Letter Sequence Other |
|---|
|
Results
Other: ML17318A294, ML19274D226, ML19309G772, ML19345F245, ML19345F247, ML20011B254, ML20023A486, ML20024E088, ML20028D207, ML20041G421, ML20065B814, ML20236J661
|
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
[Table View] |
Similar Documents at Hatch |
|---|
|
Text
.
v.. u n,, os.g..
M ) Ifc9 u.el A,eryg.
AsoG.!.,pm
',6, a y M Q6 w[6 f., N y
,,y w a n, ti. v GeorgiaPower Power Generatk,n Department 4
Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 EXAMINATION LIMITATIONS DURING 1982 INSERVICE INSPECTION Ger.tlemen:
Georgia Power Company (GPC) hereby advises you of examination areas not receiving a full-code examination during inservice inspection activities conducted during the Hatch Unit 2 1982 maintenance / refueling outage.
3 Enclosed as Attachments 1 and 2 are lists of examination limitations encountered by Southern Company Services and Southwest Research Institute examination personnel, respectively.
The lists include the examination area (weld number), the type of examination performed, the approximate percentage of the examination performed, and the limitation (s) as described on the applicable examination data sheets. Attachment 3 discusses the requirements of the various examination procedures to clearly identify and explain the limitations.
In addition, several welds examined by Southern Company Services received very limited coverage.
Therefore, the following welds will be replaced by equivalent ASME category welds during future inservice inspections:
2E21-2CS-12A-5PL-7A and 8A 2E41-2HPCI-14-R-14PS-1 and 2 2E51-2RCIC-8-TD-1 2G51-2TDP-8-D-1.
Should you have any questions or comments in this regard, please contact i
this office.
Sincerely yours,
.I p.z a.-
8209230025 820915 PDR ADOCK 05000366 L. T. Gucwa G
PDR Chief Nuclear Engineer JAE/mb Attachments xc:
H. C. Nix, Jr.
h R. F. Rogers, III J. P. O'Reilly (NRC-Region II)
ATTACHMENT 1 Southern Company Services Scope of Work Examination Areas Not Receiving A Full-Code Examination Weld No./
NDE*
Percent Examination Method Examined-Limitations 3
2E21-1CS-10A-1 UT 75%
No examination from tne up-Valve to Pipe stream side due to valve con-figuration.
0* weld and 45' transverse scans were con-ducted as a best effort due to weld crown finish. All other scans were performed as required.
3 2E41-2HPCI-10-D-33 UT 95%
45' transverse scan limited to approximately 84% due to a Pipe to Cap permanent obstruction. All other scans were performed as required.
3 2C11-2CRD-2FW-1611 UT 75%
No examination from the down-Pipe to Reducer stream side due to the reducer configuration. The 0" weld scan was inadvertenly not per-formed by the examination crew.
This weld is an exempt Class 2 piping weld and was examined to meet the requirements of NUREG-0619.
It is not as critical a weld as others examined under NUREG-0619 because the cold water mixing i
occurs further downstream. This weld received a complete UT baseline examination in February 1981 with no reportable in-dications found. The UT exami-nation during this outage again resulted in no reportable in-dications found.
In addition, it should be noted that the 0* weld scan is used to locate fr>rication flaws and is not norna11y able to detect service-induced flaws.
l t
o See Attachment 3
ATTACHMENT 1 Sheet 2 Southern Company Services Scope of Work Examination Areas Not Receiving A Full-Code Examination Weld No./
NDE*
Percent Examination Method Exam'ined Limitations 6
2E11-2RHR-24B-TS-D-15PS MT 84%
MT examination limited to Pipe Support approximately 84% due to the proximity of the penetration
- seal, o
s l
l I
l l
l l
1 j
l l
l
ATTACHMENT 2 Southwest Research Intitute Scope of Work Examination Areas Not Receiving A Full-Code Examination Weld No./
NDE*
Percent Examination Method Examined Limitations I
2N2E UT 60%
No 45*T or 60*T scans due to Nozzle to Vessel Weld the nozzle joint configuration.
2 2N4A UT 86%
Limited examination due to the Nozzle Inside Radius proximity of 2N12A.
Section 2
2N4C UT 86%
Limited examination due to the Nozzle Inside Radius proximity of 2N12B.
Section 3
2821-1MS-24B-14 UT 40%
~
No examination from the down-Elbow to Pipe stream side due to the permanent pipe support. No 0*W or 45*T scans on the weld due to the permanent pipe support.
4 2B31-1RC-4AA UT 25%
No ultrasonic examination from Branch Connection to Cap the upstream side due to the branch connection configuration.
No ultrasonic examination from the downstream side due to the cap configuration.
4 l
2831-1RC-4AB UT 25%
Limitation identical to Branch Connection to Cap 2B31-1RC-4AA.
4 2B31-1RC-4BC UT 25%
Limitation identical to Branch Connection to Cap 2B31-1RC-4AA.
4 2B31-1RC-4BD UT 25%
Limitation identical to Branch Connection to Cap 2B31-1RC-4AA.
S 2E11-1RHR-24A-R-11LU-I UT 85%
No 45* or 45*T scans from L=0" Longitudinal Weld to L=3" due to the proximity of the permanent support structure.
l l
c'See Attachment 3
ATTACHMENT 2 Sheet 2 Southwest Research Institute Scope of Work Examination Areas Not Receiving A Full-Code Examination Weld No./
NDE*
Percent Examination Method Examined Limitations 3
2E11-1RHR-24A-R-11 UT 77%
Limited examination from the Elbow to Pipe upstream and downstredm sides and on the weld due to the proximity of two permanent support structures.
5 2E11-1RHR-24A-R-11LD UT 0%
No examination possible due to Longitudinal Weld the proximity of the permanent support structure (NUREG 0313, Rev1).
.~
o ATTACHMENT 3 NDE Methods (from Previous Tables)
(1) Mechanized U1trasonic Examination of Nozzle to Vessel Weld The ultrasonic (UT) examination of the nozzle to vessel weld was to be perfonned as follows:
(a) 0, 45, and 60-degree scans were to be conducted from the vessel side of the weld with the angle beams directed toward the weld using a nozzle-to-shell remote examination device.
(b) 0, 45, and 60-degree scans were to be conducted through the nozzle blend radius and onto the nozzle boss with the angle beams directed toward the weld and away from the weld using an inner radi~us examination device.
(c) 45-and 60-degree trar,sverse scans were to be conducted on the weld and from the vessel side of the weld with the angle beams directed into and parallel with the weld.
As noted in the tables, the 45-and 60-degree transverse scans could not be performed on 2N2E due to the nozzle joint configuration.
(2) Mechanized Ultrasonic Examination of Nozzle Inside Radius Sections The UT examination of the nozzle inside radius section was to be performed as follows:
Scans were to be performed from the blend radius using a refracted longitudinal beam that strikes the inside radius surfact ?t a 45-degree 10-degree angle with the beam directed tange,t 41 to the inside surface in the clockwise and counterclockwi' e9rections using an inner radius examination device.
For the 2N4A and 2N4C nozzles, the adjacent 2N12 nozzles limited the examination for eight inches out of a possible 58 inches. These limitations are outlined in Figure 1.
(3) Ultrasonic Examination of Circumferential Piping Welds With a Nominal Wall Thickness Greater Than 0.4 Inches For the UT examination of circumferential piping welds with a nominal wall thickness greater than 0.4 inches, the following scans were to be performed:
ATTACHMENT 3 Sheet 2 l.
(a) Base Metal (Main Run of Pipe) 0-degree lamination scan 45-degree scan 60-degree scan (b) On the Weld 0-degree weld scan (as needed) 45-degree transverse scan If possible, these scans on the base metal were to be perfonned from both sides of the weld.
If this was not possible, a 0-degree scan was to be performed on the weld for those areas where an examination was not possible from both sides. As noted in the tables, full-Code coverage was not possible on five circumferential piping welds.
(4) Ultrasonic Examination of Circumferential Piping Welds With a Nominal Wall Thickness Less Than 0.4 Inches For the UT examination of circumferential piping welds with a nominal wall thickness less than 0.4 inches, the following scans were to be perfonned:
(a) Base Metal (Main Run of Pipe) 0-degree lamination scan 45-degree scan 45-degree transverse scan (for a distance ef 1 inch from each side' of fusion line)
(b) On the Weld 45-degree transverse scan If possible, these examinations on the base metal were to be performed from both sides of the weld. As noted in the tables, full-Code coverage was not possible on four circumferential piping welds.
(5) Ultrasonic Examination of Longitudinal Piping Welds For the UT examination of longitudinal piping welds, the following scans were to be performed:
(a) Base Metal (Main Run of Pipe) 0-degree lamination scan 45-degree scan
.u.
i ATTACHMENT 3 Sheet 3 i
(b) On the Weld 0-degree weld scan (as needed) 45-degree transverse scan If possible, these examinations on the base metal were to be performed from both side of the longitudinal weld.
If this was not possible, a 0-degree scan was to be performed on the weld for those areas where an examination was not possible from both sides. As noted in the tables, full-Code coverage was not possible on two longitudinal piping welds.
(6) Magnetic Particle Examination of Pipe Support Welds For the magnetic particle (MT) examination of pipe support welds, the weld and adjacent base material were to be examined such that the lines of magnetic flux were to be approximately parallel and perpendicualr to the axis of the wel d.
As noted in the tables, full-Code coverage was not possible on one weld.
..