NRC Generic Letter 1993-001: Emergency Response Data System Test ProgramML031070216 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River |
---|
Issue date: |
03/03/1993 |
---|
From: |
Partlow J Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
GL-93-001, NUDOCS 9302240242 |
Download: ML031070216 (7) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River |
---|
Category:NRC Generic Letter
MONTHYEARML23200A1832023-08-0303 August 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML17067A2782017-04-18018 April 2017 Non-Power Reactor Closeout of Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools for the Armed Forces Radiobiology Research Institute, Docket No. 50-170 (CAC No. A11010) ML17067A4042017-04-17017 April 2017 Washington State University GL 2016-01 Closeout Form Letter for Rtrs with No Credited NAM NRC Generic Letter 2007-012007-02-0707 February 2007 NRC Generic Letter 2007-01: Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients NRC Generic Letter 2006-012006-01-20020 January 2006 NRC Generic Letter 2006-01: Steam Generator Tube Integrity and Associated Technical Specifications NRC 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 1998-031998-06-22022 June 1998 NRC Generic Letter 1998-003; NMSS Licensees and Certificate Holders Year 2000 Readiness Programs 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 2023-08-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Washington Public Power Supply System]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Clinch River]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Washington Public Power Supply System]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Clinch River]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555 March 3, 1993 TO: ALL HOLDERS OF OPERATING LICENSES OR CONSTRUCTION PERMITS FOR
NUCLEAR POWER REACTORS, EXCEPT FOR BIG ROCK POINT AND FACILITIES
PERMANENTLY OR INDEFINITELY SHUT DOWN
SUBJECT: EMERGENCY RESPONSE DATA SYSTEM TEST PROGRAM
(GENERIC LETTER 93-01)
PURPOSE
to The U.S. Nuclear Regulatory Commission (NRC) is issuing this generic letter presently recommend a schedule to addressees for efficiently accomplishing the required quarterly testing of the Emergency Response Data System (ERDS), using available telephone lines. The NRC is also issuing this generic letter to of recommend an acceptable testing program to addressees, based on experience both the industry and the NRC in setting up ERDS.
BACKGROUND
On August 21, 1989, the NRC issued Generic Letter 89-15, 'Emergency Response Data System," to inform licensees and applicants about the voluntary efforts that certain licensees were taking to implement the ERDS and to solicit the participation of all applicable licensees and applicants in the ERDS program.
ERDS is a direct near real-time electronic data link between computer data systems used by licensees of operating reactors and the NRC Operations Center upon declaring an emergency classified as an alert or higher. Subsequently, on October 9, 1990, the NRC published a proposed rule in the Federal Reaister
(55 FR 41095) that would require licensees and applicants to participate in the ERDS program and to establish a schedule for its implementation.
On August 13, 1991, after considering public comments on the proposed rule, the NRC published the final rule in the Federal- Register (56 FR 40178). This final rule amended Part 50 of Title 10 of the Code of Federal Regulations
(10 CFR Part 50) to require licensees to provide hardware and software with specific characteristics to interface with the NRC receiving system
(10 CFR Part 50, Appendix E, Section VI, Paragraph 2). The amended Part 50
also requires licensees to test, maintain, and implement the ERDS
(10 CFR Part 50, Appendix E, Section VI, Paragraphs 1, 3, and 4, respectively). Finally, the amended Part 50 requires licensees to activate the ERDS in the event of an emergency, classified as an alert or higher
(10 CFR 50.72(a)(4)).
The program that has been followed by industry for the past several years in setting up the ERDS system is documented in 'Emergency Response Data System (ERDS) Implementation," NUREG-1394, Revision 1, June 1991. This document NRCis referenced in a footnote of 10 CFR Part 50, Appendix E,Section VI. The staff recommendations in this generic letter are based on this experience.
REURN TO PSEUlAT AY Crt~A ElliS
Generic Letter 93-01 - 2- March 3, 1993 REQUESTED ACTIONS
This generic letter is addressed to all facilities for which the final rule applies. This includes all licensed nuclear power reactor facilities, except Big Rock Point (which is exempt because its computer system does not have a sufficient number of parameters available for effective participation in the ERDS program) and those that are permanently or indefinitely shut down
(10 CFR Part 50, Appendix E, Section VI, Paragraph 2).
Because the NRC can connect up to three plants simultaneously for testing EROS, the NRC staff has developed a schedule (Enclosure 1) to test the system efficiently. The NRC recommends, but does not require, that each addressee follow this schedule. Each addressee should arrange EROS testing with the NRC
Operations Center at (301) 492-4102. An NRC test monitor person will be available between 8:00 a.m. and 4:00 p.m. eastern time on days scheduled for testing. The schedule is arranged by weeks of a calendar quarter, with the first week of a quarter taken to be the first entire work week (Monday to Friday) of the quarter. Scheduled test days that fall on Federal holidays will be rescheduled to Monday or Friday of the same week. Retesting may be scheduled and implemented on appropriate Mondays and Fridays per mutual agreement of the NRC and the licensee.
Based on experience of both the industry and the NRC, the NRC staff has developed a testing program that would demonstrate acceptable operation of EROS. The NRC recommends, but does not require, that each addressee use this testing program. The program consists of demonstrating the ability to
(1)establish a link with EROS, (2)transmit all parameters in the plant EROS
database for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> while meeting the requirements of the final rule, (3)
reconnect with EROS upon a loss of telephone connection, and (4)terminate the EROS link.
If an addressee chooses to test the EROS in a different manner, the addressee should document and retain in appropriate plant records a justification that the alternative program satisfies the final rule.
The EROS testing program will begin on April 1, 1993.
REPORTING REOUIREMENTS
The NRC will record the results of each test in the NRC Operations Center.
Following each test, the NRC will review the transmitted data and inform the licensee of any testing anomalies noted. The NRC does not expect applicable licensees and applicants to submit any report after a test. In the event that the NRC cannot perform the scheduled EROS test within the quarter, NRC will
K> K
Generic Letter 93-01 - 3- March 3, 1993 communicate and document this to the affected licensee(s). No written reply is required in response to this generic letter.
BACKFIT DISCUSSION
The final rule requires each licensee and applicant to test the ERDS each quarter. In this generic letter, the staff recommends but does not require (or seek to impose) an ERDS testing schedule and procedure to implement the testing required by the rule. Because the staff recommendations are voluntary in nature, this action is not considered to be a backfit under NRC procedures.
The recommended test schedule is designed to efficiently use limited facilities at the NRC Operations Center. The recommended elements of the testing program are based on the experience of both industry and the NRC in setting up the ERDS system during the past several years, as documented in NUREG-1394, Revision 1. The recommended program should enable the licensee or applicant to successfully test the ERDS with a minimum of inconvenience and yet with sufficient detail to ensure satisfactory performance of EROS.
A notice of opportunity for public comment was published in the Federal Register on August 20, 1992. Comments were received from seven licensed utilities, one industry organization, and one State agency. Copies of two documents containing the staff evaluation of these comments have been made available in the public Document Room (Accession Numbers 9210210136 and
9211040117).
The information collection contained in this request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.
The estimated average number of burden hours is 4 person hours for each licensee's response (for each unit) each calendar quarter. This estimate of the average number of burden hours pertains to the requested action. Comments on the accuracy of this estimate and suggestions to reduce the burden may be directed to Ronald Minsk, Office of Information and Regulatory Affairs
(3150-0011), NEOB-3019, Office of Management and Budget, Washington, D.C.
20503, and to the U.S. Nuclear Regulatory Commission, Information and Records Management Branch (MNBB 7714), Division of Information Support Services, Office of Information and Resources Management, Washington, D.C. 20555.
KJ
Generic Letter 93-01 - 4- March 3, 1993 If you have any questions about this matter, please contact John Jolicoeur, Office for Analysis and Evaluation of Operational Data, NRC, or your project manager in this office.
Sincerely, Jaes G. Partlow As ociate Director for Projects Office of Nuclear Reactor Regulation Enclosures: I
1. EROS Quarterly Test Schedule
2. List of Recently Issued Generic Letters TECHNICAL
CONTACT
- John Jolicoeur, AEOD
(301) 492-4155 LEAD PROJECT MANAGER: John Hickman, NRR
(301) 504-3017
Enclosure 1 GL 93-01 March 3, 1993 EROS QUARTERLY TEST SCHEDULE
1. This recommended schedule is made necessary because only three telephone lines are available in the NRC Operations Center to ERDS for testing. On some days, for example, the second and eighth Wednesdays of each quarter, a single utility is scheduled to test four units. To accommodate the testing, the licensee should establish a sequence with the test monitor person in the NRC Operations Center, (301) 492-4102.
2. The formal test on the ERDS computer at the NRC Operations Center (step 10 of the ERDS implementation process described on page A-3 of NUREG-1394, Revision 1, 'Emergency Response Data System (ERDS)
Implementation," which is referenced in 10 CFR Part 50, Appendix E) will serve as the test for the quarter in which it is completed. Quarterly testing as described in the generic letter begins in the next calendar quarter.
3. Applicants receiving operating licenses after the date of this generic letter will be added to this recommended quarterly schedule.
WEEK TUESDAY WEDNESDAY THURSDAY
1 BEAVER VALLEY 1, 2 CALVERT CLIFFS 1, 2 HOPE CREEK
FITZPATRICK GINNA INDIAN POINT 2, 3
2 LIMERICK 1, 2 MILLSTONE 1, 2, 3 NINE MILE PT 1, 2 MAINE YANKEE HADDAM NECK OYSTER CREEK
3 PILGRIM SEABROOK SUSQUEHANNA 1, 2 PEACH BOTTOM 2, 3 SALEM 1, 2 THREE MILE ISLAND 1
4 VERMONT YANKEE BROWNS FERRY 2, 3 BRUNSWICK 1, 2 CRYSTAL RIVER 3 SEQUOYAH 1, 2 GRAND GULF
5 CATAWBA 1, 2 FARLEY 1, 2 HATCH 1, 2 McGUIRE 1, 2 ROBINSON HARRIS
6 NORTH ANNA 1, 2 OCONEE 1, 2, 3 SUMMER
SURRY 1, 2
7 ST LUCIE 1, 2 VOGTLE 1, 2 BRAIDWOOD 1, 2 TURKEY POINT 3, 4 CALLAWAY BYRON 1, 2
8 CLINTON DRESDEN 2, 3 DAVIS BESSE
COOK 1, 2 LASALLE 1, 2 DUANE ARNOLD
FERMI 2
9 KEWAUNEE MONTICELLO QUAD CITIES 1, 2 POINT BEACH 1, 2 PRAIRIE ISLAND 1, 2 ZION 1, 2
10 PALISADES ARKANSAS NUCLEAR 1, 2 FT CALHOUN
PERRY COMANCHE PEAK 1, 2 SOUTH TEXAS 1, 2 COOPER
11 RIVER BEND DIABLO CANYON 1, 2 PALO VERDE 1, 2, 3 WATERFORD TROJAN
WOLF CREEK
12 SAN ONOFRE 2, 3 WASHINGTON NUCLEAR 2
WI
Enclosure 2 GL 93-01 March 3, 1993 LIST OF RECENTLY ISSUED GENERIC LETTERS
Generic Date of T*e
4 t^n TceeomA Tn Letter )UD.IecL &44UFlV¢ .
92-09 LIMITED PARTICIPATION BY NRC 12/31/92 ALL HOLDERS OF
IN THE IAEA INTERNATIONAL OLS OR CPs FOR NPRs
92-08 THERMO-LAG 330-1 12/17/92 ALL HOLDERS OF
FIRE BARRIERS OLs OR CPs FOR NPRs
92-07 OFFICE OF NUCLEAR REACTOR 10/10/92 ALL HOLDERS OF
REGULATION REORGANIZATION OLs OR CPs FOR NPRs
83-28 REQUIRED ACTIONS BASED ON 10/07/92 ALL LIGHT-WATER
SUPPLEMENT 1 GENERIC IMPLICATIONS OF SALEM REACTOR LICENSEES
ATWS EVENTS AND APPLICANTS
92-06 OPERATOR LICENSING NATIONAL 09/06/92 ALL POWER REACTOR
EXAMINATION SCHEDULE LICENSEES AND
APPLICANTS FOR AN
OL
92-05 NRC WORKSHOP ON THE 09/04/92 ALL HOLDERS OF
SYSTEMATIC ASSESSMENT OF OLs OR CPs LICENSEE PERFORMANCE FOR NPRs (SALP) PROGRAM
92-04 RESOLUTION OF THE ISSUES 08/19/92 ALL BWR LICENSEES
RELATED TO REACTOR VESSEL FOF OPERATING
WATER LEVEL INSTRUMENTATION IN REACTORS
BWRs PURSUANT TO 1OCFR50.54(F)
90-02 ALTERNATIVE REQUIREMENTS 07/31/92 ALL LWR LICENSEES
SUPPLEMENT 1 FOR FUEL ASSEMBLIES IN THE AND APPLICANTS
DESIGN FEATURES SECTION OF
TECHNICAL SPECIFICATIONS
87-02 SAFETY EVALUATION REPORT 05/22/92 ALL USI A-46 SUPPLEMENT 1 NO. 2 ON SQUG GENERIC LICENSEES WHO
IMPLEMENTATION PROCEDURE, ARE SQUG MEMBERS
REVISION 2.
OL - OPERATING LICENSE
CP - CONSTRUCTION PERMIT
Generic Letter 93-01 - 4 - March 3- 1993
, _
If you have any questions about this matter, please contact John Jolicoeur, Office for Analysis and Evaluation of Operational Data, NRC, or your project manager in this office.
Sincerely, Orig /s/'d by James G. Partlow James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosures:
1. ERDS Quarterly Test Schedule
2. List of Recently Issued Generic Letters TECHNICAL
CONTACT
- John Jolicoeur, AEOD
(301) 492-4155 LEAD PROJECT MANAGER: John Hickman, NRR
(301) 504-3017 DISTRIBUTION w/enclosures CVHodge, NRR JJolicoeur, AEOD RPriebe, AEOD EWeiss, AEOD
LSpessard, AEOD PDR Central Files DORS R/F
OGCB R/F VHodge R/F
- SEE PREVIOUS CONCURRENCES Document Name: 93-01.GL
- OGC *D/DORS:NRR *ADT/NRR ADP/NRFfiL
SLewis BGrimes WTRussell JGPartl
04/01/92 12/30/92 04/13/92 03/a/93
- D/DOA:AEODR *TA/DRPW:NRR *TA/DRPE:NRR *C/OGCB:DORS:NRR*RPB:ADM
LSpessard ELeeds MBoyle GMarcus TechEd
03/13/92 04/13/92 04/09/92 12/11/92 02/20/92
- DP32:DRPW:NRR*OGCB:DOEA:NRR *IRB:DOA:AEOD *IRB:DOA:AEOD *C/IRB:DOA:AEOD
JHickman CVHodge JJolicoeur RPriebe KBrockman
12/03/92 02/18/92 03/11/92 03/12/92 12/07/92
Template:GL-Nav