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         .V                                                                _ LICENSEE EVENT REPORT (Pt. EASE PRINT OR TYPE A . REQUIRED INFORMATIONI CONTROL BLOCK: l l    l    l      l  ,
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l i { o l l The cause of this occurrence is both procedure error and personnel error.
l i { o l l The cause of this occurrence is both procedure error and personnel error.
     ;i ;i i l Startup Procedure, PP 1102.02, was modified to assure two containment air coolers                                                                                          t
     ;i ;i i l Startup Procedure, PP 1102.02, was modified to assure two containment air coolers                                                                                          t
     ,,,7,      l are in operation during startup. Operators will be instructed to notify the Shift                                                                                      l g,;3; l Foreman when operational parameters approach their limits.                                                                                                                    l
     ,,,7,      l are in operation during startup. Operators will be instructed to notify the Shift                                                                                      l g,;3; l Foreman when operational parameters approach their limits.                                                                                                                    l I i I 4-1 l                                                                                                                                                                      so 7      8 7
                                                                                                                                                                                          !
I i I 4-1 l                                                                                                                                                                      so 7      8 7
                                       *LPCWER                        OTHER STATUS              CIS          RY                            OIScoVERY DESCRIPTION
                                       *LPCWER                        OTHER STATUS              CIS          RY                            OIScoVERY DESCRIPTION
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ACTIVtTY CCNTENT AMOUNT OF ACTIVITY                                                          LOCATION OF RELEASE RELEASED CP RELE ASE I1 I6 l l Z l h Jgl NA                                                                l              l NA                                                                        30 l
ACTIVtTY CCNTENT AMOUNT OF ACTIVITY                                                          LOCATION OF RELEASE RELEASED CP RELE ASE I1 I6 l l Z l h Jgl NA                                                                l              l NA                                                                        30 l
44                45 7      a 9                to          ti PERSONNEL EXPOSLRES NUV8ER              TY8E          *:E SCmPTION 4
44                45 7      a 9                to          ti PERSONNEL EXPOSLRES NUV8ER              TY8E          *:E SCmPTION 4 t i l 71 1010101@l Z l@l NA                                                                                                                                                      5*
                                                                                                                                                                                        !
     '      ' '      ,ERSO~N A'iNJ ES NUvsER              cESCRiariesh                                                                                                                                  l fiTTl4 1010101@l 7          3                11      12 NA                                                                                                                                        30 LOSS CP CA DAVACE To F ACILtTV TYPE        CESCRl8 tion I
t i l 71 1010101@l Z l@l NA                                                                                                                                                      5*
     '      ' '      ,ERSO~N A'iNJ ES
                                                        ''
NUvsER              cESCRiariesh                                                                                                                                  l fiTTl4 1010101@l 7          3                11      12 NA                                                                                                                                        30 LOSS CP CA DAVACE To F ACILtTV TYPE        CESCRl8 tion I
I Z l@l iQNA                                                                                                                                                        aa 7      a 9                                                                                  -
I Z l@l iQNA                                                                                                                                                        aa 7      a 9                                                                                  -
                       'us uciTv                                                                                                                                    NRC USE CNLY            '
                       'us uciTv                                                                                                                                    NRC USE CNLY            '
Line 56: Line 48:
* 8 0 0 +* O 4 073I                                    l    ll ll1llIIIi'I I
* 8 0 0 +* O 4 073I                                    l    ll ll1llIIIi'I I
                                                                                                                                       .              68 69                            s J. 4 i      M 3            10 John Johnson                                                                      419-259-5000. Ext. 277 M 142-1                  w,..te..ng.angg
                                                                                                                                       .              68 69                            s J. 4 i      M 3            10 John Johnson                                                                      419-259-5000. Ext. 277 M 142-1                  w,..te..ng.angg
                                    .
_
                                                                                                                                         ,ggy,
                                                                                                                                         ,ggy,


            -
p                                            TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR LER NP-33-77-81 DATE OF. EVENT: .0ctober 18, 1977
    -                                          .
_        FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF GCCURRENCE: . Exceeding allowed containment to. annulus differential pressure on startup.
              ,
                                                                    .
p                                            TOLEDO EDISON COMPANY
  -
DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR LER NP-33-77-81
                            .
                                                                        '
DATE OF. EVENT: .0ctober 18, 1977
_        FACILITY: Davis-Besse Unit 1
,    .
IDENTIFICATION OF GCCURRENCE: . Exceeding allowed containment to. annulus differential pressure on startup.
Conditions Prior to Occurrence: The plant was in Mode 1, with Power (MWT) = 250, and Load (MWE) = 0.
Conditions Prior to Occurrence: The plant was in Mode 1, with Power (MWT) = 250, and Load (MWE) = 0.
4 Description of Occurrence: At 0745 hours on October 18, 1977, during the routine performance of ST 5099.01, " Miscellaneous Instrument Shift Checks", it was dis-covered that containment to annulus differential pressure exceeded the Technical Specification limit of +25 inches water gauge by two inches water gauge. This placed the station in the Action Statement of Technical Specification 3.6.1.4.
4 Description of Occurrence: At 0745 hours on October 18, 1977, during the routine performance of ST 5099.01, " Miscellaneous Instrument Shift Checks", it was dis-covered that containment to annulus differential pressure exceeded the Technical Specification limit of +25 inches water gauge by two inches water gauge. This placed the station in the Action Statement of Technical Specification 3.6.1.4.
Line 78: Line 57:
           - g pressure. At 0815 hours on October 18, 1977, containment to annulus differential g
           - g pressure. At 0815 hours on October 18, 1977, containment to annulus differential g
pressure was below +25 inches water gauge which removed the station from the Action N- / Statement of Technical Specification 3.6.1.4.
pressure was below +25 inches water gauge which removed the station from the Action N- / Statement of Technical Specification 3.6.1.4.
,
Designation of Apparent Cause of Occurrence: The cause of this occurrence is both procedure error and personnel error.
Designation of Apparent Cause of Occurrence: The cause of this occurrence is both
,
procedure error and personnel error.
During startup of the reactor, only one containment air cooler was on. " Plant Startup Procedure", PP 1102.02, does not require two containment air coolers be turned-on during startup as required by SP 1104.08, " Containment Air Cooling Pro-cedure".
During startup of the reactor, only one containment air cooler was on. " Plant Startup Procedure", PP 1102.02, does not require two containment air coolers be turned-on during startup as required by SP 1104.08, " Containment Air Cooling Pro-cedure".
TheMiscellaneousInstrument5h'iftCheck'shouldhavealerted'theoperatorofthe
TheMiscellaneousInstrument5h'iftCheck'shouldhavealerted'theoperatorofthe
                          '                        '
                                             ~
                                             ~
increasing containment pressure due to a startup and appropriate action should have been taken to prevent exceeding the allowed pressure.
increasing containment pressure due to a startup and appropriate action should have been taken to prevent exceeding the allowed pressure.
Analysis of Occurrence: There was no threat to the health and safety of the public or to station personnel. Ihe slight increase.above the Technical Specification limit would not cause containment internal pressure to exceed the design pressure of 40 PSIG during loss of coolant accident condition.
Analysis of Occurrence: There was no threat to the health and safety of the public or to station personnel. Ihe slight increase.above the Technical Specification limit would not cause containment internal pressure to exceed the design pressure of 40 PSIG during loss of coolant accident condition.
                                                .                      .      .        --
U                                                          .
U                                                          .
!
l l'                            .-                        . . - -    . . - . _  . - - -
l l'                            .-                        . . - -    . . - . _  . - - -
                                                                                                -    _ _ _ _


    .
TOLEDO EDISON COMPANY
                                  ,
   - 9 AVIS-BESSE NUCLEAR PC'4ER STATION UNIT ONE UPPLEMENTAL INFORMATION FOR LER NP-33-77-81                          PAGE 2 Corrective Action: At 0800 hours on October 18, 1977, all containment air coolers were started. By 0815 hours, containment pressure was below Technical Specifica-tion limits and the station was removed from the Action Statement of Technical Specification 3.6.1.4.
        .
                                                                                      .
* TOLEDO EDISON COMPANY
   - 9 AVIS-BESSE NUCLEAR PC'4ER STATION UNIT ONE UPPLEMENTAL INFORMATION FOR LER NP-33-77-81                          PAGE 2
_
Corrective Action: At 0800 hours on October 18, 1977, all containment air coolers were started. By 0815 hours, containment pressure was below Technical Specifica-tion limits and the station was removed from the Action Statement of Technical Specification 3.6.1.4.
Plant Startup Procedure...PP 1102.02, was modified to assure two containment air coolers are in operation during startup. This should prevent the startup heating of containment from exceeding the allowed containment pressure. Operators will be instructed to notify the Shift Foreman when operational parameters approach their limits.
Plant Startup Procedure...PP 1102.02, was modified to assure two containment air coolers are in operation during startup. This should prevent the startup heating of containment from exceeding the allowed containment pressure. Operators will be instructed to notify the Shift Foreman when operational parameters approach their limits.
Failure Data: No previous similar events have occurred.
Failure Data: No previous similar events have occurred.
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Latest revision as of 01:15, 1 February 2020

LER 77-081/03L-0:on 771018,during Miscellaneous Instrument Shift Checks,Containment to Annulus Differential Pressure Exceeded Water Gauge Tech Spec Limit.Caused by Procedure & Personnel Error.Startup Procedure Modified
ML19326A566
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 11/14/1977
From: Jerrica Johnson
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19326A507 List:
References
LER-77-081-03L, LER-77-81-3L, NUDOCS 8002040738
Download: ML19326A566 (3)


Text

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.V _ LICENSEE EVENT REPORT (Pt. EASE PRINT OR TYPE A . REQUIRED INFORMATIONI CONTROL BLOCK: l l l l l ,

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57 car sa l@

T UCENSEE Co0E CON' 10111 7 8 EUE lL @lOl5l0l-J0l3l4l6 @l110J1l81717 @l1l1l114l717l@

60 61 CoCKET NUM8ER 68 69 EVENT OATE 74 75 REPORT DATE do EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h IoI2; l At 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br /> on October 18, 1977, during the routine performance of ST 5099.01, l l

ITTil 1 " Miscellaneous Instrument Shif t Checks", it was discovered that contain=ent to l o ,4 l l annulus' differential pressure exceeded the Technical Specification limit of +25 l 1o;3; ; inches water gauge by two inches water gauge. This placed the station in the Action [

lo is 1 l Statement of Technical Specification 3.6.1.4. (NF-33-77-81)  ;

l 10171 l I

~1 o t s i I 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUSCQOE COMPONENT CODE SusCCCE SU8CocE loisl ISlAl@ lDlh IZih lVjElSlSlElLj@ g @ lZl@

9 10 11 12 13 is 19 20 7 8 REVISION SEQUENTIAL OCCU R R E NCE REPORT REPORT No. CCCE TYPE N .

_. EVENT YE A R L

@ ,a'ER/RoI7I71 uE l---I I Ol 8l ll I'I 10I3I I 'l 30 l-'- I 31 I

32 I

21 22 23 24 26 27 28 29 HOURS 22 SS i FC 8. SUP LIE MAN PA TURE K A O P NT .1 E I l l l i  !  !

37 40 el 42 Q M 47 M 4 45 40 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h Plant  ;

l i { o l l The cause of this occurrence is both procedure error and personnel error.

i ;i i l Startup Procedure, PP 1102.02, was modified to assure two containment air coolers t

,,,7, l are in operation during startup. Operators will be instructed to notify the Shift l g,;3; l Foreman when operational parameters approach their limits. l I i I 4-1 l so 7 8 7

  • LPCWER OTHER STATUS CIS RY OIScoVERY DESCRIPTION

$A y W @ l 0] 0l 9l @ l NA [ lBlgl Surveillance Testing [

ACTIVtTY CCNTENT AMOUNT OF ACTIVITY LOCATION OF RELEASE RELEASED CP RELE ASE I1 I6 l l Z l h Jgl NA l l NA 30 l

44 45 7 a 9 to ti PERSONNEL EXPOSLRES NUV8ER TY8E *:E SCmPTION 4 t i l 71 1010101@l Z l@l NA 5*

' ' ' ,ERSO~N A'iNJ ES NUvsER cESCRiariesh l fiTTl4 1010101@l 7 3 11 12 NA 30 LOSS CP CA DAVACE To F ACILtTV TYPE CESCRl8 tion I

I Z l@l iQNA aa 7 a 9 -

'us uciTv NRC USE CNLY '

l0Ioj [_N_ji$$UED@DESCf118flON l NA

  • 8 0 0 +* O 4 073I l ll ll1llIIIi'I I

. 68 69 s J. 4 i M 3 10 John Johnson 419-259-5000. Ext. 277 M 142-1 w,..te..ng.angg

,ggy,

p TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR LER NP-33-77-81 DATE OF. EVENT: .0ctober 18, 1977

_ FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF GCCURRENCE: . Exceeding allowed containment to. annulus differential pressure on startup.

Conditions Prior to Occurrence: The plant was in Mode 1, with Power (MWT) = 250, and Load (MWE) = 0.

4 Description of Occurrence: At 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br /> on October 18, 1977, during the routine performance of ST 5099.01, " Miscellaneous Instrument Shift Checks", it was dis-covered that containment to annulus differential pressure exceeded the Technical Specification limit of +25 inches water gauge by two inches water gauge. This placed the station in the Action Statement of Technical Specification 3.6.1.4.

All dontainment air coolers were turned on at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> to reduce temperature and

- g pressure. At 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> on October 18, 1977, containment to annulus differential g

pressure was below +25 inches water gauge which removed the station from the Action N- / Statement of Technical Specification 3.6.1.4.

Designation of Apparent Cause of Occurrence: The cause of this occurrence is both procedure error and personnel error.

During startup of the reactor, only one containment air cooler was on. " Plant Startup Procedure", PP 1102.02, does not require two containment air coolers be turned-on during startup as required by SP 1104.08, " Containment Air Cooling Pro-cedure".

TheMiscellaneousInstrument5h'iftCheck'shouldhavealerted'theoperatorofthe

~

increasing containment pressure due to a startup and appropriate action should have been taken to prevent exceeding the allowed pressure.

Analysis of Occurrence: There was no threat to the health and safety of the public or to station personnel. Ihe slight increase.above the Technical Specification limit would not cause containment internal pressure to exceed the design pressure of 40 PSIG during loss of coolant accident condition.

U .

l l' .- . . - - . . - . _ . - - -

TOLEDO EDISON COMPANY

- 9 AVIS-BESSE NUCLEAR PC'4ER STATION UNIT ONE UPPLEMENTAL INFORMATION FOR LER NP-33-77-81 PAGE 2 Corrective Action: At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on October 18, 1977, all containment air coolers were started. By 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />, containment pressure was below Technical Specifica-tion limits and the station was removed from the Action Statement of Technical Specification 3.6.1.4.

Plant Startup Procedure...PP 1102.02, was modified to assure two containment air coolers are in operation during startup. This should prevent the startup heating of containment from exceeding the allowed containment pressure. Operators will be instructed to notify the Shift Foreman when operational parameters approach their limits.

Failure Data: No previous similar events have occurred.

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