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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny 1999-09-30
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20206U3551999-02-0505 February 1999 Refers to Concerns Recipient Expressed to V Dricks on 990126 Related to Oyster Creek About Event Which Occurred on 970801 & About Administrative Control of EDG Vendor Manuals ML20199L2471999-01-22022 January 1999 Discusses GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 & Gpu Nuclear 960418 & 981202 Responses for Ocngs.Informs That Based on Confirming GL 96-01 Commitments Review Effort Closed ML20199G8241999-01-12012 January 1999 Responds to Ltr to Senator Lt Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20199G8631999-01-0707 January 1999 Responds to Ltr to Senator Lt Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20198B2121998-12-0909 December 1998 Advises of Planned Insp Efforts Resulting from Licensee Irpm Review.Historical Listing of Plant Issues & Details of Insp Plan for Next 6 Months Encl ML20196C6001998-11-25025 November 1998 Forwards Insp Rept 50-219/98-09 on 980914-1025 & Notice of Violation.Inspector Identified That Security Force Member Left Running Unlocked Vehicle Unattended in Protected Area ML20195G8901998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G9101998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G8801998-11-17017 November 1998 Responds to to Senator Lt Conners Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G9181998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community IR 05000219/19980031998-11-13013 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/98-03 Issued on 980717.Corrective Actions Will Be Examined During Future Insp of Licensed Program ML20196D1431998-11-10010 November 1998 Forwards Exam Forms with Answers,Results Summary for Plant & Individual Answer Sheets of GFE Section of Written Operator Licensing Exam,Administered on 981007.Without Encl ML20195C4111998-11-0606 November 1998 Discusses 980825 Gpu Submittal of Proposed Mod for Ocnpp Core Support Plate Which Involved Installation of Wedges During 17R Outage.Licensee Intends to Use Recommendations of BWRVIP-25 & BWRVIP-50.SE Accepting Proposed Mod Encl ML20195B7981998-11-0505 November 1998 Discusses Alternative Evaluation of Flaws in Ferritic Piping.Core Spray Sys Test Line Was Concluded to Have Acceptable Level of Quality & Safety ML20155C6881998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7201998-10-29029 October 1998 Responds to Ltr to Assemblyman Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7051998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7481998-10-29029 October 1998 Responds to Ltr to Assemblyman Morgan, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6241998-10-29029 October 1998 Responds to Ltr to Senator Connors,Dtd 980926,re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7021998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6661998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6841998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6721998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7251998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7371998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6981998-10-29029 October 1998 Responds to Recent Ltr to Senator Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6481998-10-29029 October 1998 Responds to Ltr to Sentor Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7091998-10-29029 October 1998 Responds to Ltr to Assemblyman Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C8781998-10-29029 October 1998 Informs That Oyster Creek Generating Station Operating License,Paragraph 2.C.5 Re Evaluation of Core Spray Internals Insp Requires Authorization from NRC Before Plant Is Restarted from Refueling Outage.Plant Restart Authorized ML20155C7301998-10-29029 October 1998 Responds to Ltr to 9th District Legislative Offices, Re Possible Closure of Oyster Creek Nuclear Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155D2041998-10-26026 October 1998 Forwards Synopsis of 980604 Investigation Rept 1-98-027 Re Possible Discrimination Against Employee for Contacting NRC in Nov 1997 with Security & Safety Concerns ML20154Q9021998-10-20020 October 1998 Forwards Insp Rept 50-219/98-08 on 980727-0913.No Violations Noted.Licensee Have Established & Implemented Effective Programs for Initial & Continuing Training of Workers, Especially Those Having Access to Controlled Areas ML20154L3001998-10-14014 October 1998 Forwards Safety Evaluation Re Reduced Scope of IGSCC Insp, During Refueling Outage 17 ML20154J8251998-10-0707 October 1998 Discusses Concerns Raised to NRC on 980913 Re Oyster Creek. Thoroughness of NRC Insps as Documented in NRC Integrated Insp Rept 50-219/98-03 Was of Concern 1999-09-30
[Table view] |
See also: IR 05000219/1996009
Text
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June 20, 1997 ,
Mr. Michael B. Roche
Vice President and Director
GPU Nuclear Corporation
Oyster Creek Nuclear Generating Station
P.O. Box 388
Forked River, New Jersey 08731
SUBJECT: NRC INTEGRATED INSPECTION REPORTS 50-219/96-09 and 50-219/96-11
AND NOTICE OF VIOLATION
Dear Mr. Roche:
This letter refers to your January 24,1997 correspondence, in response to our
December 6,1996 and January 2,1997 letters.
Thank you for informing us of the corrective and preventive actions documented in your
letter. These actions will be examined during a future inspection of your licensed program.
Your cooperation with us is appreciated.
Sincerely,
Original Signed By:
Peter W. Eselgroth, Chief
Projects Branch 7
Division of Reactor Projects
Docket No.: 50-219
cc: w/o cy of Licensee's Response Letter
G. Busch, Manager, Site Licensing, Oyster Creek
M. Laggart, Manager, Corporate Licensing
cc: w/cy of Licensee's Response Letter
State of New Jersey
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PDR ADOCK 05000219
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Distribution w/cv of Licensee Response Letter
Region I Docket Room (with concurrences)
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Nuclear Safety Information Center (NSIC)
PUBLIC
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NRC Resident inspector
D. Screnci, PAO
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P. Eselgroth, DRP
I D. Haverkamp, DRP
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J. Nick, DRP
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C. O'Daniell, DRP
l W. Dean, OEDO l
i P. Milano, NRR/PD l-3 .
! R. Eaton, NRR/PD 1-3
i R. Correia, NRR
l D. Taylor, NRR
! Inspection Program Branch, NRR (IPAS)
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! DOCUMENT NAME: G:\ BRANCH 7\REPLYLTR\OC960911 rpy
To recdve e copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy
OFFICE ~31/DRP W Rl/DRP /
NAME JNick fJ PEselgroth
DATE fA7/97 6 //f/97
OFFICIAL RECORD COPY
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January 24, 1997
6730-97-2030
U. S. Nuclear Regulatory Commission
Attention: Document Control Desk
Washington, DC 20555
Dear Sir.
Subject: Oyster Creek Nuclear Generating Station
Docket No. 50 219
Reply to a Notice of Violation
inspection Reports: 96-09 and 96-11
in accordance with 10 CFR 2.201. Attachment I provides GPU Nuclear's response to the
violations identified in the subject inspection reports. During discussions held with Region 1 NRC
staff on January 6.1997, it was agreed that the due date for this response would be extended to
January 24,1997,
if you should have any questions or require further information, please contact Brenda
DeMerchant, Oyster Creek Regulatory Affairs Engineer, at 609-971-4642.
Very truly yours,
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Michael B. Roche
Vice President and Director
Oyster Creek
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NRC Project Manager
NRC Sr. Resident inspector
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Response to IR 96-009 Notice of Violations
Violation i
Technical Specification 6.81 states, written procedures shall be established. implemented, and
maintained that meet or exceed the requirements of NRC Regulatory Guide 1.33 -
NRC Regulatory Guide 1.33, Appendix A, Paragraphs 4 and I, state, in part, that procedures
should be prepared as appropriate, for Startup, Operation, and Shutdown of Safety-Related BWR !
Systems, including the Control Rod Drive System, and Administrative Procedures including
Equipment Control (e.g., Locking and Tagging).
1
Procedure 302.1, Control Rod Drive Hydraulic System, Revision 57, Section 10.0, Alternate
CRD Cooling and Drive Water Supply, Paragraph 10.3.5, Steps 10.3.5.1, and 10.3.5.2, directed
the operator to Open valves V-11-49 and V-ll-63 (to provide a water source for the Jockey _;
pump).
Contrary to the above, on September 17,1996, the operator f6?ed to follow the procedure and
opened valves V-ll-44 and V-Il-63. V-II-63 was subsequently closed to isolate a hose leak and
V-11-44 was left open. This valving error caused the cross connection of the fire water system
and the condensate transfer system and resulted in an unplanned and unmonitored release of
133,000 gallons of slightly radioactive water when the correct valve, V-l l-49, was opened to
place the alternate CRD system in service.
Procedure 108 5. Control of Locked Valves and Breakers, Revision 1, Section 4.1 1. the criteria
for locking valves shall be: Step 4.1.1.7 states, " Valves that are required to be positioned to
prevent contamination of other systems or areas (radiological, chemical, liquid waste, etc.) "
Contrary to the above, valve V-11-44, a valve that prevents cross contamination of the fire system
from the condensate transfer system, was not locked. This is a second example of failure to
follow procedure which contributed to the unplanned and unmonitored release of 133,000 gallons
of slightly radioactive water.
This is a severity Level IV violation. (Supplement I)
Response:
GPUN concurs with the violation as written.
Reason for the Violation:
l The root cause of the Procedure 302.1 violation was personnel error. The operator did not have
the procedure in hand when placing the jockey pump in service and did not properly self check his
- actions to ensure that the correct valve was manipulated.
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. The root cause of the Procedure 108.5 violation was proceduralinadequacy in that relevant
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information regarding the increased potential for cross contamination occurring while in the
temporary modification configuration was not addressed in the safety review for Procedure 3011
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l The Corrective Steos Taken and the Results Achieved. ;
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{ On September 18, at 0830. following the discoverv that an overboard discharge had occurred.
V-11-44 was locked closed and the jockey pump was relocated o a connection where there was
j no potential for an overboard discharge or cross-contamination to occur. Subsequent to this
! incident, operations personnel conducted an extensive investigation documented in a detailed
j critique.
l
Among the completed corrective actions as a result of this incident are the following:
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A walkdown was performed to ensure that p. >per controls are in place at other system interfaces
l where the potential for discharge or cross-contamination exists As a result, one other valve was
locked and warning signs were posted to indicate that a potential for cross-contamination exists
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- Valve V-l l-44 was renumbered V-9-2099, a Fire Protection System valve number.
$ Shortly after the incident, briefings were conducted with all licensed and non-licensed operators )
which included the following topics: i
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- e The need to maintain awareness of plant status above all other priorities was re-
i emphasized,
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! . Shift briefings to review plant status at the beginning of each shift were instituted;
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. The need to employ self-checking was re-emphasized,
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- e " Procedure in-hand" requirements were re-emphasized, j
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e The need to understand changing plant conditions and aggressively identify
unknown conditions was re-emphasized. 1
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A safety evaluation to address continued operation of the Fire Protection System as a
contaminated system was completed
The Corrective Steos that will be Taken to Avoid Further Violations:
Procedural guidance will be developed and training provided to assist operations personnel in
identifying tank inventories and expected changes during refueling outages when tank inventories
are subject to wide fluctuations;
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j The practice of allowing temporary modifications to be added to procedures without the
j Technical Evaluation form from Procedure 108 8 will be re-evaluated to ensure that controls are
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adequate
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, A standing order or procedural controls will be developed to include a listing of potential cross- )
[ contamination and overboard discharge points, instructions and restrictions, as needed, to ensure
l proper operation of the effected components, and instructions for response to a spill or discharge.
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These actions will be co.Nieted by the end of the first quarter,1997. 1
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l', Full compliance was achieved on September 18,1996, at 0830 when valve V-11-44 was closed
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i Code of Federal Regulations Title 10, Energy, Part 50.59, Changes, Tests and Experiments, l
l Section (a)(1), states that the holder of a license (i) may make changes to the facility as described !
j in the safety analysis report, and (ii) make changes in procedures as described in the safety
j analysis report without prior Commission approval, unless the proposed change involves a change
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in the Technical Specifications or involves an unreviewed safety question. Section (b)(1) states !
that the licensee shall maintain records of changes ... made pursuant to this section. Those
records must include a written safety evaluation which provides the basis for the determination .
that the change does not involve an unreviewed safety question l
Contrary to the above. a permanent change (September,1994) was made to Procedure 3021,
Control Rod Drive Hydraulic System and to the facility, as described in the safety analysis report
(SAR) involving use of a CRD " jockey pump" to provide a different means of providing a CRD
cooling and drive water supply than was described in the SAR without a written safety evaluation
to determine if an unreviewed safety question existed. A second minor example of failure to
perform a written safety evaluation as required by 10 CFR 50.59 occurred in July,1995, when an
annunciator alarm function described in the SAR was disabled.
This is a severity Level IV violation (Supplement 1)
Subsequent to receiving the above violation, the following similar violation was received in
Inspection Report 96-11:
Title 10. Code of Federal Regulations, Part 50 59, " Changes, Tests, and Experiments." (10 CFR )
50.59), Section (a)(1) requires, in part, that licensees may make changes in procedures as
described in the safety analysis report without prior NRC approval, unless the proposed change
involves an unreviewed safety question. Section (b)(2) of 10 CFR 50.59 requires, in part, that i
licensee's records of changes in procedures must include a written safety evaluation which
provides the bases for the determination that the change does not involve an unreviewed safety
question.
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Contrary to the above a written safety evaluation was not performed to provide the bases for the l
determination that a change to station procedure 336.3. " Generator Hydrogen Gas System," did l
not involve an unreviewed safety question. Specifically, on Febmary 23,1994, procedure 336.3 l
was changed to add instruction to manually adjust cooling How for the generator hydrogen I
coolers rather than using the automatic temperature control valve as described in the safety
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analysis repon, however, a written safety evaluation was not completed. '
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This is a severity level IV violation. I
Resnonse:
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GPU Nuclear concurs with the violations with regard to incomplete safety evaluations. The
practice of using a jockey pump is controlled as a temporary modification and, therefore, does
not constitute a permanent change to the facility.
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Eggon for the Violations:
The violations occurred due to personnel error in not accurately addressing the questions of the
GPU Nuclear 10 CFR 50.59 Safety Determination form used at that time.
The Corrective Steos Taken and Results Achieved
In all instances where inaccurate safety determinations have been performed the appropriate
system engineers have been assigneo action to review and revise or prepare, if necessary, a safety
evaluation which accurately re6ects the Safety Analysis Report (SAR) or propose a change to the ,
FS AR, if required l
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The Corrective Steps that will be taken to Avoid Further Violations:
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The Safety Review training program will be enhanced emphasizing the need to accurately answer
the safety determination questions and will include discussions of the tools available to assist in
these reviews (e g., computer databases, etc.). These violations will be used as examples to
emphasize the importance of performing thorough reviews and preparing complete
documentation, as well as examples of where SAR revisions are warranted.
A " Safety Review Newsletter" will be prepared and issued to all qualified safety reviewers
clarifying and reinforcing expectations as well as citing these examples ofimproper safety .
evaluations. l
Full compliance will be achieved when the appropriate system engineer has reviewed the incorrect
safety determination and revises or updates / corrects it. Cited safety evaluations involving
recurring outage related modifications (jockey pump) will be completed six months prior to the
next outage which is currently scheduled for October,1998. Safety evaluations involving the
remaining inaccuracies will be reviewed and revised by the end of the first quarter,1997.
Regarding Station Procedure 336.3, " Generator Hydrogen Gas System," the continued operation
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of the plant while the safety evaluation is being written has been determined to be acceptable as
the Turbine Building Closed Cooling Water System is not Nuclear Safety Related and cools no
safety related components.-
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