NRC Generic Letter 1983-023: Safety Evaluation of Emergency Procedure Guidelines.ML031210038 |
Person / Time |
---|
Site: |
Millstone, Calvert Cliffs, Browns Ferry, Oconee, Mcguire, Palisades, Palo Verde, Catawba, Saint Lucie, Watts Bar, Sequoyah, Arkansas Nuclear, Columbia, Turkey Point, Waterford, San Onofre, Maine Yankee, Big Rock Point, Midland, Bellefonte, Fort Calhoun, McGuire, 05000000, 05000307, 05000308, Washington Public Power Supply System, Satsop |
---|
Issue date: |
07/29/1983 |
---|
From: |
Eisenhut D Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
GL-83-023, NUDOCS 8306270422 |
Download: ML031210038 (4) |
|
Similar Documents at Millstone, Calvert Cliffs, Browns Ferry, Oconee, Mcguire, Palisades, Palo Verde, Catawba, Saint Lucie, Watts Bar, Sequoyah, Arkansas Nuclear, Columbia, Turkey Point, Waterford, San Onofre, Maine Yankee, Big Rock Point, Midland, Bellefonte, Fort Calhoun, McGuire, 05000000, 05000307, 05000308, Washington Public Power Supply System, Satsop |
---|
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 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves1996-09-18018 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 1995-041995-04-28028 April 1995 NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues NRC Generic Letter 1995-031995-04-28028 April 1995 NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes 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> [[:Millstone]] OR [[:Calvert Cliffs]] OR [[:Browns Ferry]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Catawba]] OR [[:Saint Lucie]] OR [[:Watts Bar]] OR [[:Sequoyah]] OR [[:Arkansas Nuclear]] OR [[:Columbia]] OR [[:Turkey Point]] OR [[:Waterford]] OR [[:San Onofre]] OR [[:Maine Yankee]] OR [[:Big Rock Point]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:McGuire]] OR [[:05000000]] OR [[:05000307]] OR [[:05000308]] OR [[:Washington Public Power Supply System]] OR [[:Satsop]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Millstone]] OR [[:Calvert Cliffs]] OR [[:Browns Ferry]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Catawba]] OR [[:Saint Lucie]] OR [[:Watts Bar]] OR [[:Sequoyah]] OR [[:Arkansas Nuclear]] OR [[:Columbia]] OR [[:Turkey Point]] OR [[:Waterford]] OR [[:San Onofre]] OR [[:Maine Yankee]] OR [[:Big Rock Point]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:McGuire]] OR [[:05000000]] OR [[:05000307]] OR [[:05000308]] OR [[:Washington Public Power Supply System]] OR [[:Satsop]] </code>. |
July 29, 1983 TO ALL OPERATING REACTOR LICENSEES, APPLICANTS FOR Ali OPERATING
LICENSE AND HOLDERS OF CONSTRUCTION PERMITS FOR COMBUSTION
ENGINEERING PRESSURIZED WATER REACTORS
Gentlemen:
SUBJECT: SAFETY EVALUATION OF "EMERGENCY PROCEDURE GUIDELINES"
(GENERIC LETTER 83-23)
The NRC staff has reviewed the proposed Combustion Engineering Emergency Procedure Guideline (EPG) Program as described in Combustion Engineering Owners Group (CEOG) letters of November 22, 1982 and March 29, 1983, and in the material accompanying those letters. We have concluded that the guidelines are acceptable for implementation and will provide improved guidance for emergency operating procedure development as discussed in Generic Letter 83-09. We suggest that implementation of the guidelines proceed in three steps:
(1) Preparation of plant specific procedures which, in general, conform to the Emergency Procedure Guidelines referenced above and implemen- tation of these procedures as required by Generic Letter 82-33, dated December 17,'1982;
(2) Preparation of supplements to the guidelines which cover changes, new equipment, or new knowledge and incorporation of these supplements into the procedures; and
(3) Completion and improvement of the guidelines to meet our long term requirements, followed by incorporation of improvements Into plant specific procedures.
The prompt implementation of Step 1 will allow the benefits of the significant improvements you have achieved to be realized soon. We note however, that the guidelines are written for the procedure writers, not control room operators, and therefore preparation and implementation of procedures will require additional Human Factors input. Step 2 refers to a program for guideline or procedure updates which will be generated as a matter of routine after the implementation. This essentially is a main- tenance function. Step 3 refers to a program for addressing those aspects of the guidelines and procedures where additional long term work may be needed in your emergency procedure program.
8 3062A.o waft*
OFFICER l ........................... ................................. ......................................... ........................ ............................. ........ ................ ........................
SURNAME >l............................. ................................. ........................ ............................. ........ ................ ........................ ................ . .................
DATE t ......... ............... ......... ____................ ....... ................. ......... ................ ............... ......... .................... ........................
NRC FORM 31B (10-80) NRCM 0240 O FFICIA L R EC O RD C OPY USGPO: 1981t335-960
- 2 - July 29, 1983 We have identified in the Safety Evaluation Report (SER) a number of items associated with the guidelines which need further work by the Combustion Engineering Owners. We require that these items be addressed by either incorporating them into a future guideline revision or otherwise Justifying the disposition of the item. Additionally, because the Emergency Procedure Guidelines must be dynamic in that changes must be made to reflect changes in equipment or new knowledge, we expect the Combustion Engineering Owners'
Group or a similar coalition of utilities and vendors to accept responsi- bility for continued maintenance of the guidelines. Therefore, we have requested in the enclosed letter that the Combustion Engineering Owners'
Group provide a plan for addressing the SER items and by letter dated February 4, 1983, we requested a description of the program for steps 2 and 3 above.
As discussed in the enclosed SER, the staff finds that the EPGs represent a significant improvement over the guidance provided in current emergency operating procedures. The approach of dividing the EPGs into a treatment of recognized "simple" conditions using Optimum Recovery Guidelines (ORGs)
and coverage of all other conditions using Functional Recovery Guidelines (FRGs) meets the requirements for a symptom oriented emergency response.
The guidelines provide sufficent guidance such that they can be translated into acceptable emergency operating procedures using the process identified in NUREG-0899, "Guidelines for the Preparation of Emergency Operating Procedures." The staff therefore concludes that although efforts to im- prove the EPGs should continue, the EPGs identified in CEN-152 Revision 1 will provide a greater assurance of operational safety and are acceptable for implementation.
Sincerely, Original signedby
,.parrell G. Eisenhut Darrell G. Eisenhut, Director Division of Licensing Enclosures:
1. Letter to Mr. ells, dated
2. SER on Guidelines Y1\x DL 5 DL:O A IR
OFFICE
SURNATE
DATE
..
i. ......
US. A..
......
8 .;.........
. 1...
........... ..............
rutoiel..
/~83 ~//3 0
.
/3......... 1 64~8
_
Itx NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORDU LOFVY USGPO. 1981-35960
Generic Letter 83-23
185036002947 172203005004 Arizona Public Service Co Arkansas Power & Light Co Nuclear Projects Energy Supply E E Van Brunt Jr W Cavanaugh III
Vice President Sr Vice President PO Box 21666 PO Box 551 Phoeniz AZ 85036 Little Rock AR 72203 Baltimore Gas & Electric Co 149201058220
Supply Consumers Power Co A E Lundvall Jr J W Cook Vice President - Supply Vice President PO Box 1475 1945 W Parnall Rd Baltimore MD 21203 Jackson MI 49201
128242028120 128242081033 Duke Power Co Duke Power Co Nuclear Production Dept Design Engineering K S Canady L C Dail Manager Vice President PO Box 33189 PO Box 33189 Charlotte NC 28242 Charlotte NC 28242
133408081117 170174028293 Florida Power & Light Co Louisiana Power & Light Co Advanced Systems & Technology Nuclear Operations Robert E Uhrig L V Maurin Vice President 142 Delaronde St PO Box 14000 PO Box 6008 Juno Beach FL 33408 New Orleans LA 70174
104336008719 104330004692 Maine Yankee Atomic Power Co Maine Yankee Atomic Power Co John B Randazza Elwin W Thurlow Vice President President
83 Edison Drive 9 Green Street Augusta ME 04336 Augusta ME 04330
106101005752 168102022680
Northeast Utilities Service Co Omaha Public Power District John Opeka Production Operations Vice President-Nuclear Operation William C Jones PO Box 270 Division Manager Hartford CT 06101 1623 Harney Street Omaha NE 68102
191770058231 137401023241 Southern California Edison Co Tennessee Valley Authority Nuclear Engr & Operations Hugh G Parris R Dietch Manager
2244 Walnut Grove Ave 500 A Chestnut St Tower II
PO Box 800 Chattanooga TN 37401 Rosemead CA 91770
GL 83-23 Page 2
120590006830 199352008688
1 US Maritime Administration Washington Pub Power Supl Sys Ofc of Advanced Ship Operations R L Ferguson Z Levine Managing Director Mar-930 Room 4100 PO Box 968 Washington DC 20590 Richland WA 99352
Template:GL-Nav