Letter Sequence Approval |
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Results
Other: ML17318A294, ML19274D226, ML19309G772, ML19345F245, ML19345F247, ML20011B254, ML20023A486, ML20024E088, ML20028D207, ML20041G421, ML20065B814, ML20236J661
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MONTHYEARML19326A4051977-04-22022 April 1977 Grants Relief from ASME Requirements for Proposed Inservice Testing Program for Pumps & Valves for Defined Period of Time.Addl Info Needed for Request for Relief from ASME Code Requirements Under Section 4.0.5b of Tech Specs Project stage: Other ML19326A4151977-04-22022 April 1977 NRC Guidelines for Excluding Exercising (Cycling) Tests of Certain Valves During Plant Operation Project stage: Other ML19326A4091977-04-22022 April 1977 NRC Guidance for Complying W/Certain Provisions of 10CFR50. 55a(g), Inservice Insp Requirements. List of Info Required for NRC Review of Inservice Insp Review & Testing Program Encl Project stage: Approval ML19329A8581977-06-27027 June 1977 Responds to NRC 770422 Request.Forwards Pump & Valve Test Program, for Compliance w/10CFR50.55a(g).Additions & Changes to Program,Which Meet Code Testing Requirements Will Be Implemented.W/O Encl Project stage: Other ML19329A9091977-11-22022 November 1977 Responds to NRC 770422 Request Re Facility Inservice Insp Program Compliance w/10CFR50.55a(g).Forwards Program for ASME Class 2 & 3 Components.W/O Encl Project stage: Other ML19329A9201977-11-22022 November 1977 ASME Section 11 Weld Examination Program for Facility: Inservice Insp Program Project stage: Other ML19317F5831978-01-0505 January 1978 ASME Section 11 Pump & Valve Test Program for Facility Project stage: Other ML19329A8551978-01-0505 January 1978 Responds to NRC 770104 Request.Forwards Second Transmittal of 770627 Rept, Pump & Valve Test Program, for Docketing. W/O Encl Project stage: Request ML19329B7741978-01-0606 January 1978 Notifies of Receipt of Util Request for Relief from Requirements of ASME Code Section 11,1974 Edition W/Addenda Through Summer 1975.Forwards Info Re Proposed Testing Program.W/O Encl Project stage: Other ML20236J6611978-03-29029 March 1978 Advises That Submittal of Second 40 Month Insp Period Plan Rescheduled to 780801.Submittal Date Changed from 780601 Due to Unanticipated Demand on Available Engineering Manpower Project stage: Other ML20112H3841978-08-0303 August 1978 Forwards Description of Planned Inservice Insp & Testing Program for Next 40-month Period & Three Sets of Modified Piping & Instrumentation Drawings,Including Applicable Components,Per Project stage: Request ML20147B6621978-10-0303 October 1978 Forwards Proposed Amend to Tech Specs Which Will Upgrade the Insvc Inspec Requirements Per 10CFR55a(g)(4)(ii).Proposed Changes Rely on Standard Tech Specs Project stage: Request ML19256A1711978-10-19019 October 1978 Notice of Granting of Relief from ASME Section XI Inservice Insp (Testing) Requirements Project stage: Other ML19256A1661978-10-19019 October 1978 Responds to Requesting Relief from Certain Requirements of Section XI of ASME Boiler & Pressure Vessel Code.Preliminary Review by NRC Finds Compliance W/Codes Would Cause Unusual Hardship & Are Waived Project stage: Other ML20062F4091978-12-12012 December 1978 Responds to 781201 Request for List of Plant Mod Being Made to Implement the Fire Hazard Analysis Rept.Fire Extinguishers Being Added to 13 Rooms & Wet Sprinkler or Spray Sys Being Added or Upgraded Project stage: Request ML19274D2261979-01-0303 January 1979 Grants Relief from Certain Inservice Insp & Testing Requirements of the ASME Boiler & Pressure Vessel Code, Section 11,pending Review Completion.Determines That Environ Statement Re This Action Is Not Necessary Project stage: Other ML19274E5471979-03-0909 March 1979 Requests Confirmation That Meb Will Not Review Inservice Testing Program in the Same Way They Review Inservice Insp Program.Asks for Name of Lead Reviewer of Testing Program Project stage: Other ML20244A5731979-03-28028 March 1979 Forwards Summary of 790222 Meeting Re Inservice Insp & Test Program.Summary Identifies Addl Info Required to Complete Review of Requested Relief from Certain ASME Code Requirements Project stage: Meeting ML20244A5791979-03-28028 March 1979 Summary of 790221 Meeting W/Util at Site Re Inservice Insp & Testing Program Project stage: Meeting ML19308A4531979-08-0808 August 1979 Discusses Review Re ASME Code,Section XI Exemption of ECCS Components from Inservice Insp Based on Water Chemistry Control.Water Chemistry Control to Minimize Stress Corrosion Is Unacceptable Basis for Exemption from Insp Project stage: Approval ML17318A2941979-09-14014 September 1979 Proposes Mods to Inservice Insp & Inservice Testing Program Review Responsibilities to Minimize Duplication of Effort at NRC & Maximize Contractor Review Activities.Sister Nuclear Facilities Should Be Managed by Same NRC Ofc Project stage: Other ML19309G7721980-05-0101 May 1980 Submits Addl Info Re Inservice Insp & Testing,In Response to NUREG-0411 Requirements.All Inservice Examinations Will Be Performed Per 1974 ASME Code XI W/Addenda Through 1975. Requests Relief from Hydrostatic Test Temp & Test Duration Project stage: Other ML19323D0821980-05-15015 May 1980 Forwards Updated Inservice Insp Program for Pumps,Valves, Welds(Including Supports,Components & Bolting) & Sys Pressure Tests Project stage: Other ML19323D0851980-05-15015 May 1980 Updated Inservice Insp Program for Pumps,Valves,Welds (Including Supports,Components & Bolting) & Sys Pressure tests.Twenty-three Oversize Drawings Encl Project stage: Other ML19345B2191980-11-14014 November 1980 Forwards Branch Questions & Comments & Request for Addl Info Re Util 800515 Revised Inservice Insp Program.Comments Will Form Basis for 801119-21 Working Session at Site Project stage: RAI ML19340E1221980-11-30030 November 1980 To Inservice Insp Program Project stage: Other ML19340E1191980-12-15015 December 1980 Forwards Revision to 800515 Inservice Insp Program.Changes Reflect Results of 801119 & 20 Meetings W/Nrc Onsite Re Lower Head Weld Insp & Requirements in 1977 Edition Through Summer 1978 Addenda of Boiler & Pressure Vessel Code Project stage: Meeting ML19345F2471981-01-27027 January 1981 Amend 2 to Inservice Insp Program Project stage: Other ML19345F2451981-01-27027 January 1981 Forwards Amend 2 to Facility Inservice Insp Program, Replacing 790606 Amend 1 Submittal.Requested Relief Does Not Affect Public Health & Safety.Requests Approval Project stage: Other ML19345G5121981-03-31031 March 1981 Forwards Editorial Revisions to Inservice Insp Program Project stage: Other ML19240C0021981-03-31031 March 1981 Inservice Testing Program for Pumps & Valves at Davis-Besse Nuclear Power Station - Unit 1 (Docket 50-346) for Period Nov 1977 Through Nov 1987, Safety Evaluation Project stage: Other ML20011B2541981-11-24024 November 1981 Forwards Info Re Class I Inservice Exam Areas Not Receiving Full Code Exam During 1981 Maint Refueling Outage.Areas Include Lugs,Reactor Recirculation Sys Vessel Nozzles,Piping Butt Welds & Recirculation Pump Studs Project stage: Other 05000270/LER-1982-002, Forwards LER 82-002/01T-0.Detailed Event Analysis Encl1982-02-0505 February 1982 Forwards LER 82-002/01T-0.Detailed Event Analysis Encl Project stage: Other 05000270/LER-1982-002-01, /01T-0:on 820122,three Core Support Assembly Thermal Shield Bolts Found W/Heads Broken Off & Shock Pad Y-2 Attachment Bolts Discovered Broken.Caused by Intergranular Stress Corrosion Cracking.Pad Removed1982-02-0505 February 1982 /01T-0:on 820122,three Core Support Assembly Thermal Shield Bolts Found W/Heads Broken Off & Shock Pad Y-2 Attachment Bolts Discovered Broken.Caused by Intergranular Stress Corrosion Cracking.Pad Removed Project stage: Other ML20041C2151982-02-0808 February 1982 Safety Evaluation Re Inservice Test Program & Granting of Relief from ASME Code Section XI Inservice Testing Requirements Project stage: Approval ML20041C2181982-02-0808 February 1982 Notice of Granting Relief from ASME Section XI Inservice Testing Requirements Project stage: Other ML20041C2071982-02-0808 February 1982 Forwards SER & Fr Notice Re Inservice Test Program & Granting of Relief from ASME Code Section XI Inservice Testing Requirements.Approval of Relief Expires on 850508 for Unit 1 & on 870401 for Unit 2 Project stage: Approval ML20040H1821982-02-16016 February 1982 Submits Editorial Revisions,Revision 3,to Inservice Insp Program Project stage: Other ML20040H1851982-02-28028 February 1982 Inservice Insp Weld & Support Insp Program,Revision 3, Editorial Changes Project stage: Other ML20041G4211982-03-12012 March 1982 Requests Addl Info Re Inservice Insp Program Relief.Info Should Be Forwarded to Science Applications,Inc,Within 30 Days of Ltr Project stage: Other ML20054D3051982-04-0606 April 1982 Requests Addl Info Required for Review of Inservice Insp Program.Response by 820611 Requested Project stage: Approval ML20054C6451982-04-0707 April 1982 Approves Util 800501 & 820311 Requests for Relief from 1974 Edition of ASME Section XI Code Re Required Inservice Insp Hydrostatic Min Test Temp of 100 F & Hold Times Project stage: Other ML20054C9571982-04-0808 April 1982 Notice of Violation from Insp on 820101-0228 Project stage: Other ML20052F3861982-05-0505 May 1982 Safety Evaluation Re ASME Code Section Xi,Inservice Insp Requirements.Granting of Relief Does Not Authorize Change in Effluent Types or Total Amounts Nor Increase in Power Level & Will Not Result in Significant Environ Impact Project stage: Approval ML20052F3771982-05-0505 May 1982 Advises That Sections 3 & 4 of 800515 Revised Inservice Insp & Testing Program Per ASME Boiler & Pressure Vessel Code Section XI of 1977 Edition Through Summer 1978 Addenda Acceptable for Remainder of 120-month Insp Interval Project stage: Other ML20052F3891982-05-0505 May 1982 Notice of Granting Relief from ASME Code Requirements Project stage: Other ML20023A4861982-09-0202 September 1982 Ei Hatch Nuclear Plant Units 1 & 2 Inservice Insp Program, Technical Evaluation Rept Project stage: Other ML20065B8141982-09-15015 September 1982 Advises of Exam Areas Not Receiving Full Code Exam During Inservice Insp Activities Conducted During Maint/Refueling Outage & Forwards Lists of Exam Limitations.Welds Receiving Limited Coverage Listed Project stage: Other ML20028D2071983-01-0707 January 1983 Comments on Upgrading Inservice Insp/Inservice Testing Program.Upgrade Requires Extensive Rewrite Due to Significant Changes in 1980 Edition of ASME Section XI Code from That Currently Used.Submittal Delayed Until 830801 Project stage: Other ML20028G1681983-02-0202 February 1983 Forwards Addl Info on Modified 821214 Code Relief Request 1 Revising Inservice Testing Program.Basis for Request Listed. Request Per ASME Section XI Iwv Re MSIVs MS-100 & MS-101 Project stage: Request 1980-12-15
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Similar Documents at Hatch |
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UNITED STATES g
g NUCLEAR REGULATORY COMMISSION 3
4j WASHINGTON. D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULAT' ION RELATED TO REQUESTS FOR RELIEF FROM INSERVICE INSPECTION REQUIREMENTS GEORGIA POWER C0'!PANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA EDWIN I. HATCM NUCLEAR PLANT, UNITS 1 & 2 DOCKET NOS. 50-321 & 50-366 INTRODUCTION Technical Specifications 4.6.K & 4.4.8 for the Edwin I. Hatch Nuclear Power Plant Units 1 & 2, respectively,' state that inservice examination of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressurs Vessel Code and applicable addenda as required by 10 CFR 50.55a(g) except where specific written relief has been granted by the Commission.
Certain requirements of later editions and addenda of Section XI are impractical to perform on older plants because of the plants' design, component geometry, and materials of construction.
Thus, 10 CFR 50.55a(g)(6)(i) authorizes the Commission to grant relief from those requirerrents upon making the necessary findings.
By letters dated August 3,1978, September 21, 1978, January 24, 1979, June 6,1979, May 1,1980, January 27, 1981, November 10, 1981, November 18,1981, March 2,1982 and June 11, 1382, Georgia Power Company submitted its inservice inspection program, revisions, or additional information related to requests for relief from certain Code requirements determined to be impractical to perform on Edwin I. Hatch Nuclear Power Plants, Units 1 & 2 during the inspection interval.
The program is based on the 1974 Edition through Summer 1975 Addenda of Section XI of the ASME Code, and covers the following:
o Unit 1, the last 80 months of the current 120-month interval, April 30, 1976 to May 5, 1986 o
Unit 2, the entire 120-month interval from September 5,1979 to September 5, 1989 EVALUATION l
Requests for relief from the requirements of Section XI which have been determined to be impractical to perform have been reviewed by the Staff's contractor, Science Applications, Inc.
The contractor's evaluations of the licensee's requests for relief and his recommendations are presented in the l
Technical Evaluation Report (TER) attached (ATTACHMENT 1).
The staff has reviewed the TER and agrees with the evaluations and recommendations.
A summary of the determinations made by the staff is presented in the following tables:
8308090160 830729 PDR ADOCK 05000321 G
PDR
,),
Based on the review summarized, the staff concludes that relief granted from the examination requirements and alternate methods imposed through this docu-ment give reasonable assurance of the piping and component pressure boundary and suppcrt structural integrity, that granting relief where the Code require-ments are impractical is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest considering the burden that could result if they were imposed on the facility.
Environmental Consideration We have determined that granting relief from specific ASME Section XI Code requirements does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environ-mental impact.
Having made this determination, we have further concluded that this is an action which is insignificant from the standpoint of environmental impact and,' pursuant to 10 CFR $51.5(d)(4), that an environmental impact statement or negative declara-ion and environmental impact aopraisal need not be preoared in connection with the grant of this relief.
Concl usion We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance.that the health and safety of the public will not be endange~ red by operation in the prooosed manner, and (2) such activities will be conducted in compliance with the Com-mission's regulations and the issuance of this. action will not be l
inimical to the common defense and security or to the health and l
safety of the public.
Date:
I l
The following NRC personnel contributed to this Safety Evaluation:
l George Johnson.
l l
I l
TABLE 1 CLASS 1 COMPONENTS LICENSEE PROPOSED RELIEF IWB-2600 IW8-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAM.
STATUS Bl.18 B-0 Reactor Pressure Volumetric None Vessel Retaining GRANTED Weld: in the Control Rod Drive Housing
~
B4.5 B-J Piping Inaccessible Volu-Surface Exami-GRANTED (Unit 1 Welds in metric mation of PROVIDED only)
Penetrations Accessible THE FIRST Flued Head ACCESSIBLE weld WELD OUT-SIDE THE PENETRATION IS VOLU-METRICALLY EXAMINED B4.5 B-J Piping Inaccessible Volu-Volumetric Welds not in metric to extend GRANTED Penetration practical and surface to supplement 84.9 B-K-1 Support Integrally Volu-Update to 1977 B5.4 Members Welded metric Edition,1979 B6.4 for Supports Addenda GRANTED (1)
Piping J,
Section XI Pumps (Surface
/
Valves
/
Exam)
(1) Relief granted by letter dat.ed January 27, 1982, Stolz to Beckham.
2
TABLE 1 CLASS 1 COMPONENTS LICENSEE PROPOSED RELIEF IWB-2600 IWB-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAM.
STATUS B4.10 B-K- 2 Hydraulic All support Visual Examine to B5.5 Snubbers, components Requirements GRANTED B6.5
- Piping, of Tech.
Pumps, &
Specs.
Valves 84.10 B-K-2 Support All-support Visual Examine to B5.5 compo-components Requirements GRANTED B6. 5 nents for of 1980 Edition (Relief.
- Piping, through Winter re-
- Pumps, 1980 Addenda quested Valves March 2, 1982)
B6.7 B-M-2 Valves Internal Visual Examine when
- surface, valve is GRANTED disassembled in i
part
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3
TABLE 2
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CLASS 2 COMPONENTS LICENSEE PROPOSED RELIEF IWC-2600 IWC-2520 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAM.
STATUS C2.1 C-F Piping Circum-Volu-Examine to C2.2 C-G ferential metric Extent GRANTED C2.3 Butt Welds practical (Unit 2 only)
C2.5 C-E-1
- Piping, Support Surface Examine to (Unit 2
- Pumps, Members Extent GRANTED only)
Valves practical l
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TABLE 2 CLASS 2 COMPONENTS LICENSEE PROPOSED RELIEF IWC-2600 IWC-2520 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE REQUEST ITEM NO. EXAM. CAT. COMPONENT EXz' MINED METHOD EXAM.
STATUS C2.6 C-E-2 Hydraulic All support Visual Examine to C3.4 Snubbers, components
' Requirements GRANTED C4.4
- Piping, of Tech. Specs.
i l
Pumps &
Valves C2.6 C-E-2 Support All support Visual
. Examine to C3.4 Compo-components Requirements C4.4 nents for of 1980 GRANTED l
- Piping, Edition
- Pumps, through 1980 Valves Addenda C3.2 C-0 Pumps Bolting Visual Surface C4.2 and Examination Surface when dis-GRANTED or volu-assembled metric i
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6 l
5 i
I
TABLE 3 CLASS 3 COMPONENTS LICENSEE RELIEF SYSTEM OR AREA TO BE REQUIRED PROPOSED REQUEST COMPONENT EXAMINED METHOD ALTERNATIVE STATUS Support Supports on Visual Examine to the Components Piping, Pumps Requirements of the GRANTED and Valves 1980 Edition through Winter 1930 Addenda Pumps.
Centrifugal Visual Examine during dRANTED River Intake IWD-2410 maintenance Pumps (b) and (c) o l
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TABLE 4 PRESSURE TEST IWA-5000 IWB-5000 IWC-5000 &
LICENSEE PROPOSED RELIEF SYSTEM OR IWD-5000 TEST ALTERNATIVE REQUEST COMPONENT PRESSURE REQUIREMENT TEST PRESSURE STATUS Class 1, 2 & 3 i Hold Time IWA-5210(a)
For non-insulated GRANTED piping hold time to be 10 min.
Class 1 IWB-5000 Where test temperature GRANTED Test Temperature of > 100*F cannot be
> 100/*F meti test @ > 70 F Class 2 IWA-5230 Test to Class 1 GRANTED non-isolable Pressures systems Class 2 IWC-5000 Where test temperature Test Temperature cannot be GRANTED
> 100*F
> 100*F test @ > 70 F Class 3 IWD-2410(b)
Test at operating (Service (Test Pressure pressure GRANTED Water Requirements 1.10 System)
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4 TABLE 5 ULTRASONIC EXAMINATION TECHNIQUE LICENSEE PROPOSED SYSTEM OR ALTERNATIVE RELIEF REQUEST COMPONENT REQUIREMENT EXAMINATION METHOD STATUS (No Relief Requested) s e
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O-TABLE 6 GENERAL RELIEF REQUESTS ALL CLASSES / COMPONENTS RELIEF LICENSEE REQUEST SYSTEM / COMPONENT REQUIREMENT ALTERNATE STATUS Class 2 Components IWC-2520(9)
Use Exemption NOT Exempted Under Exempt Piping Criteria of GRANTED IWC-1220(a)
Welds in RHR, ECCS 1977 Edition (a) Components in and CHRS through Summer systems where both 1979 Addenda temperature and pressure are equal to or less than 275 psig and 200*F respectively 1
9 1
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