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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:INCOMING CORRESPONDENCE
MONTHYEARML20217E0181999-10-0606 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
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
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
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
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
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
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
ML20211B9011999-08-18018 August 1999
Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure
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
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)
ML20206C8261999-04-22022 April 1999
Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21
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
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
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
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
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
ML20207K2471999-02-25025 February 1999
Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny
ML20206S2541999-01-20020 January 1999
Confirms Resolution of Thermo-Lag Fire Barriers in Fire Zones OB-FZ-6A & OB-FZ-6B (480 Switchgear Rooms) IAW Previous Commitments Contained in Gpuns Ltrs to NRC & 971001
ML20199J2631999-01-18018 January 1999
Requests That Listed Changes Be Made to Correspondence Distribution List for Oyster Creek Generating Station
ML20199D0271999-01-11011 January 1999
Requests Listed Addl Info in Order to Effectively Review TS Change Request 264 Re Ownership of Property within Exclusion Area
ML20199A6521999-01-0707 January 1999
Notifies That Reactor Operators G Scienski,License SOP-11319 & D Mcmillan,License SOP-3919-4 Have Terminated Licenses at Oyster Creek Nuclear Generating Station, Effective 990101
ML20198T1061999-01-0606 January 1999
Forwards Rev 15 to Gpu Nuclear Corporate Emergency Plan for TMI & Oyster Creek Nuclear Station. with Summary of Changes Which Reflect Use of EALs Approved in NRC Ltr to Gpun on 980908 & Other Changes Not Related to Use of New EALs
ML20198K0331998-12-23023 December 1998
Forwards Change Request 268 for Amend to License DPR-16. Amend Would Change TS to Specify Surveillance Frequency of Once Per Three Months
ML20198H0181998-12-22022 December 1998
Forwards Attachment Addressing New Info & Modifying 980505 Submittal Re Request for Change to Licensing Bases for ECCS Overpressure,In Response to NRC Bulletin 96-03, Potential Plugging of ECCS by Debris in Bwrs
ML20198H8521998-12-16016 December 1998
Dockets Completion of Physical Inventory Performed in July 1997,as Addl Info to Nuclear Matl Balance Rept Submitted on 980416
ML20196H4461998-12-0202 December 1998
Provides Final Response to NRC GL 96-01, Testing of Safety-Related Logic Circuits
ML20196B4471998-11-23023 November 1998
Provides Required Response 2 to NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers in Bwrs. During Recently Completed 17R Refueling Outage,New Strainers Were Installed
ML20195J8451998-11-12012 November 1998
Forwards Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan, as Change Previously Made Without Appropriate Notification to NRC
ML20195C7201998-11-11011 November 1998
Forwards 120-day Required Response to GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment,
ML20195E1221998-11-10010 November 1998
Notifies NRC of First Time Usage of Code Case N-504 & Inclusion Into OCNGS ISI Program,As Accepted by RG 1.147, Inservice Insp Code Case Acceptability
ML20155J6851998-11-0505 November 1998
Forwards TS Change Request 266,to Modify Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & Verify Channel Operability
ML20155H5641998-11-0202 November 1998
Informs That Bne Has No Comments on Proposed Change 259 to Ts,Correcting Required Water Level in Condensate Storage Tank So That Design Basis Is Correctly Implemented
ML20155G3741998-10-29029 October 1998
Forwards Response to NRC 980619 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
1999-09-30
[Table view] |
Text
J . l i
.- j GPU Nuclear Corporation G,, G Nuclear o
- cn
- rsee Forked River, New Jersey 08731-0368 609 971 4000 Writer's Direct Dial Number
C321-92-2241 September 9,1992 U. S. Nuclear Regulatory Commission Attn Document Control Desk Washington, D. C. 20555 Gentlemon:
Subject:
Oyster Creek Nuclear Generating Station Electrical Distribution Functional Inspection IR No. 50-219/92-80 Unresolved Inspection Items In your letter (dated July 9,1992), you requested that we provide a schedule for the resolution of the inspection items rnd any actions taken or planned to enhance the functionality of the electrical distribution system. We have enclosed' two attachments which satisfy ' your request. Please note that our response to the Notice of Violation (92-80-01) was sent by a separate letter.
Attachment A delineates our proposed actions and schedule for addressing the
. ten unresolved items identified in the inspection report. Attachment B provides additional information on our actions or comments to those areas which you l identified as a concern or weakness.
The sichedule for addressing the unresolved items and comments was developed with
- the consideration of multiple aspects of GPUN activities. Each item was assessed
-with respect to its safety significance and integrated into the total work scope for GPU Nuclear. The estimated completion dates incorporate priority and resource availabilities. GPUN nas a long term program associated with electrical analyses of Oyster Creek and THI Unit 1. The actions associated with the Electrical Distribution Functional Inspection serve as a subset of this total program.
15609; 92o9170064 920909 -lg DR ADOCK 0500 )
GPU Nuclear Corporation is a sut.udwy of Genera' Puboc Utomes Corporation /
u .
If you have questions on this letter or our response to the Notice of Violation, please contact Tom Blount (609 971-4007) or David Jerko (201 316-7976).
V y truly yours, J. J. a ton Vi e resident and Director _
Oy 'tm Creek k
Attachments JJB/DGJ cc: Administrator, Region I HRC Resident Inspector Oyster Creek NRC Project Mcnager l
i .
~
Attachment A Inspection Report No. 50-219/92-80 GPUN Proposed Actions and Schedule For Unre.e'ived items Item: 92-80-01 Notice of Violation - Safety related comgonents not functionally tested GPUN response: The response to the NOV is provided by separate letter, m
Ltem: 92-Q0-J2_ Edmagy of MCC Control Circuit Voltage GPUM response: The adequacy of voltages at safety related AC motor control center control circuit equipment will be analyzed by the end of February 1994.
Jtem: 92-80-03 Adecuacy of Voltage to AC Components GPUN response: The adequacy of voltages at safety related /C equipment terminals down to the 120VAC level will be analyzed by the end of August 1994.
Item; 92-80-04 BFP Start on Augiliary Transformer GPUN response: Starting of the Reactor Feed Pumps is controlled by administrative procedures which require the downstream valves to be closed when the pumps are started. The reduced pumping load will limit the motor starting time to values less than the degraded grid relay timer settings. But in order to -
provide additional documentation of motor starting capability, a study will be completed by the end of February 1994.
Item: 92-80-05 Adequacy of Voltage to DC Components GPUN response: The adequacy of voltages at safety related DC equipment terminals will be analyzed by the end of March 1994.
Item: 92-80-06 Adeq.uacy of DC Short Circuit Protection GPUN response: The DC short circuit duty of cencern is associated with DC Jistribution Center C and its downstream panels. Should the static battery charger contribution exceed 500% of full load current as suggested, there is still more than adequate margin 1 between available fault current and equipment ratings. An evaluation will be performed to determine the available short circuit contribution of our particular static chargers and if needed, the calculation will be updated by the end of February 1994. Please note that the MG set short circuit contribution used in our calculations was 750% of charger rating not 75%.
I
s .
l
,ltemi92-80-07 Adequacy of HVAC Temperature Control to 4ky and 480v Switchaear Rooms GPUN response: GPUN will provide guidelines for monitoring room temperatures and establish the maximum allowable room temperatures for the 4kV and 480V switchgear rooms. These guidelines will be provided by the end of April 1993, ite : 92-80 Me_qu_a_cy of EDG Battery liydrogen LeyeLduring Normal Operation GPUN response: An engineering evaluation was completed on 6/12/92. The resulting data indicated no detectable hydrogen in any vent opening of the battery boxes in either diesel unit. Based on this asses'; ment no further action is considered necessary.
Jtem: 92-M-@_ Seismic _!Lualification of C Battery Room Heater GPUN response: The electric heater for Battery Room C was installed to maintain a minimum temperature of 65 F dry bulb during winter outages of the plant. An evaluation of the seismic qualification of the heater will be completed by the end of October 1992.
Jtem: 92-B_0-10 lL_equacy d of TS Minimum Battery Voltage to Start tiot EDG GPUN response: An engineering evaluation to collect and review data available on the EDG battery low voltage concerns is expected to be completed by the end of September 1992.
Ltem: 92-80-1L Mequ.a_cy_gf Coordinatjon between ApS Breakers and F_us_es GPUN response: An evaluation will be conducted to determine the appropriate tripping and melting / clearing times for the associated breakers in the DC power panel and the fuses in the ADS _
circuits. This evaluation will be completed by the end of February 1993.
4 4 Attachment B Inspection Report 50-219/92-80 GPUN Additional Actions or Connents NRC comment;. The de control power for the switchyard consists of a single battery and battery charger. The absence of a program to periodically test the battery to verify its continued operability to provide power for its design period (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) is an area of potential concern. (page 6. section 2.1)
GPUfLrftigonse: Discussiens are in progress between GPU Nuclear and Jersey Central Power & Light to address general maintenance and housekeeping activities in the switchyards. The discussions will lead to an action plan being developed to address concerns such as equipment maintenance, general housekeeping and tours by plant operations.
NRC comme'1t: Two cases were identified in which valve bus voltages had been incorrectly selected from a previously prepared analysis of distribution voltages. The failure to identify the correct bus voltage in the;e two cases was of minor safety significance because the voltages used in the calculation (from the wrong bus) were more limiting than the correct voltages. The licensee committed to correct the calculation and to review .all other loads reassigned in the same modification. (p.10, sec. 2.4)
GPUN resDonse: GFUN is in the process of addressing the concerns associated with NRC Generic Letter 89-10 for motor operated valves. The calculation reviewed during the EDSFI was an interim calculation prepared to address GL 89-10 supplement 3 concerns on operability of certain M0V's. This calculation will be updated along with other studies as part of the overall __
response to GL 89-10. Other electrical equipment will be evaluated in response to unresolved item 92-80-03.
NRC comment _;. The EDG cold starting load limitation was not clearly defined in the licensee's analyses and, in one case (Calculation 5250-003), specifically omitted. Even though the loading requirements identified were well within the EDG rating, this limitation is necessary to properly evaluate future load additions. The team concluded this item to be a weakness in documentation and not a safety concern. (pgs.10,11, sec. 2.5)
GPUN response: The EDG cold starting load limitation will be evaluated and calculations will be revised as necersary by the end of October 1993.
NRC comment: The major loads on the EDG were revised by the licensee from the original automatic loading schedule. Consequently, only one core spray booster pump starts automatically. The team noted that the FSAR had not yet been revised to reflect this modification. (p. 17, Sec. 3.1) l
W
}-(_f
. G PUN.' r.e_a.qDiel The Core Spray System is a low pressure emergency core cooling
- system which consists of two independent subsystems. Each ,
subsystem contains two main pumps and two booster pumps (one 1 primary and one backup) which can receive emergency power from
-their own respective diesel generator.
A 13R modification locks out the backup booster pump if the primary booster pump on the same electrical division is running.
A change was made to the FSAR (Section 6.3.1.3.3.C) to reflect this modification; bowever, changes were not made to Tables 8.3-1 and 8.3 A Plant FSAR Update was initiated during the inspection and the appropriate change will be incorporated in
-Update 7 (December 1992).
NRC comment: Marinite board, originally installed to enhance cable separation and protection, was found in a number of cases to be ' loose, missing, or damaged. The licensee acknowledged the -
team's concern and committed to repair the identified board y deficiencies, . inspect for similar deficiencies, and conduct L periodic reinspections. (p.20, Sec. 4.1)
GPUN response: . A Material Non-Conformance Report was generated to address the
~immediate concern of- the damaged M-board in _480 volt switchgear room. Disposition of this MNCR included cPrection
.of the deficiencies by-issuing a work request. A Job Order was then issued and-the scope was expanded to include directions-for the replacement of the M-board. The work is scheduled to
- be completed by the end of September I?:-2.
A deviation report _was initiated _to :
-Perform a root cause analysis of the'M-Board problem.-
Completion is expected by the end of September 1992.
- Conduct a plant walkdown of major plant areas where the M-board is expected to'be installed. Guidelines will be provided to. identify possible M-board Ldeficiencies.
Completion of walkdowns is expected by the end of September 1992.
Review the results of the walkdown to establish the need .
to expand the inspection to other plant areas._ Identify the deficient M-board locations. Completion is expected -
by the end of October 1992.- ,
4
- Planned Additional actions include:
Provide guidelines in procedures and engineering specifications on how to maintain the M-board installations. Completion is expected by the end of netober 1992.
Training will be provided to plant personnel to educate and enhance their swareness about the need to maintain the M-board in its as-installed configuration.
Completion is expected by the end of November 1992.
The need for documentation of future M-board installations was reviewed and it was determined that periodic walkdowns would be more appropriate. This periodic walkdown inspection program will be established to identify M-board deficiencies which may occur over time. Completien of the program is expected by the end ,
of October 1992.
NRC comment: Tra inm identified that the duty cycle for ELG-2 battery had at be n established. TS section 4.7.B was not clear in that the cucy cycle rating was not specified. The licensee committed to establish the EDG battery duty cycle and to submit _ the appropriate TS amendment request. (p.21, sec.
4.2.1)
GPUN response: The duty cycle for the EDG-2 battery will be determined and the need for a Technical Specification Change Request will be evaluated by the end of August 1994.
NRC comment: The team identified that neither the generic procedure nor the PMs provided good acceptance criteria for testing breaker instantaneous trip elements. The team considered this to be a weakness. The licensee initiated actions to incorporate acceptance criteria in.new and existing PMs for the MCCs.
(p. 22,-sec. 4.2.4)
GPUN response: Motor Control Center Preventive Maintenance Procedure A100-SME-3915.01 is presently being- revised. This revision includes the acceptance criteria for fixed and adjustable instantaneous trip elements; it is expecced that it will be issued for use by the end of September 1992. All new and revised PM tasks are being developed using the acceptance criteria in accordance with the revised procedure.
The PM task upgrade activity to address this concern will continue over an extended period of time due to the significant number of tasks involved. In addition, major enhancements to extend the scope beyond the instantaneous trip tests will oe included. Completion is expected by the end of
- December 1994.
? 0
. NRC 'commin11 The calculations initiated as a result of the design basis reconstitution program were good and presented in a comprehensive manner. However, the status of old and superseded calculations was not clearly annotated to prevent potential design errors. (p. 33, sec. 5.8)
Sfl)N re H9D191 The Technical Functions Division prepares calculations using Procedure 5000-ADM-7311.01 (EP-006). This procedure provides general guidelines for the documentation of computer and manual calculations.
Prior to revision 3-01, EP-006 provided no guidance for engineers doing new work to be familiar with previous calculations and overtly void, supersede or revise previous calculations when appropi. ate based on the currently ongoing calculation activities. In 1990, Section 4.5 of EP-006 was revised to include a note:
The originator of a calculation shall review or be aware of previous calculations for the system for which the calculation is being completed. These previous calculations will be voided, superseded, or revised as appilcable.
By this change, the Technical Functions Division has already initiated corrective action to improve the performance in this area.
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