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{{#Wiki_filter:m:ic FORr..i 366 {7-77) -ICENSEE EVENT REPORT U.S. NUCLEAR REGULATORY COMMISSION e CONTROL Ei LOCK: ~I -~~--'----'---'--......jl G) 1 6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION} IV I A Is IP Is 1 1 JG)I o lo I -Io Io Io Io I o I -lo I o 101 41 11 11 11 1181 I I G) 7 8 9 LICENSEE COOE 14
{{#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 I levels less than target level. An engineering eva'iuation determined these snubbers [ill] . Ito be inoperable.
~
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 8 9 10 11 12 13 iS 19 20 SEQUENTIAL OCCUR REN.CE RE?ORT @ L::R/RO CVENTYEAR REPORT NO. CODE TYPE REPORT I 7 j 8 / L=.l 10 j4 !9 I I/I 10 13 J l2:J L=J NUMBER 21 22 23 24 26 27 28 29 30 31 ACTION, FUTURE EFFECT SHUTDOWN {22) ATTACHMENT NPRD-4 FORM :;us. PRIME COMP . SUPPLIER REVISION NO. 32 COM?ONENT MANUFACTURER 80
[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 35 36 3 7 40 41 LJ ~@ I I I 2 1 0 I 7 j@) CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ 42 43 jThe cause of the low fluid levels was leaking tube fittings.
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 'part of the visual acceptance criteria for surveillance of snubbers:
37
All snubbers !JJJJ . ITEi will be inspected prior to unit startup. I 1 a g FACILITY STATUS % POWER OTHER STATUS METHOD OF A32 47 80 ~@ IO I O ! 0 l@I ___ NA ___ __ DISCOVERY DISCOVERY DESCRIPTION 1.::.:;J ~@)~1--'E_n'-'-'g~i_n_e_e_r_'s
                                                                                                  %I   40 SU,yll@
__ o_b~s~e~r_v~a~t~i-*~o~n--'-------~
41 FORM :;us.
8 e 10 12 11 ACT1VITY CONTENT Q\ RELEASED OF RELEASE AMOUNT OF ACTIVITY '2_V l2:fil tu @ I z I@) I NA 1 a s 10 11 45 46 80 44 44 45 NA . _LOCATION OF RELEASE @ 80 ?ERSONNEL EXPOSURES f NUMBER Q TYPE DESCRIPTION 39 EI2J 10 10 10 !~@,__ _______________________
LJ SUPPLIER
____. 7 8 9 11 12 13 PERSONNEL INJURIES ,;":;\ 80 0 NUMBER,. DESCRIPTION6 NA I lu lu l@.____ ________________________
                                                                                                                                                  ~@
---J 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY '4:)\ TYPE DESCRIPTION ITli] ~@ 80 NA 7 891 ~a------------------
MANUFACTURER I I I 2 10 I 7 j@)
0---0-9-0--~-u------------------a~o 1ssu:~~~;;CRIPTION@
42                43                                47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                         @
7 9 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 NAME OF PREPARER------------------
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
(804) 357-3184 PHONE:-------------
!JJJJ .
0 ll. "
                ' 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.}}

Latest revision as of 04:21, 3 February 2020

LER 78-049/03L-0 on 781219:conduct of PT-39B Revealed 2 Snubbers W/Fluid Levels Less than Target Level.Caused by Leaking Tube Fittings
ML18113A760
Person / Time
Site: Surry Dominion icon.png
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)
v • d • e


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.

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