|
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| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:- . - . - -- |
| | r, , f 7 -,-..m.,,,, |
| | ' s,. %. * |
| | / 4 M. , |
| | QI.IXh(k[l JAN 161980 - |
| | MR |
| | ! g.SllI.ATORY 00Ch EE CDPP 1 |
| | ; MEMORA!;DUI' FOR: A. Schwencer, Chief, ORG1, 00R 1 |
| | FRoti: V. Iloonan, Chief. Engineering 3 ranch, 00R |
| | |
| | ==SUBJECT:== |
| | SURRYUtlIT2ItifEGRATEDSTARTUPTESTPROGRAMFOLLOUII;G STEAlt GE!:ERATOR REPLACE!'ENT (TAC 11517) |
| | As requested, the Engineering Granch, DOR, has reviewed the Integrated Startup Test Program to be completed prior to returning Surry Unit 2 to operation 4 following the completion of the steam generator replacement program. We re- ' |
| | viewed the VEPC0 submittal dated August 13, 1979, and their responsas to our questions telecopies to us on January 14, 1980. '.le used Regulatory Guiae 1.GG, a |
| | Revision 2, as a basis for our review. |
| | We find tha Integrated Startup Test Program acceptablo. !!owever, it siiculd be noted that the baseline eddy current inspection of 1005 of the tubing performed prior to installation cannot be considered a preservice inspecticn as dafined , |
| | , in the Westinahouse standard technical specificaticns. In order to be considered a preservice inspection, it should be performed after the field hydrostatic test. |
| | Therefore, the first inservice inspection must include all three staan generators. |
| | t Vincent S. 'iconan, Chief Engineerino Cranch Division of Cperating Reactors |
| | |
| | ==Contact:== |
| | :1. LaGrange X07C29 cc: D.'Cisenhut L. Shao G. D. Liau J. 3. ::ci hbors |
| | ! i'.. LaGrango l |
| | l r |
| | .. . ... .E B. .:.D.g+ |
| | T!"N |
| | . .. E..B..:.00..R ...4............. d ..................... ....................... .................... |
| | - .. ..RI.4 Grange.mb . .@.U.e. . . . . . . . .. Mpn An.......... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , , , , . . , , , , , , , , , , , , , , , |
| | , , , , , , ....I.n g/.s..o..... .... 1 1./. . . ../. 9 0. .. .../ ./.. .f. ./. 80. . . . . . . |
| | : 3.c m m m =cu.= 1,........... |
| | 8002130 708 |
| | '}} |
Latest revision as of 01:14, 24 July 2020
Similar Documents at Surry |
|---|
Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217D5911999-05-17017 May 1999
Forwards Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990329-0401 & 0412-15 at Surry Power Station
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Notification of 870825 Meeting W/Util in Silver Spring,Md to Discuss New Nuclear Assurance Corp Cask Design & Util Part 72 License Amend Submittal
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Forwards C Mccracken 870514 Memo on NRR Review Plan & Schedule for Info Requested from Licensees Re Responses to Facility Feedwater Pipe Rupture
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Forwards EDO Principle Correspondence Including Question by Asselstine Re Enforcement Action Following Pipe Break
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ML20207Q6961987-01-0909 January 1987
Notification of 870115 Meeting W/Technical Experts in Washington,Dc to Discuss Parameters W/Significant Role in Pipe Failure & Development of Generic Guidance to Predict & Mitigate erosion-corrosion Piping Damage Effects
ML20215B3581986-12-29029 December 1986
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ML20214J6961986-11-21021 November 1986
Notification of 861124 Meeting W/Util in Bethesda,Md to Discuss Util Request to Amend Licenses for 40-yr Operation from Date of Issuance of OLs
ML20210K0781986-04-0303 April 1986
Forwards FEMA Rept on 851004 Emergency Exercise.State Supplied Schedule of Corrective Actions Will Be Forwarded When Received.Overall Capability of Offsite Authorities Acceptable & 44CFR350 Approval Remains in Effect
ML20134N7891985-08-21021 August 1985
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Forwards Tabular Summary of Key Results from Regional Survey of plant-specific Info Re Potential for Uncontrolled Radiation Exposures in PWR Cavities,Per Jg Partlow 850315 Request.No Further Generic Action Needed
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ML20197G2791984-03-0707 March 1984
Forwards SER for Radiological Consequences of Accidents for Extended Burnup.Calculated Dose to Thyroid for Fuel Handling Accident Indicates Plant Design Adequate.Salp Also Encl
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Forwards Engineering Evaluation of 811128 Event Involving Svc Water Valve Pit Flooding.Licensee Has Installed Dikes & Lights & Upgraded Maint Procedures to Preclude Future Occurrences.No Further Action Necessary
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Forwards Incident Reporting Sys Repts Re Spill of Contaminated Water & Contamination of Personnel in Auxiliary Bldg & Failure of Control Rod Guide Tube Support Pins for Transmittal to NEA
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Forwards Incident Reporting Sys Repts Re Effects of Fire Protection Sys Actuation on safety-related Equipment & Seismic Qualification of safety-related Sys for Transmission to NEA
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Forwards Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Vessels
IA-85-516, Forwards Results of Regional Evaluations of Salp.Items Identified Added to Outstanding Items List for Facilities1980-12-31031 December 1980
Forwards Results of Regional Evaluations of Salp.Items Identified Added to Outstanding Items List for Facilities
ML20134L4961980-12-31031 December 1980
Forwards Results of Regional Evaluations of Salp.Items Identified Added to Outstanding Items List for Facilities
ML20128Q7331980-07-28028 July 1980
Discusses Proposed Rev to IE Bulletin 79-14,per 800528 Memo. Region II Requested to Identify Design Organizations Which Did Static Analyses for Plant Resistance Temp Detector Lines.Reanalysis Necessary
ML20128Q7131980-05-28028 May 1980
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ML20125E4221980-01-15015 January 1980
Accepts Integrated Startup Program for Facility.Baseline Eddy Current Insp of Tubing Should Be Performed After Field Hydrostatic Test & Be Considered Preservice Insp as Defined in Westinghouse STS
ML20133N1661979-03-27027 March 1979
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ML20133M2111979-03-14014 March 1979
Submits Schedule for S&W to Complete Calculations.Ofc of Policy Evaluation Should Prepare Paper Re Impact on Each Region of Shutdown,Degree of Relaxation from Stds Allowable & If Mods Can Be Done Over Extended Period by 790415
1999-05-17
[Table view]
Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217D5911999-05-17017 May 1999
Forwards Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990329-0401 & 0412-15 at Surry Power Station
ML20249A8021998-03-16016 March 1998
Discusses Re Review of Topical Programs
ML20249A8001998-03-0909 March 1998
Forwards Ltr from VEPCO & WOG Requesting Waiver of Fee for Staff Review of Certain Submittals Re Pilot Program Effort risk-informed Inservice Insp Program
ML18153A2541997-12-0808 December 1997
Forwards Matls Analysis Rept NESML-Q-333, Unit 2 Let Down Orifice Insp, for Use
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Staff Requirements Memo Re SECY-97-182, Proposed Enforcement Action Against VA Electric & Power Co for Violations of Maint Rule at Surry Power Station
ML20211B9461997-08-0606 August 1997
Notifies of First Meeting of Plant on risk-informed ISI on 970814 in Surry,Va W/Listed Attendees to Discuss Categorization of Piping Segments & PRA Analyses & Results
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Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness
ML20134D7161996-10-24024 October 1996
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Provides Summary of Discussion & Staff Actions Re 950921 Plant Performance Review.List of Participants,Changes to Mip & Matrix Trend Charts Encl
ML20137R9521995-03-22022 March 1995
Informs That Plant Performance Review of Listed Plants Was Held on 950316
ML18153B1391994-11-0404 November 1994
Forwards Surry Power Station Underground Oil Release Site Characterization Rept
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Forwards Documents on Proposed rules,10CFR2 & 72 Re Interim Storage of Spent Fuel in Independent Spent Fuel Storage Installation & site-specific License to Qualified Applicant
ML20057B1891993-09-14014 September 1993
Requests Commission Approval of Proposed Rulemaking to Eliminate Requirement of Prior Commission Approval for Specific License for ISFSI Under 10CFR2 & 72.Notice of Proposed Rulemaking & Addl Info Encl
ML20248E9391989-09-29029 September 1989
Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed
ML20245F6541989-08-10010 August 1989
Submits Daily Highlight.Notifies of 890816 Meeting W/Util to Discuss Proposed Mods to Svc Water Sys at Plant
ML20245G3101989-07-31031 July 1989
Notification of 890807 Mgt Meeting W/Util in Atlanta,Ga to Discuss self-assessment Conducted at Facility
ML20154N8361988-09-13013 September 1988
Notification of 880916 Significant Licensee Meeting in Region II Ofc in Atlanta,Ga to Discuss Circumstance Re Partial Loss of Level in Unit 1 Refueling Cavity on 880517
ML20196G4631988-06-23023 June 1988
Forwards AEOD Technical Review Rept T809, Blocked Thimble Tubes/Stuck Incore Detector. Events Where Recovery of Stuck Detector & Cleaning of Thimble Tubes Led to Personnel Hazard,Discussed
ML20196G4051988-06-23023 June 1988
Forwards AEOD Technical Review Rept T809, Blocked Thimble Tubes/Stuck Incore Detector, for Consideration Due to Recent Events at Braidwood Unit 1
ML20237B2681987-12-11011 December 1987
Requests That Encl 10CFR50.App I Evaluations,For Listed Facilities Not Already Covered by Repts in Dcs,Be Entered Into DCS Sys on Microfiche
ML20153E9181987-11-16016 November 1987
Forwards Oct 1987 Significant Intergovernmental Activities & Issues Rept.Rept Represents Combined Efforts of NRC Regional State Liaison Officers,State,Local & Indian Tribes Programs Staff & Regional State Agreement Representatives
ML20238B3081987-08-27027 August 1987
Notification of 870825 Meeting W/Util in Silver Spring,Md to Discuss New Nuclear Assurance Corp Cask Design & Util Part 72 License Amend Submittal
ML20245B3651987-05-27027 May 1987
Forwards C Mccracken 870514 Memo on NRR Review Plan & Schedule for Info Requested from Licensees Re Responses to Facility Feedwater Pipe Rupture
ML20214L5831987-05-21021 May 1987
Summarizes 870519 Operating Reactors Events Meeting 87-15 to Brief Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870512 Meeting.Events Discussed & Significant Elements of Events Encl
ML20245B3681987-05-14014 May 1987
Forwards Proposed Course of Action & Projected Schedule for Handling Info Received in Response to Facility Pipe Rupture Bulletin,Per J Sniezek 870507 request.SECY-86-97 Also Encl to Provide Reporting Format That Will Be Followed
ML20215B6241987-04-20020 April 1987
Forwards EDO Principle Correspondence Including Question by Asselstine Re Enforcement Action Following Pipe Break
ML20215H8851987-04-13013 April 1987
Requests Description of NRC Approach to Problem of Corrosion & Erosion in Feedrings & J-tubes Based on 870312 Nucleonics Wk Article Re French Investigation Into Pipe Wall Thinning. Rationale for Not Citing Util for Poor GDC-1 Also Requested
ML20207R2651987-03-11011 March 1987
Staff Requirements Memo Re 870225 Commission Briefing Concerning 861209 Feedwater Line Rupture Event at Facility. Commission Requested Info on Completion Dates for Generic Issue Re Check Valves & on Other Listed Items
ML20245A4951987-03-0909 March 1987
Forwards Regional Ofcs Response to NRC Request for Survey of Licensee Programs for Monitoring Secondary Pipe Thinning,Per IE Info Notice 86-106, Feedwater Line Break. Survey Conducted During Wk of 870207.Draft IE Bulletin Encl
ML20210M9631987-02-0303 February 1987
Summarizes 870130 Telcon W/M Specter of Washington Post Re Plant Pipe Failure & AEOD/E416, Erosion in Nuclear Power Plants. AEOD Procedure for Distribution of Repts,Nrc Actions & Whether Rept Sent to Util Discussed
ML20207Q6961987-01-0909 January 1987
Notification of 870115 Meeting W/Technical Experts in Washington,Dc to Discuss Parameters W/Significant Role in Pipe Failure & Development of Generic Guidance to Predict & Mitigate erosion-corrosion Piping Damage Effects
ML20215B3581986-12-29029 December 1986
Informs Augmented Insp Team (AIT) of Activities During Jan 1987 in Order to Conclude AIT Insp & Issuance of Insp Rept. Insp Rept Based on 861217 Draft Executive Summary Requested by 870109.AIT Will Reconvene During Wk of 870112
ML20214J6961986-11-21021 November 1986
Notification of 861124 Meeting W/Util in Bethesda,Md to Discuss Util Request to Amend Licenses for 40-yr Operation from Date of Issuance of OLs
ML20210K0781986-04-0303 April 1986
Forwards FEMA Rept on 851004 Emergency Exercise.State Supplied Schedule of Corrective Actions Will Be Forwarded When Received.Overall Capability of Offsite Authorities Acceptable & 44CFR350 Approval Remains in Effect
ML20134N7891985-08-21021 August 1985
Forwards Investigation Rept 2-84-015 to Be Provided to Ofc of Investigations Region II for Release to Licensee & Pdr. Part 21 Related
ML20127F3061985-06-18018 June 1985
Forwards Tabular Summary of Key Results from Regional Survey of plant-specific Info Re Potential for Uncontrolled Radiation Exposures in PWR Cavities,Per Jg Partlow 850315 Request.No Further Generic Action Needed
ML20128H7661985-06-0505 June 1985
Discusses Substantive Changes in 850416 Rev to Radiological Emergency Plans.Revs Meet Requirements of 10CFR50.54(q) & 50.47(b)
ML20210P6381984-03-0808 March 1984
Comments on Statement That NRC Has Already Authorized Three Utils to Load & Use Fuel Intended for Burnup,Per 840222 Memo.Authorization Not Yet Granted.Forwards Paper Presented at ANS Meeting
ML20197G2791984-03-0707 March 1984
Forwards SER for Radiological Consequences of Accidents for Extended Burnup.Calculated Dose to Thyroid for Fuel Handling Accident Indicates Plant Design Adequate.Salp Also Encl
ML20080D5321983-10-17017 October 1983
Informs of 831015 Fatal Accident Involving Wc Jones. Expansion Joint Ruptured During High Pressure Drain Pump Valve Operation
ML20244C1011983-02-16016 February 1983
Forwards Engineering Evaluation of 811128 Event Involving Svc Water Valve Pit Flooding.Licensee Has Installed Dikes & Lights & Upgraded Maint Procedures to Preclude Future Occurrences.No Further Action Necessary
ML20127A3681982-08-18018 August 1982
Forwards List of Plants for Which Leak Test Repts Were Selected for Review by Ornl.Leak Testing Criteria Will Be Prepared from Review.W/O Encl
ML20062D3291982-07-29029 July 1982
Forwards Incident Reporting Sys Repts Re Effects of Fire Protection Sys Actuation on safety-related Equipment & Seismic Qualification of safety-related Sys for Transmission to NEA
ML20062E0791982-07-29029 July 1982
Forwards Incident Reporting Sys Repts Re Spill of Contaminated Water & Contamination of Personnel in Auxiliary Bldg & Failure of Control Rod Guide Tube Support Pins for Transmittal to NEA
ML20126L2271981-05-0101 May 1981
Forwards Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Vessels
IA-85-516, Forwards Results of Regional Evaluations of Salp.Items Identified Added to Outstanding Items List for Facilities1980-12-31031 December 1980
Forwards Results of Regional Evaluations of Salp.Items Identified Added to Outstanding Items List for Facilities
ML20134L4961980-12-31031 December 1980
Forwards Results of Regional Evaluations of Salp.Items Identified Added to Outstanding Items List for Facilities
ML20128Q7331980-07-28028 July 1980
Discusses Proposed Rev to IE Bulletin 79-14,per 800528 Memo. Region II Requested to Identify Design Organizations Which Did Static Analyses for Plant Resistance Temp Detector Lines.Reanalysis Necessary
ML20128Q7131980-05-28028 May 1980
Discusses Proposed Rev to IE Bulletin 79-14 as Result of Overstressed Resistance Temp Detectors Found at Plants. Bulletin Should Be Revised to Include Small Bore Piping Under 2.5 Inches
ML20125E4221980-01-15015 January 1980
Accepts Integrated Startup Program for Facility.Baseline Eddy Current Insp of Tubing Should Be Performed After Field Hydrostatic Test & Be Considered Preservice Insp as Defined in Westinghouse STS
1999-05-17
[Table view] |
Text
- . - . - --
r, , f 7 -,-..m.,,,,
' s,. %. *
/ 4 M. ,
QI.IXh(k[l JAN 161980 -
MR
! g.SllI.ATORY 00Ch EE CDPP 1
- MEMORA!;DUI' FOR
- A. Schwencer, Chief, ORG1, 00R 1
FRoti: V. Iloonan, Chief. Engineering 3 ranch, 00R
SUBJECT:
SURRYUtlIT2ItifEGRATEDSTARTUPTESTPROGRAMFOLLOUII;G STEAlt GE!:ERATOR REPLACE!'ENT (TAC 11517)
As requested, the Engineering Granch, DOR, has reviewed the Integrated Startup Test Program to be completed prior to returning Surry Unit 2 to operation 4 following the completion of the steam generator replacement program. We re- '
viewed the VEPC0 submittal dated August 13, 1979, and their responsas to our questions telecopies to us on January 14, 1980. '.le used Regulatory Guiae 1.GG, a
Revision 2, as a basis for our review.
We find tha Integrated Startup Test Program acceptablo. !!owever, it siiculd be noted that the baseline eddy current inspection of 1005 of the tubing performed prior to installation cannot be considered a preservice inspecticn as dafined ,
, in the Westinahouse standard technical specificaticns. In order to be considered a preservice inspection, it should be performed after the field hydrostatic test.
Therefore, the first inservice inspection must include all three staan generators.
t Vincent S. 'iconan, Chief Engineerino Cranch Division of Cperating Reactors
Contact:
- 1. LaGrange X07C29 cc: D.'Cisenhut L. Shao G. D. Liau J. 3. ::ci hbors
! i'.. LaGrango l
l r
.. . ... .E B. .:.D.g+
T!"N
. .. E..B..:.00..R ...4............. d ..................... ....................... ....................
- .. ..RI.4 Grange.mb . .@.U.e. . . . . . . . .. Mpn An.......... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , , , , . . , , , , , , , , , , , , , , ,
, , , , , , ....I.n g/.s..o..... .... 1 1./. . . ../. 9 0. .. .../ ./.. .f. ./. 80. . . . . . .
- 3.c m m m =cu.= 1,...........
8002130 708
'
