ML19345B502: Difference between revisions
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:AC FOJ.M 366 - U. S. NUCLEA3 REGULATORY COMMISSION v i7 771 | :AC FOJ.M 366 - U. S. NUCLEA3 REGULATORY COMMISSION v i7 771 | ||
-. f . | -. f . | ||
LICENSEE EVENT REPORT LER 80-39/3L CONTROL BLOCK: l 1 | |||
1 l 'l l l Ih 6 | 1 l 'l l l Ih 6 | ||
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) l 1011lIVlT l VI Yl Sl Il @l *501 Ol I Ol Ol Ol 01 01 l 01-Ol @264 Il uCENSE 11 11ITvet 1140@ I57 CATI l@ | (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) l 1011lIVlT l VI Yl Sl Il @l *501 Ol I Ol Ol Ol 01 01 l 01-Ol @264 Il uCENSE 11 11ITvet 1140@ I57 CATI l@ | ||
7 5 9 UCENSEE CODE 14 uCENSE NvMBER 25 68 | 7 5 9 UCENSEE CODE 14 uCENSE NvMBER 25 68 CON'* | ||
CON'* | |||
I, o i i j ,"C,3 I L l@l 01 5 l 010 ! OI 21 71 1l@l ll O! 21 51 81 Ol@l11112l4i810l@ 74 75 REPORT DATE 6C | I, o i i j ,"C,3 I L l@l 01 5 l 010 ! OI 21 71 1l@l ll O! 21 51 81 Ol@l11112l4i810l@ 74 75 REPORT DATE 6C | ||
' 8 4J 61 DOCK ET NUMBER 66 69 EV ENT QATI EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h | ' 8 4J 61 DOCK ET NUMBER 66 69 EV ENT QATI EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h | ||
, le 6: i I While perf or=ing the Type C Leak Rate Testing, two valves (V16-20-20 and LRW-83) 1 | , le 6: i I While perf or=ing the Type C Leak Rate Testing, two valves (V16-20-20 and LRW-83) 1 | ||
;o,3, jwere found to have seat leakage in excess of that permitted by Tech. Spec. Section [ | ;o,3, jwere found to have seat leakage in excess of that permitted by Tech. Spec. Section [ | ||
lo iai 1 4.7.A.4. Since a second valve in each line provided containment isolation, there l t o , i r were no adverse consequences to the public health and safety. Similar events were I | lo iai 1 4.7.A.4. Since a second valve in each line provided containment isolation, there l t o , i r were no adverse consequences to the public health and safety. Similar events were I io 46 ; l reported as RO 79-28/3L, RO 77-16/3L, and RO 76-24/3L. f | ||
io 46 ; l reported as RO 79-28/3L, RO 77-16/3L, and RO 76-24/3L. f | |||
' {017j l 1 1069{ l t 80 7 8 9 SYSTEM OAUSE CAUSE COMP. VALVE OCDE CCCE SU8000E COMPONENT OODE Sus COE SUBOCDE toist 7 8 I S l 'OD l@ l E l@ l B l@ l V l A l L l V I El Xlh l X lh l Dl h 9 11 12 12 18 19 20 | ' {017j l 1 1069{ l t 80 7 8 9 SYSTEM OAUSE CAUSE COMP. VALVE OCDE CCCE SU8000E COMPONENT OODE Sus COE SUBOCDE toist 7 8 I S l 'OD l@ l E l@ l B l@ l V l A l L l V I El Xlh l X lh l Dl h 9 11 12 12 18 19 20 | ||
_, SE QUENTI AL OCCURRENCE REPORT REVISION gg fvENT VE AR . R E80RT NC. CCCE *YPE NC. | _, SE QUENTI AL OCCURRENCE REPORT REVISION gg fvENT VE AR . R E80RT NC. CCCE *YPE NC. | ||
Line 38: | Line 34: | ||
:s 29 W | :s 29 W | ||
20 bsi U | 20 bsi U | ||
22 | 22 KN O P NT M WOURS SS t FOR 8. SU ' | ||
KN O P NT M WOURS SS t FOR 8. SU ' | |||
MANU8 RER iB l@l24 Zi@ | MANU8 RER iB l@l24 Zi@ | ||
2. | 2. | ||
Line 49: | Line 43: | ||
l1 i : ; treported in accordance with Appendix J, lb CFR '9. V.B'.3. I | l1 i : ; treported in accordance with Appendix J, lb CFR '9. V.B'.3. I | ||
) | ) | ||
11 6:4 I I i t'!2ti I l i 14 1 I I 7 s e so ST A % POWER CTMER STATUS is C Y DIS 00VERY DESCMtPT10N h it !s i In l@ l 0101 Ol@l ni l W @l m-,4 m m., m.. . I | 11 6:4 I I i t'!2ti I l i 14 1 I I 7 s e so ST A % POWER CTMER STATUS is C Y DIS 00VERY DESCMtPT10N h it !s i In l@ l 0101 Ol@l ni l W @l m-,4 m m., m.. . I AfTiviW CMTENT RELEASE AuCUNT 08 ACTIVITY LOCATION OF RELEASE NA NA l : I 8e9 I-[z_l @D 7 IC 07 mELEASEL2J@l 11 44 I I 45 30 l | ||
*ERSONNEl, EXPOSUR ES NUMBER TYPE OESCRtpTION NA l i I :l' 10 10 10 l@W@l '' | |||
AfTiviW CMTENT RELEASE AuCUNT 08 ACTIVITY LOCATION OF RELEASE NA NA l : I 8e9 I-[z_l @D 7 IC 07 mELEASEL2J@l 11 44 I I 45 30 l | |||
*ERSONNEl, EXPOSUR ES NUMBER TYPE OESCRtpTION NA l i I :l' 10 | |||
10 10 l@W@l '' | |||
* l | * l | ||
. R$eN~A'INJES NUueE. oES: RiPrioN@ | . R$eN~A'INJES NUueE. oES: RiPrioN@ | ||
li h 18 9101010 l@l 7 11 12 NA 30 I | li h 18 9101010 l@l 7 11 12 NA 30 I | ||
6055 CF CR CAMAGE TO FACluTY Q | 6055 CF CR CAMAGE TO FACluTY Q TY'E DESCRIPTION v li l 9 4F9lZ l@lto NA l 4 . . | ||
30 ISSU E I : j o l d@lDE Caip*icN NA l l1IItIitiIiI l} | |||
TY'E DESCRIPTION v | |||
li l 9 4F9lZ l@lto NA l 4 . . | |||
30 | |||
ISSU E I : j o l d@lDE Caip*icN NA l l1IItIitiIiI l} | |||
7 g g to 68 69 sc ; | 7 g g to 68 69 sc ; | ||
anen P. Mudv P*aON E: M" W " ' ' E | anen P. Mudv P*aON E: M" W " ' ' E m8012 01 Ofd$08 PRE 8ARER. | ||
m8012 01 Ofd$08 PRE 8ARER | |||
i e | i e | ||
4 VTVYS1 i 05000271 LER 80-39/3L EVENT DESCRIPTION AND PROBABLE CONSEOUENCES During the performance of refuel related surveillance testing . | 4 VTVYS1 i 05000271 LER 80-39/3L EVENT DESCRIPTION AND PROBABLE CONSEOUENCES During the performance of refuel related surveillance testing . | ||
in accordance with Tech. Spec. Section 4.7.2.a. two primary -con-tainment isolation valves were found to have seat leakages in | in accordance with Tech. Spec. Section 4.7.2.a. two primary -con-tainment isolation valves were found to have seat leakages in | ||
Line 85: | Line 61: | ||
LRW-83 (Drywell Indeterminable 9/30/80 Floor Drain) | LRW-83 (Drywell Indeterminable 9/30/80 Floor Drain) | ||
Both valves were repaired and satisfactorily retested prior to plant startup as required by Tech. Spec. Section 3.7. A.4. | Both valves were repaired and satisfactorily retested prior to plant startup as required by Tech. Spec. Section 3.7. A.4. | ||
I}} | I}} |
Latest revision as of 04:56, 31 January 2020
ML19345B502 | |
Person / Time | |
---|---|
Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
Issue date: | 11/24/1980 |
From: | Murphy W VERMONT YANKEE NUCLEAR POWER CORP. |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
Shared Package | |
ML19345B485 | List: |
References | |
LER-80-039-03L, LER-80-39-3L, NUDOCS 8012010403 | |
Download: ML19345B502 (2) | |
Text
. . . . - -.
- AC FOJ.M 366 - U. S. NUCLEA3 REGULATORY COMMISSION v i7 771
-. f .
LICENSEE EVENT REPORT LER 80-39/3L CONTROL BLOCK: l 1
1 l 'l l l Ih 6
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) l 1011lIVlT l VI Yl Sl Il @l *501 Ol I Ol Ol Ol 01 01 l 01-Ol @264 Il uCENSE 11 11ITvet 1140@ I57 CATI l@
7 5 9 UCENSEE CODE 14 uCENSE NvMBER 25 68 CON'*
I, o i i j ,"C,3 I L l@l 01 5 l 010 ! OI 21 71 1l@l ll O! 21 51 81 Ol@l11112l4i810l@ 74 75 REPORT DATE 6C
' 8 4J 61 DOCK ET NUMBER 66 69 EV ENT QATI EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h
, le 6: i I While perf or=ing the Type C Leak Rate Testing, two valves (V16-20-20 and LRW-83) 1
- o,3, jwere found to have seat leakage in excess of that permitted by Tech. Spec. Section [
lo iai 1 4.7.A.4. Since a second valve in each line provided containment isolation, there l t o , i r were no adverse consequences to the public health and safety. Similar events were I io 46 ; l reported as RO 79-28/3L, RO 77-16/3L, and RO 76-24/3L. f
' {017j l 1 1069{ l t 80 7 8 9 SYSTEM OAUSE CAUSE COMP. VALVE OCDE CCCE SU8000E COMPONENT OODE Sus COE SUBOCDE toist 7 8 I S l 'OD l@ l E l@ l B l@ l V l A l L l V I El Xlh l X lh l Dl h 9 11 12 12 18 19 20
_, SE QUENTI AL OCCURRENCE REPORT REVISION gg fvENT VE AR . R E80RT NC. CCCE *YPE NC.
@ saf ,*e,RC g; I 81 01 2i 22 l-l 22 1013191 24 2s l/l 27 10!3i
- s 29 W
20 bsi U
22 KN O P NT M WOURS SS t FOR 8. SU '
MANU8 RER iB l@l24 Zi@
2.
lasZ l@ l2l@ aj010IOIOI.o I Yl@
se ai l42Y l@ d@
42 IX 19 lo 19.7l@
CAUSE OESCRIPT;ON AND CORRECTIVE ACTIONS 11 1 c i lThe valve- failures summarized in this report and their recairs and retests vill be i f
l1 i : ; treported in accordance with Appendix J, lb CFR '9. V.B'.3. I
)
11 6:4 I I i t'!2ti I l i 14 1 I I 7 s e so ST A % POWER CTMER STATUS is C Y DIS 00VERY DESCMtPT10N h it !s i In l@ l 0101 Ol@l ni l W @l m-,4 m m., m.. . I AfTiviW CMTENT RELEASE AuCUNT 08 ACTIVITY LOCATION OF RELEASE NA NA l : I 8e9 I-[z_l @D 7 IC 07 mELEASEL2J@l 11 44 I I 45 30 l
- ERSONNEl, EXPOSUR ES NUMBER TYPE OESCRtpTION NA l i I :l' 10 10 10 l@W@l
- l
. R$eN~A'INJES NUueE. oES: RiPrioN@
li h 18 9101010 l@l 7 11 12 NA 30 I
6055 CF CR CAMAGE TO FACluTY Q TY'E DESCRIPTION v li l 9 4F9lZ l@lto NA l 4 . .
30 ISSU E I : j o l d@lDE Caip*icN NA l l1IItIitiIiI l}
7 g g to 68 69 sc ;
anen P. Mudv P*aON E: M" W " ' ' E m8012 01 Ofd$08 PRE 8ARER.
i e
4 VTVYS1 i 05000271 LER 80-39/3L EVENT DESCRIPTION AND PROBABLE CONSEOUENCES During the performance of refuel related surveillance testing .
in accordance with Tech. Spec. Section 4.7.2.a. two primary -con-tainment isolation valves were found to have seat leakages in
~
l excess of that permitted by Tech. Spec. Section 4.7.A.4. For each of those valves, a second valve in the applicable line provided the Proper containment isolation capability. .It is, therefore, con-cluded that there were no adverse consequences of this event to the health and safety of the public. Similar events were reported as RO 79-28/3L, RO 77-26/3L, and RO 77-24/3L. The two valves and j their as-found leakage rates are as follows:
Valve As-Found Description Leakage Rate Test Date V16-20-20 (Contain- Indeterminable 9/29/80 ment Purge Makeup Isolation Valve)
LRW-83 (Drywell Indeterminable 9/30/80 Floor Drain)
Both valves were repaired and satisfactorily retested prior to plant startup as required by Tech. Spec. Section 3.7. A.4.
I