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{{Adams
#REDIRECT [[AECM-82-280, Forwards 37 Offnormal Event Procedures in Response to ACRS Subcommittee Request at 810917-18 Meeting]]
| number = ML20054J948
| issue date = 06/25/1982
| title = Forwards 37 Offnormal Event Procedures in Response to ACRS Subcommittee Request at 810917-18 Meeting
| author name = Dale L
| author affiliation = MISSISSIPPI POWER & LIGHT CO.
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000416, 05000417
| license number =
| contact person =
| document report number = AECM-82-280, NUDOCS 8206300231
| package number = ML20054J949
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}
 
=Text=
{{#Wiki_filter:_
MISSISSIPPI POWER & LIGHT COMPANY
                        ]
Helping Build Mississippi P. O. B O X 16 4 0. J A C K S O N. MISSISSIPPI 39205 NUCLEAH PHODUCTION DEPARTMENT U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.        20555 At t en t. ion : tir . Harold R. Denton, Director
 
==Dear tir. Denton:==
 
==SUBJECT:==
Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 File 0260/L-360.0 Off-Normal Evrnt Procedures -
ACRS Request AECtt-82/280 In response to your request at the ACRS Subcommittee meeting held September 17-18, 1981, tfississippi Power & Light Company is submitting to you copies of the Grand Gulf Nuclear Station ' Of f-Normal Event Procedures" (ONEP's) which are a part of the emergency operating instructions for personnel at the Grand Gulf facility.
I f you have any questions or require additional information, please contact this office.
Yours truly,              ,
                                                                          ,      ?
                                                          /
t-  f-c  l, ', :          /    ,
Mr          ~        '~ s u''
ll' L. F. Dale                  "
                                              /          ?!anager of Nuclear Services RFP/JGC/JDR: 1m Attachments cc: tir . N. L. Stampley (w/o)
Mr. R. B. McGehee (w/o)
Mr. T. B. Conner (w/o)
Mr. G. B. Taylor (w/o)
Mr. Richard C. DeYoung, Director (w/o)                              g{
Office of Inspection & Enforcement                                O U.S. Nuclear Regulatory Commission Washington, D.C. 20555 (Continued on Next Page) 8206300231 820625 PDR ADOCK 05000416 P                          PDR AE3T1 Member Middle South Utilities System
 
t MISSISSIPPI POWER O LICHT CCMPANY AECM-82/280 Page 2 i
cc: (Continued)
Mr. J. P. O'Reilly, Regional Administrator (w/o)
Office of Inspection & Enforcement
,            Region II 101 Marietta Street, N.W., Suite 3100 Atlanta, Georgia 30303 Mr. Herman Alderman (w/2)
Advisory Committee on Reactor Safeguards 1717 H. Street Room H 1016 Washington, D.C.      20555 4
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AE3T2
 
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Attachment to AECM-82/280 OFF-NOPJfAL EVENT PROCEDURES LISTING Procedure Number Description                                          Revision 05-1-02-I-1      Reactor Scram                                            11 05-1-02-I-2      Turbine and Generator Trips                              10 05-1-02-I-3      Single MSIV Closure                                      10 05-1-02-I-4      Loss of Offsite Power                                    11 05-1-02-I-5      Resin Intrusion Into the Reactor Vessel                  11 05-1-02-II-1    Shutdown from the Remote Shutdown Panel                  11 05-1-02-II-2    Off Gas Activity High                                    11 05-1-02-11-3    Offsite Gaseous Releases                                  10 05-1-02-II-8    High Radiation During Fuel Handling                      10 05-1-02-II-9    High Airborne                                            11 05-1-02-II-11    Liquid Radwaste System Leak or Failure                    10 05-1-02-II-12    Solid Radwaste Spill                                      10 05-1-02-III-1    Inadequate Decay ifeat Removal                            10 05-1-02-III-2    Loss of One or Both RPS Buses                            10 05-1-02-III-3    Decrease in Recirculation System Flow Rate                11 05-1-02-III-5    Automatic Isolations                                      12 05-1-02-III-11  Containment Hydrogen Control                              11 05-1-02-IV-1    Control Rod / Drive Malfunctions                          11 05-1-02-IV-6    Loss of RPIS                                              11 05-1-02-V-1      Loss of Component Cooling Water                          10 05-1-02-V-2      Loss of Turbine Building Cooling Water                    11 05-1-02-V-3      Pressure Control Failure - Reactor Pressure Decreasing 10 05-1-02-V-4      Pressure Control Failure - Reactor Pressure Increasing 11 05-1-02-V-5      Loss of Feedwater Heating                                11 05-1-02-V-6      Feedwater Control Failure Max Demand                      11 05-1-02-V-7      Loss of Feedwater Flow                                    II 05-1-02-V-8      Loss of Condenser Vacuum                                  10 05-1-02-V-9      Loss of Instrument Air                                    10 05-1-02-V-10    Loss of Standby Service Water Loop A, B, or C            10 05-1-02-V-11    Loss of Plant Service Water                              10 05-1-02-V-12    Condensate High Conductivity                              10 05-1-02-V-13    Hydrogen Explosion in the Off Gas System                  11 05-1-02-V-14    Main Generator Primary Water High Conductivity            11 05-1-02-V-15    Low System Frequency                                      10 05-1-02-VI-1    Flooding                                                  10 05-1-02-VI-2    Hurricanes, Tornados, and Severe Weather                  10 05-1-02-VI-3    Earthquake                                                10 AE3T3
_                                    _}}

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