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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-02-05
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARNRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 ML20255A1422020-09-11011 September 2020 NextEra Energy Point Beach LLC (NextEra) Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012; EA-20-081 NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2015-0026, Response to Inspection Report 05000266/2014403 and 05000301/20144032015-07-15015 July 2015 Response to Inspection Report 05000266/2014403 and 05000301/2014403 NRC 2013-0054, Response to Inspection Report 05000266/2013011 and 05000301/2013011 Preliminary Yellow Finding2013-06-28028 June 2013 Response to Inspection Report 05000266/2013011 and 05000301/2013011 Preliminary Yellow Finding NRC 2010-0064, Reply to a Notice of Violation, Inspection Report 05000266/2010-010; 05000301/2010-010, EA-09-2972010-05-0303 May 2010 Reply to a Notice of Violation, Inspection Report 05000266/2010-010; 05000301/2010-010, EA-09-297 L-2009-115, Response to Apparent Violations Inspection Report2009-05-0707 May 2009 Response to Apparent Violations Inspection Report NRC 2006-0080, Response to Apparent Violation in Inspection Report 05000266/2006011; 0500301/2006011; EA-06-2742006-12-19019 December 2006 Response to Apparent Violation in Inspection Report 05000266/2006011; 0500301/2006011; EA-06-274 NRC 2004-0002, Reply to a Notice of Violation EA-03-057 NRC Inspection Report2004-01-12012 January 2004 Reply to a Notice of Violation EA-03-057 NRC Inspection Report NRC 2003-0040, Reply to a Notice of Violation NRC Special Inspection Report No. 50-266/02-015 (Drs); 50-301/02-015 (DRS)2003-05-0202 May 2003 Reply to a Notice of Violation NRC Special Inspection Report No. 50-266/02-015 (Drs); 50-301/02-015 (DRS) NRC-2002-0068, Reply to NOV (EA-02-031), IR 05000266-01-017 (DRS) & IR 05000301-01-017 (Drs), 08/12/2002, Kewaunee & Point Beach Nuclear Power Plants2002-08-12012 August 2002 Reply to NOV (EA-02-031), IR 05000266-01-017 (DRS) & IR 05000301-01-017 (Drs), 08/12/2002, Kewaunee & Point Beach Nuclear Power Plants NRC 2002-0068, Reply to Notice of Violation (EA-02-031) to IRs 05000266-01-017 & 05000301-01-0172002-08-12012 August 2002 Reply to Notice of Violation (EA-02-031) to IRs 05000266-01-017 & 05000301-01-017 NRC 2002-0061, IR 05000266-02-003, IR 05000301-02-003, and IR 05000266-02-005, IR 05000301-02-005, Point Beach Nuclear Plant, Unit 2, Reply to a Notice of Violation2002-07-15015 July 2002 IR 05000266-02-003, IR 05000301-02-003, and IR 05000266-02-005, IR 05000301-02-005, Point Beach Nuclear Plant, Unit 2, Reply to a Notice of Violation NRC 2002-0007, Response to Non-Cited Violation Concerning Adequacy of Fire Suppression System, Per IRs 05000266/2001-012 (DRS) & 05000301/2001-012 (DRS)2002-01-14014 January 2002 Response to Non-Cited Violation Concerning Adequacy of Fire Suppression System, Per IRs 05000266/2001-012 (DRS) & 05000301/2001-012 (DRS) 2020-09-11
[Table view] |
See also: IR 05000266/2006011
Text
Point Beach Nuclear Plant Committed
to Nuclear Excellence
Operated by Nuclear Management
Company, LLC December 19,2006 NRC 2006-0080
10 CFR 2.201 U.S. Nuclear Regulatory
Commission
ATTN: Document Control Desk Washington, DC 20555-0001
Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 License Nos. DPR-24 and DPR-27 Response to an Apparent Violation
in Inspection
Report 05000266/2006011~
0500301 /2006011;
EA-06-274
Reference:
(1) Letter from NRC to NMC dated November 21, 2006 As a result of inspections
conducted
by the U. S. Nuclear Regulatory
Commission (NRC) between April 1, 2006, and October 27, 2006, an Apparent Violation
of NRC requirements
contained
in 10 CFR 50.71 (e) and a non-cited
violation
were documented
in Reference
(1). The Apparent Violation
states that the Point Beach Nuclear Plant (PBNP) Final Safety Analysis Report (FSAR) was not updated in 1983 with the results of a reactor vessel head (RVH) drop analysis conducted
in 1982. It further states that in response to NRC questions
in 2005, Nuclear Management
Company LLC (NMC) made the determination
that amendments
to the PBNP Operating
Licenses were necessary
prior to updating the FSAR with this analysis, and furthermore, that administrative
controls for the movement of the PBNP RVHs were needed. These amendments
and administrative
controls were not in place for RVH moves from 1983 through 2004. Pursuant to the provisions
of 10 CFR 2.201, Nuclear Management
Company, LLC is responding
to the Apparent Violation
in the enclosure
to this letter. NMC concurs that the Apparent Violation
has been properly characterized
as a violation
of the requirements
of 10 CFR 50.71 (e). 6610 Nu~lear Road Two Rivers, Wisconsin
54241-9516
Telephone:
920.755.2321
Document Control Desk Page 2 Summary of Regulatory
Commitments
This letter contains no new commitments
and no revisions
to existing commitments:
Dennis L. Koehl / Site Vice-President, Point Beach Nuclear Plant Nuclear Management
Company, LLC Enclosure
cc: Administrator, Region Ill, USNRC Enforcement
Officer, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC
ENCLOSURE
Response to an Apparent Violation
in lnspection
Report 050002661200601
1 ; 0500301/2006011;
EA-06-274
Pursuant to the provisions
of 10 CFR 2.201, the following
is the NMC response to an Apparent Violation (EA-06-274)
of NRC requirements
as documented
in NRC lnspection
Report 05000266/2006011;
0500301/200601
dated November 21,2006. APPARENT VIOLATION
Contrary to the requirements
of 10 CFR 50.71 (e), the Point Beach Nuclear Plant (PBNP) Final Safety Analysis Report (FSAR)
was not updated in 1983 with the results of a reactor vessel head (RVH) drop analysis conducted
in 1982. Evaluation
of this analysis by Nuclear Management
Company, LLC (NMC) in 2005, in response to questions
from the NRC, resulted in NMC's determination
that amendments
to the PBNP Operating
Licenses were necessary
prior to updating the FSAR with this analysis.
This evaluation
also concluded
that the establishment
of administrative
controls on the movement of the PBNP reactor vessel heads (RVHs) was required.
The amendments
and administrative
controls were not in place for RVH moves from 1983 through 2004. NMC RESPONSE NMC concurs that the failure to update the FSAR in accordance
with the requirements
of 10 CFR 50.71 (e) was a violation
of NRC requirements.
Reasons for Violation:
There have been several evaluations
performed
to determine
the reasons for this Apparent Violation.
A description
of each of these evaluations
and its conclusions
is provided below. 1. Root Cause Evaluation (RCE) 277, Reactor Vessel Head Drop Analysis RCE 277, Reactor Vessel Head Drop Analysis, was performed
to identify the historical
and present-day
issues relating to the absence of a design basis or licensing
basis analysis of record for a reactor vessel head (RVH) drop accident.
Page 1 of 5
2. RCE 300, Personnel
Awareness
and Understandina
of Licensina
Bases RCE 300, Personnel
Awareness
& Understanding
of Licensing
Bases, was chartered
in early December 2005, as a result of a streaming
analysis pelformed
by the PBNP senior management
team in late November 2005. RCE 300, Revision 1, was issued on April 27, 2006. The purpose of this RCE was to determine
the root and contributing
causes for the limited awareness
and inadequate
understanding
of regulatory
commitments
and requirements, including
legacy issues, such that docketed correspondence
has not always been incorporated
into licensing
basis documents, such as the FSAR. Additionally, the RCE evaluated
why regulatory
commitments
contained
in the correspondence
have not always been adequately
translated
into license basis implementing
documents
such as procedures.
3. PBSA-ENG-05-04, 10 CFR 50.59 Focused Self-Assessment
and Common Factors Assessment
A focused self-assessment
of implementation
of the 10 CFR 50.59 process at PBNP was conducted
on October 10-28,2005.
The purpose of the self-assessment
was to prepare for the baseline inspection
in December 2005, as well as to evaluate the effectiveness
of training conducted
in August 2005. One result of the self-assessment
was completion
of a common factors analysis (CFA) in order to determine
why some previous corrective
actions had not been effective.
The Common Factors Assessment (CFA) was conducted
during February 2006. 4. Common Cause Evaluation (CCE) of Component
Desiqn Basis Inspection (CDBI) Corrective
Action Documents
The purpose of this CCE was to obtain additional
insights into PBNP design and licensing
basis issues. The CCE confirmed
the conclusions
of RCE 300 with respect to its finding that design and licensing
basis information
is fragmented
and that additional
attention
should be placed on the preparation, review and approval of procedures
that implement
design requirements
to ensure these requirements
are appropriately
mapped. The reasons for the Apparent Violation
are: Activities
associated
with the design and licensing
basis were not elevated to a level of importance
such that the processes
and procedures
produce predictable
successful
outcomes.
The NMC RVH replacement
team failed to provide requested
information
on the RVH analysis to the vendor. Personnel
did not understand
the hierarchy
of the plant's licensing
and design bases within the regulatory
framework
of Title 10, Code of Federal Regulations.
Page 2 of 5
The processes
intended to implement
the regulations
were fragmented
and insufficient
to ensure that design and license basis requirements
were properly mapped into their respective
implementing
documents.
In the case of the reactor vessel head replacement
project, there were no internal processes
and procedures
to effectively
govern conduct of the project. Clear ownership, roles and responsibilities
associated
with license basis maintenance
and control were not clearly defined. Corrective
Steps Taken and Results Achieved:
Corrective
steps were taken to address issues specific to the RVH drop analysis and the non-cited
violation
of 10 CFR 50.59. These corrective
steps are summarized
as follows: 1. On April 16, 2005, commitments
were made by NMC to NRC that provided compensatory
measures to enable movement of the original RVH. These commitments
were formalized
via letter NRC 2005-0050A
dated April 20, 2005, and subsequently
implemented.
2. On April 29, 2005, an application
for a proposed amendment
was submitted
to the Commission
via letter NRC 2005-055.
This application
was supplemented
by letters dated May 13, May 19, June 1, June4, June 9, June 20, and June 23,2005. 3. On June 24, 2005, NMC issued TRM 3.9.4, Reactor Vessel Head Lift, which provides required administrative
controls during lifting of a RVH over a reactor containing
fuel assemblies.
At the time of issue, TRM 3.9.4 was applicable
only to Unit 2. 4. On July 24, 2005, NMC requested
a similar amendment
for Unit 1 via letter NRC 2005-0094.
5. On August 15, 2005, the Unit 2 RVH drop analysis was incorporated
into the FSAR and submitted
to the NRC via the periodic FSAR update as required by 10 CFR 50.71 (e). 6. On September
23, 2005, TRM 3.9.4 was revised to reflect provisions
of the NRC Safety Evaluation
which delineated
administrative
controls during lifting of a RVH over a reactor containing
fuel assemblies.
This revision of TRM 3.9.4, therefore, applied to both PBNP units. 7. On August 15,2006, the PBNP FSAR was revised and submitted
to the NRC during the periodic update of the FSAR as required by 10 CFR 50.71 (e) to reflect applicability
for both units. Page 3 of 5
8. Affected plant implementing
documents
such as Safe Load Path guidance for movement of heavy loads, RVH routine maintenance
procedures
used during each refueling
outage, Operations
containment
closure checklists
and refueling-related
procedures, etc., have been revised. 9. The NMC Project Management
Manual has been implemented
at PBNP. 10. A current licensing
basis (CLB) policy was developed
and issued on June 20, 2006. The policy defines and describes
the CLB; establishes
ownership
of CLB documents;
defines personnel
roles and responsibilities
for implementing
and maintaining
the CLB; establishes
expectations
for use and adherence
to the CLB; and describes
available
tools and methods for searching
the CLB. 11. A training needs assessment
for the CLB policy was completed
and concluded
that informational
sharing and/or formal training sessions were required for appropriate
station personnel.
Lesson plans have been developed
and approved.
Engineering, Regulatory
Affairs and 10 CFR 50.59 screening
and evaluation-qualified
personnel
received training during August 2006. 12. Corrective
actions identified
in the December 2005 10 CFR 50.59 self-assessment
were incorporated
into the Engineering
Continuing
Training Program. The revised training was provided to engineering
in August 2006. 13. A continuing
training module was developed
and conducted
with engineering
personnel
to develop a common understanding
of the definition
and vision of technical
rigor and to provide personnel
with an awareness
of the available
human performance
tools to improve technical
rigor. Training was completed
in December 2006. 14. The licensee response to the October 9, 1996, NRC "Request for lnformation
Pursuant to 10 CFR 50.54(f) Regarding
Adequacy and Availability
of Design Basis Information," was reviewed.
A validation
package was compiled supporting
the licensee response dated February 6, 1997. Following
this effort, a "living validation
package" was compiled which reflected
the 2006 status of statements
of fact contained
in the response.
15. A procedures
writerlreviewer
certification
matrix, along with a Job Familiarization
Guide (JFG), was developed
and is being implemented.
In addition, as part of this certification
process, information
sharing sessions are being conducted
to provide personnel
involved in procedure
writing and reviewing
with "hands-on" practical
experience
in searching
the site's Regulatory
lnformation
System, which includes the Regulatory
Commitment
Database.
16. Ownership
of the FSAR was transferred
from Engineering
to Regulatory
Affairs on December 15,2006. Page 4 of 5
Corrective
Steps To Be Taken: There are no additional
corrective
actions required to address this violation.
Date Full Compliance
Will Be Achieved:
Full compliance
with NRC requirements
was achieved on August 15, 2006, for both units when the vessel head drop analysis for Unit 1 was incorporated
into the FSAR. Page 5 of 5