Similar Documents at Ginna |
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Category:CORRESPONDENCE-LETTERS
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 IR 05000244/19990081999-10-14014 October 1999 Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy 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 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 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 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 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 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 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] |
See also: IR 05000244/1994017
Text
P R.IC)R.IWY'ACCELERATED
RIDS PROCESSING)
REGULATORY
INFORMATION
DISTRIBUTION
SYSTEM (RIDS)ACCESSION NBR:9409020133
DOC.DATE: 94/08/26 NOTARIZED:
YES FACIL:50-244
Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION
MECREDY,R.C.
Rochester Gas&Electric Corp.RECIP.NAME
RECIPIENT AFFILIATION
JOHNSON,A.R.
, Project Directorate
I-3 SUBJECT: Submits response to violations
noted in Insp Rept 50-244/94-17.Corrective
actions: items identified
by inspector appropriately
capped, plugged or sealed.DISTRIBUTION
CODE: IE01D COPIES RECEIVED:LTR
ENCL I SIZE-TITLE: General (50 Dkt)-Insp Rept/Notice
of Vio ation Response NOTES:License
Exp date in accordance
with 10CFR2,2.109(9/19/72).
DOCKET 05000244 05000244 RECIPIENT ID CODE/NAME PD1-3 PD INTERNAL: AEOD/DEIB AEOD/SPD/RRAB
DEDRO NRR/DRCH/HHFB
NUDOCS-ABSTRACT
~~OGC/HDS3 RES/HFB EXTERNAL: EG&G/BRYCE, J.H.NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME JOHNSON,A AEOD/SPD/RAB
AEOD/TTC NRR/DORS/OEAB
NRR/PMAS/IRCB-E
OE DIR~DR~TL~E 02 RGN1 FILE 01 NOAC COPIES LTTR ENCL 1 1 1, 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37<E>lT.504-2083)TO ELI!iIINATE
YOUR NAME FROM DISTRIBUTION
LISTS f OR DOCUMENTS YOU DON'T NEED!OTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19
,",I j ir7Zu~lrX li,",'Z'fll'i'll~
ROCHESTER GAS AND ELECTRIC CORPORATION
ROBERT C MECREDY Vice President Clnne Nucleer Production
II c W t/o'roe@~89 EAST AVENUE, ROCHESTER N.K 14649-0001
TELEPHONE AREA CODE 7t8 546'2700 August 26, 1994 U.S.Nuclear Regulatory
Commission
Document Control Desk Attn: Allen R.Johnson PWR Project Directorate
I-3 Washington, D.C.20555 Subject: Reply to a Notice of Violation Ginna Procurement
Inspection
94-17, dated July 15, 1994 R.E.Ginna Nuclear Power Plant Docket No.50-244 Dear Mr.Johnson: During an NRC inspection
conducted from June 27 through July 1, 1994, a violation of NRC requirements
was identified.
In accordance
with the"General Statement of Policy and Procedure for NRC Enforcement
Actions," 10 CFR Part 2, Appendix C, the violation is listed below: "10 CFR 50, Appendix B, Criterion VIII, states, in part,"Measures shall be established
for the identification
and control of materials, parts, and components," and Criterion XVI, states, in part,"Measures shall be established
to assure that conditions
adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances
are promptly identified
and corrected." Ginna Station,"Quality Assurance Manual," Section No.13,"Handling, Storage, and Shipping" requirement
that states, in part,"...procedures
shall require adherence to supplier's
requirements
or alternate requirements
so that the quality of items is maintained
while they are handled or stored prior to installation
or use," and"Deficiencies
noted during periodic inspections
of storage areas shall be documented
and corrected." Ginna Procedures
A-407,"Evaluation
of Items for In-Storage
Maintenance
Requirements," A-701,"Receipt and Acceptance
of Materials/Parts," and A-1501,"Control of Non-Conforming
Materials," implement the above requirements.
~.OI (T, Q 8'7 q40q0201~>
50002 94092&pop PDQC pop Q+Cgo l~
Letter: 'age 2 Subject: Violation Response 94-17-01 Date;August 26, 1994 Contrary to the above, as of July 1, 1994, handling, preservation, storage, cleaning, packaging, and inspection
activities
associated
with safety-related
items were not properly performed by the Inventory Control personnel in the Ginna Station Level B storeroom in that: (1)items were not stored with protective
caps and plugs;(2)items were not cleaned before being stored in the storage area;and (3)none'onforming
items were not reported on a nonconformance
form by Material, Procurement, and Budget personnel, nor by Quality Assurance personnel as required by Ginna Station Procedure A-1502,"Nonconformance
Reports." This is a Severity Level IV violation (Supplement
1)" The response to the violation is provided separately
for each of the three conditions
stated.A.Response for Items Stored Without Caps and Plugs (1)The reason for the violation, or, if contested, the basis for disputing the violation:
Rochester Gas and Electric Corporation (RG&E)accepts the violation, and acknowledges
that some items were not stored with protective
caps, plugs, or seals.At the time of the NRC inspection, an existing and ongoing packaging upgrade program was in place, and the initial upgrading of packaging had not yet been completed for all items.Therefore, there were still some items, as identi-fied by the.inspector, that had not been adequately
capped, plugged, or sealed.(2)The corrective
steps that have been taken and the results achieved: The items identified
by the inspector were appropriately
capped, plugged, or sealed.Management
completed a comprehensive
inspection
of materials in various storage areas to assess the extent of the missing caps, plugs, and seals.The results indicated that there were only a few isolated cases of missing caps, plugs, or seals.All of these deficiencies
were immediately
corrected.
Management
expectations
and standards regarding the importance
of caps, plugs, or seals have been reaffirmed
to the Inventory Control organization.
(3)The corrective
steps that will be taken to avoid further violations:
The packaging upgrade program will continue.Inventory Control management
will periodically
perform inspections
of materials in selected storage areas to assess the effectiveness
of packaging.
Inventory Control training modules will be reviewed to ensure the issue of adequate packaging is addressed.
Quality Assurance will perform an assessment
of these corrective
steps.
Letter: 'ubject: Date: Page 3 Violation Response 94-17-01 August 26, 1994 (4)The date when full compliance
will be achieved: Full compliance
was achieved for those items with identified
cap, plug, or seal deficiencies
on July 18, 1994, when these deficiencies
were corrected.
B.Response for Items not Cleaned Before Being Stored (1)The reason for the violation, or, if contested, the basis for disputing the violation:
RG&E accepts the violation, and acknowledges
that some Foxboro modules were physically
located in the Level B storeroom and had not been cleaned.The items were in the storage area awaiting formal processing
and integration
into existing stock and thus had not been cleaned.These modules still had an existing film of dust on the terminal ends.(2)The corrective
steps that have been taken and the results achieved: The modules were cleaned to conform to the requirements
for a Level B Storage Area.Management
performed a representative
sampling of items in various storage areas, to assess the extent of cleanliness
concerns.No other items were identified
as not being cleaned.Management
expectations
and standards regarding the importance
of cleanliness
of items in Level B storage areas have been reaffirmed
to the responsible
organization.
(3)The corrective
steps that will be taken to avoid further violations:
Quality Assurance will perform an assessment
of the cleanliness
of items located in storage areas.Inventory Control training modules will be reviewed to ensure the issue of cleaning of items, prior to items being physically
located in storage areas, is addressed.
(4)The date when full compliance
will be achieved: Full compliance
was achieved on July 7, 1994, when these Foxboro modules were cleaned.
Letter: Subject: Date: Page 4 Violation Response 94-17-01 August 26, 1994 C.Response for Nonconforming
Items not Reported The reason for the violation, or, if contested, the basis for disputing the violation:
RG&E acknowledges
that a nonconformance
report (NCR)was not initiated for grease seepage from some Limitorque
limit switches that were in storage.This seepage was previously
identified
by RG&E personnel, who immediately
contacted appropriate
RG&E and site technical personnel to determine the possible need for the initiation
of an NCR.In accordance
with administrative
procedure A-1502,"Nonconformance
Reports", a determination
was made that the grease seepage was not a condition deleterious
to the limit switches, was not a nonconforming
condition, and, therefore, did not constitute
a violation of requirements.
(2)The corrective
steps that have been taken and the results achieved: As a result of this NRC inspection, NCR 94-114 was initiated by Inventory Control to report this condition.
This NCR has been processed.
The results confirm that no nonconforming
condition existed, and that an NCR was not appropriate
for the identified
condition.
RG&E received documentation
from the manufacturer's
engineering
organization
substantiating
the conclusion
that seeping grease is not an issue of concern.The manufacturer
stated that it is a characteristic
of this grease that some oil may separate from the grease base when the grease is dormant for extended periods.Separation
of oil and grease should be expected when a geared limit switch is in storage for long periods.This separation
is not detrimental
to the function of the switch.When a switch is to be removed from storage to be placed in service, the switch should be wiped to remove any accumulation
of oil which may have occurred during storage..Management
investigated
Inventory Control's understanding
of the nonconformance
report program and reviewed NCRs that had been initiated by Inventory Control in the past.The results indicated to management
that Inventory Control personnel have an acceptable
level of understanding
of the nonconformance
report program.The corrective
steps that will be taken to avoid further violations:
Based on the results of the actions taken, no further corrective
steps are needed.
Letter: Subject: Date: Page 5 Violation Response 94-17-01 August 26, 1994 (4)The date when full compliance
will be achieved: RG&E has been, and continues to be, in full compliance.
Very T y Yours, Robert C.Mecredy Subscribed
and sworn to before me on this 26th day of August, 1994 KAP-.4 Q, j()})g~~c+~)Pl:uric: Ill l~~~wAYlvc couypy Cocntni~~~~~(.Q xc: Mr.Allen R.Johnson (Mail Stop 14D1)PWR Project Directorate
1-3 Washington, D.C.20555 U.S.Nuclear Regulatory
Commission
Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector