ML18283B400: Difference between revisions
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{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM<RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC: OREILLY J P | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM <RIDS) | ||
NO COPIES RECEIVED | DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC: OREILLY J P ORG: FOX H S DOCDATE: 05/04/78 NRC TN VALLEY AUTH DATE RCVD: 05/ii/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED | ||
==SUBJECT:== | ==SUBJECT:== | ||
LTR i ENCL i FORWARDING LlCENSEE EVENT REPT (RO 50-296/78-0i0) | LTR i ENCL i FORWARDING LlCENSEE EVENT REPT (RO 50-296/78-0i0) ON 04/09/78 CONCERNING RBM CHANNELS BECAME CONTINUOUSLY BYPASSED... ALL ROD MOVEMENT WAS TERMINATED.... W/ATT. | ||
ON 04/09/78 CONCERNING RBM CHANNELS BECAME CONTINUOUSLY BYPASSED... | PLANT NAME:BROWNS FERRY UNIT 3 REVIEWER INITIAL: X JM DlSTRIBUTOR INITIAL:Q~ | ||
ALL ROD MOVEMENT WAS TERMINATED.... | DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002> | ||
W/ATT.PLANT NAME:BROWNS FERRY | FOR ACTION: BR CHIEF LEA . | ||
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002>FOR ACTION: | 0/4 ENCL INTERNAL: REG FILE++W/ENCL NRC PDR++W/ENCL E~4W/2 ENCL MIPC<4W/3 ENCL S ITO>+W/ENCL HOUSTON++W/ENCL NOVAK/CHECK4~W/ENCL EEB~+W/ENCL KNIGHTS +W/ENCL BUTLER~~~W/ENCL HANAUER~~~W/ENCL TEDESCO+4W/ENCL EISENHUT++W/ENCL BAER~~W/ENCL SHAO<+W/ENCL VOLLMER/BUNCHw+W/ENCL KREGER/J. COLLINS>~W/ENCL ROSA~~W/ENCL K SEYFRIT/IE+~~W/ENCL EXTERNAL: LPDR S ATHENS'L++W/ENCL TIC4+W/ENCL NSIC++W/ENCL ACRS CAT B++W/16 ENCL COPIES NOT SUBNITTED GUIDE 10 ' PEP.,'EGULATORY DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78i320020 8 I ZE: iP+ iP+ iP | ||
LTR 45 ENCL 45 8 I ZE: iP+iP+iP | %%4M%%%4 %%4M%%%%%%%%%0$ %44%%%03%%%4%% THE END 4 %%%%%%%4%%4%%%%%%%%%%%%%%%%%%%%%%% | ||
%44%%%03%%%4%% | |||
THE END 4%%%%%%%4%%4%%%%%%%%%%%%%%%%%%%%%%% | |||
==Dear Mr.O'Reilly:== | 4~, | ||
J Wa | |||
This report is submitted in accordance with Browns Perry unit 3 Technical Specification 6.7.2.a.(2). | |||
Very truly yours, TENNESSEE VALLEY AUTHORXTY H.S.Pox Director of.Power Production Enclosure (3)cc{Enclosure): | TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 37401 MN c '197S Itll,II@II(Ogrffl g~[ tropIr" Mr. James P. O'Reilly, Dirac r U.S. Nuclear Regulato Comnission Cp Office of Inspection and Enforcement C~ | ||
Director (3)Office of Management Information and Program Control U.S.Nuclear Regulatory Co ssion Washington, DC ,20555 Director (40)Office of Xnspection and Enforcement U.S.Nuclear Regulatory Commission Hashington, DC 20555 gng An Equal Opportunity Employer | r Region II r 230 Peach ree Street, m., Suite 1217 roc, ., | ||
I EP | CT Atlanta, Georgia 30303 >-c~~ | ||
~Cn~ ~ C7> | |||
'I~.4 | " | ||
There have been no revious | |||
COMPOh EN T TAKEN ACT ICrl O'I PLANT hlKTHOO HOURS QT2 SUSMITIK9 FOESM$VS.SUPPLIER 4ANVSAC'TVRKR ILISLLIS'LJS | ==Dear Mr. O'Reilly:== | ||
~TO~ZQ49 9 4 9 IP~USLICITY | |||
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-,296 - | |||
- BROGANS PERRY NUCLEAR FACILITY OPERATING LXCENSE OCCURRENCE REPORT BPRO-50-296/7810 | |||
Oi E I WE. | ~ | ||
REPORTABLE OCCURRENCE REPORT Report Number: BFRO<<'50-296/7810 Report Date: May 2, 1978 Occurrence Date: April 9, 1978 Facility Browns Ferry Nuclear Plant Unit 3 Identification of Occurrence Operator observation of RBM recorders downscale and RBM bypass lights on.Conditions Prior to Occurrence Normal operation at 77-percent power, during ascension to full load.Descri tion of Occurrence Both RBM channels became continuously bypassed.Review of potential reportable occurrence report revealed report should have been a prompt report as required by Technical Specification 6.7.2.a.(2). | MR Po UNQ3-REPORTABLC fV | ||
, Desi nation of A arent Cause of Occurrence Maintained voltage on edge rod selected bus.Misinterpretation of the technical specifications. | ~fC B | ||
Anal sis of Occurrence Contact 5-6 of rod select relay KXB for CRD 38-03 stuck closed.Corrective Action Replacement of defective relay.Discussed meaning of technical specification with plant staff.Failure Data No previous failures.JGD: SGS 5/A/78 4'e"<s U 3 f}} | Crs The enclosed report provides details concerning both RBM channels which became continttously bypassed during power ascension. This report is submitted in accordance with Browns Perry unit 3 Technical Specification 6.7.2.a.(2). | ||
Very truly yours, TENNESSEE VALLEY AUTHORXTY H. S. Pox Director of. Power Production Enclosure (3) cc {Enclosure): | |||
Director (3) | |||
Office of Management Information and Program Control U.S. Nuclear Regulatory Co ssion Washington, DC ,20555 Director (40) | |||
Office of Xnspection and Enforcement U.S. Nuclear Regulatory Commission Hashington, DC 20555 gng A' | |||
An Equal Opportunity Employer | |||
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.LICENSEE EVENT REPORT | |||
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'l0/5/77 "AOOfj%I <<I BFA85 EL N. SEUCLEAR REGULATORY COMMISSION EXHIBITA 0 | |||
~$ ''$ ~$ | |||
fl CONTROL SLOCKI (PLEASE PRINT OR TYtd ALLAEOUIREO INFORh'IATIONI 1 | |||
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I UAF $ 11 | |||
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CAPT | |||
"'.".:I LJS DOCKET IEVMSER IES 4& KYKNTOA'IS | |||
' 14 )S RCPORT DATE SP EVENT OESCAIPTION ANO PROBABLE CONSEQUENCES QIO | |||
~o 1 Durin ower ascension both RBM channels became'continuously bypassed. | |||
~o The RBM was not, o erable as s e'cified in technical d ecification 3.2.C.1 ~ | |||
~ o 'I | |||
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~o 4 U n discover all rod movement was terminated. There have been no revious to the discover of the malfunction all rod | |||
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~OG rescribed b nuclear en ineers core thermal | |||
~o f c t mar in to all thermal lim ts wer'e | |||
~Oe 1 r haz rd to ublic safet | |||
~i' 4 9 SYSTEM CAVSE CAUSE COMP VALVE CODE CODE SVSCODE COMPONENT CODE sUecood sUscoDE | |||
~09 uLJS 0 10 LOS II L<<S ll IS IS S LOS ILISI0 10 SEOVEri TIAL OCCURRENCE FIEPOAT REVISION | |||
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EVENT YEAR R EPOAT NO. CODE TYPE No t" | |||
Qli Ellioii ~rl 0 ~O1 0 ~~ QJ~1 ~$ ~0 I I~S 11 11 11 14 EF 14 19 SI 41 i ACFION FUTURE EFFECT sHUTD prrN ATTACHh'TNT IESRO4 PAIMECOMP. COMPOh EN T TAKEN ACT ICrl O'I PLANT hlKTHOO HOURS QT2 SUSMITIK9 FOESM $ VS. SUPPLIER 4ANVSAC'TVRKR ILISLLIS 'LJS I'-L<<-'E-'I IPIS LEIS I | |||
O-IS | |||
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E I IS CAUSE OESCAIPTION AND COAREC'FIVE ACTIONS QST I | |||
-03 P. Clare MR4MC-1023 | |||
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C d''28 on the ed e rod bus This condition e defective rela h func ional | |||
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T "00$ LOS 9 | |||
4 9 4 | |||
FACILITY STATUS 9 | |||
AC'IIVITY CONTENT RELEASED OF RELEASE | |||
~S~I 10 | |||
'4 POAEA 11 OTHER STATUS AMoUNTos ACTIVITYQSs | |||
~ | |||
44 hlETHOD OF DISCOVERY DISCOVERY<<oESCAIPTICN QS2 or bservation. | |||
LOCATIONOS AEL'EASE Q Lgl Qss ~zQ>4 N A N A T 4 0 HI 44 | |||
~ EASDNNKL EXPOSURES QP | |||
' | |||
NVMSER TYPE DESCRIPTION ~ | |||
9 4 9 LL9JO~zS IS 11 11 | |||
. N A | |||
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OO O 0 | |||
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*LE EO 11 N/A EEOILEEEQEE TYPE OKSCRIPTIOEI | |||
~TO ~ZQ49 N/A 9 4 9 IP | |||
~ USLICITY DKSCAIPTION Qds NRC USE ISSUED O ~(~4I N/A 4 0 IP 44 49 ONLY'HONE: | |||
kAME OF PAEPAREA | |||
*Revision. Oi E | |||
I WE. | |||
REPORTABLE OCCURRENCE REPORT Report Number : BFRO<<'50-296/7810 Report Date : May 2, 1978 Occurrence Date: April 9, 1978 Facility Browns Ferry Nuclear Plant Unit 3 Identification of Occurrence Operator observation of RBM recorders downscale and RBM bypass lights on. | |||
Conditions Prior to Occurrence Normal operation at 77-percent power, during ascension to full load. | |||
Descri tion of Occurrence Both RBM channels became continuously bypassed. Review of potential reportable occurrence report revealed report should have been a prompt report as required by Technical Specification 6.7.2.a.(2). | |||
, Desi nation of A arent Cause of Occurrence Maintained voltage on edge rod selected bus. Misinterpretation of the technical specifications. | |||
Anal sis of Occurrence Contact 5-6 of rod select relay KXB for CRD 38-03 stuck closed. | |||
Corrective Action Replacement of defective relay. Discussed meaning of technical specification with plant staff. | |||
Failure Data No previous failures. | |||
JGD: SGS 5/A/78 | |||
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Revision as of 13:49, 20 October 2019
ML18283B400 | |
Person / Time | |
---|---|
Site: | Browns Ferry ![]() |
Issue date: | 05/01/1978 |
From: | Fox H Tennessee Valley Authority |
To: | O'Reilly J NRC/IE, NRC/RGN-II |
References | |
LER 1978-010-00 | |
Download: ML18283B400 (8) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM <RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC: OREILLY J P ORG: FOX H S DOCDATE: 05/04/78 NRC TN VALLEY AUTH DATE RCVD: 05/ii/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR i ENCL i FORWARDING LlCENSEE EVENT REPT (RO 50-296/78-0i0) ON 04/09/78 CONCERNING RBM CHANNELS BECAME CONTINUOUSLY BYPASSED... ALL ROD MOVEMENT WAS TERMINATED.... W/ATT.
PLANT NAME:BROWNS FERRY UNIT 3 REVIEWER INITIAL: X JM DlSTRIBUTOR INITIAL:Q~
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002>
FOR ACTION: BR CHIEF LEA .
0/4 ENCL INTERNAL: REG FILE++W/ENCL NRC PDR++W/ENCL E~4W/2 ENCL MIPC<4W/3 ENCL S ITO>+W/ENCL HOUSTON++W/ENCL NOVAK/CHECK4~W/ENCL EEB~+W/ENCL KNIGHTS +W/ENCL BUTLER~~~W/ENCL HANAUER~~~W/ENCL TEDESCO+4W/ENCL EISENHUT++W/ENCL BAER~~W/ENCL SHAO<+W/ENCL VOLLMER/BUNCHw+W/ENCL KREGER/J. COLLINS>~W/ENCL ROSA~~W/ENCL K SEYFRIT/IE+~~W/ENCL EXTERNAL: LPDR S ATHENS'L++W/ENCL TIC4+W/ENCL NSIC++W/ENCL ACRS CAT B++W/16 ENCL COPIES NOT SUBNITTED GUIDE 10 ' PEP.,'EGULATORY DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78i320020 8 I ZE: iP+ iP+ iP
%%4M%%%4 %%4M%%%%%%%%%0$ %44%%%03%%%4%% THE END 4 %%%%%%%4%%4%%%%%%%%%%%%%%%%%%%%%%%
4~,
J Wa
TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 37401 MN c '197S Itll,II@II(Ogrffl g~[ tropIr" Mr. James P. O'Reilly, Dirac r U.S. Nuclear Regulato Comnission Cp Office of Inspection and Enforcement C~
r Region II r 230 Peach ree Street, m., Suite 1217 roc, .,
CT Atlanta, Georgia 30303 >-c~~
~Cn~ ~ C7>
"
Dear Mr. O'Reilly:
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-,296 -
- BROGANS PERRY NUCLEAR FACILITY OPERATING LXCENSE OCCURRENCE REPORT BPRO-50-296/7810
~
MR Po UNQ3-REPORTABLC fV
~fC B
Crs The enclosed report provides details concerning both RBM channels which became continttously bypassed during power ascension. This report is submitted in accordance with Browns Perry unit 3 Technical Specification 6.7.2.a.(2).
Very truly yours, TENNESSEE VALLEY AUTHORXTY H. S. Pox Director of. Power Production Enclosure (3) cc {Enclosure):
Director (3)
Office of Management Information and Program Control U.S. Nuclear Regulatory Co ssion Washington, DC ,20555 Director (40)
Office of Xnspection and Enforcement U.S. Nuclear Regulatory Commission Hashington, DC 20555 gng A'
An Equal Opportunity Employer
d
,d V I meg FC vd E
n v I 1
v<
Lf fll f
"'A il "CC" 4 I
pd (
f'
I I
'
v Jf I .K II I II J. .IL ~
d Cg ~
df ( 'f j 1 I"
v v
td C C
~ d,'
I EP ~
'."..
~,
~ -~
~
'
kAC SOAM SSE IP'TTI
' '.
I
-'
,
'.
.LICENSEE EVENT REPORT
"..': .
~
'l0/5/77 "AOOfj%I <<I BFA85 EL N. SEUCLEAR REGULATORY COMMISSION EXHIBITA 0
~$ $ ~$
fl CONTROL SLOCKI (PLEASE PRINT OR TYtd ALLAEOUIREO INFORh'IATIONI 1
P ~
'I ~ . 4 l;,
~ ~0 0 LICKNZKE CODE 14 1$ LICENSE NUMSKR LICENSE TYPE JO '
I UAF $ 11
$$
CAPT
"'.".:I LJS DOCKET IEVMSER IES 4& KYKNTOA'IS
' 14 )S RCPORT DATE SP EVENT OESCAIPTION ANO PROBABLE CONSEQUENCES QIO
~o 1 Durin ower ascension both RBM channels became'continuously bypassed.
~o The RBM was not, o erable as s e'cified in technical d ecification 3.2.C.1 ~
~ o 'I
~
I
~o 4 U n discover all rod movement was terminated. There have been no revious to the discover of the malfunction all rod
~ E
~OS r
~OG rescribed b nuclear en ineers core thermal
~o f c t mar in to all thermal lim ts wer'e
~Oe 1 r haz rd to ublic safet
~i' 4 9 SYSTEM CAVSE CAUSE COMP VALVE CODE CODE SVSCODE COMPONENT CODE sUecood sUscoDE
~09 uLJS 0 10 LOS II L<<S ll IS IS S LOS ILISI0 10 SEOVEri TIAL OCCURRENCE FIEPOAT REVISION
~
'I
~
~
EVENT YEAR R EPOAT NO. CODE TYPE No t"
Qli Ellioii ~rl 0 ~O1 0 ~~ QJ~1 ~$ ~0 I I~S 11 11 11 14 EF 14 19 SI 41 i ACFION FUTURE EFFECT sHUTD prrN ATTACHh'TNT IESRO4 PAIMECOMP. COMPOh EN T TAKEN ACT ICrl O'I PLANT hlKTHOO HOURS QT2 SUSMITIK9 FOESM $ VS. SUPPLIER 4ANVSAC'TVRKR ILISLLIS 'LJS I'-L<<-'E-'I IPIS LEIS I
O-IS
.~
E I IS CAUSE OESCAIPTION AND COAREC'FIVE ACTIONS QST I
-03 P. Clare MR4MC-1023
~
I o C ~
C d28 on the ed e rod bus This condition e defective rela h func ional
~4
,, ~
.
T "00$ LOS 9
4 9 4
FACILITY STATUS 9
AC'IIVITY CONTENT RELEASED OF RELEASE
~S~I 10
'4 POAEA 11 OTHER STATUS AMoUNTos ACTIVITYQSs
~
44 hlETHOD OF DISCOVERY DISCOVERY<<oESCAIPTICN QS2 or bservation.
LOCATIONOS AEL'EASE Q Lgl Qss ~zQ>4 N A N A T 4 0 HI 44
~ EASDNNKL EXPOSURES QP
'
NVMSER TYPE DESCRIPTION ~
9 4 9 LL9JO~zS IS 11 11
. N A
"
ll SO PERSONNEL ItIJURIKS I fiij 9 4 0 L<<EO 0
OO O 0
11 Qio
- LE EO 11 N/A EEOILEEEQEE TYPE OKSCRIPTIOEI
~TO ~ZQ49 N/A 9 4 9 IP
~ USLICITY DKSCAIPTION Qds NRC USE ISSUED O ~(~4I N/A 4 0 IP 44 49 ONLY'HONE:
kAME OF PAEPAREA
- Revision. Oi E
I WE.
REPORTABLE OCCURRENCE REPORT Report Number : BFRO<<'50-296/7810 Report Date : May 2, 1978 Occurrence Date: April 9, 1978 Facility Browns Ferry Nuclear Plant Unit 3 Identification of Occurrence Operator observation of RBM recorders downscale and RBM bypass lights on.
Conditions Prior to Occurrence Normal operation at 77-percent power, during ascension to full load.
Descri tion of Occurrence Both RBM channels became continuously bypassed. Review of potential reportable occurrence report revealed report should have been a prompt report as required by Technical Specification 6.7.2.a.(2).
, Desi nation of A arent Cause of Occurrence Maintained voltage on edge rod selected bus. Misinterpretation of the technical specifications.
Anal sis of Occurrence Contact 5-6 of rod select relay KXB for CRD 38-03 stuck closed.
Corrective Action Replacement of defective relay. Discussed meaning of technical specification with plant staff.
Failure Data No previous failures.
JGD: SGS 5/A/78
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