ML18024A536: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:REGULATORY FORMATXON DOCKET NBR: 50 296 BRO>~S PER RECXPIENT:
{{#Wiki_filter:REGULATORY           FORMATXON DX STRX BUTION        TEM DOCKET NBR: 50 296 BRO>~S PER                               DOC DATE-      781108 RECXPIENT: O<REILLY               J.P.                     ACCESSION NBR:
O<REILLY J.P.ORXGINATOR:
ORXGINATOR: POZ H. S.                                       COPIES RECEIVED:
POZ H.S.DX STRX BUTION TEM DOC DATE-781108 ACCESSION NBR: COPIES RECEIVED: COMPANY NAME: TN VALLEY AUTH  
COMPANY NAME: TN VALLEY AUTH                                 LTR        1      ENCL


==SUBJECT:==
==SUBJECT:==
LTR 1 SI ZE: 1+1 ENCL R0050-296 7822 on 780822: durin startu a 3%thermal pwr, MSRV 1-4 opened 6 did not, reclose corn letel resultin in excessive vessel cooldown rate, due a arentl to excessive ilot second-stage leakage in the valve's.DISTRfBUTION CODE>-8002 DISTR I BUT ION TI~LE).INCIDENT REPORTS NOTARIZED REG PDR I L MIPC I L C SYSTEMS SR NOVAK/CHECK EEB)AD FOR ENG PLANT SYSTEMS BP HANAUFR.AD FOR PLANT SYSTEMS-AD FOR SYS L PRDJ REACTOR SAFETY BR ENGINEERING BR KREGER/J,'OLL I>>S POHER SYS BR E.Jordan LPDR , NSIC'CRS ENCLV w/4 ENCL w/ENCL<</Et4CL w/2 ENCL'8/3 ENCL W/F.NCL W/ENCL<</ENCL l"/F.NCL w/I NCL<</ENCL w/ENCL w/ENCL W/ENCL W/ENCL w/FNCL w/ENCL w/ENCL w/ENCL w/ENcL W/i6 ENCL FOR ACTION'ORB 3 BC TOTAL NUMBER OF COPIES REQUIREDI LTR ENCL NOTES: HEAD TO HEAD$0$]l Sl~1978 November 8, 1978 TENNESSEE VALLEY AUTHORIT~CHATTANOOGA.
SI ZE:     1+1 R0050-296 7822 on 780822: durin       startu a 3% thermal pwr, MSRV 1-4 opened 6 did not, reclose corn letel                   resultin in excessive vessel cooldown rate, due a arentl to excessive                     ilot second-stage     leakage in the valve's.
TENNESSEE 37401 tfkggtg(gP~f PP'%~'<rt rr Hr.James P.O'Reilly, Director U.S.Nuclear Regulatory Comrrtission Office of Inspection and Enforcement Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303  
NOTARIZED DISTRfBUTION       CODE>     -8002 DISTR   I BUT ION   TI ~LE ).
INCIDENT REPORTS ENCLV                    FOR ACTION w/4 ENCL           '
ORB 3 BC REG                              w/ENCL PDR                      <</Et4CL I  L                            w/2 ENCL MIPC                            '8/3 ENCL I  L C  SYSTEMS SR            W/F.NCL NOVAK/CHECK                      W/ENCL EEB                              <</ENCL AD FOR    ENG                  l" /F.NCL
)
PLANT SYSTEMS        BP        w/I   NCL HANAUFR                          <</ENCL
. AD FOR PLANT SYSTEMS            w/ENCL
 
AD FOR SYS L PRDJ                w/ENCL REACTOR SAFETY BR                W/ENCL ENGINEERING        BR            W/ENCL KREGER/J,'OLL I>>S              w/FNCL POHER    SYS  BR              w/ENCL E. Jordan                        w/ENCL LPDR                            w/ENCL NSIC                            w/ENcL
  'CRS                              W/i6
  ,
ENCL TOTAL NUMBER OF COPIES             REQUIREDI LTR ENCL NOTES:       HEAD TO HEAD
                                                  $ 0$ ] l Sl~
1978
 
TENNESSEE VALLEY AUTHORIT~
CHATTANOOGA. TENNESSEE 37401 November 8, 1978 tfkggtg(gP~f PP'%~'<rt           rr Hr. James   P. O'Reilly, Director U.S. Nuclear Regulatory Comrrtission Office of Inspection and Enforcement Region   II 101 Marietta Street, Suite       3100 Atlanta, Georgia 30303
 
==Dear Hr. O'Reilly:==
 
TENNESSEE VALLEY AUTHORITY  DROVES FERRY NUCLEAR PLIANT UNIT 3  DOCKET NO. 50-296    -  FACILITY OPERATING LICFSiSE DPR-68        - REPORTABLE OCCURRENCE REPORT    BFRO-50-296/7822 This refers to my letter dated September 1, 1978. Enclosed is supplemental reportable occurrence report BFRO-50-296/7822 which provides details concerning main steam relief valve 1-4 which opened during startup at
    -percent thermal power. This repoxt is submitted in accordance with Browns Ferry unit 3 technical specification 6.7.2.A.(2).
Very  truly yours, TENNESSEE VALLEY AUTHORITY H. S. Fox Director of    Power Production F~closure (3) cc (Enclosure):
Director (3)
Office of Hanagement Information        and Program    Control U.S, Nuclear Regulatory Commission li'ashington, D.CD 20555 Dixector (40)
Office of Inspection    and Enforceme      t U.S. Nuclear Regulatory Commissi Vashin ton D C        20555 An Equal Opportunity Employer V811160~%          f


==Dear Hr.O'Reilly:==
TENNESSEE VALLEY AUTHORITY-DROVES FERRY NUCLEAR PLIANT UNIT 3-DOCKET NO.50-296-FACILITY OPERATING LICFSiSE DPR-68-REPORTABLE OCCURRENCE REPORT BFRO-50-296/7822 This refers to my letter dated September 1, 1978.Enclosed is supplemental reportable occurrence report BFRO-50-296/7822 which provides details concerning main steam relief valve 1-4 which opened during startup at-percent thermal power.This repoxt is submitted in accordance with Browns Ferry unit 3 technical specification 6.7.2.A.(2).
Very truly yours, TENNESSEE VALLEY AUTHORITY H.S.Fox Director of Power Production F~closure (3)cc (Enclosure):
Director (3)Office of Hanagement Information and Program Control U.S, Nuclear Regulatory Commission li'ashington, D.CD 20555 Dixector (40)Office of Inspection and Enforceme t U.S.Nuclear Regulatory Commissi Vashin ton D C 20555 V811160~%f An Equal Opportunity Employer
>>O'a}}
>>O'a}}

Revision as of 03:06, 22 October 2019

Forwards RO#50-296/7822
ML18024A536
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 11/08/1978
From: Fox H
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024A537 List:
References
NUDOCS 7811160099
Download: ML18024A536 (3)


Text

REGULATORY FORMATXON DX STRX BUTION TEM DOCKET NBR: 50 296 BRO>~S PER DOC DATE- 781108 RECXPIENT: O<REILLY J.P. ACCESSION NBR:

ORXGINATOR: POZ H. S. COPIES RECEIVED:

COMPANY NAME: TN VALLEY AUTH LTR 1 ENCL

SUBJECT:

SI ZE: 1+1 R0050-296 7822 on 780822: durin startu a 3% thermal pwr, MSRV 1-4 opened 6 did not, reclose corn letel resultin in excessive vessel cooldown rate, due a arentl to excessive ilot second-stage leakage in the valve's.

NOTARIZED DISTRfBUTION CODE> -8002 DISTR I BUT ION TI ~LE ).

INCIDENT REPORTS ENCLV FOR ACTION w/4 ENCL '

ORB 3 BC REG w/ENCL PDR <</Et4CL I L w/2 ENCL MIPC '8/3 ENCL I L C SYSTEMS SR W/F.NCL NOVAK/CHECK W/ENCL EEB <</ENCL AD FOR ENG l" /F.NCL

)

PLANT SYSTEMS BP w/I NCL HANAUFR <</ENCL

. AD FOR PLANT SYSTEMS w/ENCL

AD FOR SYS L PRDJ w/ENCL REACTOR SAFETY BR W/ENCL ENGINEERING BR W/ENCL KREGER/J,'OLL I>>S w/FNCL POHER SYS BR w/ENCL E. Jordan w/ENCL LPDR w/ENCL NSIC w/ENcL

'CRS W/i6

,

ENCL TOTAL NUMBER OF COPIES REQUIREDI LTR ENCL NOTES: HEAD TO HEAD

$ 0$ ] l Sl~

1978

TENNESSEE VALLEY AUTHORIT~

CHATTANOOGA. TENNESSEE 37401 November 8, 1978 tfkggtg(gP~f PP'%~'>O'a