ML19249A529: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(StriderTol Bot change)
 
(2 intermediate revisions by the same user not shown)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:U. S. NUCLE AR REGUL ATORY COMMISSION NRC F ORM 36G (7-7 7)
LICENSEE EVENT REPORT CONTROL DLOCK: l                  l    l    l      l    l      I                  (PLEASE PRINT OR ".YPE ALL REQUIRED INFORMATION) 1                                      6 l0 l1l l0 l H j D l B l S                            1 @l 0l 0l -l 0 0lN lP lD l-l013l@l4 l1l1 Il l1 l@l                    23      26        LICEN50 T yP; JO l
                                                                                                                                                                      $ / t. A T 58 l@
7          8 9              LICENSEE C09E              14    15                        LICE N3E NuMt1E H CON'T 7
lol1l 7          8
[n"c l L l@l 0 [ 5COCKET b>            61 l 0 l-      l 0 l 3 l 4 l 6 l@l NUVBEH              M    b1            0DATE ENENT  l 7 l 2 l2 l 7 l 9 @[0 l 8 l 1 l 7 l 7 l 9 14      75      REPORT D ATE            HJ EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o      2 l Af ter tripping and being reset several times, Containment Post-Accident Radiation Monii o    a      ] tor RE 5030 was declared inoperable at 0430 hours on 7/23/79. This placed the unit inl Th_re was no danger to the health and safety of l o 4          Ithe Action Statement of T.S. 3.3.3.6.
lo Is! I the public or station personnel. RE 5030 does not control any equipment but is used                                                                                                l o    G      l for conitoring purposes only. The redundant monitor, RE 5029, was operable during thel l o j i j l periods that RE 5030 was inoperable.                                                  (NP-33-79-98)                                                                            l I
o    a i                                                                                                                                                                              60 SYSTEM            CAUSE            CAUSE                                                        COVP.          VALVE CODE              CODE          SUSCODE                  COYPONENT CODE                    SU8 CODE        SUBCODE 1o191                                  I n l a l@ LLi@ Lal@ I r l u l M I P xixl@
12            13                            18            13 a l@ W @      20 8                        9          10          11 7
OCCU R R E N CE          REPORT                    REVISION SE QUENTI AL E                                          REPORT NO.                            CODE                  TYPE                          N O.
LER RO
                    @ gg              ,_lVE  7 9l  NT Y E[---      A jR          j0 8l5                  y            ldl3l 28        29 l3JLl        l-31 l0 l 32
                                      .,, 21        22          23              24            26        27 HOURS            SUB ITT O        FOR                S PLIE              VAN      A T RER TAKE      A TC              O PLA T                  Ti l^ l@l Flg 33          34
[35Zjg
_            l30 Zl@            l 0l 0l 0l 0l y@
31                  40  41 l42Y l@            lA @ lVl1]1l5l@
43            44                  47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS ji      o      ]The cause of this occurrence was component failure. The motor was drawing excessivo                                                                                        I i i          [ current and tripping                          on overload because of a loss of Iubrication of the pump bear- 1 y,,,,lings due to high ambient temperature. The pump was replaced with a rebuilt pump, l i l 3 l l RE 5030 surveillance tested and declared operable at 0600 hours on 7/23/79.                                                                                    Improved l
        , 4          gpump bearings with high temperature lubricant will be installed under M"O 70-159A.                                                                                    80 7          8 9 STA S                % POWER                        OTHER STATUS                DtSCO R                                  DISCOVERY DESCRIPTION i    s      (E_j@ lll0l0 @                                NA                            l    l A l@l Operator observation                                                            l ACTIVITY CO TENT RE LE ASEC, OF RE LC ASE                    AMOUNT OF ACTIVITY                                                          LOCATION OF RELE ASE 7
i G 8 9 W h d@l        10          11 NA 44 l          l 45 NA 80 PE RSONNEL E MPO5URES NU9HER              TYPE        DESCHIPTION i 7          1010 l o j@[zj@l NA                                                                                                                                                    "
l PERSONNE t N;uW,ES NuvaE n            DESCR. riON@                                                                                                          ..
                                                                                                                                                                / (#IZ NA                                                                                                                                          l li ls l8 l9 0 l 0 l 0 l@l 7                              11      12                                                                                                                                            80 T l'E        s'C"'A'l ''''"" @                                                                79082305M                                                                  l i o          [ z_j@          NA 8 9              10                                                                                                                                                          80 7
evotic'                                                                                                                                  NRC USE ONLY                  .
7 2 o 8 9
[d@loEYCniPTiON 10 m                                              @                                                                l 68 69 l      ll1ltll1 83 5
                                                                                                                                                                                                  ]
419-259-5000, Ext. 292 DVR 79-119                      NAME OF PREPARER                    Craic E. Jensen                                                    PHONE:                                                    {
 
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-98 DATE OF EVENT: July 22, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:    Containment Post-Accident Radiation Monitor RE 5030 was inoperable Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MWT) = 2755, and Load (Gros MWE) = 908.
Description of Occurrence: At 1610 hours on July 22, 1979, the Post-Accident Radia-tion Monitor RE 5030 was found to be off as the overloads on the motor were tripped.
The overloads were reset and pump restarted at 1650 hours. After tripping repeatedly, RE 5030 was declared inoperable at 0430 hours on July 23, 1979.
This placed the unit in the action statement of Technical Specification 3.3.3.6 which requires that two post-accident containment monitoring systems be operable in Modes 1, 2, or 3. The action statement requires that the inoperable radiation moni-tor be returned to service within 30 days or the unit must be placed in hot shutdown (Mode 4) within the next 12 hours.
Designation of Apparent Cause of Occurrence: Upon disassembly of the f ailed pump, it was discovered the failure was caused by the bearing losing lubrication due to high ambient temperature and severe service conditions.
Analysis of Occurrence:  There was no danger to the health and safety of the public or to station personnel. This instrument does not control any equipment but is used for monitoring purposes only. No other systems were affected by this occurrence.
No incident requiring use of this instrumentation occurred during the time the moni-tor was inoperable. The other containment post-accident radiation monitor, RE 5029, was operable during the periods that RE 5030 was inoperable.
Corrective Action:  Under Maintenance Work Order 79-1906, the pump was replaced on RE 5030 with a rebuilt pump. On July 23, 1979 at 0600 hourc, Surveillance Test ST 5032.01, " Monthly Functional Test of Radiation Monitoring System" was completed and RE 5030 was declared operable, removing the unit from the action statement of Technical Specification 3.3.3.6.
Improvea pump oearings witu nign temperature rated luoricant will oe installed per Maintenance Work Order 78-159A. Facility Change Request 78-521 has been written to reduce pump speed in order to decrease the load on the pump bearings. A preventa-tive maintenance program has been established for these radiation monitor pumps.
LER #79-085                                                              *g/gjy
 
TOLEDO EDISON COfiPANY DA\ IS-BESSE NUCLEAR POWER STATT.0N U'IIT ONE PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-33-79-98 Failure Data: This is a repetitive failure. Previous pump related problems with the radiation monitors have been reported in Licensee Event Reports NP-33-78-30, NP-33-78-45, NP-33-78-54, NP-33-78-77, NP-33-79-37, NP-33-79-42, NP-33-79-95, and NP-33-79-96.
LER #79-085 YSl5sTj"l}}

Latest revision as of 10:29, 22 February 2020

LER 79-085/03L-0 on 790722:containment post-accident Radiation Monitor Declared Inoperable.Caused by Component Failure.Pump Replaced W/Rebuilt Pump,Surveillance Tested & Declared Operable
ML19249A529
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 08/17/1979
From: Jensen C
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19249A526 List:
References
LER-79-085-03L, LER-79-85-3L, NUDOCS 7908230529
Download: ML19249A529 (3)


Text

U. S. NUCLE AR REGUL ATORY COMMISSION NRC F ORM 36G (7-7 7)

LICENSEE EVENT REPORT CONTROL DLOCK: l l l l l l I (PLEASE PRINT OR ".YPE ALL REQUIRED INFORMATION) 1 6 l0 l1l l0 l H j D l B l S 1 @l 0l 0l -l 0 0lN lP lD l-l013l@l4 l1l1 Il l1 l@l 23 26 LICEN50 T yP; JO l

$ / t. A T 58 l@

7 8 9 LICENSEE C09E 14 15 LICE N3E NuMt1E H CON'T 7

lol1l 7 8

[n"c l L l@l 0 [ 5COCKET b> 61 l 0 l- l 0 l 3 l 4 l 6 l@l NUVBEH M b1 0DATE ENENT l 7 l 2 l2 l 7 l 9 @[0 l 8 l 1 l 7 l 7 l 9 14 75 REPORT D ATE HJ EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l Af ter tripping and being reset several times, Containment Post-Accident Radiation Monii o a ] tor RE 5030 was declared inoperable at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on 7/23/79. This placed the unit inl Th_re was no danger to the health and safety of l o 4 Ithe Action Statement of T.S. 3.3.3.6.

lo Is! I the public or station personnel. RE 5030 does not control any equipment but is used l o G l for conitoring purposes only. The redundant monitor, RE 5029, was operable during thel l o j i j l periods that RE 5030 was inoperable. (NP-33-79-98) l I

o a i 60 SYSTEM CAUSE CAUSE COVP. VALVE CODE CODE SUSCODE COYPONENT CODE SU8 CODE SUBCODE 1o191 I n l a l@ LLi@ Lal@ I r l u l M I P xixl@

12 13 18 13 a l@ W @ 20 8 9 10 11 7

OCCU R R E N CE REPORT REVISION SE QUENTI AL E REPORT NO. CODE TYPE N O.

LER RO

@ gg ,_lVE 7 9l NT Y E[--- A jR j0 8l5 y ldl3l 28 29 l3JLl l-31 l0 l 32

.,, 21 22 23 24 26 27 HOURS SUB ITT O FOR S PLIE VAN A T RER TAKE A TC O PLA T Ti l^ l@l Flg 33 34

[35Zjg

_ l30 Zl@ l 0l 0l 0l 0l y@

31 40 41 l42Y l@ lA @ lVl1]1l5l@

43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS ji o ]The cause of this occurrence was component failure. The motor was drawing excessivo I i i [ current and tripping on overload because of a loss of Iubrication of the pump bear- 1 y,,,,lings due to high ambient temperature. The pump was replaced with a rebuilt pump, l i l 3 l l RE 5030 surveillance tested and declared operable at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on 7/23/79. Improved l

, 4 gpump bearings with high temperature lubricant will be installed under M"O 70-159A. 80 7 8 9 STA S  % POWER OTHER STATUS DtSCO R DISCOVERY DESCRIPTION i s (E_j@ lll0l0 @ NA l l A l@l Operator observation l ACTIVITY CO TENT RE LE ASEC, OF RE LC ASE AMOUNT OF ACTIVITY LOCATION OF RELE ASE 7

i G 8 9 W h d@l 10 11 NA 44 l l 45 NA 80 PE RSONNEL E MPO5URES NU9HER TYPE DESCHIPTION i 7 1010 l o j@[zj@l NA "

l PERSONNE t N;uW,ES NuvaE n DESCR. riON@ ..

/ (#IZ NA l li ls l8 l9 0 l 0 l 0 l@l 7 11 12 80 T l'E s'C"'A'l '"" @ 79082305M l i o [ z_j@ NA 8 9 10 80 7

evotic' NRC USE ONLY .

7 2 o 8 9

[d@loEYCniPTiON 10 m @ l 68 69 l ll1ltll1 83 5

]

419-259-5000, Ext. 292 DVR 79-119 NAME OF PREPARER Craic E. Jensen PHONE: {

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-98 DATE OF EVENT: July 22, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Containment Post-Accident Radiation Monitor RE 5030 was inoperable Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MWT) = 2755, and Load (Gros MWE) = 908.

Description of Occurrence: At 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br /> on July 22, 1979, the Post-Accident Radia-tion Monitor RE 5030 was found to be off as the overloads on the motor were tripped.

The overloads were reset and pump restarted at 1650 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.27825e-4 months <br />. After tripping repeatedly, RE 5030 was declared inoperable at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on July 23, 1979.

This placed the unit in the action statement of Technical Specification 3.3.3.6 which requires that two post-accident containment monitoring systems be operable in Modes 1, 2, or 3. The action statement requires that the inoperable radiation moni-tor be returned to service within 30 days or the unit must be placed in hot shutdown (Mode 4) within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Designation of Apparent Cause of Occurrence: Upon disassembly of the f ailed pump, it was discovered the failure was caused by the bearing losing lubrication due to high ambient temperature and severe service conditions.

Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. This instrument does not control any equipment but is used for monitoring purposes only. No other systems were affected by this occurrence.

No incident requiring use of this instrumentation occurred during the time the moni-tor was inoperable. The other containment post-accident radiation monitor, RE 5029, was operable during the periods that RE 5030 was inoperable.

Corrective Action: Under Maintenance Work Order 79-1906, the pump was replaced on RE 5030 with a rebuilt pump. On July 23, 1979 at 0600 hourc, Surveillance Test ST 5032.01, " Monthly Functional Test of Radiation Monitoring System" was completed and RE 5030 was declared operable, removing the unit from the action statement of Technical Specification 3.3.3.6.

Improvea pump oearings witu nign temperature rated luoricant will oe installed per Maintenance Work Order 78-159A. Facility Change Request 78-521 has been written to reduce pump speed in order to decrease the load on the pump bearings. A preventa-tive maintenance program has been established for these radiation monitor pumps.

LER #79-085 *g/gjy

TOLEDO EDISON COfiPANY DA\ IS-BESSE NUCLEAR POWER STATT.0N U'IIT ONE PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-33-79-98 Failure Data: This is a repetitive failure. Previous pump related problems with the radiation monitors have been reported in Licensee Event Reports NP-33-78-30, NP-33-78-45, NP-33-78-54, NP-33-78-77, NP-33-79-37, NP-33-79-42, NP-33-79-95, and NP-33-79-96.

LER #79-085 YSl5sTj"l