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Category:NRC Generic Letter
MONTHYEARNRC Generic Letter 1999-021999-08-23023 August 1999 NRC Generic Letter 1999-002: (Errata): Laboratory Testing of Nuclear-Grade Activated Charcoal NRC Generic Letter 1983-111999-06-24024 June 1999 NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis ML0823509351999-06-0303 June 1999 Generic Ltr 99-02 to All Holders of OLs for Nuclear Power Reactors,Except Those Who Have Permanenetly Ceased Operations & Certified That Fuel Permanently Removed from Rv Re Laboratory Testing of nuclear-grade Activated Charcoal ML0311101371999-06-0303 June 1999 Withdrawn NRC Administrative Letter 1999-002: Operating Reactor Licensing Action Estimates NRC Generic Letter 1999-011999-05-0303 May 1999 NRC Generic Letter 1999-001: Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities NRC Generic Letter 1998-011999-01-14014 January 1999 NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants ML0311101601998-08-0303 August 1998 Withdrawn NRC Administrative Letter 1998-005: Availability of Summaries in Electronic Format of Technical Reports by Office for Analysis & Evaluation of Operational Data NRC Generic Letter 1998-041998-07-14014 July 1998 NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i NRC Generic Letter 1998-021998-05-28028 May 1998 NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition NRC Generic Letter 1997-061997-12-30030 December 1997 NRC Generic Letter 1997-006: Degradation of Steam Generator Internals NRC Generic Letter 1997-051997-12-17017 December 1997 NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques NRC Generic Letter 1996-061997-11-13013 November 1997 NRC Generic Letter 1996-006, Supplement 1: Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions ML0312007011997-10-0808 October 1997 Withdrawn NRC Generic Letter 1991-018, Revision 1: Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions NRC Generic Letter 1997-041997-09-30030 September 1997 NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules NRC Generic Letter 1997-031997-07-0909 July 1997 NRC Generic Letter 1997-003: Annual Financial Surety Update Requirements for Uranium Recovery Licensees NRC Generic Letter 1997-021997-05-15015 May 1997 NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report NRC Generic Letter 1995-061997-01-31031 January 1997 NRC Generic Letter 1995-006: Changes in Operator Licensing Program NRC Generic Letter 1996-081996-12-15015 December 1996 NRC Generic Letter 1996-008: Interim Guidance on Transportation of Steam Generators NRC Generic Letter 1996-051996-09-18018 September 1996 NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves NRC Generic Letter 1996-041996-06-26026 June 1996 NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks NRC Generic Letter 1995-091996-04-0505 April 1996 NRC Generic Letter 1995-009: Supplement 1: Monitoring and Training of Shippers and Carriers of Radioactive Materials NRC Generic Letter 1996-021996-02-13013 February 1996 NRC Generic Letter 1996-002: Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat NRC Generic Letter 1996-031996-01-31031 January 1996 NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits NRC Generic Letter 1989-101996-01-24024 January 1996 NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors NRC Generic Letter 1996-011996-01-10010 January 1996 NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits NRC Generic Letter 1995-101995-12-15015 December 1995 NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation ML0310701501995-10-31031 October 1995 Withdrawn - NRC Generic Letter 1995-008: 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval NRC Generic Letter 1993-031995-10-20020 October 1995 NRC Generic Letter 1993-003: Verification of Plant Records NRC Generic Letter 1995-071995-08-17017 August 1995 NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves NRC Generic Letter 1995-031995-04-28028 April 1995 NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes NRC Generic Letter 1995-041995-04-28028 April 1995 NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues NRC Generic Letter 1995-021995-04-26026 April 1995 NRC Generic Letter 1995-002: Use of Numarc/Epri Report TR-102348, Guideline on Licensing Digital Upgrades, in Determining the Acceptability of Performing Analog-To-Digital Replacements Under 10CFR 50.59 NRC Generic Letter 1995-011995-01-26026 January 1995 NRC Generic Letter 1995-001: NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities ML0312004431994-09-0202 September 1994 Withdrawn - NRC Generic Letter 1994-004: Voluntary Reporting of Additional Occupational Radiation Exposure Data NRC Generic Letter 1994-031994-07-25025 July 1994 NRC Generic Letter 1994-003: Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors NRC Generic Letter 1994-021994-07-11011 July 1994 NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors NRC Generic Letter 1994-011994-05-31031 May 1994 NRC Generic Letter 1994-001: Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators NRC Generic Letter 1993-081993-12-29029 December 1993 NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits NRC Generic Letter 1993-071993-12-28028 December 1993 NRC Generic Letter 1993-007: Modification of Technical Specification Administrative Control Requirements for Emergency & Security Plans NRC Generic Letter 1993-061993-10-25025 October 1993 NRC Generic Letter 1993-006: Research Results on Generic Safety Issue 106, Piping and the Use of Highly Combustible Gases in Vital Areas. NRC Generic Letter 1993-051993-09-27027 September 1993 NRC Generic Letter 1993-005: Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation NRC Generic Letter 1993-041993-06-21021 June 1993 NRC Generic Letter 1993-004: Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) NRC Generic Letter 1993-021993-03-23023 March 1993 NRC Generic Letter 1993-002: Public Workshop on Commercial Grade Procurement and Dedication NRC Generic Letter 1993-011993-03-0303 March 1993 NRC Generic Letter 1993-001: Emergency Response Data System Test Program NRC Generic Letter 1992-091992-12-31031 December 1992 NRC Generic Letter 1992-009: Limited Participation by NRC in IAEA International Nuclear Event Scale NRC Generic Letter 1992-081992-12-17017 December 1992 NRC Generic Letter 1992-008: Thermo-Lag 330-1 Fire Barriers NRC Generic Letter 1992-071992-10-20020 October 1992 NRC Generic Letter 1992-007 - Office of Nuclear Reactor Regulation Reorganization NRC Generic Letter 1983-281992-10-0707 October 1992 NRC Generic Letter 1983-028, Supplement 1: Required Actions Based on Generic Implications of Salem ATWS Events. ML0311304121992-09-16016 September 1992 Withdrawn NRC Generic Letter 1992-006 - Operator Licensing National Examination Schedule NRC Generic Letter 1992-051992-09-0404 September 1992 NRC Generic Letter 1992-005: NRC Workshop on the Systematic Assessment of Licensee Performance (SALP) Program 1999-08-23
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'EG(, UNITED STATES
,
REGULATORY COMMISSION NRC PDR
e -,
fNUCLEAR
D. C. 20555 Local PDR
~-,' * -WASHINGTON, 1 File A u : unJLWR
11, 1978 D. Vassallo August J. Stolz rcckt N. 50416C. E. Thomas Hylton accket No. 50-416 and 5-417OELD
B. Scott L. Dreher - G-26 Mississippi Power and Light Company ATTN: Mr. N. L. Stampley 7/ Lo 7 E -j Vice President - Production P. 0. Box 1640
Jackson, Mississippi 39205 Gentlemen:
SUPPLIES
SUBJECT: REACTOR PROTECTION SYSTEM POWER
UNITS 1 & 2)
(GRAND GULF NUCLEAR STATION,
A to General Design Criteria (Appendix such Criterion 2 of the Commission's that systems important to safety,
10 CFR Part 50) requires in part be designed to withstand the effectsIE
as the reactor protection system, systems are required to be Class of earthquakes. Reactor protection protection Category I. The normal reactor systems, hence they are seismic water General Electric Company boiling solid system power supplies for most except for those utilizing reactor nuclear steam supply systems, consist of redundant alternating current state reactor protection systems, seismically qualified.
not motor-generator sets which are license of Georgia Power Company's operating During the course of our review No. 2 (Docket No.
Nuclear Plant Unit application for its Edwin I. Hatch of the protection afforded the reactor
50-366), we questioned the adequacy sustained over-voltage, under-voltage, protection system against possible the reactor protection system power or underfrequency conditions from the capability of the reactor pro- supplies. Specifically, we questioned accommodate the effects of earthquakes tection system power supplies to of the reactor protection system to without jeopardizing the capability function.
to perform its intended safety can be of events initiated by an earthquake We determined that a sequence system damage to the reactor protection postulated which could result in loss of capability to scram the components with the attendant potential (1) the occurrence of an earthquake includes plant. This sequence of events the failure the undetected failure of a voltage sensor, (2) (3) the that would cause in an abnormal output voltage, of a motor-generator set resulting voltage, undetected by visual observa- persistence of this abnormal output a time sufficient to damage reactor for t1ons and surveillance testing, in such
(4) failure of these components protection system components, and of-capability to scram the plant.
a onanner that results in the loss
.
- 2 - August 11, 1978 the first scheduled We, therefore, required that prior to startup following systems approved IE
refueling outage, Georgia Power Company install Class system power by us and capable of de-energizing the reactor protection or their output supplies when their output voltages exceed or fall below being powered frequencies fall below limits within which the equipment to operate con- by the power supplies has been designed and qualified the designs of the tinuously and without degradation. With such systems, to the applicable reactor protection system power supplies will conformPart 50.
requirements of Criterion 2 of Appendix A to 10 CFR
that all applicants Consistent with our finding on Hatch Unit 2, we requireGeneral Electric for licenses to construct and operate plants utilizing with non-seismic Company boiling water reactor nuclear steam supply systems as the normal reactor Category I alternating current motor-generator sets Class IE systems approved by us protection system power supplies install power supplies anu capaDle of de-energizing the reactor protection system their output frequencies when their output voltages exceed or fall below or powered by the power fall below limits within which the equipment being continuously and without supplies has been designed and qualified to operate degradation.
We will implement this requirement as follows:
permit stage
(1) For those applicants with applications in the construction your receipt days of of the review process, we request that within 30 commitment your of this letter, you amend your application to reflect loading and (b)
to (a) install such systems prior to initial fuel your Final Safety Analysis provide the details of the system design in Report.
permit stage, we request
(2) For those applicants in the post-construction of this letter, you document by that within 30 days of your receipt to initial install such systems prior letter your commitment to (a) in your the details of the system design fuel loading and (b) provide Final Safety Analysis Report.
license stage
(3) For those applicants with applications in the operating your receipt of of the review process, we request that within 30 days your commitment of this letter, you amend your application to reflect loading and (b)
to (a) install such systems prior to initial fuel of the system advise us of your schedule for providing the details design in your Final Safety Analysis Report.
-3 - August 11, 1978 Because of the relatively large number of plants involved and the similarity of the reactor protection system power supply designs, we anticipate that you, the other affected applicants, and the General Electric Company may wish to combine efforts in this matter. In the interest of standardization and minimizing the impact of our review of these systems, we encourage such a combined effort.
Sincerely,
_~ /_.-\ -) ,.-,-,
Roger S. Bbyd, Director Division of Project Mana'§Wement-'
Office of Nuclear Reactor Regulation
. '4'
Mississippi Power and Light Company cc: Mr. Robert B. McGehee, Attorney Wise, Carter, Child, Steen &
Caraway P. 0. Box 651 Jackson, Mississippi 39205 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber
1747 Pennsylvania Avenue, N. W.
Washington, D. C. 20006 Bechtel Power Corporation ATTN: T. W. Haberman, Project Engineer Grand Gulf Nuclear Station Gaithersburg, Maryland 20760
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