ML18139A501: Difference between revisions

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{{#Wiki_filter:-------*----
{{#Wiki_filter:' NRC FORM (7'77)
' ., ' NRC FORM 366 (7'77) e e S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROLBLOCK:J --'----'---'--'--....__,!(2) 1 6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
            ., ' 366 e                                                          e
C§::E] I VI A I s I p I s I 11010 7 8 9 LICENSEE CODE 14 15 I O I -I O I O I O I O I O I -I O I O 101 4 I 1 I 1 I 1 I 1 101 I I 0 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T ITITI 7 8 l:'..J© I O I 5 I O I O I O I 2 I 8 I O 101 ° I 8 I 1 I 6 I 8 I O I© I o I 9 I 1 I s I s I o I@ 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES  
                                                                                                                          -------*----
<,o) l During performance of PT-15.2, MOv-Ft,Y-.1s1A failed to indicate in the closed position.
S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROLBLOCK:J           ~--'----'---'--'--....__,!(2)                         (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1                                6 C&sect;::E] I VI           A I s I p I s I 11010 I O I - I O I O I O I O I O I - I O I O 101 4 I 1 I 1 I 1 I 1 101 I I 0 7        8    9        LICENSEE CODE              14    15                  LICENSE NUMBER                     25     26       LICENSE TYPE         30     57 CAT 58 CON'T ITITI 7         8
Investigation showed valve 1rema:ined in the open position.
                        =~~~~~      l:'..J&#xa9; I OI 5 I O I O I O I 2 I 8 I O 101 &deg;I 8 I 1 I 6 I 8 I O I&#xa9; I o I 9 I 1 I s I s I o I@
Normal and. primary emergency considerations require valve to be open (in position to feed steam generator).
60           61             DOCKET NUMBER               68   69     EVENT DATE             74       75       REPORT DATE             80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES                             <,o) l During performance of PT-15.2, MOv-Ft,Y-.1s1A failed to indicate in the closed position.
Steam ~enerator can be isolated by use of valves outside containment.
Investigation showed valve 1rema:ined in the open position.                                                   Normal and. primary emergency considerations require valve to be open (in position to feed steam generator).                                                                           Steam
This condition is reportable in accordance with T.S. 6.6.2.b.(2).
                    ~enerator can be isolated by use of valves outside containment.                                                           This condition is reportable in accordance with T.S. 6.6.2.b.(2).                                             The health and safety of the public were not affected.
The health and safety of the public were not affected.
[I]]]
[I]]] 7 8 9 80 [ill] 7 8 SYSTEM CODE I c1 RI@ 9 10 r;:;,, LER/RO LVENT YEAR REPORT 1 8 1 0 1 NUMBER 21 22 ACTION FUTURE TAKEN ACTION EFFECT ON PLANT CAUSE CAUSE CODE SUB CODE COMPONENT CODE L:J@ ~@ 1v IA IL 1v jE 1x I@ 11 12 13 SEQUENTIAL REPORT NO. l=.I Io Is Is I 23 24 26 lB OCCURRENCE CODE 1/I I 0 1 3 1 27 28 29 COMP. SUBCODE ~ 19 REPORT TYPE L::J 30 VALVE SUBCODE e.J@ 20 L=.J 31 SHUTDOWN METHOD HOURS {22) ATTACHMENT NPRD-4 PRIME COMP. SUPPLIER REVISION NO. 32 COMPONENT MANUFACTURER llJ SUBMITTED FORM SUB. I I ~@ ~@) 40 41 42 ~@ ~@~@ Li@ ~ 1&deg; 1&deg; 1&deg; 33 34 35 36 37 jw Jo I 31 oj@ CAUSE DESCRIPTION Ar'j.D CORRECTIVE ACTIONS @ 43 44 47 J Mechanical failure of valve MOV-FW-151A prevented both remote and local operation.
7         8   9                                                                                                                                                                   80 SYSTEM               CAUSE       CAUSE                                                     COMP.            VALVE CODE                CODE     SUB CODE                 COMPONENT CODE                 SUBCODE          SUBCODE
MOV-FW-151A will be repaired during the next scheduled outage. ITEl 7 8 9 FACILITY '3a' STATUS % POWER OTHER STATUS Ci:TIJ L:J@ IO l 8 I 8 l@) ...... I ______ NA __ _. 80 METHOD OF @ DISCOVERY DISCOVERY DESCRIPTION
[ill]                              I c1 RI@ L:J@ ~@ 1v IA IL 1v                                             jE   1x I@ ~ e.J@
~I PT 15.2 8 9 10 12 13 ACTIVITY CONTENT (.;';;\ RELEASED OF RELEASE AMOUNT OF ACTIVITY e l.Ll@ W@I NA 7 8 9 10 11 44 45 46 80 _LOCATION OF RELEASE @) NA 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
7        8                      9          10          11         12               13                           lB          19                20 SEQUENTIAL                         OCCURRENCE            REPORT                          REVISION r;:;,,  LER/RO LVENT YEAR                                    REPORT NO.                             CODE              TYPE                            NO.
[ilD I o I o I ~6t2.J@ ____ , _N_A ____________________
                ~      REPORT NUMBER 1 8 10 1 l=.I         Io Is Is I               1/I         I28 0 1 3291          L::J             L=.J         ~
_ 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION6 I 01 0 I Ol@ ______ N_A ___________________
21          22        23          24              26      27                                  30              31           32 ACTION      FUTURE              EFFECT          SHUTDOWN                         {22) ATTACHMENT         NPRD-4         PRIME COMP.               COMPONENT TAKEN      ACTION            ON PLANT          METHOD                  HOURS  llJ   SUBMITTED         FORM SUB.         SUPPLIER              MANUFACTURER
_ 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 0 TYPE DESCRIPTION 80 NA 7 8 91 I PUBLICITY
                  ~@~@
(";;;\ . ISSUEDQDESCRIPTION NRCUSEONLY  
33          34 Li@
"' ITli] l.N.J6 ........ ________ N_A ____________
35
-..J I II I I II II I II I 7 8 9 10 -,::::q 68 69 80 0: 8 0 0 9 1 9* {iF PREPARER __ J_. _L_._w_i_l_so_n________
                                                                    ~ 1&deg; 1&deg; 1&deg; 36           37 I 40I ~@ 41
PHONE: __ (.;..8_0_4_)_35_7_-_3_1_8_4
                                                                                                                              ~@)
___ 
42
",, . , -*-**----*  
                                                                                                                                                ~@
---*"---~--
43 jw Jo 44 I 31 oj@
*---*--------*--*-~-------**-*-
47 CAUSE DESCRIPTION Ar'j.D CORRECTIVE ACTIONS                       @
---------. ,**-**------*J:::.~-<~--------*---
J Mechanical failure of valve MOV-FW-151A prevented both remote and local operation.
,~~---~-~----J"~~-~--
I MOV-FW-151A will be repaired during the next scheduled outage.
e ATTACHMENT I (PAGE l OF 1) SURRY POWER STATION, UNIT l DOCKET NO: 50-280 REPORT NO: 80-055/03L-0 EVENT DATE: 08-16-80 TITLE OF EVENT: MOV-FW-151A FAILURE TO OPERATE 1. DESCRIPTION OF EVENT: e During performance of PT 15.2, MOV-FW-151A failed to indicate in the closed position.
ITEl8 7             9                                                                                                                                                                   80 FACILITY                                                           '3a'       METHOD OF STATUS             % POWER                       OTHER STATUS   ~          DISCOVERY                            DISCOVERY DESCRIPTION          @
Investigation showed valverr.emained in the open position .. Normal and primary emergency considerations require valve to be open (in position to feed steam generator).
Ci:TIJ L:J@ IO l 8 I 8 l@)I. . . ______                               NA_ __.               ~I         PT 15.2 8   9               10               12       13                             44    45      46                                                                        80 ACTIVITY       CONTENT                                           (.;';;\
This condition is reportable in accordance with T.S. 6.6.2. b. (2)
RELEASED OF RELEASE                         AMOUNT OF ACTIVITY     e                                               _LOCATION OF RELEASE          @)
* 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS: MOV-FW-151A is in a position that will provide emergency feedwater to 'C' Steam Generator as required for a Loss of Normal Feedwater event. If auxiliary feedwater is required to be isolated from 'C' Steam Generator, sufficient time is available for manual isolation outside of the containment.
  ~ l.Ll@                       W@I                                     NA                                  NA 7       8   9               10           11                                         44           45                                                                           80 PERSONNEL EXPOSURES                               ~
Therefore, the health and safety of the public has not been affected.
NUMBER         ~ TYPE             DESCRIPTION
: 3. CAUSE OF THE EVENT: Mechanical failure of the valve operator is suspected at this time. 4. IMMEDIATE CORRECTIVE ACTION: Investigatedreason for valve failure. Verified valve in the required position, i.e. open. 5. SUBSEQUENT CORRECTIVE ACTION: Instructions provided to the operating staff for method of manual isolation, if required.
[ilD I oI o I ~6t2.J@ ____,_N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 6. FUTURE CORRECTIVE ACTION: The valve will be repaired at the next scheduled outage.and failure mode firmed. 7. GENERIC IMPLICATIONS:
7       8   9               11       12           13                                                                                                                           80 PERSONNEL INJURIES                   ~
NUMBER               DESCRIPTION6
~              I 01 0 I Ol@ ______N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
7       8   9               11       12                                                                                                                                       80 LOSS OF OR DAMAGE TO FACILITY             0 TYPE         DESCRIPTION                   ~
~~@
7         8 91 NA
                            *o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~---1 PUBLICITY               (";;;\
80
        .     ISSUEDQDESCRIPTION                                                                                                                           NRCUSEONLY                 "'
ITli] l.N.J6 ........________N_A_ _ _ _ _ _ _ _ _ _ _ _-..J I II I I II II I II I ~
7         8 9             10 -,::::q                                                                                                       68   69                             80 0:
8 0 0 9 1 9* ~~ {iF                       PREPARER _ _          J_. _L_._w_i_l_so_n________                                 PHONE: _ _          (.;..8_0_4_)_35_7_-_3_1_8_4_ _ _        ~
 
      .                     -*-**----* ---*"---~-- *- - - * - -------*--*-~-------**-*- --------- . ,* - **------*J:::.~-<~--------*--- ,~~---~-~----J"~~-~--
,
  ",,
ATTACHMENT I (PAGE l OF 1) e                                                                e SURRY POWER STATION, UNIT l DOCKET NO:   50-280 REPORT NO:   80-055/03L-0 EVENT DATE: 08-16-80 TITLE OF EVENT:   MOV-FW-151A FAILURE TO OPERATE
: 1. DESCRIPTION OF EVENT:
During performance of PT 15.2, MOV-FW-151A failed to indicate in the closed position. Investigation showed valverr.emained in the open position .. Normal and primary emergency considerations require valve to be open (in position to feed steam generator). This condition is reportable in accordance with T.S. 6.6.2.
: b. (2) *
: 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:
MOV-FW-151A is in a position that will provide emergency feedwater to 'C' Steam Generator as required for a Loss of Normal Feedwater event. If auxiliary feedwater is required to be isolated from 'C' Steam Generator, sufficient time is available for manual isolation outside of the containment. Therefore, the health and safety of the public has not been affected.
: 3. CAUSE OF THE EVENT:
Mechanical failure of the valve operator is suspected at this time.
: 4. IMMEDIATE CORRECTIVE ACTION:
Investigatedreason for valve failure.                           Verified valve in the required position, i.e. open.
: 5. SUBSEQUENT CORRECTIVE ACTION:
Instructions provided to the operating staff for method of manual isolation, if required.
: 6. FUTURE CORRECTIVE ACTION:
The valve will be repaired at the next scheduled outage.and failure mode con-firmed.
: 7. GENERIC IMPLICATIONS:
None}}
None}}

Revision as of 03:30, 21 October 2019

LER 80-055/03L-0:on 800816,during Performance of PT 15.2, MOV-FW-151A Failed to Indicate in Closed Position. Investigation Showed Valve in Open Position.Probably Caused by Mechanical Failure of Valve Operator
ML18139A501
Person / Time
Site: Surry Dominion icon.png
Issue date: 09/15/1980
From: Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139A500 List:
References
LER-80-055-03L, LER-80-55-3L, NUDOCS 8009190559
Download: ML18139A501 (2)


Text

' NRC FORM (7'77)

., ' 366 e e


*----

S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROLBLOCK:J ~--'----'---'--'--....__,!(2) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 C§::E] I VI A I s I p I s I 11010 I O I - I O I O I O I O I O I - I O I O 101 4 I 1 I 1 I 1 I 1 101 I I 0 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T ITITI 7 8

=~~~~~ l:'..J© I OI 5 I O I O I O I 2 I 8 I O 101 °I 8 I 1 I 6 I 8 I O I© I o I 9 I 1 I s I s I o I@

60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES <,o) l During performance of PT-15.2, MOv-Ft,Y-.1s1A failed to indicate in the closed position.

Investigation showed valve 1rema:ined in the open position. Normal and. primary emergency considerations require valve to be open (in position to feed steam generator). Steam

~enerator can be isolated by use of valves outside containment. This condition is reportable in accordance with T.S. 6.6.2.b.(2). The health and safety of the public were not affected.

[I]]]

7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUB CODE COMPONENT CODE SUBCODE SUBCODE

[ill] I c1 RI@ L:J@ ~@ 1v IA IL 1v jE 1x I@ ~ e.J@

7 8 9 10 11 12 13 lB 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION r;:;,, LER/RO LVENT YEAR REPORT NO. CODE TYPE NO.

~ REPORT NUMBER 1 8 10 1 l=.I Io Is Is I 1/I I28 0 1 3291 L::J L=.J ~

21 22 23 24 26 27 30 31 32 ACTION FUTURE EFFECT SHUTDOWN {22) ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS llJ SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~@~@

33 34 Li@

35

~ 1° 1° 1° 36 37 I 40I ~@ 41

~@)

42

~@

43 jw Jo 44 I 31 oj@

47 CAUSE DESCRIPTION Ar'j.D CORRECTIVE ACTIONS @

J Mechanical failure of valve MOV-FW-151A prevented both remote and local operation.

I MOV-FW-151A will be repaired during the next scheduled outage.

ITEl8 7 9 80 FACILITY '3a' METHOD OF STATUS  % POWER OTHER STATUS ~ DISCOVERY DISCOVERY DESCRIPTION @

Ci:TIJ L:J@ IO l 8 I 8 l@)I. . . ______ NA_ __. ~I PT 15.2 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT (.;';;\

RELEASED OF RELEASE AMOUNT OF ACTIVITY e _LOCATION OF RELEASE @)

~ l.Ll@ W@I NA NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES ~

NUMBER ~ TYPE DESCRIPTION

[ilD I oI o I ~6t2.J@ ____,_N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

7 8 9 11 12 13 80 PERSONNEL INJURIES ~

NUMBER DESCRIPTION6

~ I 01 0 I Ol@ ______N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 0 TYPE DESCRIPTION ~

~~@

7 8 91 NA

  • o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~---1 PUBLICITY (";;;\

80

. ISSUEDQDESCRIPTION NRCUSEONLY "'

ITli] l.N.J6 ........________N_A_ _ _ _ _ _ _ _ _ _ _ _-..J I II I I II II I II I ~

7 8 9 10 -,::::q 68 69 80 0:

8 0 0 9 1 9* ~~ {iF PREPARER _ _ J_. _L_._w_i_l_so_n________ PHONE: _ _ (.;..8_0_4_)_35_7_-_3_1_8_4_ _ _ ~

. -*-**----* ---*"---~-- *- - - * - -------*--*-~-------**-*- --------- . ,* - **------*J:::.~-<~--------*--- ,~~---~-~----J"~~-~--

,

",,

ATTACHMENT I (PAGE l OF 1) e e SURRY POWER STATION, UNIT l DOCKET NO: 50-280 REPORT NO: 80-055/03L-0 EVENT DATE: 08-16-80 TITLE OF EVENT: MOV-FW-151A FAILURE TO OPERATE

1. DESCRIPTION OF EVENT:

During performance of PT 15.2, MOV-FW-151A failed to indicate in the closed position. Investigation showed valverr.emained in the open position .. Normal and primary emergency considerations require valve to be open (in position to feed steam generator). This condition is reportable in accordance with T.S. 6.6.2.

b. (2) *
2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:

MOV-FW-151A is in a position that will provide emergency feedwater to 'C' Steam Generator as required for a Loss of Normal Feedwater event. If auxiliary feedwater is required to be isolated from 'C' Steam Generator, sufficient time is available for manual isolation outside of the containment. Therefore, the health and safety of the public has not been affected.

3. CAUSE OF THE EVENT:

Mechanical failure of the valve operator is suspected at this time.

4. IMMEDIATE CORRECTIVE ACTION:

Investigatedreason for valve failure. Verified valve in the required position, i.e. open.

5. SUBSEQUENT CORRECTIVE ACTION:

Instructions provided to the operating staff for method of manual isolation, if required.

6. FUTURE CORRECTIVE ACTION:

The valve will be repaired at the next scheduled outage.and failure mode con-firmed.

7. GENERIC IMPLICATIONS:

None