ML20137L671: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
(One intermediate revision by the same user not shown)
Line 1: Line 1:
{{Adams
#REDIRECT [[AECM-85-0175, Forwards Rev 6 to Vol 8,Section 3,Procedure 08-S-03-17, Chemistry Procedure Core Damage Estimation Safety-Related, in Response to NRC Request to Incorporate Conservative Fission Product Release Fractions.Fee Paid]]
| number = ML20137L671
| issue date = 11/22/1985
| title = Forwards Rev 6 to Vol 8,Section 3,Procedure 08-S-03-17, Chemistry Procedure Core Damage Estimation Safety-Related, in Response to NRC Request to Incorporate Conservative Fission Product Release Fractions.Fee Paid
| 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
| license number =
| contact person =
| case reference number = TASK-2.B.3, TASK-TM
| document report number = AECM-85-0175, AECM-85-175, TAC-60187, NUDOCS 8512030508
| package number = ML20137L677
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}
 
=Text=
{{#Wiki_filter:/
    '    ~
MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B O X 164 0, J A C K S O N, MIS SIS SIP PI 39215-1640 November 22, 1985 NUCLEAR LILENSING & SAFETY DEPARTMENT U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention:        Mr. Harold R. Denton, Director
 
==Dear Mr. Denton:==
 
==SUBJECT:==
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29
                        .                                            Core Damage Assessment Procedure AECM-85/0175 By letter dated April 15, 1982, Mississippi Po'wer & Light (MP&L) submitted the core damage estimation procedure for Grand Gulf Nuclear Station (GGNS) Unit 1. The NRC presented its evaluation of the procedure in GGNS Safety Evaluation Report, Supplement No. 4 (SSER4) dated May 1983. In SSER4, the NRC requested that MP&L revise the procedure to incorporate more conservative fission product release fractions and include additional plant indicators (e.g., reactor water level). These requirements were incorporated into Operating License Condition 2.C.(33).c. The purpose of this submittal is to provide the revised core damage estimation procedure as required by the license condition.
The attachment to this submittal provides the revised " Core Damage Estimation" procedure 08-S-03-17, Revision 6, dated November 15, 1985 for your review.
In accordance the provisions of 10CFR170 an application fee of $150 is attached.        If you have any questions, contact this office.
Yours truly, L. F. Dale Director MLC/JGC:bms Attachment cc:      (See Next Page)                                                                g 40
                                                                                                'l 0512030508 851122 16 PDR      ADOCK 0500 J16AECM85112101 - 1          Member Middle South Utilities System dcM m                                  .
 
AECM-85/0175 Page 2 cc:- Mr. O. D. Kingsley, Jr. (w/a)
Mr. T. H. Cloninger (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S.'Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. R. C. Butcher (w/a)
Mr. James M. Taylor, Director (w/a)
Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. J. Nelson Grace, Regional Administrator (w/a)
U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta,~ Georgia 30323 J16AECM85112101 - 2
              =}}

Latest revision as of 05:25, 9 August 2022

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML20137L671&oldid=3453830"