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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] |
Text
@
r eab k NH 03074 a Telephone (603)474 9521 f
jh h FLcsimile (603)474 2987
. Energy Service Corporation Ted C Felgenbaum Senior Vice President and i Chief Nuclear Officer NYN-92112 ,
i August 17, 1992 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk
References:
(a) Facility Operating License No. NPF-86, Docket No. 50-443 (b) NHY Letter, NYN-88090 dated July 8, 1988,
- Projected Reference Temperature Values for Pressurized Thermal Shock Eve n t s," U. S.
Thomas to USNRC (c) North Atlantic Letter, NYN-92111 dated August 17, 1992 " License Amendment Request 92-06: Revised RCS Pressure / Temperature Limits",
T. C. Feigenbaum to USNRC
Subject:
Revised Reference Temperature Values for Pressurized Thermal Shock Events Gentlemen:
North Atlantic Energy Service Corporation (North Atlantic) prov' les revised Reference Temperatures for Pressurized Thermal Shock (RTpts) for Seabrook Station in Enclosure 1.
The revised values were calculated in accordance with 10CFR50,61 " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Even ts" utilizing the methodology delineated in Revision 2 to Regulatory Guide 1.99, " Radiation Einbrittlement of Reactor Vessel Materials" The revised RTns values supersede the values that were submitted on July 8,1988 [ Reference (b)). A cmy of the July 8,1988 letter is provided in Enclosure 2.
The revised RTers values were developed by Yankee Atomic Electric Company Nuclear Services Division (YNSD) for the Seabrook Station Unit I reactor vessel. For all reactor vessel locations, the value for RTers at the end of licensed life (32 EFPY) is significantly less than the screening value, in ~ a separate transmittal dated August 17, 1992 [ Reference (b)) North Atlantic submitted License Amendment Request 92-06 which proposes to revise the Seabrook Station Technical Specification Pressure / Temperature Limits. The enclosed RTpy3 values are being submitted concurrent with the submittal of License Amendment Request 92-06 as required by 10CFR50.6L i
I l
b a member of the Northeast Utilities system 0 l 9208240004 920817
- PDR ADOCK 05000443 \\
P PDR
' United States Nuclear Regulatory Commission August 17, 1992
- Attention:
Document Control- Desk Page two
- . Should you have any questions or require further assistance, please contact Mr. James M. Peschel, Regulatory Compliance Manager, at'(603) 474 9521 extension 3772.
Very truly yours,
/ '
Ted C. Feigenba t TCF:M DO/ss/ tad -
cc: Mr. Thomas T. Martin Regional Administ'rator U. .S. Nuclear Regulatory Commissioc Region I 475 Allendale _ Road
- King _of Prussia, PA- 19406 Mr. Gordon E. Edison, Sr. Project Manager Project Directorate'l 3 .
- - .. Division of- Reactor Projects'.
U.S; Nuclear Regulatory Commis* ion
--Washington, DC- 20555 Mr.! Noel Dudley -
NRC Senior.. Resident Inspector P.O. Box 1149 Seabrook, NH 03874
, _ . . - . , . . .. _ __ _.- _. . -- . . ...m . _ . _ . .._ . ___... __ . m_. . . . __ . _ . _. .._ .
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North Atlantic En'ergy Service Corporation August 17, 1992
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- ENCLOSURE 'l TO NYN-92112 t-L f
3-.,
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y p i r,- ,p g ' p.g .c- .+- yy-~w ,, --e+ e ,-.--r- ysa.,r-vvw- re sww-.+, -
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t
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RTn3 UALUES -'SEABROOK UNIT NO.-l1_ REACTOR UESSEL'
.2 EFPY: .Cu Ni I*:+ lM t+ ART ns. =
RTns SCREENING
_ . COMPONENT. ' CODE N0'. FLUENCE- .(Wtg.Z) '~
g (Wtg .' Z ) ~(*F)= (*F) (*F) (*F)- '. VALUE/ *F :- -
2 (n/cm ) ,
- Intermediate Shell R1806-1 . 3.1 j x '101 ' ' . 0. 04 ' O.64 40- +- 34 + 34 = 108. ~ 2 7 0. '
Intermediate
- Shell R1806-2? 3;l x 10.' 1
~0. 0 5' . 'O.65 0 '+ . 34 + 41 '= 75 270 4
Intermediate _ .
Shell' R1806-3' 3.1 x:10 ' 1
'0.07 0.65 10 + 34 .+ 58 = 102 270' 4
Lower Shell R1808-1 3.1 x 10 ' 1 O.05 0.58 40 '+ 34 + 41 = 115 270
. Lower Shell RIS08-2' 3.1 x'10 19 0.05 0.57 10 + 34 + 41 = S5 270 Lower Shell R1808-3 3.1 x'10 ' 1 O.06' 0.57 40 +. 34 + 48 = 122 270 Inter to Lower.
Shell Girth Weld Seam G1. 72' '3.1 x 10 ' 1
'O.07 0.02 -50.+ 56 + '45 = 51 300 Inter and Lower Shell Long Weld .7 Seam G1.72 3.1 x 10 '"-1 0.07 0.02 -50 + 56 + 45 = 31 270
- All of the initial reference temperatures that are shown are measured values.
- Although only a few of these six longitudinal welds are located near the peak flux regions around the core, the. peak fluence was used for all of the longitudinal-welds as a conservatism.
DEFINITIONS I' - Initial Reference Temperature of the unirradiated material as defined.in ASr. Code Section'III, PP NB-2331.
M - Margin to cover uncertainties in material properties as defined in 10CFR50.61(b)(11).
RTns - . I + M + ARTns s __ . .
., . .... - -. - - .a 1
- g. ..
i' 4 9
I ., . North Atlantic Energy; Service Corporation August 17, 1992 1) o, < -
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l-- . ENCLOSURE 2 TO NYN-92112 l; -
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ll y. ,,.. . , ~ . , - - - . ,,,~--,--.m , , m e e-
George S. Thomas -
t= vice hesidani-Nuclear heduction
_- [. ..
! NYN- 88090 i Mblic Service of New Hampshire- July 8, 1988
' New $ampshire Yankee DMsion - .
United' States Nuclear Regulatory Commission Washington, D.C. 20555
-Attention: Document Control Desk
Reference:
Facility Operating License No. NPF-56, Docket No. 50-443
Subject:
' Projected Reference Temperature Values For Pressurized Thermal Shock Events Gentlemen This is provided(in ges,ponse to:a request-by.the NRC.Staffifor dnfo'rdstionp' ettaining sto the ref erence -temperatures"(RT)'for pressurized $
tthermal-shocks (PTS)*cvents. Enclosure 1 provides data developed for New Hampshire Yankee (NHY) by Vestinghoust Electric Corporation for the Seabrook Station Unit I reactor vessel. The Westinghouse information is based on the
- methods and generic assessment as outlined in 10CFR50761'(b)', and is provided
'in Enclosure-2. . Westinghouse has provided the same calculations for other similarly-designed Pressurized Water Reactors.
Should you have any questions or require further' assistance, please contact'Mr. Timothy G. Pucko at (603) 474-9574 extension 4428.
Very truly yours, d
Geor . Thomas
'Esclosure ce s. Mr.' Victor Nerses, Project Manager Project Directorate I-3
-. Division of Reactor. Projects United States Nuclear Regulatory Comission Washington,-.DC- 20555 Mr. Villiam T. Russbil Regional Administrator
~ United States Nuclear Regulatory Comission Region I 425 Allendale Road f . ,,,eg . ' King of Prussia, PA 19406 f
'Mi[7-s Mr.-Antone C. Cerne NRC Senior Realdent Inspector ,
I
'Seabrook Station
,Seabrook, NH 03874 O h94p.O. Box 300 . Seabrook, NH 03874 . Telephone (603) 474-9574
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&)}n,} jr) , -
ENCLOSURE 1 TO NYN . 88090 -
t RTpyn VALUES - SEAEROCK UNIT NO. 1 REACTOR VESSEL ,
32 EFPY Cu N1 I* + M + ARTNDT
- EIFTS SCFEENING COMPONENT CODE FO. FLUENCE (n/cm2) (Wtg.2) (Weg.I) (*F) (*F) (*F) (*F) VALUE/*F i
Intermediate Shell R1806-1 3.1 x 1019 0.04 0.64 40 + 48 + 24 - 112 270
~ntermediate Shell R1806-2 3.1 x 1019 0.05 0.65 0 + 48 + 34 - 82 270 Intermediate Shell R1806-3 '3.1 x 1019 0.07 0.65 10 + 48 + 53 - '11 270
~
Lower Shell R1808-1 3.1 x 1019 C.05 0.58 40 + 43 + 32 - 120 270 Lower Shell R1808-2 3.1 x 1019 0.05 0.57 10 + 43 + 32 -
90 270 Lower Shell R1803-3 3.1 x 1019 0.06 0.57 40 + 48 + 41 - 129 270
~
Inter to Lower Shell G1.72 3.1 x 1019 0.07 0.02 -50 + 48 + 32 - 30 300 ,
Girth Weld Seam .
Inter and Lower Shell C1.72 3.1 x 1019 ** 0.07 0.02 -50 + 48 + 32 -
30 270 Long Veld Scam
- All of the initial refere: e temperatures that are shown are measured valves.
- Although only a few of these six longitudinal welds are located near the peak flux regions around the core, the peak fluence was used for all of the longitudinal welds as a conservatism.
DEFINITIONS:
1 - Initial Reference Temperature of the unirradiated material as defined in ASME Code S : tion III, PP NB-2331.
M - Margin to cover uncertainties in material properties as defined in 10CFR30.61(b)(ii).
RTFTS - I+M+RTNDT- .
I
INCLOSURE T 70 HYN- 88090 THE CALQULATION OF ET ,
e pts
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In the PTS Rule, the NRC Staff has selected a conservative and uniform method for determining plant-specific valves of RTPTS at a given time. The prescribed equations in the PTS Rule for calculating RTPTS are actually one of several ways to calculate RTHDT. For the purpose of comparison with the Screening Criterien the value of KTp73 for the reactor vessel must be calculated for each veld and plate, or forgoing in the beltline region as given below. F>r each material, RTp73 is the lover of the results given by Equatiens 1 a*.1 2.
Equation 2:
0.270 RTPTS " I + N *s [-10 + 470(Cu) + 350(Cu)(Ni)) f A EI NDT Equation 2:
0 RT PTS = I + M +%283 f 194 <
A RT NDT vhere, I means the initial reference trancition temperature of the unirradicted
%g f
o material measured as defined in the ASMI Code, PP NB-2331. If a measured hF value is not available, tha following generic mean values must be used:
0 F for velds made with Linde 80 flux, and -56 0F for velds made with Linde 0091, 1092 and 124 and ARCOS E-5 veld fluxes.
H means the margin to be added to cover uncertainties in the values of initial RTNDT, copper and nickel content, fluence, and calculation procedures. In Equation 1, M-48 F if a measured value of I va; used, and M-59 F if the generic mean value of I was used. In Equation 2, M-0 F if 0
a measured value of I was used, and M-34 F if the generic mean value of I was used.
Cu and Ni means the best estimate weight percent of copper and nickel in the traterial, f means the maximum neutron fluence, in units of 1019n/cm2 (E greater than or equal to 1 MeV). at the clad-base-metal interface on the inside surface of the vessel at the location where the material in question receivts the highest fluence for the period of service in question.
Note that since the chemistry valurs given in Equations 1 anr' 2 are best estimate mean values, and the margin, M, causes RTPTS valuer to be upper bound predictions, the mean material chemistry values are to be e d, when available, so as not to compound conservatism.
M W.
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