ML18113A760: Difference between revisions
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{{#Wiki_filter:m:ic FORr..i 366 {7-77) -ICENSEE EVENT REPORT | {{#Wiki_filter:m:ic FORr..i 366 U.S. NUCLEAR REGULATORY COMMISSION | ||
* 1S LICENSE NUMBER | {7-77) | ||
* 25 26 LICENSE TYPE JO 57 CAT 56 CON'T [ITQ 7 B L!:J© I o I s I o I o I o I 2 I s I o 101 *1 12 I 1 I 9 I 7 I s IG) Gi w Lo~~ ~.! G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 RE?OllT D'ATE oO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ | -ICENSEE EVENT REPORT e CONTROL Ei LOCK: ~I-~~--'----'---'--......jl6 G) 1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION} | ||
jWith the unit at cold shutdown, conduct of PT-39B reveale_d two snubbers with fluid | ~ | ||
This event is reportable in accordance with T.S. 6.6.2.b.(2). | 7 8 IV I A Is IP Is 11 JG)I o lo I - Io Io Io Io I o I - lo I o 101 41 11 11 11 1181 I I G) 9 LICENSEE COOE 14 | ||
Unit! [III] 1 operation was normal from startup to shutdo,~). | * 1S LICENSE NUMBER | ||
The health and safety of the public [IT[) !were not affected. | * 25 26 LICENSE TYPE JO 57 CAT 56 CON'T | ||
[IT[] 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE [Z I ZI@ ~@ ~@ I SI u1 Pl 01 RI Tl@ t.E.J@ l£_]@ 7 | [ITQ 7 B | ||
:~~~~~ L!:J© I o I s I o I o I o I 2 I s I o 101 *1 12 I 1 I 9 I 7 I s IG) Gi w Lo~~ ~.! G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 RE?OllT D'ATE oO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ | |||
jWith the unit at cold shutdown, conduct of PT-39B reveale_d two snubbers with fluid levels less than target level. An engineering eva'iuation determined these snubbers | |||
[ill] I. | |||
~ Ito be inoperable. This event is reportable in accordance with T.S. 6.6.2.b.(2). Unit! | |||
[III] 1 operation was normal from startup to shutdo,~). The health and safety of the public | |||
[IT[) !were not affected. | |||
[IT[] | |||
7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE | |||
~8 [Z I ZI@ ~@ ~@ I SI u1 Pl 01 RI Tl@ t.E.J@ l£_]@ | |||
7 9 10 11 12 13 iS 19 20 SEQUENTIAL OCCUR REN.CE RE?ORT REVISION | |||
@ L::R/RO CVENTYEAR REPORT NO. CODE TYPE NO. | |||
REPORT NUMBER I7 j 8/ L=.l 10 j4 !9 I I/I 10 13 J l2:J L=J ~ | |||
21 22 23 24 26 27 28 29 30 31 32 ACTION, FUTURE EFFECT SHUTDOWN {22) ATTACHMENT NPRD-4 PRIME COMP . COM?ONENT | |||
* 1cKE1@f'zo1@ | * 1cKE1@f'zo1@ | ||
or~tl@ MrzT@ l O 100,os. % I SU,yll@ | 33 34 or~tl@ | ||
One snubber was re-OJJJ !placed and one was repaired and restored. | 35 MrzT@ | ||
to operable condition. | 36 l O 100,os. | ||
Tube fittings are a | 37 | ||
All snubbers !JJJJ . | %I 40 SU,yll@ | ||
41 FORM :;us. | |||
8 e 10 12 11 ACT1VITY CONTENT Q\ RELEASED OF RELEASE AMOUNT OF ACTIVITY '2_V l2: | LJ SUPPLIER | ||
~@ | |||
---J 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY '4:)\ TYPE DESCRIPTION ITli] ~@ | MANUFACTURER I I I 2 10 I 7 j@) | ||
42 43 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ | |||
jThe cause of the low fluid levels was leaking tube fittings. One snubber was re-OJJJ !placed and one was repaired and restored. to operable condition. Tube fittings are a part of the visual acceptance criteria for surveillance of snubbers: All snubbers | |||
!JJJJ . | |||
' will be inspected prior to unit startup. | |||
W\ttachment, page 1 of 1) Surry Power Station, Unit Docket No: 50-280 Report No: 78-049/0JL-0 Event Date: 12/19/78 Title of Report: Inoperable Snubbers 1. Description of Event: With the unit at cold shutdown, conduct of PT-39B revealed two snubbers, 1-RC-HSS-119 and 1-RC-HSS-135, with fluid levels less than target level. An engineering | I ITEia 1 g 80 FACILITY METHOD OF A32 STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 1.::.:;J | ||
~valuation on 12/19/78 determined these snubbers to be inoperable. | ~ ~@ IO I O ! 0 l@I___NA_ _ ___ ~@)~1--'E_n'-'-'g~i_n_e_e_r_'s__o_b~s~e~r_v~a~t~i-*~o~n--'-------~ | ||
8 e 10 12 11 44 45 46 80 ACT1VITY CONTENT Q\ | |||
RELEASED OF RELEASE AMOUNT OF ACTIVITY '2_V . _LOCATION OF RELEASE @ | |||
l2:fila tu @ I z I@) I NA NA 1 s 10 | |||
?ERSONNEL EXPOSURES NUMBER Q TYPE 11 DESCRIPTION 39 f 44 45 80 EI2J 10 10 10 !~@,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____. | |||
7 8 9 11 12 13 80 PERSONNEL INJURIES ,;":;\ | |||
NUMBER,. DESCRIPTION6 NA | |||
~ I0 lu lu l@.____________________________ ---J 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY '4:)\ | |||
TYPE DESCRIPTION ~ | |||
NA ITli] ~@ | |||
7 891 ~a--------------------- 0 090 | |||
- - --~-u------------------a~o 1ssu:~~~;;CRIPTION@ 79 1 ,I-, 3-, NRC USE ON Ly "' | |||
~ ~o.________NA_ _ _ _ _ _ _ _ _ _ _ _ _ _~ 11 11 11 1 11 11 r ~ | |||
7 8 9 10 68 69 BO ; | |||
T. L. Baucom (804) 357-3184 0 NAME OF P R E P A R E R - - - - - - - - - - - - - - - - - - ll. | |||
PHONE:------------- | |||
" | |||
W\ttachment, page 1 of 1) | |||
Surry Power Station, Unit Docket No: 50-280 Report No: 78-049/0JL-0 Event Date: 12/19/78 Title of Report: Inoperable Snubbers | |||
: 1. Description of Event: | |||
With the unit at cold shutdown, conduct of PT-39B revealed two snubbers, 1-RC-HSS-119 and 1-RC-HSS-135, with fluid levels less than target level. An engineering ~valuation on 12/19/78 determined these snubbers to be inoperable. | |||
This event is reportable in accordance with Tech. Spec. 6.6.2.b.(2). | This event is reportable in accordance with Tech. Spec. 6.6.2.b.(2). | ||
: 2. Probable Consequences of Event: Since two snubbers represent a very small percentage of the total seismic restraint installation and since these restraints are provided for a low bility event, and unit operation was normal from startup to shutdown, the health and safety of the public were not affected. | : 2. Probable Consequences of Event: | ||
3 *. Cause of Event: The cause of the low fluid levels was leaking tube fittings. | Since two snubbers represent a very small percentage of the total seismic restraint installation and since these restraints are provided for a low proba-bility event, and unit operation was normal from startup to shutdown, the health and safety of the public were not affected. | ||
: 4. Immediate Corrective Action: Snubber l-RC-HSS-119 was replaced with a Q.C. certified shop spare. The leaking fitting on snubber 1...:RC-HSS-135 was repaired and the reservoir level was restored to the proper level. 5. Subsequent Corrective Action: Prior to *.unit startup, all snubbers will be verified operable by visual inspection criteria. | 3 *. Cause of Event: | ||
The cause of the low fluid levels was leaking tube fittings. | |||
: 4. Immediate Corrective Action: | |||
Snubber l-RC-HSS-119 was replaced with a Q.C. certified shop spare. The leaking fitting on snubber 1...:RC-HSS-135 was repaired and the reservoir level was restored to the proper level. | |||
: 5. Subsequent Corrective Action: | |||
Prior to *.unit startup, all snubbers will be verified operable by visual inspection criteria. | |||
: 6. Action Taken to Prevent Recurrence: | : 6. Action Taken to Prevent Recurrence: | ||
Tube fittings are a part of the visual acceptance criteria for surveillance of snubbers. | Tube fittings are a part of the visual acceptance criteria for surveillance of snubbers. All snubbers will be inspected prior to unit startup. | ||
All snubbers will be inspected prior to unit startup. 7. Generic Implications: | : 7. Generic Implications: | ||
The generic implications are those associated with hydraulic systems in general, i.e., leakage, seal life, environmental compatability, etc. These matters are state-of-the-art problems.}} | The generic implications are those associated with hydraulic systems in general, i.e., leakage, seal life, environmental compatability, etc. These matters are state-of-the-art problems.}} |
Revision as of 08:08, 21 October 2019
ML18113A760 | |
Person / Time | |
---|---|
Site: | Surry ![]() |
Issue date: | 01/02/1979 |
From: | Baucom T VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
Shared Package | |
ML18113A757 | List: |
References | |
LER-78-049-03L, LER-78-49-3L, NUDOCS 7901090234 | |
Download: ML18113A760 (2) | |
Text
m:ic FORr..i 366 U.S. NUCLEAR REGULATORY COMMISSION
{7-77)
-ICENSEE EVENT REPORT e CONTROL Ei LOCK: ~I-~~--'----'---'--......jl6 G) 1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION}
~
7 8 IV I A Is IP Is 11 JG)I o lo I - Io Io Io Io I o I - lo I o 101 41 11 11 11 1181 I I G) 9 LICENSEE COOE 14
- 1S LICENSE NUMBER
- 25 26 LICENSE TYPE JO 57 CAT 56 CON'T
[ITQ 7 B
- ~~~~~ L!:J© I o I s I o I o I o I 2 I s I o 101 *1 12 I 1 I 9 I 7 I s IG) Gi w Lo~~ ~.! G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 RE?OllT D'ATE oO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
jWith the unit at cold shutdown, conduct of PT-39B reveale_d two snubbers with fluid levels less than target level. An engineering eva'iuation determined these snubbers
[ill] I.
~ Ito be inoperable. This event is reportable in accordance with T.S. 6.6.2.b.(2). Unit!
[III] 1 operation was normal from startup to shutdo,~). The health and safety of the public
[IT[) !were not affected.
[IT[]
7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~8 [Z I ZI@ ~@ ~@ I SI u1 Pl 01 RI Tl@ t.E.J@ l£_]@
7 9 10 11 12 13 iS 19 20 SEQUENTIAL OCCUR REN.CE RE?ORT REVISION
@ L::R/RO CVENTYEAR REPORT NO. CODE TYPE NO.
REPORT NUMBER I7 j 8/ L=.l 10 j4 !9 I I/I 10 13 J l2:J L=J ~
21 22 23 24 26 27 28 29 30 31 32 ACTION, FUTURE EFFECT SHUTDOWN {22) ATTACHMENT NPRD-4 PRIME COMP . COM?ONENT
- 1cKE1@f'zo1@
33 34 or~tl@
35 MrzT@
36 l O 100,os.
37
%I 40 SU,yll@
41 FORM :;us.
LJ SUPPLIER
~@
MANUFACTURER I I I 2 10 I 7 j@)
42 43 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
jThe cause of the low fluid levels was leaking tube fittings. One snubber was re-OJJJ !placed and one was repaired and restored. to operable condition. Tube fittings are a part of the visual acceptance criteria for surveillance of snubbers: All snubbers
!JJJJ .
' will be inspected prior to unit startup.
I ITEia 1 g 80 FACILITY METHOD OF A32 STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 1.::.:;J
~ ~@ IO I O ! 0 l@I___NA_ _ ___ ~@)~1--'E_n'-'-'g~i_n_e_e_r_'s__o_b~s~e~r_v~a~t~i-*~o~n--'-------~
8 e 10 12 11 44 45 46 80 ACT1VITY CONTENT Q\
RELEASED OF RELEASE AMOUNT OF ACTIVITY '2_V . _LOCATION OF RELEASE @
l2:fila tu @ I z I@) I NA NA 1 s 10
?ERSONNEL EXPOSURES NUMBER Q TYPE 11 DESCRIPTION 39 f 44 45 80 EI2J 10 10 10 !~@,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____.
7 8 9 11 12 13 80 PERSONNEL INJURIES ,;":;\
NUMBER,. DESCRIPTION6 NA
~ I0 lu lu l@.____________________________ ---J 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY '4:)\
TYPE DESCRIPTION ~
NA ITli] ~@
7 891 ~a--------------------- 0 090
- - --~-u------------------a~o 1ssu:~~~;;CRIPTION@ 79 1 ,I-, 3-, NRC USE ON Ly "'
~ ~o.________NA_ _ _ _ _ _ _ _ _ _ _ _ _ _~ 11 11 11 1 11 11 r ~
7 8 9 10 68 69 BO ;
T. L. Baucom (804) 357-3184 0 NAME OF P R E P A R E R - - - - - - - - - - - - - - - - - - ll.
PHONE:-------------
"
W\ttachment, page 1 of 1)
Surry Power Station, Unit Docket No: 50-280 Report No: 78-049/0JL-0 Event Date: 12/19/78 Title of Report: Inoperable Snubbers
- 1. Description of Event:
With the unit at cold shutdown, conduct of PT-39B revealed two snubbers, 1-RC-HSS-119 and 1-RC-HSS-135, with fluid levels less than target level. An engineering ~valuation on 12/19/78 determined these snubbers to be inoperable.
This event is reportable in accordance with Tech. Spec. 6.6.2.b.(2).
- 2. Probable Consequences of Event:
Since two snubbers represent a very small percentage of the total seismic restraint installation and since these restraints are provided for a low proba-bility event, and unit operation was normal from startup to shutdown, the health and safety of the public were not affected.
3 *. Cause of Event:
The cause of the low fluid levels was leaking tube fittings.
- 4. Immediate Corrective Action:
Snubber l-RC-HSS-119 was replaced with a Q.C. certified shop spare. The leaking fitting on snubber 1...:RC-HSS-135 was repaired and the reservoir level was restored to the proper level.
- 5. Subsequent Corrective Action:
Prior to *.unit startup, all snubbers will be verified operable by visual inspection criteria.
- 6. Action Taken to Prevent Recurrence:
Tube fittings are a part of the visual acceptance criteria for surveillance of snubbers. All snubbers will be inspected prior to unit startup.
- 7. Generic Implications:
The generic implications are those associated with hydraulic systems in general, i.e., leakage, seal life, environmental compatability, etc. These matters are state-of-the-art problems.