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Category:Inspection Report
MONTHYEARIR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 IR 05000333/20230062024-02-28028 February 2024 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023006) IR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 IR 05000333/20220062023-03-0101 March 2023 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2022006) IR 05000333/20220032022-11-10010 November 2022 Integrated Inspection Report 05000333/2022003 IR 05000333/20220052022-08-31031 August 2022 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2022005) IR 05000333/20220022022-08-10010 August 2022 Integrated Inspection Report 05000333/2022002 IR 05000333/20220102022-06-27027 June 2022 Reissued Design Basis Assurance Inspection (Teams) Inspection Report 05000333/2022010 ML22153A2612022-06-0202 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000333/2022010 IR 05000333/20210142022-05-23023 May 2022 Problem Identification and Resolution Inspection Report 05000333/2021014 IR 05000333/20220012022-05-0505 May 2022 Integrated Inspection Report 05000333/2022001 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2022001 IR 05000333/20210062022-03-0202 March 2022 Annual Assessment Letter for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2021006) IR 05000333/20210042022-01-27027 January 2022 Integrated Inspection Report 05000333/2021004 IR 05000333/20210032021-11-0808 November 2021 Integrated Inspection Report 05000333/2021003 IR 05000333/20210402021-11-0808 November 2021 95001 Supplemental Inspection Report 05000333/2021040 and Assessment Follow-Up Letter IR 05000333/20213012021-10-0505 October 2021 Initial Operator Licensing Examination Report 05000333/2021301 IR 05000333/20215012021-09-29029 September 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2021501 IR 05000333/20210052021-09-0101 September 2021 Updated Inspection Plan for the James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2021005) IR 05000333/20210132021-08-11011 August 2021 Biennial Problem Identification and Resolution Inspection Report 05000333/2021013 IR 05000333/20210022021-08-0303 August 2021 James A. Fitpatrick Nuclear Power Plant - Integrated Inspection Report 05000333/2021002 ML21176A0052021-06-25025 June 2021 Acknowledgement of Dispute of Violations Associated with White Finding - NRC Inspection Report 05000333/2021090 IR 05000333/20214022021-06-0909 June 2021 Security Baseline Inspection Report 05000333/2021402 IR 05000333/20210112021-06-0303 June 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000333/2021011 IR 05000333/20210012021-05-0505 May 2021 Integrated Inspection Report 05000333/2021001 IR 05000333/20210122021-05-0404 May 2021 Temporary Instruction 2515/194 Inspection Report 05000333/2021012 IR 05000333/20210902021-04-20020 April 2021 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation: NRC Inspection Report 05000333/2021090 IR 05000333/20214012021-04-19019 April 2021 Material Control and Accounting Program Inspection Report 05000333/2021401 (Letter Only) IR 05000333/20210102021-04-0707 April 2021 Triennial Fire Protection Inspection Report 05000333/2021010 IR 05000333/20200062021-03-0303 March 2021 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2020006) IR 05000333/20200042021-02-11011 February 2021 Integrated Inspection Report 05000333/2020004 IR 05000333/20200122021-01-21021 January 2021 Problem Identification and Resolution Report 05000333/2020012 and Preliminary White Finding and Apparent Violation 2024-09-19
[Table view] Category:Letter
MONTHYEARML24270A0742024-09-30030 September 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0134) - LTR ML24270A1452024-09-26026 September 2024 Notice of Enforcement Discretion for James A. Fitzpatrick Nuclear Power Plant JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 ML24106A0152024-04-15015 April 2024 Request for Withholding Information from Public Disclosure Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24107A6972024-04-12012 April 2024 Engine Systems, Inc Part 21 Report Re EMD Cylinder Liner Water Leak RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24068A0532024-03-28028 March 2024 Issuance of Amendment No. 354 Revise Technical Specifications Section 3.3.1.2, Source Range Monitors Instrumentation JAFP-24-0014, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-03-25025 March 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0010, Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2024-02-29029 February 2024 Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-24-0009, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-02-28028 February 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230062024-02-28028 February 2024 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023006) IR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines 2024-09-04
[Table view] |
Text
August31,2010
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - NRC SECURITY INSPECTION REPORT 05000333/2010402 (U)
Dear Mr. Dietrich:
On July 23, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your James A. FitzPatrick Nuclear Power Plant. The inspection covered one or more of the key attributes of the security cornerstone of the NRC's Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on July 23, 2010, with Mr. Brian Sullivan, Plant Manager and other members of your staff.
The inspection examined activities conducted under your licenses as they relate to security and complicJlnce with the Commission's rules and regulations and with the conditions of your licenses. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
This report documents three findings of very low security significance (i.e., Green as determined by the Baseline Security Significance Determination Process). Two of these findings were determined to involve a violation of NRC requirements. The deficiencies were promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspectors left the site. The findings had cross-cutting aspects in the area of human performance because conservative assumptions in decision making were not demonstrated H.1(b), incomplete procedures were provided H.2(c), and human error prevention techniques were not utilized
[H.4 (a}l).
Warning: Violation of section 147 ofthe Atomic Energy Act, "Safeguards Information" is subject to DETERMINATION MADE BY:
NAMEmTLE: _James M. Trapp, Chief,_ __
I Civil and criminal penalties. ORGANIZATION; R1/DRS/PSB1 BASIS: DG*SG*1 (300) Physical Protection Program SIGNATURE: _/RAJ DATE: 8131110 SAFEGUARDS INFORMJ'.TJON
SAFEGUARDSINFORMA~ON However, because of the very low security significance and because they are entered into your corrective action program, the NRC is treating these violations as a nonwcited violation (NCV)
consistEmt with Section VI.A.1 of the NRC Enforcement Policy.
If you contest these non-cited violations, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the FitzPatrick Nuclear Power Plant. In addition, if you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region I, and the NRC Resident Inspector at FitzPatrick Nuclear Power Station.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system, ADAMS. ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html(the Public Electronic Reading Room). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's enclosure will not be available for public inspection.
In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system, ADAMS. If Safeguards Information is necessary to provide an acceptable respoml.e, please provide the level of protection described in 10 CFR 73.22. Otherwise, mark your entire response "Security-Related Information - Withhold Under 10 CFR 2.390" and follow the instructions for withholding in 10 CFR 2.390(b)(1).
Sincerely, IRA!
James M. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety Docket No. 50-333 License No. DPR-59 Non-pUblic Enclosure:NRC Inspection Report No. 05000333/2010402 w/Attachment: Supplemental Information (CONTAINS (SGI>>
SAFEGUARDS INFORMA~ON However, because of the very low security significance and because they are entered into your corrective action program, the NRC is treating these violations as a non-cited violation (NCV)
consistent with Section VI.A.1 of the NRC Enforcement Policy.
If you contest these non-cited violations, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATIN.: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the FitzPatrick Nuclear Power Plant. In addition, if you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region I, and the NRC Resident Inspector at FitzPatrick Nuclear Power Station.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system, ADAMS. ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html(the Public Electronic Reading Room). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's enclosure will not be available for public inspection.
In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system, ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.22. Otherwise, mark your entire response "Security-Related Information - Withhold Under 10 CFR 2.390" and follow the instructions for withholding in 10 CFR 2.390(b)(1).
Sincerely, IRA!
James M. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety Docket No. 50-333 License No. DPR-59 Non-puhlic Enclosure:NRC Inspection Report No. 05000333/2010402 w/Attachment: Supplemental Information (CONTAINS (SGI>>
SUNSI Review Complete: JMT (Reviewer's Initials)
Non-Public DeSignation Category: MD 3.4 Non-Public A.3
. ADAMS ACCeSSION NO. ML102430188 DOCUMENT NAME A:\SGI 2010 Fitz BI Rev 7 2010402.doc After declaring this document "An Official Agency Record" it will be released to the Public (Letter Only).
To receive a copy of this document, indicate in the box: "e" = Copy without attachment/enclosure "e" = Copy with attachment/enclosure "N" = No copy OFFICE RI/DRS r RIIDRS I RIIDRS I RlIDRP I RIIDRS I NAME GSmith/JMT for DJohnsonlDCJ DCaron/DCC MGray/BB for JTrapp/JMT DATE 08/31/10 08/31/10 08/31110 08/30/10 08131110 OFFICIAL RECORD COpy SAfliGUARDS INfORMATION cc w/encl; w/OUO-SRI J. LaPlante, Site Security Manager. FitzPatrick Station R. Frazier, Assistant Director, New York State Department of Homeland Security F. Murray. President & CEO New York State Energy Research and Development Authority cc w/o erlcl; w/o OUO-SRI: Distribution via ListServ S...."fIiGUARDS INfORMATION
SAFEGUARDS INFORM.o.TION Distribution w/o encl; w/o OUO-SRI: (via e-mail)
M. Dapas, DRA (R10RAMaii Resource)
D. Lew, DRP (R10RAMaii Resource)
J. Clifford, DRP (R1DRPMaii Resource)
D. Collins, DRP (R1DRPMaii Resource)
D. Roberts, DRS (R1DRSMail Resource)
P. Wilson. DRS (R1DRSMail Resource)
L. Troeline, RI OEDO M. Gray, DRP B. Bick.~tt, DRP S. McCarver, DRP E. Knutson. DRP. SRI S. Rutenkroger. DRP, RI K. Kolek, Resident OA D. Bearde, DRS RidsNrrPMFitzPatrick Resource RidsNrrDorlLpl1-1 Resource ROPreports Resource@nrc.gov Distribution w/encl w/OUO:
D. Caron, DRS J. Trapp, DRS R. Albert, NSIR S. Coker, NSIR