View source for RBG-24481, Suppls 860228 & 850515 Responses to Generic Ltr 82-33, Requirements for Emergency Response Capability. Status of SPDS & Digital Radiation Monitoring Sys Discussed

{{Adams
| number = ML20210T789
| issue date = 09/29/1986
| title = Suppls 860228 & 850515 Responses to Generic Ltr 82-33, Requirements for Emergency Response Capability. Status of SPDS & Digital Radiation Monitoring Sys Discussed
| author name = Booker J
| author affiliation = GULF STATES UTILITIES CO.
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000458
| license number = 
| contact person = 
| case reference number = RTR-NUREG-0737, RTR-NUREG-737
| document report number = GL-82-33, RBG-24481, NUDOCS 8610090193
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}

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GULF STATES                         UTILITIES COMPANY RIVER BEND STATION     POST OFFICE BOX 220      ST. FRANCISVILLE LOUISIANA 70775 AREA CODE 504     635 6094        346-8651 September 29, 1986 RBG 24481 File G9.5, G9.33.4 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. c. 20555

==Dear Mr. Denton:==

River Bend Station-Unit 1 Docket No. 50-458 Gulf     States         Utilities               (GSU)          is providing herein followup information on two items from Generic Letter 82-33, Supplement I related to Emergency Response Facilities.                                            The first is a status on the River Bend Station (RBS) Safety Parameter Display System (SPDS)    and Digital Radiation Monitoring Systems (DRMS). The second item revises the list of variables monitored by the SPDS.
Gulf States Utilities (GSU) has completed its testing of the SPDS and DRMS as discussed in its {{letter dated|date=February 28, 1986|text=February 28, 1986 letter}} to your office and as required by Generic Letter 82-33, Supplement 1 to NUREG-0737      -
                          " Requirements for Emergency Response Capability".
Both of these systems are currently functional. While performing base line testing for the Digital Radiation Monitoring System (DRMS) data base and associated algorithms capabilities, GSU determined that several enhancements could be made which would significantly improve the DRMS emergency offsite dose projection computer      capabilities.                   These enhancements are expected to improve the capabilities in the areas of calculating fission product     content             change            with time; selection and use of manual / automatic parameter input for accident scenarios; use of automatic parameter input during drill and exercises; and output                                                    ,_
format for dose projection information. These enhancements are not expected to be completed until the end of 1987.                                            As noted in FSAR Table 13.3-16, the_ backups to the automated dose assessment system     of       DRMS          are manual dose assessment method                                  (e.g.
programmable calculator and/or isopleths) which are currently                                           in place. Therefore, GSU currently has redundant capabilities to perform offsite dose projection calculations.
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8610090193 860929 PDR        ADOCK 05000458                                                             l     O F                               PDR                                                       I

Mr. Denton                                                 September 29, 1986 In GSU's {{letter dated|date=May 15, 1985|text=May 15, 1985 letter}} to your office regarding the SPDS, Table 1 identified SPDS monitored variables.                     Under Containment Integrity,     the   varieble     of   containment /drywell               laydrogen concentration was listed in error.            The RBS SPDS design is consistent with the SPDS function of the General Electric (GE) approved     Emergency   Response     Information System (ERIS) as described in NEDE-30284-P dated November 1983.                       The GE SPDS displays were addressed in NRC's GESSAR-2 SSER-4, Appendix G.
Included as part of the SSER review were the basic containment and     drywell    parameters     monitored    by               the   SPDS.       The containment /drywell hydrogen concentration parameter was                         not included in the GESSAR-2 parameters to be monitored. The NRC's SSER-4 conclusions stated that the parameters selected for the GE SPDS would be acceptable with the addition of radiation monitors to show the status of the Radioactivity Control Function which is included in the RBS DRMS. Therefore, GSU concludes that the RBS SPDS monitored variables are consistent with the GE SPDS displays without the containment /drywell hydrogen concentration variable as listed in Table 1 of GSU's {{letter dated|date=May 15, 1985|text=May 15, 1985 letter}}.
Sincerely, f..
J   f. Booker E.
Manager-River Bend Oversight River Bend Nuclear Group JEB/   k/ER   je 1
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