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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML14183A6951995-09-18018 September 1995 Safety Evaluation Approving Relocation of Technical Support Ctr 1995-09-18
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers RA-97-0258, LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review1997-12-19019 December 1997 LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20217Q2751997-06-30030 June 1997 CP&L Fitness for Duty Program Performance Data for Period 970101-0630 ML14183A6951995-09-18018 September 1995 Safety Evaluation Approving Relocation of Technical Support Ctr ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20079H1571991-09-30030 September 1991 Nonproprietary Evaluation of Revised Transfer to Cold Leg Recirculation Procedure,Hb Robinson Unit 2 ML20086T2951991-06-14014 June 1991 Rev 1 to EQ Documentation Package Eqdp 36.0, Boston Insulated Wire Cable ML20086T2861991-03-0808 March 1991 Rev 1 to EQ Documentation Package Eqdp 11.1, Dekoron Instrumentation Cables ML20086T2561991-03-0808 March 1991 Rev 1 to EQ Documentation Package 10.0, Continental Shielded Instrument Cable ML20065K6961990-10-31031 October 1990 Mechanical Licensing Rept for Hb Robinson High Thermal Performance Fuel Assemblies ML20065K6971990-10-31031 October 1990 Thermal Hydraulic Compatibility Analysis of Anf High Thermal Performance Fuel for Hb Robinson,Unit 2 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20247E0701989-07-20020 July 1989 Info Rept:On 890717-0804,fire Penetration Seals Will Be Removed from Svc to Allow Access for Ventilation Sys Mod. Addl Fire Barrier Penetrations Will Be Made in Wall Between RHR Pump Pit & Fuel Handling Bldg,Per Tech Spec 3.14.7.2 ML20246E9111989-03-31031 March 1989 PDC-3:Advanced Nuclear Fuels Corp Power Distribution Control for PWRs & Application of PDC-3 to Hb Robinson Unit 2 ML20245H0821989-01-25025 January 1989 Criticality Safety Analysis of Hb Robinson Spent Fuel Pool W/4.2% Nominal Enrichment Fuel Assemblies ML20205T0551988-10-31031 October 1988 Responses to NRC Questions on RTD Bypass Elimination Licensing Rept ML20147E2371988-02-29029 February 1988 1987 Annual Rept - Primary Coolant Iodine Spikes ML20147B1971987-12-31031 December 1987 1987 Annual Rept - Primary Safety & Relief Valve Challenges ML20236K7731987-10-31031 October 1987 Monthly Operating Rept for Oct 1987 ML20235W3781987-09-30030 September 1987 Monthly Operating Rept for Sept 1987 ML20238E2741987-08-31031 August 1987 Monthly Operating Rept for Aug 1987 ML20235H3151987-06-30030 June 1987 Monthly Operating Rept for June 1987 ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20214W3241987-05-31031 May 1987 Monthly Operating Rept for May 1987 ML20214R5101987-04-30030 April 1987 Rev 1 to Monthly Operating Rept for Apr 1987,correcting Operation Statistics & Shutdown Experience Due to Mathematical Errors ML20215L4941987-04-30030 April 1987 Monthly Operating Rept for Apr 1987 ML20206F3561987-03-31031 March 1987 Monthly Operating Rept for Mar 1987 ML20210B4141987-03-31031 March 1987 Revised Monthly Operating Rept for Mar 1987 ML20205F6021987-03-23023 March 1987 Special Rept:On 870302,noble Gas Effluent Monitor for Main Steam Line B Declared Inoperable & Svc Not Returned Until 870312.Caused by Defective Detector.Detector Replaced.High Voltage for Detector Adjusted & Sys Operation Checked ML20212P3101987-02-28028 February 1987 Monthly Operating Rept for Feb 1987 ML20214Q7891987-01-31031 January 1987 Cycle 12,SAR ML20210R6341987-01-31031 January 1987 Monthly Operating Rept for Jan 1987 ML20207M2451986-12-31031 December 1986 Monthly Operating Rept for Dec 1986 L-18-120, Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi1986-12-18018 December 1986 Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi ML20215C7911986-11-30030 November 1986 Monthly Operating Rept for Nov 1986 ML20213F3121986-10-31031 October 1986 Monthly Operating Rept for Oct 1986 ML20215G1081986-09-30030 September 1986 Monthly Operating Rept for Sept 1986 ML20215F0361986-09-29029 September 1986 Special Rept:On 860902,during Cold Shutdown,Pressurizer PORV Lifted Twice to Prevent Overpressurization.Caused by Inadvertent Action by Unit Operators.Operations Personnel Counseled Re Importance of Breaker Position Indicators ML20211C0641986-09-0909 September 1986 Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson Spent Fuel Storage Racks (Unpoisoned,Low Density) W/4.2% Enriched 15x15 Fuel Assemblies ML20211C0491986-09-0202 September 1986 Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson New Fuel Storage Vault W/4.2% Enriched 15x15 Fuel Assemblies ML20212F5321986-07-31031 July 1986 Monthly Operating Rept for Jul 1986 ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 ML20202G3371986-06-30030 June 1986 Monthly Operating Rept for June 1986 ML20211B5601986-05-31031 May 1986 Monthly Operating Rept for May 1986 ML20197D2651986-04-30030 April 1986 Monthly Operating Rept for Apr 1986 1999-09-22
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENCLOSURE SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE LOCATION OF THE TECHNICAL SUPPORT CENTER CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261
1.0 INTRODUCTION
By letter dated February 24, 1995, as supplemented May 24, 1995, Carolina Power & Light Company (CP&L or the licensee) proposed to revise the H. B.
Robinson Steam Electric Plant, Unit No. 2 (HBR), Emergency Plan by relocating the Technical Support Center (TSC) outside the protected area. This revision will be an exception to the TSC location guidance in Supplement 1 to NUREG 0737, "Clarification of TMI Action Plan Requirements, Requirements for Emergency Response Capability." Specifically, the proposed revision would eliminate the current Emergency Plan commitment to incorporate the TSC, upon activation, into the protected area.
2.0 EVALUATION The HBR Emergency Plan currently indicates the TSC is to be incorporated within the site protected area, upon activation. Prior to activation of the TSC, the security force members must realign the protected area boundary to encompass that portion of the Training Building that currently houses the TSC facilities. The realignment normally involves a search of all areas of the TSC and compensatory measures added to enhance intrusion detection.
Currently, upon declaration of an emergency, the time needed to activate the TSC is approximately 50 to 60 minutes. With the proposed revision, the time required to activate the TSC is reduced to approximately 35 to 45 minutes.
With the TSC not in the protected area, the need to search and secure the TSC is not required, resulting in a 15-minute reduction in activation time.
The licensee has provided methods to ensure the availability of specific data and information from the control room, thus, limiting the need to send TSC personnel to the control room. Data is available from the Emergency Response Facility Information System/Electronic Display System (ERFIS/EDS) and the Safety Parameter Display System (SPDS), a subset of ERFIS. The Emergency Response Organization (ERO) communicator transmits selected ERFIS data points from the control room indicators to the TSC in the event of ERFIS failure.
Information may be transferred from the TSC by existing communication systems that include the site telephone system, radio system, and the site-wide Local Area Network computer system. A dedicated Hot Line telephone is provided from the Shift Supervisor's desk in the control room to the Plant Operations Director in the TSC. As a means to verify that the information available in the TSC provides accurate plant status, a camera that is remotely controlled from the EOF can be used by EOF and control room personnel to view data available to personnel and briefings held in the TSC.
9509210273 950918 PDR ADOCK 05000261 P PDR
-2 Under the 0prIop d revision, personnel in the TSC travelling to the control room must ingress to, and egress from, the protected area through the secured gate in the protected area boundary fence, which increases the transit time.
The increased transit time, 3.5 minutes, from the TSC to the control room exceeds the guidance in NUREG-0696, Section 2.2, that states, "The walking time from the TSC to the control room shall not exceed 2 minutes." However, the difference in the transit time, 1.5 minutes, is offset by the reduction in the time to activate the TSC, and the enhanced communications capabilities available between the TSC and the Control Room. Two additional routes have also been established and with estimated times of transit of 5.0 and 7.5 minutes.
Protective measures are currently established to limit the radiation dose received by personnel travelling between the TSC and the control room under severe accident conditions. Both the control room and the TSC are stocked with emergency kits that include anticontamination clothing, respirators, and dosimetry. This equipment, as well as consideration of the optimum travel route between the facilities, will serve to minimize radiation dose received by personnel travelling between the TSC and the control room under emergency conditions that involve releases of radioactive materials. Non-design verified dose estimates were performed for the longest and shortest access routes, 7.5 and 3.5 minutes, respectively. The estimated total effective dose equivalent incurred for transit along the longest route between the TSC to the control room is 8.0 mrem versus 3.0 mrem for the currently available route.
Although the estimated dose incurred for the new route is greater than the dose projected for the current route, neither dose is considered significant in this context.
3.0 CONCLUSION
The NRC staff has evaluated CP&L's proposed revision to the HBR Emergency Plan. Based on a review of the licensee's submittal and on the basis that the revision does not decrease the effectiveness of the Plan, the staff recommends that the licensee's proposed revision to eliminate the commitment to require incorporation of the TSC into the protected area be approved.
Principal Contributor: N. Stinson Date: September 18, 1995