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| | issue date = 07/29/1983 | | | issue date = 07/29/1983 |
| | title = NRC Generic Letter 1983-023: Safety Evaluation of Emergency Procedure Guidelines. | | | title = NRC Generic Letter 1983-023: Safety Evaluation of Emergency Procedure Guidelines. |
| | author name = Eisenhut D G | | | author name = Eisenhut D |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
NRC Generic Letter 1983-023: Safety Evaluation of Emergency Procedure Guidelines.ML031210038 |
Person / Time |
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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 |
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Issue date: |
07/29/1983 |
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From: |
Eisenhut D Office of Nuclear Reactor Regulation |
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To: |
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References |
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GL-83-023, NUDOCS 8306270422 |
Download: ML031210038 (4) |
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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 |
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Category:NRC Generic Letter
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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 ...........................
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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 i. ...... ...... Itx ...........
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- SURNATE .. US. A.. 8 .;.........
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.1... _DATE .........~//3 /~83 0 /3 1 64~8 NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORDU LOFVY USGPO. 1981-35960
Generic Letter 83-23 185036002947 Arizona Public Service Co Nuclear Projects E E Van Brunt Jr Vice President PO Box 21666 Phoeniz AZ 85036 Baltimore Gas & Electric Co Supply A E Lundvall Jr Vice President
-Supply PO Box 1475 Baltimore MD 21203 128242028120
Duke Power Co Nuclear Production Dept K S Canady Manager PO Box 33189 Charlotte NC 28242 133408081117 Florida Power & Light Co Advanced Systems & Technology Robert E Uhrig Vice President PO Box 14000 Juno Beach FL 33408 104336008719 Maine Yankee Atomic Power Co John B Randazza Vice President 83 Edison Drive Augusta ME 04336 106101005752 Northeast Utilities Service Co John Opeka Vice President-Nuclear Operation PO Box 270 Hartford CT 06101 172203005004 Arkansas Power & Light Co Energy Supply W Cavanaugh III Sr Vice President PO Box 551 Little Rock AR 72203 149201058220
Consumers Power Co J W Cook Vice President 1945 W Parnall Rd Jackson MI 49201 128242081033 Duke Power Co Design Engineering L C Dail Vice President PO Box 33189 Charlotte NC 28242 170174028293 Louisiana Power & Light Co Nuclear Operations L V Maurin 142 Delaronde St PO Box 6008 New Orleans LA 70174 104330004692 Maine Yankee Atomic Power Co Elwin W Thurlow President 9 Green Street Augusta ME 04330 168102022680
Omaha Public Power District Production Operations William C Jones Division Manager 1623 Harney Street Omaha NE 68102 191770058231 Southern California Edison Co Nuclear Engr & Operations R Dietch 2244 Walnut Grove Ave PO Box 800 Rosemead CA 91770 137401023241 Tennessee Valley Authority Hugh G Parris Manager 500 A Chestnut St Tower II Chattanooga TN 37401 GL 83-23 Page 2 120590006830
1 US Maritime Administration Ofc of Advanced Ship Operations Z Levine Mar-930 Room 4100 Washington DC 20590 199352008688 Washington Pub Power Supl Sys R L Ferguson Managing Director PO Box 968 Richland WA 99352
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