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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
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)
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
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
'#
I GPU Nuclear Corporation G < Nuclear "::en:r'88 forked River, New Jetsoy 08731 0388 l
009 971 4000 Wnter's Dauct Dial Number C321-91-2249 October 25, 1991 U.S. Nuclear Generating Station l Attn: Document Control Desk l Washington, DC 20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Response to Generic Letter 91-06 Resolution of Generic Issue A-30, ' Adequacy of Safety Related DC Power Supplies," Pursuant to 10 CFR 50.54(f)
As required by 10 CFR 50.54(f), the attached information provides the GPU Nuclear response to Generic Letter 91-06 dated April 29, 1991.
If further information is required, please contact Thomas Blount, OC Licensing Engineer at 609-971-4390.
s, Vgytruyyo / _,
4 o n J. Bar t V'ce Presi t and Director yster Crec k day SwornaJn3 subscribed to before me this M o f- Orik/A> 1991.
f lWO '~.
tary Public of New Jersey JB\TB:jc Enclosure "KN cc: Administrator, Region 1 g NDqr Senior NRC Resident Inspector Oyster Creek NRC Project Manager 91i1050t7s 911025 PDR f, DOCK 05000210 P PDP
,e-3 GPU Nuclear Corporahon is a sut>sdary of General Put*c Uta ties Corporation [8!
lll
t ,' .
Enclosure 1 GEUN RESEQRS1 TO GLt(ERIC 1S1UL(HD A40 "M[Q@CY OF SAFET1-R[i.ATED DC POW [RJQEELIES" (GL 91-Q11 The following information is provided by GPU Nuclear:
- 1. Unit:
Dyster Creek Nuclear Generating Station
- 2. a: The number of independent redundant divisions of Class 10 or safuty related DC power for this plant is: (Include any separate Class IE or safety related de, such as any de dedicated to the diesel generators.)
11AliDILf331EtiRL(sed _1.21V DC: TMQ Diesel Batteries ( MBs) 125V DC: TWQ_(SplLCantained Startina Batteries) b: The number of safety-related divisions of de power necessary to attain safe shutdown for this unit is:
SB: ON['
DGB: ONE
- 3. Does the control room at this unit have the following separate, independently annunciated alarms and indicatior a for each division of de power?
- a. Alarms
- 1. Battery disconnect or circuit brecker open?
Shu,1ES EBil0*J*
- There are no battery disconnects or circuit breakers for the battery.
- A DC control power knife switch open condition will be indic:ted by the " Diesel Not in AUT0" annunciator.
l l
Enclosure 1 Page 2 P ., Bat tery charger disconnect or circuit breaker open (both input ac and output dc)?
SB: YES Q.G B - H0*
- 3. de system ground?
SH: YES _
DEBi_1LS
- 4. dc bus undervoltage?
Elli__lLS '
DGB: YES
- 5. dc bus overvoltage?
SB: _YES QLD: N0*
- Local meter is read daily by operators for float vol' age. R
- 6. Battery charger failure?
SB; YES DGti N0* _
Low DC voltage annunciator will signal this condition.
- 7. Battery discharge?
SB: N0*
- Ammeter in the Control Room provides indication for discharge (negative reading). Log is taken by the plant operators every hour. ,
DGB: N0**
- Local chargina current meter is read by operators daily; low DC voltage annunciator will signal low voltage a; battery charge begins to drop.
l l
t- ,
d' Enclosure 1 Page 3 i b, Indications
- 1. Battery float charge current? ;
SB: YES ,
DGB: Y[}
2, Battery circuit output current?
SB:._ Y.fJi DGB: N0*
- With diesel in standby nearly all current is battery charge current, (observed as float charge current).
3, Battery discharge?
SB: YES DGB: N0*
- Low dc voltage annunciator will indicate this condition if it is abnormal,
- 4. Bus voltage?
SJ: YES
, DGB: N0*
- Self contained diesel battery and controls does not have a
" bus" system,
- c. Does the unit have written procedures for response to the above alarms and indications?
SB: YES DGB: YES
- 4. Does this unit have indication of bypassed and inoperable status of circuit breakers or other deviter that can be used to disconnect the battery and battery charger from its de bus and the battery charger from its ac power source during maintenance or testing?
SB:: YES DGB: N0*
- Self contained diesel battery does not have a bus distribution system.
5, If the answer to any part of question 3 or 4 is no, then provide.
information justifying the existing design features of the facility's safety-related de systems.
(Information provided as appropriate-to each response).
- ..-.- . . - - . . ~ - . _
, , a Enclosure-1 Page 4
- 6. (1) Have you conducted a review of maintenance and testing activities to minimize the potential for human error causing more than one de division to be unavailablet and, (2) do-plant procedures prohibit maintenance or testing on redundant de division at the same time?
(1) SB: YES (1) DGB: YES (2) EU: YES (2) DGB: Y[3
- 7. Are maintenance, surveillance and test' procedures regarding station batteries conducted routinely at this plant? Specifically:
- t. At least once per 7 days are the following verified to be within
' acceptable limits:
- 1. Pilot cell electrolyte level?
SB: YES DGB: YES
- 2. Specific gravity or charging current?
Sf!;_.lf5 (Pilot cell).
QGB: .YES
- 3. Float voltage?
SB: YES QGB: YES
- 4. Total bus voltage on float-charge?
SB: YES DGB: YEE*
- The self contained diesel battery docs not have a
" bus" distribution system.
- 5. Physical condition of 'all cells?
18: NES DGB: -YES
Enclosure 1
-Page 5
- b. At least once per 92 days, or within 7 days after a battery discharge, overcharge or if the pilot cell readings are outside the 7-day surveillance requirements, are the following verified to be within acceptable limits:
- 1. Electrolyte level of each cell? [
SS: YES ,
QLBi__1ES x s
- 2. The average specific gravity of all cells?
SB: YES Nominal specific gravity of each cell is DGB: YES recorded monthly and compared against the acceptance criteria.
- 3. The specific gravity of each cell?
SB: YES DGB: YES
- 4. lhe average electrolyte temperature of a representative nuniber of cells?
SB: YES DGB: YES
- 5. The float voltage of each cell?
SB: YES QGHL_US
- 6. Visually inspect or measure resistance of terminals and
, connectors (including the connectors at the dc bus)?
SB: YES (Visually inspect)
QGB: YES (Visually inspect)
Er closure 1 Page 6
- c. At least every 18 months, are the following verified:
- 1. Low resistance of each connection (by test)?
SB: N0 QDE: NO Performed every 24 months in accordance with OC Tech Specs.
- 2. Physical condition of the battery?
SB: NO DGB: NQ Performed every 24 months in accordance with OC Tech Specs.
- 3. Battery charger capability to deliver rated ampere output to the dc bus?
SlL.B0 DGB: NO Industry standards do not require charger testing. Chargers at 0.C. meet the design requirements as stated in the FSAR.
In addition, chargers are subjected to periodic preventive maintenance checks.
- 4. The cap;5ility of the battery to deliver its design duty .
cycle to ine dc bus?
SB: NQ DGB: NQ Performed every 24 months in accordance with 0.C. Tech Spec.
s
- 5. Each individual cell voltage is within acceptable limits during the service test?
SB: NO DGB: NO Performed every 24 months in accordance with 0.C. Tech Spec.
l l
l
lnclosure 1 Page 7
- d. At least every 60 months, is capacity of each battery verified by performance of a discharge test?
SHL__llS PGB: YES Performed every 24 months in accordance with 0.C. lech Sec,
- e. At least annually, is the battery capacity verified by performance discharge test, if the battery shows signs of degradation or has reachad 85% of the expected service life.
SD: NO Performed every 24 months in accordance with 0.C. Tech Spec.
DGB: YES
- 8. Does this plant have operational features such that following loss of one safety-related de power supply or bus:
- a. Capability is maintained for ensuring continued and adequate reactor cooling?
SB: YES DGB: YES
- b. Reactor coolant system integrity and isolation capability are maintained?
SS: YES ML1f3
- c. Operating proe.edures, instrumentation (including indicators and I annunciators). and control functions are adequate to initiate systems as rcquired to maintain adequate core cooling?
SB: YES DGB: YES (Blount\C3212249)
_ _ . . _ - -