPE TO ELBOW PT-H-SOO/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL 89.12 8-J NUREG-0313A 2E11-1RHRM-248-10LD-I A-23/03 UT-H-401/6 SEE NOTE A-6.
U LONGITUDINAL WELD DOWNSTREAM ON INSIDE PT-H-600/2 24-SS-1.186-131-H OF EL80W 89.12 8-J NUREG-0313A 2E11-1RHRM-248-10LD-O A-23/03 UT-H-401/6 SEE NOTE A-6.
l LONGITUDINAL WELD PT-H-600/2 24-SS-1.186-131-H DOWNSTREAM ON DUTSIDE OF EL80W 89.11 8-J NUREG-0313A 2E11-1RHRM-248-11 A-23/03 UT-H-401/6 X 24-SS-1.186-131-H ELBOW TO PIPE PT-H-800/2 l
89.12 B-J NUREG-0313A 2E11-1RHRM-248-11LD A-23/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 24-SS-1.186-131-H WELD EXTEICIING DOWNSTREAM 89.12 8-J 14JREG-0313A 2E11-1RHRM-248-11LU-I A-23/03 UT-H-401/6 X SEE M)TE A-1.
LONGITUDINAL WELD PT-H-600/2 24-SS-1.186-131-H UPSTREAM ON INSIDE OF EL80W i
-w
INFORMATION hERVICES-BIRMINGHAM
[DWIN I. HATCH NUCLEAR PLANT - UNIT 2. MJRE3-C313, REV. 2 PAGE 23 *
(FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOO PERIOD PERIOD CALIBRATION BLOCK 89.12 B-J NUCEG-0313A 2E11-1RHRM-248-11LU-O A-23/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-SOO/2 24-SS-1.186-131-H UPSTREAM ON OUTSIDE OF ELBOW B9.12 B-J NUREG-OJ13A 2E11-1RHRM-248-12 A-23/03 UT-H-401/6 24-SS-1.186-131-H PIPE TO ELBOW PT-H-600/2 89.12 B-J NUREG-0313A 2E11-1RHRM-248-12LD-I A-23/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 24-SS-1.186-131-H LOWNSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 2E11-1RHRM-24B-12LD-O A-23/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 24-SS-1.136-131-H DOWNSTREAM ON OUTSIDE OF ELBOW B9.12 B-J NUREG-0313A 2E11-1RHRM-248-12LU A-23/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 24-SS-1.186-121-H WELD EXTENDING m UPSTREAM ,
O m
B9.11 B-J M.lREG-0313A 2E11-1RHRM-248-13 A-23/03 UT-H-401/6 X 24-SS-1.186-131-H ELBOW TO TEE PT-H-600/2 89.12 B-J NUREG-0313A 2E11-1RHRM-248-13LU-I A-23/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 24-SS-1.186-131-H UPSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 2E11-1RHRM-248-13LU-O A-23/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAf. WELD PT-H-600/2 24-SS-1.186-131-H UPSTREAM DN OUTSIDE OF ELBOW
INFORMATION SERVICES-BIRMINGH,W -
EOWIN 1. HATCH MJCLEAR PLANT - UNIT 2, MJRE3-0313. REV. 2 PAGE 25 -
(FOR INFORNATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECONO THIRD REMARKS .
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCEO./REV PERIOD PERIDO PERIOD CAIIERATION BLOCK -
85.50 S-F NUREG-03130 2E21-1CS-10A-20 A-24/03 UT-H-400/7 88 X X 10-H
85.10 5-F NUREG-03130 2E21-1CS-10A-21 A-24/03 UT-H-409/3 88 X X 13.2-IN-X-1.2OO-78-H
- SAFE-EM3 TO N0ZZLE PT-H-600/2 EXAMINE 1988 20.
REE1[AM EVERY 29e RO.
85.50 8-F MJREG-03130 2E21-1CS-105-19 A-25/03 UT-H-400/7 88 X X 10-H
- PIPE TO SAFE-END PT-H-600/2 10-9-IN-X-3.600-78-H EXAMINE EVERY 2ND REFUELING OUTAGE 85.10 8-F NUREG-0313D 2E21-1CS-108-20 A-25/03 UT-H-409/3 88 X X 13.2-IN-X-1.2OO-78-H
- SAFE-END TO N0ZZLE PT-H-600/2 EXAMINE EVERY 2ND REFUELING OUTAGE m
~
N s
INFORMATION : ERVICES-BIRMINGHAM EDWIN I. HATCH MJCLEAR PLANT - UNIT 2. NURE3-C313, REV. 2 PAGE 26 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGuitE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.11 8-J NUREG-0313C 2G31-1RWCU-6-D-17 A-28/03 UT-H-400/7 88 SEE NOTE A-2.
- VALVE TO PENETRATION PT-H-600/2 2-H EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.11 8-J NUREG-0313A 2G31-1RWCUM-6-D-1 A-28/03 UT-H-401/6 X 6-SS-0.432-133-H BRANCH CONNECTION PT-H-600/2 TD PIPE B9.12 B-J P4JREG-0313A 2G31-1RWCUM-6-D-1LD A-28/03 UT-H-401/8 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXT [NDING DOWNSTREAM 89.11 B-J PAJREG-0313A 2G31-1RWCUM-6-D-2 A-28/03 UT-H-401/6 6-SS-0.432-133-H PIPE TO ELBOW PT-H-600/2 89.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-2LD-I A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H m DOWNSTREAM ON INSIDE w 0F ELBOW s
$ B9.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-2LD-O LONGITUDINAL WELD A-28/03 UT-H-401/6 PT-H-600/2 SEE NOTE A-1.
6-SS-0.432-123-H DOWNSTREAM ON OUTSIDE OF [LBOW B9.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-2LU A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING UPSTREAM 89.11 8-J NUREG-0313A 2G31-1RWCUM-6-D-3 A-28/03 UT-H-401/6 6-SS-0.432-133-H ELBOW TO PIPE PT-H-600/2 B9.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-3LD A-28/03 UT-H-401/6 SEE NOTE A-2.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING DOWNSTREAM 89.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-3LU-I A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H UPSTREAM ON INSIDE OF ELBOW
INFORMATION SERVICES-BIRMINGHAM EDWIN I. HATCH WCLEAR PLANT - UNIT 2, feJRE3-C313 REV. 2 PAGE 27 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK ~-
89.12 8-J 90 REG-0313A 2G35-1RWCUM-6-D-3LU-O A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H UPSTREAM ON OUTSIDE OF EL80W 89.11 8-J NUREG-0313A 2G31-1RWCUM-6-D-4 A-28/03 UT-H-401/6 6-SS-0.432-133-H PIPE TO ELBOW PT-H-600/2 89.12 5-J NUREG-0313A 2G31-1RWCUM-S-D-4LD-I A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H DOWNSTREAM ON INSIDE OF EL80W 89.12 5-J NUREG-0313A 2G31-1RWCUM-6-D-4LD-O A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUCINAL WELD PT-H-600/2 6-SS-0.432-133-H DOWNSTREAM ON OUTSIDE OF ELBOW 89.12 8-J NUR[G-0313A 2G31-1RWCUM-6-0-4LU A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING UPSTREAM
]
E 89.11 8-J PAJREG-0313A 2G31-1RWCUM-6-D-5 A-28/03 UT-H-401/6 6-SS-0.432-133-H W ELBOW TO PIPE PT-H-600/2 89.12 5-J NUREG-0313A 2G31-1RWCUM-6-D-5LD A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING DOWNSTREAM ,
89.12 8-J NUREG-0313A 2G31-1RWCUM-6-D-5LU-t A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H UPSTREAM ON INSIDE OF EL8OW 89.12 8-J MJREG-0313A 2G31-1RWCUM-6-D-5LU-O A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-SOO/2 6-SS-0.432-133-H UFSTREAM ON OUTSIDE CF ELBOW 89.12 B-J NUREG-0313C 2G31-1RWCUM-6-D-6 A-28/03 UT-H-401/6 88 6-SS-0.432-133-H
= PIPE TO VALVE PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL
INFORMATION SERVICES-BIRMINGHAM EDWIN 1. HATCH NUCLEAR PLANT - UNIT 2. MJRE2-0313, REY. 2 PAGE 28 *
(FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.12 8-J NUREG-0313A 2G31-1RidCUM-6-D-6LU A-28/03 UT-H-401/8 88 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 6-SS-O.432-133-H WELD EXTENDING EXAMS COMPLETE FOR UPSTREAM 10-YEAR INTERVAL 89.11 8-J NUREG-0313C 2G31-1RWCUM-6-D-7 A-28/03 UT-H-401/8 88 6-SS-0.432-133-H e VALVE TO PIPE PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL 89.32 5-J MJREG-0313A 2G31-1RWCUM-8-D-78C-1 A-28/03 PT-H-SOO/2 X PIPE TO BRANCH CODM.
89.12 8-J NUREG-0313A 2G31-1RWCUM-6-D-7LD A-28/03 UT-H-401/6 SEE NOTE A-8.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING DOWNSTREAM 89.11 8-J MJREG-0313A 2G31-1RWCUM-6-D-8 A-28/03 UT-H-401/6 X 6-SS-0.432-133-H PIPE TO 45-DEGREE PT-H-600/2 EL8OW O
e 89.12 8-J NUREG-0313A 2G31-1RWCUM-8-D-8LD-I A-23/03 UT-H-401/6 X SEE NOTE A-1.
y LONGITUDINAL WELD PT-H-600/2 6-SS-0.#32-133-H DOWNSTREAM ON INSIDE OF EL8OW 89.12 8-J NUREG-0313A 2G31-1RWCUM-6-D-8LD-O A-28/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H DOWNSTREAM ON OUTSIDE OF EL8OW 89.12 8-J MJREG-0313A 2G31-1RWCUM-6-D-8LU A-28/03 UT-H-401/8 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-SOO/2 6-SS-0.432-133-H WELD EXTENDING UPSTRFAM 89.11 8-J NUREG-0313A 2G31-1RWCUM-6-D-9 A-28/03 UT-H-401/8 6-SS-0.432-133-H 45-DEGREE EL8OW TO PT-H-SOO/2 PIPE 89.12 8-J MJREG-0313A 2G31-1RWCUM-6-D-9LD A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING
~
nA,w4 STREAM
IfEORMATION SERVICES-BIRMING*iAM EDWIN I. HATCH NtJCLEAR PLANT - UNIT 2. MJRE3-C313, REV. 2 PAGE 29 (FOR INFORMATION ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ,
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-9LU-I A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-SCO/2 6-SS-0.432-133-H UPSTREAM ON INSIDE OF ELBOW 89.12 B-J MJREG-0313A 2G31-1RWCUM-6-D-9LU-O A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H UPSTREAM ON OUTSIDE OF ELBOW B9.11 B-J MJREG-0313A 2G31-1RWCUM-6-D-10 A-28/03 UT-H-401/6 6-SS-0.432-133-H PIPE TD 45-DEGREE PT-H-SOO/2 ELBOW B9.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-10LD-I A-28/03 UT-H-401/6 SEE NOTE A-1 LONGITUDIr4AL WELD PT-H-600/2 6-SS-0.432-133-H DOWNSTREAM ON INSIDE OF ELBOW B9.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-10LD-O A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H DOWNSTREAM ON m OUTSIDE OF ELBOW 89.12 B-J MJREG-0313A 2G31-1RWCUM-6-D-10LU A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 0-SS-0.432-133-h WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313A 2G31-1RWCUM-6-D-11 A-28/03 UT-H-401/6 6-SS-0.432-133-H 45-DEGREE ELBOW TO PT-H-600/2 PIPE 59.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-11LU-! A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H UPSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-11LU-O A-28/03 UT-H-401/6 6-SS-0.432-133-H LONGITUDINAL WELD PT-H-600/2 UPSTREAM ON OUTSIDE OF ELBOW 89.12 B-J NUREG-0313A 2G31-1RWCUN-6-D-11LD A-28/03 UT-H-401/6 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING DOWNSTREAM
INFORMATION SERVICES-BIRMINGHAM EDWIN 1. HATCH NUCLEAR PLANT - UNIT 2. NURE3-C313 REV. 2 PAGE 30 (FOR INFORMATI')N ONLY)
ASME ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECONO THIRD REMARKS ,
ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIOD PERIOD PERIOD CALIBRATION BLOCK 89.11 B-J WREG-0313A 2G31-1RWCUM-6-D-12 A-28/03 UT-H-401/6 X 6-SS-0.432-133-H PIPE TO ELBOW PT-H-600/2 89.12 B-J WREG-0313A 2G31-1RWCUM-6-D-12LD-I A-28/03 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H DOWNSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-C313A 2G31-1RWCUM-6-D-12LD-O A-28/03 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL WELD PT-H-600/2 6-SS-0.432-133-H DOWNSTREAM ON OUTSIDE OF ELBOW 89.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-12LU A-28/03 UT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING UPSTREAM 89.11 B-J NUREG-0313A 2G31-1RWCUM-6-D-13 A-28/03 UT-H-401/8 X 6-SS-0.432-133-H FLBOW TO PIPE PT-H-600/2 m
Y u
" 89.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-13LU-I A-28/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUCINAL WELD PT-H-600/2 6-SS-0.432-133-H UPSTREAM ON INSIDE OF ELBOW 89.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-13LU-O A-28/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL WELD PT-H-8tv0/2 6-SS-0.432-133-H UPSTREAM ON OUTSIDE OF ELBOW 89.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-13LD / 28/03 UT-H-401/6 X SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELT. EXTENDING OOWNSTREAM 59.11 B-J NUREG-0313C 2G31-1RWCUM-6-D-14 A-28/03 UT-H-401/8 88 6-SS-0.432-133-H e PIPE TO VALVE PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL 89.12 B-J NUREG-0313A 2G31-1RWCUM-6-D-14LU A-28/03 MT-H-401/6 SEE NOTE A-6.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING UPSTREAM
- c. . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ .
INFORMATION SERVICES-BIRMINGHAM EDWIZ I. HATCH NUCLEAR PLANT - UNIT 2. NURE3-0313 REV. 2 PAGE 31 .
(FOR INFORMATION ONLY)
A!!AE ASME EXAM EXAMINATION FIGURE EXAMINATION FIRST SECOND THIRD REMARKS ITM NO. CAT. REQUIREMENT AREA IDENTIFICATION NO./REV PROCED./REV PERIDO PE;tIOD PERIOD CALIBRATION BLOCK
89.11 8-J PRJREG-031'IC 2G31-1RWCUM-6-D-15 A-28/03 UT-H-401/6 88 6-SS-0.432-133-H
= PENETRATION TO PIPE PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL 89.92 6-J NUREG-0313A 2G31-1RWCUM-6-D-15LD A-28/03 UT-H-401/6 SEE NOTE A-6.
LONG1TUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING DOWNSTREAM E9.11 8-J NUREG-0313C 2G31-1RWCUM-6-O-16 A-28/03 UT-H-401/6 88 6-SS-0.432-133-H
- PIPE TO VALVE PT-H-600/2 EXAMS COMPLETE FOR 10-YEAR INTERVAL B9.12 8-J NUREG-0313A 2G31-1RWCUM-6-D-16LU A-28/03 UT-H-401/6 88 SEE NOTE A-1.
LONGITUDINAL SEAM PT-H-600/2 6-SS-0.432-133-H WELD EXTENDING EXAMS COMPLETE FOR UPSTREAM 10-YEAR INTERVAL C
S
.