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| {{#Wiki_filter:1 M'<DOCS OI:I:SI'I I;I::~cll.l'I Y)REGULATG~INFORMATION DISTRIBUTION~STEM (RIDS)I ACCESSION NBR:9501270213 DOC.DATE: 95/01/19 NOTARIZED: | | {{#Wiki_filter:1 M'< DOCS OI:I:SI'I I; I::~cll.l'IY) |
| NO DOCKET g FACIL:50-244 Robert Emmet Ginna Nuclear plant, Unit 1, Rochester G 050pp244 AUTH.NAME AUTHOR AFFILIATION SHEPHERD,M.F. | | REGULATG~ INFORMATION DISTRIBUTION~STEM (RIDS) |
| J.L.Shepherd&Associates RECIP.NAME RECIPIENT AFFILIATION CHAPPELL,C.R. | | I ACCESSION NBR:9501270213 DOC.DATE: 95/01/19 NOTARIZED: NO DOCKET g FACIL:50-244 Robert Emmet Ginna Nuclear plant, Unit 1, Rochester G 050pp244 AUTH. NAME AUTHOR AFFILIATION SHEPHERD,M.F. J.L. Shepherd & Associates RECIP.NAME RECIPIENT AFFILIATION CHAPPELL,C.R. Division of Industrial & Medical Nuclear Safety (Post 8707 |
| Division of Industrial | |
| &Medical Nuclear Safety (Post 8707 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Constitutes initial&preliminary notification of transportation problem.DISTRIBUTION CODE: DF03D COPIES RECEIVED:LTR ENCL SIZE: TITLE: Direct Flow Distribution: | | Constitutes initial & preliminary notification of P transportation problem. |
| Subject Files&40,70,71 Dkts w out LPDRs P NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). | | DISTRIBUTION CODE: DF03D COPIES RECEIVED:LTR ENCL SIZE: |
| 05000244 0 RECIPIENT ID CODE/NAME TNTERNRL: P L'RETE 01 EXTERNAL LITCO BRYCE g J H COPIES LTTR ENCL RECIPIENT ID CODE/NAME COPIES LTTR ENCL NRC PDR NUDOCS-ABSTRACT 1 D U YO'I'E TO ALL"RI DS" RECIPI EYTS: i Ly:mE IIELP US ro Rr DUCE iVASTI:.COYWPC I"I I<I;DOCL~<ri"r C:O~"I'ROL DESk, ROOII,I PI.37 (EVI: 504.0(83)TO F I.IMIY~VI'E 5'OI'R HAMI.I f<O)I DISTRII)I)l'IO'v'ISTS FOR DOOl'MIEN"I S')'OL'OY,'1 NEF D!TOTAL NUMBER OF COPIES REQUIRED: LTTR 4 ENCL t t EP ER ASSOCIATES 1010 ARROyo AVe., SAN FERNANDO, CALIFORNIA 91340-1822 818-898-2361 FAX 818-361-8095 January 19, 1995 Cass R.Chappell Section Leader Cask Certification Section Storage and Transport Systems Branch Division of Industrial and Medical Nuclear Safety, NMSS Director, Office of Nuclear Material and Safeguards U.S.Nuclear Regulatory Commission Washington, D.C.20555 | | TITLE: Direct Flow Distribution: Subject Files & 40,70,71 Dkts w out LPDRs NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 0 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL TNTERNRL: |
| | P L'RETE 01 NUDOCS-ABSTRACT 1 EXTERNAL LITCO BRYCE g J H NRC PDR D |
| | U YO'I'E TO ALL"RI DS" RECIPI EYTS: |
| | i Ly:mE IIELP US ro Rr DUCE iVASTI:. COYWPC I"II<I; DOCL~<ri"rC:O~"I'ROL DESk, ROOII,I PI.37 (EVI: 504.0(83 ) TO F I.IMIY~VI'E5'OI 'R HAMI. I f<O) I DISTRII)I)l'IO'v'ISTS FOR DOOl'MIEN"IS ')'OL'OY,'1 NEF D! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 4 ENCL |
| | |
| | t ASSOCIATES t |
| | EP ER 1010 ARROyo AVe., SAN FERNANDO, CALIFORNIA 91340-1822 818-898-2361 FAX 818-361-8095 January 19, 1995 Cass R. Chappell Section Leader Cask Certification Section Storage and Transport Systems Branch Division of Industrial and Medical Nuclear Safety, NMSS Director, Office of Nuclear Material and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
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| ==Reference:== | | ==Reference:== |
| | 10CFR71.95 Reports. |
| | This letter will constitute the initial and preliminary notification of a transportation problem. |
| | On Tuesday, January 17, 1995, J.L. Shepherd and Associates was notified by Rochester Gas and Electric that there was a problem with the receipt of a Type A transportation package. |
| | Note: there was no breach or loss of containment of the 7ype A package, there was no release of the sources or exposures above the White I diamond label under which this package was shipped, and as a device containing radioactive materials (an Eberline Model 1000B), the operating system damage failed in the fully "safe" mode, the sources could not be exposed operationally. |
| | The Type A shipment left J.L. Shepherd and Associates on January 11, 1995 on a Nation Wide Transportation truck. The type A container was mounted on a heavy duty 48" x 48" skid, with, blocking to prevent movement, surrounded by a heavy duty box. The box was marked as fol-lows: 2 each, White I diamond labels, on opposite sides; 2 each, labels containing the Con-tainer No., Gross weight, "USA DOT 7A, Type A, (RQ) Radioactive Materials, Special Form, N.O.S., UN2974 (Inside Container. Complies with Prescribed Regulations) below the diamond label; 4 each, on each side, "Fragile" stickers; 4 each "This Side Vp" labels; and 1 each "Tip-N-Tell" indicator. |
| | The shipment was delivered by Kerr Freight Lines to Rochester Gas and Electric. Rochester Gas and Electric reported that the shipment was received without either the box or the skid, that the Type A container was damaged and that there was no indication that it was a radioac-tive material shipment, except for the receiver. According to Rochester Gas and Electric, (to paraphrase) the driver was glad to have it off of his truck because it had been rolling around. |
| | According to later preliminary reports and photographs from Rochester Gas and Electric, the source shield is not damaged and the sources are completely secured within the shield. Radia-tion levels are in accordance with the levels as shipped from J.L. Shepherd and Associates. |
| | Preliminary reports do show damage to the devices operating and interlock systems; however the sources cannot be moved to the exposed position. A complete damage estimate will be made by a J.L. Shepherd and Associates'ngineer effects complete system operational check-9501270213 950119 PDR ADOCK 05000244 p PDR |
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| 10CFR71.95 Reports.This letter will constitute the initial and preliminary notification of a transportation problem.On Tuesday, January 17, 1995, J.L.Shepherd and Associates was notified by Rochester Gas and Electric that there was a problem with the receipt of a Type A transportation package.Note: there was no breach or loss of containment of the 7ype A package, there was no release of the sources or exposures above the White I diamond label under which this package was shipped, and as a device containing radioactive materials (an Eberline Model 1000B), the operating system damage failed in the fully"safe" mode, the sources could not be exposed operationally.
| | U.S.N.R.C. |
| The Type A shipment left J.L.Shepherd and Associates on January 11, 1995 on a Nation Wide Transportation truck.The type A container was mounted on a heavy duty 48" x 48" skid, with, blocking to prevent movement, surrounded by a heavy duty box.The box was marked as fol-lows: 2 each, White I diamond labels, on opposite sides;2 each, labels containing the Con-tainer No., Gross weight,"USA DOT 7A, Type A, (RQ)Radioactive Materials, Special Form, N.O.S., UN2974 (Inside Container.
| | Office of Nuclear Material and Safeguards January 19, 1995 Page 2. |
| Complies with Prescribed Regulations) below the diamond label;4 each, on each side,"Fragile" stickers;4 each"This Side Vp" labels;and 1 each"Tip-N-Tell" indicator.
| | out repairs. Both Rochester Gas and Electric and J.L. Shepherd and Associates is in the process of establishing when and where the damage occurred and are starting a transportation claim action. |
| The shipment was delivered by Kerr Freight Lines to Rochester Gas and Electric.Rochester Gas and Electric reported that the shipment was received without either the box or the skid, that the Type A container was damaged and that there was no indication that it was a radioac-tive material shipment, except for the receiver.According to Rochester Gas and Electric, (to paraphrase) the driver was glad to have it off of his truck because it had been rolling around.According to later preliminary reports and photographs from Rochester Gas and Electric, the source shield is not damaged and the sources are completely secured within the shield.Radia-tion levels are in accordance with the levels as shipped from J.L.Shepherd and Associates.
| | On January 18, 1995, J.L. Shepherd and Associates ascertained that our Chemtrec 800 Emer-gency Response Phone Number had not been called from the date this shipment left San Fernando until the time it arrived at Rochester Gas and Electric. |
| Preliminary reports do show damage to the devices operating and interlock systems;however the sources cannot be moved to the exposed position.A complete damage estimate will be made by a J.L.Shepherd and Associates'ngineer effects complete system operational check-9501270213 950119 PDR ADOCK 05000244 p PDR
| | On January 19, 1995, Rochester Gas and Electric informed us that their on-site U.S.N.R.C. |
| | inspector has reported this situation to Region I. Although there seems to be no "instance in which there is a significant reduction in the effectiveness of the packaging", the sources re-mained intact and secure in the 7A package despite damage to the package, tlie U.S.N.R.C. |
| | notification process has started; therefore, J.L. Shepherd and Associates is providing notifica-tion to this office (within the prescribed 30 day notification period). |
| | If we may provide you with additional information, please advise. |
| | Sincerely, |
| | 'a J.L. SHEPHERD AND ASSOCIATES Mary F. Shepherd Vice President |
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| U.S.N.R.C.
| | ~ ~ |
| Office of Nuclear Material and Safeguards January 19, 1995 Page 2.out repairs.Both Rochester Gas and Electric and J.L.Shepherd and Associates is in the process of establishing when and where the damage occurred and are starting a transportation claim action.On January 18, 1995, J.L.Shepherd and Associates ascertained that our Chemtrec 800 Emer-gency Response Phone Number had not been called from the date this shipment left San Fernando until the time it arrived at Rochester Gas and Electric.On January 19, 1995, Rochester Gas and Electric informed us that their on-site U.S.N.R.C.
| |
| inspector has reported this situation to Region I.Although there seems to be no"instance in which there is a significant reduction in the effectiveness of the packaging", the sources re-mained intact and secure in the 7A package despite damage to the package, tlie U.S.N.R.C.
| |
| notification process has started;therefore, J.L.Shepherd and Associates is providing notifica-tion to this office (within the prescribed 30 day notification period).If we may provide you with additional information, please advise.Sincerely, J.L.SHEPHERD AND ASSOCIATES
| |
| 'a Mary F.Shepherd Vice President
| |
| ~~ | |
| DISTRIBUTION: | | DISTRIBUTION: |
| DOCKET NO(S)5O 244+Dock't F'i'le+PDI-3 Reading Adohnson SLittle sUBJEGT: R.E.Ginna Nuclear Poy/er Plant The following documents concerning our review of the subject facility are transmitted for your information.
| | +Dock 't F'i'le+ |
| DESCRIPTION OF DOCUMENT Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availability of Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice;Applications and Amendments to Operating Licenses Involvin No Si nifIcant Hazards Conditions See Page(s)Exemption DATED Construction Permit No.CPPR-Facility Operating License No.Order Monthly Operating Report for Annual/Semi-Annual Report: Other , Amendment No.,Amendment No.transmitted by Letter transmitted by Letter See attacl d Sifkhbi QU i@A'KA%glrtMects | | PDI-3 Reading Adohnson SLittle DOCKET NO(S) 5O 244 sUBJEGT: R.E. Ginna Nuclear Poy/er Plant The following documents concerning our review of the subject facility are transmitted for your information. |
| -IiI<See aI(:tetched As Stated CC: OFFICE>SURNAME>OATEN NRC FORM 318 Ito/SOI NRCM 0240 OFFICIAL RECORD COPY 0 r ll 4 Ginna Nuclear Powe Plant Semiannual Radioactive. | | DESCRIPTION OF DOCUMENT DATED Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availability of Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No. |
| effluent release rept for Jan-June, dated 6/30/94. | | Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses Involvin No Si nifIcant Hazards Conditions See Page(s) |
| Chief, Branch of Federal Activities Division of Habitat Conservation 400 ARLSg: U.S.Fish and Wildlife Service 1849 C Street, N.W.Washington, D.C.20240 Dr.William, C.Cunningham FDA Research Chemist NIST Building 235/B125 Gaithersburg, HD 20899 Paul A.Giardina Radiation Program Manager, Region 2 Environmental Protection Agency Room 1137-L 26 Federal Plaza New York, NY 10276}} | | Exemption Construction Permit No. CPPR- , Amendment No. |
| | Facility Operating License No. ,Amendment No. |
| | Order Monthly Operating Report for transmitted by Letter Annual/Semi-Annual Report: See attacl d transmitted by Letter Other Sifkhbi QU i@A'KA%glrtMects |
| | - IiI< |
| | See aI(:tetched As Stated CC: |
| | OFFICE> |
| | SURNAME> |
| | OATEN NRC FORM 318 Ito/SOI NRCM 0240 OFFICIAL RECORD COPY |
| | |
| | 0 r ll 4 |
| | |
| | Ginna Nuclear Powe Plant Semiannual Radioactive. effluent release rept for Jan-June, dated 6/30/94. |
| | |
| | Chief, Branch of Federal Activities Division of Habitat Conservation 400 ARLSg |
| | : U.S. Fish and Wildlife Service 1849 C Street, N.W. |
| | Washington, D.C. 20240 Dr. William, C. Cunningham FDA Research Chemist NIST Building 235/B125 Gaithersburg, HD 20899 Paul A. Giardina Radiation Program Manager, Region 2 Environmental Protection Agency Room 1137-L 26 Federal Plaza New York, NY 10276}} |
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Category:CORRESPONDENCE-LETTERS
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Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
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ML17265A7631999-10-0505 October 1999
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ML17265A7641999-10-0505 October 1999
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ML20212J3561999-09-30030 September 1999
Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
IR 05000244/19992011999-09-24024 September 1999
Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld
ML17265A7461999-08-31031 August 1999
Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML17265A7401999-08-26026 August 1999
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Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17250B3021999-08-23023 August 1999
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ML17265A7271999-07-30030 July 1999
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Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
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Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
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ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
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ML17265A6751999-06-11011 June 1999
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Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
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ML17265A6611999-05-24024 May 1999
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ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
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ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999
Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
ML17265A7651999-10-0808 October 1999
Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request
ML17265A7631999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000
ML17265A7641999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel
ML20212J3561999-09-30030 September 1999
Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7461999-08-31031 August 1999
Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML17265A7401999-08-26026 August 1999
Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A7411999-08-26026 August 1999
Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
ML17265A7061999-07-22022 July 1999
Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
ML17265A7191999-07-21021 July 1999
Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
ML17265A7141999-07-21021 July 1999
Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
ML17265A7041999-07-16016 July 1999
Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
[Table view] |
Text
1 M'< DOCS OI:I:SI'I I; I::~cll.l'IY)
REGULATG~ INFORMATION DISTRIBUTION~STEM (RIDS)
I ACCESSION NBR:9501270213 DOC.DATE: 95/01/19 NOTARIZED: NO DOCKET g FACIL:50-244 Robert Emmet Ginna Nuclear plant, Unit 1, Rochester G 050pp244 AUTH. NAME AUTHOR AFFILIATION SHEPHERD,M.F. J.L. Shepherd & Associates RECIP.NAME RECIPIENT AFFILIATION CHAPPELL,C.R. Division of Industrial & Medical Nuclear Safety (Post 8707
SUBJECT:
Constitutes initial & preliminary notification of P transportation problem.
DISTRIBUTION CODE: DF03D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Direct Flow Distribution: Subject Files & 40,70,71 Dkts w out LPDRs NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 0 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL TNTERNRL:
P L'RETE 01 NUDOCS-ABSTRACT 1 EXTERNAL LITCO BRYCE g J H NRC PDR D
U YO'I'E TO ALL"RI DS" RECIPI EYTS:
i Ly:mE IIELP US ro Rr DUCE iVASTI:. COYWPC I"II<I; DOCL~<ri"rC:O~"I'ROL DESk, ROOII,I PI.37 (EVI: 504.0(83 ) TO F I.IMIY~VI'E5'OI 'R HAMI. I f<O) I DISTRII)I)l'IO'v'ISTS FOR DOOl'MIEN"IS ')'OL'OY,'1 NEF D!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 4 ENCL
t ASSOCIATES t
EP ER 1010 ARROyo AVe., SAN FERNANDO, CALIFORNIA 91340-1822 818-898-2361 FAX 818-361-8095 January 19, 1995 Cass R. Chappell Section Leader Cask Certification Section Storage and Transport Systems Branch Division of Industrial and Medical Nuclear Safety, NMSS Director, Office of Nuclear Material and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Reference:
10CFR71.95 Reports.
This letter will constitute the initial and preliminary notification of a transportation problem.
On Tuesday, January 17, 1995, J.L. Shepherd and Associates was notified by Rochester Gas and Electric that there was a problem with the receipt of a Type A transportation package.
Note: there was no breach or loss of containment of the 7ype A package, there was no release of the sources or exposures above the White I diamond label under which this package was shipped, and as a device containing radioactive materials (an Eberline Model 1000B), the operating system damage failed in the fully "safe" mode, the sources could not be exposed operationally.
The Type A shipment left J.L. Shepherd and Associates on January 11, 1995 on a Nation Wide Transportation truck. The type A container was mounted on a heavy duty 48" x 48" skid, with, blocking to prevent movement, surrounded by a heavy duty box. The box was marked as fol-lows: 2 each, White I diamond labels, on opposite sides; 2 each, labels containing the Con-tainer No., Gross weight, "USA DOT 7A, Type A, (RQ) Radioactive Materials, Special Form, N.O.S., UN2974 (Inside Container. Complies with Prescribed Regulations) below the diamond label; 4 each, on each side, "Fragile" stickers; 4 each "This Side Vp" labels; and 1 each "Tip-N-Tell" indicator.
The shipment was delivered by Kerr Freight Lines to Rochester Gas and Electric. Rochester Gas and Electric reported that the shipment was received without either the box or the skid, that the Type A container was damaged and that there was no indication that it was a radioac-tive material shipment, except for the receiver. According to Rochester Gas and Electric, (to paraphrase) the driver was glad to have it off of his truck because it had been rolling around.
According to later preliminary reports and photographs from Rochester Gas and Electric, the source shield is not damaged and the sources are completely secured within the shield. Radia-tion levels are in accordance with the levels as shipped from J.L. Shepherd and Associates.
Preliminary reports do show damage to the devices operating and interlock systems; however the sources cannot be moved to the exposed position. A complete damage estimate will be made by a J.L. Shepherd and Associates'ngineer effects complete system operational check-9501270213 950119 PDR ADOCK 05000244 p PDR
U.S.N.R.C.
Office of Nuclear Material and Safeguards January 19, 1995 Page 2.
out repairs. Both Rochester Gas and Electric and J.L. Shepherd and Associates is in the process of establishing when and where the damage occurred and are starting a transportation claim action.
On January 18, 1995, J.L. Shepherd and Associates ascertained that our Chemtrec 800 Emer-gency Response Phone Number had not been called from the date this shipment left San Fernando until the time it arrived at Rochester Gas and Electric.
On January 19, 1995, Rochester Gas and Electric informed us that their on-site U.S.N.R.C.
inspector has reported this situation to Region I. Although there seems to be no "instance in which there is a significant reduction in the effectiveness of the packaging", the sources re-mained intact and secure in the 7A package despite damage to the package, tlie U.S.N.R.C.
notification process has started; therefore, J.L. Shepherd and Associates is providing notifica-tion to this office (within the prescribed 30 day notification period).
If we may provide you with additional information, please advise.
Sincerely,
'a J.L. SHEPHERD AND ASSOCIATES Mary F. Shepherd Vice President
~ ~
DISTRIBUTION:
+Dock 't F'i'le+
PDI-3 Reading Adohnson SLittle DOCKET NO(S) 5O 244 sUBJEGT: R.E. Ginna Nuclear Poy/er Plant The following documents concerning our review of the subject facility are transmitted for your information.
DESCRIPTION OF DOCUMENT DATED Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availability of Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses Involvin No Si nifIcant Hazards Conditions See Page(s)
Exemption Construction Permit No. CPPR- , Amendment No.
Facility Operating License No. ,Amendment No.
Order Monthly Operating Report for transmitted by Letter Annual/Semi-Annual Report: See attacl d transmitted by Letter Other Sifkhbi QU i@A'KA%glrtMects
- IiI<
See aI(:tetched As Stated CC:
OFFICE>
SURNAME>
OATEN NRC FORM 318 Ito/SOI NRCM 0240 OFFICIAL RECORD COPY
0 r ll 4
Ginna Nuclear Powe Plant Semiannual Radioactive. effluent release rept for Jan-June, dated 6/30/94.
Chief, Branch of Federal Activities Division of Habitat Conservation 400 ARLSg
- U.S. Fish and Wildlife Service 1849 C Street, N.W.
Washington, D.C. 20240 Dr. William, C. Cunningham FDA Research Chemist NIST Building 235/B125 Gaithersburg, HD 20899 Paul A. Giardina Radiation Program Manager, Region 2 Environmental Protection Agency Room 1137-L 26 Federal Plaza New York, NY 10276
