Similar Documents at Salem |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3371999-05-21021 May 1999 Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622 ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20059M9281990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20246J5581989-08-28028 August 1989 Grants 890609 & 16 Requests for Withholding of Rev 0 to TR-ESE-737 from Public Disclosure Per 10CFR2.790 ML20246C3941989-08-15015 August 1989 Forwards Safeguards Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14.No Violations Noted ML20245B2811989-06-19019 June 1989 Ack Receipt of & Payment of Civil Penalty in Amount of $50,000,per NRC .Region I Will Review Info Provided Re Limitorque Gear Case Grease Relief Example of Violation & Provide Separate Response ML18094A5401989-06-16016 June 1989 Fowards Response to NRC Bulletin 88-003 Re Potential Inadequate Latch Engagement in GE Hfa latching-type Relays. Until alternative-type Relays Available,Spare GE Hfa Relays Ordered for Replacement in-kind Applications ML20247A7781989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl ML20151Z2391988-08-25025 August 1988 Forwards Request for Addl Info Re 880227 Request for Exemptions to Allow Util to Take Credit for Respirators Fitted W/Sorbent Cartridges for Protection Against Airborne Radioidine.Response Requested within 30 Days ML20151B2481988-03-31031 March 1988 Forwards Enforcement Conference Rept 50-311/87-29 on 880212 Re Findings in Insp Rept 50-311/87-29 ML20148G5021988-03-22022 March 1988 Forwards Safeguards Insp Repts 50-272/88-06,50-311/88-06 & 50-354/88-04 on 880201-05.No Violations Noted ML20154D4221988-03-21021 March 1988 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-272/83-37. Violations Occurred as Stated in Notice of Violation & Appropriately Classified in Aggregate at Severity Level III ML20237F1231987-12-16016 December 1987 Ack Receipt of Informing NRC of Actions Taken to Correct Violations Noted in Insp Repts 50-272/87-21 & 50-311/87-26 ML20236P4951987-11-12012 November 1987 Forwards Exam Repts 50-272/87-26OL & 50-311/87-26OL for Exams Administered on 870915-17 ML20236G1551987-10-28028 October 1987 Forwards Safety Insp Rept 50-272/87-27 on 870921-25.No Violations Noted ML20238A8771987-08-31031 August 1987 Recommends That Site Specific Info Sheets & Appropriate Training Re Use Be Developed & Provided to Emergency Notification Sys & Health Physics Network Communicators to Facilitate Responses to NRC Requests for Data.Samples Encl ML20237H1641987-08-25025 August 1987 Forwards Requalification Program Evaluation Repts 50-272/87-21OL & 50-311/87-26OL of Exam Administered During Wk of 870615.Requalification Training Program Found Unsatisfactory,Per NUREG-1021 ML20237H5441987-08-12012 August 1987 Forwards Results of Nonradiological Chemistry Stds Insp Activities for All Region I Licensees During 1985-1986. Results of Measurements Made by BNL Also Included ML20236G9631987-07-29029 July 1987 Ack Receipt of Util Transmitting Proposed Amend to Plant Physical Security Plan.Addl Info,Including Commitment to Ensure Prompt Access to Vital Equipment During Emergenies & Revs to Plan,Requested Prior to NRC Approval ML20235H3711987-06-30030 June 1987 Advises That 861202 Miscellaneous Amend Changes to Security, Safeguards Contingency Plan & Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Requests Response to Unacceptable Portions within 30 Days IR 05000272/19830371987-06-15015 June 1987 Discusses Insp Rept 50-272/83-37 on 831205-06 & Forwards Notice of Violation ML20214S8001987-06-0404 June 1987 Forwards NRC Form 398 Re Personal Qualifications Statement for Licensee,Reflecting Changes to 10CFR55,effective 870526. Revised Form Requires New Applicants to Complete Each Category Completely.Form to Be Used Beginning 870526 ML20205G0571987-03-24024 March 1987 Forwards Insp Repts 50-272/87-05 & 50-311/87-07 on 870224-27.No Violations Identified ML20204G7891987-03-20020 March 1987 Advises That 870130 Temporary Change to Salem & Hope Creek Security Plans Re Compensatory Measures to Be Implemented During Training of Security Supervisors for 870202-27 Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20205E9371987-03-20020 March 1987 Forwards Exam Rept 50-311/87-06OL of Exam Administered on 870213.Concern Expressed Re Adequacy of Training Due to Lack of Sufficient Understanding of Unique Requirements of Facility Tech Specs ML20204E7631987-03-19019 March 1987 Informs That 861230 Rev 5 to QA Program Description Acceptable.Omission in Figure 17.2-1 of Original Submittal Clarified ML20207S4981987-03-17017 March 1987 Requests Remittance of Fee for 861231 Application Requiring Review & Approval of Proposed Corporate Reorganization of Atlantic City Electric Co ML20207S4041987-03-12012 March 1987 Forwards Safety Insp Repts 50-272/87-03 & 50-311/87-04 on 870127-0223 & Notice of Violation ML20207S3181987-03-11011 March 1987 Forwards Mgt Meeting Repts 50-272/86-23 & 50-311/86-23 on 870203.Three Potential Enforcement Items Identified ML20207S2901987-03-10010 March 1987 Forwards Insp Rept 50-311/87-05 on 870203-06.No Violations Observed ML20212J2161987-03-0202 March 1987 Forwards Safety Evaluation & Technical Evaluation Rept Re Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys On-Line Functional Testing. Response Acceptable ML20212F1251987-02-27027 February 1987 Forwards Corrected SALP Repts 50-272/85-98 & 50-311/85-98 for Oct 1985 - Sep 1986.Attendees List of 870218 Mgt Meeting W/Util Encl.Believes That Addl Attention Needed to Reduce Number of Challenges to Safety Sys ML20212B9031987-02-25025 February 1987 Forwards Insp Repts 50-272/87-02 & 50-311/87-02 on 870112- 16 & Notice of Violation ML20211F5611987-02-17017 February 1987 Forwards Insp Repts 50-272/87-01 & 50-311/87-01 on 870101- 26.No Violations Observed ML20210V3801987-02-11011 February 1987 Forwards Safety Insp Rept 50-311/87-03 on 870112-23. Enforcement Conference Scheduled for 870227 to Discuss Concerns Re RHR Valve Misalignments Resulting in Inoperability of ECCS on 870112-13 ML20212R2501987-01-21021 January 1987 Forwards Exam Repts 50-272/86-27OL & 50-311/86-27OL of Exam Administered During Wk of 861103 ML20197C9571987-01-20020 January 1987 Forwards SALP Repts 50-272/85-98 & 50-311/85-98 for Oct 1985 - Sept 1986.Meeting Scheduled for 870121 to Discuss Assessment & Plans to Improve Areas Needing Mgt Attention. Requests Written Comments within 30 Days After Meeting ML20212K8501987-01-16016 January 1987 Forwards Safety Insp Rept 50-311/86-35 on 861119-27.No Violations Noted IR 05000272/19860321987-01-16016 January 1987 Forwards Safety Insp Repts 50-272/86-32 & 50-311/86-36 on 861125-1231.Licensee Identified Violations Re Failure to Complete Tech Spec Surveillance Noted.No Notice of Violation Issued,Per 10CFR2,App C ML20207N5281987-01-0909 January 1987 Forwards Safety Evaluation & Eg&G Idaho Input Reviewing Util 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Program - Reactor Trip Sys Components. Response Acceptable ML20207M4391987-01-0606 January 1987 Forwards Exam Repts 50-272/86-26OL & 50-311/86-31OL of Exams Administered on 860912 ML20211Q1821986-12-16016 December 1986 Requests Util Cooperation in Increasing NRC Resident Inspector Onsite Visibility.Inclusion of Resident Inspector Videotape in General Employee Training Requested ML20214L0601986-11-19019 November 1986 Forwards AEOD SALP Input for Facilities Operations (LER Quality) for Oct 1985 - Sept 1986.LERs Sampled of Very High Quality ML20213E9011986-11-0606 November 1986 Requests That Util Investigate Allegation of Use of Controlled Substance by Employee of Util Contractor,As Discussed in 861029 & 1104 Telcons.Response Re Veracity of Allegations & Impact on Safety Requested within 30 Days ML20213E4701986-10-29029 October 1986 Advises That 860930 Temporary Change to Security Plans, Identifying Compensatory Measures to Be Taken During Const Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Consolidated Plans Must Be Separate Amend Submittal to NRR ML20215M7421986-10-24024 October 1986 Forwards Insp Repts 50-272/86-22 & 50-311/86-22 on 860915-17.No Violations Noted.Ability to Implement Emergency Plan Demonstrated ML20211C2001986-10-14014 October 1986 Requests Review of Allegation That Previous Util Employee Identified in 861001 Telcon May Not Possess Valid Educational Credentials.Results of Review & Current Employee Screening Methods Requested within 30 Days ML20210P7451986-09-25025 September 1986 Forwards Insp Rept 50-311/86-26 on 860826-30.Proposed Actions Responding to Unresolved Items Requested within 30 Days of Ltr Receipt ML20214F6671986-09-10010 September 1986 Notifies of 861029-30 Physical Protection Seminar in Cherry Hill,Nj to Discuss Results of 12-yr Implementation of 10CFR73 for Protection Against Radiological Sabotage. Preliminary Agenda Encl ML20207J2191986-07-15015 July 1986 Forwards FEMA 44CFR350 Approval for State of DE & Local Radiological Emergency Plans,Pending Public Alert & Notification Sys Verification ML20244D9251986-05-29029 May 1986 Confirms 860610 Survey of Emergency Data Sys Capabilities for Possible Use as Part of Emergency Response Data Sys. Survey Checklist Encl ML20198S4321986-05-27027 May 1986 Forwards Exam Repts 50-272/86-09 & 50-311/86-09 Administered During Wk of 860407 1990-06-13
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20198H1851998-12-15015 December 1998 Responds to to President Clinton Re Rept by Gao, Issued 970530 on NRC Oversight of Nuclear Power Industry ML20198B7611998-12-0303 December 1998 Informs That on 981007,generic Fundamentals Exam Was Administered to 148 Candidates at 21 Facilities.Summary of Statistical Results of Exam Listed.Contents of Exam Along with Associated Input Data Needed for Updating Catalog Encl ML20155J7191998-11-0505 November 1998 Fourth Final Response to FOIA Request for Documents.Records Listed in App G Being Released in Entirety.Documents Listed in App H Being Withheld in Part (Ref FOIA Exemption 5) IA-98-323, First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3)1998-10-0909 October 1998 First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3) ML20154P4011998-10-0909 October 1998 First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3) ML20154B3781998-09-25025 September 1998 Informs That Facility Scheduled to Administer NRC Generic Fundamentals Exam on 981007.Sonalysts,Inc Authorized Under Contract to Support NRC in Administration of Activities. Ltr & Encls Provide Instructions & Guidelines ML20151V8401998-09-10010 September 1998 Informs That Util Authorized to Administer Initial Written Exams to Listed Applicants on 980917.NRC Region I Operator Licensing Staff Will Administer Operating Tests on 980914- 16 ML20151W9711998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Have Been Assigned as SRAs in Region I ML20238F1581998-08-31031 August 1998 Informs That as Result of Review of Records,Duplication of Costs Charged for Insp Conducted at Salem Unit 2 Was Found. Amount Overcollected Will Be Transferred to Licensee within 10 Days from Date of Ltr ML20249C7661998-06-26026 June 1998 Second Partial Response to FOIA Request for Documents. Documents Listed in App D,Being Released in Entirety ML20247B4141998-05-0606 May 1998 Final Response to FOIA Request for Documents.Forwards Documents Listed in App a Being Made Available in PDR IA-98-179, Final Response to FOIA Request for Documents.Forwards Documents Listed in App a Being Made Available in PDR1998-05-0606 May 1998 Final Response to FOIA Request for Documents.Forwards Documents Listed in App a Being Made Available in PDR ML20217P4601998-05-0101 May 1998 Forwards ERDS Implementation Documents Including Data Point Library Updates for Robinson (Number 248),Peach Bottom (Number 249),Surry (Number 250),Crystal River (Number 251), McGuire (Numbers 252 & 254) & Salem (Number 253).W/o Encl ML20217N5851998-04-24024 April 1998 Partially Deleted Ltr Ref 10CFR2.790 Re NRC Investigation Repts 1-96-024 & 1-96-031 Conducted at Pse&G Plants Documenting That Crowe as Cas/Sas Operator,Falsified Records of Safeguards Event Log in May 1996 ML20217N8881998-04-24024 April 1998 Partially Deleted Ltr Referring to Investigation Rept 1-96-024 Conducted at Pse&G Plant,Documenting That as Wackenhut Systems Operator Supervisor,Recipient Falsified Records of Safeguards Event Log in May 1996 ML20217N5891998-04-24024 April 1998 Refers to NRC Investigations 1-96-024 & 1-96-031 Conducted by OI Re Allegations of Deliberate Posting of Inaccurate Info in Safeguards Event Logbook & Discrimination by Wackenhut Staff.Decided to Await Issuance of DOL Decision ML20217N5491998-04-24024 April 1998 Refers to NRC Investigations 1-96-024 & 1-96-031 Conducted by OI Re Activities Performed by Wackenhut Staff Working as Contract Security Force Personnel at Salem & Hope Creek. Decided to Await Issuance of DOL Decision Re Discrimination ML20217B6341998-03-20020 March 1998 Discusses NRC OI Rept 1-96-031 & DOL Case 97-ERA-52 on 971001.Contract Security Officer Employed by Wackenhut at Salem/Hope Creek Discrimiated Against for Raising Safety Concerns ML20203F2311998-02-20020 February 1998 Ltr Contract:Task Order 136 Entitled, Salem Restart Readiness Review, Under Contract NRC-03-93-026.Statement of Work Encl IA-97-325, Seventh Final Response to FOIA Request for Documents. Documents Listed in App I Being Released in Entirety. Documents Listed in App J Being Withheld in Entirety (Ref FOIA Exemption 4,6 & 7C)1997-12-10010 December 1997 Seventh Final Response to FOIA Request for Documents. Documents Listed in App I Being Released in Entirety. Documents Listed in App J Being Withheld in Entirety (Ref FOIA Exemption 4,6 & 7C) ML20203G5611997-12-10010 December 1997 Seventh Final Response to FOIA Request for Documents. Documents Listed in App I Being Released in Entirety. Documents Listed in App J Being Withheld in Entirety (Ref FOIA Exemption 4,6 & 7C) ML20202J3211997-12-0808 December 1997 Sixth Partial Response to FOIA Request for Documents.Record Subj to Request Encl & Identified in App H ML20202B0251997-11-26026 November 1997 Fourth Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App D ML20199J1611997-11-24024 November 1997 Third Partial Response to FOIA Request for Documents. Documents Listed in App C Being Released in Entirety & Encl ML20199J1161997-11-21021 November 1997 Second Partial Response to FOIA Request for Documents. Records in App B Encl & Withheld in Part (Ref FOIA Exemption 7) ML20202D0541997-11-19019 November 1997 First Partial Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in App a ML20202B6531997-06-0606 June 1997 Discusses Investigation Conducted by NRC OI to Review Whether Pse&G Intentionally Operated Outside Design Basis & Failed to Make Timely Notification of Unanalyzed Condition Re Pops.Concluded That Pse&G Made Changes to Facility ML20140E1091997-06-0505 June 1997 Ltr Contract:Task Order 112, Salem Restart Readiness Review, Under Contract NRC-03-93-026 ML20148K0551997-06-0404 June 1997 Forwards Amends 194 & 177 to Licenses DPR-70 & DPR-75, Respectively.Amends Change TSs 3.4.3 & 3.4.5, Relief Valves, to Ensure Automatic Capability of PORVs to Relieve Pressure Is Maintained When Valves Are Isolated ML20148C3561997-05-12012 May 1997 Thirty-fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App Rrr Being Made Available in Pdr.App SSS Records Being Withheld in Part (Ref FOIA Exemption 6) ML20148C2281997-05-0808 May 1997 Ltr Contract:Task Order 126, Evaluation of Salem Restart Test Program, Under Contract NRC-03-93-026,awarded to Parameter,Inc ML20137X4881997-04-11011 April 1997 Final Response to FOIA Request for Documents.Forwards App Ee Records Being Withheld in Part (Ref Exemptions 5 & 6) ML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities ML20147F8381997-03-25025 March 1997 Responds to to Chairman Jackson Expressing Concerns Re NRC Confirmatory Order Suspending Authority for & Limiting Power Operation & Containment Pressure & Demand for Info, ML20137H4051997-03-24024 March 1997 Twelveth Partial Response to FOIA Request for Documents. App DD Records Being Withheld in Part (Ref Exemptions 5 & 6) ML20137A6311997-03-14014 March 1997 Third Final Response to FOIA Request for Documents.Records in App E Encl & Will Be Available in Pdr.App F Records Withheld in Part (Ref FOIA Exemption 3) ML20137A8601997-03-11011 March 1997 Second Partial Response to FOIA Request.Records Listed in App D Encl & Will Be Available in Pdr.App C Records Withheld in Entirety (Ref FOIA Exemption 5) ML20147F8591997-02-27027 February 1997 Responds to to Hj Miller Re Millstone,Salem & Myap Npps.Provides Answers to Questions Raised in to HR Meyer ML20135C0211997-02-26026 February 1997 First Partial Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in Pdr.App B Records Withheld in Entirety (Ref FOIA Exemption 5) ML20135B7551997-02-26026 February 1997 Eleventh Partial Response to FOIA Request for Documents. App AA Document Forwarded.App Bb Documents Partially Withheld (Ref FOIA Exemption 5).App CC Documents Withheld (Ref FOIA Exemption 5) ML20134P2801997-02-22022 February 1997 Ack Receipt of & Electronic Transfer of $100,000 in Payment for Civil Penalty Proposed by NRC in ML20135B9511997-02-20020 February 1997 Responds to 970113 & 30 Ltrs Requesting That Full Commission Vote to Determine Whether Plant Should Be Permitted to Resume Operations ML20134K1311997-02-11011 February 1997 Tenth Partial Response to FOIA Request for Documents. Forwards App X & Y Documents.Documents Available in Pdr.App X Documents Withheld in Part (Ref FOIA Exemptions 3 & 5).App Z Documents Withheld in Entirety (Ref FOIA Exemption 5) IR 05000272/19970011997-02-11011 February 1997 Forwards Initial Exam Repts 50-272/97-01OL & 50-311/97-01OL Administered on 970106-10 ML20134J8571997-02-0707 February 1997 Nineth Partial Response to FOIA Request for Documents. Records in App U Encl & Being Made Available in Pdr.App V Records Being Withheld in Part (Ref Exemptions 6) & App W Records Being Withheld in Entirety (Ref Exemption 5) ML20134H2521997-02-0606 February 1997 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR 1999-09-28
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, fA 4/ UNITED STATES
- O,w ./t NUCLEAR REGULATORY COMMISSION I. ), j WASHl. 3 TON. D. C. 20555 N.?:../ NRC PDit OCT 0 61978 Docket No. 50-311 Mr. R. L. Mittl General Manager - Projects Engineering and Construction Department Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101
Dear Mr. Mitti:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW 0F THE SALEM UNITV25fdNAL SAFETY ANALYSIS REPORT (FSAR)
As a result of our continuing review of the Salem FSAR, we find that we need additional information to complete our evaluation.
The specific information required is listed in the Enclosure.
Our review schedule is based on the assumption that this additional information will be available for our review by October 20, 1978. If you cannot meet this date, please inform us so that we may revise our schedule accordingly.
Please contact us if you desire any discussion or clarification of the enclosed request.
Sincerely, 0 . arrDhief Light Water Reactors Branch No. 3 Division of Project Management
Enclosure:
Request for Additional Information cc: See next page 1 8 W M 96 A $
Mr. R. L. Mittl OCT 0 61978 cc w/ enclosure:
Richard Fryling, Jr. , Esq.
Assistant General Counsel Public Service Electric & Gas Company 80 Park Place Newark, New Jersey 07100 Mark Wetterhahn, Esq.
Conner, Moore & Cober 1747 Pennsylvania Avenue, N.W.
Suite 1050 Washington, D. C. 20006 Mr. Leif J. Norrholm U. S. Nuclear Regulatory Commission Region I Drawer I Hancocks Bridge, New Jersey 08038 l
l
REQUEST FOR ADDITIONAL INFORMATION SALEM NUCLEAR GENERATING STATION UNIT 2 DOCKET NO. 50-311 5.106 In our request for additional information 5.8B we raised a concern which is related to the postulated tornado phenomenon, '
focusing on the method used by you in combining the induced loads and how this resultant load is combined with other loads in the various load combinations considered for the design of Category I structures. Your response indicated that all three loads (wind pressure, pressure differential and postulated-tornado-missiles) were considered in the design of Category I structures and that the resultant load was used in conjunction with other loads in case D of the
- load combination. However, you did not state how these three load were combined to generate the resultant total tornado load. Having established the effective loads for each of the above three individual tornado-generated effects, the combination thereof should then be determined in a conservative manner for each particular Category I structure, as applicable. An acceptable method of combining these effects is the following:
(i)Wt+Ww b (ii) Wt"W p (iii) Wt"Nm (iv) Wt"N w +.5W p (v) Wt" w * "m ,
(vi) Wt " "w + . 5 W p +W m where: Wt . . . . . total tornado load, Wg. . . . . tornado wind load, W p . . . . . tornado differential pressure load, and Wm . . . . . tornado missile load.
s'
-2 For each particular structure or portion thereof, the most adverse of the above combinations should be used as appropriate, These combined effects constitute the total tornado load, which should then be combined with other pertinent loads as specified in applicable load combinations. You should state if the method used for combining the three tornado related loads meet the above criteria. In the event that your criteria differ ,.
from those identified above, you should discuss how your proposed criteria compare with the criteria acceptable to us by indicating the relative degree of conservatism.
5.107 In request for additional information 5.94 we asked you to provide a comparison of the response spectra and damping values utilized in your seismic analysis with those specified in Regulatory Guides 1.60 and 1.61. We also asked you to determine if the combined effect of the use of your spectra and damping values afforded the same degree of conservatism as that resulting from the combined use of R.G.1.60 and 1.61. -
You compared the damping values used in your design with those _
identified in R.G. 1.61, but did not evaluate the combined effects of tha use of your spectra and damping values with those resulting from the use of R.G.1.60 and 1.61. Provide the information requested above for our review.
5.108 In request for additional information 5.97 we requested that you state your criteria for floor response spectra broadening '
of the Category I structures located on the soil media. We pointed out that the effect of parameter variation on floor response spectrum for the soil sites are normally accounted 4 for by increasing the individual peak widths by i 15%. You stated that in a previous submittal, you proposed i 10% increase.
However, you did not attempt to justify the adequacy of the proposed criteria in relation with the regulatory staff position ,
i provided in reque t for additional information 5.97. We require that you address the discrepancy between the two criteria and justify the i 10% value proposed. ,
5.109 In request for additional information 5.96 we requested that you provide the criteria used for the selection of the number of the lumped masses for the seismic system analyses. You referred to an answer provided to a staff question raised during the earlier (1974) FSAR review. The answer is found to agree in general to our philosophy. However, it is not specific enough. You should state if you follow the following staff position in the execution of your general philosophy identified in the answer to request for additional information 5.25 or describe and justify any other proposed position. The staff position is:
1
. k .
The number is considered adequate when additional degrees of freedom do not result in more than a a 10% increase in responses. Alternately, the number of degrees of freedom may be taken equal to twice the number of modes with frequencies less than 33 cps.
5.110 In request for additional information 5.100 we asked that you state if the fundamental frequencies of the key subsystems are controlled to be either greater than twice or less than one-half the dominant frequencies of their supporting system. Your response stated that the funda-mental frequencies of the key subsystems were considered in relation to the dominant frequencies of their supporting systems. However, you did not state if the above criteria were used to accomplish the adequate design of the key subsystems or some other criteria that may be proven to be just as adequate. Provide a more detailed response to this concern.
5.111 In request for additional information 5.99 we requested that you identify the method and results of the analysis used in accounting for the torsional effects of Category I structures.
You identified how you have accounted for the torsional effects of Category I structures other than the containment building.
You considered the containment building to be axisynmetric and stated that consideration of a torsional mode is not pertinent. It is our position that a minimum of 5% accidental eccentricity should be considered due to the facts that both construction tolerances and the internal structures would introduce some degree of eccentricity effect. This can be accomplished by evaluating the structure considering a 5%
accidental eccentricity. That is the distance between the actual center of mass and the center of rigidity must be modified by the 5% eccentricity. This modification should consist of an addition of 5% and a subtraction of 5% from the center of mass as shown below, with the controlling case used for design. .
~6Yo +6%
Y fi >
IN O I
Center of Rigidity f - b-. Direction of Excitation p ,
Actual Computed Eccentricity %r
_ Center of Mass _
qAf Provide information to demonstrate the extent to which the containment structure and the components located within the structure are capabic of withstanding the largest load resulting from this criteria.
5.112 In request for additional infurmation 5.105 we requested that you state if you have considered additional load combinations for assessing sliding, overturning and flotation potential of all Category I structures, as recommended by SRP 3.8.5.3. You stated that you have considered these potential phenomena, but did not indicate if you utilized the safety factors indicated in SRP 3.8.5.3.
You should indicate if you use the same safety factors used in SRP 3.8.5.3 for sliding, overturning and flotation forces or justify the ones that you used in the event that they differ from those recommended in SRP 3.8.5.3