ML19351F631: Difference between revisions
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' CONTROL BLOCK: ! l l l l l 6 | ' CONTROL BLOCK: ! l l l l l 6 | ||
lh (PLEASE PRINT G3 TYPE ALL f,EOUl%E3 INPDRMATION) | lh (PLEASE PRINT G3 TYPE ALL f,EOUl%E3 INPDRMATION) | ||
{'o I'il8 9l l l LUCENSEE lQlA CooE l0l2 14 l@l IS 0 l 0 l 0 l -UCENsE l 0 INVMBER O l 0 l - l 0 l 025l 0 26l@l kl II Il TYPE LICENSE 1l 1l@l JG l | {'o I'il8 9l l l LUCENSEE lQlA CooE l0l2 14 l@l IS 0 l 0 l 0 l -UCENsE l 0 INVMBER O l 0 l - l 0 l 025l 0 26l@l kl II Il TYPE LICENSE 1l 1l@l JG l | ||
SF CAT $4 l@ | SF CAT $4 l@ | ||
Line 31: | Line 30: | ||
Lo l 8_J l - 80 7 as # | Lo l 8_J l - 80 7 as # | ||
*CEo'E | *CEo'E | ||
"*il s 's$'E Co CoucoNENT Coot s eS"o'ot su"NYoE TITl 7 8 Ic IF l h W h W h IP IU lM lP IX IX lh Wh [J.] h 9 to 11 12 33 18 19 20 | |||
"*il s 's$'E Co | |||
,,, st outNTI AL uCCuRRENCE REPORT Revision EVENT YEAR REPORT No. CooE TYPE No. | ,,, st outNTI AL uCCuRRENCE REPORT Revision EVENT YEAR REPORT No. CooE TYPE No. | ||
LER!Ro | LER!Ro | ||
@ ,at u g I 8101 l23_J 101317 l 1.r] 10131 It I l-l [0.J v .,,2 8 22 24 26 27 28 29 30 31 32 | @ ,at u g I 8101 l23_J 101317 l 1.r] 10131 It I l-l [0.J v .,,2 8 22 24 26 27 28 29 30 31 32 MAN F RER E AC o oN T ME MouRs h 5 e i FoM S. Su L W L2J@ l352.J@ L2 j@ l 0101 0101 l_11@ LLIO I nl@ lBl2I610Ig 33 34 36 37 40 41 42 43 44 47 CAUSE OESCRIPTION ANo CORRECTIVE ACTIONS h The enute of the ceal 1.alcace was nnemal waar nf the 0-Rino tea 11no curface. I liloll i i l The mechanical seal was replaced. The 20 RHR pump was returned to service and i g !. tes.ted satisfactorily on December 8,19fC . I 1 3 l I | ||
MAN F RER E AC o oN T ME MouRs h 5 e i FoM S. Su L W L2J@ l352.J@ L2 j@ l 0101 0101 l_11@ LLIO I nl@ lBl2I610Ig 33 34 36 37 40 41 42 43 44 47 CAUSE OESCRIPTION ANo CORRECTIVE ACTIONS h The enute of the ceal 1.alcace was nnemal waar nf the 0-Rino tea 11no curface. I liloll i i l The mechanical seal was replaced. The 20 RHR pump was returned to service and i g !. tes.ted satisfactorily on December 8,19fC . I | |||
1 3 l I | |||
( , | ( , | ||
i A | i A I | ||
I | |||
'sYE8 snowtR oTwEnsTATus @5'sEoSS0v' oisCovERv oEsCRirrioN @ | 'sYE8 snowtR oTwEnsTATus @5'sEoSS0v' oisCovERv oEsCRirrioN @ | ||
W W@ l 01010 ' @l" 1 NA . | W W@ l 01010 ' @l" 1 NA . | ||
l W @l Operational Event l | l W @l Operational Event l | ||
* AETiviTv Co'0 TENT LOCATION oF RELEASE @ | * AETiviTv Co'0 TENT LOCATION oF RELEASE @ | ||
1 6 r.EtEAsEo@of RELEASE AMOUNT NA | 1 6 r.EtEAsEo@of RELEASE AMOUNT NA | ||
@loF" ACTIVITY l | @loF" ACTIVITY l NA @ l l | ||
NA @ l | |||
l | |||
eERsoNNEL Exposures NuM8ER TYPE oEsCRIPT1oM L'_W l 01010 !@l zj@l u " | eERsoNNEL Exposures NuM8ER TYPE oEsCRIPT1oM L'_W l 01010 !@l zj@l u " | ||
I | I | ||
' ' ' ,ERso~~E!'iN;u'4 Es | ' ' ' ,ERso~~E!'iN;u'4 Es NuMeER oEsCaieTioN@ | ||
NuMeER oEsCaieTioN@ | |||
NA l 7 | NA l 7 | ||
i a 8 9 1010101@l12 11 80 I ' | i a 8 9 1010101@l12 11 80 I ' | ||
'??E ' 2^"R ?Tio's ''''''"' @ | '??E ' 2^"R ?Tio's ''''''"' @ | ||
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Lz1@l10 80 | Lz1@l10 80 Issue oEsCRtPTIoN I 7 2 o 8 9 hl to NA I 68 69 llllllllllll11 | ||
: 80. . | : 80. . | ||
Erryl E Mendenhall PHONE: | Erryl E Mendenhall PHONE: | ||
309-654-2241, ext 176 2, NAME OF PREPARER 8103 3g0. g,y, . | 309-654-2241, ext 176 2, NAME OF PREPARER 8103 3g0. g,y, . | ||
7 i | 7 i | ||
9 | 9 | ||
: 1. LER NUMBER: 80-37/03L-0 | : 1. LER NUMBER: 80-37/03L-0 | ||
: 11. LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station Ill. FACILITY NAME: Unit Two I V'. DOCKET NUMBER: 050-265 V. EVENT DESCRIPTION: | : 11. LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station Ill. FACILITY NAME: Unit Two I V'. DOCKET NUMBER: 050-265 V. EVENT DESCRIPTION: | ||
On December 7, 1980, at 0530, during a routine startup an alarm was received in the Control Room for excessive seal leakage on the 2D RHR pump. The reactor was critical at 1900 and the 20 RHR pump was taken out of service at 2125 to replace the pump's mechanical seal, which was leaking. | On December 7, 1980, at 0530, during a routine startup an alarm was received in the Control Room for excessive seal leakage on the 2D RHR pump. The reactor was critical at 1900 and the 20 RHR pump was taken out of service at 2125 to replace the pump's mechanical seal, which was leaking. | ||
VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE: | VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE: | ||
Per Technical Specification 3 5.A.4. reactor operation is permissible for 30 days following the date that one RHR pump is made or found inoperable, provided that during the 30 days the remaining active components of the LPCI mode of RHR and containment cooling mode of RHR, all active components of both core spray subsystems, and the Diesel Generator required for operation of such components if no external source of power were available shall all be operable. Action was taken af ter the first Indication of seal failure in the 2D RHR pump to verify that these conditions were satisfied by the performance of procedures QOS 1000-2, 3, 4, 5, QOS 1400-2, 3, and 40S 6600-1. The RHR pumps are sized on the basis of the flow requirements for operation in the LPCI mode, where maximum flow is required. Redundancy is provided in that only three of the four system pumps are required to deliver full capacity LPCI flow. This cor.tinued availability of LPCI and the containment cooling mode of RHR, the availability of normal feedwater, core spray, and the emergency diesel generators for backup to normal auxillary power minimized the safety implications of this equipment failure. The 2D RHR pump was returned to service on December 8, 1980, and verified operable at 2120. | Per Technical Specification 3 5.A.4. reactor operation is permissible for 30 days following the date that one RHR pump is made or found inoperable, provided that during the 30 days the remaining active components of the LPCI mode of RHR and containment cooling mode of RHR, all active components of both core spray subsystems, and the Diesel Generator required for operation of such components if no external source of power were available shall all be operable. Action was taken af ter the first Indication of seal failure in the 2D RHR pump to verify that these conditions were satisfied by the performance of procedures QOS 1000-2, 3, 4, 5, QOS 1400-2, 3, and 40S 6600-1. The RHR pumps are sized on the basis of the flow requirements for operation in the LPCI mode, where maximum flow is required. Redundancy is provided in that only three of the four system pumps are required to deliver full capacity LPCI flow. This cor.tinued availability of LPCI and the containment cooling mode of RHR, the availability of normal feedwater, core spray, and the emergency diesel generators for backup to normal auxillary power minimized the safety implications of this equipment failure. The 2D RHR pump was returned to service on December 8, 1980, and verified operable at 2120. | ||
Vll. CAUSE: | Vll. CAUSE: |
Latest revision as of 22:33, 30 January 2020
ML19351F631 | |
Person / Time | |
---|---|
Site: | Quad Cities |
Issue date: | 12/29/1980 |
From: | Mendenhall E COMMONWEALTH EDISON CO. |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
Shared Package | |
ML19351F628 | List: |
References | |
LER-80-037-03L-03, LER-80-37-3L-3, NUDOCS 8101130605 | |
Download: ML19351F631 (2) | |
Text
NRC FORL' 366 U.& NUCLEAR REGULATo3Y CoMM1551oM um T .
' LICENSEE EVENT REPORT
' CONTROL BLOCK: ! l l l l l 6
lh (PLEASE PRINT G3 TYPE ALL f,EOUl%E3 INPDRMATION)
{'o I'il8 9l l l LUCENSEE lQlA CooE l0l2 14 l@l IS 0 l 0 l 0 l -UCENsE l 0 INVMBER O l 0 l - l 0 l 025l 0 26l@l kl II Il TYPE LICENSE 1l 1l@l JG l
SF CAT $4 l@
r 7 i
CON'T lalil y',y l L ]@l 01 51 of 010121615 l@l e91 121017 l a 10 l@l1 a 1212191810 aEroRT oATE e3 l@ l e0 si coCxET NuMeER es EVENT oATE is 7 e )
EVENT DESCRIPTION AND PROSA8LE CONSEQUENCES h !
I'o'TF1 1 2D RHR pumo was Inoperable due to excessive leakage of the mechanical seal . As I gl per Technical Specification 3.5. A.4. the remaining active components of LPCI, l lT pp L ontainment C Cooling Mode of RHR, both Core Spray Systems, and the Diesel Generators l were demonstrated operable. l g o , sj l
@l l lTITl l I I
Lo l 8_J l - 80 7 as #
- CEo'E
"*il s 's$'E Co CoucoNENT Coot s eS"o'ot su"NYoE TITl 7 8 Ic IF l h W h W h IP IU lM lP IX IX lh Wh [J.] h 9 to 11 12 33 18 19 20
,,, st outNTI AL uCCuRRENCE REPORT Revision EVENT YEAR REPORT No. CooE TYPE No.
LER!Ro
@ ,at u g I 8101 l23_J 101317 l 1.r] 10131 It I l-l [0.J v .,,2 8 22 24 26 27 28 29 30 31 32 MAN F RER E AC o oN T ME MouRs h 5 e i FoM S. Su L W L2J@ l352.J@ L2 j@ l 0101 0101 l_11@ LLIO I nl@ lBl2I610Ig 33 34 36 37 40 41 42 43 44 47 CAUSE OESCRIPTION ANo CORRECTIVE ACTIONS h The enute of the ceal 1.alcace was nnemal waar nf the 0-Rino tea 11no curface. I liloll i i l The mechanical seal was replaced. The 20 RHR pump was returned to service and i g !. tes.ted satisfactorily on December 8,19fC . I 1 3 l I
( ,
i A I
'sYE8 snowtR oTwEnsTATus @5'sEoSS0v' oisCovERv oEsCRirrioN @
W W@ l 01010 ' @l" 1 NA .
l W @l Operational Event l
- AETiviTv Co'0 TENT LOCATION oF RELEASE @
1 6 r.EtEAsEo@of RELEASE AMOUNT NA
@loF" ACTIVITY l NA @ l l
eERsoNNEL Exposures NuM8ER TYPE oEsCRIPT1oM L'_W l 01010 !@l zj@l u "
I
' ' ' ,ERso~~E!'iN;u'4 Es NuMeER oEsCaieTioN@
NA l 7
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i 9 NA l 7 8 9 .
Lz1@l10 80 Issue oEsCRtPTIoN I 7 2 o 8 9 hl to NA I 68 69 llllllllllll11
- 80. .
Erryl E Mendenhall PHONE:
309-654-2241, ext 176 2, NAME OF PREPARER 8103 3g0. g,y, .
7 i
9
- 1. LER NUMBER: 80-37/03L-0
- 11. LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station Ill. FACILITY NAME: Unit Two I V'. DOCKET NUMBER: 050-265 V. EVENT DESCRIPTION:
On December 7, 1980, at 0530, during a routine startup an alarm was received in the Control Room for excessive seal leakage on the 2D RHR pump. The reactor was critical at 1900 and the 20 RHR pump was taken out of service at 2125 to replace the pump's mechanical seal, which was leaking.
VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE:
Per Technical Specification 3 5.A.4. reactor operation is permissible for 30 days following the date that one RHR pump is made or found inoperable, provided that during the 30 days the remaining active components of the LPCI mode of RHR and containment cooling mode of RHR, all active components of both core spray subsystems, and the Diesel Generator required for operation of such components if no external source of power were available shall all be operable. Action was taken af ter the first Indication of seal failure in the 2D RHR pump to verify that these conditions were satisfied by the performance of procedures QOS 1000-2, 3, 4, 5, QOS 1400-2, 3, and 40S 6600-1. The RHR pumps are sized on the basis of the flow requirements for operation in the LPCI mode, where maximum flow is required. Redundancy is provided in that only three of the four system pumps are required to deliver full capacity LPCI flow. This cor.tinued availability of LPCI and the containment cooling mode of RHR, the availability of normal feedwater, core spray, and the emergency diesel generators for backup to normal auxillary power minimized the safety implications of this equipment failure. The 2D RHR pump was returned to service on December 8, 1980, and verified operable at 2120.
Vll. CAUSE:
The RHR system pumps are equipped with a mechanical, spring loaded compression unit for a shaf t seal. The unit is a type "PT0" DuraSeal manufactured by Durametallic Corporation for Bingham Pump Company.
Excessive leakage resulted from normal wear of the 0-Ring sealing sur-faces. No prev!ous instances of seal failure have been noted for quad-Cities Unit Two.
Vill. CORRECTIVE ACTION:
The mechanical seal was replaced with a new cartridge seal unit of the same type. The pump was back in service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of being taken out of service and was tested satisfactorily.