View source for AECM-82-280, Forwards 37 Offnormal Event Procedures in Response to ACRS Subcommittee Request at 810917-18 Meeting

{{Adams
| 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 &amp; 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
i f
l
(
1 I
l i
r l
AE3T2

r
~
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
_                                     _}}