ML18024A496: Difference between revisions

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| issue date = 10/25/1978
| issue date = 10/25/1978
| title = Forwards LER 78-017/03L-0
| title = Forwards LER 78-017/03L-0
| author name = FOX H S
| author name = Fox H
| author affiliation = TENNESSEE VALLEY AUTHORITY
| author affiliation = TENNESSEE VALLEY AUTHORITY
| addressee name = OREILLY J P
| addressee name = Oreilly J
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| docket = 05000260
| docket = 05000260
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:REGULATOR NFORMATXON DXSTRIBUTION STEM DOCKET NBR: 050-260 BROWNS 2 RECXPIENT:
{{#Wiki_filter:REGULATOR     NFORMATXON DXSTRIBUTION   STEM DOCKET NBR:           050-260 BROWNS   2           DOC  DATE:    781025 RECXPIENT: O'REILLY, J.P.                         ACCESSXON NBR: 7810300168 ORIGINATOR: FOX, H.S.                             COPXES RECEIVED:
O'REILLY, J.P.ORIGINATOR:
COMPANY NAME: TN VALLEY AUTH                       LTR    1        ENCL    1
FOX, H.S.COMPANY NAME: TN VALLEY AUTH  


==SUBJECT:==
==SUBJECT:==
LERI78-017/03L-0 on 781004: Drywell DOC DATE: 781025 ACCESSXON NBR: 7810300168 COPXES RECEIVED: LTR 1 ENCL 1 SIZE: 1+2 oxygen concentration was n'ot reduced-to 4%w/in 24-hour period after placing reactor in run mode, due to personnel safety consid'erations during repair of inner drywell air lock repairs.DISTRIBUTION CODE!A002 DISTRIBUTIO<
SIZE: 1+2 LERI78-017/03L-0 on 781004: Drywell oxygen concentration was n'ot reduced to 4% w/in 24-hour period after placing reactor in run mode, due to personnel safety consid'erations during repair of inner drywell       air lock repairs.
TITLE t INCIDENT REPORTS NOTARXZED BR C~~NRC PDR'I S E I NIPC I I 8 C SYSTE"S BR I NOYAK/CHECK EEB AD FOR ENG~PLANT SYSTEMS BR~HANAUFR;AD FOR PLANT,SYSTEHS I AD FOR SYS R PROJ REACTnR SAFETY RR ENGINEERING BR KREGER/J~COLLINS~POWER SYS BRK SEYFRIT/IE
NOTARXZED DISTRIBUTION CODE! A002 DISTRIBUTIO< TITLE t INCIDENT REPORTS ENCL'              FOR ACTION BR   C~~                 W/e ENCL        ~ ORBI 3 BC W/ENCL NRC   PDR               W/ENCL
" ,LPDR ,.NSIC ACRS, ENCL'W/e ENCL W/ENCL W/ENCL".I/2 ENCL W/3 ENCL 0/FNCL W/ENCL W/ENCL W/ENCL W/l NCL t4/ENCL W/ENCL W/ENCL w/ENCL W/FNCL W/ENCL W/ENCL'l4/ENCL w/ENCL W/ENCL W/i6 ENCL" FOR ACTION~ORBI 3 BC TOTAL NUHRER QF.COPIES REOUIREnt LTR ENCL NOTES:  
  'I   S   E                 ".I/2 ENCL I   NIPC                     W/3 ENCL I     I 8   C SYSTE"S   BR   0/FNCL I     NOYAK/CHECK             W/ENCL EEB                     W/ENCL AD FOR ENG               W/ENCL
~~~C I TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 87401 October 25, 1978 Mr.James P eilly, rector U.S.Nuc ar Reg lato Commission Offic of Inspect and Enforcement Reg n II 10 Marietta Street, Suite 3100 Atlanta, Georgia 30303
~     PLANT SYSTEMS BR         W/l NCL
~     HANAUFR                 t4/ENCL AD FOR PLANT,SYSTEHS W/ENCL I     AD FOR SYS R PROJ       W/ENCL REACTnR     SAFETY RR   w/ENCL ENGINEERING BR           W/FNCL KREGER/ J   ~ COLLINS   W/ENCL
~
POWER   SYS BR          W/ENCL K SEYFRIT/IE                  'l4/ENCL
,LPDR
"                              w/ENCL
  ,. NSIC                    W/ENCL ACRS,                    W/i6 ENCL" TOTAL NUHRER QF. COPIES     REOUIREnt LTR ENCL NOTES:


==Dear Mr.O'Reilly:==
~ ~  ~
TENNESSEE VALLEY AUTHORITY-BROWNS FERRY NUCLEAR PLANT UNIT 2-DOCKET NO.50-260-FACILITY OPERATING LICENSE DPR-52<<REPORTABLE OCCURRENCE REPORT BFRO-50-260/7817 The enclosed report provides details concerning the drywell oxygen concentration which was not reduced to 4 percent within the 24-hour period subsequent to placing the reactor in the run mode.This report is submitted in accordance with Browns Ferry unit 2 Technical Specification 6.2.A.2.Very truly yours, TENNESSEE VALLEY AUTHORITY H.S.Fox Director of Power Production Enclosure (3)cc (Enclosure):
C        I TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 87401 October 25, 1978 Mr. James P        eilly,  rector U.S. Nuc ar Reg lato        Commission Offic of Inspect        and Enforcement Reg    n  II 10  Marietta Street, Suite    3100 Atlanta, Georgia 30303
Director (3)Office of Management Information a U.S.Nuclear Regulatory Commissio Washington, D.C.20555 Director (40)Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission Washington, D.C.20555 Program Control 7g-(op<o (4E An Equal Opportunity Employer}}
 
==Dear Mr. O'Reilly:==
 
TENNESSEE VALLEY AUTHORITY     - BROWNS FERRY NUCLEAR PLANT UNIT 2 - DOCKET NO. 50-260   - FACILITY OPERATING LICENSE DPR-52 << REPORTABLE OCCURRENCE REPORT BFRO-50-260/7817 The enclosed   report provides details concerning the drywell oxygen concentration which was not reduced to 4 percent within the 24-hour period subsequent to placing the reactor in the run mode. This report is submitted in accordance with Browns Ferry unit 2 Technical Specification 6.2.A.2.
Very   truly yours, TENNESSEE VALLEY AUTHORITY H. S. Fox Director of   Power Production Enclosure (3) cc (Enclosure):
Director (3)
Office of Management Information     a     Program Control U.S. Nuclear Regulatory Commissio Washington, D.C. 20555 Director (40)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 An Equal Opportunity Employer 7g-(op<   o (4E}}

Latest revision as of 21:04, 23 February 2020

Forwards LER 78-017/03L-0
ML18024A496
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 10/25/1978
From: Fox H
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024A497 List:
References
NUDOCS 7810300168
Download: ML18024A496 (2)
v • d • e


Text

REGULATOR NFORMATXON DXSTRIBUTION STEM DOCKET NBR: 050-260 BROWNS 2 DOC DATE: 781025 RECXPIENT: O'REILLY, J.P. ACCESSXON NBR: 7810300168 ORIGINATOR: FOX, H.S. COPXES RECEIVED:

COMPANY NAME: TN VALLEY AUTH LTR 1 ENCL 1

SUBJECT:

SIZE: 1+2 LERI78-017/03L-0 on 781004: Drywell oxygen concentration was n'ot reduced to 4% w/in 24-hour period after placing reactor in run mode, due to personnel safety consid'erations during repair of inner drywell air lock repairs.

NOTARXZED DISTRIBUTION CODE! A002 DISTRIBUTIO< TITLE t INCIDENT REPORTS ENCL' FOR ACTION BR C~~ W/e ENCL ~ ORBI 3 BC W/ENCL NRC PDR W/ENCL

'I S E ".I/2 ENCL I NIPC W/3 ENCL I I 8 C SYSTE"S BR 0/FNCL I NOYAK/CHECK W/ENCL EEB W/ENCL AD FOR ENG W/ENCL

~ PLANT SYSTEMS BR W/l NCL

~ HANAUFR t4/ENCL AD FOR PLANT,SYSTEHS W/ENCL I AD FOR SYS R PROJ W/ENCL REACTnR SAFETY RR w/ENCL ENGINEERING BR W/FNCL KREGER/ J ~ COLLINS W/ENCL

~

POWER SYS BR W/ENCL K SEYFRIT/IE 'l4/ENCL

,LPDR

" w/ENCL

,. NSIC W/ENCL ACRS, W/i6 ENCL" TOTAL NUHRER QF. COPIES REOUIREnt LTR ENCL NOTES:

~ ~ ~

C I TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 87401 October 25, 1978 Mr. James P eilly, rector U.S. Nuc ar Reg lato Commission Offic of Inspect and Enforcement Reg n II 10 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 2 - DOCKET NO. 50-260 - FACILITY OPERATING LICENSE DPR-52 << REPORTABLE OCCURRENCE REPORT BFRO-50-260/7817 The enclosed report provides details concerning the drywell oxygen concentration which was not reduced to 4 percent within the 24-hour period subsequent to placing the reactor in the run mode. This report is submitted in accordance with Browns Ferry unit 2 Technical Specification 6.2.A.2.

Very truly yours, TENNESSEE VALLEY AUTHORITY H. S. Fox Director of Power Production Enclosure (3) cc (Enclosure):

Director (3)

Office of Management Information a Program Control U.S. Nuclear Regulatory Commissio Washington, D.C. 20555 Director (40)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 An Equal Opportunity Employer 7g-(op< o (4E

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