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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8771999-10-25025 October 1999 Requests That Industry Studies on long-term Spent Fuel Pool Cooling Be Provided to R Dudley at Listed Mail Stop ML20217M4331999-10-19019 October 1999 Submits Rept 17, Requal Tracking Rept from Operator Tracking Sys. Rept Was Used by NRC to Schedule Requalification Exams for Operators & Record Requal Pass Dates ML20217F5841999-10-13013 October 1999 Requests Revocation of License OP-11038-1 for GE Kingsley. Individual Has Been Reassigned to Position within Naesco ML20217F5811999-10-13013 October 1999 Forwards Insp Data & Naesco Evaluation of a EDG Exhaust Insp Conducted on 990407.Insp Ensured That Unacceptable Wall Thinning Will Not Occur During 40-year Design Lifetime of Sys ML20217C7321999-10-0808 October 1999 Forwards Copy of Seabrook Station Videotape Entitled, Completion of Seal Barrier Installation. Videotape Documents Process of Selecting,Designing & Installing Seal Deterrent Barrier to Preclude Entrapment of Seals ML20217B8621999-10-0505 October 1999 Forwards Rev 28,change 1 to EPIP Er 1.1, Classification & Emergencies, Per 10CFR50.54(q).Rev to Procedure Does Not Decrease Effectiveness of Seabrook Station Radiological Emergency Plan ML20217B7471999-10-0101 October 1999 Provides Notification of Change in PCT of More than 50 F,Per Requirements of 10CFR50.46(a)(3)(i),(ii).Tabulation of Large Break LOCA PCT Margin Utilization Applicable to Seabrook Station,Encl ML20212J8271999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Seabrook Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility Over Next Six Months.Plant Issues Matrix & Insp Plan Encl ML20216J2381999-09-30030 September 1999 Responds to Re Enforcement Discretion for Nuclear Plants During Y2K Transition.Nrc Expects All Licensees to Operate Nuclear Facilities Safety IAW NRC Regulations & Requirements ML20216J2421999-09-30030 September 1999 Responds to Card Received in Aug 1999,providing Comments on NRC Interim Enforcement Policy Re Enforcement Discretion for Nuclear Plants During Y2K Transition.Informs That Naesc Reported Seabrook as Y2K Ready Prior to 990701 ML20216J2471999-09-30030 September 1999 Responds to Which Provided Comments on NRC Interim Enforcement Policy Re Enforcement Discretion for Nuclear Plants During Y2K Transition.Informs That Naesc Reported Seabrook as Y2K Ready Prior to 990701 ML20212K7921999-09-30030 September 1999 Confirms 990922 Telcon with J D'Antonio & T Grew Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Seabrook Facility ML20212J0301999-09-24024 September 1999 Forwards Insp Rept 50-443/99-10 on 990726-30 & 0809-13.No Violations Noted.Insp Discussed ML20212G5071999-09-21021 September 1999 Submits Complaint to NRC Re NRC Failure to Cite Seabrook Station NPP Operators for Failing to Periodically Calibrate & Establish Adequate Measures to Insure That Relay Equipment Met All Required Calibration Settings Prior to Installation ML20212C1881999-09-20020 September 1999 Ack Receipt of Which Raised Concerns Re NRC Enforcement Actions at Plant & Issuance of NCVs ML20212D1401999-09-17017 September 1999 Forwards SE Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20212B9511999-09-17017 September 1999 Forwards NRC Form 396 for MG Sketchley,License SOP-10685, Along with Supporting Medical Exam Info.Nrc Form 396 Has Been Superceded by Revised Version Dtd 971222,which Was Previously Submitted to NRC on 990812.Encl Withheld ML20212C3621999-09-15015 September 1999 Forwards Rev 34 to Seabrook Station Radiological Emergency Plan & Rev 85 to Seabrook Station Emergency Response Manual, Per 10CFR50,App E & 10CFR50.4 ML20212B5021999-09-14014 September 1999 Forwards Licensee Responses to EPA Questions Re Plant Seal Deterrent Barrier.Util Completed Installation of Subject Barriers on All Three Station Offshore Intake Structures on 990818.Barriers Will Preclude Entrapment of Seals ML20211Q8521999-09-0808 September 1999 Informs That Rl Couture,License SOP-11027,terminated Employment at Naesco on 990907.Revocation of License Requested ML20211N8781999-09-0303 September 1999 Forwards Response to 990820 RFI Re NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20211M3221999-09-0202 September 1999 Responds to NRC Re Violations Noted in Insp of License NPF-86 & Proposed Imposition of Civil Penalty. Corrective Actions:Conducted Prompt Review of Layoff Decision to Determine Relevant Facts DD-99-10, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-10) Expired.Commission Declined Review & Decision Became Final on 990830.With Certificate of Svc.Served on 9909021999-09-0202 September 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-10) Expired.Commission Declined Review & Decision Became Final on 990830.With Certificate of Svc.Served on 990902 ML20211J8811999-09-0101 September 1999 Forwards Comments on Seabrook Station Review of Reactor Vessel Integrity Database (Rvid)(Version 2).Minor Discrepancies Were Noted.Proposed Changes Are Encl in Order to Correct Discrepancies ML20211J8411999-09-0101 September 1999 Forwards Updated NRC Form 396 for E Decosta,Nrc License OP-10655-1.Without Encl ML20211G9191999-08-27027 August 1999 Informs NRC That Name of New Company, Ref in Order Approving Application Re Corporate Merger Is Nstar Which Is Massachusetts Business Trust ML20211J0401999-08-26026 August 1999 Responds to 990819 Request,On Behalf of Gr Pageau & Williams Power Corp,For Addl Time in Which to Reply to Nov,Issued on 990803.Response Due to NRC by 991008 ML20211H0651999-08-25025 August 1999 Forwards Insp Rept 50-443/99-05 on 990621-0801.One Violation Re Failure to Include Multiple Components within Scope of ISI Test Program Was Identified & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20211G7761999-08-24024 August 1999 Expresses Great Concern Re Lack of Enforcement Actions Against Seabrook Station Despite Citations NRC Has Issued for Violations of Seabrook Operating License ML20211J2171999-08-23023 August 1999 Expresses Disappointment with Lack of Enforcement Action Against Seabrook Station Despite Repeated Safety Violations ML20211J4971999-08-21021 August 1999 Submits Comments Re Violations Cited in Early Mar & 990509 Insps ML20211H8361999-08-19019 August 1999 Submits Concerns Re Violations at Seabrook Station ML20211F2681999-08-19019 August 1999 Discusses Former Chairman Jackson & 990602 Predecisional Enforcement Conference Re Findings of Ofc of Investigations Involving Allegations Raised by Contract Electrician.Determined That Allegations Not Supported ML20211J3241999-08-15015 August 1999 Expresses Disappointment in Apparent Failure of NRC to Cite Seabrook Station NPP for Recent Violations of Safety Regulations Uncovered During Recent Insps in Mar & May ML20211J1831999-08-15015 August 1999 Submits Concerns Over Serious Deficiencies at Seabrook Station That NRC Has Declined to Take Enforcement Actions Against ML20210T1601999-08-13013 August 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev,supp1 1, Reactor Vessel Structural Integrity, NRC Revised Info in Reactor Vessel Integrity Database & Is Releasing It as Rvid Version 2 ML20211J2071999-08-13013 August 1999 Expresses Concerns Re Violations Occurring Recently at Seabrook Nuclear Power Station.Requests Effort to See That Measures Taken to Stop Flagrant,Continuing Violations That Hold Danger to Workers & Community ML20210S9611999-08-13013 August 1999 Informs That NRC Received Encl Ltr from Pb Johnston Expressing Concern About Certain Impacts on Shareholders of New England Electric Sys with Respect to Nees Proposed Merger with Natl Grid Group ML20210S9511999-08-13013 August 1999 Responds to to Collins Expressing Concerns with Certain Terms of Proposed Merger Between New England Electric Sys & National Grid Group.Nrc Has No Authority to Interject Itself in Nees Merger with National Grid Group ML20210S2001999-08-12012 August 1999 Forwards NRC Forms 398 & 396 in Support of Applications for Renewal of Operator Licenses for Individuals Listed Below. Without Encls ML20210R8401999-08-11011 August 1999 Forwards Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20210S7331999-08-11011 August 1999 Submits Third Suppl to 980423 Application to Renew NPDES Permit NH0020338 for Seabrook Station.Suppl Provides Addl Info on Input Streams & Requests Increased Permit Limit for Chemical Used in Makeup Water Treatment Sys ML20210R9581999-08-11011 August 1999 Forwards ISI Exam Rept of Seabrook Station, for RFO 6, Period 3,for Insps Conducted Prior to & During Sixth Refueling Outage Concluded on 990510 ML20210Q7441999-08-11011 August 1999 Forwards Order Approving Indirect Transfer of Control of Canal Interest in Seabrook Station Unit 1 as Requested in Application & SER ML20210R7931999-08-10010 August 1999 Forwards Cycle 7 Startup Rept for Seabrook Station, IAW Requirements of TS 6.8.1.1 ML20210N9421999-08-0505 August 1999 Informs That North Atlantic Suggests Listed Revisions to 990730 Draft Revisions to Committee Rept & Order.Further Revs Consistent with What North Atlantic Proposed at 990608 Hearing ML20210N5721999-08-0303 August 1999 Discusses Investigations Rept 1-98-005 Conducted by OI at Naesco,Seabrook Station & Forwards NOV & Proposed Imposition of Civil Penalty - $55,000.Violation Re Failure to Promptly Correct Incorrectly Terminated Cables of Control Bldg Air ML20210P3361999-08-0303 August 1999 Discusses Investigation Rept 1-98-005 Conducted by Region I OI at Naesco,Seabrook Station & Forwards Nov.Violations Re Electrical Wiring in Control Panel for Control Bldg Air Conditioning Sys ML20210P3161999-08-0303 August 1999 Discusses Investigation Rept 1-98-005,conducted Between 980129 & 0527 at Seabrook Station & Forwards Nov.Violation Re Discrimination of Williams Power Corp,Contractor of Naesco,Against Electrician for Raising Safety Issues 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F5841999-10-13013 October 1999 Requests Revocation of License OP-11038-1 for GE Kingsley. Individual Has Been Reassigned to Position within Naesco ML20217F5811999-10-13013 October 1999 Forwards Insp Data & Naesco Evaluation of a EDG Exhaust Insp Conducted on 990407.Insp Ensured That Unacceptable Wall Thinning Will Not Occur During 40-year Design Lifetime of Sys ML20217B8621999-10-0505 October 1999 Forwards Rev 28,change 1 to EPIP Er 1.1, Classification & Emergencies, Per 10CFR50.54(q).Rev to Procedure Does Not Decrease Effectiveness of Seabrook Station Radiological Emergency Plan ML20217B7471999-10-0101 October 1999 Provides Notification of Change in PCT of More than 50 F,Per Requirements of 10CFR50.46(a)(3)(i),(ii).Tabulation of Large Break LOCA PCT Margin Utilization Applicable to Seabrook Station,Encl ML20212G5071999-09-21021 September 1999 Submits Complaint to NRC Re NRC Failure to Cite Seabrook Station NPP Operators for Failing to Periodically Calibrate & Establish Adequate Measures to Insure That Relay Equipment Met All Required Calibration Settings Prior to Installation ML20212B9511999-09-17017 September 1999 Forwards NRC Form 396 for MG Sketchley,License SOP-10685, Along with Supporting Medical Exam Info.Nrc Form 396 Has Been Superceded by Revised Version Dtd 971222,which Was Previously Submitted to NRC on 990812.Encl Withheld ML20212C3621999-09-15015 September 1999 Forwards Rev 34 to Seabrook Station Radiological Emergency Plan & Rev 85 to Seabrook Station Emergency Response Manual, Per 10CFR50,App E & 10CFR50.4 ML20211Q8521999-09-0808 September 1999 Informs That Rl Couture,License SOP-11027,terminated Employment at Naesco on 990907.Revocation of License Requested ML20211N8781999-09-0303 September 1999 Forwards Response to 990820 RFI Re NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20211M3221999-09-0202 September 1999 Responds to NRC Re Violations Noted in Insp of License NPF-86 & Proposed Imposition of Civil Penalty. Corrective Actions:Conducted Prompt Review of Layoff Decision to Determine Relevant Facts ML20211J8411999-09-0101 September 1999 Forwards Updated NRC Form 396 for E Decosta,Nrc License OP-10655-1.Without Encl ML20211J8811999-09-0101 September 1999 Forwards Comments on Seabrook Station Review of Reactor Vessel Integrity Database (Rvid)(Version 2).Minor Discrepancies Were Noted.Proposed Changes Are Encl in Order to Correct Discrepancies ML20211G9191999-08-27027 August 1999 Informs NRC That Name of New Company, Ref in Order Approving Application Re Corporate Merger Is Nstar Which Is Massachusetts Business Trust ML20211G7761999-08-24024 August 1999 Expresses Great Concern Re Lack of Enforcement Actions Against Seabrook Station Despite Citations NRC Has Issued for Violations of Seabrook Operating License ML20211J2171999-08-23023 August 1999 Expresses Disappointment with Lack of Enforcement Action Against Seabrook Station Despite Repeated Safety Violations ML20211J4971999-08-21021 August 1999 Submits Comments Re Violations Cited in Early Mar & 990509 Insps ML20211H8361999-08-19019 August 1999 Submits Concerns Re Violations at Seabrook Station ML20211J3241999-08-15015 August 1999 Expresses Disappointment in Apparent Failure of NRC to Cite Seabrook Station NPP for Recent Violations of Safety Regulations Uncovered During Recent Insps in Mar & May ML20211J1831999-08-15015 August 1999 Submits Concerns Over Serious Deficiencies at Seabrook Station That NRC Has Declined to Take Enforcement Actions Against ML20211J2071999-08-13013 August 1999 Expresses Concerns Re Violations Occurring Recently at Seabrook Nuclear Power Station.Requests Effort to See That Measures Taken to Stop Flagrant,Continuing Violations That Hold Danger to Workers & Community ML20210S2001999-08-12012 August 1999 Forwards NRC Forms 398 & 396 in Support of Applications for Renewal of Operator Licenses for Individuals Listed Below. Without Encls ML20210R8401999-08-11011 August 1999 Forwards Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20210R9581999-08-11011 August 1999 Forwards ISI Exam Rept of Seabrook Station, for RFO 6, Period 3,for Insps Conducted Prior to & During Sixth Refueling Outage Concluded on 990510 ML20210R7931999-08-10010 August 1999 Forwards Cycle 7 Startup Rept for Seabrook Station, IAW Requirements of TS 6.8.1.1 ML20210K3281999-07-30030 July 1999 Forwards Response to NRC RAI Re License Amend Request 98-17. North Atlantic Concurs with Staff That Bases Should State That Maintaining ECCS Piping Full of Water from RWST to Reactor Coolant Sys Ensures Sys Will Perform Properly ML20210H8991999-07-27027 July 1999 Forwards Tabulation of Current LBLOCA & SBLOCA Peak Clad Temp Margin Utilization Tables Applicable to Seabrook Station ML20210H0921999-07-27027 July 1999 Forwards Naesc Semi-Annual Fitness-for-Duty Rept,Jan-June 1999, Per 10CFR26.71(d).Rept Includes Data from 990101- 0610 ML20210S9911999-07-18018 July 1999 Requests NRC Intervene for All Shareholders of New England Electric System & to Help with Merger with National Grid Group & That NRC Petition Security & Exchange Commission to Investigate Matter Relative to No Shareholder Options ML20210A2521999-07-15015 July 1999 Forwards Rev 33 to Seabrook Station Radiological Emergency Plan & Rev 84 to Seabrook Station Emergency Response Manual ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G1351999-07-0909 July 1999 Forwards Relief Request Re Repair Welding on SA-351 Matl to Be Installed in Seabrook Station SW Pumps & SW Cooling Tower Pumps ML20209D2871999-07-0606 July 1999 Submits Response to NRC AL 99-02,re Numerical Estimate of Licensing Actions Expected to Be Submitted in Fy 2000 & 2001.Schedule Does Not Include Activities Which Meet AL Definition of Complex Review ML20209C9021999-06-30030 June 1999 Provides Revised Distribution List for Seabrook Station Correspondence to Reflect Current Organization ML20196G2391999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant Encl ML20196G3381999-06-23023 June 1999 Forwards LAR 99-19 for License NPF-86,increasing AOT for Cracs from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on-line Implementation of Design Enhancements During Current Operating Cycle ML20195J0981999-06-17017 June 1999 Forwards Responses to Questions Posed in Re Application of New England Power Co for Transfer of Control of Licenses NPF-49 & NPF-86.Copy of 1998 Schedule 13G, Included,As Requested ML20196D0561999-06-16016 June 1999 Forwards Certified Copy of Endorsements 77 & 78 to Nelia to Policy NF-0296 ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195J1221999-06-15015 June 1999 Forwards Addl Clarifying Info to Suppl Info Provided at 990602 Predecisional Enforcement Conference at Region I. Proprietary Declarations by Util Employees to Correct Inaccuracies Encl.Proprietary Info Withheld,Per 10CFR2.790 ML20210K4971999-06-15015 June 1999 Forwards Copy of Ltr from Concerned Constitutent AC Menninger from Franconia,Nh to Senator Smith Re Seabrook Nuclear Power Station Y2K Readiness ML20195E9731999-06-0707 June 1999 Forwards Rev 32 to Seabrook Station Radiological Emergency Plan & Rev 83 to Emergency Response Manual ML20206T4201999-05-20020 May 1999 Forwards Certified Copies of Resolution Adopted by Shareholders of National Grid Group Approving Acquisition of New England Electric Sys & Vote of New England Electric Sys Shareholders Approving Merger with National Grid Group ML20196L2001999-05-0707 May 1999 Forwards Rev 01-07-00 to RE-21, Cycle 7 COLR, Per TS 6.8.1.6.c ML20206K4301999-05-0707 May 1999 Forwards Copy of Corrective Order of Notice by State of Nh Nuclear Decommissioning Financing Committee ML20206J3321999-05-0505 May 1999 Forwards Tabulation of Number of Tubes Plugged in Each of Two SGs Inspected During Sixth Isi,Per Plant TS SR 4.4.5.5a. Sixth ISI Was Completed on 990420 ML20206J3341999-05-0505 May 1999 Informs That on 990501,ISO New England & New England Power Pool Implemented Restructured Wholesale Electricity Market. Summary of Util Action as Result of Implementation of Subject Market,Encl ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders ML20206G4371999-04-30030 April 1999 Forwards 1998 Annual Environ Operating Rept for Seabrook Station.Encl Rept Is Summary of Implementation of EPP for Period of Jan-Dec 1998 ML20206H4801999-04-30030 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Seabrook Station. Listed Info Provided in Encls 1999-09-08
[Table view] |
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Chief becutne Officer NYN 91172 October 25, 1991 United States Nuclear Regulatory Commission Washingten, D.C. 20555 Attentinn: Document Control Desk
References:
(a) Facility Operating License No NPF 86, Docket No. 50 4 83 (b) USNRC Generic Letter 91-06 dated April 29, 1991, Resolution of Generic issue A 30, ' Adequacy of Safety-Related DC Power Supplies,'
Pursuant to 10 CFR 50.54(f)"
Subject:
Respon e to Generic Letter 91-06 Gentlemen:
Generic Letter 91-06 requested information pursuant to 10 CFR 50,54(f) regarding safety-related DC power systems. In Enclosure 1 to this letter, New llampshire Yankee (N!!Y) provides the specific responses to the questions of Generic Letter 91-06 for Seabrook Station. Explanatory notes accompany the response to several questions.
The Seabrook St. tion Class IE Electrical System is divided into two load groups:
Train A and Train B. Either load group supplies all equipment necessary to safely shut down the reactor under any of the design bash, accident conditions analyzed in the Updated FSAR (UFSAR)c The safety-related DC power system for Seabrook Station, described in UFSAR Section 8.3.2.1, is an integral part of the Class 1E Electrical System . Each train en; ploys two battery banks, two battery chargers and two DC buses. Each ba:tery bank is normally connected to one vital DC bus and can also be simultaneously connected to the other vital DC bus in the same train. Each battery bank has the electrical capacity to handle the full 100 percent load requirements of both vital DC buses withir. its electrical Tr a in.- Therefore, each electrical Train, either A or B has the capability to be powered by a single battery bank. System design precludes any Train A battery, charger or DC bus from being cross. connected to its Train B counterpart.
Control Room indications and alarms are available to alert the operator to conditions of inoperability affecting the DC power system. Technical Specifications require both trains of the DC power system to be operable in Operational Modes 1 through 4 and one train to be operable in Modes 5 and 6. '
i 911Q,3,00lb4 9110 os ADOCK 0500 @- l New Hompshire Yonkee Division of Public Service Company of New Hampshire P.O. Box 300 = Seabrook, NH 03874 = Telephone (603) .t74-9521 f i} l
United States Regulatory. Commission October 25, 1991 Attcution: Document Control Desk Page two ,
New llampshire Yankee believes that at Seabrook Station, the DC power system design, the limitations of the Technical Specifications and the current level of maintenance and surveillance required by procedures ensures a high degree of availability of DC power to safety-related systems.
Should you have any questions on the above information or the specific responses to the Generic Letter 9106 questions set forth in Enclosure 1, please contact Mr. Geoffrey Kingston at (603) 474 9521 extension 3371.
Very truly yours, (pgl2 TH b Ted C. Feigenbaum Enclosure TCF:GK/ss STATE OF NEW ll AhlfSHIRE Rockingham, ss. October 25, 1991 Then personally appeared before me, the above-named Ted C, Feigenbaum, being duly sworn, did state that he _ is President & Chief Executive Officer of the New llampshire -
Yankee Division-of Public Service Company of New llampshire, that he is duly authorized
+
. to execute and file _ the- foregoing information in the name and on the behalf of New Hampshire Yankee Division of the' Public Service Company and that the statements therein are true to the best of his knowledge and belief.
\ H$6'/ / N /'d
-Tracy AheCredico, Notary Public My Commission Expires: October 3,1995
4 United States Regulatory Commission October 25, 1991 Attention: Document Control Dest Page thace ec: Mr. Thomas 1. Martin Regional Administrator U. S Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Project Directorate 1-3 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr, Noel Dudley NRC Senior Resident luspector P.O.130x 1149 Seabrook, Nil 03874 c
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l New llampshire . Yankee October 25, 1991-
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RESPONSE TO TIIE OUESTIONS OF ENCL.OSURE 1 TO GENERIC 1.ETTER OJ-06 ,
GENERIC 1 ETTER '91-06 OUESTIONS: (NHY's answLrs are in bold typeface)
The following information is provided for the following unit and site:
- 1. Unit 1. Seabroot. Station.
- 2. a. The number of independent redundant divisions of Class IE or safety related de power for this plant is 2. (luclude any separate Class IE or safety-related de, such as any de dedicated to the diesel generators).
- b. The number of functional safety-related divisions of de power necessary to attain safe shutdown for this unit is 1.
- 3. Does the co.strol room at this unit have the fo!!owing separate, independently annunciated alarms and indications for each division of de power?
i n. alarms
- 1. Battery disconnect or circuit breaker open? Yes.
- 2. Battery charger disconnect or circuit breaker open (both input ac and output dc)? See Note 3.a.2.
- 3. de system ground? Yes.
- 4. de bus undervoltage? Yes.
- 5. 'dc bus overvoltage? Yest (See Note 3.a..y.
i 4.
- 6. Battery charger failure? Yes.
- 7. Battery discharge? Yes,
- b. indications
- 1. Battery float charge current? Not (See Note 3.b.1).
- 2. Battery circuit output current? No; (See Note 3.h.2).
- 3. Battery discharge? Yes.
4.- Bus voltage? Yes.
- c. Does the urait have written procedures for response to the above alarms and indications? Yes.
I
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- 4. Does this unit have indication of bypassed and inoperable status of circuit breakers or other devices that can be used to disconnect the battery and battery charger from - 4
- its de bus and the battery charger from its ac power source during maintenance or testing? No; (See Note 4).
- 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. 'See note below. +
6, (1) llave you conducted a review of maintenance and testing activities to minimite the potential for human error causing more than one de division to be unavailable!
See Note 6 and (2) do plant procedures prohibit maintenance on redundant de divisions at the same time? No; (See Note 6).
If the facility Technical Specifications have provisions eq .ivalent to those found in the Westinghouse and Combustion Engineering Standard Technical Specifications for maintenance and surveillance, then question 7 may be skipped and a statement to that effect may be inserted here. See Note 7.
- 7. Are maintenance, surveillance and test procedures regarding station batteries conducted routinely at this plant? Specifically:
- a. At least once per 7 days are the following verified to be within acceptable limits:
- 1. Pilot cell electrolyte level?
- 2. Specific gravity or charging current?
- 3. Float voltage?
- 4. Total bus voltage on float charge?
E - 5. - Physical condition of all cells?
- b. At least once pu 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?
- 2. The average specific gravity of all cells?
lL 3. The specific gravity of each cell' L 4 'The average electrolyte temperature of a representative number of cells?
l l.
i 5. The float voltage of each cell?
- 6. Visually inspect or measure resistance ok terminals and connectors (including the connectors at the de bus)?
4 2
4
^
- c. At least every 18 months are the following verified:
- 1. Low ' resistance of each connection (by test)? '
- 2. Physical condition of the battery?
- 3. Battery charger capability to deliver rated ampere output to the de bus?
- 4. The capability of the battery to deliver its design duty cycle to the dc.
bus?
- 5. Each individual cell voltage is within acceptable limits during the service test?
- d. At least every 60 months, is capacity of each battery verified by performance of a discharge test?
' c. At least annually, is the battery capacity verified .by performance discharge test, if the battery shows signs of degradation or has reached 85% of the expected service life? '
L8. Does this plant have operational features such that following loss of one safety related dc. power supply or bus:
- a. Capability is maintained for ensuring continued and adequate reactor cooling?
Yes,
- b. Reactor coolant system integrity and isolation capability are maintained? . Yes,
- c. Operating procedures, instrumentation (including indicators and annunciators),
and control functions .are adequate.to initiate systems as required to maintain adequate core ; cooling? ' Yes.
- 9. If the answer to any part of question 6,7 ;or 8 is no, then provide your basis for not performing the ' maintenance, surveillance and test ptocedures described and/or the F
bases for not including the operational features cited. *See note' briow- .
- Note: For . questions involving supporting type information (question numbers 5 and 9)
.instead of developing and supplying the information in response to this letter, you may .
~
. commit to further. evaluate the need for such provisions -during the performance of L your individual plant examination for severe accident vulnerabilities (IPE). If you
. select this~ option, you are required to:
(1) So state in response to these questions, and (2)- Commit to explicitly address questions 5 and 9 in your IPE submittal per the guidelines outlined in NUREG-1335 (Section 2.1.6, Subitem 7), " Individual Plant Examination: Submittal Guidance."
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E.ESPONSE TO GENERIC LETTER 9106 BDTES 3.a.2. Each battery charger has four circuit breakers associated with it: an internal and an external AC input circuit breaker plus an internal and an external DC output circuit breaker. An alarm is associated with the position of the external DC output circuit breaker. The position of the remaining three circuit breakers is not directly associated with an clarm, llowever, UFSAR Section 8.3.2.1.f. describes two alarms which indicate loss of AC input voltage to the charger and loss of DC output current from the charger. These alarms effectively monitor battery charger operability.
3.a.5. As described in UFSAR Section 8.3.2.1.f.5., the DC bus overvoltage alarm is provided by an overvoltage relay at the charger, 3.b 1. UFSAR Section 8.3.2.1.f.1 indicates that an ammeter is located in the Con %d imom and at the DC switchgear to indicate battery charge and discharge, '1 he Control Room ammeter does not have sufficient resolution to read battery float current because it is scaled to display discharge current which can be much higher than float current. .'A local, digital ammeter is provided with sufficient resolution to read normal float charging current, A loss of charging current alarm derived from this digital ammeter is available in the ' Control Room. Technical Specifications require -
verification of battery float charge at least every seven days during Operational Modes 1 through 4. The NRC has reviewed the Seabrook design as described in UFSaR Section 8.3.2.1 and found it acceptable as discussed in NUREG-0896, the Safety Evaluation Report for Seabrcok Station.
3.b.2. It is assumed that this question refers to battery charger output current. As described in UFSAR Section 8.3.2.1.f.2., an ammeter located at the charger provides indication of. battery charger output current. As described above in the Note to question No.
3 b.1., two alarms monitoring charger performance are provided in the Control Room:
- a loss of battery charging current alarm and a charger failure alarm. Charger output current is indicated locally. at the charger. The NRC has reviewed the Seabrook g design as described in UFSAR Section 8.3.2.1 and found-il acceptable av discussed in. NUREG 0896, the Safety Evaluation Report for Seabrook Station.
4, The position of the station battery output fuses and circuit breakers and the charger
- AC input - and DC output circuit breakers are not direct inputs to the Bypass Indication . System described in UFSAR Sectior 7.1.2.6, These components are not '
included in the " bypassed and inoperable status" logic because maintenance and testing !
affecting operability of the batteries and chargers are not expected to be. performed more than once per year. However,- the Bypass Indication System does monitor the availability of. DC control power to the systems listed ~ in UFSAR Section 7.1.2.6.
These systems are required to operate under accident conditions. Loss of DC control:
power to _a- Train of 'any of these systems will actuate the bypass alarm for that particular Train.
- 6. An evaluation performed in response to IE Bulletin No. 79-27-was described in the UFSAR in the response to RAI 420.50. This review focused on the manner in which electrical power systems could effect the ability to achieve cold shutdown. With 1
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' respect to Class 1B DC power systems, the review concluded that failure of any single bus will 'not-affect the ability to achieve a cold shutdown condition. This review did not' assess the potential for human error causing more than one Train of the' DC power system to be' unavailable.
Potential failure modes- of the DC power system were evaluated as part of the Individual Plant Examination for Severe Accident Vulacrability (IPE). The evaluation concluded that there was no credible, internal, common.cause failure mode affecting the Station batteries and bus work of the DC distribution system.
Technical Specifications require the operability of both Trains of the DC power system.
in Operetional Modes 1 through 4 and one Train in Modes 5 and 6. The concept that redundant Trains- of safety related equipment should not be simultaneously out of .
service (unless permitted by Technical Specifications) is so axiomatic that plant procedures do not specifically prohibit such action. The responsibility to ensure that
- equipment operability status meets Technical Specifications requirements rests with the l Shift Superintendent. Control Room indications and alarms provide equipment status i information' and reminders of out of-service conditions. Procedures provide guidance, specific instructions, notes and cautions supporting the goal of meeting Technical Specifications requirements. - For example, procedures for planning anct scheduling catablish a " system week". concept under which preventive maintenance and surveillance-testing 'is performed.on one designated-Train of safety telated equipment during a calendar week. .Under this concept, if a given week were designated for Train A work, the Shift Superintendent would question t.ny request to perform work on Train '
.B equipment. As anots example, a procedure defines a tracking system to be-used upon er.tering a Technical Specifications action statement. This tracking system can assist the Shiff Superintendent in maintaining cognizance of inoperable equipment and avoiding action . to render the redundant train inoperable. As a final example, procedures for-performing vital battery discharge tests include cautions referring to Technical Specifications to remind involved personnel to maintain the required number of operable DCfpower sources. ,
- 7. cSeabrook Station Technical Specifications are based on the Westinghouse Standard Technical Specifications. Therefore, as permitted by Generic Letter 91-06, the specific responses to Question No. 7 have been omittedc a
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