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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
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k June 8, 1998 Mr. Michael Vice President and Director GPU Nuclear, Inc.
Oyster Creek Nuclear Generating Station P.O. Box 388 Forked River, New Jers.ey 08731 SUBJECT: SPECIAL INSPECTION NO. 50-219/98-04 AND ..JTICE OF VIOLATION (REPLY)
Dear Mr. Roche:
This refers to your May 20,1998 correspondence, in response to our letter regarding Oyster Creek Generating Station dated April 15,1998. This correspondence dealt with the special inspection conducted on February 26 - March 18,1998. We have reviewed this matter in accordance with NRC Inspection Manual Procedure 92702.
Thank you for informing us of the corrective and preventive actions documented in your letter. We consider these actions acceptable pending further review in a future inspection of your licensed program.
We appreciate your cooperation.
Sincerely, ORIGINAL SIGNED BY:
John R. White, Chief Radiation Safety Branch Division of Reactor Safety Docket No. 50-219 cc w/o encl:
M. Laggart, Manager, Licensing and Vendor Audits G. Busch, Manager, Nuclear Safety and Licensing I cc w/ encl:
State of New Jersey a, o n n c 'n l i c. O U V 8 9006120372 990609 I' '
PDR ADOCK 05000219 G
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egion i Docket Room (with concurrences)
Nuclear Safety information Center (NSIC)
l PUBLIC NRC Resident irtpector M. Evans, DRP N. Perry, DRP D. Haverkamp, URP C. O'Daniell, DRP J. Jang, DRS J. White, DRS J. Yerokun, DRS C. Miskey, DRS (w/ copy of letter dated May 20,1998)
B. McCabe, OEDO C. Thomas, PD1-3, NRR R. Eaton, PD1-3, NRR T. Colburn, PDI-3, NRR R. Correia, NRR F. Talbot, NRR DOCDESK Inspection Program Branch, NRR (IPAS)
DOCUMENT NAME: G:\RSB\JANG\OC9804. REP To rscrivs a copy of this document, indicate in the box: 'C" = Copy without attachment / enclosure *E* = Copy with attachment / enclosure "N"=
No copy OFFICE Rl/DRS A E Rl/DRP ,
,f h p g l NAME JJang \ $$ MEvans g/jGfa JWifyV)
DATE 06/08/98 / () 06/r/98 ~ / L C6/(J68 06/ /98 06/ /98 g OFFICIAL Fy! CORD COPY
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{ GPU Nuclear,Inc.
( U.S. Route d South NUCLEAR Post Office Box 388 Forked River, NJ 08731-0388 Tel 609-9714000 May 20, 1998 1940-98-20272 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
Dear Sir:
Subject: Oyster Creek Nuclear Generating Station Docket No. 50-219 IR 98-004: Reply to Notice of Violations In accordance with 10CFR 2.201, the enclosed provides GPU Nuclear's response to the violations
< identified in the subject inspection report.
If you should have any questions, or require funher information, please contact Brenda DeMerchant, Oyster Creek Regulatory Affairs Engineer, at 609-971-4642.
Very tmly yours,
.-
Qj Michael # Vice President and Director Oyster Creek MBR/BDE/gl Attachment
! cc: Administrator, Region I -
(_ NRC Project Manager NRC Sr. Resident Inspector
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Attichmtnt 1
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IR 98-004 Response to Notices of Violation
! Violation 1 10 CFR 50.59, Changes, tests and experiments, specifies that the licensee may make changes to its facility and procedures as described in the safety analysis report and conduct tests or experiments not described in the safety analysis report without prior Commission
,. approval, provided the change does not involve a change in the technical specifications or
! an unreviewed safety question (USQ); and requires the licensee to maintain records of
- changes in the facility, including written safety evaluations providing the bases for the determination that the change does not involve a USQ. Section 6.3.1.1.2 of the Oyster l
Creek UFSAR (Update 8; 8/93) states that "during normal plant operations, when the system is in Standby, makeup to the Isolation Condensers is from the Demineralized Water Transfer System," a normally non-radioactive system.
Contrary to the above, since initial plant operation (1969), operators implemented Procedure 307, Isolation Condenser System (ICS), which permitted fill and make up to the isolation condensers during normal plant operations, when the system was in Standby, by a means other than the Demineralized Water Transfer System (DWTS). Specifically,
- operators used the Condensate Transfer System, a normally radioactively contaminated.
system, to fill and make up to the isolation condensers when the system was in Standby, and a safety evaluation was not developed or written to provide the bases for the determination that the change did not involve a USQ.
This is a Severity Level IV violation (Supplement 1).
Response:
GPUN concurs with the violation as stated.
Reason for Violation: i Several years ago, the Isolation Condensers were drained to support internal inspections and preservation as part of refueling outage activities. At that time, the System Operating Procedures were revised to refill the Isolation Condensers using Condensate Transfer which is the installed makeup source for operational use. Additionally, this revision included an option to use Condensate Transfer for evaporative losses. During that time
. period, safety reviews did not include as rigorous a review of the FSAR and other j- Licensing Bases Documents as is presently performed. As such, it was not identified that the FSAR specified that Demineralized Water would be used for evaporative makeup.
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. IR 98-004 R::sponse to Notices of Violation Page 2
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Since the plant's original configuration does not provide for any permanent connections for Isolation Condenser makeup from the Demineralized Water Transfer System, the operators failed to recognize this inconsistency with the FSAR and thought that it was acceptable to use Condensate Transfer for evaporative losses. Furthermore, the operators have been required to makeup to the Isolation Condenser more frequently than they normally would for evaporative losses due to inadequate seating of the Condensate Return Valve. Since the Demineralized Water Transfer System requires the installation of a temporary modification and can not be controlled from the Control Room, the operators did not consider Demineralized Water Transfer as the preferred makeup source.
Corrective Steps That Have Been Taken:
Upon discovery of this inconsistency, Operations Management prohibited usage of Condensate Transfer as the makeup source for evaporative losses.
The Corrective Steps that Will Be Taken to Avoid Further Violations:
A revision to the System Operating Procedure has been developed and is in final review.
This revision incorporates adequate controls to assure the makeup to the Isolation Condensers is from the Demineralized Water Transfer System while in standby (evaporative losses).
Date of Full Compliance:
Full compliance will be achieved when procedure is approved. This action is scheduled to be completed by the end of May,1998.
l Violation 2 Section 6.8.4.a.3 of Technical Specifications (TS) requires that a radioactive emuent )
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controls program shall be provided and include " Monitoring, sampling, and analysis of radioactive liquid and gaseous emuent in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM". Section 20.1302 of 10 CFR requires that
"The licensee shall make or cause to be made, as appropriate, surveys of radiation levels in unrestricted and controlled areas and radioactive materials in emuents released to unrestricted and controlled areas to demonstrate compliance with the dose limits for individual members of the public in Section 20.1301." Section 20.1301 of 10 CFR specifies dose limits for individual members of the public.
Contrary to the above requirements, at least since December 1996, the licensee's I radioactive emuent control program did not provide for the monitoring, sampling, and analysis of tritium that was generated and released from the isolation condenser system to i unrestricted and controlled areas in order to demonstrate compliance with the dose limits for individual members of the public.
This is a L : verity Level IV violation (Supplement IV).
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IR 98-004: Response to Notices of Violation
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GPUN concurs with the violation as stated.
Reason for Violation:
While developing our 1997 Annual Emuent Report, we recognized that the release pathway from the Isolation Condensers had to be included because ofincreased tritium levels. Due to an incease in the evaporative losses from the Isolation Condensers, the contribution from this pathway was greater than previous years. Recently, we identified an increase in the tritium concentrations of our primary coolant systems that has subsequently been attributed to control rod blade leakage. Although this increase was significant with ,
respect to previous tritium levels, it is still well below any specified limits. Since evaporative makeup to the Isolation Condensers was switched to Condensate Transfer, the increased tritium concentrations and evaporative losses resulted in a greater l contribution to our emuent releases than previously considered. Although individual sections within our organization had the necessary information to identify this issue sooner, a lack of communications between departments and the absence of a single
"emuent monitoring authority" delayed this realization. As such, we failed to recognize this potential pathway when developing our previous Annual Emuent Reports. i Corrective Steos That Have Been Taken and the Results Achieved:
Organ dose and whole body dose calculations were performed using this release pathway and reported in the 1997 Annual Emuent Report. The calculations show that a regulatory limit was never exceeded nor approached.
Because of the potential release pathway, monthly samples ofIsolation Condenser shell water for tritium have been added to the chemistry schedule. In addition, actions are underway to evaluate other potential release paths for the impact ofincreasing tritium levels.
The emuent doses from the isolation condensers for 1995 and 1996 have been calculated and the emuents for 1997 have been recalculated. The calculation shows that the tritium
. from the ICs would have added 3.6 % to the maximum individual organ dose in 1995 and 6.2% in 1996; therefore, the Annual Efiluent Reports for those years do not require revision. The calculations also confirmed that the reported tritium emuent from the ICs was overestimated in 1997 by almost a factor of two.
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Doses for 1997 were reduced to about 2/3 of those originally reponed in the 1997 Effluent Release Report. A revision to that report has been prepared and will be submitted prior to May 31,1998.
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'$ IR 98-004: Response to Notices of Violation Page 4
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Corrective Steps That Will Be Taken to Avoid Further Violations:
Condensate transfer will be used for surveillance requiring its use (Inservice Testing) and Isolation Condenser initiation evolutions and will not be used as the nominal make-up source for evaporative losses.
l Demineralized water will be used to make up for normal evaporative losses. In addition, evaporative losses will be tracked using an integrator thereby providing for a more accurate estimate of the potential dose contribution from this source.
During the upcoming refueling outage, efforts will be made to repair the seat on the isolation condenser condensate return valve and to replace those control rods which are the most likely source of the increasing tritium concentration.
Additionally, actions are ongoing to establish a more formal interdepartmental effluent system performance team. This should be in place by June 30,1998.
Date of Full Comoliance:
When this situation was recognized, we administratively suspended usage of Condensate Transfer for makeup to the Isolation Condensers for evaporative losses. Additionally, l we're monitoring routine makeup and usage to ensure that any releases via this pathway i
are appropriately included in our Annual Effluent Reports.
Currently, Oyster Creek is in full compliance with the ODCM and all other Licensing Bases Documents.
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