05000259/LER-1997-003, Forwards LER 97-003-00 Which Provides Details Re Valve Alignment Which Could Reduce Effectiveness of Pressure Suppression Function of Suppression Pool: Difference between revisions

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{{Adams
#REDIRECT [[05000259/LER-1997-003]]
| number = ML20216G827
| issue date = 09/09/1997
| title = Forwards LER 97-003-00 Which Provides Details Re Valve Alignment Which Could Reduce Effectiveness of Pressure Suppression Function of Suppression Pool
| author name = Crane C
| author affiliation = TENNESSEE VALLEY AUTHORITY
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000259
| license number =
| contact person =
| document report number = NUDOCS 9709160060
| package number = ML20216G831
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
}}
{{LER
| Title = Forwards LER 97-003-00 Which Provides Details Re Valve Alignment Which Could Reduce Effectiveness of Pressure Suppression Function of Suppression Pool
| Plant =
| Reporting criterion =
| Power level =
| Mode =
| Docket = 05000259
| LER year = 2097
| LER number = 3
| LER revision =
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
{{#Wiki_filter:_i; .
Temesseo Vaney Authority, Post Offce Box 2000, Decatur. Alabama 35009-2000 Christopher M. (Chns) Crane
                  ' Ace President, Browns Ferry Ntriear Plant September-9, 1997 10 CFR 50.73 U.S. Nuclear Regulatory Commission
              ' ATTN:        Document Control Desk Washington,-D.C. 20555
 
==Dear Sir:==
 
BROWNS .?ERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 - DOCKET NOS.-50-259,'260,-AND 296 - FACILITY OPERATING LICENSE DPR-33, 52, AND 68 - LICENSEE EVENT REPORT 50-259/97003 The enclosed report provides. details concerning a valve.
alignment which could reduce the effectiveness of the pressure suppression function of the suppression pool. If Division 1 of the Primary Containment Isolation System faf. led while in this valve alignment and a Design Basis Loss of Coolant Accident occurred, containment pressure could exceed the maximum containment design pressure. The root cause was a design error, in that no interlock precluded this method,-nor did design output or the Final Safety Analysis Repvrt (FSAR) caution against this alignment. Consequently, this report is submitted in accordance with 10 CFR 50.73 (a) (2) (ii) (B) as any event or condition that resulted in the nuclear power plant being in a condition that was outside the design basis of the plant.
Sin      r e l ,.
C. M. Crane cc:      See page 2                                                                      '
gG 9-9709160060 970909 PDR        ADOCK 05000259 8                              PDR 4 (((' tb i
1
 
              ~UlS.-Nuclear Regulatory Commission Page 2
              - September 9.-1997 Enclosure cc (Enclosure):
Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulstory Commission  .
61 Forsyth Street, S.W.
Suite 23T85              ,
Atlanta, Georgia  30323:
NRC Resident: Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens,-Alabama  35611 Mr. J. F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland  20852 a
}}
 
{{LER-Nav}}

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